ML032940409
| ML032940409 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/29/2003 |
| From: | NRC/RGN-II |
| To: | Progress Energy Florida |
| References | |
| 50-302/03-301 50-302/03-301 | |
| Download: ML032940409 (40) | |
See also: IR 05000302/2003301
Text
Draft Submittal
(Pink Paper)
CRYSTAL RIVER AUGUST
EXAM 50-30212003-301
AUGUST 25 29,2003-
1. Senior Reactor Operator Written Exam
QUESTIONS REPORT
for all draft ques
1. 003AA2.03 001
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 after an event the following conditions are observed:
NI-5 54% Imbalance at -1 0
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.
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
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
Tuesday, October 14, 2003 08:36:32AM 1
QUESTIONS REPORT
for all draft ques
Category 1: 1 Category 2: 2
Category 3: SRO #83 Category 4: CIA 3.613.8
Category5: M Category 6: CR303301
Categoryl: S Category 8: ATK
Tuesday, October 14, 2003 06:36:32AM 2
QUESTIONS REPORT
for all draft ques
2. 004A2.09 001
Following a power increase RCS dose equivalent Iodine-131 increased to 1.6 pci/gm with the
sample taken at 0100 on 3-3-03. Additional sample results are as follows:
0500 1.5 FCi/gm 3-3-03
0900 1.4 pCi/gm 3-3-03
1300 1.3 pCi/gm 3-3-03
1700 1.2 pCi/gm 3-3-03
2100 1.1 pCi/gm 3-3-03
0100 1.O pCi/gm 3-4-03
0500 0.9 pCi/gm 3-4-03
How will this impact the plant and what actions, if any, should behave been taken?
A. No additional actions are required other than to request additional sampling of the
secondary plant due to the possibility of increased radiation levels. The 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> TS
requirement for RCS activity has been met.
B. Secondary plant radiation levels will increase within a few hours. A plant
shutdown to Mode 3 with Tave < 500' F is required within 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> of the initial
sample.
C.* A significant increase in radiation levels could occur in the area of the condensate
demins. A plant shutdown should have been started no later than 0100 on 3-4-03
unless VP approval for continued operation was obtained.
D. A significant increase in radiation levels could occur in the area of the condensate
demins. SR 3.4.15.2 is required within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of the initial sample and shutdown
to Mode 3 with Tave < 500" F is required within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of the initial sample.
Reasons:
A. The requirements of TS 3.4.15 are met however CP-155 is not met.
B. If activity had not decreased below 1.OpCi/gm then this would be the
correct action to take.
C. Correct. Per CP-155, Step 4.5.6, the administrative limit has been exceeded
and continued operation greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> must have VP approval.
D. These are the required actions for RCS gross specific activity, not dose
equivalent Iodine-13 1.
Tuesday, October 14.2003 08:36:32 AM 3
QUESTIONS REPORT
for all draft ques
SRO - New
References provided CP-155 & TS 3.4.15
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
Categoly 1: 2 Category 2: 1
Category 3: SRO #88 Category 4: CIA 3.013.9
Category5: N Category 6: CR303301
Categoly7: S Category 8: ATK
Tuesday, October 14, 2003 08:36:32AM 4
QUESTIONS REPORT
for all draft ques
3. 009EK3.06 001
While operating at power RM-A6 is observed to be trending up. MUV-31 is taken to manual
and the following data is gathered for evaluation.
Time 0900 Pzr Lvl - 220" MUT Lvl - 80"
Time 0902 Pzr Lvl - 216" MUT Lvl - 81"
The following data is provided:
Pressurizer level = 12.2 gal/inch MUT level = 30.8 gal/inch
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 14,200308:36:32AM 5
QUESTIONS REPORT
for all draft ques
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 1 2 3 4 5 6 7 8 9
Answer: C C A B C B A D B D Scramble Range: A - D
Category 1: 1 Category 2: 1
Category 3: SRO #76 Category 4: CIA 3.714.0
Category 5 : B Category 6: CR303301
Category 7: S Category 8: ATK
Tuesday, October 14,2003 08:36:32 AM 6
QUESTIONS REPORT
for all draft ques
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 LT1. 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 LT1 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.
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
Tuesday, October 14,2003 08:36:32 AM 7
QUESTIONS REPORT
for all draft ques
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
Category 1: 2 Category2: 2
Category 3: SRO #92 Category 4: CIA 3.513.6
Category5: B Category 6: CR303301
Category7: S Category 8: ATK
Tuesday, October 14,200308:36:32 A M a
QUESTIONS REPORT
for all draft ques
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 2 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: TS 3.3.1
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 E C D A B C Scramble Range: A - D
Category 1: 2 Category 2: 1
Category 3: SRO #89 Category 4: CIA 2.613.8
Category 5 : B Category 6: CR303301
Category? S Category 8: ATK
Tuesday, October 14,2003 08:36:32 AM 9
QUESTIONS REPORT
for all draft ques
6. 0 2 5 ~ ~ 1 . 0001
1
The following plant conditions exist:
- TS required plant shutdown in progress.
- RCS temperature is 285'F.
- Two RCPs are running.
- DHP-1A is 00s due to a broken shaft.
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 most appropriate action@)?
A. Be in Mode 5 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B. Restore either train to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
C. Be in Mode 4 within 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> and Mode 5 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. +
. Be in Mode 4 within 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> and remain in this mode until DHR capability exists.
Reasons:
A. The plant is in Mode 3 and this action is per TS 3.5.3, Condition C (Mode 4).
However, with both DHRnPI trains unavailable the bases recommends
staying in Mode 4 until one train is operable. TS 3.0.3 should be entered.
B. This action is per TS 3.5.2, Condition A. The stem statement does not meet
the second part of this condition. TS 3.0.3 should be entered.
C. These are the correct actions per TS 3.0.3 however the bases for TS 3.5.3
recommends staying in Mode 4.
D. Correct. TS 3.0.3 requires Mode 4 within 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> and the bases for TS 3.5.3 recommends staying in Mode 4 until at least one train is restored.
TS 3.0.3, 3.5.2, 3.5.3 &Bases
SRO - New
References provided: TS 3.0.3,3.5.2,3.5.3 &Bases
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 D D D D D D D D D Items Not Scrambled
Tuesday, October 14,2003 08:36:32 AM 10
QUESTIONS REPORT
for all draft ques
Category 1: 1 Category2: 1
Category 3: SRO #I1 Category 4: CIA 3.914.3
Category 5: N Category 6: CR303301
Categoryl: S Category 8: ATK
Tuesday,October 14,2003 08:36:32 AM
QUESTIONS REPORT
for all draft ques
7. 02602.4.47 001
The following plant conditions exist:
- SW surge tank, SWT-1, is at 9 ft and lowering.
- "A" DC surge tank, DCT-lA, 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-1B.
OPS 4-83 Section 1-4.0.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
Category 1: 1 Category 2: 1
Category 3: SRO #78 Category 4: CIA 3.413.7
Category5: M Category 6: CR303301
Category7: S Category 8: ATK
Tuesday, October 14,2003 083632 AM 12
QUESTIONS REPORT
for all draft ques
8. 0 2 9 ~ ~ 2 . 0001
9
Rev. 1
The following plant conditions exist:
- The plant is at 55% reactor power.
- The ICs +24 volt DC bus has degraded to +18 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 08:36:33AM 13
QUESTIONS REPORT
for all draft ques
OPS 4-12 Section 2-2.0.D: OPS 4-14 Section 1-8.0.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
Category 1: 1 Category 2: 1
Category 3: SRO #79 Category 4: CIA 4.414.5
Category 5 : B Category 6: CR303301
Category7: S Category 8: ATK
Tuesday, October 14,2003 08:36:33 AM 14
QUESTIONS REPORT
for all draft ques
9. 03462.3.10 001
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-1A 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. Must stop due to insufficient level for shielding required to reduce radiation levels
on the Spent Fuel floor to within limits.
C. * Must stop due to insufficient volume for iodine retention if a fuel handling 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 1-4.0A.3; TS 3.7.13 LCO and Bases
SRO - Direct [Newops 4-29-0011
References provided: TS 3.7.13 & Bases
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
Category 1: 2 Category2 2
Category 3: SRO #93 Category 4: MEM 3.113.3
Category5: B Category 6: CR303301
Category I: S Category 8: ATK
Tuesday, October 14, 2003 08:36:33AM 15
QUESTIONS REPORT
for all draft ques
10. 03SEA2.13 001
The "A" OTSG has a tube leak. RM-A12 , Main Condenser Off Gas Radiation Monitor, has
slowly increased to a stable reading of 188 cpm. Which of the following sections of CP-152,
Primary to Secondary Leakage, is now applicable?
A. Increased Monitoring
B. Action Level 1
C. Action Level 2
D. Action Level 3
Reasons:
A.,B.,C.,&D. 188 cpm = 5.7 gpd
2 5 gpd and < 30 gpd is in the 'Increased Monitoring'
sections of CP-152.
CP-152 and RM-A12 Conversion Table (Simulator Verison)
SRO - Direct
References provided: CP-152 and RM-A12 conversion table
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
Category 1: 1 Category 2: 1
Category 3: SRO #SO Category 4: CIA 3.113.7
Category5: B Category 6: CR303301
Category 7: S Category 8: ATK
Tuesday, October 14,2003 08:36:33AM 16
QUESTIONS REPORT
for all draft ques
11. 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.
Details 1. 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.
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.
Tuesday, October 14,2003 08:36:33AM 17
QUESTIONS REPORT
for all draft ques
OPS 5-94 Section 1-4.0.D
SRO - New
References provided: None
MCS Time: 1 Points: 00 Ver! n: 0 1 2 3 4 5 6 7 8 9
Answer: B B B B B B B B B B Items Not Scrambled
Category 1: 1 Category2: 1
Category 3: SRO #SI Category 4: MEM 4.414.4
Category 5: N Category 6: CR303301
Category 7: S Category 8: ATK
Tuesday. October 14,2003 08:36:33 AM 18
QUESTIONS REPORT
for all draft ques
12. 055EG2.4.07 001
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.
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
Tuesday, October 14, 2003 08:36:33AM 19
QUESTIONS REPORT
for all draft ques
Category 1: 3 Category 2:
Category 3: SRO #82 Category4: MEM 3.113.8
Category 5 : B Category 6: CR303301
Category 7: S Category 8: ATK
Tuesday, October 14,200308:36:33AM 20
QUESTIONS REPORT
for all draft ques
13.061A2.05 001
Rev. 1
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 corner 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 ,
EFWIAFW Control, should be entered.
Tuesday, October 14,200308:36:33 AM 21
QUESTIONS REPORT
for all draft ques
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 4-3 1 Section 1-4.O.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
Category 1: 2 Category 2: 1
Category 3: SRO #90 Category 4: CIA 3.113.4
Category 5: N Category 6: CR303301
Category 7: S Category 8: ATK
Tuesday, October 14,200308:36:33 AM 22
QUESTIONS REPORT
for all draft ques
14. 06162.1.34 001
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
Category 1: 1 Category 2: 2
Category 3: SRO #84 Category 4: MEM 2.513.3
Category 5: N Category 6: CR303301
Category 7: S Category 8: ATK
Tuesday, October 14, 2003 08:36:33AM 23
QUESTIONS REPORT
for all draft ques
15. 064A1.03001
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-I 7 N B 51 kW DCP-1NB 79 kW
AHF-18AL3 50 kW EFP- 1 698 kW
AHF-19AB 18 kW MUP-1NBK 694 kW
BSP-INB 222 kW RWP-2NB 554 kW
CHP-1A/B 19 kW RWP-3NB 198 kW
CHHE-1NB 196 kW SWP-1N B 497 kW
A. e 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-IB) + 198 kW (RWP-3B) + 79 kW (DCP-1B) = 3349
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-lB)=3201 kW.
OPS 4-06 Section 1-2.O.E.l.d)
-
SRO Direct [Newops 4-06-0101
References provided: None
Rev. 0 to NRC on 4-1 1-03
Tuesday, October 14,2003 08:36:33A M 24
QUESTIONS REPORT
for all draft ques
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
Category 1: 2 Category2: 1
Category 3: SRO #91 Category 4: CIA 3.213.3
Category 5: B Category 6: CR303301
Category? S Category 8: ATK
Tuesday, October 14,2003 08:36:33 AM 25
QUESTIONS REPORT
for all draft ques
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 S 6 7 8 9
Answer: B A C D B C B C B D Scramble Range: A - D
Category 1: 1 Category2 2
Category 3: SRO #85 Category 4: CIA 3.814.1
Category 5: B Category 6: CR303301
Category7: S Category 8: ATK
Tuesday, October 14,200308:36:33AM 26
QUESTIONS REPORT
for all draft ques
17. BWA02AAI.l 001
The plant has experienced a loss of NNI-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 directions would you give 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 MUV-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 NNI-X.
C. Correct. On a loss of NNI-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 3.14 & 3.21; OPS 4-9 Section 1-8.B.4; OPS 4-52 Section 1-4.2
NRCM98
SRO - Direct mewops 4-52-01 11
References provided None
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 S 6 7 8 9
Answer: C D A B C D A B C D Scramble Range: A - D
Category 1: 1 Category2: 2
Category 3: SRO #86 Category 4: MEM 4.0/3.8
Category5: B Category 6: CR303301
Category7: S Category 8: ATK
Tuesday, October 14,2003 08:36:33 AM 27
QUESTIONS REPORT
for all draft ques
18. BWA05G2.2.20 001
A fault on the Unit #2 Startup transformer has caused a voltage imbalance in the 230 KV
switchyard resulting in a loss of offsite power to Unit #3. The "A" EDG energized the "A" ES
bus as designed but the "B" EDG did not start. As the CRS what instructions would you give
to the RO?
A. Write a Work Request and have maintenance scheduled.
B.* Ensure Enclosure 2, Failed EDG Recovery, is performed per AP-770.
C. Ensure Enclosure 1, Recovery of a Faulted ES Bus, is performed per AP-770.
D. Start the EDG and utilize OP-703, Plant Distribution System, and try a one time
closure of breaker 3210, "B" EDG output breaker.
Reasons:
A. Actions in AP-770 should restore the bus.
B. Correct. Since the bus is not faulted Enclosure 2 should be used.
C. Enclosure 2 should be used.
D. Step 3.2.12 allows a one time reclosure if a breaker trips and no fault
indications are apparent but the actions in AP-770 take priority.
AP-770 Step 3.40
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
Category 1: 1 Category 2: 2
Category 3: SRO #87 Category 4: MEM 2.213.3
Category5 N Category 6: CR303301
Category7: S Category 8: ATK
Tuesday, October 14,2003 08:36:33AM 28
QUESTIONS REPORT
for all draft ques
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. 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 TS 5.2
MCS Time: 1 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
Category 1: 3 Category 2:
Category 3: SRO #94 Category 4: MEM 2.313.4
Category5: M Category 6: CR303301
Category7: S Category 8: ATK
Tuesday, October 14, 2003 08:36:33AM 29
QUESTIONS REPORT
for all draft ques
20. G2.1.12 001
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. * 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 & 3.0.6
SRO - Direct [Newops ROT 5-01 1271
References provided TS 3.7.9,3.8.1 & 3.0.6
Rev. 0 to NRC on 4-1 1-03
MCS Time: 1 Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer: C D 3 A A D C D C D Scramble Range: A - D
Tuesday, October 14,2003 08:36:33 AM 30
QUESTIONS REPORT
for all draft ques
Category 1: 3 Category 2:
Category 3: SRO #95 Category 4: CIA 2.914.0
Category5: B Category 6: CR303301
Category 7: S Category 8: ATK
Tuesday, October 14, 2003 08:36:33AM 31
QUESTIONS REPORT
for all draft ques
21. G2.2.22 001
During three RCP operation (RCP-ID secured) the following readings are recorded:
- RCS total flow 105 x 106 l b m h
- RCSThot "A" loop 603" F "B" Loop 603' F
- RCS pressure "A" loop 2055 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. & D. One DNB parameter is not within limits.
B. The DNBR safety limit has not been exceeded per 2.1.1-1.
C. Correct. Total flow is required to be 2 99.7 E6 lbm/hr with 3 RCPs and
RCS pressure, in the loop with 2 RCPs running, is required to be >
2064 psig.
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 mewops 4-060-0131
References provided: TS 3.4.1, Figure 2.1.1-1 and COLR
MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: C D C B A C D B B B Scramble Range: A - D
Category 1: 3 Category 2:
Category 3: SRO #96 Category 4: CIA 3.414.1
Category5: M Category 6: CR303301
Category7: S Category 8: ATK
Tuesday, October 14, 2003 08:36:33AM 32
QUESTIONS REPORT
for all draft ques
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 lom6%.
- 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: FP-203
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
Category 1: 3 Category 2:
Category 3: SRO #97 Category 4: CIA 2.613.5
Category 5 : B Category 6: CR303301
Category7: S Category 8: ATK
Tuesday, October 14,2003 083633 AM 33
QUESTIONS REPORT
for all draft ques
23. (32.3.06 001
The following plant conditions exist:
- Plant is in Mode 4.
- A waste gas tank release has been in progress for 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
- Notified by Chemistry that the RM-A2 particulate sampler is non-functional.
- RM-A4 indicates a slow, increasing trend.
Which of the following actions should be be taken?
The release:
A. must be secured until the sampler is declared operable.
B. may continue until completion since RM-A2 Gas will secure the release if its high
setpoint is reached.
C. may continue for up to one hour with no additional actions.
D. * may continue for more than one hour as long as samples are continuously taken
with auxiliary sampling equipment.
Reasons:
A. The release can continue if additional actions are taken.
B. While RM-A2 Gas will secure the release if the high setpoint is reached the
ODCM requires additional actions.
C. The release could continue for up to one hour if RM-A4 did not indicate an
increasing trend.
D. Correct. As long as continuous sampling is in progress the release may
continue.
ODCM Section 2.2, Table 2-3 Action 25
NRCN99
SRO - Direct [Newops 4-025-0151
References provided: ODCM
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
Tuesday, October 14,200308:36:34 AM 34
QUESTIONS REPORT
for all draft ques
Category 1: 3 Category 2:
Category 3: SRO #98 Category4: CIA2.113.1
Category 5: B Category 6: CR303301
Category 7: S Category 8: ATK
Tuesday, October 14,2003 08:36:34 AM 35
QUESTIONS REPORT
for all draft ques
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
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..4 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 08:36:34 AM 36
QUESTIONS REPORT
for all draft ques
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 Scramble Range: A - D
Category 1: 3 Category 2:
Category 3: SRO #99 Category 4: MEM 3.U4.0
Category 5 : B Category 6: CR303301
Category7: S Category 8: ATK
Tuesday, October 14, 2003 08:36:34AM 37
QUESTIONS REPORT
for all draft ques
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 Barrier 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 Barrier 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 Barrier 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
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 14,200308:36:34AM 38
QUESTIONS REPORT
for all draft ques
Category 1: 3 Category 2:
Category 3: SRO #lo0 Category 4: CIA 2.314.1
Category 5: B Category 6: CR303301
Category7 S Category 8: ATK
Tuesday, October 14, 2003 08:36:34AM 39