ML031250637

March/April 50-413/2003-301 Exam-Final SRO Written Exam

ML031250637
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: ML031250637 (28)

See also: IR 05000413/2003301

Text

Final Submittal

CATAWBA EXAM 2003-301

50-413 & 50-414

March 31 - April 4 &

April 10, 2003

1. senior operator Written Examination

NRC Official 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

Applicant Information

Name:

Date: 4/18/2003 Facility/Unit: Catawba

Region: II Reactor Type: W

Start Time: Finish Time:

Instructions

of

Use the answer sheets provided to document your answers. Staple this cover sheet on top

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

the

eight hours to complete the combined examination, and three hours if you are only taking

SRO portion.

Applicant Certification

All work done on this examination is my own. I have neither given nor received aid.

Applicant's Signature

Results

RO / SRO-Only / Total Examination Values /_ / Points

Applicant's Scores / / Points

Applicant's Grade / / Percent

NUREG-1021, Draft Revision 9

Question #l Catawba Nuclear Station SRO Exam

a

I Pt(s) Unit I is operating in mode 3 preparing for a reactor startup following

refueling outage. Given the following events and conditions:

• NC Pump IC is running.

• Reactor trip breakers are tagged open.

• Maintenance determines that the MOV test data from the outage

indicates that the torque switches for 1ND-65B (ND TRAIN lB HOT

LEG INJ ISOL) 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 IND-65B?

REFERENCES PROVIDED:

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.

For Official Use Only Page 1

Ques_096.1

Question #2 Catawba Nuclear Station SRO Exam

1 Pt(s) Unit I 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 = I 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 PROVIDED:

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.

For Official Use Onlv Page 2

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Catawba Nuclear Station SRO Exam

Question #3

I Pt(s) E-3 (Steam Generator Tube Rupture) step 18 reads as follows:

WHEN "P-1I PZR S/I BLOCK

PERMISSIVE" status light (ISI-18) is lit,

THEN:

_a. DepressECCS Steam Pressure "BLOCK" pushbuttons.

1.

Pressurizer pressure is 1985 psig when the SRO transitions to ECA-3.

statements is

After the transition into ECA-3. 1, which one of the following

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 18a, 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

the

notify the SRO that the permissive status light is LIT and

SRO will return to step 18a and direct the action.

Page 3

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quesj- .L

Question #4 Catawba Nuclear Station SRO Exam

I Pt(s) Unit I is responding to a main steam line break into containment.

Given the following events and conditions:

• The operators completed E-O (Reactor Trip and Safety Injection) and

transitioned to E-2 (FaultedSteam GeneratorIsolation)

• 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. I (Response to Imminent Pressurized Thermal Shock Condition)

from step 4 of FR-Z. 1.

Following the completion of FR-P. I 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.1 step 4 and complete the procedure, then return

to E-2 step 8.

D. Enter ES-O.O (Rediagnosis) and rediagnose the situation.

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Ques-357

Question #5 Catawba Nuclear Station SRO Exam

I Pt(s) Unit I 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

Safety Injection)

• 0210- transitioned to E-3, (Steam GeneratorTube Rupture)

• 0215 - 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

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Ques-478.1

Question #6 Catawba Nuclear Station SRO Exam

I Pt(s) Unit 2 is conducting a containment purge in accordance with

OP121A164501015(ContainmentPurge System). Given the following

conditions provided bn the GWR permit:

• Most restrictive release rate 16000 CFM

• Recommended release rate = 16000 CFM

• 2EMF-39(L) trip I setpoint= iOE5 CPM

• 2EMF-39(L) trip 2 = 2.0E5 CPM

• 1EMF-36(L) is in service

Time 0200 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

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Ques 479.3

Question #7 Catawba Nuclear Station SRO Exam

1 Pt(s) Unit I 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.

• All conditions and indications on the Fuel Handling Manipulator Crane

are satisfied for inserting the fuel 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.

D. Supervises reactivity management and personally monitors the

fuel insertion operation. Must give his permission to the

FHMCO prior to unlatching the assembly.

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Ques-483. 1

Question #8 Catawba Nuclear Station SRO Exam

1 Pt(s) Unit I was shutdown in mode 6. Engineering reported that a recent test on

the IB KC heat exchanger showed that fouling had reduced its heat transfer

capability.

• The heat exchanger was now incapable of meeting the design A

temperature with a maximum (FSAR) lake water temperature of 90 'F.

• The design A temperature could be met with lake water with a maximum

temperature of 80 'F.

• Current lake temperature is 68 'F.

• Lake temperature is not expected to reach 80 'F for another 30 days.

• 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

0

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 IF.

C. The B train of KC is operable but degraded as long as Lake Wylie

temperature remains below 90 'F.

D. The B train of KC is operable but degraded as long as Lake Wylie

temperature remains below 80 'F.

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Ques_485.2

Question #9 Catawba Nuclear Station SRO Exam

I Pt(s) Unit I experienced a LOCA with a breach of containment at 0200. The

OSM assumed the duties of the Emergency Coordinator and declared a

general emergency ai 0210. The initial recommended protective actions at

0225 were as follows:

• Shelter zones A2, A3, B2, C2, D2, E2, F2, F3

• Evacuate zones AO, Al, BI, Cl, Dl, El, Fl

At 0235, the initial dose projection information was presented to the OSM.

Given the following conditions at 0245:

• Wind direction = 4500

• Wind speed = 4 MPH

• Projected dose at the site boundary

• TEDE = 250 mrem

• CDE thyroid = 400 mrem

• Containment radiation levels

• IEMF53A= 950R/hr

• 1EMF53B = 955 R/hr

Which one of the following protective action recommendations are correct in

accordance with RP/0/A/5000/05?

REFERENCES PROVIDED:

A. Change the protective action recommendation in zones Al and

Bi from evacuate to shelter.

B. Extend the evacuation to zones A2, A3, B2, C2

C. Extend the evacuation to zones D2, E2, F2

D. The initial set of protective action recommendations remain in

effect with no changes required.

Ques-491.1 For Official Use Only Page 9

Question #10 Catawba Nuclear Station SRO Exam

1 Pt(s) A LOCA occurred on Unit I at 2:00 AM. Given the following events and

conditions:

0201 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.

0

• Core exit T/Cs indicate temperatures of 1300 F

• RVLIS lower range level indicates 90%

• IEMF-53A/1B indicate 85 R/hr

• The Operators enter FR-C. I (Response to Loss of Core 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.

D. Provide the first follow-up notification for a site area emergency

to the State and Local authorities no later than 0315.

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Ques_502.1

Question #11 Catawba Nuclear Station SRO Exam

I 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.

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Ques-718

Question #12 Catawba Nuclear Station SRO Exam

1 Pt(s) Unit I 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 IB and CA pump IA are isolated for differential pressure

testing.

• Engineering has reported that a test on the IB 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 PROVIDED:

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 lB KC heat exchanger within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or 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 /> or 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 />.

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Question #13 Catawba Nuclear Station SRO Exam

1 Pt(s) Unit I 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 IMC-5 reads 200 CFM.

• lEMF-36 (Unit Vent Gas Monitor) is at the trip I 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 IMC-5 fails high.

B. 1EMF-39 (ContainmentGas 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_962 For Official Use Only Page 13

Question #14 Catawba Nuclear Station SRO Exam

1 Pt(s) Unit I is operating at 65% power. Given the following events and conditions:

• Annunciator IAD-2, B/9 (Control Rod Bank Lo-Lo Limit) failed to

illuminate during annunciator testing.

• LEA 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 Control Rod Bank Lo Limit

(IAD-2, A/9) annunciator setpoint to the ControlRod 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 are

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.

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Ques 969

Question #15 Catawba Nuclear Station SRO Exam

I Pt(s) Unit I 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-1 18A (NI Pump IA C-Leg INJISOL) and 1NI-150B (NI

Pump IA C-Leg INJISOL) are open with power applied

B. INI-162A (NI to C-Legs INJHDR ISOL) is closed with power

applied

C. 1NI-121A (NI Pump IA To H-Legs B&C) and 1NI-152B (NI

Pump IB To H-Legs A&D) are closed with power removed

D. INI-IOOB (NIPMPSSUCTFROMFWST) is open with power

removed

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Ques 988

Question #16 Catawba Nuclear Station SRO Exam

I 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

0230 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 PROVIDED:

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.

__ ______ __

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Ques-989

Question #17 Catawba Nuclear Station SRO Exam

I Pt(s) Unit I 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 1150 psig

• All S/ 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 OfSecondary Heat Sink)

B. FR-H.4 (Response To Loss Of Normal Steam Release Capabilities)

C. AP-22 (Loss of Instrument Air)

D. AP-29 (Loss of Vital or Aux ControlPower)

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Ques_1000

Question #18 Catawba Nuclear Station SRO Exam

I Pt(s) Unit I was operating at 100% power, all rods out at 226 steps. Given the

following events and conditions:

• A runback occurs

• Reactor power is lowered to 60%

• Rod D-4 is stuck out at 226 steps

Which one of the following statements correctly describes the indications for

this stuck rod?

REFERENCESPROVIDED:

A. Core exit T/C T-3 is lower than T-61

N43 is lower than N44

B. Core exit T/C T-3 is higher than T-61

N43 is lower than N44

C. Core exit T/C is T-3 lower than T-61

N43 is higher than N44

D. Core exit T/C T-3 is higher than T-61

N43 is higher than N44

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Catawba Nuclear Station SRO Exam

Question #19

I 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.

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Ques-1002

Question #20 Catawba Nuclear Station SRO Exam

1 Pt(s) Unit 2 was shutdown in accordance with OP/2/A16 100/002 (Controlling

Procedurefor 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?

REFERENCESPROVIDED:

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 1OCFR5O.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 1OCFR5O.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 IOCFR50.72

D. 60 day notification in accordance with IOCFR50.73

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Ques-1003

Question #21 Catawba Nuclear Station SRO Exam

I Pt(s) Unit I is operating at 50% power. Given the following events and

conditions:

• 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 IVS-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 IVI-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 IVI-12 must be closed to isolate the VI leak.

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Ques-1004

Question #22 Catawba Nuclear Station SRO Exam

I Pt(s) Unit 2 is responding to a LOCA and trip from full power.

Given the following conditions:

• A safety injection has occurred

• Train "B" Sp signal failed to actuate (automatically and manually)

• The 2A NS pump started automatically

• The 2B NS pump was started manually by an operator

• The Ss signal and sequencer have been reset

• The Train "A" Sp signal has not been reset

• Both pumps were stopped for shifting suctions to the containment sump

• 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.

D. No action required because both NS pumps should automatically

restart.

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Ques-1005

Question #23 Catawba Nuclear Station SRO Exam

I Pt(s) Unit I was operating at 100% power when a LOCA occurred. Given the

following events and conditions:

• The Crew has entered E-0 (Reactor Trip or Safety Injection)

• Containment pressure reached 5 psig

0

• The inadequate core cooling monitor indicates -10 F subcooling

• 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

IPt(s) A Unit Istartup is in progress in accordance with OP/1/A6100/001

(ControllingProcedurefor 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 IAS-4,

(Main Steam to AS HDR CTRL Bypass).

Who should be notified prior to the operator closing AS-4?

I

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 CROshould be notified that reactor power may

decrease slightly.

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Ques-1007

Question #25 Catawba Nuclear Station SRO Exam

I Pt(s) Unit I is operating at 100% power with a Igpm condenser tube leak present.

Given the following plant conditions and events:

• 8:00 AM Chemistry reports that secondary chlorides have increased to

action level 3.

• 8:15 AM Power reduction in accordance with OP/I/A/6100/003

(Controlling ProcedureFor Unit Operation)initiated.

• 8:45 AM Chemistry reports that chloride sample analysis was verified

correct.

• 2:00 PM power has been reduced to 35%.

Which one of the following actions must be performed at 2:00 PM?

REFERENCES PROVIDED:

A. Initiate a rapid power reduction in accordance with AP-9 (Rapid

Downpower).

B. Continue power reduction in accordance with OP/1/A/6100/003

(Controlling ProcedureFor Unit Operation).

C. Enter OP/I/A16100/002 (ControllingProcedureFor Unit

Shutdown).

D. Trip the reactor and enter E-0 (Reactor Trip or Safety Injection).

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