IR 05000313/1998303

NRC Operator Licensing Exam Rept 50-313/98-303 & 50-368/98-303 on 981218.Exam Results:On Reactor Operator License Applicant Passed Written Exam

ML20202C497
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/07/1999
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20202C462	List: IR 05000313/1998303 ML20202C459 ML20202C476
References
50-313-98-303, 50-368-98-303, NUDOCS 9902010049
Download: ML20202C497 (70)

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l-i- ENCLOSURE 1'

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U.S. NUCLEAR REGULATORY COMMISSION REGION IV .

Docket Nos.: 50-313; 50-368 .

License Nos.: DPR-51 Report No.: '50-313/98-303;50-368/98-303 Licensee: Entergy Operations, In Facility: Arkansas Nuclear One, Units 1 and 2 Location: Junction of Hwy. 64W and Hwy. 333 South Russellville, Arkansas

. Dates: December 18,1998

~ Inspector: John L. Pellet, Chief, Operations Branch

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Approved By: ArthurT. Howell 111, Director Division of Reactor Safety i

ATTACHMENTS:

^ Attachment 1; Supplementalinformation L

Attachment 2: Final Written Examination and Answer Key I

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9902010049 990121

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l 2-EXECUTIVE SUMMARY Arkansas Nuclear One, Unit 1 NRC Inspection Report 50-313/98-303 NRC examiners evaluated the competency of one reactor operator license applicant for issuance of operating license at the Arkansas Nuclear One, Unit 1. The licensee developed the retake written examination using NUREG-1021, Interim Revision 8, January 1997. NRC examiners reviewed, and approved the examination. The written examination was I administered on December 18,1998, by facility proctors in accordance with the guidance in NUREG-1021, Interim Revision Operations l

. The reactor operator license applicant passed the examination. (Section 04.1).

• The test material was adequate for administration as submitted (Section 05.1). ,

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l -3-Report Details

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! Summary of Plant Status The plant operated at essentially 100 percent power on both units for the duration of this inspectio I. Operations l

04 Operator Knowledge and Performance 0 Initial Written Examination Inspection Scope On December 18,1998, the facility licensee proctored the administration of the written examination approved by the NRC to the individual who had reapplied for a reactor operator license. The licensee proposed grades for the written examination and evaluated the results for question validity and generic weaknesses. The examiner reviewed the licensee's result Observations and Findinas The minimum passing score was 80 percent. The candidate's score for the written examination was 93 percent. The licensee's post-administration analysis identified . hat the administered examination was acceptable. There were no post-examination I comments or changes to the written examinatio l Conclusions l The applicant passed the written examination. No broad knowledge or training !

weaknesses were identified as a result of evaluation of the graded examinatio Operator Training and Qualification 0 Initial Licensina Examination Development The facility licensee developed the initial licensing examination in accordance with guidance provided in NUREG-1021," Operating Licensing Examination Standards,"

Interim Revision 8, dated January 1997.

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-4-l 05.1.1 Examination Outline l

Inspection Scope The facility licensee submitted the initial examination outlines on October 30,1998.

! The chief examiner reviewed the submittal against the requirements of NUREG-1021,

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Interim Revision Observations and Findinas The chief examiner determined that the initial examination outlines satisfied NRC requirement Conclusions i- The licensee submitted an adequate examination outlin .1.2 Examination Packaae Inspection Scope The draft examination was transmitted by the licensee to the NRC on December 3, 1998. The licensee submitted the completed final examination package on ,

December 11,1998. The chief examiner reviewed the examination against the l requirements of NUREG-1021, Interim Revision Observations and Findinas The draft written examination contained 100 questions. The draft examination was technically valid, discriminated at the proper level, and responsive to the outline i submitted by the licensee. The written examination was considered adequate for administration as submitted, Conclusions The test material was adequate for administration as submitted by the licensee. No significant changes to examination materials were required as : result of administratio V. Manaaement Meetinas X1 Exit Meeting Summary The chief examiner telephonically presented the inspection results to members of the licensee management at the conclusion of the inspection on January 5,1999. The

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licensee acknowledged the findings presented.

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The licensee did not identify as proprietary any information or materials examined during this inspectio .6-r%

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L i ATTACHMENT 1 SUPPLEMENTAL INFORMATION ,

PARTIAL LIST OF PERSONS CONTACTED

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Licensee G. Giles, Operations Training Supervisor l

NRC l l

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INSPECTION PROCEDURES USED  !

l NUREG-1021, NUREG-1021, " Operating Licensing Examination Standards," Interim Revision i 8, January 1997

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ATTACHMENT 2 FINAL WRITTEN EXAMINATION AND ANSWER KEY

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ES-401 - Site-Specific Written Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific Written Examination ApplicantInformation Name: Region:llli/Illh Date: Facility / Unit ANOUnitOne License Level: hl SRO ReactorType: W/CE h GE StartTime: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. The passing grade requires a final grade of atleast 80.00 percent. Examination papers will be collected four hours after the examination starts.

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

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Applicant's Signature Results Examination Value 100 Points l

Applicant's Score Points

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. Applicant's Grade Percent

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NUREG-1021 39of 39 Interim Pev. 8, January 1997

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ANO Unit 1 - December 1998 Reactor Operator License Exam 12n0as

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Question N QID: 013/ Point Value: 1 If channel A of the RPS is currently in channel bypass, what would result if the channel bypass switch for channel B was then placed in the bypass position?

a. The RPS would be plac' ed in a 2 out of 2 coincidence logic, b. Interlock would cause both channels to drop out of bypas c. ne B cluumel would be in bypass and the A channel would I automatically be removed from bypas I d. The channel B bypass is prevented by an interlock from I the channel alreadyin bypass l Question No. 2 QID: 0132 Point Value: 1 l "

The makeup tank has decreased from 81 inches to 73 inches. Assuming that the level decrease was due to a loss of RCS inventory, how much has been lost?

a. 220 to 229 gallons b. 230 to 239 gallons l

c. 240 to 249 gallons -

d. 250 to 259 gallons i

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ANO Unit 1 - December 1998 Reactor Operator License Exam mlaps Question No. J QID: 0133 Point Value: 1 Which of the following are the two purposes for maintaining a one gpm continuous spray flow bypassing the pressunzer spray valve?

a. Assists in pressurizer level control and maintains pressunzer heaters at minimal firing rat b. Minimizes surge and spray line temperature differentials and maintains pressurizer boron concentration near that in the RC c. Assists in maintaining pressunzer level and maintains pressurizer boron concentration near that in the RC d. Minimizes surge and spray line temperature differentials and raises the differential pressure across the spray valv Question No. 4 QID: 0134 Point Value: 1 The Gamma Metrics system uses discrimination circuitry to provide accurate indication of source range power levels. Why is discrimination nwmsy in source range nuclear instrumentation and what is the result ofincorrect discrimination?

a. Discrimination separates out alpha and neutron pulses to provide a true gamma puls With the discrimination set too high power will indicate higher than actual powe b. Discrimination separates out gamma and neutron pulses to provide a tme alpha puls With the discrimination set too low, power will indicate higher than actual powe c. Discrimination separates out gamma and alpha pulses to prmide a true neutron puls With the discrimination set too high, power will indicate lower than actual powe d. Discrimination separates out beta and gamma pulses to provide a true neutron puls With the discriminator set too low, power will indicate lower than actual powe i Page 2

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l ANO Unit 1 - December 1998 Reactor Operator License Exam m>avs Question No. J QID: 0135 Point Value: 1 A LOCA has occurred which has resulted in an ESAS actuation of channels I through 1 Which ESAS channels have actuated the RB cooling units and what is the correct RB cooling alignment?

a. ES channels 7 & 8, VSF-1 A, IB, IC, & ID running with service water aligned to the cooling coil b. ES channels 3 & 4 VSF-1 A, IB, IC, ID, & IE running with chilled water aligned to the cooling coils.

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c. ES channels 5 & 6, VSF-1 A,1B, IC, & ID running with service water aligned to the cooling coil d. ES channels 1 & 2, VSF-1 A, IB, IC, ID, & IE running with chilled water aligned to the cooling coil !

Question No. 6 QID: 0136 Polet Value: 1  !

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During a LOCA inside the Reactor Building, RE-3814, Service Water 140p I Ratharion Monitor alarm l SWImop IIindications are norma Which of the conditions below when combined with the above condition would nuke it necessary ,

to isolate the "A" & "B" RB Emergency coolers? i

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a. Loop II Service Water monitor is also in alar j b. Instrument Airislos c.: Discharge Flume monitor is also in alarm, d. RB area monitors are also in alar .

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ANO Unit 1 - December 1998 Reactor Operator License Exam almss !

Question No. 7 QID: 0137 Point Value: 1 Which one of the following is NOT a function of the Rapid Feedwater Reduction feature ofICS?

a. Low Load and Startup Control Valve demands are reduced to zero, b. Main Feedwater Pump speed goes to minimu c. Both Main Feedwater Block Valves close in slow spee d. Both Loop Feedwater demands are reduced to zer Question No. 8 QID: 0138 Point Value: 1 During the performance of Main Turbine Governor Valve testing, while governor valve #1 was closed in the test position governor valve #3 fails closed. What turbine problems does this impose?

a. Moisture impingement on the turbine bladin b. Thermal shock to the turbine roto c. Turbine will trip due to low loa d. Turbine overspeed conditio i Question No. 9 - QID: 0139 Point Value: 1 ,

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Which of the following systems are isolated to the Reactor Building by ESAS?

a. RCP motor cooling, chill water, RB senice water coolin b. Seal injection, CRD cooling, RB leak detector c. Seal injection, RCP motor cooling, RB service water coolin d. CRD cooling, chill water, RB leak detecto ,

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ANO Unit 1 - December 1998 Reactor Operator License Exam mlass i

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Question No.10 QID: 0140 Polot Value: 1 Initial conditions:

-100% power with P 36C supplying normal makeup and seal injection. ICW pumps P-33A and P-33C in servic What RCP support system would be most affected by a loss of bus A47 a. SealInjection b. Motor Cooling c. SealBleedofI d. OilLiftPressure

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Question No.11 QID: 0141 Running with 'A' & 'B' RCP's on and 'C' & 'D' RCP's off with RCS pressure below 260 psig should be minimized to prevent:

a. excessive seal wear and cavitatio b. excessive motor winding temperatures and casitatio c. excessive seal wear and shaft crackin d. excessive thrust bearing wear and shaft cracking.

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ANO Unit 1 - December 1998 Reactor Operator License Exam mlass Question No.12 QID: 0142 Point Value: 1 Under what conditions can the Control Board Operator bypass or defeat a component automatically actuated by ESAS?

a. Bypassing or defeating a component automatically amated by ESAS is not allowe b. The Control Board Operator, after careful consideration, determines that the component is no longer require !

c. ONLY when procedurally directed by the Emergency Operating or the Abnormal Operating procedure d. After it is deternuned that the component is no longer needed and approval is obtained from the CRS/S l Question No.13 QID: 0143 Point Value: 1 j The plant is shut down for Refueling. A letdown system valve alignment is being done  ;

inside Controlled Access. Two of the valves are in a locked high radiation area and  !

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have no remote position indication. The first check was made, but the Shift Superintendent decided to waive the second check to reduce the exposure to high radiatio Which one of the following statements most ccurately describes why the Shift Superintendent's decison is acceptable or una :ceptable?

a. Acceptable, independent verifications are always waived for valve alignments inside High Radiation Areas, b. Unacceptable, independent verification cannot be waived if NO remote valve position indication is provide c. Acceptable, independent verification can be waived for valve alignments on a case-by<ase basis with the Superintendent's approva d. Unacceptable, independent verifications cannot be waived for j i

valve alignments without the approval of the Manager of Plant Operation l

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Question No.14 - QID: 0144 Point Value: 1 -

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A qualified Category III advanced radworker is assigned to perform a valve lineup in an area with c, - posted general area dose rate of 150 mR/hr To enter this area without an HP escort, which of the following is NOT required?

a. Radworker must be logged in on the appropriate Radiation Work Permi b. Radworker must be in possession of a suitable survey meter.'

c. P.adworker must be knowledgeable of the area dose rate d. Radworker must have a pocket ion-chamber self reading dosimeter (SRD).

Questica No.15 QID: 014 Point Value: 1 -1

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t The purpose of the IN-LIMIT (LATCH) BYPASS switch on the Diamond panel is to: j 'y power to the CRD motor which will engage the latching mechanis ..

b ' det a fault condition provided the fault has cleare c. Reset the AC breakers, DC breakers, and programmer controls, d. Allow driving in Groups 1 thru 7 to engage roller nuts with lead screws.

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L ANO Unit 1 - December 1998 Reactor Operator License Exam mla9s Question No.16 QID: 0146 Point Value: 1 i

The plant is operating at 100% power, when annunciator K07-C1,

. REACTOR FEEDWATER LIMTED, alarms. The following conditions i exist:

- RCS pressure and temperature are increasin !

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- OTSG levels = 60% and decreasin i l -Main feedwater flow is decreasin )

What procedure contains the required mitigating operator actions?

a. 1203.027, " Loss of Steam Generator Feed"

! b. 1203.001, "ICS Abnormal Operating" c. 1203.018, " Turbine Trip Below 43% Power" j i

d. 1202.001, " Emergency Operations Trocedure" l Question No.17 QID: 0147 Point Value: 1 ,

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.100% power

- ICS in full automati;  ;

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- Low Load Limit set at 60%

Annunciators "CRD WithdrawalInhibited" and " Control Rod Asymmetric" are received as a result of Group 2, Rod 3 dropping and fully inserting into the core. Which of the following best describes plant response?

a. ICS will nm the plan: back at 30Wmin and power will stabilize at 40%.

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b. ICS will run the plant back at 50Wmin and power will stabilize at 40%.

l c. ICS will run the plant back at 30Wmin and power will stabilize at 60%.

d. ICS will run the plant back at 50Wmin and power will stabilize at 60%.

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ANO Unit 1 - December 1998 Reactor Operator License Exam Imass Question No, ls QID: 0152 Point Value: 1 The plant is in hot shutdown with preparations for statup in progres Which of the following is an acceptable offsite power source alignment in accordance with Technical Specification 3.77 a. Startup Transformer #1 and Unit Auxiliary Transformer backfed from 500 KV via main generator outout breakers b. Stantup Transformer #2 and Unit Auxiliary Transformer powered from 22 KV switchyardline c. Startup Transformer #1 and Unit Auxiliary Transformer powered from 22 KV switchyardline d. Startup Transformer #2 and Unit Auxiliary Transformer backfed from 500 KV via main generator outout breakers Question No.19 QID: 0153 Point Value: 1 Actuation of any Control Room isolation radiation monitor will cause:

a. Both emergency Recire Fans to start, all isolation dampers close b. Either emergency Recirc Fan will stant, only the isolation dampers for that CR close c. Neither emergency Recire Fan will start, only isolation dampers close t . .

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d. . One emergency Recirc Fan will start, all isolation dampers close

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ANO Unit 1 - December 1998 Reactor Operator License Exam maps i

Question No. 20 QID: 0154 Polet Value: 1 l i

Given, only ONE failure caused the following.: )

- Plant running back i

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- A" main feedwater flow rapidly increasing

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- B" main feedwater flow rapidly decreasing  !

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- Feedwater pumps discharge crosstic valve shut Which one of the following equipment / component responses produced this plant condition?

a. RCP trip b. "A" loop RCS flow transmitter failure c. MFWPtrip d. "B" loop RCS flow transmitter failure Question No. 21 QID: 0155 Point Value: 1 The plant is steady at 100% powe Loop 'A' RCS narrow range pressure instrument, PT-1021 fails high instantaneousl What effect will this failun: have on plant equipment?

l a. The ERV will ope b. RPS channe! A will tri I c. Pressurizer heaters will go of ,

I d. PZR spray valve will open.

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- Question No. 22 QID: 0156 Point Value: 1 -

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• A reactor trip has occurre !

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• RCS pressure is 1800 psig, ,

• RCS T-cold is $32 degrees :

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• "A" OTSG pressure is 650 psi * "B" OTSG pressure is 970 psig,

• Reactor Building pressure is 6 psi I Which emergency operating procedure contains the specific steps to mitigate the consequences of this even ,

t a. ESAS 1202.010 l

b. Overcooling 1202.003 7 c. HPI Cooldown 1202.011 i d. Loss of Subcooling Margin 1202.002 i

Question No. 23 QID: 0157 Point Value: 1

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Given: "Ihe plant is at 500 MWe and you are the CBO If condenser vacuum dropped from 27" to 25.5", you would see indications of:

a. Increasing main turbine load (MWe).

b. Condenser vacuum pump shifting to hogging mod !

c. Automatic main turbine tri l

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d. Condenser vacuum pump auto stanin j

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i ANO Unit 1 - December 1998 Reactor Operator License Exam mlas8 ;

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Question No. 24 QID: 0158 Point Value: 1 L i

The outside door of the personnel lock was t,pened to replace a seal gasket 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago. How i long does operations have to perform an LLRT on the personnel lock before a loss of containment integrity will exist?

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b.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> c. 6 days l

.d.13 days

..Questica No. 25 QID: 0159 Point Value: 1

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Given:

- A LOCA has occurre )

- All RCPs are runnin (

- SPDS ATOG display indicates " Loss of Subcooling Margin Elapsed Time 00:04:15" j Width of the following actions should be taken?

a. Stop all RCP b. Stop one RCP in each loo c. Stop all RCPs except for one RCP in PZR loo '

d. Continue to keep all RCPs runnin t Page 12 l

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ANO Unit 1 - December 1998 Reactor Operator License Exam 12nass Question No. 26 QID: 0/60 Point Value: 1

' During a Rx trip transient, all nine of the + or - 24v DC NNI/ICS power supply status lights go ou The most likely cause is:

a. Loss of Offsite Power b. Loss of DC Bus Dll c. Loss of YO2 d. Loss of DC Bus D21 Question No. 27 QID: 0161 Point Value: 1 Given:

- Power escalation is in progress following a shutdow Reactor power is 30%.

- Rod 4 of Group 5 drop Which of the following actions should be taken?

a. Insert all regulating rods in sequential mod b. Trip the reactor and go to Reactor Trip, 1202.001, c. Verify plant stabilizes at 320 MWe after ICS runbac d. Refer to Tech Specs and recover the dropped ro Page 13

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ANO Unit 1 - December 1998 Reactor Operator License Exam wlase !

i Question No. 28 QID: 0162 Point Value: 1 Reactor power is 90% and generated megawatts is 800. AAer a sunback for loss of one main feedwater pump, the ICS should stabilize the plant at  ;

a. 360 MWe b. 340 MWe

c. 45%ReactorPower d.' 40% Reactor Power Question No. 29 QID: 0/63 Point Value: 1 After a reactor trip with all immediate actions performed, which of the following requires an entry into 1202.004 " OVERHEATING"?

a. T-hot is rising above 560 deg F with the "C" RCP running.

! ' b, Both main feedwater pumps tripped, aux feed pump 00 c. T-hot rising above 580 deg F and subcooling margin is los d. CETs rising above 610 deg F with all of the RCPs of ,

Question No. 30 QID: 0164 Point Value: 1 An outage is in progress. The RCS is drained to 371.5 feet as indicated by RCS hot leg level. Decay heat removal flow

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becomes erratic. Indicated flow is ~2500 gpm. Which ONE l of the following actionsis correct?

i a. Reduce decay heat removal flow below 2000 gpm.

l l b. Stop the operating decay heat removal pump.

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c. Raise RCSleve d. Raise decay heat removal flo ..

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ANO Unit 1 - December 1998 Reactor Operator License Exam mlass Question No. 3/ QID: 0163 Point Value: 1 Given:

- Reactor tripped

- OTSG pressures 830 psig and decreasing-Tave 536 degrecs F Which plant condition below correlates to these parameters?

a. All rods not on bottom b. Turbine did not trip ,

c. Al did not transfer to SUI d. RCS is saturated Question No. 32 QID: 0166 Point Value: /

During an OTSG tube rupture with RCS temperature at 525' F, which of the following would require using the emergency cooldown rate?

a. Bad OTSG level 410" and rising b. BWSTIcvel28'and dropping c. Projected activity at the site boundary is at NUE criteri d. Tube-to shell differential temperature 60*F tubes hotte Page 15

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ANO Unit 1 - December 1998 Reactor Operator License Exam wwp8 Question No. 33 QID:0/67 Point Value: 1 What immediate action is required upon receipt of Liquid Radwaste Process Monitor (RI-4642) high alarm?

a. Start another cire water pump to increase dilution flo b. Verify no release in progress at Disch Flow to Flume (F1-4642) on C19, c. Verify with Unit 2 no c4her release is in progres d. Have chemistry sampic discharge flume for radionuclide .

Question No. 34 QID: 0168 Point Value: 1

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A high radiation condition has resulted in the Unit I and Unit 2 Control Room Radiation Detectors actuating the Control Room Emergency Ventilation System. Both VSF-9 and 2VSF-9 are operatin Which of the following is correct con =rning this alignment?

a. The control room will become overpressurized which will result in 2VSF-9 trippin b. The alignment can result in conditions that may ause excessive radiation exposure, c. The alignment should be maintained as is since it is an allowable configuratio .

d. The control room will become overpressurued which will result in VSF-9 trippin _

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ANO Unit 1 - December 1998 Reactor Operator License Exam class

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l Questica No. 35 QID: 0169 Point Value: 1 i

Given:

! - Plant is at 100% powe PZR level trancmitter LT-1001 selected sia HS-1002 on C0 PZR temperature element TE-1001 A selected sia HS-1000 on C04.

l The PZR temperature indicator, TI-1000, on C04 drops suddenly to 50'F (bottom of scale).

Without operator action, what will be the effect on the PZR Level Control System?

l a. PZR Level Control Valve, CV-1235, will open to establish a higher steady-state PZR leve b. PZR Level Control Valve, CV-1235, will maintain the same steady-state PZR leve c. PZR Level Control Valve, CV-1235, will close to establish a lower steady-state PZR leve d. PZR Level Control Valve, CV-1235, will fail open to continuously raise PZR leve l Question No. 36 QID: 0170 Point Value: 1 During a loss of offsite power with a SG tube leak, the A2 bus is re-energized from the A4 bu The A4 bus is supplied by #2 ED What is the key reason for this action?

a. To start P-7B EFW pump and secure P-7 b. To restart cire. water and re-establish condenser vacuum.

l l c. To allow operation of the Aux Feedwater pump (P-75).

l d. To re-establish Instrument Air and ICW cooling.

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ANO Unit 1 - December 1998 Reactor Operator License Exam 12na98 Question No. 37 QID: 0171 Point Value: 1 Given: Reactor power is stable at 85% with ICS in full automatic mod A group 6 control rod dropped into cor What are the required Operator actions that should be taken as a result of this condition?

a. Recovery of the dropped rod must be accomplished within the next 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> b. Declare the rod inoperable and verify a 1.5% available shutdown margin exist c. Exercise remaining rods within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per CRD System Operating Procedure 1105.00 d. Shutdown the reactor by inserting all regulating control rods in sequenc P l Question No. 38 QID: 0172 Point Value: 1 Which of the following conditions would require that a Natural Circulation Cooldown be performed?

a. A plant cooldown is required and normal offsite power is NOT availabl b. A steam generator tube leak exist post reactor trip and P-7B EFW pump is NOT availabl c. EFW CST (T-4IB) level has dropped to less than 3' during a Blackout conditio d. A loss of offsite power has occured and both DGs are tied to their respective busses

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with an adequate SCM and SU Transformer #1 becomes available.

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l Question No. 39 - QID: 0173 Point Value: 1 During an Emergency Boration condition, as directed by Repetitive Task 1202.012, the batch controller is set:

a. As required to maintain makeup tank level >55 inche b. For maximum batch size and adjusted based on calculation.

L c. To a vahn obtained from the Emergency Boration graph.

l i di To batin in 100 gallons of acid at 15 minute intervals.

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l l _ Questlom No. 40 QID: 0174 Point Value: 1 l

l l When recovering from a Station Blackout condition with no offsite power available

! and only one EDG operable, which of the following is true?

l a. 'Ihe EDG output breaker will automatically close once the EDG has started and l l all other feeder breakers to it's respective bus are open.

l l b. The EDG output breaker handswitch must be momentarily held in the "ciose' position to override the ES bus undentitage rela c. The A3-A4 crosstic breakers are closed prior to closing the EDG output breake d. The EDG should be used to backfeed A2 to restore essentialload Question No. 41 QID: 0175 Point Value: 1 Given:

- ICW system is in a normal alignment with P-33 A & C in operatio Non-Nuclear loop flow is 1950 gp Nuclear Loop flow is 1550 gp Annunciator K12-B4 (ICW Flow Lo) is in soli No ESAS signalis presen Which of the following would be the LEAST APPROPRIATE action for the l ControlRoom Operator to take?

a. Verify ICW Pump (P-33C or P-33B) is operatin I b. Verify ICW for Ixtdown Coolers and RCP Seal Coolers Outlets  ;

(CV-2214 & CV-2215) are ope c. Verify ICW for RCP Air and Lube Oil Coolers and Control Rod ,

Drive Outlets (CV-2220 & CV-2221) are ope d. Verify ICW for Letdown Coolers and RCP Seal Coolers Inlet (CV-2233)is ope l

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i ANO Unit 1 - December 1998 Reactor Operator License Exam 12n w9s

- Question No. 42 Q1D: 0176 Point Value: 1 l l

Given:

- Annunciator " FIRE" (K12-AI) in alar wer North Piping Area 335' red LED light ON on C46 HP technician calls the Control Room and repons smoke on the 335' elevation of the Aux Buildin What are the appropriate operator actions?

a. Notify the WCO to obtain a fim extinguisher and check Lower North Piping Area for indications of fir b. Actuate Lower North Piping Area deluge valve by the manual trip switch on C46 c. Notify Health Physics Dept. and dispatch two operators with SCBAs to Iower North Piping Are d. Notify the WCO to obtain HP coverage and check Lower North Piping Area for indications of fir Question No. 43 QID: 0177 Point Value: 1 During the performance of an Alternate Shutdown, RO #2 is directed to throttle EFW TURB K3 TripsThrottle Valve (CV.6601 A) as neuary to maintain P-7A discharge pressure at ~1400 psig. What would be the initial effect on RCS parameters if P-7A discharge pressure was maintained at ~700 psig?

a. RCS Tave would drop, RCS pressure would drop, Pressurizer level would go u b. RCS Tave would sise, RCS pressure would rise, Pressurizer level would dro c. RCS Tave would rise, RCS pressure would rise, Pressurizer level would ris d. RCS Tave would drop, RCS pressure would drop, Pressurizer level would dro ;

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- ANO Unit 1 - December 1998 Reactor Operator License Exam '12 nap 8 Question No. 44 QID: 0178 Point Value: 1

AAer entering Inadequate Core Cooling EOF (1202.005), RCS

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temperature and pressure indicate entry into Region 4 of Figure 4.

l -(See attached Figure 4)

What RCP action is appropriate to restore core cooling?

a. Start a!! RCPs even if RCP services are not availabl b. Restore RCP services and start one RCP/ loo c. Restore RCP semces and bump RCPs until pri: nary to secondary heat transfer is establishe d. Bump all RCPs even if RCP services are not availabl Question No. 45 QID: 0180 ,

Point Value: 1 A reactor trip has just occurred. Which of the following would NOT cause a transition to the overcooling procedure (1202.003)?

a. MSL1 actuates automatically causing both MSIVs to go close b. . 'A' SG pressure 1000 psig, 'B' SG pressure 800 psig, Tcold 550 degree .

c. 'A' SG ;n sure 1020 psig, 'B' SG pressure 980 psig, Tcold 535 degree d. Tave 560 degrees, SCM 25 degrees, RCS pressure 2100 psig, Question No. 46 QED: 0181 Point Value: 1 i

During a small break LOCA, which of the following would require manual -

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action to balance HPIflow?

a. Both trains of HPI operating and RCS pressure >600 psi b. Both trains of HPI operating and RCS pressure <600 psi l

)

c. Only one train of HPI operating and RCS pressure >600 psi d. Only one train of HPI operating and RCS pressure <600 psig.

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1202.013 E0P FIGURES REV 2 PAGE 4 of 6

1 FIGURE 4 '

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I ANO Unit 1 - December 1998 Reactor Operator License Exam 12na98 l i

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i Question No. 47 QID: 0182 Point Value: 1 A LOCA is in progres Which one of the following actions is required to be performed prior to the BWSTlevel reaching 6 feet?

-;

r a. Secure running Reactor Coolant Pump b. Align Pressurizer AUX Spray to LPI syste c. Secure running High Pressure Injection Pump d. Align one LPI train to gravity flow from RCS hot leg to RB sump.

,

Question No. 48 - QID: 0183 Point Value: 1 During restoration of normal makeup and seal injection, which of the following is true?

a. If PZR level is <$5", normal makeup is restored before seal injectio b. If RCP seal bleedoff tempie s are >180 degrees, seal injection control valve (CV-1207) is quickly opened to establish previous flow rat . c. If RCP seal bleedoff temperatures are >180 degrees, CV-1207 is slowly opened to minimize thermal shock to the RCP seal ' d. BWST outlet valve assocuted with the operating HPI pump must be closed prior to opening CV-120 l

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ANO Unit 1 - December 1998 Reactor Operator License Exam 12/10/ps Question No. 49 QID: 0184 Point Value: 1 During a reactor startup with source range NI-2 and reactor power wide range recorder NR-502 inoperable, source range NI l fails to 10 E Intermediate range NI-3 indicates 5 E Il amps and intermediate range NI-4 is off scale lo What is required of the CBOR7 a. Continue the startup utilizing NI-3 until NI-4 comes on scal b. Perform a plant shutdown in accordance with normal operating procedures due to lack of proper overla c. Trip the reactor due to no on-scale indication of neutron flux availabl d. Hold power constant and perform an NI calibratio Question No. 50 QID: 0186 Point Value: 1 Given:

- Reactor tripped with Thot temperatures 590 degrees and risin '

- A' & 'B' SG levels 13". l

- All 4 RCPs are operating with RCS pressure 2200 psi Both DGs are in emergency standb l l

Which of the following procedures provides appropriate guidanec7  !

a. Loss of Subcooling Margin (1202.002)

b. Overheating (1202.004) i c. Inadequate Core Cooling (1202.005)

d. Degraded Power (1202.007)

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ANO Unit 1 - December 1998 Reactor Operator License Exam mlaa8 Question No. 51 QID: 0187 Point Value: 1 The reactor hasjust tripped from 100% power. The turbine trip solenoid light l is on. Breaker position lights on the RIGHT side of C10 are of i What are the actions required of the CBOT?

a. Trip the main generator output breakers.

l b. Transfer Dil to emergency supply D02.

I c. Trip all RCPs.

(

d. Transfer D21 to emergency supply D01.

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l Question No. 52 QID: 0188 Point Value: 1 Given:: Fuel handling is in progress in the Reactor Buildin A new fuel assembly is in the Main Bridge mas Reactor Building Fuel Handling Area (RI-8017) area i, - radiation monitor has a Failure alarm in soli i

'

ll What actions should be taken by the refueling team?

l a. Place the assembly in the nearest core location and then secure refueling activities until repairs are made to RI-801 b. Continue refueling activities and notify Health Physics to perform area suncys of the Main Bridge every 15 minutes, c. Cc% .uc refueling activities as long as two subcritical core neutron flux

mt..ators are availabl d. Secure fuel handling activities until RI-8017 is operable or a suitable portable survey instrument is obtained.

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ANO Unit 1 - December 1998 Reactor Operator License Exam 12n wp8 Question No. JJ QID:0/89 Point Value: 1 The plant is operating at 100% powe Dunng pre-outage scaffolding construction in Lower North Piping Room (LNPR),

' the instrument air line to the Pressurimr level Control Valve (CV-1235) is inadvertently severe With no operator action, which of the following describes the expected system response?

a. CV-1235 fails open and Pressuriar level will ris b. CV-1235 fails closed and Pressurimr level will lowe c. CV-1235 fails open and Pressunar level will lowe d. CV 1235 fails closed and Pressuriar level will rise.

l l Question No. 54 QID: 0190 Point Value: 1 l-

. Given:

- Plant is at 100% powe On Cl3, the RCP Seal Leakage Collecting Tank (T-111) Fill Timer "A" reads 20.0 and " TIMER ON" light is ON. '

- Fill Timer "B" reads 25.0 and " TIMER ON" light is OF What is the cunent total RCP seal leakage?

a.1.1 gpm b.1.6 gpm c. 2.0 gpm l

d. 2.5 gpm l I i

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P ANO Unit 1 - December 1998 Reactor Operator License Exam am9s Question No, $5 QlD: 0191 Point Value: 1 The level setpoint at which the Makeup Tank Vent Valve (CV 1257)

automatically opens is:

a. 86 inches b. 55 inches c.18 inches d.10 inches Question No. 56 QID: 0192 Point Value: 1 Reactor Building Pressure Transmitter (PT-2407) has failed high causing an ES CH3 Trip (analog 3) and the ESAS Partial Trip annunciator (K11-F6) to come into alar With the above conditions, a power loss to which of the following would cause an ESAS actuation?

a. RSI b. Bil

' c. RS3 d. B21 Question No. 57 QID: 0193 Point Value: 1 Several plant parameters can be monitored to ensure accurate indications of reactor power are available. Which of the following sets of parameters would be indicative of 60% reactor power? j a. Tave $79 degttes, Thot 593 degrees, Tcold 564 degrees, total FW flow 6.5 million Ibm /h b Tave 580 degstes, Thot 599 degxces, Tcold $60 degrees, total FW flow 8.4 million Ibm /h ' c. Tave 579 degrees, Thot 588 degrees, Tcold 570 degrees, total FW flow 6.5 million Ibm /h d. Tave 581 degrees, Thot .490 degrees, Teold 565 degrees, total FW flow 9.8 million Ibm /h Page 26

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l ANO Unit 1 - December 1998 Reactor Operator License Exam mm9s i

Question No. 58 QID: 0194 Point Value: 1 During a natural circulation cooldown, which of the following indicate that head voids have formed in the reactor vessel due to an excessive cooldown rate?

a. Pressurizer level dropping while depressurizin b. Thot tracking CET temperature c. Difficulty in reducing RCS pressur d. Tcold rising with associated SG Tsat droppin Question No. 59 QID: 0195 Point Value: 1 Unit 1 is operating at 100% power with no abnormal conditions or alignment 'B' MFP SUCT PRESS LO (K07-C8) annunciator is receive ;

Where can the Control Room Operators read the 'B' MFW pump suction pressure WITHOUT leaving the control room?

a. The 'B' MFP Lovejoy Operator Control Station (OCS).

b. 'B' MFP Suction Pressure (PI-2830) indicato c. 'B' MFP Suction Pressure computer point (P2830)

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' d. The Operator Information Touchscreen (OIT).-

Question No. 60 QID: 0196 Point Value: 1 l While performing a reactor building purge evolution, the operator notes all four RB Purge Isolation Valves go closed. What is the most likely cause? j

' a., An ESAS actuation of channels I and 2 has closed the valve b. A loss ofload center B-S has occurred causing the valves to fail close c. A high radiation setpoint has been exceeded on SPING d. RB Purge Exhaust Fan (VEF-15) has tripped causing the valves to clos Page 27

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ANO Unit 1 - December 1998 Reactor Operator License Exam mlas8 Question No. 6/ QID: 0197 Point Value: 1 The plant is operating at 100*/. power. The Core Flood system is properly aligned with the following CFT parameters:

T-2A level - 12.9 feet T-2B level - 11.9 feet

"-2A pressure - 605 psig T-2B pressure - 610 psig The Core Flood system parameters are unacceptable because?

a. Levels may preclude having sufficient N2 pressure to fully inject the CFT contents into the vesse b. N2 pressure could cause RCS inventory to be lost out of the break in the event of a LOC c. Levels may not be sufficient to reflood the vessel following a LOC d. N2 pressure may not be sufficient to fully inject the CFT content into the vessel during a LOC Question No. 62 Q1D: 0198 Point Value: 1 Why must Reactor Building Spray flow be throttled to 1050-1200 gpm when on Reactor Building sump suction?

a. To prevent inadequate pump suction pressure on ECCS pumps, b. To prevent pump runout on the spray pump c. To lower load on the vital electrical buse d. To limit reactor building cooldown rat Page 28

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ANO Unit 1 - December 1998 Reactor Operator License Exam 12/ lass Question No.' 63 QID:0/99 Point Value: 1 Identify the correct response concerning the Reactor Building Purge Isolation Valves (CV-7401, 7402, 7403, & 7404).

a. The valves roccive an ESAS actuation signal from ESAS channels 5 & b. The valves receive an ESAS actuation signal from ESAS channels 3 & c. The valves receive an ESAS actuation signai from ESAS channels 9 & 1 ,

.'d. The valves do not receive an ESAS actuation signa Question No. 64 QID: 0200 Point Value: 1

..

A break has occurred on the discharge line downstream of the discharge valve ofin service

. Spent Fuel Cooling Pump (P-40A). The pump is stopped and the discharge valve is close Which of the following statements is correct concerning the Spent Fuel Pool inventory?

a. ' The SFP will drain to ~ 2 feet above the spent fuel assemblie b. Emergency mairaip from service water will be reeded to prevent the SFP level from reaching the spent fuel assemblic c. The SFP level will stay relatively constant due to siphon holes in the discharge pipin t bottom of the ' pip d. The SFP level will drop -3 feet to ' he Page 29

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ANO Unit 1 - December 1998 Reactor Operator License Exam m/ ass Question No. 65 QID: 0201 Point Value: 1 l

l Stanup Transformer #1 has locked out following a reactor trip from 100% powe Steam generator levels will be fed up to which of the following levels (assume no operator actions)? '

a. 20-80 inche b. 100-150 inche c. 300-340 ireche d. 370-410 inche Question No. 66 QID: 0202 Point Value: 1 A plant startup is in progress with the reactor critical below the point of adding hea 'B' SG Turbine Bypass Valve (CV-6688) fails full open and is unable to be closed with the handjack. Given the following plant conditions:

-Tave 526 degrees and dropping

- Pressurizer level 205 inches and dropping-RCS pressure 2120 psig and dropping What is the proper course of action?

a. Initiate MSLI for the 'B' SG and maintain the reactor critical using 'A' SG TBV to control RCS temperature and pressur b. Continue the reactor stanup maintaining startup rate <1 DPM while continuing to monitor primary and secondary plant parameter c. Go directly to the Overcooling tab (1202.003) of the EOP for actions to mitgate the oversteaming of the 'B' S d. Trip the reactor and go to Reactor Trip tab (1202.001) of the EO Page 30

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ANO Unit 1 - December 1998 Reactor Operator License Exam 12nasS l l

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Question No. 67 QID: 0203 Point Value: 1 l' l

, Red powered EFW Pump Turbine (K-3) Steam Admission Valve Bypass Valve (SV-2663)

l has failed to open during regularly scheduled surveillance testing. What are the required l: operator actions?

l j l a.- Decnergize SV-2663 closed and declare P-7A inoperabl I b. Declare SV 2663 inoperable and manually open the valv c. Declare SV 2663 inoperable and deenergize CV-2663 closed.

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! d. Decnergize SV-2617 open and declare P-7B inoperabl .

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l . Question No. 68 QlD: 0204 Point Value: 1 j The #1 DG monthly surveillance is in progress with the DG on-line and fully loade EDG-1 Non<ritical Trouble (K01-D2) has been in solid for ~3 minute EDG Critical Trouble (K01-C2) comes into alar The inside AO reports that the T-30A day tank level is ~150 gallons and going down slowl The outside AO reports that Emergency Storage Tank T-57A level is >165 inches.

l

Which of the following is correct with regard to #1 DG status?

a. #1 DG is operable because fuel oil can be supplied from #2 DG transfer pump P-16B.

l b. #1 DG is inoperable due to the level in T-30A being <160 gallon c. #1 DG is operable because day tank level is not required to remain above alarm setpoint as lorg as the emergency storage tank (T-57A) is full.

l d. #1 DG is inopetable due to Emergency storage tank level >160 inches.

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ANO Unit 1 - December 1998 Reactor Operator License Exam 12 naps Question No. 69 QID: 0205 Point Value: 1 l

During 3 circulating water pump operation, the 'A' circ water pump trip l The standby cire pump was started and plant ::onditions have been stabilize '

It is noticed that the condenser waterbox dis:harge temperature is 10 degrees i higher and plant efficency has dropped. Which of the following is the most likely I

cause of this condition?

l a. The stopping and starting of a cire pump caused fouling to be removed from

,

the tube sheet promoting better heat transfer capabilitie j

.

b. The discharge valve on the tripped pump did not go completely closed and

! circulating wateris short cyclin l c. The debris on the bar grates of the circulating water bays was stirred up during the circ pump swap causing reduced flo ;

d. These are normal conditions following rotation of circulating pumps and temperatures will return to normal within 30 minute Question No. 70 QID: 0206 Point Value: 1 i The Main Control Room Ceiling Halon system has been properly placed in Inhibit by taking the switch on the right side of Module B3-2L to the dowit position in Fire Protection Panel (C463).

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Select the best statement below concerning the actuation capability of the l Main Control Room Ceiling Halon s>1; te l a. It will automatically actuate if both detector strings have valid I detection signals presen b. It can ONLY be actuated locally from the Halon bottles in the Auxiliary Buildin c. It can NOT be actuated with the system in Inhibit. '

d. It can be actuated locally or by placing the MAN 'IRIP switch

.

on C463 to the OPERATED position.

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l ANO Unit 1 - December 1998 Reactor Operator License Exam 12/ lass Question No. 71 QID: 0207 Point Value: 1 Given:

Refueling outage is in progress with the Decay Heat Removal System in servic RCS pressure is 100 psi i

- I&C wants to de-energize ESAS Analog Channel l l

What would be the effect on plant operations ifI&C is allowed to continue?

a. Auto start of'A" Decay Heat pum b. Opening ofER c. Loss of RCS level indication on ICCMD l l

d. Loss ofdecay heat remova I Question No. 72 QID: 0208 Point Value: 1 Given:

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- All Pressunzer heaters O RCS pressure is 2000 psig and going dow ,

- Quench Tank (T-42) pressure rising )

- Pressurizer Level Control Valve, CV-1235, full close What actions should be performed by the control room operators?

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a. Close the Spray Line Isolation Valve (CV-1009).

b. Close the ERV isolation Valve (CV 1000).

c. Take manual control of CV-1235 and ope !

d. Maximize letdown flo Page 33 l

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ANO Unit 1 - December 1998 Reactor Operator License Exam 12na/9s Question No. 73 QID: 0209 Point Value: 1 During the performance of a plant shutdown, cooldown and depressurization of the RCS, the following valves are required to be closed at one point during these evolutions:

- NaOH to P-34 A/P-35 A Suction (CA-61)

NaOH to P-34B/P-35B Suction (CA-62)

- NaOH Storage Tank (T-10) Outlet (CA-49)

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Whatis the reason for this action?

a. Prevent contamination of the NaOH Tank from RCS back leakage during decay heat removal operation b. Prevent NaOH from leaking into the DH system and causing chemical contamination of the RCS.

l c. To prevent NaOH from being sprayed into containment when access is open to R d. Prevent overpressurizing the NaOH tank outlet piping from backleak during decay heat removal operation Question No. 74 QID: 0210 P.oint Value: 1 Givere

- A LOCA has been in progress for eight hour Hydrogen Recombiner M-55B is in standby and M-55A is in senic When would it be necessary to place Hydrogen Recombiner M-55B in senice?

a. When M-55A average thermocouple temperature reaches 1225' b. When H2 concentration >2% with a ramp increase in M 55A temperatur c. When M-55A power indication reaches 60 KW and is at steady stat d. When Hydrogen concentration exceeds 3% with M-55 A temperature at 1450*F.

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ANO Unit 1 - December 1998 Reactor Operator License Exam 12nass Question No. 7J QID: 0211 Polot Value: 1 ne unit is operating at 100% powe Service water pumps P-4A and P-4B are in senic A loss of P-4A occurs What is required of the operator to restore senice water to the i required Technical Specifications configuration?

a. Swap P-4B MOD (A6) to the A3 supply and start P-4 b. Start P-4C, stop P-4B, swap P-4B MOD (A6) to the A4 supply and start P-4 c. Stop P-4B, swap P-4B MOD (A6) to the A3 supply and start P-4B and P-4 d. Start P-4C, stop P-4B, swap P-4B MOD (A6) to the A3 supply and start P-4 Question No. 76 QID: 0212 Point Value: 1 With regard to Technical Specification Limiting Conditions for Operations, )

which one of the following conditions would require that the condition be corrected within one hour to avoid performing the LCO contingencies?

a. The Boric Acid Addition Tank (BAAT) temperature drops to a temperature that is 5 degrees above c:ystallization temperatur b. The Q CST (T-41B) level has dropped to a level of 8 fee c. A Pressunzer Code Safety valve becomes inoperabl d. One circuit of the control room emergency air conditioning and isolation system becomes inoperable.

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ANO Unit 1 - December 1998 Reactor Operator License Exam 12naas Question No. 77 QID: 0213 Point Value: 1 Given:

- Refueling outage in progres Fuel handlers are moving fuel from core to Spent Fuel Poo You are assigned to perform Att. B, Refueling Boron, Temperature, Tritium, and Imel Check from 1502.004, Control of Unit 1 Refuelin While performing Att. B you discover the Spent Fuel Ventilation Exhaust Fan VEF-14A flow rate is less than the minimum requiremen What should your first action be to ensure procedural and Tech Spec compliance?

a. Notify fuel handlers to stop fuel movement in the Spent Fuel Pool are b. Start Spent Fuel Ventilation Exhaust Fan VEF-14 c. Adjust ventilation dampers to restore flow rate above minimu d. Request 1 & C to verify validity of flow indication.

Question No. 78 QID: 0214 Point Value: 1 Widch of the following Control Room control panels does NOT have post accident components that are verified per Repetitive Task (RT-10) following an ESAS actuation?

a.' Control Panel C26 b. ControlPanelC16 c. Control Panel C10 d. ControlPanelCl3 Page 36

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ANO Unit 1 - December 1998 Reactor Operator License Exam 12nass Question No. 79 QID: 0215 Point Value: 1 '

Process monitor Failed Fuel Gross (RI-1237) indication has changed from 1.8 E5 to 4.5 E6 due to a crud burst l- that was caused by the starting of an RCP. Assuming the change in RI-1237 indication is from gross activity alone, desenbe the failed fuel ratio change that should be seen on plant computer point R1237R7 i

a. A slight rise in the indicated ratio on R1237R will be observe ;

b. A slight drop in the indicated ratio on R1237R will be observe c. A marked rise in the indicated ratio on R1237R will be observe ,

d. A marked drop in the indicated ratio on R1237R will be observe Question No. 80 QID: 0216 Point Value: 1 i Given: l

- A 15 gpm Steam Generator tube leak cooldown is in progress l

- Normal cooldown limits are being used with the good OTS .

- RCS pressure is 1000 psig, Tave is 405' l

- The CBOR is maintaining the RCS at about 140'F subcoole What is the primary reason the CBOR's actions are incorrect for this accident?

a. Tube to shell Delta T limits are being exceede b. A high primary to secondary Delta P is increasing primary coolant los c. Excessive thermal stresses are being imposed on the Rx vesse j d. Overfill could cause the ruptured SG main steam safeties to lif l

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ANO Unit 1 - December 1998 Reactor Operator License Exam mias8 l

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Question No. 81 QID: 0218 Point Value: 1 Given the following plant condition ;

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- 100% power -

- Condensate Pumps P-2A and P-2C are in senice

- Startup Xfmr #2 Feed to Al (A-lll) is inadvertently close *

What is the expected condensate pump response and necessary operator response to this condition? ,

a. Condensate Pump P-2C will trip leaving only P-2A runmng; trip reactor and carry out immediate actions of 1202.001, Reactor Tri b. Condensate Pump Start /Stop responses are not affected by Startup Transformer operations; no operator action is require c. Condensate Pump P-2A will trip, P-2B will auto start; verify MFW pump suction pressure recovers to norma d. Heater Drain Pump P-8A will trip causing P-2B to auto start; verify plant runs back to 40% of 902 MW Question No. 82 QID: 0219 Point Value: 1

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- LOCA in progress with Degraded Power conditions

- EDG #2 did NOT start  !

RCS pressure stabilized at 140 psig

- SCM is 5 degrees With these accident conditions, which of the following would pose the greatest challenge to core cooling?

l a. Tube Leak in the 'A' Steam Generator )

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b. EDG #1 critical trouble alarm j

c. BWST level at 15 feet d. P-35A Reactor Building Spray Pump trip Page 38 l

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ANO Unit 1 - December 1998 Reactor Operator License Exam wias8

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Question No. 83 QID: 0220 Point Value: 1 l Given:

- Reactor power steady at 80%.

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- PZR Level Control selected to LT 1001 on C04  ;

- A break in LT-1001's reference leg causes it to drain completel l Ilow will Makeup Tank (T-4) level be affected by this failure?

a. Makeup flow drops, Makeup Tank level will ris b. No effect, SASS will auto select LT-100 ]

l c. Makeup flow rises, Makeup Tank level will dro d. Letdown flow drops, Makeup tank level also drop Question No. 84 QID: 0221 Point Value: 1 Given:

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- A" RPS has been placed in Channel Bypass due to RCS pressure transmitter (PT-1021)

failed low-Plant is at 100% power and stable 1

- A lightning strike by the Reactor Building has resulted in the trip of 120V Vital AC distribution panel RS- ' )

What is the status of the reactor and the RPS following the trip of RS-37 a. Reactor has tripped due to I channel of RPS trippe b. Reactor is at 100% power with one :hannel of RPS trippe c. Reactor has tripped due to 2 channelt of RPS trippe d. Reactor is at 100% power with no RPS channels trippe l l

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ANO Unit 1 - December 1998 Reactor Operator License Exam m1 ass Question No. 85 QID: 0222 Point Value: 1 Initial Conditions: Reactor power 75%

RCS pressure 2160 psig RCS Tave is $80 degrees What would be the immediate response of the Pressunzer Spmy Valve (CV-1008) upon an 'A' MFW pump trip?

a. Iniually remain closed and then responds to pressure change b. Initially to 40% open and then responds to preuure change c. Initially to 75% open and then responds to pressure change d. Initially to 100% open and then responds to pressure change Question No. 86 QID: 0223 Point Value: 1 Given:

- Plant is in cold shutdow All necessary components have been aligned per 1305.006, Integrated ES System Tes All ES EVEN Digital Channels actuated per procedure using RB pressure transmitter Which of the following is a properly actuated ES component for this test?

a. P-35A RB Spray pump flow ~1500 gp b. Red Train BWST Outlet valve (CV-1407) ope c. P-35B RB Spray Block valve (CV-2400) ope d. P-35B NaOH Tank Outlet valve (CV-1617) ope Page 40

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ANO UDit 1 - December 1998 Reactor Operator License Exam 12n w 8 Question Ni 87 QID: 0224 Point Value: 1 Given: 'Ihe plant is in cold shutdow ;

24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> endurance run on #1 DG in progres 'B' Decay Heat I4cp in servic RCS is intact. - -

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HPI pumps P-36A & P-36B are makeup flow sources Electricians have requested that D-11 be transferred to the emergency  !

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power supply to check out the transfer switc !

Should this evolution be allowed?

a. Yes, the swap to the emergency source does not disrupt any powe b. No, the swap will result in a loss of decay hea *

c. Yes, the swap will result in a momentary loss of DC control power to a makeup source, however, the source is still availabl d. No, the swap will result in tripping the #1 D Question No. 88 . QID: 0125 Point Value: 1 During the performance of the normal DG1 monthly surveillance test, while the CBOT is paralleling the diesel to the grid, he accidentally goes to closed on the output breaker with the synchroscope at the 15 minute past position. What would be the consequences of this action?

a. The output breaker will close in and immediately trip back ope b. The output breaker will close in and the diesel will automatically tri ,

c. A protective feature will prevent the output breaker from closing i d. Breaker will remain open due to a lockout relay trip.

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ANO Unit 1 - December 1998 Reactor Operator License Exam sla9s Question No. 89 QID: 0226 Point Value: 1 Given:

- Reactor has trippe Soon aAer the trip a loss of DC bus D01 occurs which resulted in an actuation of all ES even digital channel This has caused a loss ofICW cooling to all RCPs, what RCP cooling has NOT been lost?

a. sealcoolers b. seal return coolers c. lube oil coolers

' d. motor coolers Question No. 90 QID: 0227 Point Value: 1 Instrument Air pressure has dropped to 75 psi Which of the following is the appropriate response for the given plant conditions to restore or consen e Instrument Air pressure?

a. Verify Service Air to Instrument Air cross-connect automatically open b. Open Unit I to Unit 2 Instrument Air cross-connec c. Trip Reactor, actuate EFW and MSLI on both SG d. IfICW available, isolate SealInjection by closing CV 120 .

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l n ANO Unit 1 - December 1998 Reactor Operator License Exam mlaas -

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Question No. 91 QID: 0228 Point Value: 1

, Given:

- Unit at 100% power

- Due to a failure, "A" Low SG level initiate bistable is tripped in the "A" EFIC cabinet

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- I&C has the 'B' EFIC channel in bypass for monthly testing with an EFW trip signal

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present on the initiate, modul l

- I&C inadvenantly pla tbc 'C' RPS channel in manual bypas What wC!the EFIC response be?

a. H:.'ltnp on both EFIC EFW trains b. Train 'A" EFIC EFW actuation

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c. Train "B" EFIC EFW actuation d

d. Both EFIC trains will actute EFW

Question No. 92 QID: 0229 Point Value: 1 ,

Given:

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Plant startup in progress with reactor power at 10% ,

Condenser E-IIA Vacuum Pressure Switch (PS-2850) fails to 0 "H What efixt will this have on Turbine Bypass Valve (TBV) and Atmosphene Dump Valve (ADV) operadons?

a. All TBVs will temain open, both ADV isolations will open and both ADV control valves will remain close b. Only TBVs for E-11 A will close, both ADV isolations open and

'A' SG ADV will begin controlling 'A' SG pressur c. All TBVs will close, both ADV control valves will open and both ADV isolations will remain close d. Only TBVs for E-11 A will close, both ADV control valves and both ADVisolatior;willope Page 43

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ANO Unit 1 - December 1998 Reactor Operator License Exam 12naas Question No. 93 QID: 0230 Point Value: 1 I

While responding to the " RCS PRESSURE HI-LO" alarm, the CBOR observes RCS pressure at 1650 psig and falling rapidl Which oOhe following actions would be appropriate for the CBOR?

a. Obtain concurrence from CBOT, then manually actuate ESAS and make announcemen b. Announce parameter and imminent ESAS actuation, then verify proper automatic actuatio c. Obtain concurrence from CRS and then bypass ES AS prior to automatic actuatio d. Simultaneously announce action while manually actuating ESA Question No. 94 QID: 0231 Point Value: 1 Which of the following conditions is correct with regard to preparation and installation authorization of a common unit tagout?

. a. Installation may be authorized by either the Unit 1 CRS or the Unit 2 CR b. Preparers and reviewers from both units must be licensed operator j l

c. Installation shall be authorized by both the Unit I and the Unit 2 CR d. Preparer and Verifier may be non-licensed if the opposite unit verifier is license I l

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ANO Unit 1 - December 1998 Reactor Operator License Exam 12/ lass Question No. 95 QID: 0232 Point Value: 1 During a Reactor Stanup, the licensed Control Room Operators performing /supenising the stanup shall not conduct shiA relief until the reactor is critical and power is above a specific level OR the reactor is shutdown by a specific margi This does not apply during physics tesd.t Choose the answer with the correct power and shutdow1: margi POWER SDM a. >= 1.0% 1.5% delta k/k b. >= 5.0% 5.0% delta k/k c. >= 1.0% 5.0% delta k/k d. >= 5.0% 1.5% delta k/k Question No. 96 QID: 0233 Point Value: 1 An NI calibrsiion was performed yesterday. Due to a problem with a Condenser Vacuum pump, tractor power had to be lowered to 89% and has subsequently been returned to 100%. When is the next NI calibration required to be performed?

a. Within the next 7 day b. Within the next 3 day c. Within the next 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> d. Within the next 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Page 45 l

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l ANO Unit 1 - December 1998 Reactor Operator License Exam 12/laeps

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Question No. 97 QID:023,f Point Value: 1 During a SGTR, which of the following actions is performed specifically to reduce plant personnel exposure?

a. Maintaining RCS pressure low within limits of Fig. b. Steaming bad SG to maintain tube-to-shell DT <l50' c. Aligning HPI to provide PZR Aux Spray.

, d. Removing all but C & D condensate polishers from senic i

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Question No. 98 QlD: 0235 Point Value: 1 A reactor building entry is required at power to investigate a potential leak on the RCP Seal Cooling Pump (P-114).

You have been assigned to perform this tas The dose rate in area of P-Il4 is 1.8 rem /h ' Your yearly exposure to date is 1.6 re Which one of the following is the LONGEST stay time allowable WITHOUT exceeding Administrative Dose Control Limits? l

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l a. 5 minutes b.10 minutes i

l C.15 minutes

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I l d. 20 minutes j l

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ANO Unit 1 - December 1998 Reactor Operatf,r License Exam mm9s Question No. 99 QID: 0236 Point Value: /

Given:

- Alternate Shutdown in progress due to fire in the Cable Spreading Roo ;

- An imraediate control room evacuation was require Which of following is performed by the Control Board Operator (RO#1 or RO#2)?

a. Manually trip both Main FW pumps locally, b. Start and stop HPI pump to maintain PZR leve c. Manually trip the Main Turbine at the front standar d. Align steam to EFW pump P-7 Question No.100 QID: 0237 Point Value: 1 It is known that c!cvated contauunent temperatures and radiation levels can affect instrument reading How are allowances for these etTects made when parameter values are required in EOP steps?

a. Transmitters inside containment are emironmentally qualified for these effect '

b. The SE uses a set ofinstrument tables during accident condition c. SPDS displays alternate values when these conditions are reache d. EOP parameter values for these conditions are inside brackets.

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ANO Unit 1 - December 1998 Initial RO Exam Key 12nass Question No. / QID: 0131 Point Value: 1

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Answer:

d. The channel B bypass prevented by an interlock from

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' the char.nel already in bypas :

Question No. 2 QID: 0132 Point Value: 1 l

. Asswer:

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- c. 240 to 249 gallons  ;

Question No. J QID: 0133 Polet Value: 1 Answer: j b. Minimizes surge and spray line temperature differentials and ,

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maintains pressuruer boron concentration near that in the RC Question No. 4 QID: 0134 Point Value: 1 Answer: i c. Discrimination separates out gamma and alpha pulses to pro 5ide a true neutron puls With the discrimination set too high, power will indicate lower than actual powe i

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Question No. J !QID: 0135 Point Value: 1

Answer: I c. ES channe's 5 & 6. VSF-1 A, IB, IC, & ID running with senice water aligned to the cooling coil Question No. 6 QID: 0136 Point Value: 1 Answer:

c. Discharge Flume monitor is also in alar i

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- Question No. 7 QID: 0137 Point Value: 1 Answer: )

c. Both Main Feedwater Block Valves close in slow spee l

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l ANO Unit 1 - December 1998 Initial RO Exam Key 12nass Question No. 8 QlD: 0138 Point Value: 1 Answer:

b. Thermal shock to the turbine roto Question No. 9 QID: 0139 Poir.t Value: 1 Answer:

d. CRD cooling, chill water, RB leak detecto Question!!a 10 QID: 0140 Point Value: 1 Answer; a. SealInjection Question No.11 QID: 0141 Point Value: 1 Answen ,

a excessive seal wear and cavitatio I i

Question No.12 QID: 0142 Point Value: 1 '

Antwer:

d. AAct it is determined that the component is no longer needed and approval is obtained from the CRS/S Question No.13 QID: 0143 Point Value: 1 Answer:

c. Acceptable, independent verification can be waived for valve  ;

' alignments on a case by-case basis with the Superintendent's  :

approva Question No.14 QID: 0144 Point Value: 1 Answer:

d. Radworker must have a pocket ion chanoer self reading dosimeter (SRD).

Question No.15 QID: 0143 Point Value: 1 Answer:

d. Allow driving in Groups I thru 7 to engage roller nuts with lead screw _ _ - _ . _ _ _. __ _ _ . _ _ -- ._ .. - ANO Unit 1 - December 1998 Initial RO Exam Key map 8 Question No.16 QID: 0146 Point Value: 1 Answen a. 1203.027, %ss of Steam Generator Feed" l

Question No.17 QID: 0147 Point Value: 1 Answen l a. ICS will mn the plant back at 30%fmin and power will stabilize at 40%

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Question No.18 QID: 0152 Point Value: 1 1 Answen b. Startup Transformer #2 and Unit Auxiliary Transformer powered from 22 KV switchyard line l

Question No.19 QID: 0153 Point Value: 1 Answen d. One emergency Recite Fan will start, all isolation dampers close Question No. 20 QID: 0154 Point Value: 1 Answen a. RCP trip  !

Question No. 21 QID: 0155 Point Value: 1 Answer: j b. RPS channel A will tri ]

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Question No. 22 QID: 0156 Point Value: 1 Answer: l b. Overcooling 1202.003 Question No. 23 QID: 0157 Point Value: 1

- . Answer: i d. Condenser vacuum pump auto stanin .,

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i ANO Unit 1 - December 1998 Initial RO Exam Key 12nas8 Question No. 24 QID: 0158 Point Value: 1 Answer:

c. 6 days Question No. 25 QID: 0159 Point Value: I j Answer:

b. Stop one RCP in each loo Question No. 26 QID: 0160 Point Value: 1 Answer; b. Loss of DC Bus D11 i

Question No. 27 QID: 0161 Point Value: 1  !

Answen- l d. Refer to Tech Specs and recover the dropped ro {

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Question No. 28 QID: 0162 Point Value: I j Answer: )

a. 360 MWe ,

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Question No. 29 QtD: 0163 Point Value: I j Answer:

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d. CETs rising above 610 deg F with all of the RCPs of Question No. 30 QID

0164 Point Value: 1 Answer:

I a. Reduce decay heat removal flow below 2000 gpm.

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Question Nc 31 QID

0165 Point Value: 1

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Answer:

b Turbine die not trip

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ANO Unit 1 - December 1998 Initial RO Exam Key naas8 !

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Question No. 32 QID: 0166 Point Value: 1 Answen a. Bad OTSG level 410" and rising Question No. JJ QID: 0167 Point Value: 1 Answen b. Verify no release in progress at Disch Flow to Flume  ;

(F14642) on C1 j l

Question No. 34 QID: 0168 Point Value: 1 Answen b. The alignment can result in conditions that may cause excessive radiation exposur j i

Question No. JJ QID: 0169 Point Value: 1 Answen a. PZR Level Control Valve, CV-1235, will open to establish a higher steady-state PZR leve Question No. 36 QID: 0170 Point Value: 1 Answen d. To re-establish instrum:nt air and ICW coolin Question No. 37 QID: 0171 Point Value: 1 Answen

, b. Declare the rod inoperable and verify a 1.5% available shutdown margin exist Question No. 38 QID: 0172 Point Value: 1 Answen a. A plant cooldown is required and normal offsite power is NOT availabl Question No. 39 QID: 0173 Point Value: 1

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Answer:

b. For maximum batch size and adjusted based on calculation.

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h ANO Unit 1 - December 1998 Initial RO Exam Key 12nass t

't Question No. 40 QID: 0174 Point Value: 1 Answen a. The EDG output breaker will automatically close once the EDG has staned and j

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all other feeder breakers to it's respective bus are ope Question No. 41 QID: 0175 Point Value: 1 Answen c. Verify ICW for RCP Air and Lube Oil Coolers and Control Rod l Drive Outlets (CV-2220 & CV-2221) are ope l l

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Question No. 42 QID: 0176 Point Value: 1 Answen c. Notify Health Physics Dept. and dispatch two operators with SCBAs to Lower North Piping Are l

Question No. 43 QID: 0177_ _ Point Value: 1 Answen c. RCS Tave would rise, RCS ptessure would rise, Pressurizer level would rise j l

Question No. 44 QID: 0178 Point Value: 1 Answer:

a. Start all RCPs even if RCP services are not availabl Question No. 45 QID: 0180 Point Value: 1 l Answer:

d. Tave 560 degrees, SCM 25 degrees. RCS pressure 2100 psig  ;

Question No. 46 QID: 0181 Point Value: 1 Answer:

c. Only one train of HPI operating and RCS pressure >600 psi ; Question No. 47 QID: 0182 Point Value: 1 Answer:

b. Align Pressurizer AUX Soray to LPI syste _ __ _ ___ _ ._

i ANO Unit 1 - December 1998 Initial RO Exam Key class l

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l Question No. 48 QID: 0183 Point Value: 1 Answen c. If RCP seal bleedotitemperatures are >l80 degrees, CV-1207 is slowly opene:i j to minimize thermal shock to the RCP seal Question No. 49 QID: 0184 Point Value: 1 l

Answen c. Trip the reactor due to no on-scale indication of teutron flux availabl Question No. 50 QID: 0186 Point Value: 1 Answer: )

b. Overheating (1202.004)

Question No. 51 QID: 0187 Point Value: 1 Answen j d. Transfer D21 to emergency supply D0 Question No. 52 QID: 0188 Point Value: 1 l Answen d. Secure fuel handling activities until RI-8017 is operable or a suitable portable surveyinstrument is obtaine Question No. JJ QID: 0189 Point Value: 1 i Answen b. CV-1235 fails closed and Pressunzer level will lowe l Question No. 54 QID: 0190 Point Value: I f Answer:

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b.1.6 gpm 40 / 25 = 1.6 l

Question No. JJ QID: 0191 Point Value: 1 Answen c. - 18 inches

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ANO Unit 1 - December 1998 Initial RO Exam Key naa98 Questio:s No. 56 QID: 0192 Point Value: 1 Answer:

a. RSI Question No. 57 QID: 0193 Point Value: 1 Answer:

a. Tave 579 degrees, Thot 593 degrees, Tcold 564 degrees, total FW flow 6.5 million Ibm /h Question No. JS QID: 0194 Point Value: 1 Answen  ;

c. Difficulty in reducing RCS pressure l Question No. 59 QID: 0195 Point Value: 1 Answer:

c. 'B' MFP Suction Pressure computer point (P2830)

Question No. 60 -QID: 01 % Point Value: 1 Answen c. A high radiation setpoint has been exceeded on SFING Question No. 61 QID: 0197 Point Value: 1 Answer:

c. Levels may not be sufficient to reflood the vessel following a LOC Question No. 62 QID: 0198 Point Value: 1 .

Answer:

a. To prevent inadequate pump suction pressure on ECCS pumps.

r Question No. 65 QID: 0199 Point Value: 1

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Answer:

, b. The valves receive an ESAS actuation signal from ESAS channels 3 & 4.

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t ANO Unit 1 - December 1998 Initial RO Exam Key m1 ass Question No. 64_ QID: 0200 Point Value: 1 Answen c. The SFP level will stay relatively constant due to siphon holes in the discharge pipin Question No. 65 QID: 0201 Point Value: 1 Answen c. 300-340 inche Question No. 66 QID: 0202 Point Value: 1 Answen d. Trip the reactor and go to Reactor Trip tab (1202.001) of the EO s Question No. 67 QID: 0203 Point Value: 1 Answen

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c. Declare SV-2663 inoperable and deenergize CV-2663 closed.

Question No. 68 QID: 0204 Point Value: 1 Answen b. #1 DG is inoperable due to the level in T-30A being <160 gallons.

Question No. 69 QID: 0205 Point Value: 1 Answen b. The discharge valve on the tripped pump did not go completely closed and circulating wateris short cycling.

Question No. 70 QID: 0206 Point Value: I f Answen d. It can be actuated locally or by placing the MAN TRIP switch on C463 to the OPERATED position.

Question No. 71 QlD: 0207 Point Value: 1 Answen d. less of decay heat remova I

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ANO Unit 1 - December 1998 Initial RO Exam Key m1 ass Question No. 72 QID: 0208 Point Value: 1 Answen b. Close the ERV Isolation Valve (CV-1000).

Question No. 73 QID: 0209 Point Value: 1 Answen b. Prevent NaOH from leaking iro W:. DH system and causing chemical contamination of the RC l Question No. 74 QID: 0210 Point Value: 1 Answen

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d. When H2 concentration exceeds 3% with M-55A temperature at 1450'F.

Question No. 75 .QIP: 0211 Point Value: 1 Answen d. Start P-4C, stop P-4B, swap P 4B MOD (A6) to the A3 supply and start P-4B.

Question No. 76 QID: 0212 Point Value: 1 Answen c. A Pressunzer Code Safety valve becomes inoperabic.

Question No. 77 QID: 0213 Point Value: 1 Answen i a. Notify fuel handlers to stop fuel movement in the Spent Fuel Pool are ;

l Question No. 78 QID: 0214 Point Value: 1 1

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Answen d. ControlPanelCl3 Question No. 79 QID: 0215 Point Value: 1 Answen c. A marked rise in the indicated ratio on R1237R will be observe i l

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ANO Unit 1 - December 1998 InitiN RO Exam Key naas8 ,

Question No. 80 QID: 0216 Point Valutt 1 Answen -

b. - A high primary to secondary DP is increasing primary r.oolant los Question No. al ta'ah 0218 Point Value: 1 Answen a. Condensate Pump P-2C will trip leaving only P-2A running; trip reactor and ::arry out inunedate actions of 1202.001, Reactor Tri Question No. 82 QID: 0219 Point Value: 1 Answer: ,

b. EDd #1 critical troubic alarm Question No. 83 QID: 0220 Point Value: 1 l Answer:

a. Makeup flow drops, Makeup Tank level will rise.

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Question No. 84 QID: 0221 Point Value: 1 )

Answer:

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b. Reactor is at 100% power with one channel of RPS trippe l Question No. 85 QID: 0222 Point Value: 1 Answer:

a. Initially remain closed end then respond to pressure changes.

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Question No. 86 QID: 0223 Point Value: 1 I ' Answer:

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. d. P-35B NaOH Tank Outlet valve (CV-1617) ope !

Question No. 87 QID: 0224 Point Value: 1 Answer: ,

d. No, the swap will rr.sult in tripping the #1 D '

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ANO Unit 1 - December 1998 bitial RO Exam Key 12nass Question No. 88 QID: 0225 Point Value: 1 i

Answer:

c. A protective feature will prevent the output breaker fmm closing i :

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Question No. 69 QID: 0226 Point Value: 1 Answer:

b. seal return coolers 1

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j Question No. 90 QID: 0227 Point Value: 1 l

Answer:

b. Open Unit I to Unit 2 Instrument Air cross-connec l

Question No. 91 QID: 0228 Point Value: 1 J

- Answer: i c. Train *B" EFIC EFW actuation Question No. 92 QID: 0229 Point Value: 1 Answer:

b. Only TBVs for E-11 A will close, both ADV isolations open and

'A' SG ADV will begin controlling 'A' SG pressur Question No. 93 QID: 0230 Point Value: 1 Answer:

d. Simultaneously anounce action while manually actuating ESA Question No. 94 QID: 0231 Point Value: 1 Answer:

c. Installation shall be authorized by both the Unit I and the Unit 2 CRS.

l Question No. 95 QlD: 0232 Point Value: 1 Answer:

a. >= 1.0% power -

1.5% delta k/k l

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ANO Unit 1 - December 1998 Initial RO Exam Key 12a mP8

Question No. 96 QID: 0233 Point Value: 1 Answen c. Within the next 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ,

Question No. 97 QID: 0234 Point Value: 1 Answen d. Removing all but C & D condensate polishers from service.

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Question No. 98 QID: 0235 Point Value: 1 i Answen I b.10 minutes Question No. 99 QID: 0236 Point Value: 1 Answen  !

d. Align steam to EFW pump P-7 Question No.100 QID: 0237 Point Value: 1 Answen d. EOP parameter values for these conditions are inside bracket .