ML033460189
| ML033460189 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/15/2003 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Gordon Peterson Duke Energy Corp |
| References | |
| 50-413/03-301, 50-414/03-301 50-413/03-301, 50-414/03-301 | |
| Download: ML033460189 (28) | |
See also: IR 05000413/2003301
Text
Final Submittal
2 CATAWBA APRIL 2003 EXA
50-413 & 50-414/2003-301
-
MARCH 31 APRIL 4 &
APRIL 30,2003
- +----*=--.UarrU-."~--~ ..-_.
I.
I
Senior Operator Written Examination
NRC Officiai Use Only
Nuclear Regulatory Commission
Senior Reactor Operator Licensing
Examination
Catawba Nuclear Station
This document is removed from
Official Use Only category on
Date of examination
NRC Official Use Only
ES-401 Site-Specific SRO Written Examination Form ES-401-8
Cover Sheet
U.S. Nuclear Regulatory Commission
Site-Specific
SRO Written Examination
Name:
Date: 411812003 FaciIityIUnit: Catawba
Region: II Reactor Type: W
Start Time: Finish Time:
Instructions
Use the answer sheets provided to document your answers. Staple this cover sheet on top of
the answer sheets. To pass the examination you must achieve a final grade of at least 80.00
percent overall, with a 70.00 percent or better on the SRO-only items if given in conjunction
with the RO exam; SRO-only exams given alone require an 80.00 percent to pass. You have
eight hours to complete the combined examination, and three hours if you are only taking the
SRO portion.
Applicant Certification
All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature
ResuIts
RO I SRO-Only I Total Examination Values -I I~ Points -
Applicant's Scores --- I I Points
~~ ~ ~
Applicant's Grade ~ I I - Percent -
NUREG-1021, Draft Revision 9
Question #l Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 1 is operating in mode 3 preparing for a reactor startup following a
refueling outage. Given the following events and conditions:
NC Pump 1C is running.
Reactor trip breakers are tagged open.
Maintenance determines that the MOV test data from the outage
indicates that the torque switches for IND-65B (NO TRAIN I B HOT
LEG LVJJISUL) have been set too low.
The SWM requests OSM approval to tag closed 1ND-65B for repairs.
Which one of the following statements correctly describes the operating
restrictions and implications of tagging closed lND-65B?
REFERENCES PRO WDED:
A. 1ND-65B may be tagged closed for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, if the steam
generator in the running NC loop is operable.
B. 1ND-65B may not be tagged closed because this would make both
trains of ND inoperable.
C. 1ND-65B may not be tagged closed, unless two NCPs are running
with operable steam generators.
D. 1ND-65B may be tagged closed, if 1ND-65B is restored to
operation prior to transitioning to mode 2.
Ques-096.1 For Official Use Only Page 1
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Question #2 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 1 is shutdown, in mode 5, following a S/G tube rupture event.
Maintenance is dewatering the main condenser into a portable holdup tank
outside the turbine building (for disposal offsite). Upon completion of the
dewatering and piping flushes, the tank is contains 500 gallons. Given the
following radiochemistry analysis of the tank contents:
Total tank activity = 18 Ci with a combined half life of 6 days
Tritium activity = 1 Ci with a half life of 12.6 years
Noble gas activity = 5 Ci with a half life of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
Which one of the following action(s) (if any) meets plant requirements for
these conditions?
REFERENCES PRO WDED:
A. Suspend additions and allow the contents to decay for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
B. Add 300 gallons of demineralized water to dilute the curie
concentration below limits.
C. Remove 25 gallons of tank contents and the curie content will be
within SLC limits.
D. The tank is within limits of the SLC, further additions may be
allowed.
Qu es-3 23.2 For Official Use Only Page 2
Question #3 Catawba Nuclear Station SRO Exam
1 Pt(s) E-3 (Steam Generator Tube Rupture) step 18 reads as follows:
WHEN P-11 PZR SB BLOCK
PERMISSIVE status light (1SI-18) is lit,
THEN:
-a. Depress ECCS Steam Pressure BL0CKpushbuttons.
Pressurizer pressure is 1985 psig when the SRO transitions to ECA-3.1.
After the transition into ECA-3.1, which one of the following statements is
correct with regard to this step?
A. The step is applicable only while in E-3. The SRO shall not
return to the step when notified that permissive status light is
LIT.
B. The step is applicable only while in E-3. The RO shall
immediately perform the actions of sub step lSa, only after
reentering E-3 upon completion of ECA-3.1.
C. The step is applicable while in E-3 and after transition to
ECA-3.1 until alternative guidance is provided. The RO shall
immediately perform the actions of sub step 18a when the
permissive status light is LIT and report this action to the SRO.
D. The step is applicable while in E-3 and after transition to
ECA-3.1 until alternative guidance is provided. The RO shall
notify the SRO that the permissive status light is LIT and the
SRO will return to step 18a and direct the action.
Ques-339.2 For Official Use Only Page 3
Question #4 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 1 is responding to a main steam line break into containment.
Given the following events and conditions:
The operators completed E-0 (Reactor TrQ and Safe& Injection) and
transitioned to E-2 (Faulted Steam Generator Isolation)
A RED PATH on Containment Integrity occurred and the operators
transitioned to FR-Z. 1 (Response to High Containment Pressure) at step 8
of E-2.
A RED PATH on NC Integrity occurred and the operators transitioned to
FR-P. 1 (Response to Imminent Pressurized Thermal Shock Condition)
fkom step 4 of FR-Z. 1.
Following the completion of FR-P. 1 and a report from the STA that all CSFs
are now GREEN, what is the correct procedure transition?
A. Return to E-2 step 1 and continue.
B. Return to E-2 step 8 and continue.
C. Return to FR-Z.l step 4 and complete the procedure, then return
to E-2 step 8.
D. Enter ES-0.0 (Redlagnosis) and rediagnose the situation.
,
Ques-357 For Official Use Only Page 4
Question #5 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 1 is responding to a faulted steam generator from 100% power. Given
the following events at their respective times:
0200 - a reactor trip occurred, the crew entered E-0, (Reactor Trip or
Safeg Injection)
02 10- transitioned to E-3, (Steam Generator Tube Rupture)
02 15 - entered FR-Z. 1, (Response to High Containment Pressure), on a
valid orange path
0220- safety injection was actuated manually after a failure of auto S/I
0225 - completed FR-Z. 1
If the SRO determined that they were responding to the event in the wrong
procedure, which one of the following is the EARLIEST time that the SRO
could have transitioned to ES-0.0, (Rediagnosis)?
A. 0211
B. 0216
c. 0221
D. 0226
Ques-478.1. For Official Use Only Page 5
Question #6 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 2 is conducting a containment purge in accordance with
OP/2/PJ6450/0 1S(C0ntainmenf Pwge System). Given the following
conditions provided on the GWR permit:
Most restrictive release rate = 16000 CFM
Recommended release rate = 16000 CFM FJ(3T--:T m a m F - 3 9 C L )
0 2EMF-39(L) trip 1 setpoint = 1.OE5 CPM
2EMF-39(L) trip 2 = 2.OE5 CPM @@401d6 AT 0200 5 To
0 q'@MF-36(L) is in service @L7CB&rOW& 64 WIm,
Time 0215 0230 0245
Release rate (CFM) 15750 16800 15900 16500
EMF-39 (CPM) 2.2E5 1.8E5 3.2E5 3.2E5
If the operators restart the VP purge whenever allowed by procedure, what is
the EARLIEST time that the operators are required to terminate the
gaseous release and obtain a revised GWR?
A. 0200
B. 0215
C. 0230
D. 0245
Ques-479.3 For Official Use Only Page 6
Question #7 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 1 is in mode 6 and refueling operations are in progress. Given the
following conditions and events:
The Fuel Handling Manipulator Crane Operator (FHMCO) has indexed
the mast over the location where fuel assembly H-8 will be inserted.
0 All conditions and indications on the Fuel Handling Manipulator Crane
are satisfied for inserting the he1 assembly.
Which one of the following statements describes the responsibility of the
Fuel Handling SRO associated with inserting the fuel assembly?
A. Must give his permission to the OATC prior to inserting the
assembly. Operates the Latch/Unlatch switch. Verifies the fuel
handlers are documenting satisfactory completion of each rod
latch.
B. Must obtain permission from the OATC prior to inserting the
assembly. Operates the Latch/Unlatch switch. Documents
satisfactory completion of each assembly insertion.
C. Supervises reactivity management and verifies maintenance
technicians are continuously monitoring the load cell. Must
obtain permission from the OATC prior to inserting the
assembly.
Ques-483.1 For Official Use Only Page 7
Question #8 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 1 was shutdown in mode 6. Engineering reported that a recent test on
the 1B KC heat exchanger showed that fouling had reduced its heat transfer
capability.
0 The heat exchanger was now incapable of meeting the design A
temperature with a maximum (FSAR) lake water temperature of 90 O F .
0 The design A temperature could be met with lake water with a maximum
temperature of 80 O F .
0 Current lake temperature is 68 O F .
0 Lake temperature is not expected to reach 80 O F for another 30 days.
0 The plant is expected to remain in mode 6 for another 30 days.
Which of the following statements correctly characterizes the operability of
the KC system?
REFERENCES PROVIDED
A. The B train of KC is inoperable because it is unable to maintain
KC system temperatures below 120°F during a plant shutdown.
B. The B train of KC is inoperable because it is unable to maintain
normal KC temperatures below 90 O F .
C. The B train of KC is operable but degraded as long as Lake Wylie
temperature remains below 90 O F .
D. The B train of KC is operable but degraded as long as Lake Wylie
temperature remains below 80 O F .
Ques-485.2 For Official Use Only Page 8
Question #9 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 1 experienced a LOCA with a breach of containment at 0200. The
OSM assumed the duties of the Emergency Coordinator and declared a
general emergency at 02 10. The initial recommended protective actions at
0225 were as follows:
0 Shelter zones A2, A3, B2, C2, D2, E2, F2, F3
0 Evacuate zones AO, A l , B1, C1, D1, El, F1
At 0235, the initial dose projection infomiation was presented to the OSM.
Given the following conditions at 0245:
0 Wind direction = 450"
0 Wind speed = 4 MPH
Projected dose at the site boundary
0 TEDE = 250 mrem
0 CDE thyroid = 400 men1
0 Containment radiation levels
0 1EMF53A = 950 R/hr
0 1EMF53B = 955 R/hr
Which one of the following protective action recommendations are correct in
accordance with RP/O/A/5000/05?
REFERENCES PROVIDED:
A. Change the protective action recommendation in zones A1 and
B1 from evacuate to shelter.
B. Extend the evacuation to zones A2, A3, B2, C2
C. Extend the evacuation to zones D2, E2, F2
Ques-491.1 For Official Use Only Page 9
Question # l O Catawba Nuclear Station SRO Exam
1 Pt(s) A LOCA occurred on Unit 1 at 2:OO AM. Given the following events and
conditions:
020 1 A containment air release was in progress and was immediately
terminated.
0205 The control room operators are responding to the events in E- 1.
0210 The OSM has assumed the role of the Emergency Coordinator.
0215 A Site Area Emergency is declared
0230 Completed initial notification of the State and Local authorities for
declaration of a site area emergency
0240 The OSM notes the following plant conditions and determines the
appropriate classification for the following indications:
Containment pressure indicates 18 psig
Containment Hydrogen concentration is 1.5%
Containment valve VQ-2B failed to isolate on phase A signal.
Core exit T/Cs indicate temperatures of 1300°F
RVLIS lower range level indicates 90%
lEMF-53AB indicate 85 R/hr
The Operators enter FR-C. 1 (Response to Loss of Coi-e Cooling)
If the OSM determines the appropriate classification when the conditions are
first indicated, which one of the following statements correctly describes the
first notification that is required?
REFERENCES PROVIDED:
A. Notify the State and Local authorities that the plant has declared
a general emergency no later than 0255.
B. Notify the NRC Headquarters Operations Center of plant
conditions no later than 0300.
C. Notify the State and Local authorities that the plant has declared
a general emergency no later than 0310.
Ques-502.1 For Official Use Only Page 10
Question #ll Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 2 is conducting a plant shutdown from 100% power. Given the
following events and conditions:
Reactor power is 6%
All manual actions have been taken as required in the procedures
Intermediate Range channel N-36 fails HIGH.
Which one of the following statements correctly describes how this failure
affects the reactor shutdown and subsequent operation of the Nuclear
Instrumentation System?
A. The reactor will trip; the source range detectors will reenergize
when N-35 decreases to the proper setpoint.
B. The reactor will trip; the source range detectors will have to be
manually reenergized.
C. The reactor will not trip; the source ranges will reenergize when
N-35 decreases to the proper setpoint.
D. The reactor will not trip; the source ranges will have to be
manually reenergized.
Ques-718 For Official Use Only Page 11
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Question #12 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 1 recently shut down. Given the following events and conditions:
NCS temperature is 230°F.
Both trains of ND are operable with A train in service
KC loops A and B are operating.
CAPT is tagged for maintenance.
CA pump 1B and CA pump 1A are isolated for differential pressure
testing.
Engineering has reported that a test on the 1B KC heat exchanger showed
that fouling had reduced its heat transfer capability below the minimum
design value.
The plant is expected to remain in mode 4 for another 7 days for special
testing.
Which one of the following is the FIRST required action that must be taken?
REFERENCES PRO VTDED:
A. Return at least one motor driven CA pump to operable status or
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. Return at least one motor driven CA pump to operable status or
be in mode 5 within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
C. Clean the 1B KC heat exchanger within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> o r be in mode 5
within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
D. Clean the 1B KC heat exchanger within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> o r be in mode 5
within the next 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />.
Ques-936.1 For Omcial Use Only Page 12
Question #13 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 1 is conducting a containment air release at 85% power. Given the
following events and conditions:
The last containment atmosphere sample at 0600 was consistent with
the current gaseous waste release (GWR) permit.
The latest air release was started at 1400.
The release flow indicator on 1MC-5 reads 200 CFM.
0 1EMF-36 (Unit Yenl Gas Monitor) is at the trip 1 setpoint.
The VQ flow totalizer is out of service.
Which of the following conditions reported at 1700 requires isolation of the
air release until a new GWR permit is approved?
A. The VQ air release flow indicator on 1MC-5 fails high.
B. 1EMF-39 (Contairzmerzt Gas Monitor.) increases to Trip 2 alarm
due to a power supply fluctuation.
C. The 1800 containment atmosphere sample must be delayed for 4
hours due to sample valve repairs.
D. 1EMF-37 (Unit Vent Iodine Monitor) increases to Trip 2 alarm
due to a fuel pin failure.
Ques-9 62 For O f k i a l Use Only Page 13
Question #14 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 1 is operating at 65% power. Given the following events and conditions:
Annunciator 1AD-2, B/9 (Control Rod Bank Lo-Lo Limit) failed to
illuminate during annunciator testing.
IAE has reported that a failed annunciator card must be replaced but the part
will not be available until next week.
Which one of the following actions is required in response to this failed alarm?
A. The shift work manager must direct reactor engineering to initiate a
temporary modification to change the Coiztrof Rod Bank Lo Limit
(1AD-2, A/9) annunciator setpoint to the Control Rod Bank Lo-Lo rod
insertion limit.
B. The unit supervisor must initiate a control panel information tag for
the 1AD-2, B/9.
C. The operations shift manager shall ensure that alternate indications a r e
monitored to duplicate the function of the failed annunciator.
D. The reactor operator must enter the requirement to verify RIL limits
manually during transients in the shift turnover log.
Ques-969 For Official Use Only Page 14
Question #I5 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 1 was operating at 100% power when the pressurizer spray line
developed a leak. Which one of the following conditions would cause the
safety injection system to be inoperable during this accident?
A. 1NI-118A (NIPump 1A C-LegINJISOL) and 1NI-15OB (NI
Pump 1A C-Leg INJISOL) are open with power applied
B. 1NI-162A (NI to C-Legs INJHDR ISOL) is closed with power
applied
C. 1NI-121A (NIPunzp 1A To H-Legs B&C) and 1NI-152B (NI
Pump 1B To -LegsA&D) are closed with power removed
D. 1NI-IOOB (NIPMPSSUCT FROMFWST) is open with power
removed
Ques-988 For Official Use Only Page 15
Question #16 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 1 was operating at 100% power when the following containment floor
and equipment sump indications were noted:
Time Sump A level indication Sump B level indication
0200 4.1 5.9
0215 4.2 6.0
023 0 4.3 6.1
0245 4.4 6.2
0300 6.5 6.9
A chemistry sample from the sumps shows the presence of boric acid in the
water.
If the OAC is unavailable, which one of the following statements correctly
describes the required actions by Tech Specs?
REFERENCES PRO WDED:
A. Shutdown to mode 3 required no later than 0815
B. Shutdown to mode 3 required no later than 0900
C. Shutdown to mode 3 required no later than 1300
D. Operations may continue indefinitely.
Ques-989 For Official Use Only Page 16
Question #17 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 1 is operating at 100% power. Given the following events and
conditions:
CF REG valves drift close
Reactor trip occurs on S/G Lo-Lo level
ES-0.1 (Reactor Trip Response) has been entered
Total CA flow indicates 460 gpm
Steam dumps do not operate
S/G PORVs do not open in AUTO
S/G pressure in all S/Gs is 1 150 psig
All S/G NR levels are 15%
NC system pressure 2345 increasing
NC PORVs do not operate
Which one of the following procedures should be implemented?
REFERENCES PROVIDED:
A. FR-H. I (Loss Of Secondary Heat Sink)
B. FR-H.4 (Response To Loss Of Normal Steam Release Capabilities)
C. AP-22 (Loss of Iiistrwnient Air)
D. AP-29 (Loss of Vital 01 Aux Control Power)
Ques-10 00 For Official Use Only Page 17
Question #18 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 1 was operating at 100% power, all rods out at 226 steps. Given the
following events and conditions:
0 A runback occurs
Reactor power is lowered to 60%
0 Rod D-4 is stuck out at 226 steps
Which one of the following statements correctly describes the indications for
this stuck rod?
REFERENCES PROVIDED:
A. Core exit T/C T-3 is lower than T-61
N-43 is lower than N-44
B. Core exit T/C T-3 is higher than T-61
N-43 is lower than N-44
C. Core exit T/C is T-3 lower than T-61
N-43 is higher than N-44
D. Core exit T/C T-3 is higher than T-61
N-43 is higher than N-44
Ques- 1001 For Official Use Only Page 18
Question #19 Catawba Nuclear Station SRO Exam
1 Pt(s) Fire suppression valve position is currently verified semiannually. The
required review of fire suppression valve position reveals that the valves
were in the correct position 98.5% of the time.
Which one of the following actions should be taken concerning the frequency
of performing the valve position check?
REFERENCES PROVIDED:
A. The check could be decreased to an annual frequency.
B. The check should continue on a semiannual frequency.
C. The check should be increased to a quarterly frequency.
D. The check should be increased to a monthly frequency.
Ques-1002 For Official Use Only Page 19
Question #20 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 2 was shutdown in accordance with OP/2/A/6 100/002 (Controlling
Procedure for Unit Shutdown) is in progress. Given the following events and
conditions:
I&E was testing the safety injection actuation relay for the 2B NI pump.
A human error by a technician caused the NI pump to start
The 2B NI pump injected into the NC system
Which one of the following is the correct requirement for notifying the
NRC?
REFERENCES PROVIDED:
A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> notification in accordance with lOCFR50.72
B. 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification in accordance with 10CFR50.72
C. 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification in accordance with 10CFR50.72
D. 60 day notification in accordance with 10CFR50.73
Ques-1003 For Official Use Only Page 20
Question #21 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 1 is operating at 50% power. Given the following events and
conditions:
0 Diesel air compressor is out of service for maintenance
VI compressors D, E, and F are running
VI and VS pressure were decreasing slowly due to an air leak
VI and VS air pressures are equalized at 74 psig
If all air system components operate as designed (no component failures
other than the air leak), which one of the following statements correctly
describes the location of the air leak and the required action to isolate the VI
system?
REFERENCES PROVIDED:
A. An air leak exists between 1VS-78 and the VS air receivers.
1VS-78 must be closed to isolate the VS leak from the VI system.
B. An air leak exists between 1VS-78 and 1VI-500 in the VS oil
removal filters. 1VS-78 must be closed to isolate the VS leak
from the VI system.
C. An air leak exists downstream of a VI system purge exhaust
muffler, The VI exhaust muffler must be manually isolated.
D. An air leak exists between 1VI-12 and the 1A VI air receiver.
The 1VI-12 must be closed to isolate the VI leak.
Ques-1004 For Official Use Only Page 2 1
Question #22 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 2 is responding to a LOCA and trip from full power,
Given the following conditions:
A safety injection has occurred
0 Train B Sp signal failed to actuate (automatically and manually)
0 The 2A NS pump started automatically
The 2B NS pump was started manually by an operator
0 The Ss signal and sequencer have been reset
0 The Train A Sp signal has not been reset
0 Both pumps were stopped for shifting suctions to the containment sump
0 Containment pressure is 2.5 psig
Following the completion of the swapover, which one of the statements
correctly describes the operation of the NS pumps?
A. The operator will need to manually restart the 2A and 2B NS
pumps.
B. The operator will need to manually restart the 2B NS pump only.
C. No action required because containment pressure is less than 3
psig.
Ques-1005 For Official Use Only Page 22
Question #23 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 1 was operating at 100% power when a LOCA occurred. Given the
following events and conditions:
The Crew has entered E-0 (Reactor Trip OY Safety Injection)
0 Containment pressure reached 5 psig
0 The inadequate core cooling monitor indicates -10 O F subcooling
0 All NI and NV pumps have malfunctioned and will not start.
What action (if any) should the crew take regarding the NCPs?
A. Secure all the NCPs.
B. Secure 3 NCPs and leave 1 running.
C. No action, the NCPs must continue to run.
D. Monitor trip parameters and secure the NCPs if trip parameters
are reached.
Ques-1006 For Official Use Only Page 23
Question #24 Catawba Nuclear Station SRO Exam
1 Pt(s) A Unit 1 startup is in progress in accordance with OP/l/A6 1OO/OO 1
(Controlling Procedure for Unit Startup). Given the following events and
conditions:
Auxiliary steam from Unit 2 was being used for turbine warming.
NC system pressure is 2235 psig
Steam dumps are controlling NC Tave at 557 F
The crew is preparing to restore AS to a normal alignment by closing 1AS-4,
(Main Steam to A S HDR CTRL Bypass).
Who should be notified prior to the operator closing 1AS-4?
A. Plant personnel should be notified to remain clear while closing
the valve.
B. The NLO in the field should be notified to monitor the closing of
the valve.
C. The CRSRO should be notified to expect an increase in unit 2
generator megawatts.
D. The unit 2 CRO should be notified that reactor power may
decrease slightly.
Ques-1007 For Official Use Only Page 24
~~
Question #25 Catawba Nuclear Station SRO Exam
1 Pt(s) Unit 1 is operating at 100% power with a lgpm condenser tube leak present.
Given the following plant conditions and events:
0 8:OO AM Chemistry reports that secondary chlorides have increased to
action level 3.
0 8: 15 AM Power reduction in accordance with OP/l/A/6100/003
(Controlling Procedure For Unit Operation) initiated.
0 8:45 AM Chemistry reports that chloride sample analysis was verified
correct.
0 2:OO PM power has been reduced to 35%.
Which one of the following actions must be performed at 2:OO PM?
REFERENCES PROVIDED:
A. Initiate a rapid power reduction in accordance with AP-9 (Rapid
Do wizpower).
B. Continue power reduction in accordance with OP/l/A/6100/003
(Controlling Procedure For Unit Operation).
C. Enter OP/l/A/6100/002 (Controlling Procedure For Unit
Slzutdo wn).
I). Trip the reactor and enter E-0 (Reactor Trip or Safety Injection).
Ques-1008 For Official Use Only Page 25