ML032940401
| ML032940401 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/29/2003 |
| From: | NRC/RGN-II |
| To: | Progress Energy Florida |
| References | |
| 50-302/03-301, FOIA/PA-2004-0122 50-302/03-301 | |
| Download: ML032940401 (172) | |
See also: IR 05000302/2003301
Text
Final Submittal
CRYSTAL RIVER AUGUST
EXAM 50-30212003-301
-
AUGUST 25 29,2003
1. Combined RO/SRO Written Exam with KAs,
Answers, References, and Analysis
QUESTIONS REPORT
for NRC Reviewed RO BANK
1. OOIK5.28 002
The following plant conditions exist:
- The reactor has been at 100% power for 12 days.
- Rod index is 290%.
- 300 EFPD.
1100 ppm boron.
Due to erratic indications in the CRD system engineering has requested a rod index of 260% to
perform trouble shooting activities. Determine the final boron concentration required to reach
this rod index while maintaining 100% reactor power. (disregard Xenon)
A. 1034 ppm boron
B. 1040 ppm boron
C.' 1052 ppm boron
D. 1056 ppm boron
Reasons:
Using Curve 14, CRG 5-7 Integral Reactivity Worth (equilibrium Xenon), +0.314% A& !
reactivity must be added. Using Curve 4, Inverse Boron Worth vs Cycle Lifetime at HFP, the
value is 152.5 ppmb/ %Ak/k.
A. If Curve 8A, CRG 5-7 Integral Reactivity Worth (peak Xenon), was used
then this answer would be arrived at.
B. If Curve 8A, CRG 5-7 Integral Reactivity Worth (peak Xenon), was used,
and Curve 4 at HZP instead of HFP, then a boron reduction of 60 ppmb
would be required.
C. Correct. A boron dilution of 48 ppmb is required.
D. If Curve 4 at HZP instead of HFP was used then a boron reduction of 44
ppmb would be required.
Tuesday, October 14,2003 10:3903AM 1
QUESTIONS REPORT
for NRC Reviewed RO BANK
OP-l03C, Curves 4 & 14
RO - NEW
References provided: OP-103C
Rev. 0 to NRC on 5-9-03
Rev. 1 to NRC on 6-17-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C C C C C C C C C C Items Not Scrambled
Tier: 2 Group: 2
Keyword RO #56 Cog Level: CIA 3.513.8
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:03AM 2
QUESTIONS REPORT
for NRC Reviewed RO BANK
2. 002K1.09 001
Which of the following describes the effect on PZR conditions during a large reactor coolant
insurge?
A. Actual liquid temperature will decrease; Tsat of the surface liquid will decrease.
B. . Actual liquid temperature will decrease; Tsat of the surface liquid will increase.
C. Actual liquid temperature will decrease; Tsat of the surface liquid will remain the
same.
D. Actual liquid temperature will remain the same; Tsat of the surface liquid will
increase.
Reasons:
A,, C. & D. For these plant conditions the following should occur:
1. RCS pressure should increase because the insurge will squeeze the PZR steam bubble.
2. PZR level should increase because MUV-31 does not have the capacity or time
response needed to maintain level at setpoint.
3. PZR fluid temperature should decrease due to the insurge of colder water from the RCS.
B. Correct. Liquid temperature will decrease due to the approximately 600" F
water mixing with the 648" F water. While the insurge is in progress RCS
pressure will increase which will cause Tsat of the liquid to increase.
NRCM98
RO - Direct [Newops ROT-4-60-1581
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B C D A B C D A B C Scramble Range: A - D
Tier: 2 Group: 2
Keyword RO #57 Cog Level: CIA 4.U4.1
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:03 AM 3
QUESTIONS REPORT
for NRC Reviewed RO BANK
3. 003AK3.07 001
A reactor startup is in progress with the reactor critical. Control rod 5-4 drops into the core
and the following parameters are noted:
- The reactor is still critical.
- Tave is 524" F.
Which of the following describes the actions that should be taken and the reasons for these
actions?
A. * Increase Tave to 2 525" F, using secondary parameters, to maintain instrumentation
on scale.
B. Increase Tave to 2 525' F, using small control rod withdrawals, to maintain the
plant within analyzed accident ranges.
C. Fully insert all control rods to establish and maintain Mode 3 reactivity conditions
since criticality is prohibited at < 525' F.
D. Fully insert control rod groups 5-7 to establish and maintain Mode 2 reactivity
conditions since criticality is prohibited at < 525" F.
Reasons:
A. Correct. If the reactor is critical then Tave must be restored immediately
using secondary parameters.
B. Control rods should not be used to restore Tave.
C. Only required to insert the regulating rods, not safety rods, ifunable to
restore Tave.
D. The plant is required to be in Mode 3, not Mode 2, if unable to restore Tave.
OP-203 Step 3.2.7,0P-210 Step 3.2.2,OI-01 Step 4.5
RO - New
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A A A A A A A A A A Items Not Scrambled
Tuesday, October 14,2003 10:3903 AM 4
QUESTIONS REPORT
for NRC Reviewed RO BANK
Tier: I Group: 2
Keyword: RO#19 Cog Level: MEM 3N3.9
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:03AM 5
QUESTIONS REPORT
for NRC Reviewed RO BANK
4.003K1.03 001
The following conditions are observed for the "A"Reactor Coolant Pump,
- Reactor Coolant System pressure 2150 psig
- Second stage seal cavity pressure 2 100 psig
- Third stage seal cavity pressure 1055 psig
- Controlled bleedoff flow increased
- Seal leakage flow no change
Which of the following failures would cause the above indications?
A. * The first stage seal.
B. The second stage seal.
C. The third stage seal.
D. The restriction bushing.
Reasons:
A. Correct. When the first stage seal fails, the second stage seal will reflect
RCS pressure and the third stage seal should reflect approximately 1/2 of
the RCS pressure.
B. If the second stage seal had failed the second stage seal cavity pressure
would be closer to 1/2 of the RCS pressure.
C. If the third stage seal had failed, seal leakage would have increased and the
cavity pressure would be closer to atmospheric pressure.
D. With all the pressures being normal (except the second stage seal cavity)
and tbe bleedoff and seal leakage flows normal for a first stage seal failure,
no restriction bushing failure i s indicated.
OPS 4-60 Section 1-4.0.5.7
RO - Direct
References provided: None
Rev. 0 to NRC on 4-1 1-03
Tuesday, October 14,200310:39:03AM 6
QUESTIONS REPORT
for NRC Reviewed RO BANK
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A B C D A B C D A B Scramble Range: A - D
Tier: 1 Group: 1
Keyword: RO #5 Cog Level: CIA 2.912.9
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:03AM 7
QUESTIONS REPORT
for NRC Reviewed RO BANK
5. 003K3.05 001
The following plant conditions exist at 100% power:
'A'OTSG Level 80% B'OTSG Level 80%
'A'MFW Flow 5.4 E6 lbmihr B'MFW Flow 5.4 E6 l b m h
Core AT 45'F
A problem develops with RCP-IC and the decision is made to run the plant back and secure
the pump. At 80% power RCP-IC trips and an ICs runback occurs to 75% power. Which of
the following describes the approximate expected plant parameters, as compared to the above
values, after the plant stabilizes at 75% power?
A. .d 'A'OTSG Level unchanged
B'OTSG Level 50% of original
'A'MFW Flow unchanged
B'MFW Flow 50% of original
Core AT 45" F
B. 'A'OTSG Level unchanged
B'OTSG Level 50% of original
'A'MFW Flow unchanged
B'MFW Flow 50% of original
Core AT 34' F
C. 'A'OTSG Level 75% of original
B'OTSG Level 50% of original
'A'MFW Flow 75% of original
B'MFW Flow 50% of original
Core AT 45" F
D. 'A' OTSG Level 75% of original
B'OTSG Level 50% of original
'A'MFW Flow 75% of original
B'MFW Flow 50% of original
Core AT 34' F
Tuesday, October 14,2003 10:39:03AM 8
QUESTIONS REPORT
for NRC Reviewed RO BANK
Reasons:
B. Core AT will remain at 45" F for these conditions.
C. The 'A'OTSG is still removing the same amount of energy therefore level
and flow will remain at the same value.
D. The 'A'OTSG is still removing the same amount of energy therefore level
and flow will remain at the same value. Core AT will remain at 45" F.
OPS 4-14 Section 1-7.O.C.3.b)2); OP-103A Curve 6
NRCN99
RO - Direct
References provided: None
Rev. 0 to NRC on 4-1 1-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A A A A A A A A A A Items Not Scrambled
Tier: 2 Group: 1
Keyword: RO #28 Cog Level: CIA 3.613.7
Source: B Exam: CR03301
Test R Misc: ATK
Tuesday, October 14,2003 10:3903 AM 9
QUESTIONS REPORT
for NRC Reviewed RO BANK
6. 003K6.04 001
The plant is operating at 100% power when the SW Return valve from RCP-IC (SWV-86)
closes. Attempts to reopen the valve have failed.
Which of the following describe the action required to be taken with respect to RCP-lC?
RCP-IC:
A. * must be shutdown within 5 minutes due to loss of motor cooling.
B. must be shutdown within 5 minutes due to loss of RCP seal cooling.
C. may continue operation as long as RCP Seal Injection is maintained.
D. may continue operation because cooling is maintained by internally circulating
RCS.
Reasons:
A. Correct. Loss of SW alone only affects the RCP motor cooling.
B. RCP seal cooling is still available as long as Seal Injection is maintained.
C. This is true for a loss of Seal Injection, not loss of SW.
D. RCP must be stopped within 5 minutes to protect the motor from damage.
OP-302 Step 3.2.5
RO - Direct [4-060-0031
References provided: None
Rev. 0 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A A D C D D C A A D Scramble Range: A - D
Tier: 2 Group: 1
Keyword RO #29 Cog Level: MEM 2.U3.1
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:03 AM 10
QUESTIONS REPORT
for NRC Reviewed RO BANK
7. 004A1.12001
The following plant conditions exist:
- Plant is near EOC at 90% power.
- Deborating demins are in service.
- OP-304, Soluble Poison Concentration Control, calculation requires 60 gpm
letdown flow for one hour.
Due to a malfunction with MUV-5 1, letdown flow control valve, actual letdown flow was
80 gpm.
Which of the following describes how the plant will respond?
A. Control rods will insert; reactor power will decrease.
B. Control rods will insert; reactor power will remain approximately the same.
C. Control rods will withdraw; reactor power will increase.
D. Control rods will withdraw; reactor power will remain approximately the same.
Reasons:
A. Reactor power will remain at about 90%.
B. Correct. Rods will insert due to the deboration and power should remain at
90%.
C. Control rods will insert and power should remain at 90%.
D. Control rods will insert.
OPS 4-59 Section 1-4.0.V, OPS 4-52 Sections 1-2.0.D & 1-3.0.C, OPS 4-52 Obj 2,
RO - New
References provided None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B B B B B B B B B B Items Not Scrambled
Tier: 2 Group: 1
Keyword RO #30 Cog Level: CIA 2.813.2
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:03AM 11
QUESTIONS REPORT
for NRC Reviewed RO BANK
8. 005~4.08002
The following plant conditions exist:
- A LOCA is in progress.
- RCS pressure is 400 psig.
- Two High Pressure Injection Pumps are operating.
- Two Low Pressure Injection Pumps are operating.
Which of the following is the correct flow path for core heat removal?
A. * Manual alignment of piggy-back flow through the Makeup Pumps with the Decay
Heat pumps taking a suction from the Reactor Building Sump prior to BWST level
decreasing to < 7 feet.
B. Automatic alignment of piggy-back flow through the Makeup Pumps with the
Decay Heat pumps taking a suction from the Reactor Building Sump prior to
BWST level decreasing to < 7 feet.
C. Manual alignment of piggy-back flow through the Makeup Pumps with the Decay
Heat pumps taking a suction from the Reactor Building Sump prior to BWST level
reaching 15 feet.
D. Automatic alignment of piggy-back flow through the Makeup Pumps with the
Decay Heat pumps taking a suction from the Reactor Building Sump prior to
BWST level reaching 15 feet.
Reasons:
A. Correct. Manual alignment of piggy-back flow from the RB Sump must be
completed prior to BWST level reaching < 7 feet.
B. Alignment to this mode is a manual, not automatic, evolution.
C. The action for this alignment starts at 15 feet in the BWST. This is also the
level that Building Spray is aligned to the RB Sump.
D. This is a manual evolution and suction transfer starts at 15 feet. Does
not have to be completed until 7 feet.
Tuesday, October 14, 2003 10:39:03 AM 12
QUESTIONS REPORT
for NRC Reviewed RO BANK
OPS 4-54 Secion 1-3.0.C; EOP-14, Enclosure 19, ECCS Suction Transfer
RO - Direct [Opsbank ROT 4-054-0521
References provided: None
Rev. 0 to NRC on 4-22-03
Rev. 1 to NRC on 6-17-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A B C D A B C D A B Scramble Range: A - D
Tier: 2 Group: 1
Keyword RO #31 Cog Level: MEM 3.113.5
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:03AM 13
QUESTIONS REPORT
for NRC Reviewed RO BANK
9. 00662.1.28 002
Which of the following describes the purpose and operation of the HPI Throttle valves
(MUV-590,591,592 & 593)?
To limit:
A. MUP flow to the MUT. These valves may be throttled from the Control Room.
B. MUP flow to the RB sump in the case of a high MUT level. These valves are fixed
in position.
C. EDG loading and balance HPI flow. These valves may be throttled from the
Control Room.
D. * EDG loading and balance HPI flow. These valves are fixed in position.
Reasons:
A. The HPI Throttle valves do not control flow back to the MUT.
B. This describes the HPI recirc to sump valves, not the throttle valves.
C. The valves cannot be throttled from the control room.
D. Correct. These valves were added to limit EDG loading and to balance HPI
flow. The valves are tack welded in position.
OPS 4-52 Section 1-4.0.EE
RO - NEW
References provided None
Rev. 0 to NRC on 4-22-03
Rev. 1 to NRC on 6-1 7-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D A B C A A C B D D Scramble Range: A - D
Tier: 2 Group: 1
Keyword: RO #33 Cog Level: MEM 3.213.3
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:03AM 14
QUESTIONS REPORT
for NRC Reviewed RO BANK
10. 006K4.05 001
The plant is conducting a shutdown and cooldown with Reactor Coolant System (RCS)
pressure at 1200 psig and temperature at 400" F. The High Pressure Injection (HPI) portion of
the Engineered Safeguards (ES) actuation system has been bypassed per procedure. An RCS
pressure transient occurs which raises RCS pressure to 1820 psig. How does the ES system
react to this condition?
A. The actuation and bypass bistables will automatically reset. There will be no
actuation of the HPI systems.
B. The actuation and bypass bistables will NOT automatically reset. There will be a
full actuation of the HPI systems.
C. The actuation bistable will automatically reset, but the bypass bistable will NOT
automatically reset. There will be no actuation of the HPI systems.
D.* The actuation bistable will NOT automatically reset, but the bypass bistable will
automatically reset. There will be a full actuation of the HPI systems.
Reasons:
A. The actuation bistable will not auto reset and there will be an actuation.
B. The bypass bistable will auto reset.
C. The actuation bistable will not auto reset and the bypass bistable will auto
reset.
D. Correct. The bypass bistable will automatically reset at 1800 psig and
because the actuation bistable is still tripped a full HPI actuation will occur.
OPS 4-13 Section 1-2.0.D
NRCCP97
RO - Direct
References provided: None
Rev. 0 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D C D A C C A D C A Scramble Range: A - D
Tuesday,October 14, 2003 10:39:03 AM 15
QUESTIONS REPORT
for NRC Reviewed RO BANK
Tier: 2 Group: 1
Keyword: RO #32 Cog Level: CIA 4.314.4
Source: 3 Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:03 AM 16
QUESTIONS REPORT
for NRC Reviewed RO BANK
11. 007A4.10001
The following plant conditions exist:
- Reactor coolant average temperature is 579' F.
- Reactor coolant pressure is 2100 psig and decreasing at 100 psiglmin.
- Pressurizer temperature is 643' F and decreasing at 6" Flmin.
- Makeup flow is 8-10 gpm higher than normal.
- The Reactor Coolant Drain Tank level and pressure are stable.
- PZR level is stable.
- Reactor power is 40%.
Which of the following is the most probable cause for the above indications?
A. RCS pressure transmitter tubing rupture.
B. Partially stuck open PORV.
C. +. Code safety valve flange leak.
D. MUV-567, letdown isolation valve, bonnet leak.
Reasons:
A. & D. Loss of RCS pressure without a loss of level is an indication of steam
space leak.
B. An open PORV would cause RCDT level andor pressure to increase.
C. Correct. Other than the PORV this is the only leak path that will
lower pressure this fast with little change in makeup.
NRCN99
RO - Direct [Newops 4-60-0181
References provided None
MCS Time: 1 Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer: C D A B C D A B C D Scramble Range: A - D
Tier: 2 Group: 1
Keyword: RO #34 Cog Level: C/A 3.613.8
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:03AM 17
QUESTIONS REPORT
for NRC Reviewed RO BANK
12.007EA2.02 002
The following sequence of events have occurred:
- The plant was in Mode 3 with Group 1 withdrawn and RCS pressure at 2155 psig.
- The PORV failed open and the RO closed the PORV block valve.
- RCS pressure is currently 1875 psig and increasing slowly.
- Currently Group 1 is still withdrawn.
Which of the following describes the immediate action(s) that should be taken for these
conditions?
A. Enter AP-490, RCS Boration, and start emergency boration.
B. Enter AP-520, Loss of RCS Coolant or Pressure, to recover RCS pressure.
C. * Depress the Rx trip pushbutton, enter EOP-2, Vital System Status Verification and,
if Group 1 is still withdrawn, open breakers 3305 and 3312.
D. Depress the Rx trip pushbutton, enter EOP-2, Vital System Status Verification and,
if Group 1 is still withdrawn, depress the 'HPI MAN ACT'pushbuttons for Trains A
and B to initiate emergency boration.
Reasons:
A. Entry conditions for AP-490 are not met.
B. Entry conditions for AP-520 were met but the RO took prompt and prudent
action to mitigate the PORV failure and the immediate concern is taking
actions to ensure the reactor is tripped.
C. Correct. Group 1 should have tripped when RCS pressure decreased below
1900 psig. If Group 1 is still withdrawn then the immediate action is to
remove power.
D. Depressing the 'HPI MAN ACT'pushbuttons for Trains A and B is only
done if NIs indicate the reactor is not shutdown after breakers 3305 and
33 12 are opened.
Tuesday, October 14, 2003 10:39:03 AM 18
QUESTIONS REPORT
for NRC Reviewed RO BANK
EOP-2 Step 3.3; OPS 5-96 Section 1-4.0.C
RO - New
References provided: None
Rev. 0 to NRC on 4-1 1-03
Rev. 1 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C A C A B A A C A A Scramble Range: A - D
Tier: 1 Group: 1
Keyword RO#1 Cog Level: CIA 4.314.6
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:04AM 19
QUESTIONS REPORT
for NRC Reviewed RO BANK
13. 008A4.07 001
Which of the following describes the normal method for maintainingkontrolling the level in
the Nuclear Services Closed Cycle Cooling System Surge Tank (SWT-I)?
A. Manual control by the Primary Plant Operator.
B. Automatic valve control set to maintain level between two setpoints.
C.+. Manual operation of the control switch for the fill valve on the Main Control Board.
D. Manual operation of the Demin Water transfer pumps on the Main Control Board.
Reasons:
A. The Primary Plant Operator can locally fill the SW surge tank but this is
not the normal method.
B. The DC surge tanks have automatic control but the SW surge tank does
not.
C. Correct. SWV-277 is the manual valve used for normal fill of the SW surge
tank.
D. Starting a DW transfer pump will increase flow to the SW surge tank but
only if the fill valve is opened manually.
OPS 4-56 Section 1-4.0.1.2.c
RO - Direct
References provided: None
Rev. 0 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C C B C D D B C D D Scramble Range: A - D
Tier: 2 Group: 1
Keyword RO #35 Cog Level: MEM 2.9/2.9
Source: B Exam: CR03301
Test: R Mix: ATK
Tuesday, October 14,2003 10:39:04 AM 20
QUESTIONS REPORT
for NRC Reviewed RO BANK
14.008AK1.01 001
The following plant conditions exist:
- Reactor Coolant (RCS) pressure 2220 psia.
- Reactor Coolant Drain Tank (RCDT) pressure is 50 psia.
- The PORV is stuck partially open.
What is the approximate temperature and phase of the fluid downstream of the PORV?
A. 649°F and Superheated
B. 298°F and Superheated
C. * 28 1"F and Saturated
D. 259°F and Saturated
Reasons:
A. This temperature is saturation for current pressurizer pressure but,
since the PORV flow is a constant enthalpy process, the downstream
temperature would not be at saturation for the pressurizer. It would more
closely approximate saturation temperature of the downstream RCDT and
be saturated, not superheated.
B. Downstream conditions should be saturated, not superheated. This
temperature can be obtained if the student adds 15 psi to the stem value of
RCDT pressure (50 psia).
C. Correct. Using the Mollier, conditions are saturated and the temperature is
28 1OF
D. Downstream conditions should be saturated, not superheated. This
temperature can be obtained if the student subtracts 15 psi from the stem
value of RCDT pressure (50 psia).
Tuesday, October 14,2003 10:3904 AM 21
QUESTIONS REPORT
for NRC Reviewed RO BANK
Steam table with Mollier diagram
RO - Direct
References provided: Steam table with Mollier diagram
Rev. 0 to NRC on 4-1 1-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C D A B C D A B C D -
Scramble Range: A D
Tier: 1 Group: 1
Keyword: RO #2 Cog Level: CIA 3.213.7
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:04AM 22
QUESTIONS REPORT
for NRC Reviewed RO BANK
15. 009EK2.03 001
The following plant conditions exist:
- A small break LOCA (SBLOCA) event is in progress.
- RCS pressure is 1500 psig.
Which of the following describes the reason for maintaining the OTSGs available as a heat
sink?
A. To ensure RCS heat removal while RCPs are operating.
B. To provide an alternate means of RCS pressure control.
C.* RCS pressure may remain too high for adequate HPI cooling.
D. Boiler-condenser cooling is the primary method for heat removal during a
SBLOCA event.
Reasons:
A. The RCPs will probably already be secured but, if not, their heat input to the
RCS is minimal.
B. While the cooldown may be controlled with the OTSGs RCS pressure is not.
C. Correct. Certain size SBLOCAs rely on the OTSGs for adequate heat removal.
D. Reflux boiling may occur in certain size SBLOCAs but this is not the primary
method of heat removal.
OPS 3-21 Section 1-2.O.B.5.b) 2)
RO - New
References provided None
Rev. 0 to NRC on 4-1 1-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C C C C C C C C C C Items Not Scrambled
Tier: 1 Group: 1
Keyword RO#3 Cog Level: MEM 3.0/3.3
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:04 AM 23
QUESTIONS REPORT
for NRC Reviewed RO BANK
16. 010K5.01 001
While at power, a feedwater transient caused a rapid out-surge of the pressurizer followed by a
rapid in-surge. Due to a pressurizer heater control problem all heaters are in manual and off.
The following conditions exist:
- Pressurizer temperature is 630" F.
- That is 600' F.
- Tcold is 555' F.
- Pressurizer level is at 240 inches and slowly returning to normal.
With no operator action RCS pressure will stabilize at approximately:
A. 100 psig.
B. 550 psig.
C. * 900 psig.
D. 2155 psig.
Reasons:
A. Psat for T cold temp of 555" F
B. Psat for T hot temp of 600" F.
C. Correct. Psat for this current PZR temp of 630 O F.
D. Psat for normal PZR temp of 648" F.
OPS 4-60 Section 1-4.0.E; OPS 4-12 Section 1-3.O.C.2.h & i
RO - New
References provided: Steam tables
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C A C D D B A A B D Scramble Range: A - D
Tier: 2 Group: 1
Keyword RO #36 Cog Level: CIA 3.514.0
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:05AM 24
QUESTIONS REPORT
for NRC Reviewed RO BANK
17. 011EG2.4.20001
A note in EOP-8, LOCA Cooldown, states the following:
"Do not open PORV or use high pressure Aux spray to depressurize RCS if ICC Region 3 was
previously entered."
Which of the following describes the reason for this note?
A. 4. The RCS may contain large amounts of non-condensable gasses and opening the
PORV could result in additional gas bubbles forming in the hot legs.
B. Due to documented PORV failures in the industry, the risk of losing excess
additional RCS inventory if the core had previously entered Region 3 has been
determined to be unacceptable.
C. Engineering calculations have determined that the effectiveness of high pressure
Aux spray is greatly diminished if the core had previously entered Region 3 and
does not create a success path for this condition.
D. A commitment to the NRC to justify not installing the RV head vent requires the
use of the hot leg high point vents only for RCS depressurization.
Reasons:
A. Correct. Due to the rapid depressurization of the RCS if the PORV was opened
additional gas bubbles may form faster than the HPVs can remove the gasses.
B. While there have been PORV failures in the industry this is not the reason the
PORV is not used.
C. Use of high pressure Aux spray has not been analyzed for use if the core has
previously entered Region 3.
D. The commitment requires using the PZR vent only
OPS 5-95 Section 3.24
RO - NEW
References provided: None
Rev. 0 to NRC on 4-22-03
Tuesday, October 14, 2003 10:39:05AM 25
QUESTIONS REPORT
for NRC Reviewed RO BANK
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A A A A A A A A A A Items Not Scrambled
Tier: 1 Group: 1
Keyword: RO #4 Cog Level: MEM 3.314.0
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:05 AM 26
QUESTIONS REPORT
for NRC Reviewed RO BANK
18.012K1.03 001
While in a plant cooldown the following conditions exist:
- Reactor Coolant Pressure is 400 psig.
- RCS temperature is 350' F.
- Control Rod Group 1 is withdrawn.
- The "D" Reactor Protection System channel is tripped.
The "C" RPS channel is bypassed for trouble shooting activites. The I & C technician asks
permission to pull the RCS flow module in the "C" RPS channel. If permission is granted
what will be the condition of the Control Rod Drive (CRD) breakers?
A. All CRD breakers are open.
B. * All CRD breakers are closed.
C. The "C" breaker is open; all other CRD breakers remain closed.
D. The "C" and "D" breakers are open; all other CRD breakers remain closed.
Reasons:
A. With the "C" channel in bypass the RPS is placed in a 2 out of 3 trip logic.
Pulling the module would have resulted in 2 channels being tripped if the
"C" channel was not bypassed.
B. Correct. Two channels of RPS are not tripped.
C. Since the "C" channel was bypassed prior to pulling the module this channel
will not trip.
D. Since the "C" channel was bypassed prior to pulling the module this channel
will not trip and no CRD breakers will open.
OPS 4-12 Section 1-4.0.A.4 & 2-14.0 Table 2
RO - Direct [Newops 4-012-01 11
References provided: None
Rev. 0 to NRC on 4-22-03
Tuesday, October 14,2003 10:39:05 AM 27
QUESTIONS REPORT
for NRC Reviewed RO BANK
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B D B C A A A B C B Scramble Range: A - D
Tier: 2 Group: 1
Keyword RO #37 Cog Level: CIA 3.713.8
Source: B Exam: CR03301
Test R Misc: ATK
Tuesday, October 14, 2003 10:39:05AM 28
QUESTIONS REPORT
for NRC Reviewed RO BANK
19.013K1.13 001
The following plant conditions exist:
- AHF-1A is ES selected for "A" ES Train operation.
- AHF-1B is ES selected for "B" ES Train operation.
- AHF-1C is tagged out due to a motor ground.
- HPI actuation on 1625 psig has occurred on both trains.
Which of the following statements describes AHF-1A and AHF-IB operation one minute after
the actuation?
A. AHF-IA and AHF-IB should be running in slow speed.
B. AHF-1A and AHF-IB should be running in fast speed.
C. AHF-IA should be running in slow speed and AHF-IB should be off.
D. AHF-1B should be running in fast speed and AHF-1A should be off.
Reasons:
A. Following an ES actuation only one fan will be running.
B. HPI Block 1 should trip the fast speed coils on all running fans.
C. Correct. Only one fan will be running and the "A" train fan, if available,
will start.
D. "A" train fan logic is biased to start first and AHF-IB, if running, should be
in slow speed.
OPS 4-13 Section 1-14.0 Table 2
RO - Direct
References provided: None
Rev. 0 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C C C C B D C B C B Scramble Range: A - D
Tuesday, October 14,2003 10:3905 AM 29
QUESTIONS REPORT
for NRC Reviewed RO BANK
Tier: 2 Group: I
Keyword RO #39 Cog Level: MEM 2.W3.1
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:05 AM 30
QUESTIONS REPORT
for NRC Reviewed RO BANK
20. 013K6.01001
The following plant conditions exist:
- An RBIC actuation has occurred.
- One 4 psig pressure switch in the "A" train has failed in the non-actuated
position.
- Two 4 psig pressure switches in the "B" train are failed in the non-actuated
position.
Assuming no input to any isolation valves from diverse isolation (HPI), which of the following
statements describes the status of the RBIC actuation and the RB isolation safety function for
these conditions?
A. Both "A" and "B" trains of RBIC would actuate. The safety function would be met.
B. "A" train of RBIC would actuate, "B" train would not actuate. The safety function
would be met.
C. "A" train of RBIC would actuate, "B" train would not actuate. The safety function
would not be met.
D. Neither train of RBIC would actuate. The safety function would not be met
Reasons:
A. "B" train would not actuate due to two failed switches.
B. Correct. "A" train would actuate due to two tripped channels, "B" train would
not actuate due to two failed switches. Either train will meet the safety
function.
C. "A" train would actuate due to two tripped channels, "B" train would not
actuate due to two failed switches. Either train will meet the safety function.
D. "A" train would actuate due to two tripped channels.
Tuesday, October 14, 2003 10:39:05AM 31
QUESTIONS REPORT
for NRC Reviewed RO BANK
OPS 4-13 Section 1-2.0.Bl.e
RO - Direct
References provided: None
Rev. 0 to NRC on 4-22-03
MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B C D A B C D A B C Scramble Range: A - D
Tier: 2 Group: I
Keyword RO #38 Cog Level: CIA 2.713.1
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:05AM 32
QUESTIONS REPORT
for NRC Reviewed RO BANK
21. 014K4.05001
In the Control Rod Drive system which of the following will cause an OUT INHIBIT when the
diamond panel is in automatic control?
A. Asymmetric fault with reactor power less than 60%.
B. Loss of safety rods out limit with reactor power greater than 60%.
C. Loss of motor power supply with reactor power less than 60%.
D. A sequence inhibit with reactor power greater than 60%.
Reasons:
A. Reactor power would have to be 5.60% for an asymmetric fault to generate an
out inhibit.
B. Correct. Loss of the safety rod out limit at > 60% reactor power will generate
an out inhibit.
C. Motor power has no input to the out inhibit circuitry.
D. Sequence inhibit will not give an out inhibit but it will require the rods to be
moved in manual.
OPS 4-28 1-4.0.M.l.r) &Figure 16
RO - Direct [Opsbank ROT-4-28-0101
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 S 6 7 8 9
Answer: B C D A B C D A B C Scramble Range: A - D
Tier: 2 Group: 2
Keyword RO #58 Cog Level: MEM 3.113.3
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:3905 AM 33
QUESTIONS REPORT
for NRC Reviewed RO BANK
22. 015A1.04002
During a power increase the RO notices the following NI indications. The power increase is
stopped and the plant is stabilized. The following indications are recorded.
- NI-5 upper chamber 42.0% NI-7 upper chamber 42.4%
- NI-5 lower chamber 43.3% NI-7 lower chamber 44.4%
- NI-6 upper chamber 43.3% NI-8 upper chamber 48.0%
- NI-6 lower chamber 44.6% NI-8 lower chamber 49.4%
Which of the following describes the required actions, if any, for the above indications?
A. Reduce thermal power to < 60% of the allowable thermal power within two hours
AND reduce the nuclear overpower trip setpoint to 5 65.5% of the allowable
thermal power within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
B. Reduce thermal power 2 2% RTP from the allowable thermal power for each 1% of
QPT greater than the steady state limit within 30 minutes AND restore QPT to less
than or equal to the transient limit within two hours.
C. No TS actions are required. These indications are expected due to the increased
shielding from Tcold at lower power levels.
D. No TS actions are required. These indications are expected due to the decreased
shielding from Tcold at lower power levels.
Reasons:
A. Correct. With power > 60% and QPT greater than the Transient
Limit this is the correct action to take.
B, The QPT calculation equals 9. This is greater than the transient but
less than the maximum and there is no misaligned rod. TS 3.2.4
condition D applies.
C. TS 3.2.4 is required to be entered due to QPT. Shielding is decreased
due to a hotter Tcold at lower power.
D. TS 3.2.4 is requried to be entered due to QPT.
Tuesday, October 14,2003 10:39:05AM 34
QUESTIONS REPORT
for NRC Reviewed RO BANK
RO - Direct [Newops 4-10-0071
References provided COLR & TS 3.2.4
Rev. 0 to NRC on 5-9-03
Rev. 1 to NRC on 6-17-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A B C D A B C D A B Scramble Range: A - D
Tier: 2 Group: 2
Keyword: RO #59 Cog Level: CIA 3 3 3 . 7
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:05 AM 35
QUESTIONS REPORT
for NRC Reviewed RO BANK
23. 016A3.01 001
The following plant conditions exist:
- The plant is at 40% power with turbine control in ICS/Auto.
- Turbine is selected to "A" header pressure for control.
- The header pressure setpoint is currently set at 46 for maintenance trouble
shooting activities of the turbine header pressure control circuit.
Which of the following describes the plant response if the selected "A"header pressure
transmitter failed rapidly to mid-scale?
A. * SASS will swap to the unaffected transmitter. Turbine and TBV control will not be
affected.
B. SASS will swap to the unaffected transmitter. Turbine control will not be affected
but the TBV associated with the failed transmitter must be controlled in manual.
C. SASS will not swap to the unaffected transmitter. The turbine and TBVs must be
controlled in manual.
D. SASS will not swap to the unaffected transmitter. Turbine control will not be
affected but the TBV associated with the failed transmitter must be controlled in
manual.
Reasons:
With HP setpoint @ 46 the controlling HP signal is 876# vs the normal 885#. A failure
mid-scale of the transmitter will result in a 900# signal. A delta of 24#. SASS requires a 3%
scale change to transfer. This equates to 18# of the 600# to 1200# scale. If HP setpoint was at
its normal setpoint of 47.5 then the SASS transfer would not occur.
A. Correct. SASS will automatically swap and there will be no affect on the
turbine or TBVs.
B. TBV control is unaffected.
C. SASS will swap. Turbine and TBVs can remain in automatic.
D. SASS will swap. TBV control is not affected.
Tuesday,October 14, 2003 10:39:05AM 36
QUESTIONS REPORT
for NRC Reviewed RO BANK
OPS 4-09 Section 1-14.0
RO - New
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer: A A A A A A A A A A Items Not Scrambled
Tier: 2 Group: 2
Keyword RO #60 Cog Level: CIA 2.912.9
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:05 AM 37
QUESTIONS REPORT
for NRC Reviewed RO BANK
24. 022A2.04 001
Ten minutes after an RBIC actuation occurred a malfunction results in the closure of SWV-36,
AHF-1A Cooling Water Inlet isolation valve. Which of the following describes the affected
component(s) and required operator action(s)?
A. Only AHF-IAs cooling coils will lose SW cooling water; cooling water supply
should be swapped to Industrial Cooling (CI) within 5 minutes.
B. AHF-IAs cooling coils and motor cooler will lose SW cooling water; cooling
water supply should be swapped to Industrial Cooling (CI) within 5 minutes.
C. Only AHF-IAs cooling coils will lose SW cooling water; AHF-1B should be
started in slow speed and AHF-1A should be secured.
D. 4. AHF-1As cooling coils and motor cooler will lose SW cooling water; AHF-1B
should be started in slow speed and AHF-1A should be secured.
Reasons:
A. Motor coolers are also cooled by SW. CI is isolated on an RBIC actuation
and even if actions were taken to restore CI cooling to the RB flow could not
be restored to this fan because both SW and CI use the same cooling valves
inside the RB.
B. CI is isolated on an RBIC actuation and even if actions were taken to
restore Cl cooling to the RB flow could not be restored to this fan because
both SW and Cl use the same cooling valves inside the RB.
C. Motor cooler will also lose cooling water.
D. Correct. Both the cooling coils and motor cooler will lose cooling. The
alternate ES fan should be started in slow speed and AHF-1A should be
secured.
OPS 4-56 Section 1-3.0.C
RO - New
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer: D D D D D D D D D D Items Not Scrambled
Tuesday, October 14,2003 10:39:05 AM 38
QUESTIONS REPORT
for NRC Reviewed RO BANK
Tier: 2 Group: 1
Keyword: RO #40 Cog Level: MEM 2.913.2
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:05AM 39
QUESTIONS REPORT
for NRC Reviewed RO BANK
25. 022AA2.04 002
The following plant conditions exist:
- Turbine is ready to sync on line.
- PZR level normal.
- Letdown flow is 75 gpm.
- Seal injection flow is 40 gpm.
- MUV-3 1 has failed closed.
- MUV-31 bypass flow indicates 20 gpm.
PZR level = 12 galhnch
Assuming no operator action approximately how long would it take for the PZR Low level
alarm to annunciate? (disregard CBO flow)
A. 8 minutes
B. 12 minutes
C. * 16 minutes
D. 20 minutes
Reasons:
With the turbine ready to synch the operator knows the RCS is at normal temperature and PZR
level should be at 220".
A.,B.,C.,&D.
220" (PZR normal) - 200" (PZR Low alarm) = 20" 20" X 12 galhnch = 240 gal.
20 gpm (makeup) + 40 gpm (seal injection) - 75 gpm (letdown) = -15 gpm
240 gallons divided by 15 gpm = 16 minutes
OPS 4-09 Section 1-4.0.B.6
RO - New
References provided: None
Rev. 0 to NRC on 4-1 1-03
Rev. 1 to NRC on 4-22-03
Tuesday,October 14,2003 10:39:05 AM 40
QUESTIONS REPORT
for NRC Reviewed RO BANK
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C C C C C C C C C C Items Not Scrambled
Tier: 1 Group: 1
Keyword RO#6 Cog Level: CIA 2.913.8
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:05AM 41
QUESTIONS REPORT
for NRC Reviewed RO BANK
26. 025AK2.05 001
When aligning the DHR system for boron precipitation, EOP-14, Enclosure 20, Boron
Precipitation Control, directs that the seal-in circuits for DHV-42 and 43 be defeated.
Enclosure 20 also directs that the valve control switch be held in the open position for 6
seconds before the DH drop-line valves are opened.
Which of the following describes a possible consequence if DHV-42 or 43 were fully open
when drop-line flow commenced?
The resulting drop-line flow could cause:
A. vortexes in the core region.
B. * RB sump screen damage and loss of the running DHWLPI pump.
C. voiding in the core region from the rapid pressure drop that would occur.
D. inadequate mixing of the RB sump water with the trisodium phosphate (TSP)
resulting in a higher than calculated pH required for adequate iodine removal.
Reasons:
A. Drop line flow cannot cause vortexing in the Rx vessel due to the flowpaths
in the Rx vessel.
B. Correct. Reduced flow limits challenges to the operating DHWLPI train
C. Voiding in the core region will not occur due to the flowpath from the core
to the hotleg and then out the drop line to the RB sump.
D. The TSP baskets are located near the sump, but not in the drop-line flow
path.
EOP-14, Enclosure 20, OPS 5-1 16 Sections 20.9 & 10
RO - Direct [Newops 5-1 16-0101
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 S 6 7 8 9
Answer: B C D A B C D A B C Scramble Range: A - D
Tuesday,October 14,2003 10:39:05AM 42
QUESTIONS REPORT
for NRC Reviewed RO BANK
Tier: 1 Group: I
Keyword RO#7 Cog Level: MEM 2.612.6
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:05 AM 43
QUESTIONS REPORT
for NRC Reviewed RO BANK
27. 026A3.01 001
The following plant conditions exist:
- Breakers 4900 & 4902 have opened (feeders to the OPT).
- A LOCA in containment is in progress.
- RB pressure is 34 psig.
- RCS pressure is 725 psig.
Based on the above conditions which of the following describes the status of DHP-1A,
BSP-lA, DHV-110 and BSV-3? (assume sufficient time has elapsed for all automatic actions
to occur)
A. DHP-1A Off ,
BSP-1A Running
DHV-110 Open
BSV-3 Throttled
B. DHP- 1A Off
BSP-1A Running
DHV-110 Throttled
BSV-3 Throttled
C. DHP-IA Running
BSP-1A Running
DHV-110 Throttled
BSV-3 Open
D. DHP-1A Running
BSP-1A Off
DHV- 1 10 Open
BSV-3 Closed
Tuesday, October 14, 2003 10:39:05 AM 44
QUESTIONS REPORT
for NRC Reviewed RO BANK
Reasons:
A. DHV-110 is throttled in its ES standby position. The valve must first see
its respective DHP start then, after a 30 second time delay, the valve will
control flow at 3000 gpm.
B. Correct. LOOP conditions exist for the "A" ES bus. The RBIC cascade start
of DHP-1A is defeated on a LOOP. If RCS pressure decreases below 500
psig the LPI actuation signal will start the pump. BSP-1A is running due
to the HPI actuation accompanied by RB pressure > 30 psig. DHV-110 is
still in its ES standby position because DHP-1A has not started. BSV-3 is
throttled to control flow at 1500 gpm.
C. DHP-1A is not running due to LOOP conditions. BSV-3 should be throttled
controlling flow.
D. DHP-1A is not running due to LOOP conditions. BSP-1A should be
running. If DHP-1A were running then DHV-110 would be full open
attempting to achieve 3000 gpm flow. BSV-3 will be full open due to the
RBIC but should now be throttled due to the 30# signal.
OPS 4-13 Tables 2 , 4 , 5 & 6, OPS 4-62 Sections 1-4.0.B & C, OPS 4-54 Sections 1-4.O.C.7.b
& 1-4.O.G.3.e
RO - New
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B B B E E E E B B E ltems Not Scrambled
Tier: 2 Group: 1
Keyword: RO #41 Cog Level: CIA 4.314.5
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:05 AM 45
QUESTIONS REPORT
for NRC Reviewed RO BANK
28. 026AA1.04 001
Multiple CRDM high stator temperature alarms are in. Which of the following conditions
could cause these indications?
A. * Standby SW booster pump auto-start and CRD filter delta P > 30 psid.
B. SWV-763, CRD Temperature control valve, fails to its maximum closed position.
C. The low SW flow interlock to the SW booster pumps fails and sends a low flow
signal to the pumps.
D. During performance of SP-344A, RWP-2A, SWP-1A and Valve Surveillance,
RWV-150, recirc to RW pit valve, fails full open.
Reasons:
A. Correct. The filter is clogged and reducing flow to the stators
B. This valve has a mechanical gag that prevents overheating the stators by
ensuring a minimum supply flow.
C. A failure of this interlocklow will send a start signal to the standby pump.
D. With RWP-2A running this failure will not effect RW flow to the SW heat
exchangers.
OPS 4-56 Section 1-4.0.6.F
RO - New
References provided: None
Rev. 0 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A A A A A A A A A A ltems Not Scrambled
Tier: 1 Group: 1
Keyword: RO #8 Cog Level: MEM 2.7/2.8
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,200310:39:05AM 46
QUESTIONS REPORT
for NRC Reviewed RO BANK
29. 027AA1.05 001
With the plant operating at 65% power a Sudden Pressurerelay actuates on the Startup
Transformer.
Based on the above conditions which of the following electrical line-ups could be used to
supply power to the ATrain PZR heaters?
A. MTDG-I; 4160V Rx Aux Bus 3; 480V Rx Aux Bus 3A.
B. * EDG-1A; ES 4160V BUS3A; ES 480V BUS3A; 480V RXAUXBUS3A.
C. BEST; ES 4160V Bus 3A; ES 480V Bus 3A; 480V Rx Aux Bus 3A.
D. EDG-IB; ES 4160V Bus 3B; 480V Plant Aux Bus; 480V Rx Aux Bus 3A.
Reasons:
A. 4160V Rx Aux Bus 3 cannot feed 480V Rx Aux Bus 3A.
C. The BEST has been lost due to the relay actuation associated with the
Startup Transformer.
D. This used to be a viable option until the removal of the feed to 480V Rx Aux
Bus 3A.
OPS 4-89 Figure 1; OPS 4-88 Sections 1-2.0-C.3.f, 1-2.0-I.3.b; AP-770
NRCN99
RO - Direct
Reverences provided: None
Rev. 0 to NRC on 4-1 1-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B C D A B C D A B C Scramble Range: A - D
Tier: 1 Group: 1
Keyword: RO #9 Cog Level: CIA 3.313.0
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:3905AM 47
QUESTIONS REPORT
for NRC Reviewed RO BANK
30. 028AK2.02 002
The following plant conditions exist:
- Plant is at 100% power.
- The selected PZR level transmitter rapidly fails low.
Which of the following describes what effect, if any, this malfunction will have on M W - 3 1
(PZR level control valve) operation?
MUV-3 1
A. will throttle closed in an attempt to restore PZR level.
B. will throttle open in an attempt to restore PZR level.
C. is interlocked to freeze in position without a valid PZR level signal.
D. operation will be unaffected because SASS will transfer to the alternate level
control signal.
Reasons:
A. &. B. For a rapid failure SASS will automatically swap control to the
alternate level transmitter.
C. This interlock does not exist on this valve but does on other similar
air operated valves.
D. Correct. Since the level transmitter failure was fast SASS will
transfer to the good signal.
OPS 4-09 Section 1-4.O.A.5.a
RO - Direct [Newops 4-009-0071
References provided: None
Rev. 0 to NRC on 4-22-03
Rev. 1 to NRC on 6-17-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D C A C C A D D A C Scramble Range: A - D
Tuesday, October 14, 2003 10:39:06 AM 48
QUESTIONS REPORT
for NRC Reviewed RO BANK
Tier: 1 Group: 2
Keyword RO #20 Cog Level: MEM 2.612.7
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:06 AM 49
QUESTIONS REPORT
for NRC Reviewed RO BANK
31. 029EK3.1 I 001
The following plant conditions exist:
- Reactor power is 50%.
- RCS pressure is 1950 psig.
- RCS Thot is 604" F.
- FW flow is 2.6 E6 l b d h r in each loop.
Based on the above conditions determine if an ATWS event hashas not occurred and which of
the following actions should be taken?
A. An ATWS event has occurred. Immediate actions of EOP-2 should be performed
and a manual turbine trip is required if reactor power remains at 50%.
B. * An ATWS event has occurred. Immediate actions of EOP-2 should be performed
and RCS boration is required if reactor power remains at 50%.
C. An ATWS event has not occurred. Excessive FW has caused the RCS pressure
decrease and FW flow should be lowered.
D. An ATWS event has not occurred. A steam leak has caused the RCS pressure
decrease and the reactor should be tripped if the leak cannot be isolated.
Reasons:
A. The third immediate action of EOP-2 requires the operator to remain at
that step and borate until the reactor is shut down. The next step requires
the turbine trip actions.
B. Correct. RCS pressure is too low for current RCS Thot. The variable low
pressure trip setpoint is exceeded and the reactor should have
automatically tripped. Boration is required if the reactor does not indicate
shutdown.
C. An ATWS event has occurred and FW flow is normal for this power level.
D. An ATWS event has occurred. A steam leak would cause RCS pressure to
decrease but would not cause Thot to increase.
Tuesday, October 14, 2003 10:39:06 AM 50
QUESTIONS REPORT
for NRC Reviewed RO BANK
OPS 5-96 Section 1-2.0.C; OPS 4-12 Obj. 4 Section 1-3.O.C.2.h; EOP-2 Step 3.3
RO - New
References provided: None
Rev. 0 to NRC on 4-1 1-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B B B B B B B B B B Items Not Scrambled
Tier: 1 Group: 1
Keyword: RO #10 Cog Level: CIA 4.214.3
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:3906AM 51
QUESTIONS REPORT
for NRC Reviewed RO BANK
32. 029K4.03 008
The plant is in Mode 5 with an RB purge in progress. High radiation in the containment
atmosphere has now resulted in RM-AI gas and RM-A6 gas channels going into high alarm.
Which of the following describes the expected automatic actions for these conditions?
A. Both RB purge exhaust fans will be tripped by RM-AI interlocks.
B. * AHV-IA, lB, lC, and 1D will be closed by RM-AI interlocks.
C. Both RB purge exhaust fans will be tripped by RM-A6 interlocks.
D. AHV-lA, IB, IC, and I D will be closed by RM-A6 interlocks.
Reasons:
A. No automatic trip is supplied to these fans from radiation monitors.
B. Correct. An interlock for RM-A1 gas channel in high alarm is the closure of
AHV-lA, IB, 1C and 1D.
C. RM-A6 has no interlocks which reposition equipment.
D. RM-A6 has no interlocks which reposition equipment.
OPS 4-25 Section 1-4.O.F.4.g
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B C D A B C D A B C Scramble Range: A - D
Tier: 2 Group: 2
Keyword RO #52 Cog Level: MEM 3.213.5
Source: B Exam: CR303301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:06 AM 52
QUESTIONS REPORT
for NRC Reviewed RO BANK
33.033AA2.04 001
A plant startup is in progress with the indications below. If the "C" RPS cabinet were to lose
power which of the following sets of conditions would have met overlap requirements and
allow continued power ascension?
A. NI-3 1 x 10-5
NI-4 1 x 10-5
NI-5,6,7 & 8 3%
B. + N1-3 1 x 10-5
NI-4 I x 10-5
NI-5, 6, 7 & 8 12%
C. NI- 1 9 x 105
NI-2 9 X IO5
NI-3 3 x 10-10
NI-4 3 x 10-10
D. NI-1 9 X IO5
N1-2 9 X IO5
NI-3 3 x 10-11
NI-4 3 X 10-l'
Reasons:
A. Overlap requirements have not been met.
B. Correct. Overlap requirements have been met and since the plant was in
Mode 1 prior to losing NI-3 power ascension may continue.
C. Overlap requirements have been met but since the plant is in Mode 2 power
ascension may not continue until NI-3 is declared operable.
D. Overlap requirements have not been met.
Tuesday, October 14, 2003 10:39:06AM 53
QUESTIONS REPORT
for NRC Reviewed RO BANK
TS3.3.1,3.3.9&3.3.10; OPS4-10FigureI
RO - New
References provided: TS 3.3.1 0
Rev. 0 to NRC on 5-9-03
MCS Time: 1 Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer: B D D B C B A A C D Scramble Range: A - D
Tier: 1 Group: 2
Keyword: RO #21 Cog Level: CIA 3.213.6
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:06 AM 54
QUESTIONS REPORT
for NRC Reviewed RO BANK
34. 035K4.01 001
RCP-IB has been secured due to an oil leak. A plant shutdown is in progress to repair the
leak. Which of the following describes how OTSG levels are controlled once Low Level
Limits are reached on the "A"OTSG?
A. The ATc circuit ensures additional flow will be maintained to the "B" OTSG to
maintain ATc at 0" F.
B. The RCS Flow Ratio circuit ensures additional flow will be maintained to the "B"
OTSG to maintain ATc at 0" F.
C .* The Total FW Flow Control circuit ensures additional flow will be maintained to
the "B" OTSG to maintain LLL in the "A"OTSG.
D. The FW Temperature Compensation circuit ensures additional flow will be
maintained to the "B" OTSG to maintain LLL in the "A"OTSG.
Reasons:
A. The ATc circuit is blocked when either OTSG reaches LLL.
B. The RCS Flow Ratio circuit still attempts to control FW but is overridden
when the conditions for the Total FW Flow Control circuit are met.
C. Correct. The Total FW Flow Control circuit conditions are met and this
circuit will override FW flow input from all the other circuits.
D. This circuit is upstream of the Total FW Flow Control circuit and any input
it may have is overridden.
RO - New
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C C C C C C C C C C Items Not Scrambled
Tier: 2 Group: 2
Keyword: RO#61 Cog Level: MEM 3.6/3.8
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:06 AM 55
QUESTIONS REPORT
for NRC Reviewed RO BANK
35. 037AK3.05 001
The crew has entered EOP-6, Steam Generator Tube Rupture, and minimized subcooling
margin by RCS depressurization as required.
Which of the following describes the reason for minimizing subcooling margin?
Minimizes:
A. + RCS leakage through the leaking OTSG tube.
B. time required for cooldown of the RCS.
C. potential of lifting Main Steam Safety Valves.
D. tensile stresses on affected OTSG tubes.
Reasons:
A. Correct. The reduction of subcooling margin minimizes the delta pressure
across the OTSG tube and therefore minimizes the leak rate.
B. Minimizing RCS pressure has no affect on the time required for RCS
cooldown.
C. Even though RCS pressure is minimized it still will initially be greater
than MSSV setpoints.
D. RCS pressure reduction does not minimize tensile stresses on the OTSG
tubes.
EOP-6 Step 3.17; OPS 5-101 Section 1-4.0-0
RO -Direct [Newops 5-101-0051
References provided: None
Rev. 0 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A B C D A B C D A B Scramble Range: A - D
Tuesday, October 14, 2003 10:39:06AM 56
QUESTIONS REPORT
for NRC Reviewed RO BANK
Tier: 1 Group: 2
Keyword RO #22 Cog Level: MEM 3.7/4.0
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:06 AM 57
QUESTIONS REPORT
for NRC Reviewed RO BANK
36. 038EA2.08 002
The following plant conditions exist:
- A 150 gpm OTSG tube rupture has occurred on the A OTSG.
- A Loss of Off-site Power (LOOP) and Reactor trip have occurred.
- B OTSG has been isolated because of an unisolable steam leak.
- A plant cooldown and depressurization is in progress in accordance with EOP-6.
- The Reactor Coolant System (RCS) is presently at 491F (Tincore) and 1225
psig.
- A OTSG is being maintained at its natural circulation level by EFP-3.
- Initial Dose Equivalent (DE) 1-131 was 1.35 pci/g.
- Borated Water Storage Tank (BWST) level is 38.5 feet.
Based on these conditions, which of the following describes the action which should be taken?
A. The A OTSG should be isolated because TRACC limits are being exceeded.
B. * The AOTSG should be steamed to atmosphere and cooldown rates maintained
within normal limits.
C. Cooldown rate should be increased to 240Fhr until B OTSG is recovered or
Off-site power is available.
D. Cooldown must be stopped until the B OTSG or Off-site power can be recovered.
Reasons:
A. EOP-6, Step 3.33. Do not have secondary side integrity on both OTSGs. Will
not isolate (TRACC) only available OTSG due to DE 1-131 > limit..
B. Correct. With the conditions given, normal cooldown rates should be used;
TRACC limits do not apply.
C. The RCS is below 500 degrees. The emergency cooldown rates should not
be used.
D. Cooldown should not be stopped. Continued cooldown and depressurization
will minimize the leak rate into the OTSG, maximize makeup capabilities
and maximize the time that BWST inventory will last.
Tuesday, October 14,2003 10:39:06A M 58
QUESTIONS REPORT
for NRC Reviewed RO BANK
EOP-6, Step 3.33
RO - Direct
References provided: EOP-6
Rev. 0 to NRC on 4-1 1-03
Rev. 1 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B C D A B C D A B C ScrambleRange: A - D
Tier: 1 Group: 1
Keyword: RO #I 1 Cog Level: C/A 3.814.4
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:06 AM 59
QUESTIONS REPORT
for NRC Reviewed RO BANK
37. 039A2.05 002
The reactor has just been taken critical when an atmospheric dump valve fails open.
Which of the following describes what will happen to Tave and nuclear power and what
operator actions should be taken?
A. Tave will rise; final power will be at the point of adding heat (POAH). The ADV
should be closed and rods inserted to restore Tave.
B. Tave will rise; final power will exceed the POAH. The ADV should be closed and
secondary parameters used to restore Tave.
C. Tave will lower; final power will be at the POAH. The ADV should be closed and
rods withdrawn to restore Tave.
D. * Tave will lower; final power will exceed the POAH. The ADV should be closed
and secondary parameters used to restore Tave.
Reasons:
A. The steam leak will cause RCS temperature to decrease; the size of the
steam leak should approximate the final power level.
B. The steam leak will cause RCS temperature to decrease.
C. The size of the steam leak should approximate the final power level. Rods
should not be withdrawn to restore Tave.
D. Correct. Tave will lower and the positive reactivity addition will increase
reactor power to approximately the size of the steam leak.
OPS 3-22 Section 3-2.0.C and 3-5.0.G
NRC 6-97
RO - Direct
References provided: None
Rev. 0 to NRC on 4-1 1-03
Rev. 1 to NRC on 6-1 7-03
Tuesday, October 14,2003 10:3906AM 60
QUESTIONS REPORT
for NRC Reviewed RO BANK
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D A B C D A B C D A Scramble Range: A - D
Tier: 2 Group: 1
Keyword RO #43 Cog Level: MEM 3.313.6
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14.2003 10:39:06AM 61
QUESTIONS REPORT
for NRC Reviewed RO BANK
38. 039K3.04 002
The plant is currently at 95% power and decreasing power due to an unisolable steam leak two
feet downstream of MSV-53, MN STM to FWP & TURB BP, STM GEN A ISOL. What
effect, if any, will closing this valve have on the "A" MFWP?
When reactor power decreases to = 80% the:
A. swap to reheat steam can occur as normal.
B. . swap to auxiliary steam can occur as normal.
C. MFWP will trip since the swap to main steam cannot occur.
D. MFWP will trip since the swap to auxiliary steam cannot occur.
Reasons:
A. The MFWPs use reheat steam from about 80% to 100% power.
B. Correct. At about 80% power the auxiliary steam supply will come from
MSV-179, not MSV-53.
C. & D. The normal steam supply from 80% down is auxiliary steam supplied
by main steam. The transfer can occur as it normally does.
OPS 4-66 Section 1-2.0.B.2, OPS 4-67 Section 2-3.0
RO - New
References provided: None
Rev. 0 to NRC on 4-22-03
Rev. 1 to NRC on 6-17-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B B B B B B B B B B Items Not Scrambled
Tier: 2 Group: 1
Keyword RO #42 Cog Level: MEM 2.512.6
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:06 AM 62
QUESTIONS REPORT
for NRC Reviewed RO BANK
39. 041A2.02 001
With the plant at full power the following conditions exist:
- The AULD is 00s.
- Tave has decreased about 2" F.
- Reactor power has increased about 3%.
Which of the following failures could have caused these conditions and what would be the
appropriate action to take?
A. A MSSV has failed open. The associated MSIV should be closed.
B. A MSSV has failed open. The associated isolation valve should be closed.
C. A TBV has failed open. The associated MSIV should be closed.
D. * A TBV has failed open. The associated isolation valve should be closed.
Reasons:
A. The MSIVs are downstream of the MSSVs.
B. There are no individual isolation valves on the MSSVs.
C. While closing the MSIV will isolate the TBV this is not the appropriate
action to take, especially at full power.
D. Correct. The TBVs have individual isolation valves that can be closed.
AI-505 Step 4.14.1.b
RO - New
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D D D D D D D D D D Items Not Scrambled
Tier: 2 Group: 2
Keyword: RO #62 Cog Level: CIA 3.613.9
Source: N Exam: CR03301
Tesl: R Misc: ATK
Tuesday, October 14, 2003 10:39:06 AM 63
QUESTIONS REPORT
for NRC Reviewed RO BANK
40.045K3.01 002
The following plant conditions exist:
- A reactorhrbine trip has occurred.
- The turbine governor valves indicate "CLOSED".
- The turbine throttle valves indicate "OPEN".
- "B" OTSG has developed a small steam leak and pressure is steady at
approximately 800 psig.
The "A" OTSG pressure should stabilize at approximately:
A. * 800 psig.
B. 885 psig.
C. 1010 psig.
D. 1025 psig.
Reasons:
A. Correct. With the TVs open there is a direct path from one OTSG, through
the turbine, to the other OTSG.
B. Normal header pressure. With the OTSGs cross-connected both OTSG's
pressure should be approximately equal.
C. This is the normal post trip pressure if the TBVs are controlling pressure
D. This is the normal post trip pressure if the ADVs are controlling pressure.
OPS 4-66 Section 1-8.0.C; OPS 5-96 Section 1-2.0.E
RO - Direct [Newops ROT 4-66 0321
References provided: None
Rev. 0 to NRC on 4-1 1-03
Rev. 1 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A D B B B B A B A C Scramble Range: A - D
Tuesday, October 14, 2003 10:39:06AM 64
QUESTIONS REPORT
for NRC Reviewed RO BANK
Tier: 2 Group: 2
Keyword: RO #63 Cog Level: CIA 2.913.2
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,200310:39:06AM 65
QUESTIONS REPORT
for NRC Reviewed RO BANK
41.054AA1.02 001
The following plant conditions exist:
- A LOOP has occurred with the plant previously at 40% power.
- EFP-2 did not start.
- EFP-3 has a red light on the control handle but no flow is indicated.
Which of the following "prompt and prudent" actions should be taken?
Attempt to:
A. start EFP-I.
B. start FWP-7.
C. open MSV-55 and/or MSV-56 (EFP-2 steam isolation valves).
D. * open ASV-5 and/or ASV-204 (EFP-2 steam control valves).
Reasons:
A. & B. These actions would not be taken without prodedural guidance.
C. MSV-55 & 56 are normally open valves. There is no automatic
closure signal to these valves.
D. Correct. Prompt and prudent actions may be taken for failure of an
automatic system to respond correctly. If ASV-5 didn't open
automatically then it or its sister valve, ASV-204, should be manually
selected to open.
AI-505 Step 4.1.4.b; OPS 4-31 Section 1-2.O.D.2.a)
RO - New
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D D D D D D D D D D Items Not Scrambled
Tier: 1 Group: 1
Keyword RO #I3 Cog Level: MEM 4.414.4
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:06 AM 66
QUESTIONS REPORT
for NRC Reviewed RO BANK
42. 055EK3.02 001
Step 3.4 of EOP-12 Station Blackout directs the operator to:
"Actuate MSLI on both OTSGs."
Which of the following describes the reason for this step?
A. + Limit cooldown to aid in maintaining RCS inventory.
B. To prevent OTSG dryout due to the loss of Main Feedwater.
C. To ensure OTSGs are isolated due to the loss of power to automatic Main Steam
Line Isolation logic.
D. To maintain greater than 100 psig in the OTSGs due to the loss of turbine bypass
valve control.
Reasons:
A. Correct. This step aids in reducing or limiting the RCS cooldown thereby
maintaining RCS inventory since no RCS makeup is available.
B. OTSGs will not dryout due to feeding from EFP-2 or 3
C. Power is still available from EFIC for MSLI
D. Turbine bypass valves are not used due to the loss of all circulating water
pumps and isolating the OTSGs, in this case, has nothing to due with
maintaining OTSG pressure.
EOP-12 Step 3.4; OPS 5-100 Section 1-4.0.F
RO - Direct [Newops 5-100-0041
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A B C D A B C D A B Scramble Range: A - D
Tier: 1 Group: 1
Keyword RO #I4 Cog Level: MEM 4.314.6
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:06 AM 67
QUESTIONS REPORT
for NRC Reviewed RO BANK
43.056AG2.1.02 001
The following plant conditions exist:
- A LOOP has occurred.
- AEDG did not start due to an electrical lockout.
- BEDG initially started and loaded on the bus and then the output breaker tripped open for
no apparent reason. The EDG engine remained at 900 rpm.
Which of the following describes the electrical lockouts, at a minimum, which must be reset if
both EDGs are to be loaded on the ES buses?
A. * AEDG - 86DG, generator differential current lockout relay
BEDG - 86B, lockout relay
B. AEDG - 4160V undervoltage lockout relay
BEDG - 4160V undervoltage lockout relay
C. AEDG - 86B, lockout relay
BEDG - 86DG, generator differential current lockout relay
D. AEDG - 86DG, generator differential current lockout relay
BEDG - 86DG, generator differential current lockout relay
Reasons:
B. The AEDG undervoltage lockout will not prevent the engine from
starting. The BEDG undervoltage lockout will not open breaker 3210.
C. The AEDG 86B lockout will not prevent the engine from starting. The B
EDG engine would have shutdown if this lockout actuated.
D. The BEDG engine would have shutdown if this lockout actuated.
OPS 4-06 Section 1-4.0.M; OPS 4-90 Section 1-4.0-F; AP-770
NRCN99
RO - Direct [Newops 4-90-0011
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A B C D A B C D A B Scramble Range: A - D
Tuesday, October 14,2003 10:3906 AM 68
QUESTIONS REPORT
for NRC Reviewed RO BANK
Tier: 1 Group: I
Keyword RO #I 5 Cog Level: C/A 3.0/4.0
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:06AM 69
QUESTIONS REPORT
for NRC Reviewed RO BANK
44.056K1.03 001
Which of the following describes the direct signal that decreases condensate flow demand on a
loss of one MFW pump at 80% power?
A. A signal from the DFT high level interlock.
B. A runback signal from the ULD sub-section of the ICs.
C. A signal that compares existing CD flow with FW flow and HW level.
D. +. A signal that compares existing CD flow with FW flow and DFT level.
Reasons:
A. This interlock will trip all running CDPs, not lower CD demand.
B. A runback will be in effect however there is no direct signal to condensate
to lower demand.
C. FW flow and CD flow are compared to modifiy condensate demand. Hotwell
level will increase but this will only modify the position of CDV-88, not
actual CD demand.
D. Correct. CD demand is directly modified by actual FW flow and DFT level.
OPS 4-69 Section 1-4.O.B.5.f
NRCN99
RO - Direct
References provided: None
Rev. 0 to NRC on 4-1 1-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D A B C D A B C D A Scramble Range: A - D
Tier: 2 Group: 1
Keyword: RO #44 Cog Level: MEM 2.612.6
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:06AM 70
QUESTIONS REPORT
for NRC Reviewed RO BANK
45.058AA2.02 002
The plant has been in a Station Blackout for approximately three hours when Annunciator
P-4-1, Inverter A Failure, comes into alarm. Which of the following is the reason for this
alarm?
A. The inverter has lost its AC power supply due to failure of the static transfer switch
and its DC power supply due to battery depletion.
B. The inverter has lost its AC power supply due to the Station Blackout and its DC
power supply when the static transfer switch failed.
C. * The inverter has lost its AC power supply due to the Station Blackout and its DC
power supply due to battery depletion.
D. The inverter has lost its AC power supply and DC power supply due to a static
transfer switch failure.
Reasons:
A. The static transfer switch is located on the output of the inverter to the
VBDPs. There is no static switch for the supply to the inverter.
B. There is a single DC power supply to the inverter. The static switch is on
the inverter output.
C. Correct. The SBO has de-energized the AC input to the inverter. Battery
depletion has lowered the battery output to < 105 VDC.
D. Static transfer switches are only on the output of the inverters, not the
inputs.
OPS 4-64 Section 1-4.0.C.3; AR-701 EP 0159
RO - Direct [Opsbank ROT 4-64-0181
References provided: None
Rev. 0 to NRC on 5-9-03
Rev. 1 to NRC on 6-17-03
Tuesday, October 14, 2003 10:39:07 AM 71
QUESTIONS REPORT
for NRC Reviewed RO BANK
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C D A B C D A B C D Scramble Range: A - D
Tier: 1 Group: 1
Keyword RO #16 Cog Level: MEM 3.3/3.6
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:07 AM 72
QUESTIONS REPORT
for NRC Reviewed RO BANK
46. 059A4.10 001
The following plant conditions exist:
- Plant is operating = 20% power.
- SUCV position = 95% open.
- LLCV position = 5% open.
I & C technicians have requested that the 'B' train SUCV and LLCV H/A stations be taken to
hand in order to record some data on the proportionalhntegral module supplying the input to
these stations. Permission is received and these stations are placed in manual. After the
technicians are finished, with no problems noted, preparations are made to return these stations
to automatic.
Which of the following describes the appropriate actions to return these stations to automatic?
A. Place the SUCV in auto first, then place the LLCV in auto.
B. * Place the LLCV in auto first, then place the SUCV in auto.
C. Open the SUCV to 100% to allow the LLCV full control. Place the LLCV in auto
first and then the SUCV.
D. Close the LLCV to allow the SUCV full control. Place the SUCV in auto first and
then the LLCV.
Reasons:
A. The LLBV must be open at this point. The SUCV cannot be placed in
automatic first if the LLBV is open.
C. The SUCV and LLCV are operating as designed. The operator should not
manipulate control valve position unnecessarily.
D. The SUCV and LLCV are operating as designed. The operator should not
manipulate control valve position unnecessarily. The SUCV cannot be
placed in automatic first if the LLBV is open.
Tuesday, October 14,2003 10:39:07 AM 73
QUESTIONS REPORT
for NRC Reviewed RO BANK
OP-504 Section 4.4; OPS 4-14 Section 1-4.O.H.13.d.2
NRCN99
RO - Direct [Newops 4-014-0101
References provided: None
Rev. 0 to NRC on 4-1 1-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B C D A B C D A B C Scramble Range: A - D
Tier: 2 Group: 1
Keyword RO#45 Cog Level: C/A 3.9/3.8
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:07AM 74
QUESTIONS REPORT
for NRC Reviewed RO BANK
47. 05962.122 001
Based on the following plant conditions:
- FWV-28 (Feedwater Cross Connect) - OPEN
- "B" Main Feedwater Pump (FWP-2B) - TRIPPED
- "A" Startup Control Valve's Differential Pressure - 85 psig
- "B" Startup Control Valve's Differential Pressure - 75 psig
Which of the following statements describes the "A" Main Feedwater Pump (FWP-2A) control
mode?
A. Lowest loop FW flow error.
B. Individual loop FW flow error.
C. Delta Pressure across the "A" loop control valves.
D. Delta Pressure across the "B" loop control valves.
Reasons:
A.,B.,C.,&D. With FWV-28 open the MBVs are closed. Both FWPs shift to
delta P control when the MBVs are closed. If a MFWP is
tripped then the logic shifts to lowest loop delta pressure
control.
OPS 4-14Section 1-4.0.H.13
RO - Direct
References provided None
Rev. 0 to NRC on 4-11-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D A C C A C A D D B Scramble Range: A - D
Tier: 2 Group: 1
Keyword: RO #46 Cog Level: MEM 2.813.3
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:07 AM 75
QUESTIONS REPORT
for NRC Reviewed RO BANK
48. 061K2.01 001
A maintenance worker inadvertently hits the power supply wiring for EFV-57, EFP-3 to B'
OTSG control valve, pulling the wire out of the valve body. The control room is immediately
notified and a decision is made to isolate this EFW line and ensure it cannot feed if an EFIC
actuation were to occur.
Which of the following action(s), if any, could be taken to ensure this line is isolated?
A. No action is necessary. EFV-57 has failed closed due to the loss of power.
B. Select manual and closed at EFV-57's control station and select closed EFV-33,
block valve for EFV-57, on the main control board.
C. Select closed EFV-33, block valve for EFV-57, at the control board and de-energize
its power supply at DPDP-8C.
D.' Select closed EFV-33, block valve for EFV-57, at the control board and de-energize
its power supply at DPDP-8D.
Reasons:
A. EFV-57 fails open on a loss of power.
B. EFV-57 fails open on a loss of power. EFV-33 will get an open signal if an
EFIC actuation occurs.
C. EFV-33 is powered from DPDP-8D ("B" train power supply), not DPDP-8C.
D. Correct. EFV-33 is powered from DPDP-8D.
OPS 4-37 Obj. 3; OPS 4-31 Section 1-4.D.l.c, OPS 4-37 Sections 1-4.H.1,2,3,4 and 1-4.1.1,2
NRCM98
RO - Direct
References provided: None
Rev. 0 to NRC on 4-1 1-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D A B C D A B C D A Scramble Range: A - D
Tuesday, October 14,2003 10:39:07 AM 76
QUESTIONS REPORT
for NRC Reviewed RO BANK
Tier: 2 Group: 1
Keyword: RO #41 Cog Level: CIA 3.213.3
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:07 AM 77
QUESTIONS REPORT
for NRC Reviewed RO BANK
49. 062AK3.02 001
The following plant conditions exist:
- RWP-1 is in operation.
SP-354B, Monthly Test of EDG-lB, is in progress with the diesel paralleled
to the bus.
A steam leak occurs in the RB and pressure increases to 5 psig.
Which of the following describes the response of the RW system?
A. RWP-1 trips due to an ES trip command.
B. RWP-2A starts on low RW pressure due to the loss of RWP-I.
C. RWP-2B starts on low RW pressure due to the loss of RWP-1.
D.* RWP-3A starts due to an ES start command.
Reasons:
A. RWP-1 will trip after an ES signal is generated but not from an ES trip
command.
B. RWP-2A will receive an ES start signal but does not start because of the
low pressure.
C. RWP-2B will start on low pressure except when EDG breaker 3210 is
closed. RWP-2B will receive an ES start signal.
D. Correct. RWP-3A will start when it receives an ES start command.
OPS 4-57 Sections 1-4.0.B &. C
RO - New
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D D D D D D D D D D Items Not Scrambled
Tier: 1 Group: 1
Keyword: RO #17 Cog Level: CIA 3.613.9
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:07 AM 78
QUESTIONS REPORT
for NRC Reviewed RO BANK
50. 06262.1.33 001
With RCS temperature at 190" F which of the following conditions would require entry into a
Technical Specification?
A. VBDP-7 is aligned to its alternate AC power supply.
B. +. Total stored EDG lube oil inventory of 260 gallons.
C. The Offsite Power Transformer is 0 0 s due to an oil leak.
D. "A" EDG is 00s due to a turbo charger failure.
Reasons:
A. VBDP-7 is a non-safety related vital bus.
B. Correct. Per TS 3.8.3 > 280 gallons is required.
C. At 190" F the plant is in Mode 5 and only one offsite circuit is required.
D. At 190" F the plant is in Mode 5 and only one EDG is required to be
TS 3.8.2 and 3.8.3
RO - New
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer: B B B B B B B B B B items Not Scrambled
Tier: 2 Group: 1
Keyword: RO #49 Cog Level: CIA 3.414.0
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:07 AM 79
QUESTIONS REPORT
for NRC Reviewed RO BANK
51. 062K3.01 001
The following plant conditions exist:
- A Loss of Offsite Power has occurred.
- RB pressure is 32 psig.
- RCS pressure 900 psig.
- Adequate subcooling margin does exist.
- A 480V overcurrent lockout has occurred on breaker 3310 (feeder breaker for
the B'ES bus).
Which of the following describes all running equipment that must be secured because of these
conditions? (assume all components have sequenced on as designed)
A. BSP-lB, MUP-1C and RWP-3B.
B. RWP-2B and RWP-3B.
C. BSP-lB, MUP-1B and RWP-3B.
D. DHP-IB, MUP-IC, BSP-IB and RWP-3B
Reasons:
A. Correct. The overcurrent lockout on the "B" bus will keep the EDG from
powering up the bus and all "B" train 480 volt loads will be lost. However
this does not stop the "B" train 4160 volt loads from starting. DCP-IB is a
480 volt load and should provide cooling water for BSP-lB, MUP-IC and
RWP-3B.
B. RWP3B is cooled by SW and should be left running.
C. MUP-1B is cooled by SW and should be left running.
D. DHP-1B will not be running for these conditions.
Tuesday, October 14,2003 10:39:07AM 80
QUESTIONS REPORT
for NRC Reviewed RO BANK
OPS 4-55 Figure I , OPS 4-13 Table 11, OPS 4-90 Section 1-4.O.I.5.b; OP-700A Enclosure 9
NRCN99
RO - Direct
References provided: None
Rev. 0 to NRC on 4-1 1-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A B C D A B C D A 3 Scramble Range: A - D
Tier: 2 Group: 1
Keyword: RO #48 Cog Level: CIA 3.513.9
Source: B Exam: CR03301
Test: R Mix: ATK
Tuesday, October 14,2003 10:39:07 AM 81
QUESTIONS REPORT
for NRC Reviewed RO BANK
52. 063A3.01 001
The following readings were taken on the "A" battery charger following a BATTERY A
DISCHARGE HIGH alarm in the control room:
- 120 volts
- 75 amps
Shortly after these readings were taken the amp meter increases to 360 amps.
Which of the following action(s) will occur following this increase?
A. The "A" and "C" inverter will trip.
B. * The "A" battery charger will trip and the battery will supply bus loads.
C. The "A"and "C" inverter will not trip but will swap to the AC input.
D. The "A" battery charger will trip and the "C" battery charger will automatically be
placed in service.
Reasons:
A. There may be problems with the inverters but they should not trip.
B. Correct. The battery charger will trip at 350 amps.
C. There may be problems with the inverters but they should not trip. The
inverter is normally supplied from its AC source.
D. The "A"charger will trip but the "C" charger does not have any automatic
closing feature.
OPS 4-64 Section 1-4.0.B; AR-701 EP 169 & 1945; OP-705 Step 3.1.7
NRCCP97; NRCM98
RO - Direct [Newops ROT-4-64-0241
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer: B C D A B C D A B C Scramble Range: A - D
Tuesday, October 14,2003 10:39:07AM 82
QUESTIONS REPORT
for NRC Reviewed RO BANK
Tier: 2 Group: 1
Keyword: RO #SO Cog Level: CIA2.713.1
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:07 AM 83
QUESTIONS REPORT
for NRC Reviewed RO BANK
53. 064A2.08 002
SP-354A, Monthly Functional Test of EDG-lA, is in progress.
4160 volts 4190 volts
60 hz 60 hz
Based on these conditions which of the following indications are expected when the EDG-1A
output breaker is closed and what action should be taken?
There will be:
A. * VARS out. Excitation voltage should be decreased.
B. VARS out. Excitation voltage should be increased.
C. VARS in. Excitation voltage should be decreased.
D. VARS in. Excitation voltage should be increased.
Reasons:
A. Correct. With the EDG voltage higher than the bus voltage the EDG will
pick up reactive load (VARS out). Excitation voltage should be decreased to
lower VARS out.
B. Excitation voltage should be decreased.
C. VARS will be out.
D. VARS will be out and voltage should be decreased.
OPS 4-06 Sections 1-4.0.L.6 & 1-4.O.B.2.d
-
RO NEW
References provided: None
Rev. 0 to NRC on 4-22-03
Rev. 1 - KFO fixed
Tuesday, October 14, 2003 10:39:07 AM a4
QUESTIONS REPORT
for NRC Reviewed RO BANK
MCS Time: I Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer: A A A A A A A A A A Items Not Scrambled
Tier: 2 Group: 1
Keyword RO #5 1 Cog Level: CIA 2713.1
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:07 AM 85
QUESTIONS REPORT
for NRC Reviewed RO BANK
54. 06962.1.33 001
With the plant at full power which of the following conditions would require entry into a
Technical Specification LCO?
A. EFP-1 has excessive packing leakage. EFP-2 & 3 are operable.
B. AHF-IC motor bearing has seized. AHF-1A & 1B are operable.
C. MUP-1A has a large oil cooler leak. MUP-1B & 1C are operable.
D. * AHV-1A leakage is outside its limit. AHV-lB, 1C & 1D are operable.
Answers:
A. EFP-1 is not required to be operable for TS.
B. Only two of the three fans are required to be operable per TS.
C. Only two of the three MUPs are required to be operable per TS.
D. Correct. All four valves are required to be operable.
RO - New
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D D D D D D D D D D Items Not Scrambled
Tier: 1 Group: 2
Keyword RO #23 Cog Level: MEM 3.414.0
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:07AM 86
QUESTIONS REPORT
for NRC Reviewed RO BANK
55.071K3.04 001
A small leak has just occurred in the Waste Gas Decay Tank area. Which of the following
describes thefirst radiation monitor that should detect this leak and the automatic actuations
that should occur?
A. RM-A4; trips AHF-10
B. d. RM-A3; trips AHF-1 lA/B and closes AHD-29 & 36.
C. RM-A3; trips AHF-1 I N B , closes WDV-393, 394, & 395 (recycle isolation valves)
and closes WDV-439 (common waste gas isolation).
D. RM-A1 1; closes WDV-393,394, & 395 (recycle isolation valves) and closes
WDV-439 (common waste gas isolation).
Reasons:
A. If RM-A4 trips then this action would occur. However RM-A3 will detect
the gas leak first.
B. Correct. RM-A3 monitors the WGDT area. This monitor should detect a
leak first and initiate automatic actions.
C. If RM-A3 trips it will not close the recycle valves or the common waste gas
isolation valve.
D. If RM-A1 1 trips then these actions would occur. RM-A1 1 is not in service
unless a waste gas release is in progress and will only trip if the preset
release values are exceeded.
OPS 4-25 1-4.O.F.5.d)
RO - Direct [Newops ROT-4-25-0631
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B C D A B C D A B C Scramble Range: A - D
Tier: 2 Group: 2
Keyword RO #64 Cog Level: MEM 2.712.9
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:07AM 87
QUESTIONS REPORT
for NRC Reviewed RO BANK
56. 076A2.02 001
The following plant conditions exist:
- SWP-lA, RWP-2A and MUP-1B are running.
- Computer points for three CRDM stators have reached their "Hi Warning"
setpoint of 113°F and are slowly trending up.
- MUP-1B lube oil temperature is slowly trending up.
- RWP-2A discharge is currently 56 psig and has increased 4 psig over the
last four hours.
- Spent Fuel pool level has increased 1 inch over the last four hours.
Which of the following could cause these indications and what actions should be taken?
A. Enter AP-330, Loss of Nuclear Service Cooling, ensure both SW Booster pumps
are running and place the spare CRDM filter in scrvicc. The on-line CRDM filter is
clogged.
B. Use OP-408, Nuclear Services Cooling System, and isolate SW flow to the Spent
Fuel coolers. The leak has caused decreased SW flow to other components.
C. Enter AP-330, Loss of Nuclear Service Cooling, place the standby SWHE in
service and remove the fouled one. At least one of the in service SWHEs is
excessively fouled.
D. Use OP-408, Nuclear Services Cooling System, and close the discharge valves on
RWP-1 and RWP-2B. Backflow through the standby RWPs has decreased RW
flow.
Reasons:
A. This action is only taken when the CRDMs are the only components
exhibiting increased temperatures.
B. An SW leak could cause the SF pool level increase but would not cause RWP
discharge pressure decrease. Entry conditions for AP-330 are met.
C. Correct. This is the only failure that could cause all of the conditions given
in the stem.
D. Conditions are met for entering AP-330. The AP does not have the operator
check for back flow unless RWP discharge pressure decreases to 48 psig.
Tuesday, October 14,2003 10:39:07 AM 88
QUESTIONS REPORT
for NRC Reviewed RO BANK
AP-330 Step 3.10
RO - New
References provided: AP-330
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C C C C C C C C C C Items Not Scrambled
Tier: 2 Group: 1
Keyword RO #53 Cog Level: CIA 2.7/3.1
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:07AM 89
QUESTIONS REPORT
for NRC Reviewed RO BANK
57. 078K2.01 001
With IAP3C running as the Lead compressor, I A P J B running as the First Lag and IAP-3A
running as the Second Lag compressor the power supply to the compressor motors should be
as follows:
A. IAP-3A powered from 480V Rx Aux Bus 3A
IAP-3B powered from 480V Rx Aux Bus 3B
IAP-3C powered from the 12kV line
B. * IAP-3A powered from 480V Rx Aux Bus 3A
IAP-3B powered from the 12kV line
IAP-3C powered from 480V Rx Aux Bus 3B
C. IAP-3A powered from the 12kV line
IAP-3B powered from 480V Rx Aux Bus 3A
IAP-3C powered from 480V Rx Aux Bus 3B
D. IAP-3A powered from 480V Rx Aux Bus 3B
IAP-3B powered from 480V Rx Aux Bus 3A
IAP-3C powered from the 12kV line
Reasons:
When IAP-3B or IAP-3C are selected as the Lead compressor OP-411 recommends that they
be powered from the 480V Rx Aux Bus 3B. Since both cannot be powered from the same
source, due to the MTSW-5 dual transfer switch characteristics, the remaining compressor will
be powered from the 12kV line. Also IAP-3B and IAP-3C cannot be powered from 480V Rx
Aux Bus 3A.
A. IAP-IC should be powered from Rx Aux Bus 3B.
B. Correct. Lineup is as recommened in OP-411.
C. IAP-3B cannot be powered from Rx Aux Bus 3A.
D. With IAP-3C being the lead compressor it should be powered from Rx Aux
Bus 3B.
Tuesday, October 14, 2003 10:39:07 AM 90
QUESTIONS REPORT
for NRC Reviewed RO BANK
OP-411 Steps 4.2.1.3 and 4.2.3
RO - Direct [Newops 4-081-0011
References provided: None
Rev. 0 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B C D A B C D A B C Scramble Range: A - D
Tier: 2 Group: 1
Keyword: RO #54 Cog Level: MEM 2.7/2.9
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:07AM 91
QUESTIONS REPORT
for NRC Reviewed RO BANK
58. 086A4.06 001
The Halon system has actuated. Multiple cable spreading room smoke detectors still detect
smoke. What operator actions must be taken, if any, to ensure both banks of Halon have
discharged?
A. ./ The operator must select the alternate Halon bank.
B. The operator must select the alternate Halon bank and actuate the pull station
located in the control room.
C. No additional operator actions are required. Both banks will automatically
discharge to ensure a Halon concentration of at least 5%.
D. No additional operator actions are required. After the selected bank discharges a
preset timer will start. Once this time has elapsed, and smoke is still detected by at
least one detector in each zone, the other bank will automatically discharge.
Reasons:
A. Correct. Since multiple detectors still sense smoke the only required action
by the operator is to select the alternate bank.
B. Actuation of the pull station is not required.
C. Only the selected bank will discharge.
D. Only the selected bank will discharge.
OPS 4-07 Section 1-4.0.P
RO - New
References provided: None
Rev. 0 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A A A A A A A A A A Items Not Scrambled
Tier: 2 Group: 2
Keyword: RO #65 Cog Level: MEM 3.2/3.2
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:07AM 92
QUESTIONS REPORT
for NRC Reviewed RO BANK
59. 103A3.01 001
The following plant conditions exist:
- A small break LOCA has occurred in the RB.
- RB pressure is 4.6 psig.
- ES status lights are as indicated.
Component Light Component Light
AHV- 1A AMBER swv-79 GREEN
AHV- 1B AMBER SWV-80 GREEN
AHV- 1C AMBER SWV-81 GREEN
AHV- 1D AMBER SWV-82 GREEN
LRV-70 GREEN SWV-83 GREEN
LRV-7 1 GREEN SWV-84 GREEN
LRV-72 GREEN SWV-85 GREEN
LRV-73 GREEN SWV-86 GREEN
Based on the above conditions which of the following describes the status of these containment
isolation valves?
The AH valves are indicating:
A. open and should be closed; all other components are in their expected position.
B. closed and should be open; all other components are in their expected position.
C.* open and should be closed; the SW valves are indicating closed and they should be
open.
D. closed and should be open; the SW valves are indicating open and they should be
c1osed .
Tuesday, October 14,2003 10:39:07 AM 93
QUESTIONS REPORT
for NRC Reviewed RO BANK
Reasons:
A. The SW valves should be open.
B. The AH valves are indicating open and should be closed and the SW valves
are indicating closed and should be open.
C. Correct. RBIC should close all the AHVs but not the SWVs unless there is
also a low SW surge tank level.
D. The AH valves are indicating open and should be closed and the SW valves
are indicating closed and should be open.
OPS 4-13 Section 1-4.E.8.e & Table 6
RO - New
References provided: None
Rev. 0 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C D A B C B D A B A Scramble Range: A - D
Tier: 2 Group: 1
Keyword RO #55 Cog Level: C/A 3.914.2
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:08AM 94
QUESTIONS REPORT
for NRC Reviewed RO BANK
60.BWAOlAA2.02 001
The following plant conditions exist:
- Plant is at 70% power.
- MFW Booster pump 1A suction valve receives a false signal and strokes 10% in the
closed direction and then stops.
Which of the following describes the required operator actions for this condition?
A. * Ensure plant runback to 52% power.
B. Manually trip one MFWP and ensure plant runback to 52% power.
C. Reduce power to 45% and manually trip MFW Booster pump 1A.
D. There will be sufficient flow through the valve since it is still 90% open.
Troubleshooting efforts should be initiated immediately.
Reasons:
A. Correct. The "A" MFWBP trips when its suction valve leaves its open seat.
B. The plant must be above 75% power before the requirement to trip a
MFWP is in effect.
C. For this combination of pumps the plant may remain at 52%. The MFWBP
would have automatically tripped as soon as the suction valve left its
full open position.
D. The MFWBP would have automatically tripped as soon as the suction valve
left its full open position.
OPS 4-14 Section 1-4.O.F.4.e; OPS 4-14 Obj 3; AP-545 Step 3.20; OPS 4-68 Section 1-4.0.B
NRCN99
RO - Direct
References provided: None
Rev. 0 to NRC on 4-1 1-03
Tuesday, October 14. 2003 10:39:08AM 95
QUESTIONS REPORT
for NRC Reviewed RO BANK
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 X 9
Answer: A B C D A B C D A B Scramble Range: A - D
Tier: 1 Group: 2
Keyword: RO #24 Cog Level: CIA 3 3 3 . 8
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:3908AM 96
QUESTIONS REPORT
for NRC Reviewed RO BANK
61. BWA04AA1.01 002
The following plant conditions exist:
- The plant is at 15% power.
- The turbine is latched.
- The "A" MFWP is on turning gear.
- Condenser vacuum has just decreased to 5 in/HgA coincident with a loss
of the "B" MFWP.
Which of the following describes the operator's immediate actions and the expected plant
response?
A. * Ensure the turbine is tripped. TBVs will control steam pressure at 885 psig.
B. Ensure the reactor and turbine are tripped. TBVs will control steam pressure at 885
psig.
C. Ensure the turbine is tripped. Due to the low condenser vacuum the ADVs will
control steam pressure at 1025 psig.
D. Ensure the reactor and turbine are tripped. Due to the low condenser vacuum the
ADVs will control steam pressure at 1025 psig.
Reasons:
A. Correct. Below 20% power the reactor should not be tripped due to the loss
of both MFWPs. Since the reactor is not tripped the 125# bias is not
applied and pressure should be maintained at 885# by the TBVs.
B. The reactor should not be tripped.
C. The vacuum setpoint for auto-closure of the TBVs 5 in/Hg vacuum.
D. The reactor should not be tripped and the vacuum setpoint for auto-closure
of the TBVs 5 idHg vacuum.
Tuesday, October 14,2003 10:39:08AM 97
QUESTIONS REPORT
for NRC Reviewed RO BANK
OPS 4-22 Sections 1-4.0.S.4 & 1-4.0.S.7.c).3)
RO - New
References provided: None
Rev. 1 to NRC on 7-29-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A A A A A A A A A A Items Not Scrambled
Tier: 1 Group: 2
Keyword: RO #25 Cog Level: CIA 3.5133
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:08 AM 98
QUESTIONS REPORT
for NRC Reviewed RO BANK
62. BWA07AK1.02 002
The plant is at 70% power with the following maintenance activities in progress:
- "B" SCHE shoot and clean activities.
- "B" CWP breaker investigation (breaker tripped open for no apparent reason).
The "Cond. Pump Pit Sump Level High" alarm has just annunciated in conjunction with the
SPO reporting water coming out of the SCHE and that CWV-5, "B" SCHE inlet valve from
CWP-ID, has failed partially open. Water level in the CDP pit is about 1'and rising slowly.
Based on these conditions which of the following actions are required?
A. Trip the reactor and transition to EOP-02; then stop all CWPs.
B. Trip the reactor and transition to EOP-02; then stop CWP-ID.
C. * Concurrently perform AP-510; when reactor power is < 60% stop CWP-1D.
D. Concurrently perform AP-510; when reactor power is < 45% trip the turbine; stop
CWP-1D and transition to AP-660.
Reasons:
A. The reactor does not need to be tripped and only the affectected CWP
should be stopped.
B. The reactor does not need to be tripped.
C. Correct. Since the affected CWP is in a hotwell that has another CWP
running then power only needs to be reduced to < 60% and the pump
stopped.
D. If the affected CWP was in a hotwell with only 1 CWP running then power
would have to be reduced to <45% and the turbine tripped.
Tuesday, October 14, 2003 10:39:08 AM 99
QUESTIONS REPORT
for NRC Reviewed RO BANK
AP-1050 Step 3.7
RO - New
References provided: AP-1050
Rev. 0 to NRC on 4-1 1-03
Rev. 1 to NRC on 7-29-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C A D B B D C B B D Scramble Range: A - D
Tier: 1 Group: 2
Keyword: RO #26 Cog Level: CIA 3.313.7
Source: N Exam: CR03301
Test: R Mix: ATK
Tuesday, October 14,2003 10:39:08 AM 100
QUESTIONS REPORT
for NRC Reviewed RO BANK
63. BWE04EK1.03 001
The following plant conditions exist:
- An Inadequate Heat Transfer event is in progress due to a loss of Main and
Emergency Feedwater.
- HPI/PORV cooling has been established in accordance with EOP-4, Inadequate Heat
Transfer.
- The Subcooling Margin Monitor now indicates -7 SC.
- AFW restoration is expected.
- OTSG integrity does exist.
Based on these conditions which of the following describes the actions that should be taken?
A. Remain in EOP-4, Inadequate Heat Transfer.
B. Transition to EOP-3, Inadequate Subcooling Margin.
C. Transition to EOP-7, Inadequate Core Cooling.
D. Transition to EOP-8, LOCA Cooldown.
Reasons:
A. Correct. If SCM is lost as a result of HPUPORV cooling then you should
remain in EOP-4.
B. Normally you would transition to EOP-3 on a loss of SCM except for this
particular condition that requires remaining in EOP-4.
C. If superheat conditions were indicated then transition to EOP-7 would be
correct.
D. If OTSG heat transfer restoration was not expected then transition to
EOP-8 would be correct.
EOP-4 Step 3.19
RO - New
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A A B D A A C D B B Scramble Range: A - D
Tuesday, October 14,2003 10:3908 AM 101
QUESTIONS REPORT
for NRC Reviewed RO BANK
Tier: 1 Group: 1
Keyword RO #I 8 Cog Level: C/A 4.0/4.0
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:08 AM 102
QUESTIONS REPORT
for NRC Reviewed RO BANK
64.BWE05EA1.02 002
The plant has just experienced a spurious reactor trip from 100% full power. Due to control
signal interference the output voltage signal from the high select module associated with
NI-5/6 remains at 100% reactor power. Select the statement below which describes the
operator's actions with the above conditions.
Perform EOP-2, Vital System Status Verification, Immediate Actions and:
A. continue with the followup actions in EOP-2. No adverse conditions were created
with the above failure.
B. due to the above failure transitioning to EOP-3, Inadequate Subcooling Margin,
would be necessary.
C. due to the above failure transitioning to EOP-4, Inadequate Heat Transfer, would be
necessary.
D.' due to of the above failure transitioning to EOP-5, Excessive Heat Transfer, would
be necessary.
Reasons:
A. With these malfunctions the plant will overcool and EOP-5 will have to be
entered.
B. The plant will overcool with these failures, not lose SCM.
C. The plant will have excessive heat transfer, not inadequate heat transfer,
with these failures.
D. Correct. With the output of either high select remaining at 100% SASS will
transfer to this signal. This will defeat RFR and send a cross-limit to FW
keeping total FW flow within 5% of this signal resulting in a major
overfeed to each OTSG. TS cooldown limits will be exceeded and EOP-5
must be entered.
Tuesday, October 14,2003 10:39:08 AM 103
QUESTIQNS REPORT
for NRC Reviewed RO BANK
OPS 4-14 Section 1-4.0.H.10; OPS 5-94 Obj. 1; OPS 4-9 Obj. 3
RO - New
References provided: None
Rev. 0 to NRC on 5-9-03
Rev. 1 to NRC on 6-17-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D C C C D C C C D D Scramble Range: A - D
Tier: 1 Group: 1
Keyword: RO #I2 Cog Level: CIA 3.613.6
Source: N Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:08 AM 104
QUESTIONS REPORT
for NRC Reviewed RO BANK
65. BWE13EK2.01 001
The following plant conditions exist:
- The RCS has suffered a Small Break LOCA and a reactor trip has occurred.
- RCS pressure has stablilized at 1450 psig.
- RB pressure is 20 psig and increasing slowly.
- The Operator has carried out actions of EOP-13, Rule #2, HPI Control, for
Bypassing/Resetting ES actuations for the "A" train of ES but has NOT done "B" train.
Which of the following statements correctly describes the response of BSP-1A & 1B when RB
pressure reaches 30 psig? (assume no other operator actions taken)
A. BSP-1A & 1B will NOT auto start.
B. * BSP-1A & 1B will auto start.
C. BSP-1A will auto start but not BSP-1B.
D. BSP-1B will auto start but not BSP-1A.
Reasons:
A. Both will auto start.
B. Correct. Rule 2 allows the operator to bypassheset the HPI actuation.
However, the HPI Seal-in Reset pushbutton is not depressed at this time.
This keeps the HPI permit in place for the BSPs in case RB pressure does
eventually reach 30 psig. If this seal-in was reset then the BSP would not
automatically start at 30 psig RB pressure.
C. BSP-1B will start.
D. BSP-1A will start.
OPS 4-13 Section 1-2.0.F.3; EOP-13 Rule 2
RO - Direct [Opsbank ROT-4-13-0091
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B C D A E C D A B C Scramble Range: A - D
Tuesday, October 14,2003 10:39:08 AM 105
QUESTIONS REPORT
for NRC Reviewed RO BANK
Tier: 1 Group: 2
Keyword RO #27 Cog Level: MEM 3.613.4
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14, 2003 10:39:08AM 106
QUESTIONS REPORT
for NRC Reviewed RO BANK
66. G2.1.07 001
The following plant conditions exist:
- RCS pressure is 1500 psig and slowly lowering.
- PZR level is slowly lowering.
- Feedwater flows and OTSG levels are normal.
- "RB Fan A Condensate High" alarm is in.
Based on the above conditions which of the following could cause these indications?
A. An OTSG tube leak.
B. A main steam leak inside containment.
C .I* A loss of coolant accident inside containment.
D. A loss of coolant accident outside containment.
Reasons:
A. An OTSG tube leak should not cause the fan alarm.
B. A steam leak will cause RB pressure to increase and may have an effect
on FW flow.
C. Correct. A SBLOCA inside containment could cause all of these
conditions.
D. A SBLOCA outside of containment should not cause the fan alarm.
OPS 3-21 Section 1-2.0.B
RO - New
References provided: None
Rev. 0 to NRC on 4-1 1-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C C C C C C C C C C Items Not Scrambled
Tier: 3 Group:
Keyword RO #bb Cog Level: CIA 3.714.4
Source: N Exam: CR03301
Test: R Misc: ATK
ruesday, October 14,2003 10:39:08 AM 107
QUESTIONS REPORT
for NRC Reviewed RO BANK
67.G2.1.20 002
A LOOP, concurrent with a SBLOCA, has resulted in a loss of adequate subcooling margin.
The A EDG has not started and the A 4160V ES bus is dead.
When the operator verifies proper HPI discharge flowpath the following is observed:
MUV-23 (HPI Injection valve to A RCP discharge) has no power and is closed.
MUV-24 (HPI Injection valve to B RCP discharge) has no power and is closed.
MUV-25 (HPI Injection valve to C RCP discharge) is open.
MUV-26 (HPI Injection valve to D RCP discharge) is partially open (amber light).
MUV-586 (HPI Crosstie valve) is open.
MUV-587 (HPI Crosstie valve) is open.
What of the following describes the appropriate operator actions per EOP-3?
A. * Align alternate power to MUV-23 and 24 and open them.
B. Send the PPO to attempt to manually open MUV-26.
C. Send the PPO to attempt to manually open MUV-23 and 24.
D. Continue on; a proper HPI flowpath exists with the B Train.
Reasons:
A. Correct. Proper flowpath does not exist so the IF THEN statement is
followed.
B. EOP actions require the power supplies to be swapped.
C. EOP actions require the power supplies to be swapped.
D. A proper flowpath does not exist.
EOP-3 Step 3.3
RO - Direct [Newops 5-85-0031
References provided: None
Rev. 0 to NRC on 5-9-03
Rev. 1 changed per telcom
Tuesday, October 14, 2003 10:39:08AM 108
QUESTIONS REPORT
for NRC Reviewed RO BANK
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A B C D A B C D A B Scramble Range: A - D
Tier: 3 Group:
Keyword: RO #67 Cog Level: MEM 4.3/4.2
Source: B Exam: CR03301
Test: R Misc: ATK
Tuesday, October 14,2003 10:39:08AM 109
QUESTIONS REPORT
for NRC Reviewed RO BANK
68. 132.1.24001
4125 VDC
-L
INITIATING
TO VA4VE
nOTOR CIRCUIT K3 RELAY
--L-----
(ENERGIZE TO OPEN VALVE1
IDEENERGIZE TO CLOSE VALVE)
T Y P I C A L VALVE CONTROL C I R C U I T
Using the above drawing which of the following will close the valve?
(initial valve position is open) (drawing shown in shelf state)
A. * Loss of 125 VDC.
B. Both #1 and #2 contacts open.
C. Either #1 or #2 contact opens.
D. Depressing the S1 pushbutton with the initiating condition present.
Reasons:
A. Correct. With the valve initially in the open position the K3 relay must be
energized. This relay will seal-in contact #3. The only way to de-energize
the relay is to depress the S1 pushbutton or lose DC power to the circuit.
B. Even with both contacts open the relay stays energized though the parallel
path.
C. While this will break the path through the right side of the circuit the relay
stays energized though the parallel path.
D. This would work if the initiating condition was not present.
. ..
OPS 2-20
RO - Direct
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A B C D A B C D A B Scramble Range: A - D
Tier: 3 Group:
Keyword: RO #68 Cog Level: MEM 2N3.1
Source: B Exam: CR03301
Test: R Misc: ATK
. . .
The following plant conditions exist:
- A plant heatup and pressurization are in progress.
- LPI ES actuation bistables are currently bypassed.
Which of the following describes a required operator action in regard to the LPI ES actuation
bistables?
A. Manually reset the LPI actuation bistables when RCS pressure is greater than 500
psig and increasing.
B. Manually reset the LPI actuation bistables when RCS pressure is greater than 900
psig and increasing.
C. Verify automatic reset of the LPI actuation bistables when RCS pressure is greater
than 500 psig and increasing.
D. Verify automatic reset of the LPI actuation bistables when RCS pressure is greater
than 900 psig and increasing.
Reasons:
A. Correct. The LPI actuation bistables must be manually reset once RCS
pressure is greater than 500 psig and increasing.
B. This pressure is the LPI bypass permit pressure not the LPI actuation
bistable pressure setpoint.
C. The LPI actuation bistables do not automatically reset.
D. The LPI actuation bistables do not automatically reset
OPS 4-13 Sections 1-5.0.F.14 and 1-7.0.B.2; OP-202 Step 4.5.8
RO - Direct
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A B C D A B C D A B Scramble Range: A - D
Keyword RO #69 Cog Level: MEM 4.0/3.5
Source: B Exam: CR03301
Test: R Misc: ATK
The following plant conditions exist:
- Plant shutdown in progress.
- Reactor power at 2%.
- OTSG pressure is 885 psig.
- Shutdown Margin is -4.6% Akik from a calculation using -3.62% A!& reactivity
from xenon.
Which of the following statements will apply? Assume that the xenon reactivity will decay to
O%Akik.
Section 6 of Enclosure 1 in SP-42 1:
A. must be completed. Sufficient shutdown margin will be preserved even when
xenon decays to zero.
B. .J must be completed. Insufficient shutdown margin will result when xenon decays to
zero. Boron must be increased to maintain adequate shutdown margin.
C. need not be completed. Sufficient shutdown margin will be preserved even when
xenon decays to zero.
D. need not be completed. Insufficient shutdown margin will result when xenon
decays. Boron must be increased to maintain adequate shutdown margin.
Reasons:
A. Shutdown margin will be less than the minimum 1% A Wk after xenon
decays to zero.
B. Correct. Shutdown margin will be less than the required 1% A Wk.
C. Section 6 must be completed because xenon was used in Section 4.
Shutdown margin will be less than the minimum 1% A kik after xenon
decays to zero.
D. Section 6 must be completed because xenon was used in Section 4.
SP-421 Step 4.1 and Enclosure 1
NRCM98
RO - Direct [Newops 5-010-0021
References provided: SP-421
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B C D A B C D A B C Scramble Range: A - D
Tier: 3 Group:
Keyword RO #70 Cog Level: C/A 3.013.4
Source: B Exam: CR03301
Test: R Misc: ATK
Which of the following defines a "VERY HIGH RADIATION AREA" and describes the
control requirements for this type of area?
A. An area, accessible to individuals, in which radiation levels could result in an
individual receiving an absorbed dose in excess of 500 rads in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 1 foot from
a radiation source or from any surface that the radiation penetrates and the area
must be locked and controlled in such a manner that an individual cannot walk or
climb into it.
B. An area, accessible to individuals, in which radiation levels could result in an
individual receiving an absorbed dose in excess of 1000 rads in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 1 foot
from a radiation source or from any surface that the radiation penetrates and the
area must be conspicously posted and contain a flashing light.
C. An area, accessible to individuals, in which radiation levels could result in an
individual receiving an absorbed dose in excess of 500 rads in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 1 meter
from a radiation source or from any surface that the radiation penetrates and the
area must be locked and controlled in such a manner that an individual cannot walk
or climb into it.
D. An area, accessible to individuals, in which radiation levels could result in an
individual receiving an absorbed dose in excess of 1000 rads in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 1 meter
from a radiation source or from any surface that the radiation penetrates and the
area must be conspicously posted and contain a flashing light.
Reasons:
A. Distance is 1 meter, not 1 foot.
B. Dose is 500 Rads at 1 meter, not 1000 Rads at 1 foot. The area must also be
controlled such that an individual cannot walk or climb into it.
C. Correct. Doses in excess of 500 Rads in I hour at 1 meter and the
area controlled in such a manner that an individual cannot walk or climb
into it.
D. Dose is 500 Rads, not 1000 Rads and the area must be controlled in such a
manner that an individual cannot walk or climb into it.
OPS 2.32 Sections I-12.0.BBB & 1-3.0.C
RO - Direct [Newops ROT 5-043-0321
References provided: None
Rev. 0 to NRC on 4-1 1-03
Rev. 1 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C D A B C D A B C D Scramble Range: A - D
Tier: 3 Group:
Keyword RO #71 Cog Level: MEM 2.6/3.0
Source: B Exam: CR03301
Test: R Mix: ATK
As a radiation worker you are expected to keep your radiation exposure as low as reasonably
achievable. Which of the following shows a radiation exposure that is outside CR-3s
administrative limits for a radiation worker with a current dose history (NRC form 5) on file?
(Note: This is the first exposure of the year for each radiation worker).
A. ./ A 20 year old worker receives a TEDE exposure of 1 rem during work inside an
OTSG which brings his total lifetime TEDE exposure to 22 rem.
B. A 40 year old worker receives a TEDE exposure of 1.8 rem during the week while
completing a reactor vessel ISI. This brings his lifetime exposure to 25 rem.
C. A 45 year old worker receives a SDE-WB exposure of 25 rem after cutting open a
reactor coolant system pipe to complete a maintenance work order.
D. A 35 year old chemist receives a LDE exposure of 5 rem while sampling the reactor
coolant system for indication of failed fuel.
Reasons:
A. Correct. The annual TEDE administrative limit for a 20 year old is 2.0 Rem or
0.5 REM if lifetime dose > age.
B. The annual TEDE administrative limit is 2.0 Rem; 1.8 does not exceed that
limit.
C. The annual SDE-WB administrative limit was 40 Rem; this is not currently an
administrative limit.
D. The annual LDE administrative limit was 40 Rem; this is not currently an
administrative limit.
OPS 5-43 Section 1-3.0.D
RO - Direct [Newops 5-043-0011
References provided: None
Rev. 0 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A B C D A B C D A B Scramble Range: A - D
Keyword: RO #72 Cog Level: CIA 2.513.1
Source: B Exam: CR03301
Test: R Misc: ATK
. ..
The following plant conditions exist:
- The plant is at 30% power.
- Turbine vibration on bearing #7 is 10 mils.
- Hydrogen Cooler outlet temperature is 60" C.
Based on the above conditions which of the following action(s) should be taken?
A. Enter AP-510, Rapid Power Reduction, and perform a plant shutdown.
B. Enter OP-204, Power Operations, and perform a plant shutdown.
C. Enter EOP-02, Vital System Status Verification, and trip the reactor.
D." Enter AP-660, Turbine Trip, and trip the turbine.
Reasons:
A,, B. & C. Hydrogen Cooler outlet temperature is above the limit of 55OC per
OP-203. The entry conditions for A'-660 are met.
D. Correct. If Hydrogen Cooler outlet temperature exceeds 55' C the
turbine is required to be tripped.
OP-203 Step 3.2.1 1
NRCCP97; NRCM98
RO - Direct [Newops ROT-5-29-0061
References provided None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D A B C D A B C D A ScrambleRange: A - D
Tier: 3 Group:
Keyword RO #73 Cog Level: MEM 4.314.6
Source: B Exam: CR03301
Test: R Misc: ATK
The following plant conditions exist:
- The plant is in Mode 3 with RCS pressure at 2150 psig.
- AP-990, Shutdown from Outside the Control Room, has been entered and transfer
to the Remote Shutdown Panel is complete.
- MUV-31 has failed.
- The CRS directs that PZR level be maintained at an indicated = 100 inches.
Which of the following actions should be taken and what would be the approximate actual
PZR level for these conditions?
A. Open MUV-27 and direct the PPO to open MUV-30, bypass around MUV-31; =
160 inches.
B. #. Use an available HPI valve; = 160 inches.
C. Open MUV-27 and direct the PPO to open MUV-30, bypass around MUV-31; = 40
inches.
D. Use an available HPI valve; = 40 inches.
Reasons:
A. Per step 3.52 an available HPI valve should be used.
B. Correct. HPI valves can be controlled from the RSP. PZR level
indication on the RSP is not temperature compensated. Actual level for
this pressure and temperature is approximately 60" higher than
indicated.
C. Per step 3.52 an available HPI valve should be used. Actual level for
these conditions should be = 160 inches.
D. Actual level for these conditions should be = 160 inches.
OPS 4-09 Obj. 4; AP-990 Step 3.52; OPS 4-16 Section 1-7.A.l.f
NRCM98
RO - Direct [Newops 5-031-0021
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B C D A B C D A B C Scramble Range: A - D
Tier: 3 Group:
Keyword: RO #I4 Cog Level: C/A 3.413.6
Source: B Exam: CR03301
Test: R Misc: ATK
AP-990, Shutdown from Outside the Control Room, has been entered. After control has been
transferred to the RSP a followup step directs the RO to ensure BSP-1A is tripped by opening
the DC knife switch and depressing the manual trip pushbutton.
Which of the following describes where this action is performed and its purpose?
A. * The "A" ES 4160V switchgear room; to protect the pump from loss of essential
support functions.
B. The "A" ES 480V switchgear room; to protect the pump from loss of essential
support functions.
C. The "A" ES 4160V switchgear room; to ensure RCS inventory control problems are
not created by component failures.
D. The "A" ES 480V switchgear room; to ensure RCS inventory control problems are
not created by component failures.
Reasons:
A. Correct. The breaker is located in the "A" ES 4160V switchgear room and
due to possible fire damage to the ES actuation circuits this action will
ensure the pump cannot start.
B. This BSP is 4160V powered, not 480V.
C. This is the reason for securing the other ES pumps, not the BSP.
D. This BSP is 4160V powered, not 480V and this is the reason for securing
the other ES pumps, not the BSP.
OPS 5-3 1 Section 1-4.0.T
RO - New
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A A A A A A A A A A Items Not Scrambled
Tier: 3 Group:
Keyword: RO #75 Cog Level: MEM 3.313.5
Source: N Exam: CR03301
Test: R Misc: ATK
QUESTIONS REPORT
for NRC Reviewed SRO BANK
1. 003AA2.03 002
The following initial plant conditions exist at 100 EFPD:
NI-5 100% Imbalance at 0
NI-6 100% Rod Index of 292%
NI-7 100%
NI-8 100%
Fifteen minutes later the following conditions are observed:
NI-5 54% Imbalance at -10
NI-6 50% Rod Index of 250%
NI-7 50%
NI-8 50%
Which of the following is the most likely condition to cause these indications?
A. * Stuck rod.
B. Dropped rod.
C. Boration event in progress.
D. Loss of one reactor coolant pump.
Reasons:
A. Correct. The stuck rod is near NI-5.
B. Dependent on rod position in the core a single NI could indicate lower
than the other three, but not higher.
C. & D. All NIs should indicate the same for these events.
Tuesday. October 14, 2003 10:40:01 AM 1
QUESTIONS REPORT
for NRC Reviewed SRO BANK
OPS 5-68 Section 1-4.0.1; OPS 4-28 Section 1-8.O.C.2.d)4)
NRCN99
SRO - Modified [Newops 5-068-0041
References provided None
Rev. 1 to NRC on 7-29-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A A A B B D D A B D Scramble Range: A - D
Tier: 1 Group: 2
Keywords: SRO #83 Cog Level: CIA 3.613.8
Source: M Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14, 2003 10:40:01 AM 2
QUESTIONS REPORT
for NRC Reviewed SRO BANK
2.004A2.09002
A crud burst has occurred. How could this impact the plant and what actions can be taken to
help mitigate this problem?
A. The makeup pre-filters and post-filters will absorb most of the contaminants and
their radiation levels will increase. A hydrogen peroxide flush per OP-403H,
Hydrogen Peroxide Addition, will help reduce radiation levels.
B. The makeup pre-filters and post-filters will absorb most of the contaminants and
their radiation levels will increase. Decreasing letdown flow will help lower
radiation levels in the purification loop.
C. The makeup demins and post-filters will absorb most of the contaminants and their
radiation levels will increase. A hydrogen peroxide flush per OP-403H, Hydrogen
Peroxide Addition, will help reduce radiation levels.
D. * The makeup demins and post-filters will absorb most of the contaminants and their
radiation levels will increase. Decreasing letdown flow will help lower radiation
levels in the purification loop.
Reasons:
A. The pre-filters are not normally in service and the addition of hydrogen
peroxide will initially increase the probability of additional crud bursts.
B. The pre-filters are not normally in service.
C. The addition of hydrogen peroxide will initially increase the probability of
additional crud bursts.
D. Correct. Demins and post-filters will absorb most of the contaminants and
decreasing letdown flow will initially decrease radiation levels.
CP-155 Step 4.5.1.2.b
SRO - New
References provided: None
Rev. 0 to NRC on 5-9-03
Rev. 1 to NRC on 7-18-03
Tuesday, October 14,2003 10:40:01AM 3
QUESTIONS REPORT
for NRC Reviewed SRO BANK
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D D D D D D D D D D Items Not Scrambled
Tier: 2 Group: 1
Keywords: SRO #88 Cog Level: CIA 3.013.9
Source: N Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14,2003 10:40:01 AM 4
QUESTIONS REPORT
for NRC Reviewed SRO BANK
3. 009EK3.06 001
While operating at power M - A 6 is observed to be trending up. M W - 3 1 is taken to manual
and the following data is gathered for evaluation.
Time 0900 Pzr Lvl - 220" MUT Lvl - 80"
Time 0902 Pzr Lvl - 21 6" MUT Lvl - 8 1"
The following data is provided:
Pressurizer level = 12.2 galhnch MUT level = 30.8 galhnch
Based on these indications, which of the following describes current RCS leakage and
procedural/TS requirements? (disregard controlled bleedoff flow)
Conditions indicate RCS leakage:
A. is less than 1 gpm; CP-152, Primary to Secondary Leakage Operating Guideline,
will apply.
B. is less than 1 gpm; SP-317, RCS Water Inventory Balance, will apply.
C .* is greater than 5 gpm but less than 10 gpm; TS entry is required because
unidentified leakage is greater than 1 gpm.
D. is greater than 5 gpm but less than 10 gpm; TS entry is not required because
identified leakage is less than 10 gpm.
Reasons:
Over a two minute period: PZR lost 48.8 gallons, MUT gained 30.8 gallons. Total leakage
equals 9 gpm.
A. Leakage is greater than 1 gpm and Primary to Secondary leakage is not
indicated.
B. Leakage is greater than 1 gpm.
C. Correct. Leakage is 9.0 gpm. Since the leakage has not yet been located
the TS for unidentified leakage must be entered.
D. Since the leakage has not yet been located the TS for unidentified
leakage must be entered.
Tuesday, October 14,2003 10:40:01 AM 5
QUESTIONS REPORT
for NRC Reviewed SRO BANK
AP-520 Step 3.15; TS 3.4.12
NRCOO
SRO - Direct [Newops 5-1 14-21
References provided: None
Rev. 0 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer: C C A B C B A D B D Scramble Range: A - D
Tier: I Group: 1
Keywords: SRO #76 Cog Level: C/A 3.714.0
Source: B Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14,200310:40:01 AM 6
QUESTIONS REPORT
for NRC Reviewed SRO BANK
4. 01162.4.46 001
While the unit is operating at 100% the following sequence of events occurs:
- "SASS MISMATCH" annunciator alarms and does not clear.
- Investigation reveals the amber "MISMATCH" lamp to be lit on the
PRESSURIZER LEVEL channel. All other lamps in that channel and all other
"MISMATCH" lamps are off.
- Control board readings for PZR level are as follows:
LTl 222"
LT2 160"
LT3 221"
- All readings are stable.
Which of the following statements is correct concerning these conditions?
A. The alarm is valid. SASS has functioned properly. No operator action is required.
B. The alarm is valid, however, SASS should have transferred to LTl. The operator
should select LT1 and issue a work request on LT3.
C. The alarm is NOT valid. The operator should depress the "AUTO" pushbutton to
return the channel to normal operation.
D. * The alarm is NOT valid. The operator should issue a work request on the SASS
channel.
Reasons:
A. Mismatch alarm is 3% of scale (9.6") between LTl and LT3. Alarm is not
valid and SASS has malfunctioned.
B. The alarm is not valid and no transfer should occur.
C. Per OP-501 a work request should be written.
D. Correct. A work request should be written.
Tuesday, October 14, 2003 10:40:01 AM 7
QUESTIONS REPORT
for NRC Reviewed SRO BANK
OPS 4-09 Obj. 6; OPS 4-09 Section 1-4.0.B; OP-501 Enclosure 3, Page 3; OP-501 Step 4.7.2
SRO - Direct [Opsbank ROT-4-09 0601
References provided: None
Rev. 0 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D A B C D A B C D A Scramble Range: A - D
Tier: 2 Group: 2
Keywords: SRO #92 Cog Level: CIA 3.513.6
Source: B Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14,2003 10:40:02 AM 8
QUESTIONS REPORT
for NRC Reviewed SRO BANK
5. 01262.2.24 001
At 80% power maintenance testing determines that two channels of the control oil pressure for
loss of MFW Pumps actuation are set at 52 psig. Which of the following Technical
Specification actions are required?
Place:
A. both channels in bypass in one hour.
B. one channel in bypass in one hour and place the second channel in trip in one hour.
C. one channel in bypass in one hour and restore one channel to operable status in 24
hours.
D. one channel in trip in one hour and restore one channel to operable status in 72
hours.
Reasons:
A. An electrical interlock prevents this.
B. Correct. TS 3.3.1 Condition B and Table 3.3.1-1. Table specifies a setpoint
of > 55 psig.
C. TS requires one channel to bypass and one channel to trip for these
conditions.
D. TS requires one channel to bypass and one channel to trip for these
conditions.
TS 3.3.1 &Table 3.3.1-1
SRO - Direct [Opsbank ROT 5-01 0501
References provided: None
Rev. 0 to NRC on 4-1 1-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B C D A B C D A B C Scramble Range: A - D
Tuesday, October 14,2003 10:40:03 AM 9
QUESTIONS REPORT
for NRC Reviewed SRO BANK
Tier: 2 Group: 1
Keywords: SRO #89 Cog Level: CIA 2.613.8
Source: B Exam: CR303301
Test: S Mise: ATK
Tuesday, October 14, 2003 10:40:03 AM 10
QUESTIONS REPORT
for NRC Reviewed SRO BANK
6.0 2 5 ~ ~ 1 .002
01
The following plant conditions exist:
- TS required plant shutdown to Mode 4 is in progress due to a broken shaft on
DHP-1A.
- RCS temperature is 285'F.
- RCP-1A and 1B are running.
While checking DHP-1B for start the PPO reports an oil spill around the motor and the oil
bubbler empty.
Which of the following describes the appropriate action(s) to be taken?
A. Remain in this mode until either DHP-1A or 1B are repaired.
B. Remain in this mode and declare an Unusual Event based on the "Inability to reach
required mode within ITS time limits".
C .* Continue to Mode 4, invoke lOCFR 50.54 X & Y, and remain in Mode 4 until
either DHP-1A or 1B are repaired.
D. Continue to Mode 5 since LCO 3.0.3 now applies due to the inoperability of both
DH removal trains.
Reasons:
A. The plant should be taken as low in Mode 4 as possible while still allowing
the OTSGs to remain the source of heat removal.
B. The plant should be taken as low in Mode 4 as possible while still allowing
the OTSGs to remain the source of heat removal. An Unusual Event will be
declared.
C. Correct. Since 3.0.3 now applies lOCFR 50.54 X & Y must be invoked to
remain in a mode not specified by TS.
D. While LCO 3.0.3 does apply, and Mode 5 is required per this LCO, the plant
cannot safely get there. With no DH removal train available the OTSGs are
required for heat removal. This requires maintaining RCS temperature
greater than Mode 5 values.
Tuesday, October 14, 2003 10:40:03 AM 11
QUESTIONS REPORT
for NRC Reviewed SRO BANK
TS 3.0.3,3.5.2,3.5.3 &Bases
SRO - New
References provided None
Rev. 0 to NRC on 4-22-03
Rev. 1 to NRC on 7-1 8-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C C C C C C C C C C Items Not Scrambled
Tier: 1 Group: 1
Keywords: SRO #I1 Cog Level: CfA 3.9f4.3
Source: N Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14, 2003 10:40:03 AM 12
QUESTIONS REPORT
for NRC Reviewed SRO BANK
7. 026AG2.4.47 001
The following plant conditions exist:
- SW surge tank, SWT-1, is at 9 ft and lowering.
- "A" DC surge tank, DCT-1A, is at 9 ft and steady.
- "B" DC surge tank, DCT-lB, is at 9 ft and steady.
- Auxuliary Building sump is steady.
- Turbine Building sump is rising.
Which of the following could be the cause of the lowering level in SWT-I?
A. A tube leak in the "B" letdown cooler, MUHE-1B.
B. A crack in the SW supply piping near the CRDM filters.
C. * A crack in the suction header near the normal duty SW pump, SWP-IC.
D. Improper valve alignment for cooling water to the "C" Makeup pump, MUP-IC.
Reasons:
A. A tube leak in MUHE-1B would cause SWT-1 level to rise.
B. If the leak was near the CRDM filters the AB sump would be increasing, not
C. Correct. A leak in this area would first be drained to the Nuclear Services
sump and then be pumped directly to the TB sump.
D. If the SW and DC cooling water valves to MUP-IC were not in their
proper alignment, SW could be flowing into the DC system, raising the level of
DCT-IB.
OPS 4-83 Section I-4.0.E
SRO - Modified [Newops 4-56-0011
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C D D D B B B B C D Scramble Range: A - D
Tuesday, October 14.2003 10:40:03 AM 13
QUESTIONS REPORT
for NRC Reviewed SRO BANK
Tier: 1 Group: 1
Keywords: SRO #78 Cog Level: CIA 3.413.7
Source: M Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14, 2003 10:40:03 AM 14
QUESTIONS REPORT
for NRC Reviewed SRO BANK
8. 0 2 9 ~ ~ 2 . 0002
9
The following plant conditions exist:
- The plant is at 55% reactor power.
- The ICs +24 volt DC bus has degraded to +I8 volts.
- RPS high reactor coolant system pressure setpoint has been exceeded.
Assuming no operator actions what would be the plant's response to this situation?
A. ATWS removes power from the safety rods and initiates EFIC.
B. AMSAC trips the main turbine and initiates EFIC.
C. DSS opens the "E" and "F" contacts to the safety rods.
D. RPS trips the reactor due to the trip of both MFW pumps.
Reasons:
A. The ATWS subsystem (DSS) removes power from the regulating rods, not
the safety rods, if conditions are met. The other sub-system of ATWS
(AMSAC) will initiate EFIC under these conditions (>50% power and 4 7 %
MFW flow).
B. Correct. This failure will cause the MFW pumps to decrease to minimum
speed, which will immediately stop all feedwater flow. This will actuate
both channels of AMSAC ( 4 7 % flow and > 50% power) and trip the turbine
and actuate EFIC.
C. DSS will remove power (by opening the "E" & "F" contacts, gating power)
from the regulating rods if RCS pressure exceeds 2450#.
D. This failure will cause both MFW pumps to decrease to minimum speed
(the S1 and S2 breakers open at <22 VDC) but will not cause the pumps to
trip.
Tuesday, October 14, 2003 10:40:03AM 15
QUESTIONS REPORT
for NRC Reviewed SRO BANK
OPS 4-12 Section 2-2.0.D; OPS 4-14 Section I-8.0.F.3
NRCN99
SRO - Direct [Newops 4-012-0021
References provided: None
Rev. 0 to NRC on 4-1 1-03
Rev. 1 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B C D A B C D A B C Scramble Range: A - D
Tier: 1 Group: 1
Keywords: SRO #79 Cog Level: CIA 4.414.5
Source: B Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14, 2003 10:40:03 AM 16
QUESTIONS REPORT
for NRC Reviewed SRO BANK
9. 03462.3.10 002
The plant is operating at 100% power. Fuel shuffle is in progress in the Spent Fuel Pool.
Water level in the spent fuel pool is normal at 158.5 ft. The suction line to SFP-IA ruptures
and cannot be isolated. Movement of spent fuel in the spent fuel pool:
A. Must stop due to insufficient volume for cooling to maintain pool temperature less
than 190" F.
B. May continue because adequate level will still be maintained for shielding
requirements.
C. * Must stop due to insufficient volume for iodine retention if a fueVhandling accident
were to occur.
D. May continue because level will not drop below the minimum Technical
Specification value.
Reasons:
A. Cooling may be affected but this is not why a minimum volume is required
in the spent fuel pool.
B. Radiation levels might increase slightly but this is not why a minimum
volume is required in the spent fuel pool.
C. Correct. The minimum volume of 23 feet above the pool is based on a fuel
handling accident and the pools ability to retain iodine from a ruptured
spent fuel assembly.
D. Level will drop to approximately 154.5 ft which is below the minimum level
required for movement of irradiated fuel assemblies in the spent fuel pool.
OPS 4-29 Section 1-4.0.A.3; TS 3.7.13 LCO and Bases
SRO -Direct [Newops 4-29-0011
References provided: None
Rev. 1 to NRC on 7-29-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C D A B C D A B C D Scramble Range: A - D
Tuesday, October 14, 2003 10:40:03 AM 17
QUESTIONS REPORT
for NRC Reviewed SRO BANK
Tier: 2 Group: 2
Keywords: SRO #93 Cog Level: MEM 3.113.3
Source: B Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14, 2003 10:40:03AM 18
QUESTIONS REPORT
for NRC Reviewed SRO BANK
10.040AK3.2 001
A step in EOP-5, Excessive Heat Transfer, states:
IF at any time, ES systems have,
OR should have actuated,
THEN ensure ES equipment is properly aligned.
Detailsl. Ensure applicable ES actuations:
RBIC (4 psig RB PRESS)
2. Bypass or reset ES actuations:
Auto
Manual
3. Control ES systems as required.
[Rule 2, HPI Control]
[Rule 5, EDG Control]
4. IF RBIC has actuated, AND adequate SCM exists,
THEN stop all RCPs: RCP-lA, lB, 1C & 1D
What is the purpose of Detail #4?
Because it is not reasonable to expect the operating crews to be able to adequately evaluate the
safety implications of: bypassing the ES actuation and
A. restoring seal injection within 5 minutes.
B. * reopening the CBO valves within 5 minutes.
C. reopening the SW cooling valves within 5 minutes.
D. the effect on OTSG tube stresses in the isolated OTSG within 5 minutes.
Tuesday, October 14,2003 10:40:03AM 19
QUESTIONS REPORT
for NRC Reviewed SRO BANK
Reasons:
A. Restoring seal injection is not a concern. RCS water will adequately supply
the seals if seal injection is terminated.
B. Correct. If the CBO valves are closed for more than 5 minutes on a running
RCP the seals would have to be inspectedreplaced.
C. An RBIC actuation does not normally isolate the SW cooling valves to the
RCPs.
D. This is the reason for minimizing RCS temperature changes.
OPS 5-94 Section 1-4.0.D
SRO - New
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B B B B B B B B B B Items Not Scrambled
Tier: 1 Group: 1
Keywords: SRO #81 Cog Level: MEM 4.4/4.4
Source: N Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14,2003 10:40:03 AM 20
QUESTIONS REPORT
for NRC Reviewed SRO BANK
11. 05562.4.07 001
A step in EOP-12, Station Blackout, states the following:
"Stop DC motors."
Partial details of this step have the Reactor Operator:
- Select MUP backup lube oil pumps (MUP-3A, B, C) to "Pull To Lock."
- Select MUP backup gear oil pumps (MUP-SA, B, C) to "Stop."
Which of the following describes why the DC motors should be stopped?
This is necessary for the 1E batteries to meet their:
A. 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> coping requirement.
B. * 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> coping requirement.
C. 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> coping requirement.
D. 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> coping requirement.
Reasons:
A. The required time is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. This answer could be chosen if assuming a
per battery basis.
B. Correct. The required time is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for the SBO coping studies.
C. The required time is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. This answer could be chosen if assuming a 4
hours per battery basis.
D. The required time is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. This answer could be chosen if assuming a 8
hours per battery basis.
Tuesday, October 14,2003 10:40:03 AM 21
QUESTIONS REPORT
for NRC Reviewed SRO BANK
EOP-12 Step 3.7; OPS 5-100 Section 1-4.0.H; OPS 4-64 Obj. 7, Section 1-4.0.A.2; FSAR
Section 14.1.2.9.5.2
SRO - Direct [Newops 5-100-0051
References provided: None
Rev. 0 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B C D A B C D A B C Scramble Range: A - D
Tier: 3 Group:
Keywords: SRO #82 Cog Level: MEM 3.113.8
Source: B Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14, 2003 10:40:03 AM 22
QUESTIONS REPORT
for NRC Reviewed S R O BANK
12. 057AK3.01 001
With the plant at 100% power a catastrophic failure of VBIT-IC rendered itself inoperable and
caused both of the VBXSs that it feeds to fail "as is" .
Which of the following describes the EOP/AP action(s), if any, that should be taken?
A. AP-581, Loss of NNI-X, should be entered.
B. AP-582, Loss ofNNI-Y, should be entered.
C. .4 AP-430, Loss of Control Room Alarms, should be entered.
D. Trip both MFW pumps and the reactor due to the loss of ICs power. EOP-2, Vital
System Status Verification, and Rule 3, EFW Control, should be entered.
Reasons:
A. The ABT for "I-X should transfer to VBDP-I on a loss of VBDP-5.
B. Neither VBDP-5 or 9 feed "I-Y therefore no loss of power should occur.
C. Correct, VBDP-5 powers the annunciator monitor and typer.
D. This is the correct response for a loss of ICs power however neither
VBDP-5 or 9 feed ICs therefore no loss of power should occur.
OPS 4-91, Figure 1; OPS 4-9 Section 1-4.0.1
NRCM98
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C D A B C D A B C D Scramble Range: A - D
Tier: 1 Group: 1
Keywords: SRO #SO Cog Level: MEM 4.U4.4
Source: B Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14,2003 10:40:03 AM 23
QUESTIONS REPORT
for NRC Reviewed SRO BANK
13.061A2.05 002
With the plant at 35% power
you notice the "EFW MAN" light
flashing on the Emergency
Feedwater Initiation and
Control (EFIC) module
shown. A few seconds later the "FULL" light
starts to flash. Select the statement
below which describes these indications
and required action(s), if any, which
should be taken.
A. These indications are expected during low power operation. No additional actions
are required.
B. These lights are memory lights only. They will normally stay flashing until the test
pushbutton in the lower right comer of this module is depressed. Maintenance
should be contacted
C. An EFIC actuation has occurred due to the loss of both MFWPs. Since the "EFW
MAN" light was on prior to the actuation it should continue to flash. EOP-2, Vital
System Status Verification, and EOP-13, Rule 3, EFW/AFW Control, should be
entered.
D.' An EFIC actuation has occurred due to the loss of all RCPs. The "EFW MAN"
light should have stopped flashing and the "EFW AUTO" should have started
flashing. EOP-2, Vital System Status Verification, and EOP-13, Rule 3,
EFW/AFW Control, should be entered.
Tuesday, October 14, 2003 10:40:03 AM 24
QUESTIONS REPORT
for NRC Reviewed SRO BANK
Reasons:
A. The only lights that should be flashing are the three "AUTO" lights.
B. The lights are not memory lights. They indicate current plant conditions.
C. The "EFW MAN" light indicates the EFW control valve is in manual. The
valve should revert to automatic when EFIC actuates. A loss of MFWPs
will cause the "LOW" light to flash, not the "FULL" light.
D. Correct. The "FULL" light will only come on if an EFIC actuation has
occurred due to a loss of all RCPs and the "EFW AUTO" light should flash
when the control valve swaps to automatic control. The reactor should trip
and EOP-2 and Rule 3 should be entered.
OPS 4-31 Section I-4.0.P.6
SRO - New
References provided: None
Rev. 0 to NRC on 4-1 1-03
Rev. 1 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D A A C A C D A B A Scramble Range: A - D
Tier: 2 Group: 1
Keywords: SRO #90 Cog Level: CIA 3.113.4
Source: N Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14,2003 10:40:03AM 25
QUESTIONS REPORT
for NRC Reviewed SRO BANK
14.061AG2.1.14001
Which of the following describes a condition that requires notification of all plant personnel?
A. RM-A2 particulate monitor goes into high alarm.
B. RM-A2 iodine monitor goes into high alarm.
C. RM-A5 particulate monitor goes into high alarm.
D../ RM-A5 iodine monitor goes into high alarm.
Reasons:
A. Only RM-A2 gas requires entry into AP-250 and notification of all plant
personnel.
B. Only RM-A2 gas requires entry into AP-250 and notification of all plant
personnel.
C. RM-A5 gas and iodine monitors in high alarm require entry into AP-250,
not RM-A5 particulate.
D. Correct. RM-A5 iodine high alarm requires entry in AP-250 and the
notification of all plant personnel.
AP-250 Section 1.O
SRO - New
References provided None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D D D D D D D D D D Items Not Scrambled
Tier: 1 Group: 2
Keywords: SRO #84 Cog Level: MEM 2.513.3
Source: N Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14, 2003 10:40:03 AM 26
QUESTIONS REPORT
for NRC Reviewed SRO BANK
15. 064A1.03 001
Assume the "B" EDG is the sole power supply available to the "B" ES 4160V bus. Which of
the following activities would produce the lowest diesel load that would cause the EDG's
elapsed time meter (MCB) to start? (disregard starting currents)
AHF-17AlB 51 kW DCP-1NB 79 kW
AHF-l8A/B 50 kW EFP-1 698 kW
AHF-l9A/B 18 kW MUP- 1NB/C 694 kW
BSP-1NB 222 kW RWP-2NB 554 kW
CHP-1A/B 19 kW RWP-3NB 198 kW
CHHE- 1N B 196 kW SWP- 1N B 497 kW
A. ./ Initial EDG loading of 2440 kW. MUP-IC and its associated cooling water pumps
are started.
B. Initial EDG loading of 2850 kW. BSP-1B and its associated cooling water pumps
are started.
C. Initial EDG loading of 1800 kW. EFP-1 and its associated cooling water pumps are
started.
D. Initial EDG loading of 2920 kW. "B" train normal control complex cooling fans
and chiller are started.
Reasons:
A. Correct. 2440 kW + 694 kW (MUP-IC) + 198 kW (RWP-3B) + 79 kW (DCP-1B)
= 341 1 kW. Meter starts recording at 3376 kW. Actual setpoint is 3401 kW -
25 kW for instrument error.
B. 2850 kW + 222 kW (BSP-1B) + 198 kW (RWP-3B) + 79 kW (DCP-1B) 53349
kW.
C. EFP-1 loading will have no effect on the EDG-1B.
D. 2920 kW + 51 kW (AHF-17B) + 18 kW (AHF-19B) + 196 kW (CHHE-1B + 19
kW (CHP-1B) = 3201 kW.
Tuesday, October 14,2003 10:40:03 AM 27
QUESTIONS REPORT
for NRC Reviewed SRO BANK
OPS 4-06 Section 1-2.0.E.l.d)
SRO - Direct [Newops 4-06-0101
References provided: None
Rev. 0 to NRC on 4-1 1-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A B C D A B C D A B Scramble Range: A - D
Tier: 2 Group: 1
Keywords: SRO #91 Cog Level: CIA 3.213.3
Source: B Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14, 2003 10:40:03 AM 28
QUESTIONS REPORT
for NRC Reviewed SRO BANK
16. 074EA2.03 001
The following plant conditions exist:
- EOP-3, Inadequate Subcooling Margin, was entered following a LOCA.
- Reactor Coolant (RCS) pressure was 850 psig.
- EFP-2 is the only operating and the only available EFW/AFW pump.
Tincore temperature is currently 900" F and RCS pressure is 1000 psig. Which of the
following methods would be used to maintain the OTSGs as a heat sink?
A. Lower OTSG pressure to 200 psig using the Turbine Bypass valves (TBVs).
B. * Lower OTSG pressure to 380 psig using the Turbine Bypass valves (TBVs).
C. Lower OTSG pressure to 200 psig using the Atmospheric Dump valves (ADVs).
D. Lower OTSG pressure to 380 psig using the Atmospheric Dump valves (ADVs).
Reasons:
A. OTSG pressure should be lowered to the highest of the pressure choices, 380
or 200 psig.
B. Correct. TBVs are the preferred method. OTSG pressure should be lowered to
the highest of the pressure choices, 380 psig.
C. OTSG pressure should be lowered to the highest of the pressure choices, 380
or 200 psig. TBVs are preferred.
D. The ADVs could be used but the TBVs are preferred.
EOP-3 Step 3.15; EOP-07 Step 3.1 1 &Figure 2
SRO - Direct [Newops 3-025-0021
References provided: EOP-3 & EOP-7
Rev. 0 to NRC on 4-22-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: B A C D B C B C B D Scramble Range: A - D
Tuesday, October 14, 2003 10:40:03 AM 29
QUESTIONS REPORT
for NRC Reviewed SRO BANK
Tier: I Group: 2
Keywords: SRO #85 Cog Level: CIA 3.814.1
Source: B Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14, 2003 10:40:03AM 30
QUESTIONS REPORT
for NRC Reviewed SRO BANK
17.BWA02AAI.1 002
The plant has experienced a loss of "I-X power which causes a spurious closure of MUV-49,
letdown isolation valve. Pressurizer level is increasing due to the loss of letdown. Which of
the following actions, by procedure, should be directed to decrease seal injection flow in order
to slow down the increase in PZR level?
Direct the:
A. PPO to manually reduce flow by throttling MW-16, seal injection control valve.
B. RO to reduce MUV-16 valve demand using the setpoint knob with the handauto
station in auto.
C.' RO to reduce MUV-16 valve demand using the toggle switch with the handauto
station in manual.
D. PPO to isolate MUV-16 and use the manual bypass valve to allow continued seal
injection.
Reasons:
A. While this action would work it is definitely not the preferred method.
B. MUV-16 will not work in automatic with a loss of "I-X.
C. Correct. On a loss of "I-X a backup power supply (powered from
VBDP-3) will enable operation of MUV-16 in the manual mode only.
D. OP-402 has direction for manually throttling the bypass valve however
manual control from the MCB is preferable.
AP-581 Step 3.13 & 3.21; OPS 4-9 Section 1-8.B.4; OPS 4-52 Section 1-4.2
NRCM98
SRO - Direct [Newops 4-52-01 13
References provided None
Rev. 0 to NRC on 5-9-03
Rev. 1 to NRC on 6-17-03
Tuesday, October 14, 2003 10:40:03 AM 31
QUESTIONS REPORT
for NRC Reviewed SRO BANK
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C D A B C D A B C D Scramble Range: A - D
Tier: 1 Group: 2
Keywords: SRO #86 Cog Level: MEM 4.013.8
Source: B Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14, 2003 10:40:04 AM 32
QUESTIONS REPORT
for NRC Reviewed SRO BANK
18. BWA05G2.2.20 002
After performance of a surveillance procedure on the "A" EDG the diesel is determined to be
Which of the following actions should be taken to ensure troubleshooting activities will not
render the redundant train inoperable?
A. Electronically lock the doors to the "B" EDG so that only personnel approved by
the Superintendant of Shift Operations will have access.
B. Electronically lock the doors to the "B" ES 4160V switchgear room so that only
personnel approved by the Superintendant of Shift Operations will have access.
C. Perform an EOOS evaluation, change the "Plant Condition" color to red and have
flyers produced.
D. . Post protected train signs and conduct a field walkdown of the appropriate opposite
train equipment.
Reasons:
A. & B. These doors are always electronically locked but additional
restrictions on electronic access is not implemented.
C. An EOOS evaluation will be performed but the "Plant Condition"
color will only increase to Yellow.
D. Correct. Protected train signs will be placed on the "B" Train
equipment and a field walkdown should be performed.
01-07 Form 7
SRO - New
References provided: None
Rev. 0 to NRC on 5-9-03
Rev. 1 to NRC on 6-17-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D D D D D D D D D D Items Not Scrambled
Tuesday, October 14, 2003 10:40:04 AM 33
QUESTIONS REPORT
for NRC Reviewed SRO BANK
Tier: 1 Group: 2
Keywords: SRO #87 Cog Level: MEM 2.2/3.3
Source: N Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14,200310:40:04 AM 34
QUESTIONS REPORT
for NRC Reviewed SRO BANK
19. G2.1.04001
The following plant conditions exist:
- The plant is in a refueling outage and the reactor is defueled.
- One of the two available PPOs assigned to the Auxiliary Building slips and severely
sprains his ankle while performing a walkdown of the Reactor Building.
- The PPO is contaminated and is escorted to the hospital by both available Health
Physics technicians.
Which of the following describes the required minimum staffing for this situation?
A. 4. No action is required. Minimum staffing levels are still met.
B. If it is two hours or less until shift turnover is scheduled to occur no action is
required.
C. Another PPO should be called in immediately and should arrive within two hours.
D. Another HP technician should be called in immediately and should arrive within
two hours.
Reasons:
A. Correct. An HP technician is not required if the reactor is defueled.
B. No action is required at any time when the plant is defueled.
C. Only one PPO is required to meet staffing levels.
D. HP is not required when the plant is defueled.
TS 5.2.2; AI-500 Section 4.6
NRCM98; NRCN99
SRO - Modified [Newops 5-001-0071
References provided: None
MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A D D D C B D D B A Scramble Range: A - D
Tuesday, October 14, 2003 10:40:04 AM 35
QUESTIONS REPORT
for NRC Reviewed SRO BANK
Tier: 3 Group:
Keywords: SRO #94 Cog Level: MEM 2 3 3 . 4
Source: M Exam: CR303301
Test: S Mix: ATK
Tuesday, October 14, 2003 10:40:04 AM 36
QUESTIONS REPORT
for NRC Reviewed SRO BANK
20. (32.1.12 001
The following plant conditions exist:
- Plant is at 100% power.
- RWP-2A tagged out for shaft alignment 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago.
- TS 3.7.9 was entered when RWP-2A was tagged out.
- The PPO has just reported the trip mechanism for the "B" EDG is broken.
Which of the following actions should be performed when "B" EDG is declared inoperable?
A. Perform SR 3.8.1.1 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, declare "A" EDG inoperable within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
B. Immediately declare both RWP-2A and 2B inoperable, enter LCO 3.0.3, be in
Mode 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, Mode 4 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> and Mode 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
C.y Perform SR 3.8.1.1 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, declare RWP-2B inoperable within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and
determine the "A" EDG is not inoperable due to a common cause failure within 24
hours
D. Perform SR 3.8.1.1 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, declare all "B" train ES components inoperable
within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and determine the "A"EDG is not inoperable due to a common
cause failure within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
Reasons:
A. "A" EDG is not inoperable after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, only the redundant features
supported by the "B" EDG.
B. RWP-2B does not have to be declared inoperable for four hours.
C. Correct. These are the requirement per TS 3.8.1, Condition B.
D. All "B" train components are not required to be declared inoperable per TS 3.0.6.
TS 3.7.9, 3.8.1 8~3.0.6
SRO - Direct [Newops ROT 5-01 1271
References provided: None
Rev. 0 to NRC on 4-1 1-03
Tuesday, October 14, 2003 10:40:04 AM 37
QUESTIONS REPORT
for NRC Reviewed SRO BANK
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C D B A A D C D C D Scramble Range: A - D
Tier: 3 Group:
Keywords: SRO #95 Cog Level: CIA 2.914.0
Source: B Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14,2003 10:40:04 AM 38
QUESTIONS REPORT
for NRC Reviewed SRO BANK
21. G2.2.22 002
During three RCP operation (RCP-1D secured) the following readings are recorded
- RCS total flow 1.14 x 108 Ibm/hr
- RCSThot "A" loop 603" F "B" Loop 603" F
- RCS pressure "A" loop 2070 psig "B" Loop 2090 psig
Based on the above conditions what action(s), if any, are required to be taken?
A. No action required. All parameters are within limits for three RCP operation.
B. The DNBR Safety Limit has been exceeded. Be in Mode 3 within one hour.
C. One DNB parameter is not within limits. Restore the parameter to within limits in
two hours.
D. Two DNB parameters are not within limits. Restore the parameters to within limits
in two hours
Reasons:
A. Correct. Total flow is require. :o be 3 99.7 E6 lbmkr with RCPs and
RCS pressure, in the loop with 2 RCPs running, is required to be ?
2064 psig.
B. C. & D. Refer to Reason A.
TS 3.4.1; TS Figure 2.1.1-1; OPS 4-60 Section 1-10.A, OPS 5-01 Obj. 9
NRCM98; NRCN99
SRO - Modified [Newops 4-060-0131
References provided: None
Rev. 0 to NRC on 5-9-03
Rev. 1 to NRC on 7-18-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: A D C B A D A C B C Scramble Range: A - D
Tuesday, October 14,2003 10:40:04 AM 39
QUESTIONS REPORT
for NRC Reviewed SRO BANK
Tier: 3 Group:
Keywords: SRO #96 Cog Level: CIA 3.414.1
Source: M Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14,2003 10:40:04 AM 40
QUESTIONS REPORT
for NRC Reviewed SRO BANK
22. G2.2.27 001
Refueling is in progress with eight (8) fuel assemblies in the core. As the ninth assembly is
being placed in the core the following NI readings are observed:
- NI-1 increases from a base count of 203 to 430 cps.
- NI-14 increases from a base count of 9.3 x to 2.3 x
- NI-2 and NI-15 are out-of-service.
Which of the following actions, if any, should be taken by the refueling supervisor?
A. No action is required. This is an expected NI response.
B. Once the assembly is placed in the core, reactor engineering should be contacted to
perform a subcritical multiplication calculation.
C. Cease insertion of the fuel assembly and submit a sample request for boron
concentration of the reactor coolant system.
D.* Withdraw the fuel assembly, stop any other core alterations in progress, perform
Co/Ci calculations, and obtain a boron analysis.
Reasons:
A. An action is required, count rate has increased by more than 1.5 times. The
required action for an NI increase of this type is to withdraw the fuel assembly
in question, immediately cease all other core alterations, perform a subcritical
multiplication and obtain a boron analysis of the RCS.
B. The assembly should not be placed into the core.
C. The fuel assembly being inserted should be removed, not just cease insertion.
D. Correct. The fuel assembly should be removed, core alterations suspended and
an engineering evaluation performed.
FP-203 Step 3.2.1.1.1
SRO - Direct [Newops 4-26-0021
References provided None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: D A B C D A B C D A Scramble Range: A - D
Tuesday, October 14, 2003 10:40:04 AM 41
QUESTIONS REPORT
for NRC Reviewed SRO BANK
Tier: 3 Group:
Keywords: SRO #91 Cog Level: CIA 2.613.5
Source: B Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14, 2003 10:40:04AM 42
QUESTIONS REPORT
for NRC Reviewed SRO BANK
23. G2.3.06 002
The following plant conditions exist:
- Plant is in Mode 5.
- The "A" DHR train is in service.
- SDT-1, Secondary Drain Tank, recirc is complete and ready for release.
- RWP-1 is running.
- RWV-150 is closed.
- CWP- 1A and 1 D are running.
- RM-L2/7 "Bypass" switch is selected to "Bypass".
- Minimum RW dilution flow rate is 11,800 gpm per the release permit.
Which of the following action(s), if any, must be taken before the release can be started?
A. Adequate dilution flow exists. No further actions required.
B. Adequate dilution flow exists as long as a minimum of two (2) CWPs remain in
operation.
C. * Inadequate dilution flow exists. RWP-2A or 2B must be started prior to release.
D. Inadequate dilution flow exists. RWP-3A or 3B must be started prior to release.
Reasons:
A. Adequate dilution flow does not exist. RWP-1 is only rated at 10,800 gpm
and the permit requires a dilution flow rate of 11,800 gpm.
B. Adequate dilution flow does not exist. RWP-1 is only rated at 10,800 gpm
and the permit requires a dilution flow rate of 11,800 gpm. CWP dilution
flow is not used in addition to RW dilution flow any more.
C. Correct. RWP-2A & 2B are rated at 14,100 gpm.
D. With RM-L2/7 "Bypass" switch selected to "Bypass" the dilution flow
rate is based on SW Raw Water pumps. Starting a DC Raw Water pump
will have no effect on dilution calculations.
Tuesday,October 14, 2003 10:40:04AM 43
QUESTIONS REPORT
for NRC Reviewed SRO BANK
OP-407N Section 4.3
SRO - NEW
References provided: None
Rev. 0 to NRC on 4-22-03
Rev. 1 to NRC on 7-1 8-03
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C C D C A B A A A C Scramble Range: A - D
Tier: 3 Group:
Keywords: SRO #98 Cog Level: CIA 2.113.1
Source: N Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14, 2003 10:40:04 AM 44
QUESTIONS REPORT
for NRC Reviewed SRO BANK
24. G2.4.06 001
The plant has experienced a Rx trip and now no source of main, emergency or auxiliary
feedwater is available. The crew has entered EOP-04, Inadequate Heat Transfer. Step 3.12 of
EOP-04 states:
WHEN any of the following exist:
RCS pressure approaches the NDT limit
PORV opens automatically
RCS press > 2400 psig
THEN continue in this procedure.
Why are we required to wait to initiate HPI / PORV cooling when the RCS is in an Inadequate
Heat Transfer condition?
A. To allow the crew to wait for the appropriate amount of time to determine if Natural
Circulation will develop.
B. To prevent the plant from entering into a Pressurized Thermal Shock condition.
C ../ To ensure the highest RCS level is being maintained once RCS inventory starts
being lost.
D. To allow for the natural decrease in the post trip decay heat level.
Reasons:
A. If forced flow was not effective in heat removal then natural circ would be
even worse. Also with no source of feedwater natural circ will not
develop.
B. Pressurized Thermal Shock is not a concern on a plant heatup.
C. Correct. Up to this point the inventory in the RCS has not been lost. When
any of these conditions occur the inventory in the RCS is being lost and now
must be replaced by HPI. Since no hole in the RCS exists then the PORV is
opened after HPI flow is verified.
D. By the time the OTSGs have dryed out and the RCS is heating up the decay
heat level of the core has already dropped significantly and further
decreases are very slow to occur.
Tuesday, October 14, 2003 10:40:04 AM 45
QUESTIONS REPORT
for NRC Reviewed SRO BANK
OPS 5-102 Step 3.12
SRO - Direct [Newops 5-102-0031
References provided: None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C D A B C D A B C D Scramb1eRange:A - D
Tier: 3 Group:
Keywords: SRO #99 Cog Level: MEM 3.114.0
Source: B Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14,2003 10:40:04 AM 46
QUESTIONS REPORT
for NRC Reviewed SRO BANK
25. G2.4.41 001
The following plant conditions exist:
- Rx tripped on low RCS pressure from 100% power.
- OTSG tube rupture on the 'A'OTSG (estimated at 250 gpm).
- HPI actuation on low RCS pressure.
- Main Steam Safety Valve on 'A'OTSG will not close.
Use only the above information to classify the event. (Do NOT use EC judgement)
A. Unusual Event
B. Alert
C. * Site Area Emergency
D. General Emergency
Reasons:
A. Using the Fission Product Bamer matrix a total of 5 points is determined
which places the emergency at the Site Area Emergency level. An Unusual
Event would have to be less than or equal to 2 points.
B. Using the Fission Product Bamer matrix a total of 5 points is determined
which places the emergency at the Site Area Emergency level. An Alert
would have to be less than or equal to 4 points.
C. Correct. A stuck open safety valve is an unisolable steam leak outside the
RB with an OTSG leak > 10 gpm. (2 points) ES actuation on low RCS
pressure. (3 points) Total equals 5 points -- Site Area Emergency
D. Using the Fission Product Bamer matrix a total of 5 points is determined
which places the emergency at the Site Area Emergency level. A General
Emergency would have to be greater than 8.5 points.
EM-202 Enclosure 1
SRO - Direct [Newops 5-034-0061
References provided: EM-202
Tuesday, October 14,2003 10:40:04 AM 47
QUESTIONS REPORT
for NRC Reviewed SRO BANK
MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C D A B C D A B C D Scramble Range: A - D
Tier: 3 Group:
Keywords: SRO #IO0 Cog Level: CIA2.314.1
Source: B Exam: CR303301
Test: S Misc: ATK
Tuesday, October 14,2003 10:40:04 AM 48