ML042450264
| ML042450264 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 04/05/2004 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Scalice J Tennessee Valley Authority |
| References | |
| 50-390/04-301 50-390/04-301 | |
| Download: ML042450264 (114) | |
See also: IR 05000390/2004301
Text
Draft Submittal
WATTS BAR JULY 2004 EXAM
50-390/2004-301
JULY 23, & JULY 26-30,2004
WATTS BAR NUCLEAR PLANT
REACTOR OPERATOR
NRC
WRITTEN EXAM
JULY 23,2004
REFERENCE COPY
NRC
I
008 AK3.03 001
Given the following plant conditions:
-
Unit 1 was initially at 100% power.
- A small break LOCA has occured due to a failed open PZR P6RV.
-
The associated PQRV block valve will NOT close.
-
The operating crew transitions tu E-I, boss of Reactor or Secondary
Coolant.
-
RCS pressure has lowered to 1450 psig and the crew trips all Reactor
Coo9ant Pumps (KCPs) in accordance with step 1.
.
.
'.d
Which ONE of the following indicztes the reason the RCPs were tripped by the
crew?
A. To minimize RCS cooldown rate.
BY To minimize RCS inventory loss.
C. To prevent RCP damage due to everspeed.
D. To reduce RCS heat input
The correct answer is B.
A. Incorrect - Student may select this distractor since securing RCPs would
reduce KCS forced Row cooldown (86s is still coupled to SiGs). However a
WCS cooldown would lessen the severity of core uncovery which is the
objective of the step to secure the RCPs.
L
B. Correct
~ RCPs are tripped to prevent excessive depletion of RCS water
inventory through a small break which might lead to core uncovery if RCPs
were tripped later in the accident
RCPs. Motors would be connected to a 60 hz stable power source in this
situation. Student may incorrectly believe that RCPs may overspeed due to
steam formation.
D. Incorrect - RCP current will not increase in this situation to a level that could
cause damage to the motor. Student may believe that the RCP will be doing
more work UR the system and tie that to an overcurrent condition.
C. Incorrect - Under the stated condition it is not possible tu overspeed the
4
Page: 1 of2
5/27/2004
REFERENCES:
Lesson plan 3-OT-EOPOlQ0, p. 14
INPO Bank Point Beach 9/29/2003
1 OCFK55 41.5, IO, 45.6, 13
Knowledge of the reasons for the following responses as they apply to the
Pressurizer Vapor Space Accident: Actions contained in EOP for PZR vapor
space accident/ LOCA
b,
R O - 1
SRO-2
Reference:
3-OT-EOPO 100
KiA value:
4.1
Level:
I
TierGrp:
i!l
-
PaEe: 2 of 2
WA Number: 008 AK3.05
Last Used:
09!29!2003
Source:
BANK
SRQ Only:
009 EK1.01 001
Which ONE of the following describes reflux flow following a small break LOCA?
A. Liquid heated by the core is subsequently cooled inside the steam generator
tubes and returned to the core via natural circulation flow along the bottom of
each cold leg pipe.
B. Liquid heated by the core is subsequently cooled inside the steam generator
tubes and returned to the core via counterflow along the bottom of each
partially filled hot leg pipe.
C. Steam produced inside the core is condensed in the steam generator tubes
and returned to the core via natural circulation flow along the bottom of each
cold leg pipe.
D?' Stearn produced inside the core is condensed in the steam generator tubes
and returned to the core via gravity counterflow along the bottom of each
partially filled hot leg pipe.
-kr.
The correct answer is D.
A. Incorrect - Reflux flow occurs after coke boiling starts. Steam has formed
over top of core. Student may select due to liquid flow and reflux flow. Cold
leg pipe is also incorrect.
B. Incorrect - Keflux flow occurs after COT& boiling starts. Steam has formed
over top of core. Student may select due to liquid flow and reflux flow. Hot
leg pipe would be correct transport pipe.
~\\..
C. incorrect - Steam produced in the core is transported vie the hot leg pipe
where it is cooled and travels back aiong the same hot leg pipe to the core.
Natural circulation has stopped at this point. Student may see this as natural
circulation, however flow will not return in the cold leg pipe.
B. Corrects Reflow flow is the transport of steam to the SlGs where it is
condensed and travels back to the core along the hot leg pipe.
hd
Page: 1 of 2
5/27/2004
REFERENCES:
Lesson plan 3-OT-MCDOOQ2, p. 11
Lesson plan 3-OT-TAB013, p. 16
k
INPQ Bank Braidwood 7/17/2002
20CFR55 41.8, 10, 45.3
Knowledge 06 the operational implications of the following concepts as they
apply to the small break LOCA: Natural circulation and cooling, including reflux.
80-2 SRO-2
Changed stern of question due to feedback from Ron Aiello.
Reference:
3-OT-MCD0002
KIA value:
4.2
Level:
1
TicdGrp:
1/1
-
Page: 2 of 2
K/A Number: 009 EKI .O I
Last Used:
07i17R002
Source:
BANK
SRO Only:
01 I EK2 02 001
Unit 1 is initially at 60% power:
-
-
-
?A-A containment Spray pump is out of service.
$A-A Safety Injection pump is out of service.
RWST was at its minimum level for operability when the event occurred.
L
A barge break LOCA occurs. The operating crew takes action in accordance
with E-?, Loss of Reactor or Secondary Coolant.
The following conditions currently exist:
-
-
-
-
Containment pressure is 3 2 psig, DROPPING slowly.
RCS pressure is 200 psig. STABLE.
Pressurizer level is offscale LOW.
All operable pumps are delivering DESIGNED flowrate
Which ONE of the following lists the approximate time before to transition to
ES-I .3, "Transfer to Containment Sump" is required? (Use reference provided)
A. 15 minutes
BY 20 minutes
C. 25 rninutes
D. 30 minutes
k-
The correct answer is 8.
A. Incorrect - If ALL pumps are used at designed flow (15450 gpm) the WWST
would reach 34% (recirc swapover setpoint) in 14.2 minutes.
3.
Correct - With design flowrate used OR AVAILABLE pumps (10725 gprn) the
RWST will reach 34% (recirc swapover setpoint) in 20.5 minutes.
C. incorrect - Using ALL pumps at design flow (15450 gpm) will completely
empty the WWST in 24.5 minutes.
RWST level to 8%, (level at which all pumps taking a suction on RWST must
be secured) in 29 minutes.
B. lncorrect - Using available pumps at design flow (10725 gprn) will reduce
.:
.*->
Page: 1 of2
5/27/2001
REFERENCES:
TI-4 part II appendix 29 - Must be provided to the examinees
Lesson plan 3-OP-SYSQ63A
Lesson plan 3-OT-SYS072A
INPO Bank Beaver Valley 12/01/2002
10CFR55 41.7,45.7
Knowledge of the interrelations between the and the following Large Break
LOCA: Pumps (note: WA wording is exact\\y as given in NUREG-1122 Rev. 2)
--A
R O - 3
SRO-3
Reference:
3-OT-SYS063A
&'A value:
2.6
Level:
2
TieriGrp:
111
Page: 2 of 2
WA Number: 01 1 EK2.02
Last ilsed
12/01!2002
Source:
SRO Only:
5/27/2004
017AA1.03 001
Given the following plant conditions:
- The Unit is operating at 100%.
-
Loop 2 RCP #I
SEAL LEAKOFF FLOW HI alarm is LIT.
-
Loop 2 RCP #2 SEAL STANDPIPE LEVEL Hl/LO alarm is NOT LIT
-
Loop 2 RCP #2 seal leakoff flow recorder indicates offscale HIGH.
-
Charging flow has risen 40 gpm to maintain pressurizer level.
Which ONE of the following Loop 2 RCP seal failures has occurred?
@he #I
seal has failed and the RCS pressure drop is across the #2 seal.
E!. The #I and #2 seals have failed and the RCS pressure drop is across the #3
seal.
6. The #2 seal has failed and is allowing water from the standpipe to flow out
the #I
seal leakoff line.
D. The #2 and #3 seals have failed and the RCS pressure drop is across the #1
seal.
The correct answer is A.
A. Incorrect - operator may misdiagnose indications.
B. Incorrect -operator may misdiagnose indications.
C f-3 Core f - # 1 seal failure results in high leakoff Rowrate as indicated by aaarm
D. Incorrect - operator may misdiagnose indications.
If operator had misconception of seal flow and leakoff paths he would not be
able to differentiate between different types of seal failures.
REFERENCE:
AOI-24, "RCP Seal Abnormalities During Pump Operation" Rev. 27.
Lesson plan 3-OT-A812400
Lesson plan 3-OT-SYSO68B
IOCFR41.5,41.10145.6,45.13
Ability to operate and /or monitor the following as they apply to the Reactor
Coolant Pump Malfunctions: Reactor trip alarms, switches, and indicators.
\\?$,,ah
recorder. Full system pressure will be placed upon the #2 seal.
R O - 4
SRO-4
.
-
a
Page: 1 of 2
5/27/2004
Reference:
AOI-24
KIA value:
3.713.8
Level:
2
TierjGrp:
1!1
-4
WANumber: 017 AA1.03
Last Used:
Source:
BANK
SRO Only:
-*
Page: 2 of 2
022 G2.4.7 001
Given the following plant conditions:
-
Unit is at 8Pko power.
-
1A-A Charging Pump is in service.
-
C-S CCS pump is aligned to its normal source.
-
A loss of 6.9kV Shutdown Board 1 B-B occurs.
--
-
1A-A CCS pump is tagged out of service.
Which ONE of the following actions is required within 10 minutes in order to
maintain charging and seal injection?
A? Manually align ERCW flow to CCP 1A-A in the pump room.
B. Start Thermal Barrier Booster Pump 1A-A from the main control room
6. Transfer C-S CCS pump to its alternate power supply using the local transfer
switch.
D. Align 25-B CCS pump to replace 1 B-E3 CCS pump from the main control
The correct answer is A.
room.
A. Correct - if ERCW is manually aligned to supply cooling flow to CCP 1/4-14
within 10 minutes the pump should continue to run and supply seal flow and
charging.
5. Incorrect- start of TBBP will not ensure protection of RCP seals since no
CCS pumps are avaiiable to supply their suction. Examinee may think if the
"A" train pump is started cooling will be provided to the thermai barriers.
C. Incorrect - transfer of the C-S CCS pump power supply will not restore flow
to "A' train CCS. Examinee may confuse which pumps are aligned to
provide CCS to "A' train ESF equipment.
D. Incorrect - 2B-B CCS pump can not be aligned to replace the 1 B-%I CCS
pump but may be aligned to replace the C-S pump.
REFERENCES:
Lesson plan 3-OT-AOI1500; AOI-15
10CFW55 43.5 i45.13
Loss of Reactor Coolant Makeup: Knowledge of local auxiliary operator tasks
during emergency operations including system geography and system
implications.
R O - 5 SRO-5
.-
Page: 1 of 2
5/28/2004
Reference:
AOI-15
K!A valuc:
1.evel:
2
TieriGrp:
lil
.
Page: 2 of 2
K'A Number: 022 (72.4.35
Last I k d :
Source:
RANK
SRO Only:
5/28/2004
025 G 2.1.33 001
Given the following conditions:
-
Plant is in MODE 5 with "A" Train of RHR in service.
-
All 4 SlG's drained for maintenance to inspect moisture separators
-
RCS loops remain filled.
-
RCS temperature 100" F.
-
.
.
'\\*.
RCS boron concentration stable at 1240 ppm and NO dilution in
progress.
Which ON of the following describes correct operator actions if the
operating RHR pump trips on overcurrent due to motor fault?
Enter Tech Spec LCO action, place "B" RHR pump in service and;
A. Exit the Tech Spec action.
B. Align boration fiowpath to the RCS, then exit the Tech Spec action
CY Return the " A pump to operable status, then exit the Tech Spec action.
D. Restore level in at least 1 SIG to 2 6% wide range (WR), then exit the
Tech Spec action.
The correct answer is C
A. incorrect - Action statement will be applicable until the inoperable pump is
returned to service. Student may mistakenly exit statement once there is
an operable loop in operation.
..~..-.
'
B. Incorrect - Specification only requires that operations involving RCS
dilutions be suspended. No provisions are made to align boration
flowpath. Student may choose this distractor to ensure there is no
possibility to dilute the RCS.
C. Correct - Acton statements are of the immediate category and will be
active until the inoperable pump is declared operable. Only then is the
action statement exited.
D. Incorrect - Action to restore two S/G's level to 5 6% narrow range (NR)
applies to loops filled specifiation however the distracter provides only f
SIG and wide range (WR) level. Examinee may only think one SIG is
adequate since normally only one SlG is required as a heat sink by
system design or confuse NR and WR level requirements.
I
Page: I: of 2
5/28/2004
Reference:
WBN Bank - SYS074.42.002
Lesson plan 3-OT-SYS074A
TIS 3.4.8 RCS loops - MODE 5 loops Not Filled
10 CFR 55 43.2, 3,45.3
Ability to recognize indications for system operating parameters which are
entry-level conditions for technical specifications.
R O - 6
SRO-6
Revised from comments from Ron Aiello.
-
Reference:
3-OT-SYS074A
WA value:
3.4
I.eve1:
2
TieriGrp:
1!1
Page: 2 of 2
K!ANumber:
023 G 2.1.33
Last Csed:
Source:
BANK
SRO Only:
026 AAI 06 001
Given the following plant conditions:
-
A tube leak has developed in the Non-Regenerative heat exchanger.
-
Charging and Letdown have been isolated.
The operating crew is placing excess letdown in service in accordance
with AOI-15 "Loss of Component Cooling Water (CCSJ".
Which ONE of the following is the correct final adjustment of Excess Letdown
temperature?
A. CCS outlet flow is adjusted to ensure maximum letdown flow while
maintaining CCS outlet temperature less than 200OF.
-
B. CCS outlet flow is adjusted to ensure maximum letdown flow while
maintaining LETDOWN outlet temperature less than 200OF.
6. Letdown outlet flow is adjusted to ensure maximum letdown flow while
maintaining CCS outlet temperature less than 2Q00F.
D./ Letdown outlet flow is adjusted to ensure maximum letdown flow while
maintaining LETDOWN outlet temperature less than 200OF.
The correct answer is D.
A. hcorrect - CCS outlet flow is not adjusted. Outlet temperature maintained is
.
.
.
-'
letdown temperature. Student may think it is CCS that is adjusted.
B. incorrect ~ CCS outlet flow is not adjusted. Second part of response is
C. Incorrect - Letdown flow is adjusted. CCS outlet temperature is not the
parameter maintained less than 200OF. Students may think CCS outlet
temperature is maintained parameter.
correct. Student may think it is CCS that is adjusted.
B. Correct - Letdown flow is adjusted and letdown outlet temperature is the
parameter maintained less than 200OF.
REFERENCES:
Lesson plan 3-OT-SYS062A
AOl-15 Loss of Component Cooling Water
10CFR55 41.7,45.5, 6
Ability to operate and I or monitor the following as they apply to the LQSS of
Component cooling Water:Control of flow rates to components cooled by the
CCWS
R O -7
SWO-7
.'..
5/27/2004
Reference,
3-OT-SYS062A
WA value:
2.9
Level:
2
TierGrp:
lil
b
.~
Page: 2 of 2
W h Number: 026 AA1.06
Last Used:
Source:
NEW
SRO Only:
5/47/2004
027 AK2.03 001
Given the following plant conditions:
-
Plant is at 100% power.
-
Following a step load change pressurizer pressure drops to 2205 psig
- Automatic pressure control cycles all pressurizer backup heaters ON.
- As pressure rises to 2215 psig, Master Pressure Controller,
PIC-68-340A, is inadvertently placed in MANUAL.
.
.
L-
As Pressurizer pressure RISES, which ONE of the following describes the
system response if the operator takes NO action?
A. Spray valves open to control pressure.
BJ Only PORV PCV-68-334 opens to control pressure.
C. Only PORV PCV-68-340 opens to control pressure
B. PORV PCV-68-334 and PCV-68-340 both open to control pressure
The correct answer is B.
A. Incorrect - Spray valves are being controlled in manual and will not respond
to high pressure signal. Student may select wanting spray valves to control
pressure.
B. Correct - PORV 68-334 is not controlled by master controller. PORV will
open at setpoint to control pressure.
not open to control pressure. Student may confuse PBRVs.
respond.
REFERENCES:
Lesson plan 3-OT-SYS068C p.21-22
AOl-$8 p. 13 Discussion
1 QCFR55 41.7, 45.7
Knowledge of the interrelations between the Pressurizer Pressure Control
Malfunctions and the following: Controllers and positioners
C. Incorrect - PORV 68-340 is controlled by master controller in manual and will
B. incorrect - Both PORVs will not open. Student may select thinking both
R O - 8
SRO-8
Reference:
AOI-18
K:A value:
2.6
Level:
2
.i
TierKirp:
111
Page: 1
KIA Number: 027 AK2.03
Last {!sed:
Source:
BANK
SKO Only:
5/28/2004
029 EK2.06 001
Given the following plant conditions:
-
-
~
RCS leakage has risen above Charging pump capacity.
The OAC initiates a reactor trip from the control room.
While verifying Step 'I of E-0 "Reactor Trip or Safety Injection", the red
indicating lights for both Reactor Trip Breakers (52lRTA and 52iRTB) are
illuminated and the green indicating lights are extinguished.
\\r-
Which ONE of the following describes the current status of the components
associated with each Reactor Trip Breaker (RTB)? (assume the RTBs are NOT
mechanically bound)
A. The Undervoltage Coil is energized, the Shunt coil is energized.
B. The Undervoltage Coil is de-energized, the Shunt coil is energized.
C!, The Undervoltage Coil is energized, the Shunt coil is de-energized
D. The Undewoltage Coil is de-energized, the Shunt coil is de-energized.
The correct answer is C.
A. Incorrect
~ Student may confuse distractor.
B. incorrect
~ Student may confuse distractor
C. Correct - Reactor trip signal was not passed to the breakers, Therefore the
coils remain in thier normal state. UV-energized and Shunt de-energized.
L-.-
D. Incorrect - Student may confuse distractor.
When a Reactor Trip signal is passed to the RTBs the klV coil will de-energize
and the Shunt coil will energize. This question tests the students abiltty to
recognize that a trip signal has not been sent to the RTBs (ATWS) and the
correct status of each coil. (normal and trip states)
REFERENCES:
Lesson plan 3-OT-SYS099A p. 19
Braidwood exam 711 712002
10CFR55 41.7, 45.7
Knowledge of the interrelations between the and the following an ATWS: Breaker,
relays, and disconnects.
RO -9 SRO-9
Page: 1 of 2
5/27/2004
Reference:
3-OT-SYS099A
KiA value:
2.9
Level:
2
TierlCrp:
111
WA Number: 029 EK2.06
Last Used:
4:17/2002
Source:
BANK
SRO Only:
.:
-
Page: 2 of 2
5/27/2004
038 EK3.01 001
Given the following plant conditions:
-
A Steam Generator tube Rupture has occurred.
-
The operating crew is performing actions contained in E-3 "Steam
Generator Tube Rupture".
.
.
"-.
Which ONE of the following describes the primary reason for reducing RCS
pressure to match ruptured S/G pressure in E-3 ?
A? To restore RCS inventory and reduce break flow prior to stopping ECCS
pumps.
B. To eliminate the concern for S/G overfill and damage to secondary steam
C. To minimize the probability of a Pressurized Thermal Shock event when RCS
piping.
'.:
cooldown is commenced.
D. To ensure that there will be no release of radioactivity througfi the SIG
Atmospheric Bump valves for the duration of the SGTR.
The correct answer is A
A. Correct - The object of the depressurization is to stop 10 to 20 leakage,
restore RCS inventory as demonstrated by PZR level prior to securing ECCS
--
flow.
B. Incorrect - May not be able to stop overfill and the concern for secondary
C. Incorrect - PTS is only a concern if S/G pressure is low. ( also faulted)
D. Incorrect - May not be able to stop release if SGTR is large enough.
REFERENCES:
Lesson plan 3-OTdOP0300 p. 28 -29
E-3 "Steam Generator Tube Rupture"
Background document 4 p. 94
Indian Point Exam 3/10/2003
piping.
20CFR55 46.5, 18,45.6, 13
Knowledge of the reasons for the following responses as they apply to the
SGTK: Equalizing pressure on primary and secondary sides of ruptured SIG.
R O - I 0
SRO-10
--a
Page: 1 of 2
5/27/2554
Reference:
3-01-E010300
KIA value:
4.1
Level:
1
TieriGrp:
11
-
-.
Page: 2 of 2
WA Number: 038 EK3.01
Last Used:
3/10/2003
Source:
BANK
SRO Only:
5/27/2004
054 AAI 02 001
Given the following plant conditions:
-
-
S/G pressures 1100 psig.
-
SI6 level is being maintained on program with By-pass Feed Reg valves
in AUTO.
-
A trip of the Standby Main Feed pump has occurred due to an overcurrent
condition.
Unit 1 is currently in Mode 3
k
-
Tavg=5570F
Which ONE of the following describes the correct operator action in accordance
with AOB-16 "Loss of Normal Feedwater" ?
A. Verify auto initiation of all AFW pumps.
5. Manually start one MDAFW pump only.
C. Manually start the TDAFW pump only.
D? Manually start all AFW pumps.
The correct answer is D.
A. Incorrect - Trip of Standby Feed pump does to auto start AFW. Student may
mistake this for Auto start signal.
-
5. Incorrect - One MDAFW pump would be enough feed to prevent loss of heat
sink but only feeds 2 of 4 S/Gs. Student may want to start only one pump.
C. Incorrect Two MDAFW pumps will feed all SGs. Student may be reluctant
to start TDAFW pump with only RCPs providing heat for steam production.
8. Correct - AOI-16 requires start of all AFW pumps. Manual actions match the
plant response to an auto initiation which would start all AFW pumps.
REFERENCES:
Lesson plan 3-OT-A0%1600
AOI-16 "Loss of Normal Feedwater"
10CFR55 41.7, 45.5, 6
Ability to operate and I or monitor the following as they apply to the boss of
Main feedwater: Manual startup of electric and steam-driven AFW pumps.
RO-ll SRO-11
-..*
incorporated comments from Ron Aiello
Page: 1 of 2
5/27/2004
Reference:
3-OT-AO! 1600
WA value:
4.4
Level:
i
TieriGrp:
111
.-
WANumber: 054 AA1.02
Last Used:
Source:
NEW
SRO Only:
i
Page: 2 of 2
5/27/2004
055 EK1.02 001
Given the following plant conditions:
-
A loss of all AC power occurred while the unit was at 100% power.
-.
-
ECA-0.0, boss of Shutdown Power, was impiemented.
- The crew is performing step 20, Depressurize intact SIGs to 305 psig.
-
All SIG levels drop to - 10% narrow range.
-
Operating crew terminates the SIG depressurization.
Which ONE of the following describes the operational implication if all SIG levels
are allowed to drop below 15% NR level?
A? Natural circulation may NOT be effective in removing heat from the RCS.
B. Sufficient steam supply may NOT remain available for TBAFWP operation
C. SIG tubes may NOT remain covered in order to insulate liquid and vapor
space to prevent sudden depressurization.
D. Primary to secondary leakrates would be excessive in the event a SGTR
occurred during the depressurization.
The correct answer is A
A. Correct - SIG narrow range level must be maintained above 10% to provide
B. Incorrect
~ although steam pressure and S/G levels may drop, TDAFWP
adequate heat transfer to ensure natural circulation.
-
operation should not be a concern at this point. Operator may incorrectly
prioritize this issue.
C. Incorrect - the potential for uncovering the tubes is a potential, however the
concern is NOT for potential sudden depressurization. Operator may relate
this distractor to similar bases in E-3 for SGTR which is not correct for this
situation.
8. Incorrect - an individual who does not understand the mechanics of
transients may believe that maintaining tubes covered would help mitigate
SIG tube leakage.
-
Page: 1 of 2
5/27/2001
REFERENCE:
WBN exam bank ECA0000.04 004
- Lesson Plan 3-OT-ECA0000
10 CFR 55 41.8 I41.10 145.3
Knowledge of the operational implications of the following concepts as they
apply to the Station Blackout: Natural circulation cooling.
RQ-12 SRO-$2
Reference:
ECA-0.0
KIA value:
4.114.4
Level:
2
Tieri'Grp:
1!1
. -a
Page: 2 of 2
WA Number: OS5 EK1.02
Last Used:
Source:
SRO Only:
5/27/2004
056 ~ 4 2 . 1 8
001
Given the following conditions:
-
-
Reactor tripped from IQQ%
power due to a [oss of offsite power.
T-HOT as observed on the control room recorder initially drops, then
rises over the next several minutes.
-
Which QNE of the following correctly describes the observed conditions?
AY This is normal because a AT is needed to established the thermal driving
head for Natural Circulation.
B. This is normal because of the long time delay for AFW to provide water
for decay heat removal.
C. This is normal because initially the Steam Dump System ramps open and
then modulates closed causing AT to rise.
B. This is abnormal and indicates Natural Circulation is NOT being
established.
The correct answer is A
A. Correct - T-hot will lower following a trip then rise to establish delta4 for
naturai circulation.
B. Incorrect
~ AFW will have no effect on T-hot until natural circulation is
established.
L-
C. Incorrect - Steam dumps will also be in-effective until natural circulation is
established and will have no initial effect on T-hot.
B. Incorrect - Students may wish to see T-hot stable or lowering when
natural circulation is established. Natural circulation has not yet been
established, therefore T-hot lowering would not be observed.
REFERENCES:
ES-0.2 WQG Backgound Document
lQCFR55.43.5145.13
Ability to determine and interpret the following as they apply to the Loss of
Offsite Power.
RO-?3
SRO-13
--
Page: I of 2
5/27/2004
Reference:
WAvalue:
3.8
Level:
2
TPierGrp:
111
v
s.
Page: 2 of 2
&'A Number: 056 AA2.18
Last Used:
Source:
BANK
SRO Only:
5/25/2004
057 AK3.01 002
Given the following plant conditions:
-
Plant is at 100% power.
-
A loss of 120V AC Vital Instrument Power Board 4-1 occurs.
-
The operating crew implements AOI-25.01, "Loss of 120V AC Vital
Instrument Power Board 1-1 and 2-1".
-
The OAC is directed to ensure controi rods in MANUAL.
i-I
-
All systems operating normally.
Which ONE of the following describes the reason control rods are placed in
MANUAL?
A. J
B.
C.
D.
Loss of the Tref signal causes control rods to step IN if in AUTO.
Failure of channel B NIS power range instrument causes rods to step IN if
in AUTO.
CCP suction shifts from the VCT to the RWST resulting in a boration that
causes control rods to move OUT if in AUTO.
MFW reg valve control(ers fail causing MFW transients that cool the RCS
and cause control rods to move OUT if in AUTO.
The correct answer is A.
- A. Correcf - AOI-25.03 has operator place rods in MANUAL to prevent outward
motion
B. Incorrect loss of this power supply affects channel I PRM and causes it to
fail however, the failure is low and would not affect the auctioneered high
signal from NIS power range monitors to the control rod drive system.
6. Incorrect - this action does occur and would resuit in boration with resultant
rod motion in outward direction however this effect is not immediate thus not
the primary reason for placing rods in MANUAL.
closed and would result in heat up of RCS that would resuit in rods moving in
to compensate.
D. Incorrect - MFW reg and MFWP controllers fail however, the reg valves faiB
..*
Page: 1 oft
ft27/2004
REFERENCES:
AOl-25.03
- 1OCFR55.41.5, I O , 45.6, 45.13
Knowledge of the reasons for the fOllOWiRg responses as they apply to the Loss
of Vital AC Instrument Bus: Actions contained in EOP for loss of vital ac
electrical instrument bus.
80-14 SRO-14
Reference:
3-OT-A012500
WA value:
4.1
Level:
2
TieriGrp:
lil
W A Number: 057 AK3.01
Last Used:
Source:
NEW
SRO Only:
.
Page: 2 of 2
5/27/2004
062 AA2.03 001
Which ONE of the following correctly describes the required actions of
AOI-13, "Loss of ERCW, for a I-A ERCW s~ipply header in the yard?
A? Align 1A-A and 2A-A DIG ERCW supplies to the B Train supply headers.
8. Align 1A-A and 1 B-B BIG ERCW supplies to the 8 Train supply headers.
C. Align 15-B and 28-8 DIG ERCW supplies to the B Train supply headers.
D. Align 2A-A and 2B-B BIG ERCW supplies to the B Train supply headers.
The correct answer is A
-
A. Correct - 1A-A and 2A-A are aligned to B train supply.
B. Incorrect - Student may confuse which EDGs are supplied from 2-A
i
C. Incorrect - Student may confuse which EBGs are supplied from I-A
D. Incorrect - Student may confuse which EBGs are supplied from I-A
REFERENCES:
L#
3-OT-A011300 p.16
AOI-13 Section 3.4 step 9
IOCFR 55.43.5/45,13
Ability to determine and interpret the following as they apply to the boss of
Nuclear Service Water: The valve lineups necessary to restart the SWS while
bypassing the portion of the system causing the abnormal condition.
8 0 - 1 5
SRO-15
Reference:
3-OT-AI01300
IC'A value:
2.6
Level:
1
TieriGrp:
Ill
IUA Number: 062 AA2.03
Last Used
Source:
BANK
SRO Only:
Page: 1
5/27/2004
E04 EA22 001
Given the following plant conditions:
-
A small break LOCA has occurred outside containment.
-
RCS pressure was slowly DROPPING.
-
One CCP was injecting.
-
As valves are being closed in an effort to identify and isolate the leak, a
second CCP is made available; the pump is started and is injecting.
-
RCS pressure begins slowly RISING.
-2
-
ECA-I 2,
"LOCA Outside Containment" has been implemented.
Which ONE of the following describes the operating crew's response regarding
adherence to the EOPs?
A. Continue in ECA-2.2; IF break is isolated, THEN transition to ECA-1.1, "Loss
B? Continue in ECA 1.2; IF break is isolated, THEN transition to E-? "Reactor
Trip or Safety Injection".
C. IMMEDIATELY exit ECA-1.2 and transition to ECA-1 .I,
Recirculation".
D. IMMEDIATELY exit ECA-2.2 and transition to E-1, "Loss of Reactor or
Secondary Coolant".
The correct answer is B.
A. Incorrect - Examinee may believe that since LOCA was outside containment
L.
that transition must be to ECA-1 .I.
B. Correct - if the break is isolated when the transition step is reached, transition
C. Incorrect - transition to another procedure is not made until the procedure is
completed and break status is determined, then transition will be made lo
either E-I or ECA-I .I.
Examinee may think that since RCS pressure is rising
that the break is isolated or loss of inventory has been mitigated and
transition to another procedure is allowed.
D. Incorrect -transition to another procedure is not made until the procedure is
completed and break status is determined, then transition will be made to
either E-? or ECA-1.1. Examinee may think that since RCS pressure is rising
that the break is isolated or loss of inventory has been mitigated and
transition to another procedure is alLowed.
to E-I is correct.
_-
Page: I oh2
5/27/2004
REFERENCE:
INPO exam bank Beaver Valley 12/01/2003
L- Lesson Plan 3-OT-ECAO101
10 CFR 55 41.7 I 45.5 / 45.6
Ability to determine and interpret the following as they apply to the (LOCA
Outside Containment) Adherence to appropriate procedures and operation
within the limitations in the facility's license and amendments.
RO-16
SRO-16
Reference:
ECA-I .2
KIA value:
3.6I4.2
Level:
2
TierIGrp:
1/1
,
Page: 2 of 2
WA Number: E04 EA22
Last Used:
12/01I2003
Source:
BANK
SRO Only:
5/27/2004
E0S.EKI.I 001
Given the following plant conditions:
-
The Operating crew is responding to a Loss of AFW in accordance with
FR-H.1 "Loss of Secondary Heal Sink".
~
The control room crew notes the foilswing:
-
Containment conditions are normal.
-
-
'.-'
RCS pressure is 2275 psig
SG wide range levels are:
- 2
- 2
- 3
- 4
34% 35% 34% 38%
-
No AFW pumps can be restored at this time.
Given these plant conditions, which ONE of the following identifies the
operationai implication (basis) of stopping the RCPs in accordance with step 9 of
FR-H.7 "Loss of Secondary Heat Sink"?
A. Prevents core uncovery and minimize an inadequate care cooling condition.
8. Establishes natural circulation to enhance the bleed and feed capability of
CY Improves the effectiveness of the remaining water inventory while continuing
5. Protects the RCPs from the low pressure caused by the subsequent
...-.
depressurization of the RCS.
The correct answer is C.
safety injeetian.
effori: to establish a feed train.
A. Incorrect - This is the basis for Bleed and Feed. Bleed and Feed conditions
have not been satisfied in this question. Student may select this if it is
believed that a transfer to Bleed and Feed is required.
B. Incorrect - Natural circulation will not enhance the Bleed and Feed capability
C. Correct - RCPs are stopped to prolong the time for establishment of a
of SI.
secondary feed train. The heat input from the RCPs is removed.
&4.Lcc/;y,
, .
B. Incorrect - RC.Ps)lurM not initially threatened by low RCS pressure in this
event. When the PORV is opened RCS pressure will drop. Student may
select this option to protect the RCPs from cavitation.
Page: 1 of 2
5/28/2004
REFERENCES:
Lesson plan 3-QT-FRH0001 p.14
Knowledge of the operational implications of the following concepts as they
apply to the (Loss of Secondary Heat sink) Components, capacity, and function
of emergency systems.
v
10CFR55.41.8/41.10/45.3
RQ-17
SRO-17
Reference:
3-OT-FRH000 1
KiA value:
3.8
Level:
I
TiedGip:
lii
. _
Page: 2 of 2
KIA Number: W!EOS.EKf
. I
Last Used:
Source:
NEW
SRO Only:
5/28/2003
E l i 2 4.21 001
Given the following plant conditions:
- A large break LOCA has occurred.
-
1-FCV-63-72 and 1-FCV-63-73, RHR sump suction valves failed to open
following automatic initiation of sump swapover and could NOT be
manually opened.
-
RHR and Containment Spray are aligned to the WWST
-
The operating crew implemented ECA-2 .I
Recirculation".
~
The STA observes Containment pressure at 6 psig and transition to
FR-2.1 is performed.
Which ONE of the following identifies the procedure that should be used to
operate the containment spray pumps and why?
A. FR-%.I; maintains full containment spray
B. FR-Z.1; because the orange path for FR-2.1 takes precedence over
-
ECA-1 .I.
C? ECA-1 .I
- provides for reduced containment spray
D. ECA-I . 2 ; because the ECA must be completed prior to implementing an
The correct answer is C
A. Incorrect - FW-Z.l allows full operation of containment spray. Orange path
does exist and FR-Z.1 will be implemented, however ECA-1.1 states that
containment spray should NOT be operated in accordance with FR-2.1.
ET. Incorrect - orange path does exist and FR-Z.1 will be implemented, however
ECA-1 .I
states that containment spray should NOT be operated in
accordance with FR-Z.1.
FRI.
b
6. Correct
~ ECA-1 .I
controls containment spray operation until it is aligned to
the cntmt sump or RWST makeup is sufficient. Reduces Containment spray
to conserve the RWST inventory.
D. Incorrect
~ examinee may confuse ECA-1.1 with ES-1.3, "Transfer To
Containment Sump" which is a higher priority than the FRls, however
ECA-2 .'I states that containment spray should NOT be operated in
accordance with FR-Z.1.
i
Page: 1 of 2
5/27/2004
REFERENCE:
INPO Bank ~ Diablo Canyon 10/01/2002
- Lesson Plan 3-OT-ECA0101
ECA-1. I,
Loss of RHR Sump Recirculation
10 CFR 55 43.5145.12
Knowledge of the parameters and logic used to assess the status of safety
functions including; 1. Reactivity control; 2. Core cooling and heat removal; 3.
Reactor coolant system integrity; 4. Containment conditions; 5.Radioactivity
release control.
RQ-18
SRQ-18
Reference:
ECA-I .I
WA value:
3.7!4.3
Level:
2
Tier!Grp:
111
-
Page: 2 012
WA Number: El 1 2.4.21
Last Used:
IOi01/2002
Source:
BANK
SRO Only:
5127/2004
005 AK1 03 001
Given the following plant conditions:
Unit is currently at 80% RTP.
The crew identifies one control rod in B bank at 155 steps.
The misaligned rod has been declared inoperable.
-
-
-
--
-
Control bank D rods are at 180 steps.
Which ONE of the following describes a concern associated with the inoperable
rod if left uncorrected?
A. Xenon buildup will have the greatest affect on core power distribution in the
first hour.
3. Xenon burnout will have the greatest affect on core power distribution in the
first hour.
CY Xenon buildup will have the greatest affect on core power distribution after
the first hour.
D. Xenon burnout will have the greatest affect on core power distribution after
the first hour.
The correct answer is C
A. Incorrect - Xenon will build in during the first hour but will have only a limited
affect on core power distribution.
B. Incorrect - Burnout at the affected location should not be occurring.
C. Correct - if left uncorrected Xenon will continue to build until peak value is
reached in -6 - 8 hrs and core power distribution will be affected the most.
B. Incorrect - Xenon will not burn out in the area of the inoperable rod.
REFERENCES:
Lesson plan 3-OT-TAA008; AOI-2; 3-OT-A010200
Knowledge of the operationai implications of the following concepts as they
apply to hoperable I Stuck controi Rad: Xenon transient.
RO-19 SRO-13
Reference:
3-OT-TAAOOS
KiA value:
3.7-
Level:
2
TieriGrp:
1 i2
K!A Number: 005 AK1.03
Last Used:
Source:
NEW
SRO C)nly:
Page: 1
5/28/2004
024 AKZ.OL001
The foflowing alternate flowpaths for Immediate Boration are provided in AOI-34,
"Immediate Boratiun", for use if the normal flowpath through the Boric Acid
Blender is NOT injecting boric acid:
1. Align CCP suction from the RWST
2. Manual boration using 1-ISV-62-929
3. Emergency borate valve 1 -FCV-62-138
Which ONE of the following is the priority sequence in which these alternate
flowpaths are directed to be attempted by AOI-34 until adequate boration flow is
established?
A? 3, 2, 1
B. 2, 1,3
6. 2, 3, 1
D. 1,2,3
The correct answer is A.
A. Cumcf - This is the order of priority given in AOI-34.
5. Incorrect Student may confuse order.
C. Incorrect - Student may confuse order.
D. Incorrect - Student may confuse order.
REFERENCES:
Lesson Plan 3-OT-A013400 p. 8-9
18 CFW55.41.7/45.7
Knowledge of the interrelations between the Emergency Boration and the
following: Valves..
M
RO-20
SRO-20
Reference:
3-OT-A013400
K/A value:
2.7
Level:
1
Tier!Grp:
I /2
WA Number: 024 AK2.01
Last Used
Source:
BANK
SRO Only:
Psge: 1
5/27/2004
037 AK3.06 001
Given the following plant conditions:
-
The operating crew is responding to a tube leak in accordance with
AOI-33, "Steam Generator Tube beak".
-
Chemistry reports at 0815 that S/G #I tube leakage is .07 gpm.
-
At 0845 S G tube leakage is reported to be .08 gpm.
- At 0915 SIG tube leakage is reported to be .09 gpm.
.-.-
Which ONE of the following describes the action and basis for this event? (use
the references provided)
A. Shutdown to 5 50% power with in one hour and be in MODE 3 within the next
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to minimize the possibility of exceeding the 16 CFRICO limits at the
site boundary.
3. Shutdown to 5 50% power with in one hour and be in MODE 3 within the next
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to prevent the crack propagation into a tube rupture.
C. Shutdown to MODE 3 within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to minimize the possibility of
exceeding the 10 CFRIOO iimits at the site boundary.
D!' Shutdown to MODE 3 within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to prevent the crack
propagation into a tube rupture.
The correct answer is D,
A. Incorrect - The rise in leak rate is less than 30 gpdlhr so this action does not
apply. Basis statement also incorrect.
B. Incorrect - the rise in leak rate is less than 36 gpdihr so this action does not
apply. Basis statement correct.
C. Incorrect - Action statement correct, basis statement incorrect.
.~.
D. Correct - Action statement and basis match AOI-33 actions.
REFERENCES:
Lesson plan 3-OT-AO13300
'lOCFR55 41.5, 10, 45.6, 13
Knowledge of the reasons for the following responses as they apply to Steam
Generator Tube Leak: Normal operating precautions to preclude or minimize
SGTR.
RO-21
SRO-21
Page: B of 2
5/28/2004
Reference:
- -01'-A013300
K:A value:
3.6
Level:
-
TierKirp:
1 /2
7
Page: a of 2
KIA Number: 037 AK3.06
Last Used:
Source:
NEW
SRO Only:
OS1 AA2 02 001
Given the following plant conditions:
Turbine load is 600 MW.
.-
-
Condenser backpresslire is 4 0" Hga
-
Which ONE of the following is the MAXIMUM condenser backpressure allowed
by procedure if turbine load is to be raised greater than 600 MW?
A. 3.5 in. Wga
6. 4.5 in. Hga
CY 5.5 in. Hga
D. 6.2 in. Hga
The correct answer is C.
A. incorrect - this setpoint is the maximum allowed by AOI-11 for turbine
load 2 365MW (-3Q%).
B. Incorrect - this value is halfway between the setpoints for 38 and 50% turbine
load.
C. Correct - this value is the maximum allowed for operation 2 600MW(-50%)
id
turbine load in accordance with AOI-I 1.
B. Incorrect -this setpoint is the maximum allowed by AOI-I 1 for turbine
REFERENCE:
load 2 1050MW (-90%).
WBN Bank AOII 100.02 003
AOI-11, Loss of Condenser Vacuum
Lesson Plan 3-OT-AOllIOO
IOCFR 55 43.5 145.13
Ability to determine and interpret the following as they apply to the Loss of
Condenser vacuum: Conditions requiring reactor andlor turbine trip.
RO-22 SRQ-22
Reference:
AOl-l 1
K/A value:
3.9i4.1
Level:
I
---
TierKirp:
i i2
WA Number: 05 1 AA2.02
Last Used:
Source:
BANK
SRO Only:
Page: 1
5/27/2004
6
06j,2.4.11 001
Given the following conditions:
-
Unit 1 at 100% RTP.
Several Auxiliary Building Area Radiation Monitors rise to
the aiam setpoint.
. ,
-,
Which ONE of the following actions should be taken?
A. Check the Aux Bldg Gen Exhaust Fan running.
B? Use the PA to evacuate the Auxiliary Building.
C. Activate the prant emergency alarm and initiate plant assembly.
D. Initiate a Containment Vent isolation (CVI).
The correct answer is E3
A. lncorrect - AOI-31 will have the operator check this fan stopped. Student
may want to have this fan running to provide ventibation of particuiate
activity.
B. Correct - AOI-31 step 1 of section 3.2 has the operator evacuate the
affected area.
Ld
C. incorrect - AOI-31 wit1 have the crew refer to EPlPs but does not force an
emergency alarm or plant assembly.
D. lncorrect - CVI is initiated in section 3.3, this section inifiates an ABI.
Reference:
AOI-31 Section 3.2
10CFR55 41.10143.5l45.13
Knowledge of abnormal condition procedures.
R.0- 23
SRO-23
Reference:
3-OT-A013 1000
KIA value:
3.4
Level:
1
TieriGrp:
1 /2
K1A Number: 061 2.4. I I
Last Used:
Source:
BANK
SRO Only:
-._.
Page: 1
5/27/2004
E01 FAI.1 001
Given the following conditions:
-
-
Reactor Trip and Safety Injection have occurred.
-
- The Unit Supervisor has implemented ES-0.0, "Rediagnosis".
During performance of ES-0.0, the operator reports the following:
- #3 SIG level indicates -43% and RISING
-
AFW level control valves for #3 SI6 indicate CLOSED.
-
Pzr level and pressure slowly BROPPIMG.
Which ONE of the following describes the event that is indicated by the
operator's report?
A. Loss Secondary heat sink.
B. Loss of RCS pressure boundary.
C. Loss of Secondary pressure boundary
D?' Loss of Steam Generator tube integrity
The correct answer is 8.
A. Incorrect - examinee may note the closed status of AFW LCVs and betive
there is an issue with heat sink availability.
B. Incorrect - due to dropping PZR level and Press the examinee may believe a
loss of RCS integrity has occurred. However in accordance with ES-0.0, it
would only be diagnosed as such if SIG parameters indicated no STGR in
progress.
-,
C. Incorrect - examinee may choose this distracter if they thought SiG level
were rising due k~
dropping pressure due to loss of secondary pressure
boundary.
controlled and a SGTR is diagnosed.
D. C o ~ e c t -
SIG levels rising with AFW LCVs closed indicates levels are not
._
Page: 1 of 2
5/27/2004
REFERENCES.
Lesson Plan 3-OT-EOP050
E§-5.0, "Rediagnosis
10CFR5541.7 145.5145.6
Ability to operate and I or monitor the following as they apply to the (Reactor Trip
or Safety lnjectionlaediagnosis: Components, and functions of control and
safety systems, including instrumentation, signals, interlocks, failure modes and
automatic and manual features.
-
80-24
SRO-24
Reference:
E§-0.0
L'A value:
3.713.7
Level:
I
TierIGrp:
I12
_ *
Page: 2 of 2
WA Number: E01 EA1 . i
Last Used:
Source:
NEW
SRO Only:
5/27/2004
E02 EKL 1 001
Given the following piant conditions.
-
Watts Bar has had a Reactor trip and Safety Injection.
-
The crew has transitioned to E§-1 .I,
"Si Termination" and is currently
performing step 4, which states,"if two charging pumps are running then
stop one charging pump and place in &Auto".
L
Which ONE of the fdowing describes the reason for securing one of two
running charging pumps?
A. To prevent pressurizer overfill which may force an undesirable transition to
B. To allow parallel alignment and restart of the stand-by pump after a normal
C!, To determine if one charging pump is sufficient to make-up for RCS shrink or
FR-1.1 ,"High Pressurizer Level".
charging flowpath is established in step 6.
break flow.
8). To determine if pressurizer level is under the control of the operator and if it
is NOT then a transition to ES-I 2,
"Post LOCA Cooldown and
Depressurization", is made.
The correct answer is C.
La-,
A. Incorrect - With two charging pumps running and SI termination criteria met
there may be some concern of a PZR overfill however this is not the reason
for stopping the pump.
B. Incorrect - Step aBgns the remaining running charging pump to normal
charging path. The stand-by pump will not be restated.
control of the operator and that in fact SI Termination criteria have been met.
One charging pump should be capable of maintaining KCS conditions stable
D. Incorrect - If PZW level cannot be maintained then a transition to E-I would
be made.
C. Correct - One charging pump is secured to ensure that RCS is under the
'-,_l
Page: 1 of 2
5R7RQ04
REFERENCES:
Lesson pian 3-OY-EOQOIOO
WOG background document for ES1.l
10CFR55 41.8, 10, 45.3
Knowledge of the operational implications of the following concepts as they
apply to the (SI Termination): Components, capacity and function of emergency
systems.
-
RO-25 SRO-25
Reference:
3-01-EOP0100
WA value:
3.2
Level:
I
Tier/Grp:
1 :2
._
-
Page: 2 of 2
W A Number: WIE02 EK I ~ 1
Last Used:
Source:
NEW
SRO Only:
i
B
E08-2.4.2 001
Given the following temperature and pressure history:
Pime
0000
Cold Lea Temps
RCS Dressure
363OF
1 100 psig
.
-
0030
3
3
~
955 psig
0100
265OF
790 psig
0130
2350F
710 psig
Using the attached critical safety function status tree (FK-P), which ONE of the
following identifies the functional restoration procedure, if any, that the STA
should have recommended at time 81 OO? (Consider only the information
provided)
A.
FR-P.l (Red Path)
B.
FR-P.1 (Orange Path)
C.J
FK-P.2 (Yellow Path)
D.
The correct answer is C.
Status tree satisfied (Green Path)
A. Incorrect - cooldown 4 O O O F in last hour and cold leg temp > 240OF.
B. Incorrect - Cold leg temps =. 2400F.
6. Correct
~ Cooldown a IOOOF, RCS temp > 350OF, pressure > cold over
_I
pressure limit but 248OF.
D. Incorrect - pressure > cold overpressure limit.
REFERENCES:
Lesson Plan 3-OT-FRP0001
FR-0 "Status Trees"
IOCFR55.41.7,45.7, 8
Knowledge of system setpoints, interlocks and automatic actions associated with
EOP entry conditions. Note: the issue of setpoints and automatic safety features
is not specifically covered in the system sections.
80-26 SRO-26
Reference:
3-OT-FRF'000 i
WA value:
3.9
TierGrp
I R
--
Level.
2
WA Number: WE08 2.4.2
Last Used:
Source:
NEW
SRO Only:
..:
Page: 1
5/27/2004
E15 EK3.3 001
Given the following conditions:
-
-
-
The unit has tripped from 100% power.
Phase 3 Containment Isolation has been initiated.
FR-Z.2, "Containment Flooding", has been entered
Which ONE of the following identifies the reason it is important to identify and
isolate the source of flooding that has caused level to exceed 83%.
A. The high level will lower the effectiveness of the ice condenser to remove
heat.
El? Rant components necessary for recovery could be damaged or rendered
6. Wili lead to an overpressure condition that could challenge containment
integrity.
D. Will cause excessive backpressure on recirculation sump isolation valves
and hinder or prevent sump swapover actions.
The correct answer is B.
A. Incorrect - containment levei should not approach a point where it would
block flow through the ice condenser. An Examinee that is not familiar with
physical design of the ice condenser and containment may select this
distrader.
B. Correct - components and instrumentation needed for orderly and safe plant
shutdown are above design flood levei. Fiooding above that levei could
impact those components.
C. Incorrect - since level will reduce total volume in containment pressure some
increased pressure may be expected. Examinee may think pressure rise
would be excessive due to the volume reduction.
8. Incorrect - head pressure caused by the excessive flooding may be greater
that expected however: not enough to interfere with operation of these
valves.
Page: 1 of 2
5/28/2004
REFERENCES:
Lesson Plan 3-OT-FRZQCOI p. 12
WOG background document p.2 FR-Z.2
lQCFR55.41.5/41 .TQ/45.6/45.13
Knowledge of the reasons for the following respon s as they apply to the
(Containment Flooding): Manipulation of controls required to obtain desired
operating results during abnormal, and emergency situations.
FR-Z.2
,.-.
RO-27
SRO-27
Reference:
FR-%.?
KiA value:
2.9
LWd:
I
TiedGrp:
112
Page: 2 of 2
K!A Number: W E I S iiK3.3
last L:sed:
Source:
BANK
SRO Only:
003 K3.03 001
Given the following plant conditions:
-
~
Unit was operating at 40% power when the #4 Reactor Coolant
Pump (RCP) lower bearing temperature began to steadily RISE.
Power was reduced to 8% and the #4 RCP stopped.
Which QNE of the following statements identifies the operator response
necessary to control level in #4 steam generator (SG) when the RCP was
stopped?
A. Feedwater flow to #4 SG will be controlled by the MFW reg valve and will
be greater than the flow to the other 3 SGs.
B. Feedwater flow to the #4 SG wiil be controiled by the MfW reg valve and
will be less than the flow to the other 3 SGs.
.
.
.-.,'
i
6. Feedwater flow to the #4 SG will be controlled by the MFW bypass reg
D? Feedwater Row to the #4 SG will be controlled by the MFW bypass reg
vaive and will be greater than the flow to the other 3 SGs.
valve and will be less than the flow to the other 3 SGs.
The correct answer is D.
A. Incorrect - MFW flow should be controlled by the bypass regs at this
power, and flow must be reduced as steam flow decreased.
5. Incorrect - MFW flow should be controlled by the bypass regs at this
power, however flow would be reduced as steam flow decreased.
.-.
C. Incorrect - MFW flow would be controlled by the bypass regs, however
flow must be reduced as steam flow decreased.
B. Correct - MFW flow would be controlled by the bypass regs at this power
and the flow must be reduced as steam flow decreased.
REFERENCES:
Lesson Plan 3-OT-A010508 p.6
801-5
10CFW55.41.7l45.6
Knowledge of the effect that a loss or malfunction of the RCPs will have on the
following: Feedwater and emergency feedwater.
RQ-28 SRQ-28
Page: 1 ora
5/27/2004
Reference:
AOI-5
WA value:
2.8
Level:
2
TierEPp:
2/1
'4
Page: 2 of2
WA Number: 003 K3.03
Last Used:
NRC9801
Source:
BANK
SRO Only:
5/27/2004
004 K6.07 001
1-TCV-70-192, Letdown HX Temp control Valve, fails due to a broken air line.
Assuming NO actions taken by the operating crew, which ONE of the following
describes the effect of this failure on the plant?
A. Letdown temperature goes UP; the RISE in letdown temperature causes the
letdown demineralizers to remove more boron, resulting in a minor dilution.
.-.
BY Letdown temperature goes DOWN; the LOWERiNG of letdown temperature
causes the letdown demineralizers to remove more boron, resulting in a
minor dilution,
C. Letdown temperature goes UP; the RISE in letdown temperature causes the
D. Letdown temperature goes DOWN; the LOWERING of letdown temperature
causes the letdown demineralizers to removarnore boron, resulting in a
minor boration.
The correct answer is B
letdown demineralizers to release boron, resulting in a minor boration.
.:
A. Incorrect - Letdown temperature goes down.
B. Correct - Mixed bed demineralizers will remove more boron when the inlet
temperature is lowered causing a minor dilution.
.-.
C. Incorrect - Letdown temperature goes down
D. Incorrect - Dilution will occur.
REFERENCES:
Lesson plan 3-OT-SYS062A p. 61
Lesson plan 3-0T-SYS7QA p.28
IN890 exam bank Indian Point 3/10/2QQ3
10CFR55 41.7, 45.7
Knowledge of the effect of a loss or malfunction on the following CVCS
components: Heat exchangers and condensers.
RO- 29
SRO-29
Reference:
3-OT-SYS062A
WA value:
2.7
Level:
2
TieriGrp:
2/1
KIA Number: 004 K6.07
Last Used:
3/10/2003
Source:
BANK
SRO Only:
--
Page: I
5/27/2004
005 K6.03 001
The operating crew is responding to a "Loss of CCS to RHR System" in
accordance with AOI-14, "Lass of Shutdown Cooling". Step one (1) requires the
operators to stop the affected RHR pump.
Which ONE of the following identifies wh
directed to stop
the affected RHR pump?
A:, To prevent severe steam hammer in CCS.
B. To prevent the heat-up of the entire RHR loop.
C. Po prevent cavitation of the affected RHR pump.
B. Te prevent seal failure of the affected RHR pump.
The correct answer is A.
A. Correct - If RHK flow were continued, the HX would heat-up with the KHR
loop. Steam could then form on the CCS side of the HX and a steam
hammer event when CCS re-started.
c _ _ - ~
\\d'
A ?
B. Incorrect - Studeht may confuse this distractor and not want the entire RHR
loop to heat-up with the core.
cavitation and select this distractor.
C. Incorrect - Student may believe increased heat at the suction will lead to
'.-.-
D. Incorrect RHR seal packages are sensitive to heat and student may sebct
to prevent pump failure.
REFERENCES:
Lesson Plan 3-OT-AO11400 p.22
106FR55.41.7145.7
Knowledge of the effect of a loss or malfunction on the following will have on the
RHRS: RHR heat exchanger.
88-30 SRO-30
Reference:
3-OT-A011400
K'A value:
2.5
Level:
2
TierKirp:
2il
WA Number: 005 K6.06
Last Used:
Scurce:
NEW
SROOniy:
NEW
s'
Page: I
5/27/2004
006 K5.09 001
Given the following plant conditions:
- A iarge break LOCA has occurred.
-
Appropriate actions in accordance with E-0, 'Reactor Trip or Safety
Injection", El, "Loss or Reactor or Secondary Coolant", and E§-1 3,
"Transfer To Containment Sump" have been completed.
RCS pressure is stable at 50 psig.
ECCS is operating in cold leg recirculation mode.
L
-
-
Which ONE of the following statements describes the primary method of long
term decay heat removal?
A. Heat transfer from Reflux boiling in the SIGs.
B. Heat transfer between the RCS and the SIGs due to natural circulation flow.
C. Heat transfer between the RCS and the SiGs due to forced circulation flow.
D!' Heat transfer from the injection of water from the containment sump and the
removal of steamIwater out of the break.
The correct answer is 8.
A Incorrect - SIG are heat source in Large break LOCA event.
B. Incorrect - SIG are heat sourcri in large break LOCA event
C. Incorrect - SIG are heat source in large break LOCA event.
D. Correct - Injection flow and break flow are cooling the core.
REFERENCES:
Y
Lesson plan 3-OT-TAAO13 p. 8
UFSAR section 15.4-2
lOCFR55.41.5145.7
Knowledge of the operational implications of the following concepts as they
apply to ECCS: Thermodynamics of water and steam, including subcooled
margin, superheat, and saturation.
RO-31
SRO-31
Reference:
3-OT-TAA013
WAvalue:
3.3
Level:
2
Tier1Gq.s
2!1
WA Number: 006 K5.09
Last Used:
Source:
RANK
SRO Only:
Page: 1
5/27/2004
007 K5 02 001
Operators are in the process drawing a pressurizer bubble following vacuum
refill of the RCS in accordance with GO-10, Reactor Coolant System Drain and
Fill Operations. GO-10 has a CAUTION, warning the operator to ensure that
PRT (Pressurizer Relief Tank) conditions are returned to normal before
exceeding 85 psig RCS pressure.
Which ONE of the following describes the operational implication of this
CAUTION?
-,
A? Establishing normal conditions in the PRT will preciude damage to the PRT
B. Establishing normal conditions in the PRT will preclude damage to the waste
C. Establishing norma! conditions in the PRY will allow operations to monitor
D. Establishing normal conditions in the PRT will preclude vacuum collapse
rupture disk.
gas header since it normally operates at much less than 85 psig.
PZR reliefs and safeties fer seat leakage before pressure exceeds 85 psig.
damage to the PRT if an RCS eooldown were initiated prior to establishing a
PZR bubble.
The correct answer is A.
A. Correct - The two rupture disks on the PRT at designed to relieve pressure at
B. Incorrect - the PRT is isoiated from the waste gas header at 8 psig by
.-
approximately 85 pig.
PCV-68-301.
C. Incorrect - It may or may not be possible to determine any seat leakage at
D. Incorrect
~ Tank is designed for full vacuum.
REFERENCES:
this RCS pressure or temperature.
GO-10 p.136
3-OP-SYSQ68C p.35
10CFR55 41.5, 45.7
Knowledge of the operational implications of the following concepts as they
apply to PRTS: Method of forming a steam bubble in the PZR.
RO-32
SRO-32
Reference:
GO-10
__
WA value:
3.1
Level:
2
TieriGrp:
2/1
Page: 1
KIA Number: 007 K5.02
Last Used:
Source:
NEW
SRO Only:
5/27/2004
008 KI .04 00 I
Given the following initial conditions in the Component Cooling System
-
-
-
Unit I
SURGE LEVEL HllLQ annunciation in alarm.
L
-
Side A level, I-LI-70-63A, is 87% and RISING.
Side B level, 1-LI-70-698, is 87% and RISING.
U-I Surge Tank makeup valve, q-LCV-70-63A CLOSED.
The CRO observes the following alarms associated with CCS
-
-
-
Which ONE of the following describes the automatic actions that would be
indicated by these alarms?
A. Surge tank vent closed due to high return flowrate from the RCP's
thermal barrier.
B. Surge tank vent closed due to a high return temperature from WCP's
thermal barrier.
C. RCP thermal barrier heat exchanger inlet and discharge valves closed
due to high return temperature.
BY KCP thermal barrier heat exchanger inlet and discharge valves closed
The correct answer is D.
a. Incorrect - high return flow may cause alarms but will not close the surge
tank vents, they close on high radiation.
b. Incorrect - high return temperature from RCP's thermal heat exchanger
would indicate a leak and generate annunciation but not close the vent.
Incorrect - High temperature would not close the Thermal Barrier
isolation.
--,-
due to high differential flowrate
c
d. Correct- high differentia%
flowrate wouid indicate a leak in the thermal
barrier heat exchanger and cause its isolation valves to close.
-_
Page: 1 of 2
5/27/2004
REFERENCE:
WEN Bank SYS070A.08 007
801-15, Loss of Component Cooling Water; Lesson plan 3-0P-A011500
,.-
10CFR50 41.2-41.9 145.7-45.9
Knowledge of the physical connections and/or cause-effect relationships
between the CCWS and the following systems: RCS, in order to determine
ssurce(s) of RCS leakage into the CCWS.
RO-33
SRO-33
Reference:
AOI-15
WA value:
3.3!3.3
Level:
2
TiedGrp:
211
-
Page: 2 of 2
K/A Number: 008 K1.04
Last Used:
NRC980 I
Source:
BANK
SRO Only:
5/27/2004
008 G2.4.18 001
Given the following plant conditions;
-
A LOCA has occurred.
-
Crew has implemented E-0, "Reactor Trip or Safety Injection".
~
Containment pressure is 6 psig.
- 6.9KV Shutdown Board {A-A has a fault and is de-energized.
-
RCS pressure is 1650 psig.
- All systems responded normally to automatic actuation signals.
-
The operator was directed to stop all RCPs.
-J
Which ONE of the following describes the basis for stopping the RCPs?
A. Phase A signal causes isoiation of CCS cooling to RCP oil cooler.
6. Phase A signal causes isolation of ERCW cooling to RCP motor cooler.
C? Phase E3 signal causes isolation of CCS cooling to the RCP oil cooler.
D. Phase B signal causes isolation of ERCW cooiing to RCP motor cooler.
The correct answer is C.
a. Incorrect - examinee may confuse components affected by Phase A or
Phase 6. Phase A does NOT isolate CCS to RCP oil coolers.
b. Incorrect - examinee may confise components affected by Phase A or
-. L.'
..
Phase B. Phase A does not isolate ERCW to the RCP motor coolers.
c. Correct
~ Phase B isolates CCS cooling water to the RCP oil coolers which
could result in damage to the RCPs.
d. Incorrect - Phase B does isolate ERCW cooling to the RCP motor coolers,
however is not the basis for stopping RCPs.
REFERENCE:
E O , "Reactor Trip or Safety Injection"; 3-OT-EOPOQ00.
10CFR50 41 .?(I
I 45.13
Component Cooling Water System: Knowledge of the specific bases for EOPs.
RO-34
SRO-34
Reference.
E-1
WA value:
2.4G.6
Level:
2
TierIGrp:
211
KJA Number: 008 G2.4.18
Last Used:
Source:
NEW
SRO Only:
Page: 1
5/27/2004
010 K5.01 001
Given the following plant conditions:
-
Unit 1 is in mode 5.
- Vacuum refill is complete and the pump has been isolated from the PRT.
-
Charging and letdown have been ba[anced to hold PZR level at 60%.
-
All PZR heaters are energized.
- The pressure in the PRT is 3.8 psig and one PZR P O W is open.
-.-
-
RHR in service at 128OF.
Which ONE of the following lists the PZR liquid space temperature when a
steam bubble will start to form in the Pressurizer?
A. 15106
i
ID. 272oF
The correct answer is C
A. Incorrect - This is the temperature for saturation at 3.8 psia. Student may not
convert 3.8 psig to psia.
L.- 6. Incorrect - Incorrect reading of the steam tabte.
C. Correct - From table 1 of stearn tables this is the Temperature at which
D. Incorrect - Incorrect reading of the steam table.
REFERENCES:
steam will begin to form at 6 psia.
Lesson plan 3-OT-GFETO03
GO-10 RCS Drain and Fill
10CFR55 41 .5,45.7
Knowledge of the operational implications of the following concepts as they
apply to the PZW PCS: Determination of condition of fluid in PZR, using steam
tables.
86-35 SRO-35
Reference:
3-OT-GFET00368C
WA value:
3.5
Level:
2
TieriGrp:
211
WA Number: 010 K5.01
Last Used:
Source:
NEW
SRO Only:
Page: 1
5/27/2004
012 K4.09001
Which ON of the following describes the method used to ensure separation of
control and protection functions sf Eagle-22 Reactor Protection System?
A? Signals sent to the control circuits from Eagle-21 are sent through isolation
B. Control and Protection circuits in Eagle21 receive signals from independent
.-,
devices.
transmitters.
C. Signais sent to the Eagle 21 from control circuits are sent through isolation
devices.
B. Eagle-21 receives input signals from the control circuits output after it has
been verified accurate by the loop processor subsystem.
The correct answer is A.
.:
A. Correcf
~ Signal send to control functions are sent from Eagle-21 through an
isolation device.
B. Incorrect - The same transmitter is used.
C. Incorrect - Signals are used in control circuits after Eagre-21 protection.
B. Incorrect - Eagle-24 gets the signal direct from the transmitter.
.-.
REFERENCES:
Lesson plan 3-OT-SYS099b p.9
10CFR55 41.7 i45.7
Knowledge of the RPS design feature($) andlor interlock@) which provide for the
following: Separation of control and protection circuits.
RO-36
SRO-36
Refwence:
3-OT-SYSO99B
WAvalue:
2.8
Level:
1
TieriGrp:
2;l
K/A Number: 012 K4.09
Last Used:
Source:
NEW
SRO Only:
..
Page: 1
5127f2004
013 K3.02 001
Given the foilowing plant conditions:
-
Unit 1 is at 208% RTP
- All control systems are in AUTO maintaining normal plant parameters.
- An inadvertent Train 'A SI signal has actuated.
B, .
Based upon the conditions stated, which ONE of the following is the expected
effect on the Reactor Coolant System and resultant SSPS actuation? (Assume
NO operator action is taken)
A. HIGH pressurizer level will cause Reactor Trip Breaker 'K to open.
B. LOW pressurizer pressure will cause Train ' B SI equipment to AUTO start.
C. HIGH pressurizer pressure will cause Reactor Trip Breaker 'B' to open.
D!' HIGH containment pressure will cause Train 'B' SI equipment to AUTO start.
The correct answer is D
A. Incorrect - Reactor trip breaker 'A' will be opened by the Train 'A SI. After Rx
B. Incorrect
~ Pressure normally drops following a Rx trip and SI however
trip PZR pressure will go high and generate a trip signal.
charging injection will cause pressure to go high. There will not be a signal to
.d
the Train 'B SI.
C. Incorrect - A high PZR pressure signal will be generated but will not cause
B. Correct - Train 'A' SI will trip the reactor, Charging injection will fill the PZR,
the reactor trip breaker to open since the SI has already opened the breaker.
POWVs and Safeties will fill and rupture the PWT, and SI will auto actuate on
high containment pressure.
REFERENCES:
Lesson plan 3-OT-SYSQ63A
10CFW55 41.7,45.6
Knowledge of the effect that a loss or malfunction of the ESFAS wil have on the
following: RCS
RO-37
SRO-37
Reference:
3-OT-SYS099B
WAvalue:
2.8
Level:
2
.-
TiedGrp:
2/1
WA Number: 013 K3.02
Last Used
Source:
NEW
SRO Only:
Page: I
5/25/2004
023 A2.03 001
Given the following plant conditions:
-
Unit 1 is at 200% KTP.
- Annunciator 104-8 LWR CNTMT CLK FLOW LO is lit.
-
The affected Lower compartment Cooler has tripped.
-
Eiectrical maintenance has determined the cooler has tripped on motor
overload and can not be restarted.
-
The operating crew has attempted to start the stand-by Lower
Compartment Cooler unsuccessfully.
-
Containment temperature is 12WF and RISING.
-
Annunciator 104-6 LWR CNTMT TEMP HI is now LIT.
L-'
Annunciator response instruction (ARI) 10443 LWR CNTMT TEMP HI, provides
additional methods to cool the lower Containment compartment.
1. Containment air return fans.
3. CRBM cooiing fans.
Which ONE of the following is the correct order/priority of listed methods that the
operating crew should implement to restore containment temperature to c 120
OF.
A. 1,3,2
B. 2,1,3
C? 3,1:2
8. 3,2,1
The correct answer is 6.
A. incorrect - List containment air return fans first. This would reduce the ice
contained in the containment and would be less desired than the start of
CRDM fans in the supplemental cooling mode.
B. Incorrect - Selects containment spray first. Exposes containment to water
environment and is less desired than CRBM supplemental cooling.
C. Correct - CKDM suppkmental cooling is the preferred method, followed by
air return fans, then containment spray.
D. lncorrect - Containment air return fans are preferred over containment spray.
Page: 1 of 2
5/28/2004
REFERENCES:
Lesson plan 3-OT-SYSC30C
ARB 104-A, 104-B
iB
1 OC F W55 4 1 .5/43.5/45.3/45.13
Ability to (a) predict the impacts of the following malfunctions or operations on
the CCS; and (bj based on those predictions, use procedures to correct, control,
or mitigate the consequences of those malfunctions or operations: Fan motor
thermal overload high-speed operation.
RQ-38 SRO-38
Reference:
3-OT-SYSO3OC
K!A value:
2.6
Level:
2
TiedGrp:
211
.-.-
Page: 2 of 2
K/A umber:
022 A2.0.3
Last Used:
Source:
NEW
SRO Only:
5/28/2664
025 K601 001
Which ONE of the following describes the problem with excessive frost build-up
in the ice condenser system.
A. Frost build-up may accelerate the process of sublimation which will raise post
accident sump level.
-
B?' Frost build-up may restrict ice condenser door operation and result in a
degradation of the ice condenser effectiveness.
C Frost may raise the pH of the water in the containment sump above the Tech
Spec limit during a LOCA event.
D. Frost may dilute the boron concentration of the water in the containment
sump below the Tech Spec limit during a LOCA event.
The correct answer is 8.
i
A. Incorrect - sublimation could possibly lower Cntmt sump level.
B. Correct -frost build up on ice condenser doors could impede their proper
C. Incorrect - any frost formed would be made up of steam from primary or
operation.
secondary leaks and shouBd be at a pH of -7.0 and would only tend to lower
pW in the sump since ice is maintained at a pH of 9.0 - 9.5.
D. Incorrect - there is no Tech Spec limit on the Cntmt Sump pH during a LOCA.
Examinee may confuse this with the fact that there is a Tech Spec limit on
the ice.
-4
REFERENCES:
Lesson plan 3-OT-SYS061A
INPQ Bank DC Cook 7/07/97
10CFR55 41.7145.7
Knowledge of the effect of a loss or malfunction of the following will have on the
ice condenser system: Upper and iower door of the ice condenser.
Page: 1
RO-39
SRO-39
Reference:
3-OT-SYSO6 130C
KIA value:
3.4
Level:
I
TierfGrp:
211
WA Number: 025 K6.01
Last Used:
7/07/97
Source:
BANK
SRO Only:
5/21/2004
025 Ci2.1.9001
Given the following plant conditions:
-
Plant is operating at 100% power.
CLOSED, goes into alarm.
The ARI directs the operator to defeat the failed AHU.
.
.
-
Annunciator window 744-8, ICE COND AHU BACKDRAFT DMPR
-
Which ONE of the following describes the actions that the control room operator
must take to defeat the failed AHU?
A. Defeat the failed AHll using ICs from the main control room.
6. Defeat the failed AHU input into RONAN from the main control room using
OPDP-4, "Annunciator Disablement".
C. Direct an NAUO to enter the upper ice condenser plenum to open the AHU
local motor circuit protector for the failed AHU.
QY Direct an NAUO to enter the incore instrument room to defeat the failed AHU
using toggle switches on local panel located in the incore instrument room.
The correct answer is B.
A. Incorrect - AHUs cannot be defeated using ICs. Examinee may think
alarm may be removed from alarm scan in ICs
3. Incorrect - the annunciator could be defeated, however this method would
defeat any potential alarms generated by other AHUs.
C. Incorrect - AHUs can be stopped from this location but does not remove
the failed AH19 from the annunciator input and would allow other alarms to
be masked.
B. Correct - allows the input to the alarm circuit to be defeated and will allow
other AHUs to continue to alarm as required. Performed locally in the incore
instrument room.
REFERENCE:
SQI-61 . O l ARI-138-144
10 CFR 55 43.1 145.12 145.23
Ice Condenser: Ability to direct personnel activities inside the control room.
88-40 SRO-48
._
Page: I of 2
5/27/2004
Reference:
AN-138-114
K!A value:
2.5j1.0
Level:
1
Tier!Cirp:
2/ 1
Page: 2 of 2
E A Number: 025 G2.1.Y
Last Used:
Source:
NEW
SRO Only:
5/27/2004
.--
026 K3.02 001
Given the following plant conditions:
-
-
-
-
-
-
2200 - The operating crew is responding to a LOCA.
1225 - ES-1.3 "Transfer to Containment Sump" is in progress.
1235 - RWST level has reached 8% and spray pumps are placed in
1240 - Attempts to establish containment spray recirculation flow
have been unsuccessful.
The crew suspects containment spray recirc sump blockage.
1241 - Step 27 of ES-1.3 directs transition to ECA 1.1 'Loss of
RHR Sump Recirculation", however containment pressure is 11 psig
and FR-Z.l, "High Containment Pressure", is implemented.
2250 -The crew reaches Step 10 of FR-Z.1 "High containment
Pressure", to determine if RHR spray should be placed in service.
Which ONE of the following statements is correct concerning RHR spray?
RHR spray may NOT be started:
A. Until containment pressure reaches 13.5 psig.
B. Until the crew verifies both CCPs and SIPS running
C. Because the RHR pump is aligned to the containment sump.
PULL-TO-LOCK.
-
-.
D? Because RHR injection flow is still needed for emergency core cooling.
The correct answer is D
A. Incorrect - The pressure requirement is 9.5 psig or greater. Student may
confuse 13.5 psig for the pressure required in the status tree for a RED
path in containment.
B. incorrect - Procedure requires only one CCP and one SIP to be running,
and one hour elapsed.
C. Incorrect - RHR pump suction MUST be aligned to the containment sump
to allow RHR spray.
D. Correct - RHR spray flow is not permitted in the first hour following the
accident because RHR injection is needed for core cooling.
Page: 1 of2
5/27/2004
REFERENCES:
Lesson Plan 3-0T-FRZ0001
FR-Z.l
--
IOCFR55.41.7/45.6
Knowledge of the effect that a loss OF malfunction of the CSS will have on the following:
Recirculation spray system.
RO-41
SRO-41
Reference:
3-OT-FR%000 I
K/A value:
4.2
Level:
2
Tier/Grp:
211
Page: 2 uf 2
WA Number: 026 K1.02
Last Used:
Source:
NEW
SRO Only:
039 K4 06 001
Which ONE of the following describes how the Main Steam System design
provides protection against biowdown of ALL SlGs in the event one SIG is
faulted inside containment?
A.
1
ALL MSlVs receive a close signal when actuated by Phase B
Containment Isolation
5 ~ * ALL MSlVs receive a close signal when actuated by High-High
Containment pressure.
Only affected SIG MSlV will receive a close signal when actuated by
Phase 3 Containment Isolation.
Only affected SIG MSIV will receive a close signal when actuated by
High-High Containment pressure.
C.
D.
The correct answer is 5.
A. Incorrect - closure of all MSlVs provide protection for the stated conditions
however Phase B signal does not close MSIVs. Examinees may confuse the
actuation signals since Phase I3 is actuated by High High containment
pressure.
B. Correct - closure of all MSlVs provide protection for the stated conditions and
are closed by High High Containment pressure signal.
c
C. Incorrect
~
High-High Containment Pressure signal cioses all four MSlVs
D. Incorrect - High-High Containment Pressure signal closes all four MSIVs.
REFERENCES:
Lesson Plan 3-OV-SYS002A p. 15&20
FSAR 10.3-3
Main Steam system description p. 27
1QCFR55.41.7
Knowledge of MRSS design feature(s) andlor interlock(s) which provide for the
following: Prevent reverse steam flow on steam line break.
80-42 SRO-42
Reference:
3-(YI'-SYS001 A
KJA value:
3.3
Level:
1
'TierKiip:
2 3
IGA Number: 039 K4.06
Last Lised:
Source:
NEW
SRO Only:
Page: 1
5/28/2004
056 A2.04 001
Given the following plant conditions:
-
Unit 1 was operating at 90% power.
- The suction pipe of the 'A' Hotwell pump ruptured.
-
The unit tripped and all systems responded as designed with the
exception that the crew was unable to start any AFW pumps.
-
The crew has performed the immediate actions of E-0, 'Reactor trip
or Safety Injection".
-
SIG narrow range levels are 13% and dropping.
Which ONE of the foliowing statements identifies the correct procedure transition?
A. Transition to FR-H.l "Loss of Secondary Heat Sink", from the foldout
page of ES-0. I,
"Reactor Trip Response".
Response", at step 3 if AFW can not be established.
B. Transition to FR-H.1 "LQSS of Secondary Heat Sink", from of ES-0.1 "Reactor Trip
CJ Transition to FR-H.1 "Loss of Secondary Heat Sink, from the foldout
page of ES-0.1 "Reactor Trip Response", when all SIG narrow range
levels are less than 10%.
D. Transition to FR-H.1, "Loss of Secondary Heat Sink, fromgof ES-0.1
z
"Reactor Trip Response"; when all SIG narrow range levels are less than
10% and the STA completes the next update of status trees.
.
The correct answer is C.
A. Incorrect - FR-H.l entry requires NR level less than 10% with no feed
flow. bevels at 13% do not meet entry requirements.
B. Incorrect - Step 3 requires the operators to verify less than 10% level
before a transition to FR-H.l
C. Correct- When NR levels go below 10% the operators should transition
to FR-H.l
D. Incorrect - The crew should not wait on the STA to complete status tree
monitoring but should transition off the foldout page.
REFERENCES:
ES-0.1 Foldout page.
TI-12.0 ) predict the impacts of the following malfunctions or operations on the
Condensate System; and (bj based on those predictions, use procedures to
correct, control, or mitigate the consequences of those malfunctions or
operations: Loss of condensate pumps.
RO-43
SRO-43
Page: I of 2
5/28/2004
Reference:
Ti-12.04
KIA value:
2.6
1 .evel:
2
TierGrp:
2 3
Page: 2 of 2
W.4 Number: 056 A2.04
Last Used:
Source:
NEW
SRO Only:
5/28/2004
059 A3 02 00 I
The unit was operating at 80% power with all systems operating normally when
PRM-142 fails LOW.
Which ONE of the following lists how SI6 NR kevels will change?
A. SJG 1 drops -18%.
B. SIG 2 drops -22%.
-*
CY SIG 3 drops -18%.
D. SIG 4 drops -22%.
The correct answer is 6.
a. Incorrect - SIG 1 is not affected by failure of N-142, however the amount of
change corresponds to the correct value.
b. Incorrect - SIG 2 is affected by failure of N-142, however this is an incorrect
value for the change in level. Value is based upon 200% power.
c. Correct - SIG 3 is affected by failure of N-142 and level is reduced to the zero
power setpoint of 38%.
d. Incorrect S/G 4 is not affected by failure of N-?42. Value is based upon
100% power.
REFERENCES:
3-OT-SYSOQ3A; SOL2 13 3.QZ "Condensate and Feedwater System"
10 CFR 55 41.7 I45.5
Ability to monitor automatic operation of the MFW, including: Programmed level
of the SIG.
RO-44
SRO-44
Reference:
SOI-2&3.1
IVA value:
2.9!3.1
Level
2
TiedGrp:
212
K/A Number: 059 A3.02
Last Used:
Source:
NEW
SRO Only:
Page: 1
5/27/2004
06lK2.02 001
Given the following conditions:
-
-
The unit has just tripped.
6.9 KV Shutdown Board ?A-A trips on bus differential relay operation.
.-.--/
-
AFW Pumps are maintaining SG levels.
Which ONE of the following describes how AFW will be supplied to the steam
generators?
A. SG 1 & 3 supplied by TD AFW pump, SG 2 & 4 supplied by A-A AFW
5. SG 3 & 4 supplied by TD AFW pump, SG 1 & 2 supplied by 5-B AFW
pump.
C. SG 1 through 4 supplied by TD AFW pump, SG I & 2 supplied by A-A AFW
pump.
pump.
D!' SG 1 through 4 supplied by TD AFW pump, SG 3 & 4 supplied by B-B AFW
Pump.
The correct answer is D.
A. Incorrect - TB AFW pump supplies all 4 S/Gs, SlGs 2&4 are supplied by
different MD AFW pumps. A-A MD AFW pump has no power.
,.,_
.'
B. Incorrect - TD AFW pump supplies all 4 S/Gs: S/Gs 2&4 are supplied by
different MB AFW pumps. A-A MD AFW pump has no power.
C. Incorrect - SlGs 182 are supplied by the A-A Mi3 AFW pump that is
without power due to lockout of 6.9 KV Shutdown board 1A-A.
B. Correct - TD AFW pump supplies all SlGs and B-B supplies SlGs 3&4
REFERENCES:
3-OT-SYS003
10CFK55.41.7
Knowledge of the bus power supplies to the following:
AFW electric driven pumps.
80-45 SRO-45
Reference:
3-OT-SYS003R
WA value:
3.7
Level:
2
'IierErp:
2!1
IC'A Number: 061K6.02
Last Used:
Source:
BANK
SRO Only:
Page: 1
5/27/2004
062 K2.01 001
Which ONE of the following describes how the loads on the 120 VAC instrument
panel 141 NORMALLY receive power?
A. 125 VBC from vital battery board II; rectified to 220 VAC
5. 125 VBC from vital battery board II; inverted to 120 VAC.
C. 480 VAG from Shutdown Board; inverted to 125 VDC and rectified to 120
..,. --_
.
VAC.
D!' 480 VAC from Shutdown Board; rectified to 125VDC and inverted to 120
VAC .
The correct answer is D
A. Incorrect - Battery board I1 is the back-up power supply but it is not rectified.
5. Incorrect - Battery board II is the back-up power supply .
C. Incorrect - 480 VAG from Shutdown board Is rectified first, then inverted.
D. Correct - 480 VAC from Shutdown board is rectified, then inverted and
supplied to VAC loads.
REFERENCES:
- _,
Lesson plan 3-OT-SYS235 p.13
10CFR55 41.7
Knowledge of bus power supplies to the following: Major system loads.
RO-46
SRO-46
Reference:
3-OT-SYS235A
K/A value:
3.3
Level:
I
TieriGrp:
211
K/A Number: 062 K2.01
Last Used:
Source:
NEW
SRO Only:
Page: 1
5/27/2004
062 62.1.2 00 I
Given the following plant conditions:
-
Reactor trip occurs.
-
-
The crew has implemented E-0, "Reactor Trip or Safety Injection".
While performing the Immediate Operator Actions of E-0 the CRO
observes that BOTH 6.9 KV Shutdown Boards are de-energized.
Which ONE of the following describes the responsibility of the CRO with respect
to emergency starting of the Diesel Generators?
A? Emergency start the Diesel Generators without SRO direction prior to
B. Emergency start the Diesel Generators with SRQ direction prior to entering
entering emergency procedures.
emergency procedures.
C. Emergency start the Diesel Generators when directed by the SRQ while
reading E-0, "Reactor Trip or Safety Injection".
5. Emergency start the Diesel Generators when directed by the SRO while
reading ECA-0.0, "Loss of Shutdown Power".
The correct answer is A
a. Correct - RNO for immediate action step 3 directs operator to start the diesel
generators and should be performed without direction.
b. Incorrect - CRO does not have be directed by the SRO to start the Diesel
Generators since they are started as the RNO for an immediate action.
c. Incorrect - Diesel Generators should be started in accordance with E-0 step 3
RNO and not wait only until directed by the SRQ.
d. Incorrect - the examinee may confuse the order of substeps contained in E-0
step 3. Transition to ECA-0.0 should only be made after actions taken to
restore power to the Shutdown Boards have been performed.
..
REFERENCES:
E-0, "Reactor Trip or Safety Injection"; 3-08-EOPOOQO
1 OCFR55 41.10 I45.13
AC Electrical Distribution - Knowledge of operator responsibilities during all
modes of plant operation.
8 0 - 4 7
SRO-47
Page: 1 of 2
5/27/2004
Reference:
E-0
lCiA value:
3.W4.0
Ixvel:
1
TierlGrp:
2!2
\\~-/
Page: 2 of2
KIA Number: 062 G2.1.2
I ~ s t
Used:
Source:
NEW
§KO Onfy:
5/27/2004
063 A4.03 001
Given the following plant conditions:
-
The reactor trips due to a loss of all AC power (Station Blackout)
- The crew is currently performing ECA-Q.O,"Loss of Shutdown Power".
-
Step 18 requires an evaluation of the DC buses to shed non-essential
loads.
Which ONE of the following identifies the procedural guidance the crew will use
to reduce Vital Battery discharge rate?
A. Sol-236, "125V DC Vital Battery Board" series.
BY AOI-48, "Station Blackout".
C. 801-43, "Loss of Shutdown Board"'series
D. ECA-0.0, "boss of Shutdown Power".
The correct answer is 8.
A. Incorrect - Sol-236 series is the appropriate SO1 for the operation of the
Vital battery board but is not used in the situation.
B. Correct - ECA-0.0 directs the use of AOI-40 to complete load shed of
non-essential BC loads.
C. Incorrect - AQI-43 series procedures will address the use of a spare
Battery Charger for the affected bus but is not used to load shed.
D. Incorrect - ECA-0.0 directs the use of AOI-40.
REFERENCES:
Lesson Plan 3-OT-AQi4000
AOI-40
EC.4-0.0
1OCFR55.41.7/45.5 to 45.8
Ability to manually operate and/or monitor in the controi room: Battery discharge
rate.
RO-48
SRO-48
Reference:
AOI-S
W h value:
3.0
Level:
1
TieriGrp:
211
K/A Number: 063 A4.03
Last IJsed:
Source:
NEW
SRO Only:
Pxge: I
5/28/2004
063 A4.01 001
Given the following plant conditions:
- Reactor was operating at 50% power.
-
A ioss of 125V DC Vital Battery Board I occurred.
- 881-21.01, "Loss of 125V DC Vital Battery Bd I" has been
implemented.
-
Operators have been dispatched to perform Appendix B, "Transfer
of 125V BC Busses".
-
Contrary to step 1, the BO-RESET switch was NOT depressed and
held when the DC control bus was RE-ENERGIZED.
-_
Which ONE of the following identifies the the effect this will have?
A. A trip of running cumponents on the 6.9KV Shutdown Board 1A-A would
occur.
B. Load shedding and sequencing would not occur if a loss of offsite power
were to occur after the control bus was re-energized.
CY Unwanted starts of components on the 6.9KV Shutdown Board 1A-A would
occur.
D. An unwanted start of the 1A-A Emergency Diesel Generator would occur.
The correct answer is C.
A. Incorrect - BO relays trip components. Student may beheve holding the relay
Ld
will prevent trips.
preventing UVX and U W relays from actuating.
prevents unwanted start of Train A equipment.
B. Incorrect - May believe the relay for BO have not been toggled to normal thus
C. Correct - Note in appendix 8 states that holding the BO-RESET switch
B. Incorrect - EBG has already started.
Reference:
A01 21.01 and 02 Section 2.2.6
3-OT-SYS021
1 OCFR55.41.7145.5 to45.8
Ability to manually operate and/or monitor in the control room:
Major breakers and control power fuses.
R8-49
SRO-49
Page: 1 of2
5/27/2004
Reference:
3-0T-AOI2 100
WAvalue:
2.8
Level:
2
TierIGrp:
2/1
K/A Number: 063 A4.01
Last Used:
Source:
BANK
SRO Only:
Page: 2 of 2
5/27/2004
064A1.04 001
The Diesel Generator crankcase ventilation system is designed to reduce the
combustibility of the oil vapors in the crankcase.
Which ONE of the following lists the normal condition of the crankcase and how
it is protected against potential combustion of oil vapors?
A. Maintained at a slightly positive pressure; High crankcase pressure trip.
Bf Maintained at a slightly negative pressure; High crankcase pressure trip.
6. Maintained at a slightly positive pressure; High crankcase temperature trip
B. Maintained at a slightly negative pressure; High crankcase temperature trip.
The correct answer is B.
A. Incorrect - crankcase is normally maintained at a slightly negative pressure
.Le,.
and protected against vapor combustion by the high crankcase pressure trip.
Examinee may believe a positive pressure is maintain to exclude the vapors.
and protected against vapor combustion by the high crankcase pressure trip.
and protected against vapor combustion by the high crankcase pressure trip.
Examinee may believe high temperatures associated with vapor combustion
would actuate a high temperature device.
5. Correct - crankcase is normally maintained at a slightly negative pressure
C. Incorrect - crankcase is normally maintained at a slightly negative pressure
.
.
D. Incorrect - crankcase is normally maintained at a slightly negative pressure
and protected against vapor combustion by the high crankcase pressure trip.
Examinee may believe high temperatures associated with vapor combustion
would actuate a high temperature device.
REFERENCES:
Lesson Plan 3-OT-SYSQ82A; System 82 System Description
lQCFR55.41.5 145.5
Ability to predict andlor monitor changes in paramenters (to prevent exceeding
design limits) associated with operating the DIG system controls including:
Crankcase temperature and pressure.
80-50 SRO-50
Keferenc.e:
SYSTEM DISC
&'A value:
2.8/2.9
Level:
I
TierIGrp:
2: I
K/A Number: 064A1.04
Last Used:
Source:
NEW
SRO Only:
Page: 1
o n ~ 2 . 0 1
ooi
Given the following conditions:
- Radwaste AUO is in the process of making a liquid radwaste release
- 1-RM-90-122, WBS Liquid Effluent, radiation monitor has just been
- The release flowrate has been adjusted and 1-ISV-77-660, Cooling
- Annunciators 181-A WDS RELEASE LINE LlQ RAD HI and 181-C
---"
from the monitor tank.
placed in service.
Tower Blowdown Release Header IsQI, OPENED.
WBS RELEASE LINE lNSTR MALF have just alarmed.
If the alarms are the result of a power supply failure which ONE of the
following actions would the operator perform?
A. VERIFY 0-RE-90-9 (ARM) is NOT in alarm, if clear: release is permitted to
continue.
BI/ ENSURE automatic isolation of 0-RCV-77-43, Waste Condensate
Discharge Radiation Isolation Valve, to terminate the release.
C. CHECK 1-RM-90-122 alarms on the local radwaste panel, 0-L-2. if NO
additional alarms have been received the releas
rmitted to continue
D. MONITOR 1-RM-9Q-I22 alarms in the Main gontrol Room and manually
isoiate cooling tower blowdown diffuser valves, 1-FCV-27-100 and 101.
._
The correct answer is B.
A. Incorrect - ARB 181-8 step 2 has the operator check 0-RE-90-9 but the
release should have auto terminated.
5. Correct- ARB 181-A&C step 1 ensures that the release has auto terminated
C. Incorrect - Used as a distractor to entice student to back-up MCR alarms. If
by the closing for Q-RCV-77-43.
not due to radiation student may continue release.
D. Incorrect - Student may also send the release to a safer location if no
radiation alarms in MCR.
Page: 1 of 2
1/28/2004
Reference:
3-OT-SYS090A p.64
ARI 181-8
ARI 181-C
b.*
1 OCFR55.41.5/43.5/45.3/4!5.13
Ability to (a) predict the impacts of the following malfunctions or operations on
the PRM system; and (b) based on those predictions, use procedures to correct,
control, or mitigate the consequences of those malfunctions or operation: Erratic
or failed power supply.
RO-51
SRO-51
Reference:
3-OT-SYS090A
WA value:
2.5
Level:
2
'TiedGrp:
211
Page: 2 of 2
WA Xumber: 073 A2.01
Last lised:
Source:
N t W
SRO Only:
5/28/2004
076 AI 02 001
Given the following plant conditions:
-
Plant was operating at 100% power when an earthquake
occurred.
- The intake Pumping Station (IPS) suffered substantial damage.
-
All ERCW headers lost flow either due to damage to the pumps or
strainers.
- The operating crew implemented AOI-I 3, "Loss of Essential Raw Cooling
Water".
- The OAC is directed to start 1 B-B CCP and stop '?&A CCP.
j-.
Which ONE of the following describes the reason for starting the 1B-B CCP?
A? Low heat load on "5" train CCS allows for extended pump operation.
5. HPFP will be aligned to provide cooling to 1 B-3 CCP using Attachment "F
of AOI-13.
C. CCP operation is alternated between 1A-A and 48-8 pumps in order to
extend the run time.
D. 1A-A CCP must be shut down in order to align HPFP cooling using
Attachment "E" of 801-13.
The correct answer is A.
A. Correct - since the heat load on "5" train CCS is minimal, more cooling is
available to the 1 B-B CCP therefore it would be able to run for a more
extended time than the 1A-A CCP.
5. Incorrect - AOI-13 will align HPFP to the IA-A CCP for temporary cooling but
not to the 1 B-5 CCP.
C. Incorrect - some plants would alternate between the two CCPs to extend the
run time but WBN aligns temporary cooling to the la-A CCP.
D. Incorrect - 1 B-B CCP is not ORIY started to allow alignment of HPFP. It is
started since it's run time would be extended since "B" train CCS has very
small heat load besides the 1 B-5 CCP.
Page: 1 of 2
5/28/2004
REFERENCES:
Lesson Plan 3-OP-AO11300; AOI-13
1QCFR55.41.5 I45.5
--,
Abitity to predict andlor monitor changes in parameters (to prevent exceeding
design limits) associated with operating the SWS system controls including:
Reactor and Turbine building closed cooling water temperatures.
RQ-52 SRO-52
Reference:
AOI-13
WA value:
2.62.6
Level:
2
TierGrp:
I :2
Page: 2 of 2
WA Number: 076 AI .02
Last lised:
Source:
NEW
SRO Only:
5/28/2004
098 A3.01 001
If Station Control and Service Air System air pressure is dropping, the
Service Air System automatically isolates from the Control Air System when
pressure drops below which ONE of the following?
A. 83 psig.
--.
B? 88 psig.
C. 79.5 psig.
The correct answer is B
A. Incorrect - This is the setpoint for the low air pressure ahrrn.
B. Correct
~ PCV-33-4 shuts at 80 psig.
C. Incorrect - This is the automatic setpoint at which essential air will isolate
from the non-essential and aux air.
8.
Incorrect -this is the setpoint at which the containment isolation valve
close on a loss of IAS.
Reference:
.--
3-OT-SY S032A
lOCFR55.42.7145.5
Ability to monitor automatic operation of the (AS, including: Air pressure
80-53
SRO-53
Reference:
3-OT-SYS032
WA value:
3.1
Level:
1
TieriGrp:
211
U A Number: 078 A3.01
Last Used:
Source:
SRO Only:
.-
Psge: 1
5/27/2004
103 K1.05 001
Which ONE of the following describes how the operation and design of the
personnel access hatch ensures containment integrity is maintained for
accident response during containment entry at power.
A. Both doors open outward away from containment, and each door has a
single gasket seal.
--
B!, Both doors open in toward the containment, and neither door can be
unlatched until the opposite doer is closed.
6. Both doors open outward away from containment, and neither door can
be unlatched until the opposite door is closed.
D. Both doors open in toward the containment, and each door has a single
gasket seal.
The correct answer is B
A. Incorrect
~ Both doors open inward toward containment so that a rise in
containment pressure will force the door closed. A double gasket is
installed.
3. Correct - Both open in toward containment. An interlock prevents
opening either door until the opposite door is shut and latched.
C. Incorrect - Both doors open inward toward containment so that a rise in
t,
containment pressure will force the doer closed.
D. incorrect - A double gasket is installed.
REFERENCES:
3-OT-SYS088A p. 21-22
10CFR55.42.2 to 41 .$145.7 to 45.8
Knowledge of the physical connections and/or cause-effect relationship between the
containment system and the foDlowing systems: Personnel access hatch.
RO-54
Reference:
3-OT-088A
KIAvalue:
2.8
Level:
I
TiedGrp:
2/1
K/A Number: 103 K1.05
Last Used:
Source:
NEW
SRO Only:
Page: 1
5/27/2004
I03 A406 001
Given the following plant conditions:
-
The unit is shutdown for refueling.
-
Fuel handling personnel are in the process of moving irradiated fuel
assemblies from the core to the spent fuel pit.
-
A Main Control Room operator observes that annunciator 158-8, UPR
CNTMT AIRLOCK INNERIOUTER, is LIT.
-
NAUO reports that both doors for the upper containment personnel
airiock are open to allow laborers to move materials through the airlock
with one individual assigned to close airlock doors as needed.
-
All other plant systems normally required operable during this MODE are
Which ON of the following describes the required actions? (use the attached
Tech Spec)
A Suspend movement of irradiated fuel assemblies; Close one air lock door.
B. Suspend movement of irradiated fuel assemblies; Allow both doors to remain
open.
C. Ensure ABGTS is operabke; Close one air lock door
D!' Ensure ABGTS is operable; Allow both doors to remain open.
The correct answer is D.
A. Incorrect
~ both personnel airlock doors are allowed to be open during
k-,
movement of irradiated fuel assemblies and suspension of fuel handling is
not required as long as A5GTS is operable.
movement of irradiated fuel assemblies and suspension of fuel handling is
not required as long as ABGTS is operable.
of both airlock doors, however it is not necessary to close one door if ABGPS
is operable.
movement of irradiated fuel assemblies as long as ABGTS is maintained
B. Incorrect - both personnel airlock doors are allowed to be open during
e. Incorrect - A5GTS must be operable in order to allow simultaneous opening
D. Correct - both personnel airlock doors are allowed to be open during
5/27/2004
REFERENCES.
Examinee must be provided a copy of Tech Spec 3.4.9
Lesson Plan 3-OT-SYS088A; Tech Spec 3.9.4
1OCFR55.41.7 145.5 to 45.8
Ability to manually operate and/or monitor in the control room: Operation of the
personnel airlock door.
-
80-55 SRO-55
Reference:
3-OT-SYS08SA
KIA value:
2.712.9
Level:
2
TierIGrp:
211
WA Number: 103 A4.06
Last Used:
Source:
NEW
SRQ Only:
Page: 2 oF2
5/27/2004
001 K2.01OOL
Which ONE of the following is the NORMAL supply to the Controi Rod Drive
__
A. 4 8 0 ~
Shutdown Bd ?AI-A
BY 48Qv Unit Bd IA.
C. 480v Aux Bldg Common Bd
8. 480v Turbine Bldg Common Bd.
The correct answer is B.
A. Incorrect - Not powered from Shutdown hoard. Students may confuse
B. Correct - M16 sets are powered from respective 480v Unit Boards.
C. Incorrect - Not powered from Aux Common Board. Students may confuse
power supply.
i
power supply.
D. incorrect
~ Not powered from Turbine Common Board. Students may
confuse power supply.
REFERENCES:
3-OP-SYS085B p. 7, 10
IOCFR55.42.7
Knowledge of bus power supplies to the following: One-line diagram of power
supply to M/G sets.
RB-56
SRO-56
Reference:
3-OY-SYSO85B
WAvalue:
3.5
Level:
I
TierlGrp:
212
WANumber: 001 K2.01
Last Used
Source:
BANK
SIP0 Only:
. _
Page: 1
5/27/2004
002 AI.09 001
Which ONE of the following conditions or events will REDUCE the margin
between Delta T and the OPAT trip setpoint?
__
A Pressurizer spray valve sticks open for 15 seconds (assume no reactor trip).
B. A reactor boration is initiated at 50% power.
C. Feedwater flow to a steam generator is raised.
D? A power ascension from 75% to 108% power
The correct answer is D.
A. Incorrect - RCS pressure is not input to the setpoint calculation for OBDT
B. Incorrect - Boration will lower Pave. Lower Tave does not affect the QPDP
setpaint but lower power will reduce actual BT.
6. Incorrect - Additional feed flow will lower Pave and initially supress power
B. Correct - Power ascension raises actual DT closer to setpoint. Setpoint
not affected until Tave exceeds 588.2CF.
REFERENCES:
<--.
3-OT-TAA0001 p. 3-6
lOCFR55.41.5 i45.7
Ability to predict and/or monitor changes in parameters (to prevent exceeding design
limits) associated with operating the RCS controls including: RCS Tave.
RO-57 SRO-57
Reference:
3-ClT-099A
K:A value:
3.7
Level:
2
TierIGrp:
2 2
K/A Number: 002 A1.09
Last Used:
Source:
EAKK
SRO Only:
Page: 1
014A4.01 001
Which ONE of the following describes the setting of the Bank Overlap Unit
thumbwheel switches and the Rod Bank Select switch position in which the
Bank Overlap Unit is enabled?
A? Switches set to maintain 100 steps overlap; Rod Bank Select switch in
MANUAL or AUTOMATIC.
E. Switches set to maintain 100 steps overlap; Rod Bank Select switch in
MANUAL or BANK SELECT.
C. Switches set to maintain 128 steps overlap; Rod Bank Select switch in
MANUAL or AUTOMATIC.
D. Switches set to maintain 128 steps overlap; Rod Bank Select switch in
MANUAL or BANK SELECT.
The correct answer is A,
A. Correct - 100 step overlap is the correct setting for the Bank Overlap Unit
thumbwheel switches and the unit is enabled when the control rod mode
selector switch is in MANUAL or AUTOMATIC.
B. Incorrect - 150 step overlap is the correct setting for the Bank Overlap
Unit thumbwheel switches but the Bank Overlap Unit is NOT enabled in
the Bank Select position. The examinee may confuse the function of the
different switch positions on the rod control mode select switch.
C. Incorrect - 128 step overlap is NOT the correct setting for the Bank
Overlap Unit thumbwheel switches but the unit is enabled when the
control rod mode selector switch is in MANUAL or AUTOMATE
-
D. Incorrect - 128 step overlap is the correct setting for the Bank Overlap
Unit thumbwheel switches and the Bank Overlap Unit is NOT enabled in
the Bank Select position. The examinee may confuse the function of the
different switch positions on the rod control mode seiect switch.
REFERENCES:
WBN Bank - SYS085A.08.002
3-OT-SYS085A
1OCFR55.41.7 145.5 to 45.8
Ability to manualiy operate and/or monitor in the control room: Rod selection control.
80-58
SRO-58
Refertiice:
3-0Y-SYS085A
WA value:
3.3i3.1
Level:
I
'IieriGrp:
2i2
.
.
Page: 1
WA Number: 014 A4.01
Last Used:
Source:
RANK
SRO Only:
5/27/2004
016 K5 01 001
While the plant is operating at 100% power a short circuit occurs internally on
the Master Pressurizer Pressure Controller, t-PIC-68-34QA.
Which ONE of the following describes the effect of this fault on the Reactor
Protection system?
A. The controller short circuit will feed back into the protection circuit causing
the associated channel to trip
-
BY The controller short circuit will NOT feed back into the protection circuit due
to the use of isolation amplifiers.
C. The controlier short circuit will feed back into the protection circuit preventing
the associated channel from tripping
D. The controller short circuit will NOT feed back into h e protection circuit since
separate sensors (pressure transmitters) are used for control and protection.
.
The correct answer is B.
A. Incorrect - short circuit will not feed back into the protection circuit since it
the protection and control circuits are separated by isolation amplifiers.
B. Correct - short circuit will not feed back into the protection circuit since it
the protection and controi circuits are separated by isolation amplifier.
C. Incorrect - short circuit will not feed back into the protection circuit since it
the protection and control circuits are separated by isolation amplifier.
the examinee may misunderstand how channel failures impact the abiiity
to trip associated bistables.
c-
D. Incorrect - short circuit will not feed back into the protection circuit since it
the protection and control circuits are separated by isolation amp!idier
not because of the use of redundant sensors. The examinee may
confuse the use of redundant instrumentation with the separation of
controls and protection.
Page: I of2
5/27/2004
REFERENCES:
Lesson Plan - 3-QT-SYS068C
lNPO Bank - Kewaunee 1 9/06/2002
10CFR55.41.5 145.7
Knowledge of the operational implications of the following concepts as they
apply to the IS:
Separation of control and protection circuits.
88-59
SRO-59
-
Reference:
3-OT-SYS068C
WA value:
27/28
Level:
I
TierlGrp:
2/2
WANumher: 016 K5.01
Last Used:
9/06/2002
Source:
BANK
SRO Only:
i
j..
Page: 2 of 2
028 K3.01 001
Given the following plant conditions:
~
A large break L06A occurs from 100% power.
- " A
Hydrogen Reeombiner has been placed in service.
-
Subsequently the "A" Hydrogen Recombiner trips on overcurrent.
Which ONE of the following indicates how the concentration of hydrogen will be
controlled inside containment?
A. A continuous vent path is provided that allows hydrogen to vent t~ the
annulus and then be removed by EGTS.
B. Containment Purge Suppiy and Exhaust fans are placed in service to dilute
the hydrogen concentration in containment.
,-
..
- " 6
Hydrogen recombiner is tagged out.
.:
C.J Air Return Fans create a mixing effect and the hydrogen igniters will burn
hydrogen to maintain it below an explosive concentration,
D. Emergency Gas Treatment System will remove hydrogen which collects in
the Containment dome and discharge to the shield building vent.
The correct answer is C.
A. Incorrect
~ containment purge cleanup units do net recirculate to
containment remove hydrogen -gas.
8. Incorrect - A continuous vent is available from the containment to the
annulus during normal operation but this path is isolated on a containment
vent isolation signal. Examinee may not understand this isolation since
this continuous vent is a recent design change to the plant.
C. Correcf - Air return fans do create a mixing effect to prevent pockets of
hydrogen from forming, and the igniters would cause hydrogen to burn and
reduce hydrogen concentration.
D. Incorrect - EGTS takes suction from the top of the annulus dome instead of
the containment dome. Examinee may mistake the two.
.- /
Page: I of 2
5/27/2004
REFERENCES:
47W61I-30-1, Lesson plan 3-OT-SYS083A p. 21, 24.
-~
WBN exam bank
10CFR55.41.7 145.6
Knowledge of the effect that a loss or malfunction of th HRPS will have on the
following: Hydrogen concentration in containment.
RO - 60
SRO - 60
Reference:
SYS083A
L'A value:
3.3
Level:
2
Tier1Grp:
212
W A Number: 028 K6.01
Last Used:
Source:
BANK
SRO Only:
,..
Page: 2 of 2
5/17/2004
029 ~ 3 . 0 1
001
Given the following plant conditions:
-
Plant is shutdown for refuelina
'
1
~
'
train Containment purge gystem is in service.
r--.
Which ONE of the following will
he Containment Purge fans?
A. High flux detected by Source Range detector. NI-132.
6. High radiation detected by Spent Fuel Pit area radiation monitor,
C.* Containment Vent Isolation from high radiation detected by containment
purge exhaust radiation monitor, 1-RM-90-130.
8. Phase A Containment Isolation from high radiation detected by upper
containment radiation monitor radiation monitor, 1-RM-90-112.
The correct answer is C.
A. Incorrect - the SRMs actuate Containment evacuation alarm and high flux
B. Incorrect- 1-RM-90-102, Spent Fuel Pit area monitor actuates much ofthe
same equipment as an AB! but does not trip the containment purge fans.
An AB1 signail would trip the purge fans.
Containment Purge fans via 1 -RM-90-130, containment purge exhaust
radiation monitor.
at shutdown alarm but do not trip the purge fans.
C. Correct - Containment Vent Isolation will provide a trip signal to the
D. Incorrect - 1-RM-90-112 does net initiate a containment vent isolation signal,
however the examinee may select this since the RM-90-112 monitor samples
upper containment atmosphere.
REFERENCES:
3-OT-SYS03QC
10CFR55. 41.7 145.5
Ability to monitor automatic operation of the Containment Purge System
including: CPS isolation.
RO-SI
SRQ-61
Reference:
3-~i--s~s030c
K!A value:
3.81.1.0
I.evcl:
I
Tier/Grp:
2/2
K/A Number: 029 A3.01
Last Used:
Source:
NF,W
SRO Only:
Page: 1
5/28/2004
035 ti3 05 00 I
Which ONE of the following is the basis for 'S/G Water bevel Low-bow
Reactor Trip" at 17% narrow range on 2/3 level switches on 1 aut of 4 SlGs
if power is greater than 50%?
To ensure there is adequate reserve inventory to ....
A. continue RCP operation until generator breaker is opened
3. cool turbine blading in the event turbine fails to trip.
C!' allow AFW pump start before SIG tubes are uncovered
D. continue MFW pump operation until AFW pumps start.
The correct answer is C.
b-
A. Incorrect - Generator breaker opening is delayed for 30 seconds to allow
RCP coastdown, but steam flow is isolated to the turbine at this time.
B. Incorrect - Students may wish to provide steam flow to keep turbine
C. Correct - Basis states that AFW needs time to start to prevent SIG tube
D. Incorrect - MFPs are tripped on main feedwater isolation which occurs
blades cooled if a trip does not OCCUF.
uncovery.
.-
after reactor trip at 564OF.
REFERENCES:
3-OT-SYS-003D p.13
15CFR55.41.7
Knowledge of SlGs design feature(s) and/or interlock(s) which provide for the following:
Amount of reserve water in SIG.
80-62
SKO-62
Reference:
3-OT-SYS-0031)
WA value:
2.9
Level:
1
1iedGrp:
212
K;'A Number: 035 K4.05
Last used:
Source:
NEW
SRO Only:
i,
Page: 1
068 K1.07 001
Given the following plant conditions:
Plant is at 100% power.
.
d
~
RCBT level is RISING.
-
Which ONE of the following describes the cause of this level RISE?
A* Reactor head inner "0" ring seal failure.
B. Reactor Building Pocket Sump discharge.
C. RHR suction relief valve leaking through
D. # I Seal bypass for the RCPs leaking through.
The correct answer is A.
A. Correcf - leakage from the reactor head "0" ring is routed to the RCBT and
would result in RISING level.
B. Incorrect - Reactor Building Pocket Sump pump discharge is not routed to
the RCDT. Examinee may think waste water collected in the containment is
iikely tritiated and should be routed from the RCDT to the Tritiated Drain
Collector Tank.
i.-
C. incorrect
~ RHR suction relief valve is not routed to the RCBT. Examinee
may think it is routed to the RCBT to be processed since it is primary coolant.
D. Incorrect - RCP #I
seal bypass valve does not route water to the RCDT.
Examinee may think it is routed to the RCDT to be processed since it is
primary coolant.
REFERENCES:
lNP0 bank - Prairie Island 1 (6/16/2997)
Lesson Plan 3-QT-SYS077A: Print 47W813
15CFR55.41.2 to 41.9 145.7 to 45.8
Knowledge of the physical connections and/or cause effect relationships
between the Liquid Radwaste system and the following systems:
Sources of liquid wastes for LRS.
RO-63
SRQ-63
Reference:
3-OT-099A
WA value:
2.712.9
Level:
1
.
~
TieriGrp:
212
IC'A Number: 068 KI .07
Last Used:
Source:
BANK
SROOnly:
Page: 1
5/27/2004
049A2.01 001
Given the following plant conditions:
-
Unit 1 is at 100% power.
- A leak has developed on the Control Air System.
-
Control Air pressure has reduced and stabilized at 76 psig.
- All control systems associated with Control Air have actuated as
expected.
-
The operating crew implemented 8 0 1 - I O , 'Loss of Control Air'.
Which ONE of the following describes the actions the operating crew should
implement in accordance with AOl-30.
A. PLACE MSlV HSs in Close.
--.
BY START available ABGTS and EGTS.
C. CLOSE charging isol, 1-FCV-62-90 and I-FCV-62-91
D. MINIMIZE RCP seal flow at greater than 6 gpmlpump.
The correct answer is B.
A. Incorrect - Hand switches for MSlVs are only placed in close if the MSIVs
shut due to loss of air.
B. Correct - systems are started as a precautionary step for loss of air to aux
C. Incorrect
~ Charging is isolated only if letdown isolated due to loss of air
D. incorrect
~ Seal flow is minimized only if PZR level exceeds 70%.
REFERENCES:
bldg dampers.
Lesson Plan 3-OT-AO11000 p.10
AOI-10
106FR55.41.5l43.5l45.3l45.13
Ability to (a) predict the impacts of the following malfunctions or operations on
the SAS; and (b) based on those predictions, use procedures to correct, control,
control, or mitigate the consequences of those malfunctions or operations:
Cross-connection with [AS.
RO-64
SRO-64
Reference:
AOI-I0
WA value:
2.9
TiedGrp:
212
- '
Level:
2
Page: 1
WA Number: 079 A2.01
Last Used:
Source:
NEW
SRO Only:
v2712004
086 K6.04 001
Detection Zone 130 in the Unit 2 Ventilation and Purge Air Room, Aux Bldg.
el.734, is out of service.
Which ONE of the following is the required action? (use the reference provided)
A.
B~+'
C.
-,
No actions required since this is a Unit 2 area
Enter OR-14.3.l.a 3 since the detection is on the Aux Bldg, el 737
Enter OR-141.1 since the detection has failed
D.
Enter OR-24.3.1.a.l since detection is affected and this inhibits the assaciated
suppression.
The correct answer is B.
A. Incorrect - Students mat decide that this equipment is Unit 2 related and not
affected by fire protection plan.
El. Correct ~ Since this detector is elevation 737 of Aux Bldg OR-14.3.1.a.3 must
be applied.
C. Incorrect - Detectors are all Function B. 14.1 applies to Function A
detectors.
D. Incorrect - This action is less restrictive and is not specific to elevation 737.
\\Id
Student may select this distractor id they fail to completely scan the
document.
REFERENCES:
Lesson Plan 3-OT-TSOR14 p.6&7
lOCFR55.41.7145.7
Knowledge of the effect that a loss or malfunction of the following will have on the Fire
Protection System: Fire, smoke , and heat detectors.
RO-65
SRQ-65
Reference:
3-OT-TSOR14
WAvalue:
2.6
Level:
2
TierlGrp:
212
WA Number: 086 K6.04
Last Used:
Source:
BANK
SRO Only:
_-
Page: 1
5/27/2004
G 2 I2001
Under which ONE of the following conditions is the Operator at the Controls
(QAC) allowed to leave the normal QAC surveillance area, without obtaining a
relief, during plant operations?
A. To enter the Shift Manager clerk's office to obtain a controlled key.
B To obtain a print from from the tagging office in order to verify ongoing work.
C. To respond to an expected annunciator alarm on a back panel in MODE 6.
DJ To verify receipt of an annunciator alarm on a back panel during an
The correct answer is D.
A. Incorrect - OAC is not allowed to leave the control room without proper
c
emergency.
relief. Examinee may believe it is acceptable as long as it is just outside
the control room and still within the control building
E). Incorrect
~ QAC is not allowed to leave the control room without proper
relief. Examinee may believe this acceptable since it is still part of the
operations office area.
C. Incorrect - QAC is not allowed to leave the QAC surveillance area under
normal circumstances, even if the alarm is expected. Examinee may
confuse the acceptable exception during defueled conditions with
refueling (MODE 6).
r__
13. Comcf - QAC is allowed to leave under emergency conditions to verify
receipt of an alarm.
REFERENCES:
INPO Bank - Seabrook 1 5/3012003
3-QT-SPP1008
10CFR55 41 .I
0 / 45.1 3
Knowledge of operator responsibilities during all modes of plant operation.
8 0 - 6 6
SRO-66
Reference:
SPP-10.0
K!A
value:
3.0;4.0
Level:
1
TierlGrp:
3/3
WA Number: G 2.1.2
Last Used:
5/30/2003
Saurce:
BANK
SRO Only:
Page: I
5/27/2004
G 2.1 25 001
Given the following plant conditions:
-
-
-
-
The Unit is in Mode 5, following a Refueling outage.
The RCS is in Mid Loop operation, at 'IIO" F.
1A-A RHR pump is in service at 2000 gpm.
Preparations are in progress to begin RCS Vacuum Refill
-
Which ONE of the following describes the expected time to raise RCS vacuum
from 12 in Hg. to the maximum allowable value? (use references provided)
A. 85 minutes
BI, 90 minutes.
C. 125 minutes.
B. 130 minutes
The correct answer is B.
A. Incorrect -this answer is used to provide consistent distractor and allows for
minor interpretation differences.
6. Correct - answer is correct considering beginning vacuum at 22" Hg and
raising vacuum to the maximum allowable value determined by using the
RHR flowrate of 2,500 gpm.
C. Incorrect -this answer is possible if the examinee does not account for
beginning at 12" Hg.
D. Incorrect - this answer is used to provide consistent distractor and allows for
minor interpretation differences.
... -.
REF EKE N C E :
WBN Bank - GO1000.0'l ,008
GO-2 0, "Reactor Coolant System Drain and Fill Operations".
15 CFR 55 41 . I O 143.5 I45.12
Ability to obtain and interpret station reference materials such as graphs,
monographs, and table, which contain performance data.
RO-67
SRO-67
Reference:
GO-10
L'A value:
2.8ij.I
Level:
2
TieriGrp:
3!3
KIA Number: G 2.1.25
Last Lsed:
Source:
BANK
SRO Only:
?age: 1
5/27/2004
G 2.1 27 001
The reactor protection system is designed such that a loss of f!ow in one reactor
loop will trip the reactor above the P-8 permissive.
Which ONE of the following describes the bask for this trip?
A. Provides anticipatory protective action for the subsequent low-low S16 water
level trip.
--'
B. Prevents pressure fluctuations in the main steam system from damaging the
CY Provides protection against dropping DNBR below it's !hit due to reduced
heat removal rate.
B. Prevents uneven fuel burning which can iead to localized power peaks
The correct answer is C.
A. Incorrect - SIG level is expected to drop due to shrink caused by the loss of
heat input, however is not the reason for tripping the reactor upon loss of
acs flow.
6. Incorrect - pressure fluctuation would occur in the main steam system due
the change in heat input for the affected loops SIG, however is not the
reason for tripping the reactor upon loss of RCS flow.
C. Correct - loss of RCS flow will reduce DNBR. The rapid reactor trip
generated by low flow will prevent DNBR from dropping below it's h i t .
D. Incorrect - potentially uneven fuel burning can occur due to temperature
distribution changes across the core, however is not the reason for tripping
the reactor upon loss of RCS flow.
exceeding kw/ft limits.
\\4p.
REFERENCES:
INPO Bank - Seabrook 1 5/30/2003
3-OT-SYS099A
fOCFR55 41.7
Knowledge of system purpose andlor function.
RO- 68
SRO-68
Reference:
3-OT-SYS099A
KIA value:
2.8i2.9
TieriGrp:
3t3
.- Level:
1
KIA Number: G 2.1.21
LDst Used:
5!30/2003
Source:
BANK
SRO Only:
i
Page: 1
5/27/2004
G 2.2.22 001
Given the following plant conditions:
- T
.RQperformed the Surveillance Instruction, I
-Sl-68-32, "RCS Inventory
@nce"
~n?i-kund the total RCS leakage
, ,, . x
- Chemistry reports SIG tube leakage to be as follows:
.. ..
---%
1, rate to be 11.2 gpm.
.I0 gprn - SIG #I
...~~
.31 gpm - SIG #2
no leakage exists in remaining S/Gs.
- Further investigation finds the following :
RCDT level rising at 4.7 gpm.
PRT level rising at 5.1 gpm.
Of the listed leakage types:
1 -Identified
2 -Unidentified
3 -S/G tube (individual SIG)
4 -Total SIG tube
Which One of the following identifies the Tech Spec limits for operational leakage that
havebeenexceeded?
8 3 1.3
B. 2 , 4
D. 3.4
The correct answer is A.
A. Correct - Identified leakage
B. Incorrect - 4, total c 600 gpd. Student may select thinking limit is 500 gpd.
C. Incorrect - 2, Unidentified leakage 6 1 gprn and 4, total
D. Incorrect - 4, total e 600 gpd. Student may select thinking limit is 500 gpd
I O gpm and # 2 S/G
150 gpd.
600 gpd.
.-
Page: 1 of 2
5/27/2004
REFEKENCES:
Lesson plan 3-OT-T/S0304 p.8
TIS 3.4.23
1 OCFK55.43.2I45.2
.
Knowledge of limiting condition for operations and safely limits.
RO-69 SRO-59
Reference:
3-OT-TIS0304
KA value:
3.4
Level:
a
TieriGrp:
I 3
. ..
Psge: 2 of2
KIA Number: G 2.2.22
Last Used:
Source:
NEW
SKO Only:
5/27/2004
61 2.2.25 001
The Safety Injection System, along with other ECCS subsystems, ensures that the
ECCS Acceptance Criteria of 10CFR50.46 is met.
Ail of the following are part of this criteria EXCEPT:
A? The maximum fuel pellet centerline temperature shall not exceed 2000 OF.
8. Changes in core geometry shali be such that the core remains amenable
to cooling.
C. The total oxidation of the cladding shall nowhere exceed 0.27 times the total
cladding thickness before oxidation.
..-,.
D. The total amount of hydrogen generated from the chemical reaction of
the cladding with water or steam shall not exceed 0.01 times the
hypothetical amount generated if all of the metal in the cladding were to
react.
..:
The correct answer is A.
A. Correct ~ ECCS acceptance criteria states centerline temperature shall
not exceed 2200 OF.
B. Incorrect
~ This is an acceptance criteria.
C. Incorrect - This is an acceptance criteria.
D. incorrect -This is an acceptance criteria.
-
REFERENCES:
3-OT-SYS063A p. 14
Tech Spec 3.5.1 basis
lOCFR55.43.2
Knowledge of basis in technical specification for limiting conditions for operations and
safety limits.
RQ-70
SRO-70
Reference:
3-OT-SYS063
W.4 value:
2.5
Level:
1
TieriGrp:
313
WA Number: G 2.2.25
Last Used:
Source:
NEW
SRO Only:
'.
Page: 1
5/27/2004
G 2.3.9 001
During operation of the Containment Purge system pressure imbalances may
occur and cause inadvertent opening of Ice Condenser inlet doors.
Which ONE of the following sequences for purging lower containment will
prevent pressure imbalances from causing Ice Condenser doors to open?
A. Start upper containment purge first to stabilize pressures; start lower
containment purge, then stop upper Containment purge.
B. Start lower containment purge first to stabilize pressures; start upper
containment purge, then stop lower containment purge.
containment purge, then start lower containment purge.
--..,
C? Start upper containment purge first to established pressures; stop upper
0. Start lower containment purge first to established pressures; stop lower
The correct answer is C ,
A. Incorrect -the upper will be stepped prior to starting the lower purge system
containment purge, then start upper containment purge.
examinee may have misconception that both must remain running to
maintain balanced pressures between upper and lower containment.
B. Incorrect - the upper containment will be purged first. Examinee
C. Correct - upper containment is purged first to stabilize pressures. It will be
may have misconception that lower will be purged ftrst.
\\< "*..
stopped then lower continue will be purged.
D. Incorrect - the upper containment will be purged first. Examinee
REFERENCES:
may have misconception that lower will be purged first.
SOI-30.02, Precaution and Limitation "F".
lQCFR55.43.4l45.10
Knowledge of the process for performing a containment purge.
KO-71 SRO-71
Reference:
SOK-30.02
KIA value:
2.5i3.4
Level:
L
TiedGrT:
3
1
K/A Kurnber: G 2.1.9
Last Used:
Source:
NEW
SUO Only:
Page: 1
5/28/2004
G 2.3.10 001
Given the following plant conditions:
-
Plant is at 100% power.
- The Radwaste NAUO reports a Waste Gas Decay Tank is ruptured and
depressurizing into the Auxiliary Building.
- The operating crew implemented AOI-31, "Abnormal Release of
Radioactive material".
i
-
Several Auxiliary Building radiation monitors are in alarm.
Which ONE of the following lists the actions to be taken by the operating crew to
isolate and lEmit the release to the environment?
A. Initiate Containment Vent Isolation (CVI); Check Emergency Gas Treatment
fans running (EGTS).
Treatment fans running (ABGTS).
fans running (EGTS).
6. Initiate Containment Vent Isolation (CVI); Check Auxiliary Building Gas
C. Initiate Auxiliary Building Isolation (AM); Check Emergency Gas Treatment
D3 Initiate Auxiliary Building Isolation (ABI); Check Auxiliary Building Gas
The correct answer is D.
A. Incorrect - CVI would not isolate the release nor would EGTS limit the
release to the environment. since Waste Gas Decay Tanks are released
through the shield building vent examinee may think a CVI will isolate the
release. EGTS would cleanup containment releases.
release to the environment. since Waste Gas Decay Tanks are released
through the shield building vent examinee may think a CVI will isolate the
release. ABGTS would limit a release to the environment from the Aux.
Bldg.
Treatment fans running (ABGTS).
L
8. Incorrect - CVI would not isolate the release nor would EGTS limit the
C. Incorrect - AB1 would isolate the Aux. Bldg. to prevent release but EGTS
D. Correct ~ AB1 would isolate the Aux. Bldg. to prevent release and ABGTS
would not limit a release from the Aux. Bldg.
would limit the release by cleanup action of HEPA and charcoal.
-
.._
Page: 1 of 2
5/21/2004
REFERENCES:
3-OT-8013100; AOI-32
-
10CFR55 43.4 145.10
Ability to perform procedures to reduce excessive levels or radiations and guard
against personnel exposure.
80-72 SRO-72
Reference:
AOI-3 1
lCiA value:
2.9/3.3
Level:
1
Tier/Grp:
313
WA Number: G 2.3.10
Last Used
Source:
NEW
SRO Only:
-
.,
Page: 2 of 2
5/21/2004
~
2
7
I I O O I
The Unit Supervisor has directed a Unit shutdown based on RCS activity exceeding
Tech Spec limits.
In the event of a subsequent SGTR, which ONE of the following actions is designed to
limit the release of radioactivity?
-
A. MSiVs are closed.
BY RCS is cooled down below 500 OF.
C. Condensate polishers are in service at full flow
8. S/G atmospheric dump valve for the affected S/G is placed in OFF
The correct answer is 3.
A. Incorrect - Closing MSlVs would contribute to Rad release through SJG
PORVs if cooldown not performed in a timeiy manner.
13. Correct - Basis states that the cooldown to
500 O F will lower thr RCS
temperature below the saturation pressure of the S/G reliefs.
C. Incorrect -While the polishing system would help clean the secondary, it
8. Incorrect - PORV setpoint are raised to 90% to limit release of
radioactivity.
REFERENCES:
is not an action contained in the procedure.
j-,
3-OT-T/SQ304 p. 8
Tech Spec 3.4.16 basis
E-3 'SIG Tube Rupture'
Beaver Valley 12/01/2002
1 OCFR55.43.4/45.10
Ability to control radiation releases.
RO-73
SRO-73
Reference:
3-OT-SYS063
W A value:
2.1
Level:
1
TierIGrp:
3
KIA Number: 0 2.3.1 1
Last Used:
12/01/2002
Source:
BANK
SRQ Only:
.-
_-
Page: 1
5/27/2004
G 2.4.12 001
Given the following plant conditions:
-
-
-
-
-
The plant was initially at 100% power when a Reactor Trip occurred.
The control room crew implemented E-0, and are performing their Immediate
Operator Actions.
During the event, one PZR PORV opened and RGS pressure dropped to
1825 psig.
The 086 noticed the valve was open and closed it.
Plant conditions are now as follows:
-
Charging flow on l-FC62-93A is 87 gpm.
-
Letdown flow on 143-62-82 is 75 gpm.
-
RCS pressure is 1900 p i g and rising.
-
Charging pressure is 2400 psig.
-
VCT level is 35% and stable.
Given the plant conditions above, which QNE of the following describes Si status
and the required crew response?
A? NOT initiated and IS required. The crew should manually initiate Si and
continue in E-O.
B. NOT initiated and IS NOT required. The crew should transition to ES-O.I,
"REACTOR TRIP KESPONSE" to stabilize the plant.
..-
C. Automatically initiated but IS NOT required. The crew should continue in the
emergency procedures until SI can be terminated.
D. Automatically initiated and IS required. The crew should verify initiation of SI
and continue in the emergency procedures until SI can be terminated.
The correct answer is A
A. Correct - SI should have Auto initiated at 2870 psig. If SI signal was generated then
Ietdawn would have been isolated by Phase A. Crew is required to back-up auto
signals, even if the initiating signal is no longer present. SI will be initiated and
verified in 4.
3. Incorrect - SI is required. Students may select this due to current plant conditions
C. Incorrect - SI has not Auto initiated. Phase A would have isolated letdown if the SI
signal generated. Student may select based on pressure rising and charging flows
given. Second part of question gives option for procedural flowpath if selected.
D. Incorrect - SI has not Auto initiated. Phase A wouid have isoiated letdown if the SI
signal generated. Student may select based on pressure rising and charging flows
given. Second part of question gives option far procedural flowpath if selected.
._
-
Page: 1 of 2
5/27/2004
REFERENCES:
Lesson plan 3-OY-EOPOO00
E-Q 'Reactor Trip or Safety Injection'
Knowledge of general operating crew responsibilities during emergency operations.
RQ-74
SRO-74
Reference:
3-OT-EOP0000
G A value:
3.4
Level:
2
TieriGrp:
3
',__.,
Page: 2 of 2
U'h Number: G 2.4 12
Last Used:
Source:
IMNK
SRO Only:
5/27/2004
G 2.4.17 001
Match the following terms with their definition as provided in TI-22.04, "Users
Guide for Abnormal and Emergency Operating Instructions".
A. Check
B. Ensure
C. Actuate
exists.
D. Verify
Z . To manually cause a normaliy automatic signal to occur.
2. To observe that an expected characteristic or condition
3. TO observe that an expected characteristic or condition
exists and, if necessary, to take actions to make the
condition occur.
4. To investigate the position or status of a specified
function or variakde.
5. TO bring about, to take necessary actions to cause a
specified set of conditions to exist.
Which ONE of the following groups is correctly matched?
A. A-5, 8-2,
6-1,
D-3
3. 8-4, B-3, C-5, D-2
CY A-4, B9, C-I, D-2
D. A-5, 8-2, 0-1, B-4
The correct answer is C
A. Incorrect - Wrong ordered pairs (see definitions)
\\_ '
B. Incorrect - Wrong ordered pairs (see definitions)
C. Corect - see definitions
0. Incorrect - Wrong ordered pairs (see definitions)
A.
- To investigate the position or status of a specified function or
variable.
5. Ensure - To observe that an expected characteristic or condition exists and, if
necessary, to take actions to make the condition occur.
C. Actuate - To manuaily cause a normally automatic signal to occur
D.
- To observe that an expected characteristic or condition exists.
REFERENCES:
TI-12.04
Lesson plan 3-08-811204
IOCFR55.4? .10/45.13
--
Knawiedge of EOP terms and definitions.
RO-75
SRQ-75
Reference:
TI-12.04
ICIA value:
3.1
Level:
1
TieriGrp:
3
KiA Number: G 2.4.17
Last Used:
Source:
BANK
SRO Only:
._
..
._
.