IR 05000368/1998301

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NRC Operator Licensing Exam Rept 50-368/98-301 for Test Administered on 980831-0904
ML20154M270
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 10/14/1998
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20154M198 List:
References
50-368-98-301, NUDOCS 9810200215
Download: ML20154M270 (119)
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Text

{{#Wiki_filter:.-..- - - -- . . ! ..- . ENCLOSURE -

U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

, Docket Nos.: 50-313;50-368 - License Nos.: APF-6 Report No.: 50-313/98-301; 50-368/98-301 Licensee: Entergy Operations, Inc.

Facility: Arkansas Nuclear One, Units 1 and 2 Location: Junction of Hwy. 64W and Hwy. 333 South

Russellville, Arkansas ' Dates: August 31through September 4,1998 l Inspector (s): Michael E. Murphy, Chief Examiner Howard F. Bundy, Senior Reactor Engineer, Examiner / Inspector Ryan E. Lantz, Reactor Engineer, Examiner / Inspector Steve L. McCrory, Senior Reactor Engineer, Examiner / Inspector Tom O. McKernon, Senior Reactor Engineer, Examiner / Inspector , Approved By: John L. Pellet, Chief, Operations Branch Division of Reactor Safety , ATTACHMENTS: ' Attachment 1: Supplemental Information Attachment 2: Final Written Examinations and Answer Keys , , 9910200215 981014 j ', PDR ADOCK 05000368 s V PDR +

- . -2-EXECUTIVE SUMMARY ' Arkansas Nuclear One, Unit 2 NRC Inspection Report 50-368/98-301 i l NRC examiners evaluated the competency of eight senior operator and six reactor operator license applicants for issuance of operating licenses at the Arkansas Nuclear One, Unit 2. The licensee developed the initial examinations using NUREG-1021, !nterim Revision 8, January 1997. NRC examiners reviewed, and approved the examinatione. The initial written examinations were administered to all nine applicants on August 28,1998, by facility proctors in accordance with the guidance in NUREG-1021, Interim Revision 8. The NRC examiners administered the operating tests on August 31 through September 4,1998.

Operations All 14 (6 reactor operators and 8 senior operators) license applicants passed their

examinations. The applicants exhibited good oversight and peer checking and effective communications (Sections 04.1,04.2).

] l The operating test material was inadequate for administration as submitted

(Section 05.1).

The facility staff's highly responsive revision and replacement of the examination

material precluded any affect on the examination administration schedule. No significant changes to examination materials were required as a result of administration (Section 05.1).

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! -3-Report Details , Summary of Plant Status - The plant operated at essentially 100 percent power on both units for the duration of this inspection.

l. Operations

Operator Knowledge and Performance 04.1 Initial Written Examination a.

Insoection Scope On August 28,1998, the facility licensee proctored the administration of the written examinations approved by the NRC to six individuals who had applied for initial reactor operator licenses, three individuals who had applied for initial instant senior operator l licenses, and five individuals who had applied for initial upgrade senior operator licenses. The licensee proposed grades for the written examinations and evaluated the results for question validity and generic weaknesses. The examiners reviewed the licensee's results.

' b.

Observations and Findinas The minimum passing score was 80 percent. The candidates' scores for the written examination ranged from 83 to 94 percent. The overall average score wa:; 88.6 percent. The licensee's post-administration analysis identified that Questions 83 and 86, common to both the reactor operator and senior operator examinations, were missed by more that 50 percent of the applicants. Analysis indicatect this was due to a failure to include specific information on the subject in the licenso class training program. The licensee initiated a training evaluation action request to ensure the information will be included in future license class training programs. No broad training or knowledge weaknesses were identified during review of applicant performance on the administered examinations. There were no post-examination comments or changes to the written examination.

c.

Conclusions All 14 apptcants passed the written examinations. No broad knowledge or training weaknesses were identified as a result of evaluation of the graded examinations.

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. - ... -. - -.. - - -.. - -.. - .. -... -.- .. .. -. _ -. - ~. - - ~ . . i-4-04.2 initial Operatina Test i a.

Lnspection Scope The examination team administered the various portions of the operating examination to the 14 applicants on August 31 through September 3,1998. Each applicant participated in the appropriate number of dynamic simulator scenarios. Each reactor operator and

instant senior operator applicant received a walk through test, which consisted of ten system and four administrative areas. The upgrade senior operator applicants were tested in five sy0 tem and four administrative areas.

b.

Observations ar,9 Findinas All applicants passed all portions of the operating test. Overall, the applicants

performed very well in the dynamic simulator scenarios with good oversight and peer checking, and effective communications noted by the examiners. The applicants displayed good knowledge of technical specifications and facility abnormal and emergency procedures. The applicants performed well on the walk-through and administrative sections of the examination.

c.

Conclusions All 14 applicants passed the operating tests. The applicants exhibited good oversight, peer checking and effective communications.

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Operator Training and Qualification 05.1 Initial Licensino Examination Develooment 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.

j 05.1.1 Examination Outline a.

Inspection Scoce ' The facility licensee submitted the initial examination outlines on May 4,1998. The chief examiner reviewed the submittal against the requirements of NUREG-1021, Interim Revision 8.

b.

Observations and Findinas The chief examiner determined that the initial examination outlines satisfied NRC requirements.

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Conclusions The licensee submitted an adequate examination outline.

05.1.2 Examination Packaae a.

Inspection Scope The draft examinations were transmitted by the licensee to the NRC on July 2,1998.

The licensee submitted the completed final examination package on August 21,1998.

The chief examiner reviewed the examinations against the requirements of NUREG-1021, interim Revision 8.

b.

Observations and Findinos The draft written examination contained 134 questions,66 of which were common to both the reactor operator and senior reactor operator examinations. All of the questions were developed for this examination. The draft examination was considered technically valid, to discriminate at the proper level, and responsive to the outline submitted by the licensee on May 4,1998. The written exatnination was considered adequate for administration as submitted.

The draft operating test consisted of four sets of administrative topics, two sets of control room systems and facility walk-through tests, and six integrated plant operation scenarios. Review of the submitted materialidentified extensive problems with format ' and quality. For example, the job performance measurements provided for the administrative topics area were not formatted to present the step by step actions expected or the acceptance standards applicable to the actions (e.g., JPM-CCWSA).

None of the Day 2 JPMs specified a radiation controlled area entry, which is required.

The wrong topic was applied in one area of all four sets and several topic area questions were presented as multiple choice instead of the short answer format of the administration test (e.g., A.1-1, A.1-2, A.3-4, A.2-8; and others). Numerous prescripted questions required extensive revision or replacement because they did not meet the predominant open reference requirements (e.g., both questions of JPM RCP020); one job performance measurement had to be replaced and a second one revised to meet the proper discriminatory level. All of the scenarios required extensive revision to insure the application of the proper transients and events as defined in the NRC Examination Standards. The operating test was inadequate for administration as submitted.

The facility staff responded with prompt and efficient revisions and resubmitted the final examination materialin a timely manner, eliminating any affect on the examination schedule.

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c.

Conclusions ! The operating test material was inadequate for administration as submitted by the

. licensee. However, the facility staff's highly responsive revision and replacement of the ! examination material precluded any affect on the examination administration schedule.

i No significant changes to examination materials were required as a result of administration.

' l 05.1.3 Licensina Conditions I ! . a.

Inspection Scooe

The chief examiner reviewed the final applications as submitted by the facility for the license applicants against the requirements of NUREG-1021, interim Revision 8.

! b.

Observations and Findinas The chief examiner verified that the facility licensee properly identified the required five l

significant reactivity manipulations on the reactor operator and senior operator, instant, l applications. The chief examiner also verified that the facility had propedy documented I these manipulations and that they were significant in accordance with NRC Information , l . Notice 97-67.

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c.

Conclusions

! The facility's program was adequate to ensure that initial applicants for reactor operator

licenses met licensing conditions for performance of significant reactivity manipulations.

05.2 Simulation Facility Performance a.

Insoection Scope l The examiners observed simulator performance with regard to fidelity during the examination validation and administration.

L ' b.

Observations and Findinas The sirnulator performance was excellent. No fidelity problems were noted. The licensee's simulator support staff was very efficient and greatly enhanced the examination schedule. Turn around times between scenarios and job performance measurements were very fast. This reduced time between scenarios and helped ease applicant stress levels.

c.

Conclusions .

The simulator and simulator staff supported the examinations well. No fidelity issues were identified.

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._. .. . - - - ... , _ _. _ _.. - . . -.... .... l .. i-7-V. Mananement Meetinos - X1 Exit Meeting Summary The examiners presented the inspection results to members of the licensee , management at the conclusion of the inspection on September 4,1998. The licensee acknowledged the findings presented.

  • The licensee did not identify as proprietary any information or materials examined during this inspection.

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....,. . . -. -. ... .. - . . ATTACHMENT 1 SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED Licensee , ! B. Bement, U-2 Plant Manager M. Blancharo, U-2 Simulator Instructor R. Byford, Operations Training S. Cotton, Training /EP Director J. Giles, Operations Training Supervisor J. Hatman, Simulator instructor L McLerran, Simulator Supervisor T. Russell, U-2 Operations Manager D. Sealock, Simulator Supervisor G. Woolf, Simulator Instructor

NRC K. Kennedy, Senior Resident inspector

INSPECTION PROCEDURES USED NUREG-1021, NUREG-1021," Operating Licensing Examination Standards," Interim Revision 8, ' January 1997"

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4 ATTACHMENT 2 FINAL WRITTEN EXAMINATIONS AND ANSWER KEYS

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+ U.S. Nuclear Regulatory Commission l Sito-Specific ! Written Examination Appscantinfonnation l Name: Repon: IV Date: Facibty/ Unit ANO-UNIT 2 License Level: RO ReacbrType: CE StartTrne: FmishTrne: I instructions Use the answer sheets provided to document your answers. Suple this cover sheet on top of the answer sheets. The passing grade requires a Anal grade of at least 80.00 percent. Examination papers l will be collected four hours after the examination starts l Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Appbcanfs Signature l Results l Examination Value 100 Points Applicants Score Points Appicanfs Grade Percent ! !

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.. . - -... - -. - - -.. . - . _ -.. _. -. . -. -.. - _. .. -.. ~...... - - - -.. Q ANO UNIT 2 - INITIAL RO EXAM ' QUESTION:

QlD: 0069 Rev: 000 Point: 1.00 A small Main Feedwater line break downstream of Main Feedwater Check valve (2FW-5A) at full i power will depressurize the affected Steam Generator and start an uncontrolled cooldown when: l A. The reactor trips on low Steam Generator level.

B. The main feedwater isolation valve is closed to "A" Steam Generator.

C. Main Feedwater and Emergency Feedwater to "A" Steam Generator is secured.

D. The "A" Steam Generator level drops below 50% W& Range level.

QUESTION:

QlD: 0007 Rev: 000 Point: 1.00 Which one (1) of the following methods is used to verify the position of a FULLY OPEN m anually-operated valve? i A. Operate the handwheel to close the valve fully and then reopen the valve to a lightly backseated open position.

B. Operate the handwheel approximately one (1) tum toward the closed dirochon and then back to a fully open position.

C. Operate the handwheel towwd the open direction direction, if the handwheel does not move, the valve is fully open D. Operate the handwheel toward the open direction until the valve is backseated open ' one-half turn.

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_ _ _ _...., _.... _ _ . _ _. _ _ _.. _. _. _. _ _ _ _.. _ _ _ _ _ _ _ _.. _ _.. _. _ Q ANO UNIT 2 - INITIAL RO EXAM , . QUESTION:

QlD: 0005 Rev: 001 Point: 1.00 A plant startup is in progress and the following condstions exist-

  • The rcactor is entical at SE-5% power.
  • Tave is at 545 degrees F.
  • A rod control failure causes the selected control bank of rods to step out five (5) steps before being stopped by the operator.
  • No reactor trip occurs.

Which one of the following desenbos the effect that this event will have on reactor parameters over the next minute? A. Reactor Power will rise, Tave will be unaffected.

B. Reactor Power and Tave will both rise.

C. Reactor Power will be unaffected, Tave will rise.

D. Reactor Power will rise, the response of Tave will depend upon core life.

O QUESTION:

QlD: 0004 Rtv: 000 Point: 1.00 Which one of the following alarms requires entry into OP 2203.020 (High Reactor Coolant Activity)? A. Annunciator 2K11-A10. "SEC SYS RADIATION Hi".

B. Annunciator 2K12-A1, " LETDOWN RADIATION Hl/LO".

C. Annunciator 2K11-C10, " PROC LIQUID RADIATION Hl/LO".

D. Annunciator 2K10-A6, "CNTMT RADIATION Hi".

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QlD: 0011 Rev: 000.

Point: 1.00 Which one (1) of the following conditions requires the affected Reactor Coolant Pump (RCP) to be tripped? , l 'A. Seal Bleadoff Temperature reaches 180 degrees F.

' B. Motor Wmdmg Temperature reaches 180 degrees F.

C. Vapor Seal Pressure reaches 750 psia.

- D. Component Coolmg Water Flow is lost for over 10 minutes.

_ QUESTION:

QlD: 0015 Rev: 000 Point: 1.00 ) l ' Given the following:

  • Two (2) CEAs failed to insert on a Reactor Trip from full power.

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  • RCS Pressure is 1800 psia.

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  • HPSI Pump 2P89A is running.

l . l Which one (1) of the following Emergency Boration methods should be selected if VCT Outlet valve (2CV-4873-1) is open and will NOT close from the Main Control Board? A. Open Boric Acid Gravity Feed valves (2CV-4921-1 and 2CV-4922-1).

B. Open RWT to Charging Pump Suchon valve (2CV-4950-2).

C. Open Emergency Borate valve (2CV-4916-2) and start BAM Pump.

D. Open CVCS to HPSI Train valve (2CVC-115).

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_ _ -. _. _ _ _ _.. . _ -. _ _.. _. _ _ _ _ _ _. _ _ _ . _ _ _. _. _. _. _. _ _ _ _ _. _ _ _. A Q ANO UNIT 2 - INITIAL RO EXAM QUESTION:

Q1D: 0016 Rev: 000 Point: 1.00 l ! Given the following plant condstions:

  • The plant has tnpped from 100% power.

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  • 2202.001, Standard Post Trip Actions, has been entered.

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  • The Main Turbine did NOT automatically trip.

i Which one (1) of the following actions should be performed per 2202.001, Standard Post Trip Actions? - . & ' A. Manually close the MSIVs from the control room.

B. Manually open the Generator output breakers.

C. Manusily trip the Generator Exciter Field breaker.

! l D. Manually trip the Turbine at control panel 2C01.

, ! ! . I l ' - QUESTION:

QlD: 0018 Rev: 000 Point: 1.00 . ). Given the following: , !

  • The reactor has tripped from 100% power.

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  • Pressurizer pressure is 1275 psia and DECREASING.

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  • Pressurizerlevelis 3%

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  • CETS indicate 450 degrees F.
  • All required ESFAS Actuation have actuated.

l Which one (1) of the following is the MINIMUM operator schon for the above conditions per 2202.001, Standard Post Trip Actions? . A. De-energize the pressurizer backup heaters and reduce auxiliary spray to less than 165 gpm.

i j B. Secure pressurizer spray and energize ALL heaters.

C. Stop one (1) RCP in each RCS loop, j D. Stop ALL RCPs.

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QlD: 0021 Rev: 000 Point: 1.00-Which one (1) of the folloung is best to determine the Steam Generator (SG) to be isolated when a l tube rupture occurs in BOTH Steam Generators? ) ' A. Water Levels.

B. Feedwater Flow Rates.

I* C. Radiation Levels.

D. Boron Concentrations.

L QUESTION:

QlD: 0023 Rev: 000 Point: 1.00 Which one (1) of the following Refueling conditions requires boration per Technical Specification 3.9.1, Refueling Operations? A. RCS boron concentration is 2250 ppm.

O , B. 1/M plot is a horizontal line after fuel movement has ceased.

l C. RCS temperature is 68 degrees F.

D. Keff is less than 0.95.

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Q ANO UNIT 2 - INITIAL RO EXAM l QUESTION:

QlD: 0027 Rev: 000 Point: 1.00 Given the follomng:

  • The RCS has a stuck open Pressurizer Safety valve.

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  • The reactor tripp>d and safety injechon has actuated.
  • The RCS has rap'dly depressurized to saturation conditions.

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  • Pressurizer levelinitially dropped and then began to rise rapidly.

' ) Which one (1) of the following charactenzos the relationship between pressunzer level and RCS j inventory and the reason for these conditions? , A. Level is NOT an accurate indicabon of inventory. RCS voidmg may result in a rapidly '

l increasing pressurizerlevel.

B. Level is NOT an accurate indicabon of inventory. The cold calibrated pressunzer level l I channels indicate high during high temperature, low pressure conditions.

C. Level is an accurate indicabon of inventory. Voidmg would occur first in the pressunzer steam space due to the high temperature of the pressurizer walls.

D. Level is are accurate indication of inventory. RCP flow would sweep any voids from the

_ RCS to the pressurizer steam space and out the safety, i l , ' QUESTION:

QlD: 0028 Rev:001 Point: 1.00 Given the following-

  • Reactor poweris 10%.
  • A main turbine roll to 1800 rpm is in progress.
  • Condenser vacuum has begun degrading.
  • Annunciators 2K03-A3/A4 "2E11A/B Pressure Hi) are actuated l

Which one (1) of the following immediate actions should be taken by the Crew? A. Reduce turbine speed to stabilize condenser vacuum.

I' B. Raise Tave to reduce SDBCS load.

C. Trip the turbine before exceeding 7 inches Hg absolute.

. D. Observe the vacuum trend to determine if the turbine must be tripped over the next five (5) minutes.

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- -. - - - _.. - -.. _ Q ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0030 Rev: 000 Point: 1.00 Which one (1) of the following desenbos the effect on the source range nuclear instruments if excessive voids are formed in the core due to inadequate core coolmg? A. Count rates would decrease due to more moderation vnthin the core causing less fast neutron leakage B. Count rates would decrease due to less moderation vnthin the core inserting negative reactivity to decrease the shutdown power level.

C. Count rates would increase due to less moderation within the core causing more fast neutron leakage.

D. Count rates would increase due to more moderation within the core inserting positive reactivity to increase the alwtdown power level.

QUESTION:

QlD: 0031 Rev: 000 Point: 1.00 Given the following conditions:

  • The plant is in Refuelmg Operstma with core alterations in progress.
  • Steam Generator secondary manways are removed.
  • The Steam Generator primary side manways are open with nozzle dams installed.
  • Both LPSI and Spray Pumps are operable Which one (1) of the followmg maintenance activities requires a suspension of core alterations and movement of irradiated fuel in Containment?

A. Testing the automatic isolation of the Containment Purge valves.

B. One (1) LPSI Pump is taken out of servk:e to test breaker over-current settings.

C. Starting to perform the eddy current testing of the steam generators.

D. Steamline safety valves are removed for bench testing of lift setpoint.

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Q- . ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0036 Rev: 000 Point: 1.00 Which one (1) of the followng describes the apphcation of CAUTIONS in Emergency Operating ~ Procedures (EOPS)? A. Only apply to the contmuous acbon steps of that procedure.

B. Apply to ALL steps following the CAUTION statement.

C. Apply to the entire procedure in which the CAUTION is listed.

D. Apply to the step immediately folioeng the CAUTION.

QUESTION:

QlD: 0037 Rev: 001 Point: 1.00 Which one (1) of the folloung would require development of a Temporary Alterate package? (Reference material provided) A. Performing a channel calbrate in which the procedure requires installing jumpers to s electncaly bypass automatic actuabon.

B. A blank flange is installed on a tagged out line while reroutng the line under an approved Job Order.

C. Connectmg cables from 480V Motor Control Center (MCC) to a temporary power panel for outage maintenance support.

> D. Maintenance technicians installmg a temporary drain hose to support changing oil in a pump.

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QlD: 0038 Rev: 000 Point: 1.00 l While performing a Techn6 cal Specification Surveillance Test, sa unacceptable condition occurs.

Which one (1) of the following is the required action? A. Continue the test to the next logical hold point while recording data as required and then inform the Shift Supenntendent.

B. ImmMiately notify the Shift Supenntendent.

C. Record data as observed and allow Shift Superintendent to compare parameter with acceptance cnteria upon completion of the test.

D. Record data ss observed and note the out-of-spec parameter in the comments sechon.

QUESTION:

QlD: 0043 Rev: 000 Point: 1.00 Cuttog and welding in the Auxiliary Building were completed at 1410. Which one (1) of tl e following is the EARLIEST time the fire watch can be secured? O A. 1420.

B. 1430.

C. 1440.

D. 1510.

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Q1D: 0044 Rev: 001 Point: 1.00 A Maintenance Contractor assigned to the Refuelmg Team has been assigned the task of breaking the incore detector flanges. Given the following infonnation on dose history and dose rate, what is his stay time for the job? - Committed Dose Equivalent- 0.75 REM - Deep Dose Equivalent- 0.8 REM - Lens Dose Equivalent- 0.2 REM , - Commdted Effective Dose Equivalent-0.2 REM ' - Dose Rate at Flanges 0.g R/HR i " A.1.0 hour.

j B. 2.0 hours.

C. 3.0 hours.

D. 4.0 hours.

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i QUESTION:

Q1D: 0045 Rev: 000 Point: 1.00 ' Which one (1) of the following is the required MAXIMUM interval between performing safety function status checks per 2202.004, Loss of Coolant Acadent? i A. Perform every 5 minutes.

B. Perform every 10 mmutes.

C. Perform every 15 minutes.

D. Perform every 30 minutes.

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. QlD: 0046 Rev: 000 Point: 1.00 Given the following conditions:

  • The MSIVs must be tagged in the OPEN position for repacking in MODE 6.
  • The instrument Air supply isolation valve will be tagged CLOSED.

Which one (1) of the following items should be included in the MINIMUM Personnel Protective equipment tagging requirements? A. Lift the leads on the MSIS solenoid valves.

B. Place the Control Room handswitches for the MSIVs to OPEN.

! C. Open the vent on the valve operator.

D. Installlocking pins for MSIVs.

QUESTION:

QlD: 0049 Rev: 001 Point: 1.00 t Which of the following parameters determine the Pressurizer Level Setpoint Program? A. Main Steam flow.

B. RCS flow.

C. RCS Thot.

D. RCS Tave.

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QlD: 0052 Rev: 001 Point: 1.00 Given the following conditions:

  • A small feedime break inside containment has resulted in containment temperature increasing from 100 degrees F to 160 degrees F and containment pressure increasing from 14.5 to 17.0 psia.

Which one (1) of the following describes how and the reason why the increase in containment temperature will affect the indicated pressurizer level? A. Indicated level will be LOWER than actual level because of the elevated containment pressure.

B. Indicated level will be HIGHER than actual level because the reference leg fluid density decreases.

C. Indicated level will be HIGHER than actual level because of the elevated containment pressure.

D. Indicated level will be LOWER than actual level because the reference leg fluid density decreases.

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_ - _. _. _. _ _. _ _. -. _.. _ _. _ _ _.... _. _. _ _ _.. _.. _. _ _ _ _ _ _ _. _ _. _. _ ] - ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0053 Rev: 000 - Point: 1.00 Given the following conditions:

  • The plant is in HOT SHUTDOWN.
  • Safety injechon Tank parameters are as follows:

SlT LEVEL (%) PRESSURE BORON (PPM) 2T2A

605 2300 2T2B

610 2400 2T2C

615 2500 2T2D

620 2600 Which one (1) of the Safety injechon Tanks (SITS) will prevent entry in HOT STANDBY per , Technical Specifications? A. 2T2A.

B. 2T2B.

, C. 2T20.

V D. 2T20.

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. QUESTION:

QlD: 0059 Rev: 000 Point: 1.00 . Given the followmg Main Feedwater Pump operating parameters exist for one (1) minute: .

  • Suchon pressure is 200 psig.

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  • Suction flow is 2700 gpm.

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  • Bearing temperature is 170 degrees F.

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  • Bearing oil pressure is 15 psig.

f-Which one (1) of the following conditions will automatically trip the Main Feedwater Pump? ) A. Suchon pressure.

I B. Suction flow.

! j C. Bearing temperature.

D. Bearing oil pressure.

LO l ! !' age 13 i 1,

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Q ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0060 Re'1;.^00 Point: 1.00 Which one (1) of the following desenbos the effect of a Waste Gas Decay Tank pressure increasing to 400 psig? A. A rupture disc will relieve pressure to Containment.

B. A rupture disc will relieve pressure to the Waste Gas Surge Tank.

C. A rupture disc will unisolate a relief valve and relieve pressure to Containment.

D. A rupture disc will unisolate a relief valve and relieve pressure to the Waste Gas Surge Tank.

QUESTION:

Q1D: 0061 Rev: 000 Point: 1.00 Which one (1) of the followng Area Radiation Monitors has Technical Specircabon operability requirements? A. 2RITS-8903,354 Aux Bldg VCT Access Area monitor.

B. 2RITS-8912,404 Containment SW End Refueling Dock monitor.

C. 2RITS-8916,404 Spent Fuel Pool General Area monitor.

D. 2RITS-8917,354 Aux Bldg Hot Lab Sample Room Area monitor.

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- . ... - - -. - .. .. - - -. - - _.. . - - - _ -. -... - -. _ - - - - - -.. i Q ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0062 Rev: 001 Point: 1.00 Which one (1) of the folioeng actons confirms that a Process Liquid radiation monitoring instrument with a normal background reading is functional from the detector to the meter? A. Placing the selector switch in HV (High Voltage) and insuring detector voltage is correct.

B. Placing the selector switch in LEVEL CAL, checking the high alarm setpoint and valve isolation.

C. Placing the selector sutch in CHECK SOURCE, observing an increasing meter reading and valve isolation.

D. Removing the high-voltage power cable and observing the count rate decreasing to a lower value.

QUESTION:

QlD: 0063 Rev: 000 Point: 1.00 . Which one (1) of the follomng describes the purpose of the thermocouples in the incore detector , strings? A. Temperature compensabon for the Reactor Vessel Level Monitoring System.

B. Indication of core coolant outlet temperature.

, C. Coolant temperature data to the excore nuclear instruments for density correchon D. Mapping of core temperature for calibration of RTDs.

i

O ,

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I Q ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0066 Rev: 000 Point: 1.00 Which one (1) of the following fuel handling events is addressed in 2502.001, Fuel Shuffle? A. A spent fuel assembly is damaged whde being withdrawn from the core.

B. A new fuel assembly if found with the moton sensors tripped during fuel receipt inspection.

C. The Reactor goes entical while a fuel assembly is being inserted into the core.

D. A CEA is hanging from the upper guide structure during the removal of the upper guide structure.

QUESTION:

QlD: 0067 Rev: 000 Point: 1.00 l A Loss of Offsite Power has occurred and both Emergency Diesel Generators and AAC Generator have failed to start automatically or manually, if power intenuption is expected to exceed minutes, then Vital Inverters 2Y13 and 2Y24 are to be secured? A.15 minutes.

B. 30 minutes.

C. 60 minutes.

D.120 minutes.

QUESTION:

QlD: 0002 Rev: 000 Point: 1.00 The plant is at 75% power when a new Lotdown Domineralizer is placed in service. Which one of the following will occur if the boric acid saturation of this domineralizer is incomplete? A. Tave willincrease.

B. Tave will decrease.

C. Lithium concentration will go up.

D. Letdown flowrate will decrease.

O Page 16 ._ _ _

.--. . - -. -. . - -... -. . - -.. -.. - - -. -. - -. -. - -. - - . -.. -. - - - , Q ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0071 Rev: 000 Point: 1.00 Which of the followmg describes the reason for the requirement to have a Hot Leg vent path for a Loss of Shutdown Cooling when the Steam Generator nozzle dams are installed? A. To prevent steam formation in the hot leg from causing an erroneously high Reactor Vessel levelindication.

B. To prevent steam formatum in the Reactor Vessel head from pressurizing the RCS, leading to core uncovery.

C. To prevent steam formation in the hot leg which will ultimately collapse, causing severe water hammer.

D. To prevent the loss of RCS inventory caused by lifting a Low Temperature Overpressure ' Protection (LTOP) relief valve.

QUESTION:

QlD: 0072 Rev: 000 Point: 1.00 i ' While operating at power, significant current oscillations (100 amps) are observed on 480V bus 2B5.

Annunciator 2K12-B3, " CHARGING PUMP HEADER FLOW LOW" actuates and shortly thereafter, l Charging Pump 2P36A trips on overcurrent. Which of the following actions should be taken? A. Start an attemate charging pump after verifying its suction and discharge path.

B. Restart Charging Pump 2P36A after resetting the overcurrent trip.

C. Secure letdown and initiate an investigation for the loss of Charging Pump 2P36A.

D. Secure letdown, start an alternate charging pump, then restore letdown.

O Page 17 ,- - .-. . .. - .

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QlD: 0073 Rev: 000 Point: 1.00

All of the following allow termination of Safety injechon after a small tM LOCA except? A. Subcooled magin 50 degrees F.

, B. Pressurizer Level 35% and dropping slowly.

C. RVLMS level 2 wet.

D. Steam Generator Level 23% NR.

l QUESTION:

QlD: 0077 Rev: 000 Point: 1.00 l l If a fire in the Cable Spreading Room bums for 45 minutes before it is extinguished, which of the i followng will still be reliable irubcabon for RCS pressure? A. Safety Parameter Display System (SPDS) poet P4624-2.

B. Pressurizer Pressure Control Channel Indicator P4626A.

C. Pressurizer Pressure Safety Channel Indicator 2P4626-1B.

j D. Pressurizer Pressure Low Range Pressure Indicator 2P4623-1.

l l l QUESTION:

QlD: 0078 Rev: 000 Point: 1.00 immediately upon confirmation of a fire, the dedicated Board Operator is responsible for all of the followmg actions EXCEPT: A. Making preliminary repor=bility verification.

B. Notify person reporting the fire to evacuate all non-fire brigade personnel from the area.

C. Obtaining pertment information from the person confirming the alarm.

D. Ensure the SS/CRS is nobfied.

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\\ ! Q ANO UNIT 2 -. INITIAL RO EXAM l-QUESTION:

QlD: 0079 Rev: 000 Point: 1.00 .! .

Which of the following Reactor Trip Circuit Breakers would indicate open on a loss of 120V Vital AC j bus 2RS-17

A. Breakers 1 and 5.

l-B. Breakers 2 and 7.

' l C. Breakers 3 and 6.

i D. Breakers 4 and 8.

i

i j ( QUESTION:

Q10: 0081 Rev: 000 Point: 1.00

{ Which of the following reflects the pnmary concern of the operators after a major steam line break i upstream of the MSlV in which the affected Steam Generator blows dry? . A. Ensure the RC'3 reheats back to normal operating temperature vnthin Tech Spec heatup limits.

lO i B. Maintain r,ubcooling margin between 30F and 200F.

i j C. Energira all pressunzer heaters to re-establish aaturated conditions in the pressurizer.

! D. Re-estselish all safety injection flow.

i } QUESTION:

QlD: 008g Rev: 000 Point: 1.00 1-Which of the following desenbos a condition snat prevents the Refueling Machine from entering the - upender zone? f i-l A. Fuel Holst Box is latched.

' B. Hoist is at Holst Up limit.

C. Spreaderis fully retracted.

D. Uponderis completely horizontal.

O Pa0819 <

i

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. . d l ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0090 Rev: 000 Point: 1.00 , Which of the EE ;f..g devices is used for detecting Pressunzer Code Safety lift? , A. Heated juncbon thermocouple.

f B. Resistive Temperature device.

j-C. Accelerometers.

! j j ~ D. Proximity device.

i

-

a

QUESTION:

QlD: 0093 Rev: 000 Point: 1.00 Which of the following is the correct response if an EDG is paralleled to the grid and the govemor

and voltage control hand switches are both taken to Raise / Increase? f l A. KW increases and EDG speed increases.

i ' B. Reactive load irweases and KW increases.

  • C. Indicated output voltage increases and reactive load increases.

. l D. EDG speed increases and indicated output voltage increases.

e , ! QUESTION:

QlD: 0094 Rev: 000 Point: 1.00 . Which of the followmg describes 4160V breaker operation if DC control power is lost? < A. Breakers will remain in their"as is" condation and operation would only be possible by local i manual means.

i

B. Automatic breaker trips would remain operational but remote operation of breakers would j not be possible.

C. Breakers would remain remotely operable but automatic trip functions would become inoperable.

. i ] D. Breakers would trip open and operation would not be possible by local means.

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Q ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0095 Rev: 001 Point: 1.00 The output of the Vital 120VAC Inverters is considered to be urtinterruptit,le because: A. Auchoneered AC power supplies are provided to the recbfier sechon B. Inverter input is auchoneered between the rechfier output and a DC Battery Bus supply.

' C. An internal battery is autioneered with the rectifier output.

D. The static transfer switch automatically transfers to AC attenate source.

QUESTION:

QlD: 0097 Rev: 000 Point: 1.00 A cooldown to Mode 5 using the Steam Dump and Bypass Control System is in progress.

] Plant conditions are as follows: j

. l

  • Steam Generator A & B pressures are 745 psia.
  • Reactor Coolant System temperature is 508F.
  • Pressurizer pressure is 2100 pais and level is 33%.

,

  • RCPs 2P32A, B and C are operating.

'

  • Charging Pumps 2P36A and 2P36B are operating and Letdown is in automatic control.

i Select the action which should be performed to prevent an inadvertent Engineered Safety Features l Actuation #,.wl (ESFAS).

A. Roset the Pressurizer low pressure trip setpoints.

B. Raise Pressurizerlevel to 50%. ? C. Bypass the Pressurizer low pressure trip.

D. Roset the Steam Generator low pressure trip setpoints.

, O Page 21 ' _ _ -.

. _ _ _.. _ _ _ _ _.. _ _ _ _ _ _ ~. _ _ _ _ _ _ _ _ _ _, _ _ _ _ _ _ _. _... _ _. _. _ _ _ _ _ _ _ _ _.. . Q ANO UNIT 2 - INITIAL RO EXAM , QUESTION:

QlD: 0099 Rev: 001 Point: 1.00 Following a single channel CPC trip, how can the opcmtor quicidy determine if the trip signal is due , to an auxiliary trip? A. By obtaining the CEAC Trip Buffer Report.

B. By observing a trip light without the associated protrip light.

C. By obtaining the trip TRA report.

D. By observing that Diverse Scram System (DSS) Trouble annunciator has actuated.

j l ' QUESTION:

QlD: 0101 Rev: 000 Point: 1.00 The motor thermal overloads for 2CV-5015-1 (High Pressure Safety injechon valve) are bypassed ' on..... A. RAS to ensure the valve can be &uto opened and ovemden closed.

O B. SlAS to ensure the valve can be manually opened only.

C. SlAS to ensure the valve can be opened.

D. SIAS to ensure the valve can be closed.

, QUESTION:

QlD: 0102 Rev: 000 Point: 1.00 The RCS High Point Vents are required to be operable in Modes 1,2,3 and 4 to: A. Limit combustible mixtures.

B. Prevent steam or non-condensables from interfering with natural circulation.

C. Equalize pressure between the Pressurizer and Reactor Vessel head.

' D. Ensute that hot leg injechon reaches the core.

O Page 22 . - . .- - -.

. - . - - -. - -. _.. -. - -. .. -... -. -. _ -. -. -.. . l l Q ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0104 Rev: 001 Point: 1.00 An EFAS 1 signal will be present for which of the following? (consider each answer separately).

A. SG "A" Level = 20% NR & Press = 600 psia SG "B" Level = 26.5% NR & Press = 600 psia.

B. SG "A" Level = 30% NR & Press = 700 psia SG "B" Level = 25% NR & Press = 680 psia.

C. SG "A" Level = 15% NR & Press = 200 psia SG "B" Level = 20% NR & Press = 400 psia.

D. SG "A" Level = 5% NR & Press = 500 psia SG "B" Level = 10% NR & Press = 370 psia.

l l QUESTION:

QlD: 0105 Rev: 001 Point: 1.00 Which of the following events is in progress for the given conditions? - RCS pressure, temperature, power, and inventory stable.

- Steam Generator pressure and levels stable.

,

- Containment temperature, pressure and humidity rising rapidly.

- Containment Sump indicates a 150 gpm increase.

A. RCS leak in Containment.

B. Main Steam Leak in Containment.

! C. CCWleakin Containment.

D. Main Feedwater leaUn Containment.

! l < Page 23 I .__-

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_ _. _ _. _.... _ _ _. _ _. _ _ -. _ _ _. _ _ _... _. _. _. _ _._..___ _, . i i Q ANO UNIT 2 - INITIAL RO EXAM i QUESTION:

QlD: 0106 Rev: 000 Point: 1.00 With Hot and Cold leg injection in progress, which of the following temperature indications should be i

used to monitor RCS temperature? a ~1 A. - Average Core Exit Thermocouples.

l B. Hot leg safety channel.

l C. Cold leg safety channel.

D. Hot leg control channel.. , t i 7- !

QUESTION:.52 QlD: 0110 Rev: 000 Point: 1.00 i

The following condstions exist i

i

  • A feedline break has occurred inside containment.

!

  • Containment pressure is 18.5 psia.

l

  • Containment radiation is normal.

- * PZR pressure is 1825 psia.

[

  • RWTlevel!s 92%.

}

  • SG pressures are (SG"A") 925 psia, (SG"B") 580 psia.

j

  • SG levels are (SG"A") 22% NR, (SG"B") 10% NR

All of the following actuation signals should have occurred with the exception of:

s ' A.SMS B. MSIS C. EFAS 1 D.CSAS O Page 24 .. _ -

. _ _ _.. _ _. _.. _... _ _.. _. _ _. _ _ _.. _. _ _.. _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _. - . i O ANO UNIT 2 - INITIAL RO EXAM i QUESTION:

QlD: 0114 Rev: 000 Point: 1.00 ' , Which of the following is the reason for preventing the start of the fourth Reactor Coolant Pump until . RCS temperature is greater than 500 degrees Farenheight? ' ' A. To prevent exceedmg RCS heatup rate lets.

B. To prevent excessive RCP startmg currents.

C. To limit Steam Generator tube. stresses.

, , D. To limit core uplift.

QUESTION:

QlD: 0115 Rev: 000 Point: 1.00 A cooldown and depressurization is in progress. RCS pressure is currently at 1100 psia and seal pressures for RCP 2P32B are:

  • vapor 40 psia.

O

  • Upper 40 psia.
  • Middle 530 psia.

Which RCP seal has failed? A. Lower seal.

B. Middle seal.

C. Upper seal.

D. Vapor seal.

O

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.._. _ _._..... _. _. _ _ _ _.. _. _....-._._. _._ _ _ _ _. _. _.._ _. _ - i ANO UNIT 2 - INITIAL RO EXAM ' QUESTION:

QlD: 0116 Rev: 000 Point: 1.00 While performing a reactor stastup, which of the following indicates the EARLIEST time that you should antmipate eMiy? A. When the shutdown banks are being withdrawn.

2 _ B. When the first regulahng group is being withdrawn.

C.' When the 1/M plot indmates enticality within the next 100 inches.

D. When inside the window of five to seven doublings.

QUESTION:

QlD: 0118 Rev: 000 Point: - 1.00 The CBOR is withdrawing CEA's in the Manual Sequential mode during a Reactor Startup.

Regulating Group 4 has just started outward motion from 0.0 inches. At what Regulatmg Group 4 ' position should Regulating Group 5 start outward motion? ' A. 50 inches.

s B. 75 inches.

' C.100 inches.

D.125 inches.

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ANO UNIT 2 - INITIAL RO EXAM ,

QUESTION:

QlD: 0121 Rev: 000 Point: 1.00 ! Fuel is being reloaded into the Reactor Vessel when the Shift Supervisor informs you that one , startup channel neutron flux monitor has failed. Which of the following describes the required schon? ' A. Fuel reload may contmue provided backup boron samples are taken every four (4) hours.

B. Fuel reload may continue provided the inoperable channel is retumed to operable status within four (4) hours.

. ' C. Suspend core alteratums until boron sampling has been inititated every twelve (12) hours for 36 hours.

' D. Suspend core altersbons until the inoperable channelis retumed to operable status.

QUESTION:

QlD: 0124 Rev: 000 Point: 1.00 , Which of the fol!owing best describes the condition in which the ANO overbme working hour pohcy applies? \\ A. a person working in training performing simulator operations.

, l B. a person working on a procedure revision for a quality related system.

C. a person working on a non-safety related system or component.

, i ' O. e person working on safety-related system or component.

! '! !

! $

) , !O .' { Page 27

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_. _.. _. _ _. _. _ _. _.. _ _. _.. _ _ _ _ _. _ _ _. _ _ _. _ _ _ _. _ _. _. _ _. _. _ _ _. _ _. O ANO UNIT 2 - INITIAL RO EXAM QUESTION:

Q1D: 0125 Rev: 000 Point: 1.00 A Waste Control Operator is required to complete a valve Imeup in an area where the radiation level is 50 rnrem/ hour. The operator's current Total Effective Dose Equivalent (TEDE) is 1730 mrom.

What is the maximum time he can work in this area and not exceed his Administrative Dose Control Level (ADCL)? A.1 hour.

B. 5 hours.

C.10 hours.

l D. 25 hours.

) , QUESTION:

QlD: 0127 Rev: 000 Point: 1.00 Given the following plant conditions:

  • Unit operating at 100% power.
  • Channel "D" upper detector of excore safety channel monitors ie.N HIGH.

Which one (1) of the f*2,g describes the expected response of Channel *D" Reactor Protection System to this failure? (No other fasiures are present) A. High Local Power Density and Low DNBR trips without pre-trips.

B. High ' og Power, High Local Power Density and Low DNBR trips and pre-trips.

C. High Log Power, High Local Power Density and Low DNBR trips without pre-trips.

D. High Linear Power, High Local Power Density and Low DNBR trips and protrips.

O Page 28

. _ _ _ _ _ __ ... _ _ _ _ _. _ - _ _. _ _... _ _ _ _. . _.___ ___ _..._ _ , lQ ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0129 Rev: 000 Point: 1.00 j

Given the follomng condetions: < !

  • Pressurizer Level Control System master controller is in AUTO REMOTE.
  • Level Control is selected to Channel 2.

!

  • Heater Low Level Cutout is selected to BOTH.
  • Reference leg of 2LT-4627-2 develops a leak.

. j WHICH ONE of the following describes the response of the Pressurizer Level Control System? ! A. Backup charging pump starts, heaters energize, letdown flow decreases.

' B. Backup charging pump starts, heaters cutout, letdown flow decreases.

i

C. Backup charging pump gets a stop signal, heaters energize, letdown flow increases.

D. Backup charging pump gets a stop signal, heaters do not change state, letdown flow j increases.

e h t-I - QUESTION:

QlD: 0130 Rev: 000 Point: 1.00

l An accident has occurred that results in the follomng indications which have been tracked for the - past FIVE minutes:

  • RCS Pressure:

1650 psia and stable.

  • RCS Cold Leg Temperatures:

540,542,538,542 degrees F.

!

  • Pressurizer Level:

20% and decreasing.

  • Margin To Saturation 67 degrees F.
  • Containment Pressure 18.9 psia.

]

  • RCPs:

All running.

i Which one of the following descnbos the operator schon required to respond to these conditions? l Assume all automatic actions have occurred correctly.

j A. Stop the RCPs since the SIAS has isolated CCW flow to the RCPs.

j B. Stop the RCPs since the CIAS has isolated CCW flow to the RCPs.

i C. Trip two RCPs since SlAS has actuated.

i i D. Override and restore CCW Flow to RCPs.

, LO

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q i

)Q ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0133 Rev: 000 Point: 1.00 i Which one of the followmg DC electrical sources supplies control power to Emergency Diesel ' Generator #17 A. 2D23 ! q B. 2D24

C. Battery Eliminator 2D35.

D. Rectified exater output.. i QUESTION:

QlD: 0135 Rev: 000 Point: 1.00

1

-Assummg two Atmosphenc Dump valves are out of service. Which one of the following best i.

approximates the remaining total steam flow capacity of the Steam Dump and Bypass Control j System? {' A. 25% B. 30% , C. 40% ! ' D. 50% , i- !. QUESTION:

QlD: 0138 Rev: 000 Point: 1.00 All of the following components / subsystems can be discharged into the Quench Tank EXCEPT: I A. RCP Vapor Seal Leakoff.

I B. PressurizerVent.

C. RCP Control Bleedoff relief, a l D. Reactor Vessel Head Vent.

4-i $

i i Page 30

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._ _ _ _ _ __. _. _ _ _.~._... _._ _. _ _ _.__... _ _ _ _. __ _ _._._ _. _ . ! l ' ] ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0141 Rev: 000 Point: 1.00 While performing a natural circulaten cooldown following a Steam Generator Tube Rupture, pressurizer level is varying by large amounts inconsistent with the cooldown and depressurization of l the RCS. Which one of the following statements correctly describes the cause of wide deviations from the expected pressurizer level? A. Pressurizer level instrument reference leg flashing B. Automatic operation of charging pumps.

C. CeiG.cti,en of the RCS dunng the cool down - D. Voiding in the Reactor Vessel Head area.

.

i QUESTION:

QlD: 0143 Rev: 000 Point: 1.00 Assuming ANO-2 was operstmg at 100% power initially and given the following data:

  • SG "A" Pressure 700 psia
  • SG "B" Pressure 750 psia
  • SG "A" Level 15%
  • SG "B" Level 24 %
  • Cold Leg"A" Temperature 503F
  • Cold Leg "B" Temperatures 510F
  • ContainmentTemperature 200F
  • Containment Pressure 17.3 psia Which one (1) of the following components should NOT have received an ESFAS signal to actuate?

(Assume Reactor tnpped on Steam Generator Low Pressure) A. Emergency Foodwater Pump Turbine Steam Supply valve (2CV-0340-2).

B. Main Feedwater Block valve (2CV-1024-1).

. C. Service Water To CCW Hx Supply valve (2CV-1530-1).

D. Main Steam Isolation valve (2CV-10101).

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] ANO UNIT 2 - INITIAL RO EXAM ! QUESTION:

QlD: 0144 Rev: 000 Point: 1.00 The reactor is entical at 10E-4% power when charging pump suction inadvertently swaps from the VCT to the RWT. This occurs for approximately 10 minutes, then is stopped by the operators.

! Which one (1) of the following descnbos the comparative effect that this will have on letdown flow? A. It will decrease the most at BOL.

B. It will decrease the most at EOL C. It willincrease the most at BOL D. It will not be significantly affected ~ l QUESTION:

QlD: 0146 Rev: 000 Point: 1.00 With a Control Element Assembly misaligt ed less then 19 inches, Technical Specifications allow the operator one hour to take corrective acbon. The one hour time limit will.

i A. proclade a decrease of available shutdown margin.

B. minimize the effects of Xenon redistribution.

. C. preclude large effects on power distribution.

' D. preserve assumed worth of an ejected rod.

QUESTION:

QlD: 0149 Rev: 001 Point: 1.00 Verification of Containment Spray System operation is required when Refueling Water Tank level decreases to < 8% during a Loss of Coolant Accident in order to: A. provide long term post-acadent core cooling.

B. remove iodine from the containment atmosphere.

C. provide mixing of the sodium hydroxide.

D. provide flow to reduce electrolytic corrosion.

O Page 32 -.-_

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Q ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0150 Rev: 000 Point: 1.00 Which one (1) of the following reactor trips pim against an uncontrolled CEA Wdhdrawal from a subcritical condition? (Assume no operator action is taken) A. Hi Linear Power.

B. Lo DNBR.

" C. Hi LPD.

D.- Hi Log Power.

QUESTION: 72' QlD: 0178 Rev: 000 Point: 1.00 Given the following plant conditions:

  • Mode 6
  • Fuel movementin progress.

f

  • 2RITS-8905 (Elevation 354' Radiation Monitor by Equipment Hatch fails low.

- Which of the following schons should be performed? A. Suspend all fuel movement.

B. Evacuate the Containment Building C. Verify portable radiation monitor on Main Refueling Bridge is operable.

D. Verify 2RITS-8909 (Personnel Hatch Rad Monitor) is operable O ' Page 33 . _.

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i O ANO UNIT 2 - INITIAL RO EXAM v

- QUESTION: 73' QlD: 0153 Rev: 000 Point: 1.00 Following the determination that a CEA in Shutdown Bank "A" is misahoned by four (4) inches and mechanically bound, shutdown margin is calculated to be 4.9%. Which one (1) of the folkmng actions should be taken? - , A. Continue plant operation without restriction B. Reduce power to less than or equal to 81%. C. Start a plant shutdown and be in Mode 3 within 8 hours.

. '

D. Initiate Emergency Boration.

, QUESTION:

QlD: 0157 Rev: 000 Point: 1.00 The unit is at 50% power dunng a ramp to full power, when a reactor and turbine trip occur. Which - I one (1) of the followmg statements describes the immediate response of the atmospheric dump valves (ADVs) and Bypass Control valves? O , , - A.- ADVs receive a " quick-open" signal and bypass valves modulate to control main steam J

pressure.

j , ~i B. Bypass valves and one ADV receive " quick open" signal then modulate to control main steam pressure.

l C. ADVs modulate to control RCS temperature and bypass valves roesive a " quick-open" signal.

D. Reactor trip blocks all " quick open" signals then ADVs and bypass valves receive modulate

signal from the master controller to control RCS temperature.

!. }

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_. _ _. _.. _. _ _ _... _. _.. _. - _ _. _. _ _ _. _ _ _. _.. _ _ _ _ _ _ _.. _. _ _ _ _. _. _ _ _ _... _ _ _ _ _ _ _ ' Q ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0158 Rev: 000 Point: 1.00 When a manual reactor trip is attempted and the reactor does NOT trip after depressing the manual trip pushbuttons,2202.001, Standard Post Trip Actions procedure contingency schons require the power supply to the CEDM MG Sets to be de-energized. Which of the following will accomplish this schon from the control room? A. Open 480V Load Center 283 and 2B4 feeder breakers (2B-312 and 28-412).

B. Open 480V Load Center 287 and 2B8 feeder breakers (28-712 and 2B-812).

C. Open 480V MCC 2B31 and 2B41 feeder breakers (2B-321 and 28-421) D. Open 480V MCC 2B71 and 2B81 feeder breakers (2B-732 and 2B-823).

. QUESTION:

QlD: 0159 Rev: 001 Point: 1.00 Which of the following pressurizer heater banks are powered by 480V Vital Power? A. Proportional heaters banks #1 and #2, backup heaters #1 and #2.

B. Backup heaters banks #1, #2, #3, #4.

C. Proportional heater banks #1 and #2.

D. Backup heaters banks #1 and #2.

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. -.... -...-. .. _. - -. .. _ -.. -. -. ... - _ - _. _.. -.. -. - h Q ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0160 Rev: 000 Point: 1.00 Given the follomng plant conditions:

  • Plant shutdown and cooldown just completed from 100% power.
  • Shutdown Cooling has JUST been established.
  • A Loss of Instrument Air occurs.

Which of the following desenbos the Shutdown Cdoleng System response? ' A. All SDC flow is lost.

B. SDC heat removal is lost.

C. SDC flow is degraded.

D.' No sigrwficant effect.

QUESTION:

QlD: 0161 Rev: 000 Point: 1.00

Given the follomng conditions:

  • A small break Loss of Coolant Accident is in progress.
  • RCS pressure is 1600 psia.
  • Containment pmssure is 16 psia and slowly increasing.

'

  • Containment Hi Range Radiation Monitors raad 13 R/Hr and increasing.
  • No operator actions have been performed Which one (1) of the following actions should be performed?

' A. Isolate letdown B. Manually actuate SIAS.

C. Manually actuate CIAS.

D. Manually actuate CSAS.

, i O Page 36 ._ _ _.

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_ . . _ _ _. _ _ _ _ _ _ _. _ _. _ _. _ _ _ _ _. _... _.. _. _ _ _. _ _ _. O ANO UNIT 2 - INITIAL RO EXAM O QUESTION:

QlD: 0162 Rev: 000 Point: 1.00 Why does OP 2202.006, Loss of Foodwater require the operators to feed the Steam Generators , using the EFW system flow at less than 150 gpm for five minutes when narrow range level is less than 48%7 A. To minimize the amount of shrinig to the steam generator level.

B. To minimize the possibility of water hammer in the emergency feedwater system.

C. To minimize the possibility of damage to the steam generator feed ring.

D. To ensure the most reliable source of feedwater is used to restore steam generator level.

QUESTION:

QlD: 0164 Rev: 000 Point: 1.00 Which is the maximum temperature expected as measured downstream of a leaking Pressurizer Code Safety valve on 2T!-4694, Quench Tank Temperature indicated on 20047 A. 212 degrees F.

B. 300 degrees F.

' C. 375 degrees F.

' D. 650 degrees F.

, 't

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QlD: 0165 Rev: 001 Point: 1.00 Given the kent.,g conditions:

  • Unit is operating at 100% power..
  • Current reactor coolant system lenke is as follows:
  • Pressure boundary leakage - 0.0 &pm
  • Identified valve packing leakage - 4.6 gpm
  • Leakage to "D" Steam Generator- 0.3 gpm
  • Other Leakage - 0.7 gpm Which one of the followmg is true for LCO 3.4.6.2, Reactor Coolant System Operational leakage?

A. Met, based on totalleakage.

B. Not met, based on unidentified leakage.

t C. Met, based on total identified leakage.

D. Not met, based on pnmary-to-secondary leakage.

~O ' QUESTION:

QlD: 0168 Rev: 000 Point: 1.00 .. ! Which of the following desenbos the effect of a loss of green DC Bus,2D26 will have on the j operation of Emergency Feedwater Pump 2P7A? A. All 2P7A dischage valves to both Steam generators will fail open.

B. All 2P7A chscharge valves to both Steam generators will fait closed.

' , C. 2P7A will overspeed D. 2P7A will go to mtoimum speed ) . Page 38 .. . -.-. - . .. ... _ - --

-_ - _ - - - . -. -. _ -. . - - - - -. -. -.. - - - -.. - Q ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0169 Rev: 000 Point: 1.00 The following plant condtons exist '

  • CCW Pump 2P33A is supplying Loop 1 CCW.
  • CCW Pump 2P338 is suf+lilr.g Loop 11 CCW.
  • CCW Pump 2P33C is tagged out for maintenance.
  • 2K12-F6, PUMP 2P33A/B/C LOCKED, is actuated.

Which of the following desenbes what would happen to the CCW Loop Crossover valves if 2PO3A Tripped? A. Loop 1 Crossover valves automatically open and Loop ll Crossover valves automatically close.

B. Loop 1 Crossover valves automatically open and Loop 11 Crossover valves stay open so that 2P33B can supply both loops.

C. The Control Board operator will have to manually open the Loop 1 Crossover valves and throttle closed Loop ll Crossover valves to balance loop flows.

D. The Loop I and Loop ll Crossover valves will remain in the pos4on they were in prior to , 2P33A trip.

, QUESTION:

QlD: 0170 Rev: 000 Point: 1.00 ' What would the initial pnmary plant temperature and pressure response be for a 100% turbine load rejection? A. RCS temperature and pressure constant due to SDBCS valves opening to controlling SG pressure B. RCS temperature snd pressure constant due to main spray valves opening.

C. RCS temperature and pressure increasing even with SDBCS valves and main spray valves opening.

D. RCS temperature and pressure decreasing due to SDBCS valves and main spray valves opening.

,

4

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- -. _ __._. _. _ _ _ _ _ _. _ _ _ _.. _ _.. _. _.. _.... _ _ _ _.. _ _. _.. _ _ _ _. _.... _ .- ' '] ANO UNIT 2 - INITIAL RO EXAM . QUESTION:

Q1D: 0171 Rev: 000 Point: 1.00 Why ere Service Water Pump 2P48 Disconnect Sutches on 2A5 interlocked such that only one l disconnect and its associated breaker can be closed at the same time? A. To prevent exceedmg the disconnect switch current lemets.

B. To provide ESFAS input to 2P48 trip circuitry.

C. To provide train separation of 2P48 power supplies.

L D. To prevent simultaneous operatum of cross-over valves.

QUESTION: 86. QlD: 0173 Rev: 001 Point: 1.00-l Given the following plant conditions:

  • Full power Mode 1.
  • Circ Water Pump 2P3A trips.

Which of the following best descnbos why turbine load must be reduced for the given condations? A. Prevent condenser overpressurizatum.

' B. Prevent cavitation of Circ Water Pump 2P38.

C. Prevent exceeding 40F cire water delta T across condensors.

D. Prevent exhaust hood temperature from exceeding 200F.

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! Q ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0174 Rev: 000 Point: 1.00 , j The 90% limit switch on the MSIVs (2CV-1010A and 2CV-1060A) causes the:

A. Exercise valve (2HS-1011 and 2HS-1061) green light to illumirate.

E. Exercise valve (s) to open to prevent inadvertent MSIV closure.

i " C. Intermediate position irxiscation on the MSIV hand-switches (2HS-1010-1 and 2HS-1060-2).

I D. MSIV bypass valve to close when opening the MSIV.

i t QUESTION:

'QlD: 0175 Rev: 000 Point: 1.00 !

What effect would a decreasing Spent Fuel Pool Level from Elevation 401' 6" to Elevation 401' 1" l , have on the operation of the Spent Fuel System or the working area adjacent to the Spent Fuel Pool? ' ) !, - A. Complete loss of NPSH to SFP cooling pumps.

i B. Humidity levels will increase to greater than Tech Spec limit.

.. ! C. Boron concentration will decrease.

l D. Radiation levels willincrease.

t . !

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Q ANO UNIT 2 - lNITIAL RO EXAM _ QUESTION:

QlD: 0176 Rev: 000 Point: 1.00 Given the following plant conditions:

  • Mode 5
  • Equipment hatch is to be opened Which of the following schons should be used to property align the Containment Purge System?

A. Place Purge Supply Fan,2VSF-2, in HAND then secure Purge Exhaust Fan,2VEF-15.

B. Place Purge Exhaust Fan,2VEF-15, in HAND then secure Purge Supply Fan,2VSF-2.

C. Manually close one Purge Exhaust Damper, then secure Purge Exhaust Fan,2VEF-15.

D. Manually close one Purge Supply Damper, then secure Purge Supply Fan,2VSF-2.

QUESTION:

QlD: 0177 Rev: 000 Point: 1.00 Which of the following desenbos why full power Containment Pressure is maintained betweran 11.9 psia and 14.2 psia? A. Prevent exceeding design limits on Containment for a large break LOCA.

B. Prevent exceeding design limits on Containment for an Excessive Steam Demand event.

C. Ensure a cushion exists for a Loss of Service Water.

D. Ensure a cushion exists for a Loss of Chilled Water.

O Page 42 -

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QlD: 0151 Rev: 000 Point: 1.00 , t Given the following condshons: I

  • Unit instially at 100% power.
  • CEA 46 (Regulahng Group 6 CEA) drops fully into the core.
  • Crew lowers main turbine load to match Teve with Tref.
  • Power is reduced by 24% over the next hour.
  • After stabilizabon at 76% power, dilution is used to maintain temperature constant while repairs are made.

Which one (1) of the followng is correct concerning shutdown margin? A. Adequate margin existed throughout the event.

B. Inadequate margin exists because of the dilution.

C. Inadequate margin exists because CEA 46 is unavailable for inserbon.

D. Adequate margin exists because power was not lowered to less than 30%. O QUESTION:

QlD: 0179 Rev: 000 Point: 1.00 Given the EE-2g plant condstions:

  • FullPowerOperations
  • Condensate Pumps 2P2A,2P2B and 2P2C running
  • Condensate Pump 2P2A trips Which of the following automabc schons should occur?

A. Heater Drain Pump 2P8A will auto start.

B. Condensate Pump 2P2D will auto start.

C. Recirculabon valve for Condensate Pump 2P2B will auto close.

D. Main Feed Water Pump 2P1 A will trip on low su%on flow.

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. . -... - -.... - -.. -. _ -.. -... _. - -.. - -.. - _ .. - - - -. -. - _. - _ _ -. _. -. Q ANO UNIT 2 - INITIAL RO EXAM QUESTION: g3 QlD: 0180 Rev: 000 Point: 1.00 Given the following plant condetsons:

  • Mode 5
  • Pressurizer Manway removed
  • LPSI Pump 2P60A through Shutdown Cooling Heat Exchanger 2E35A
  • High alarm actuated on Radiabon Monitor 2RITS-1453 (SW From SDN Ht Exch 2E-35A)

Which of the following actions would be required? A. Secure 2P60A, close SDC RCS isolation MOVs and start RCPs for RCS heat removal via SGs.

B. Secure 2P60A, close SDC RCS isolation MOVs and steam both SGs in Natural Circulation for , l heat removal.

i l C. Align SW and RCS to 2E35B and isolate SW and RCS to 2E35A.

D. Start Contaenment Spray Pump 2P358 and align to 2E35B and secure 2P60A and isolate SW and RCS to 2E35A.

O QUESTION:

QlD: 0181 Rev: 000 Point: 1.00 Given the following conditions:

  • Mode 3 post trip from full power.

-

  • EFAS signal present with EFW Pumps 2P7A and 2P78 running.
  • 2P75 feeding SG's via 2CV-0762 (AFW to EFW).

Which of the following desenbos why flow should be limited to 1200 gpm for the given conditions?

' l A. Limit flow velocstles.

i B. Prevent binding of EFW block valves.

' C. Prevent thermal shock to SGs.

D. Prevent AFW pump runout.

i

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_.___._ _._.__ _ __ _ _ _ Q ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0182 Rev: 000 Point: 1.00 Which of the following indications will be observed on a Loss of Inverter 2Y-11 ( Red )? A. Half Leg Trip.

B. ReactorTrip.

C. All Red ESFAS components will actuate.

D. NO Red ESFAS comp'wmts will actuate.

QUESTION:

QlD: 0183 Rev: 000 Point: 1.00 Given the followng conditions: , l

i

  • Mode 2 operations.
  • Reactor Power 5E-5% and stable.
  • Annunciator 2K04-G9, MSSV Valve Open actuates and will not clear.

O

  • No operator schons taken.

Which of the followmg conditions will result in the highest power for the condsbons given above? A. Initial CEA height.

B. Initial RCS Tave.

C. BOL Core.

D. EOL Core.

i.

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. _ _. _... _ _ _ _ _ _- _ _ _. _. ~ _.. _ _. _ _. _. _... _. _ _ _ _. _ _ _ _. _ _ _ _ _ _. _. _.. < Q ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QID: 0188 Rev: 000 Point: 1.00 Given the following condsbons:

  • Reactor has tripped from full power.
  • 110 gpm SGTR.
  • 60 gpm LOCA.
  • RCS cooldown and depressurization in progress.
  • RCS pressure 1200 psia.
  • RVLMS level 4 indicates wet.
  • RCS Thot 530F Which of the following actions should be performed for the above condsbons?

A. Stop depressurization until RVLMS level 1 indicates wet.

B. Stop cooldown.

C. Secure one (1) RCP in each loop.

D. Open Reactor Vessel High Point vents to Containment Atmosphere.

, O ' QUESTION:

QlD: 0190 Rev: 000 Point: 1.00 Which of the following desenbos why RCS pressure is mamtained within 100 psia of RCP NPSH during a primary to secondary leak of 20 gpm?

A. Ensures margin to saturation is greater than 50F.

B. To minimize RCS Break flow.

I C. Ensures sealinjection can be maintained.

D. Prevents lifting primary code safeties.

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' \\ ' ANO UNIT 2 - INITIAL RO EXAM QUESTION:

QlD: 0191 Rev: 001 Point: 1.00 Which of the f*;iig describes the status of Pressurizer Pressure Fisher-Porter controller,2PIC- , 4626A after a temporary loss of power? A. Automatic mode of operation.

' B. Manual mode of operation.

C. Minimum Output on controllar.

D. Maximum Output on corfsoller, i QUESTION: 100 QlD: 0194 Rev: O Point: 1.00 ' While performing Shift Tumover Checklist Modes 1-4 (1015.0168), you find no power indicated for

Control Room Emergency Filtration Fan (2VSF-9). Which of the followmg schons would be the most ' =f-s-xi'i for this situabon? ' A. Leave the 2VSF-9 operatnisty status on the checklist blank until you complete the remainder of ' ,, the checklist.

  • B. Both the Unit 1 and Unit 2 Shift Superintendent should be immediately nobfied.

C. Place the Control Room Ventilabon in the Emergency Mode by closing supply and exhaust dampers and starting 2VUC-27A or 2VUC-278.

D. Designate 2VSF-9 operability not applicable (N/A) on check list if Unit i VSF-9 is operable because only one fan can be operated at a time.

i

Pa08 47 ' - _ ..

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- ANO UV S. -INITIAL RO EXAM ANSWER KEY QUESTIONI1 QlD: 0069 Point: 1.00 C.~ Main Foodwater and Emergency Feedwater to "A" Steam Generator is secured . QUESTION: 2 QlD: 0007 Point: 1.00 B. Operate the handwhool ppiMT * 'i one (1) tum toward the closed direction and then back to a fully open position.

QUESTION: 3 QlD: 0005 Point: 1.00 A. Reamor power will rise, Teve will be unaffected QUESTION: 4 QlD: 0004 Point: 1.00 B. Annunciator 2K12-A1, " LETDOWN RADIATION Hl4.0".

QUESTION: 5 QlD: 0011 Point: 1.00 D. Component Cooling Water Flow is lost for over 10 minutes.

QUESTION: 6 QlD: 0015 Point: 1.00 C. Open Emergency Borate valve (2CV-4916-2) and start BAM Pump.

QUESTION: 7 QlD: 0016 Point: 1.00 D. Manually trip the Turbine at control panel 2C01.

QUESTION: 8 QlD: 0018 Point: 1.00 C. Stop one (1) RCP in each RCS loop.

, QUESTION: 9 QlD: 0021 Point: 1.00 C. Radiation Levels.

QUESTION: 10 QlD: 0023 Point: 1.00 I ~ ' A. RCS boron concentration is 2250 ppm.

QUESTION: 11 QlD: 0027 Point: 1.00 A. Level is NOT an accurate indicanon of inventory. RCS voiding may result in a rapidly increasing pressurizerlevel.

QUESTION: 12 QlD: 0028 Point: 1.00 C. Trip the turbine before exceedire 7 inches Hg absolute.

QUESTION: 13 QlD: 0030 Point: 1.00 C. Courd rates would increase due to less moderation within the core causing more fast neutron , .locka0s.

QUESTION: 14 QlD: 0031 Point: 1.00 D. Steamline safety valves are removed for bench testing of lift setpoint.

QUESTION: 15 QlD: 0036 Point: 1.00

D. Apply to the stop immediately following the CAUTION.

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\\n ANO UNIT 2 -INITIAL RO EXAM ANSWER KEY ') QUESTION: 16 QlD: 0037 Point: 1.00 C. Connecting cables from 480V Motor Control Center (MCC) to a temporary power panel for outaa rnaintenance support.

QUESTION: 17 QlD: 0038 Point: 1.00 B. Immediately notify the Shift Superintendent.

QUESTION: 18 QlD: 0043 Point: 1.00 C. 1440.

QUESTION: 19 QlD: 0044 Point: 1.00 A.1 hour.

QUESTION: 20 QlD: 0045 Point: 1.00 C. Perfom every 15 minutes.

QUESTION: 21 QlD: 0046 Point: 1.00 D. Installlocking pins for MSIVs.

QUESTION: 22 QlD: 0049 Point: 1.00 D. RCS Tave.

QUESTION: 23 QlD: 0052 Point: 1.00 O B. Indicated level will be HIGHER than actual level because the reference leg fluid density (_/ decreases.

QUESTION: 24 QlD: 0053 Point: 1.00 , A. 2T2A.

QUESTION: 25 QlD: 0059 Point: 1.00 A. Suction pressure.

QUESTION: 26 QlD: 0060 Point: 1.00 l D. A rupture disc will unisolate a relief valve and relieve pressure to the Waste Gas Surge Tank.

QUESTION: 27 QlD: 0061 Point: 1.00 C. 2RITS-8916,404 Spent Fuel Pool General Area monitor.

QUESTION: 28 QlD: 0062 Point: 1.00 C. Placing the selector switch in CHECK SOURCE, observing an increasing meter reading and valve isolation.

QUESTION: 29 QlD: 0063 Point: 1.00 B. Indication of core coolant outlet temperature.

QUESTION: 30 QlD: 0066 Point: 1.00 A. A spent fuel assembly is damaged while being withdrawn from the core.

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? n ANO UNIT 2 -INITIAL RO EXAM ANSWER KEY ! V QUESTION: 31 QlD: 0087 Point: 1.00 D.120 minutes.

' QUESTION: 32 QlD: 0002 Point: 1.00 l A. Teve willincrease.

. QUESTION: 33 QlD: 0071 Point: 1.00 B. To prevent steam formation in the Reactor Vessel head fmm pressurtzing the RCS, leading to

core uncovery.

i QUESTION: 34 QlD: 0072 Point: 1.00 A. Start 'an altemate charging pump after verifying its suction path.

QUESTION: 35 QlD: 0073 Point: 1.00 l B. Pressurizer Level 35% and dropping slowly.

!

QUESTION: 36 QlD: 0077 Point: 1.00 l.

. A. Safety Parameter Display System (SPDS) poird P4624-2.

QUESTION: 37 QlD: 0078 Point: 1.00 . i A. Making preliminary reportability verification.

! QUESTION: 38 QlD: 0079 Point: 1.00 ' O A. Breakers 1 and 5.

QUESTION: 39 QlD: 0081 Point: 1.00 ' B. Maintain subcooling margin between 30F and 200F.

i QUESTION: 40 QlD: 0089 Point: 1.00 i

D. Uponder is completely horizontal.

, ' QUESTION: 41 QlD: 0090 Point: 1.00 . C. Accelerometers.

QUESTION: 42 QlD: 0093 Point: 1.00 ' B. Reactive load increases and KW increases.

,

QUESTION: 43 QlD: 0094 Point: 1.00 l A. Breakers will remain in their"as is" condition and operation would only be possible by loca! ' manual means.

QUESTION: 44 QlD: 0095 Point: 1.00 . B. Im esier input is auctioneered between the rectifur output and a DC Battery Bus supply.

QUESTION: 45 QlD: 0097 Point: 1.00 D. Roset the Steam Generator low pressure trip setpoints.

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- - - -. n ANO UNIT 2 -INITIAL RO EXA'd ANSWER KEY QUESTION: 46 QlD: 0099 Point: 1.00 B. By observing a trip light without the associated pretrip l%ht.

QUESTION: 47 QlD: 0101 Point: 1.00 C. SIAS to ensure the valve can be opened QUESTION: 48 OlD: 0102 Point: 1.00 3. Prevent steam or non-condensables from interfering with natural circulation.

l-QUESTION: 49 QlD: 0104 Point: 1.00 D. SG "A" Level = 5% NR & Press = 500 psia SG "B" Level = 10% NR & Press = 370 psia.

QUESTION: 50 QlD: 0105 Point: 1.00 D. Main Foodwater Leak in Containment.

QUESTION: 51 QlD: 0106 Point: 1.00 A. Average Core Exit Thermocouples.

QUESTION: 52 QlD: 0110 Point: 1.00 D. CSAS QUESTION: 53 QlD: 0114 Point: 1.00 D. To limit core uplift.

Q) f~ QUESTION: 54 QlD: 0115 Point: 1.00 C. Upper seal.

QUESTION: 55 QlD: 0116 Point: 1.00 A. When the shutdown banks are being withdrawn.

QUESTION: 56 QlD: 0118 Point: 1.00 C.100 inches.

QUESTION: 57 QlD: 0121 Point: 1.00 D. Suspend core alterations until the inopx*Ne channel is retumed to operable status.

QUESTION: 58 QlDT0124 Point: 1.00 D. a person working on safety-related system or component.

QUESTION: 59 QlD: 0125 Point: 1.00 B. 5 hours.

QUESTION: 60 QlD: 0127 Point: 1.00 D. High Linear Power, High Local Power Density and Low DNBR trips and pretrips.

QUESTION: 61 QlD: 0129 Point: 1.00 C. Backup charging pump gets a stop signal, heaters energize, letdown flow increases.

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^" " " ' ' ' ' ' " ' ' ' ^ ' " " * ^ " ^ " * * * " " ' ' C) QUESTION. 62 QlD: 0130 Point: 1.00 . D. Override and restore CCW Flow to RCPs.

QUESTION: 63 QlD: 0133 Point: 1.00 A. 2D23 QUESTION: 64 QlD: 0135 Point: 1.00 D. 50% QUESTION: 65 QlD: 0138 Point: 1.00 A. RCP Vapor Seal Leakoff.

QUESTION: 66 QlD: 0141 Point: 1.00 D. Voiding in the Reactor Vessel Head area.

QUESTION: 67 QlD: 0143 Point: 1.00 A. Emergency Feedwater Pump Turbine Steam Supply valve (2CV-0340-2).

QUESTION: 68-QlD: 0144 Point: 1.00 D. It will not be significantly affected.

QUESTION: 69 QlD: 0146 Point: 1.00 B. minimize the effeds of Xenon redistribution.

l QUESTION: 70 QlD: 0149 Point: 1.00 s A. provide long term post-accident core cooling l QUESTION: 71 QlD: 0150 Point: 1.00 D. Hi Log Power.

QUESTION: 72 QlD: 0178 Point: 1.00 C. Verify portable radiation monitor on Main Refueling Bridge is operable QUESTION: 73 QlD: 0153 Point: 1.00 l D. Initiate Emergency Boration.

QUESTION: 74 QlD: 0157 Point: 1.00 8. Bypass valves and one ADV receive ' quick open" then modulate to control main steam pressure.

QUESTION: 75 QlD: 0158 Point: 1.00 B. Open 480V Load Center 287 and 288 feeder breakers (28-712 and 2B-812).

, QUESTION: 76 QlD: 0159 Point: 1.00 C. Proportional heater banks #1 a.wi #2.

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. - _ _ _.. _ _ _... _ _ _. _ _ _. _ _ _. _ _. _ _..... _ _ _. _. _. _ _ _ _. , ! I ANO UNIT 2 -INITIAL RO EXAM ANSWER KEY l-QUESTION: 77 QlD: 0160 Point: 1.00

. B. SDC heat removal is lost.

QUESTION: 78 QlD: 0161 Point: 1.00 . C. Manually actuate CIAS.

j

QUESTION: 79 QlD: 0162 Point: 1.00 ' C. To minimize the panaMy of damage to the steam generator feed ring.

, QUESTION: 80 QlD: 0164 Point: 1.00 B. 300 degrees F.

) l l QUESTION: 81 QlD: 0165 Point: 1.0tr D. Not met, based on primary-to-secondary leakage.

l QUESTION: 82 OID:- 0168 Point: 1.00 l C. 2P7A will overspeed.

QUESTION: 83 QlD: Ot69 Point: 1.00 D. The Loop I and Loop 11 Crossover valves will remain in the position they were in prior to 2P33A trip.

QUESTION: 84 QlD: 0170 Point: 1.00 - q C. RCS temperature and pressure incr - ' a even with SDBCS valves and main sprey valves ,( opening.

QUESTION: 85-QlD: 0171 Point: 1.00 C. To provide train separation of 2P48 power supplies.

QUESTION: 86 QlD: 0173 Point: 1.00 D. Prevent exhaust hood teciperature from exceedeng 200F.

QUESTION: 87 QlD: 0174 Point: 1.00 A. Exercise valve (2HS-1011 and 2HS-1061) green light to illuminale.

QUESTION: 88 QlD: 0175 Point: 1.00 l D. Radiation levels willincrease.

QUESTION: 89 QlD: 0176 Point: 1.00 ~ 8. Place Purge Exhaust Fan,2VEF-15, in HAND then secwe Purge Supply Fan,2VSF-2.

QUESTION: 90 QlD: 0177 Point: 1.00 D. Ensure a cushion exists for a Loss of Chilled Water.

QUESTION: 91 Ql0: 0151 Point: 1.00 A. Adequate margin existed throughout the event.

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. ._ . _ _. .. . l i ANO UNIT 2 -INITIAL RO EXAM ANSWER KEY , O,o ' QUESTION: 92 QlD: 0179 Point: 1.00 B. Condensate Pump 2P2D will auto start.

QUESTION: 93 QlD: 0180 Point: 1.00 C. Align SW and RCS to 2E358 and isolate SW and RCS to 2E35A.

QUESTION: 94 QlD: 0181 Point: 1.00 A. Limit flow velocities.

QUESTION: 95 QlD: 0182 Point: 1.00 A. Half Leg Trip.

QUESTION: 98 QlD: 0183 Point: 1.00 D. EOL Core.

i ' QUESTION: 97 QlD: 0188 Point: 1.00 A. Stop depressurization until RVLMS level 1 indicates wet.

QUESTION: 98 QlD: 0190 Point: 1.00 B. To minimize RCS Break flow.

QUESTION: 99 QlD: 0191 Point: 1.00 i B. Manual mode of operation.

- QUESTION: 100 QlD: 0194 Point: 1.00 B. Both the Unit 1 and Unit 2 Shift Supedntendent should be immediately notified.

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. _ _. _ _. _ _.. _. _ _ _ _ _. _. _ _. _. _.. _ _ _ _ _ _ _ _ _. _. _ _. _. F I O ' U.S. Nuclear Regulatory Commission Sito-Specific Written Examination App 5cantinformation Name: Region: IV Date: Fachty/ Unit ANO-UNIT 2 License Level: SRO ReactorType: CE l StartTime: Finish Time: l Instructions i Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. The passing grade requires a Anal grade of atleast 80.00 percent Examination papers ' will be collected four hours aner the examination starts.

App 5 cant Certification All work done on this examination is my own. I have nedher given nor received aid.

] Appbcanfs Signature -- Results ExaminationValue 100 Points Apphcanfs Score Points Appbcanfs Grade Percent O l . - - - . - . -- m- - -- "' 'Y '

- -.... -.. -.. -.. -. -. -. -.... - - - . -.. -. - _. -. _ - - -... -. -.. . ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0002 Rev: 000 Point: 1.00 The plant is at 75% power when a new Letdown Dominerakzer is placed in service. Which one of the following will occur if the boric acid saturation of this dominershzer is incomplete? A. Teve willincrease.

j B. Teve will decrease.

C. Lithium concentratum will go up.

D. Letdown flowrote will decrease.

QUESTION:

QlD: 0003 Rev: 000 Point: 1.00 The following sequence of events occurs:

  • A Safety injechon Actuabon Signal (SIAS) has started all ECCS pumps.
  • The diesels are running normally.
  • 5 minutes after the SIAS, offsite power is lost.

y WHICH ONE (1) of the following desenbos the expected response of the ECCS pumps to the Loss of Offsite Power? A. All ECCS pumps restart when their train's EDG output breaker closes.

j B. The LOCA Sequencer will' restart the ECCS Pumps.

\\ ' C. ECCS pumps will restart in time delayed sequence.

D. The SIAS will have to be reset and the pumps started by operator schon.

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. _. _ _ _. _ _. _ _ _ _. -.. _ _.. _ _. _. _. _ _. _ _ _ _ _.. _ _. _ _ _ _ _ _ _. _ _ _ _... _ _ _ Q ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0004 Rev: 000 Point: 1.00 l Which one of the following alarms requires entry into OP 2203.020 (High Reactor Coolant Activity)? A. Annunciator 2K11-A10 "SEC SYS RADIATION Hi".

B. Annunciator 2K12-A1, " LETDOWN RADIATION Hl/LO".

I C. Annunciator 2K11-C10. " PROC LIQUID RADIATION Hl/LO".

D. Annunciator 2K10-A6, "CNTMT RADIATION Hi".

QUESTi M

Q1D: 0005 Rev: 001 Point: 1.00 A plant startup is in progress and the following conditions exist:

  • The reactor is entical at SE-5% power.
  • Tave is a: 545 degrees F.
  • A rod control failure causes the selected control bank of rods to step out five (5) steps before being stopped by the operator.

'

  • No reactor trip occurs.

Which one of the following describes the effect that this event will have on reactor pyrameters over the next minute?

A. Reactor Power will rise, Tave will be unaffected.

B. Reactor Power and Teve will both rise.

. C. Reactor Power will be unaffected, Tave will rise.

' D. Reactor Power will rise, the response of Tave will depend upon core life.

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, . ANO UNIT 2 - SRO EXAM . QUESTION:

QlD: 0010 Rev: 000 Point: 1.00

j Which one (1) of the followJng states the basis for maintaining at least one OPERABLE containment isolation valve in each penetration in MODES 1 through 47 A. Ensures release of radioactive materials is restncted to specified pathways.

! B. Limits total containment leakage volume so as to NOT exceed the value assumed in the safety analysis.

>

C. Ensure containment atmosphere is isolated from the outside environment in the event of

radioactive release or pressurization.

! j D. Provides assurance the containment atmosphere is isolated within the time frames ! assumed in the safety analysis.

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i t, QUESTION:

QlD: 0011 Rev: 000 Point: 1.00 , } Which one (1) of the following condations requires the affected Reactor Coolant Pump (RCP) to be l tripped? !

A. Seal Bleedoff Temperature reaches 180 degrees F.

l - B. Motor Winding Temperature reaches 180 degrees F.

! C. Vapor Seal Pressure reaches 750 psia.

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D. Component Cooling Water Flow is lost for over 10 minutes.

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Q ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0012 Rev: 000 punt: 1.00 While performing a reactor start-up, enticality is achieved with Group 5 @ 120 inches withdrawn.

Which one of the following schons must be taken as a result of this? A. Emergency borate until adequate shutdown margin is demonstrated.

B. Stop all further outward rod mobon, begin a normal boration and recalculate ECP.

C. Stop all further outward rod motion and contact Reactor Engmeering for support.

D. Fully insert the control and shutdown banks and recalculate the ECP.

QUESTION:

QlD: 0018 Rev: 000 Point: 1.00 Chen the following:

  • The reactor has tripped from 100% power.
  • Pressurizer pressure is 1275 psia and DECREASING.
  • Pressurizerlevelis 3%.
  • CETS indicate 450 degrees F.
  • All required ESFAS Actuabon have actuated.

Which one (1) of the felic25 is the MINIMUM operator action for the above conditions per 2202.001, Standard Post Trip Actions? A. De-energize the pressurizer backup heaters and reduce auxiliary spray to less than 165 gpm.

B. Secure pressurizer spray and energize ALL heaters.

C. Stop one (1) RCP in each RCS loop.

D. Stop ALL RCPs.

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QlD: 0020 Rev: 000 Point: 1.00 ! Given the following plant conditions:

  • A small break LOCA is in progress and SIAS has actuated.

,

  • All systems and automatic schons are operating as expected.

Which one (1) of the followng is the reason for maintainmg a secondary heat sink? A. To ensure removal of RCS heat since two (2) RCPs are still running.

B. RCS pressure may remain so high that cooling from the injechon flow alone is inadequate.

C. Reflux boiling is the pnmary means of heat removal prior to voidmg in the hot legs.

D. To provide an altamative method of RCS pressure control.

QUESTION:

QlD: 0021 Rev: 000 Point: 1.00 Which one (1) of the following is best to determine the Steam Generator (SG) to be isolated when a tube rupture occurs in BOTH Steam Generators? , A. Water Levels.

B. Feedwater Flow Rates.

, C. Radiation Levels.

D. Boron Concentrations.

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- -. -. _. - - -.....~. - - -. - - - __ _ _ - - ] ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0025 Rev: 000 Point: 1.00 Given the followmg:

  • A Loss of Offsite Power has occurred.
  • Both EDGs started and energized their respective 4160V ESF Buses.
  • Breaker 2A301,480V ESF Bus 285 feeder breaker is tripped on overcurrent.

Which one (1) of the fo!!owing is the requirement for stopping 2DG1 based on the above conditions? A. Immediately.

B. Within three (3) minutes.

C. When jacket water temperature from the engine reaches 170 degrees F.

D. When lobe oil temperature from engine indicates 190 degrees F.

QUESTION:

QlD: 0027 Rev: 000 Point: 1.00 O Given the following:

  • The RCS has a stuck open Pressurizer Safety valve.
  • The reactor tripped and safety injection has actuated.
  • The RCS has rapidly depressurized to saturation conditions.
  • Pressurizer level initially dropped and then began to rise rapidly.

Which one (1) of the following characterizes the relationship between pressurizer level and RCS inventory and the reason 10r these conditions? A. Level is NOT an accurate indication of inventory. RCS voiding may result in a rapidly increasing pressurizerlevel.

B. Level is NOT an accurate indication of inventory. The cold calibrated pressurizer level channels indicate high during high temper.ature, low pressure conditions.

C. Level is an accurate indication of inventory. Voiding would occur first in the pressurizer steam space due to the high temperature of the pressurizer wallt.

D. Levelis an accurate indication of inventory. RCP flow would sweep any voids from the RCS to the pressurizer steam space and out the safety.

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ANO UNIT 2 - SRO EXAM l' . i . QUESTION:

QlD: 0028 Rev: 001 Point: 1.00

.

Given the following

  • Reactor power is 10%.
  • A main turbine roll to 1800 rpm is in progress.
  • Condenser vacuum has begun degradmg.

~ Annunciators 2K03-A3/A4 "2E11A/B Pressure Hi) are actuated.

,

Which one (1) of the following immediate actions should be taken by the Crow? L i j A. Reduce turbine speed to stabilize condenser vacuum.

I ' B. Raise Tave to reduce SDBCS load.

I i C. Trip the turbine before exceedmg 7 inches Hg absolute.

'

D. Observe the vacuum trend to determine if the turbine must be tripped over the next five ] (5) minutes.

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i QUESTION:

QlD: 0031 Rev: 000 Point: 1.00 . j Given the following conddions: ) j

  • The plant is in Refueling Operations with core alterations in progress.
  • Steam Generator secondary manways are removed.
  • The Steam Generator pnmary side manways are open with nozzle dams installed.

'

  • Both LPSI and Spray Pumps are operable.

i L Which one (1) of the following maintenance activities requires a suspension of core alterations and

movement of irradiated fuel in Containment? A. Testing the automatic isolation of the Containment Purge valves.

B. One (1) LPSI Pump is taken out of service to test breaker over-current settings.

C. Starting to perform the eddy current testing of the steam generators.

D. Steamline safety valves are rwmoved for bench testing of lift setpoint.

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_. _. _ _ _ _ _. - _ _.. _ _ _ _ _ _ _. _ _ _. _.. _. _ _ _ _ _ _ _. _ _ _ _ Q ANO UNIT 2 - SRO EXAM V QUESTION:

QlD: 0033 Rev: 000 Point: 1.00 Which one (1) of the following is the reason that Hot Log injechon is NOT established before two (2) ! hours following a Loss of Coolant Accident (LOCA)? A. Boron precipitation is not a problem before two (2) hours due to the large steam flow through the break.

B. To avoid possible entrainment of Si flow through the break due to a substantial amount of steam flow present before two (2) hours.

C. Cold Leg flow is needed for two (2) hours to ensure boron is " washed" to top of core.

D. To allow time for vessel head coolmg to prevent the possiblity of void formation in the vessel head which would reduce core coolmg.

. QUESTION:

QlD: 0034 Rev: 000 Point: 1.00 Following a dropped Control Element Assembly (CEA), Reactor Power is required to be reduced to O less than or equal to 80% by boration within one (1) hour. Which one (1) of the following paramete~. is the Technical Specificabon basis for this requirement? A. Samarium Redistnbution.

B. Axial Shape Index.

C. Fuelintegrity.

D. Quadrant PowerTilt.

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_ . - _ __ _.__._._.____._._..__..._____._.....-_m... . _ __ ___.._._ _, l l-{ ANO UNIT 2 - SRO EXAM QUESTION:-

QlD: 0036 Rev: 000 Point: 1.00 Which one (1) of the following describes the application of CAUTIONS in Emergency Operating Procedures (EOPS)?- A. Only apply to the continuous action steps of thm procedure.

B. Apply to ALL steps following the CAUTION statement.

C. Apply to the entire procedure in which the CAUTION is listed.

D. Apply to the step immediately followng the CAUTION.

,- l QUESTION:

QlD: 0037 Rev: 001 Point: 1.00 i i Which one (1) of the following would require development of a Temporary Alteration package? (Reference material provided) A. Performing a channel calibratio.l in which the procedure requires installing jumpers to ) electricaly bypass automatic actuaten.

B. A blatt flange is installed on a tagged out line while rerooting the line under an approved Job Order.

C. Connecting cables from 480V Motor Control Center (MCC) to a temporary power panel for l outage maintenance support.

' D. Maintenance technicians installing a temporary drain hose to support changing oil in a pump.

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.. _ _. _ _ _ _. _ _ _.. _. _ _ _. _.. _ _ _. _ _ _ _ _ _.. _ _ _.. _. _ _.. _. _ _. _ _ _ _ _ _. ~. Q ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0038 Rev: 000 Point: 1.00 While performing a Technical Specification Surveillance Test, an unacceptable condition occurs.

Which one (1) of the fc"r;i,g is the required action? A. Continue the test to the next logical hold point while recordmg data as required and then inform the Shift Superintendent.

B. Immediately notify the Shift Superintendent.

C. Record data as observed and allow Shift Supenntendent to compare parameter with acceptance criteria upon completion of the test.

D. Record data as observed and note the out-of-spec parameter in the comments section

QUESTION:

QlD: 0040 Rev: 000 Point: 1.00 Which one (1) of the following is an example of an INTENT procedure change? A. Minor alterations to the purpose for clarification.

B. Changing a tolerance to un operating parameter.

C. Changing a valve number to conect a typo.

D. Changing a step into two (2) substeps for clarification.

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_ _ _ _ _ _ _. _ _ _ _. _ _ _. _ _... _. _ . _. _. _ _... _ _. _.. _ _ _ _. _. _ _ _ _ _. _ _ Q ANO UNIT 2 - SRO EXAM ~ QUESTION:

QlD: 0042 Rev: 000 Point: 1.00 Given the followng conditions: ,

  • The plant is in Power Operation.

,

  • You are performing the duties of Control Room Supervisor.
  • You have been on shift for twelve (12) hours.

.* All the shifts are manned to MINIMUM composition per Technical Specifications.

  • Your relief is not on site for shift tumover.

Which one (1) of the followmg desenbos the requirements regarding shift composition and required schon in this situation? A. Cannot drop below the min 6 mum due to a relief being absent. Romam on watch until relieved.

B. Cannot drop below minimum unless individual will exceed sixteen (16) hours on watch.

- Tumover your watchstation to the oncoming Shift Engineer and depart.

. ! C. May be one (1) less than the mirumum for two (2) hours. Tum over your watchstation to the oncoming Shift Engineer, D. May be one (1) less than the minimum while attemptog to contact the absent individual.

O Tumover your watchstation to an inactive SRO and attempt to contact the absent individual.

, i UESTION:

QlD: 0043 Rev: 000 Point: 1.00 Cuttbg and weldmg in the Auxiliary Building were completed at 1410. Which one (1) of the following is the EARLIEST time the fire watch can be secured? A. 1420.

B. 1430.

C. 1440.

D. 1510.

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ANO UNIT 2 - ' SRO EXAM i j. QUESTION: 23-QlD: 0044 Rev:001 Point: 1.00 l-

- A Maintenance Contractor assigned to the Refuehng Team has been assigned the task of tweaking

I the incore detector flanges. Given the following information on dose history and dose rate, what is his stay time for the job? 1- - Commdted Dose Equivalent - 0.75 REM ' [ - Deep Dose Equivalent- 0.8 REM

- Lens Dose Equivalent- 0.2 REM i - Committed Effective Dose Equivalent---0.2 REM

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- Dose Rate at Flanges 0.9 R/HR $ ! , t i A.1.0 hour.

! i B. 2.0 hours.

+ , ' i C. 3.0 hours.

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D. 4.0 hours.

] i ! l QUESTION:

QlD: 0045 Rev:000 Point: 1.00 !

.

Which one (1) of the E"r;iig is the required MAXIMUM interval between performing safety function i status checks per 2202.004, Loss of Coolant Accident?

j A. Perform every 5 minutes.

l B. Perform every 10 minutes.

l C. Perform every 15 minutes.

! D. Perform every 30 minutes.

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. ' O ^" " " ' ' ' - 5" "*^" QUESTION:

QlD: 0046 Rev: 000 Point: 1.00 ! Given the Em ;chg conditions: c N MSIVs must be tagged in the OPEN position for repacking in MODE 6.

  • l.
  • The Instrument Air supply isolation valve will be tagged CLOSED.

l-Which one (1) of the following items should be included in the MINIMUM Personnel Protective equipment tagging requirements? ! A. Lift the leads on the MSIS solenoid valves.

' l ' B. Place the Control Room handswitches for the MSIVs to OPEN.

l ' C. Open the vent on the valve operator.

D. Installlocking pins for MSIVs.

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QUESTION:

QlD: 0049 Rev: 001 Point: 1.00

Which of the following parameters determine the Pressurizer Level Setpoint Program? , A. Main Steam flow.

B. RCS flow.

l o C. RCS Thot.

l D. RCS Tave.

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Q ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0052 Rev: 001 Point: 1.00 , Given the following condsbons:

  • A small feedline break inside containment has resulted in containment temperature increasing from 100 degrees F to 160 degrees F and containment pressure increasing from 14.5 to 17.0 psia.

Which one (1) of the following desenbes how and the reason why the increase in containment temperature will affect the indicated pressurizer level? A. Indicated level will be LOWER than actual level because of the elevated containment pressure.

B. Indicated level will be HIGHER than actual level because the reference leg fluid density decreases.

C. Indicated level will be HIGHER than actual level because of the elevated containment pressure.

D. Indicated level will be LOWER than actual level because the reference leg fluid density decreases.

O QUESTION:

QlD: 0056 Rev: 000 Point: 1.00 Given the felicei,g conditions:

  • A reactor startup is in progress.
  • Reactor enticality has Just been achieved.
  • An inadvestent reactivity addition results in a three (3) DPM Startup Rate.

Which one (1) of the following RPS trips will provide protection in this condition? A. High Log PowerTrip.

B. Variable Overpower Trip.

C. High Pressurizer Pressure Trip.

D. High DNBR Trip.

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] ANO UNIT 2 - SRO EXAM QUESTION:

QD: 0061 Rev: 000 Point: 1.00 Which one (1) of the E"ccis Area Radiation Morutors has Technical Specification operability requirements? A. 2RITS-8903,354 Aux Bide VCT Access Area monitor.

B. 2RITS-8912,404 Containment SW End Refueleng Dock monitor.

C. 2RITS-8916,404 Spent Fuel Pool General Area monitor.

D. 2RITS-8917,354 Aux Bldg Hot Lab Sample Room Area monitor.

QUESTION:

QlD: 0066 Rev: 000 Point: 1.00 Which one (1) of the following fuel handling events is addressed in 1 J.uti. Fuel Shuffle? A. A spent fuel assembly is damaged while being withdrawn from the core.

B. A new fuel assembly if found with the mobon sensors tnpped dunng fuel receipt inspection.

C. The Reactor goes cntecal whsie a fuel assembly is being inserted into the core.

D. A CEA is hanging from the upper guide structure dunng the removal of the upper guide structure.

QUESTION:

QlD: 0067 Rev: 000 Point: 1.00 A Loss of Offsite Power has occurred and both Emergency Diesel Generators and AAC Generator have failed to start automatically or manual:y. If powerinterruption is e:<pected to exceed minutes, then Vital Inverters 2Y13 and 2Y24 are to be secured? A.15 minutes.

B. 30 minutes.

C. 60 minutes.

D.120 minutes.

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Q ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0069 Rev: 000 Point: 1.00 A small Main Feedwater line break downstream of Main Feedwater Check valve (2FW-5A) at full power will depressurize the affected Steam Generator and start an uncontrolled cooldown when: A. The reactor trips on low Steam Generator level.

B. The main feedwater isolation valve is closed to "A" Steam Generator.

C. Main Feedwater and Emergency Foodwater to "A" Steam Generator is secured.

D. The "A" Steam Generator level drops below 50% Wxie Range level.

QUESTION:

QlD: 0070 Rev: 001 Point: 1.00 Standard Post Trip Actions,2202.001, Contingency Step 2.A.2 directs the operator to open the feeder breakers to 480 VAC Load Center busses 287 and 288 for ten (10) seconds and then reclose them. The purpose of rociosing the feeder breakers is to: l A. Restore power to the CEDMCS in order to verify that all CEAs have fully inserted.

B. Re-energize the 2B7 and 2B8 busses before the under voltage relays strip the individual , loads from the busses.

) C. Restore power to the Pressurizer backup heaters.

D. Restore power to Component Cooling Water Pump 2P33C and 480V MCCs.

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_.. _ _ _ _.. _ _ _.. - _ - _. _. _ _ _ _ _ _ _ _ _. _ _ _ l , Q ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0071 Rev: 000 Point: 1.00 I Which of the following descnbos the reason for the requirement to have a Hot Leg vent path for a Loss of Shutdown Cooling when the Steam Generator nozzle dams are installed? A. To prevent steam formation in the hot leg from causing an erroneously high Reactor Vessel levelindicabon.

B. To prevent steam formation in the Reactor Vessel head from pressurizing the RCS, leading to core uncovery.

C. To prevent steam formation in the hot leg which will ulumately collapse, causing severe water hammer.

D. To prevent the loss of RCS inventory caused by lifteg a Low Temperature Overpressure Protection (LTOP) relief valve.

QUESTION:

QlD: 0072 Rev: 000 Point: 1.00 While operating at power, significant current oscillations (100 amps) are observed on 480V bus 285.

Annunciator 2K12-B3, " CHARGING PUMP HEADER FLOW LOW" actuates and shortly thereafter, Charging Pump 2P36A trips on overcurrent. Which of the followng actions should be taken? A. Start an altamate charging pump after verifying i'.s suchon and discharge path.

B. Restart Charging Pump 2P36A after resetting the overcurrent trip.

C. Secure letdown and initiate an investigation for the loss of Charging Pump 2P36A.

D. Secure letdown, start an altomate charging pump, then restore letdown.

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ANO UNIT 2 - SRO EXAM , QUESTION:

QlD: 0077 Rev: 000 Point: 1.00 ,

j If a fire in the Cable Spreading Room bums for 45 minutes before it is extinguished, which of the j following will still be rehable in& cation for RCS pressure?

A. Safety Parameter Display System (SPDS) point P4624-2.

iI B. ' P sssunzer Pressure Control Channel Indicator P4626A.

l C. Pressurizer Pressure Safety Channel in&cator 2P4626-18.

f D. Pressurizer Pressure Low Range Pressure Indicator 2P4623-1.

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! QUESTION:

QlD: 0078 Riv: 000 Point: 1.00 i i-Imme&ately upon confirmation of a fire, the dedicated Board Operator is responsible for all of the

following actions EXCEPT: i f j A. Making prelimmary reportability verification.

B. Notify person reportng the fire to evacuate all non-fire bngade personnel from the area, , i j C. Obtsming pertinent information from the person confirming the alarm.

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D. Ensure the SS/CRS is notified.

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QUESTION:

QlD: 0079 Rev: 000 Point: 1.00 i

Which of the following Reactor Trip Circuit Breakers would indicate open on a loss of 120V Vital AC

bus 2RS-17

i i A. Breakers 1 and 5.

j B. Breakers 2 and 7.

f l C. Breakers 3 and 6.

D. Breaters 4 and 8.

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] ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0081 - Rev: 000 Point: 1.00 Which of the following reflects the primary conce n of the operators after a makr steam line break upstream of the MSIV in which the affected Stee n Generator blows dry? A. Ensure the RCS reheats back to normal oporatmg temperature withm Tech Spec heatup limits.

B. Maintam subcoolmg margin between 30F and 200F.

C. Energize all pressunzer heaters to re-establish saturated conditions in the pressurizer.

D. Re-establish all safety injechon flow.

QUESTION:

QlD: 0084 Rev: 000 Point: 1.00 The plant is at normal operating temperature and pressure when the Loop ll Component Cooling Water Surge Tank level starts increasing Select which of the following components could be causing this levelincrease. (Assume normal equipment conditions) A. Spent fuel pool heat exchanger.

B. RCP seal cooler heater exchanger.

C. Startup and Blowdown Domineralizer. Sample Cooler.

D. Main Chiller A.

QUESTION:

QlD: 0089 Rev: 000 Point: 1.00 Which of the following describes a condition that prevents the Refueling Machine from entering the upender zone? A. Fuel Hoist Box is latched.

B. Holst is at Hoist Up limit.

C. Spreaderis fully retracted.

D. Uponder is completely horizontal.

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. -. _.. - - , Q ANO UNIT 2 - SRO EXAM . QUESTION:

QlD: 0092 Rev: 000 Point: 1.00 With an inoperable Liquid Radweste Discharge Radiation Monitor (2RITS-2330), all of the following are required to perform a discharge from the Waste Condensate Tanks EXCEPT: A. Obtain and analyze independent samples from the Waste Condensate Tank.

B. Perform an independent venfication of discharge valve imeup C. Perform an independent vonficabon of proper Unit 1 Cire Water flow.

' O. Perform an independent venfication of release rate calculation.

t , QUESTION:

QlD: 0093 Rev: 000 Point: 1.00 i i Which of the following is the correct response if an EDG is paralleled to the grid and the govemor and voltage control hand switches are both taken to Raise / increase? , i ! A. KW increases arxi EDG speed increases.

! B. Reactive load increases and KW increases.

l ) C. Indicated output voltage increases and reactive load increases.

- D. EDG speed increases and indicated output voltage increases.

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QUESTION:

QlD: 0094 Rev: 000 Point: 1.00 ,

l Which of the following describes 4160V breaker operatum if DC control power is lost? l A. Breakers will remain in their "as is" condition and operation would only be possible by local j manual means.

i B. Automatic breaker trips would remain operatxmal but remote operation of breakers would l not be possible, i ! C. Breakers would remain remotely operable but automatic trip funcbons would become { inoperabio.

lO . D. Breakers would trip open and operation would not be possible by local means.

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_ _ _ _ _.. _ _ _.... _ _ . .... _. _ _. _.. _. _. _ _ _ _ -. _ -. _.. _. _... . _... _ . t' ' , Q ANO UNIT 2 - SRO EXAM . QUESTION:

QlD: 0095 Rev: 001 Point: 1.00 The output of the Vital 120VAC inverters is considered to be uninterrupbble because: , L A. Auctioneered AC power supphes are provided to the rechfier section.

. B. Inverter input is auctioneered between the rectifier output and a DC Battery Bus supply.

C. An internal battery is autioneered with the rechfier output.

D. The stabc transfer switch automabcally transfers to AC attenate source.

QUESTION:

Q1D: 0096 Rev: 000 Point: 1.00 The reactor trips from 100% power. The control room operators verify that the reactor is tnpped and immediately note that the turbine has not inpped and the generator breakers remain closed. If left unresolved this malfuncbon will cause: A. An uncontrolled cool down of the RCS, resulting in less shutdown margm.

B. Main turbine blade heating, possit.4y resulting in damage to the main turbine rotor and shaft.

C. A loss of condenser vacuum, resulting in the loss of condenser steam dumps.

D. An increase in RCS pressure, possibly resulting in the Pressurizer safety valves hfbng . i [ Page 21 L.

. . .. . . . .. .

_. . _. _ _. _ _. _ _. _ _ _ _ _ _ - -. _ _ _ _ _.. _ _ .. _ _ _. _ _ _ _. _ _ _. _. _ _ ] ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0097 Rev: 000 Point: 1.00 A cooldown to Mode 5 usmg the S'.aam Duinp and Bypass Control System is in progress.

Plant condmons are as follows:

  • Steam Generator A & B pressures are 745 pais.
  • Reactor Coolant System temperature is 508F.
  • Pressurizer pressure is 2100 psia and level is 's3%.
  • RCPs 2P32A, B and C are operating
  • Charging Pumps 2P36A and 2P368 are operstmg and Letdown is in automatic control Select the action which should be performed to prevent an inadvertent Engineered Safety Features

~ Actuation Signal (ESFAS).

A. Roset the Pressurizer low pressure trip setpoints.

B. Raise Pressurizerlevel to 50%. ' C. Bypass the Pressurizer low pressure trip.

D. Roset the Steam Generator low pressure trip setpoints.

O QUESTION:

QlD: 0099 Rev: 001 Point: 1.00 Following a single channe; CPC trip, how can the operator quickly determine if the trip signal is due to an auxiliary trip? A. By obtaining the CEAC Trip Buffer Report.

B. By observing a trip light without the associated protrip light.

C. By obtaining the trip TRA report.

D. By observing that Diverse Scram System (DSS) Trouble annunciator has actuated.

. l , O Page 22 . , -,, - + -.- e , - +,. - - --e.- , e- -, e

... -.. -. - -. -.. .. -. _ -.-. - - -.--. - -.-.. -..... - -.. -... - -.... -.. -._... -. ] ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0103 Rev: 001 Point: 1.00 l ' When cooling down the plant per OP 2102.010, Plant Cooldown, when are the Low Temperature Over Pressure Protechon Relief Valves (LTOPs) required to be aligned to service? A. Prior to closing the Safety injechon Tank's isolate valves.

B. Prior to entenng Mode 4.

j C. Prior to placing both Letdown Flow Control valves in service.

D. Between 275 and 270 degrees F RCS Temperature.

QUESTION:

QlD: 0104 Rev: 001 Point: 1.00 An EFAS 1 signal will be present for which of the following? (consider each answer separately).

A. SG "A" Level = 20% NR & Press = 600 psia SG "B" Level = 26.5% NR & Press = 600 psia.

, B. SG "A" Level = 30% NR & Press = 700 psia SG "B" Level = 25% NR & Press = 680 psia.

' C. SG *A" Level = 15% NR & Press = 200 psia SG "B" Level = 20% NR & Press = 400 psia.

D. SG "A" Level = 5% NR & Press = 500 psia SG "B" Level = 10% NR & Press = 370 psia, i O Page 23

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.. . . -.... . -.. . -. -. -- - -- . ,] ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0105 Rev: 001 Point: 1.00 Which of the following events is in progress for the given conditions? - RCS pressure, temperature, power, and inventory stable.

- Steam Generator pressure and levels stable.

- Containment temperature, pressure and humidity rising rapidly.

- Containment Sump indmates a 150 gpm increase.

  • A. RCS leak in Containment.

B. Main Steam Leak in Containment.

C. CCWleak in Containment.

' D. Main Feedwater leak in Containment.

QUESTION:

QlD: 0107 Rev: 000 Point: 1.00 i.

Which of the following could be an indication of core uncovery? (Assume instruments are accurate) CET Temperature equal to: , A. 550 degrees Farenheight with RCS Pressure equal to 1100 psia.

B. 570 degrees Farenheight with RCS Pressure equal to 1300 psia.

C. 590 degrees Farenheight with RCS Pressure equal to 1350 psia.

, D. 610 degrees Farenheight with RCS Pressure equal to 1700 psia.

. b G Pa0e 24 x

. _.... -.. ...... . . -... -.. ... -.. .. -. -. ... . -. -. . Q ANO UNIT 2 - SRO EXAM ' QUESTION: _53 QlD: 0110 Rev: 000 Point: 1.00 , . i . The following condsbons exist:

  • A feedline bnnak has occurred inside containment.

,

  • Containment pressure is 18.5 psia.
  • Containment radiation is normal.
  • PZR pressure is 1825 psia.
  • RWTlevelis 92%.
  • SG pressures are (SG"A") 925 psia, (SG"B") 580 psia.
  • SG levels are (SG"A") 22% NR, (SG"B") 10% NR All of the following actuation signals should have occurred with the excephon of:

A. SIAS . B. MSIS C. EFAS 1 D.CSAS O = ' QUESTION:

QlD: 0111 Rev: 001 Point: 1.00 The plant is in Mode 3 with Pressuriza Level Control System and Letdown in automatic. The CBOR notea letdown flow rising. Which of the following is a possible cause? A. Loss of instrument Air to Letdown Backpressure Regulating Valve.

~ B. The selected Pressurizer Level Control Channel has failed high.

C. Volume Control Tank Level has dropped to less than 10%. D. SDBCS controller setpoint has failed low.

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O ^"O UNIT 2 - SRO EXAM

QUESTION:

QlD: 0i14 Rev: 000 Point: 1.00 ! Which of the following is the reason for preventing the start of the fourth Reactor Coolant Pump until

RCS temperature is greater than 500 degrees Farenheight? j A. To prevent exceeding RCS heatup rate limits.

i l B. To prevent excessive RCP starting currents.

! C. To limit Steam Generator tube stresses.

. [ D. To limit core upleft.

i l

QUESTION:

QlD: 0115 Rev: 000 Point: 1.00

< ! A cooldown and depressurization is in progress. RCS pressure is currently at 1100 psia and seal j pressures for RCP 2P32B are: i

  • Vapor 40 psia.

!(

  • Upper 40 psia.

[

  • Middle 530 psia.

i l Which RCP seal has failed?

A. Lower seal.

! B. Middle seal.

! C. Upper seal.

D. Vapor seal.

, ! - !

1

. Page 26

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-. ... _. - -. -. -... -.. .. -. - -. _. _ - ... - - -. - _. - -.... - - - - - _ Q ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0121 Rev: 000 Point: 1.00 Fuel is being reloaded into the Reactor Vessel when the Shift Supervisor informs you that one startup channel neutron flux monitor has failed. Which of the following desenbos the required action? A. Fuel reload may continue provided backup boron samples are taken every four (4) hours.

B. Fuel reload may continue provided the inoperable channel is returned to operable status ' within four(4) hours.

l C. Suspend core alterates until boron sampling has been irutstated every twelve (12) hours for 36 hours.

D. Suspend core alterations until the inoperable clunnel is returned to operable status.

l l l~ QUESTION:

Q1D: 0123 Rev: 000 Point: 1.00 i Which of the following best describes how far back in the Station Log an oncoming Shift Superintendent must review, prior to shift tumover, if that individual has not been on shift for 30 days? l l A. since the last shift watch that was stood.

B. three days.

C. one week.

D. two weeks.

. . l l Page 27 i ~ ' --- - , ,, - .

. _... _ _.. _... _ _ _. _... _. . _. _ _ _ _ _.. _ _ _ _... _. _ _ _. _. _ _. _ _ _ Q ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0124 Rev: 000 Point: 1.00 Which of the following best describes the condstion in which the ANO overtime working hour pokcy applies? A. a person working in training performing simulator operations.

B. a person workmg on a procedure revision for a quality related system.

C. a perso working on a non-safety related system or component.

D. a person working on safety-related system or component.

QUESTION:

QlD: 0125 Rev: 000 Point: 1.00 . L A Waste Control Operator is required to complete a valve kneup in an area where the radiation level . is 50 mrom/ hour. The operator's current Total Effective Dose Equivaient (TEDE) is 1730 mrom.

What is the maximum time he can work in this area and not exceed his Administrative Dose Control Level (ADCL)? O A.1 hour.

B. 5 hours.

C.10 hours.

D. 25 hours.

i- ! i i i e.

' Page 28

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.. - -.- -.. .... - ... -. -. - -... - -.. -. _. -. .. -. -. - - - -. - -... - Q ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0127 Rev: 000 Point: 1.00 Given the following plant conditions-

  • Unit operating at 100% power.
  • Channel"D" upper detector of excore safety channel monitors fails HIGH.

l Which one (1) of the following desenbos the expected response of Channel"D" Reactor Protection l System to this failure? (No other failures are present) A. High Local Power Density and Low DNBR trips without pre-trips.

B. High Log Power, High Local Power Density and Low DNBR trips and pre-trips.

C. High Log Power, High Local Power Density and Low DNBR trips without pre-trips.

i D. High Linear Power, High Local Power Density and Low DNBR trips and protrips.

1 i QUESTION:

QlD: 0128 Rev: 001 Point: 1.00 O

Given the followmg conditions: L

  • Unit is operating at 100% power.
  • Action statement 3.6.2.1 states, "with one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours or be in a least HOT STANDBY within the next 6 hours...."

l

  • Contamment Spray System "A" becomes INOPERABLE at 1200 on 11/10.

'

  • Containment Spray System "B" becomes INOPERABLE at 1100 on 11/12.

j

  • Containment Spray System "A" becomes OPERABLE at 1130 on 11/12.

l l Which of the following identifies the time and date for restoratior, of Containment Spray "B" before plant shutdown must be commenced? l l A.1200 on 11/12.

B.1200 on 11/1'> C.110C on 11/15.

D.1130 cm 11/15.

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<

i j QUESTION:

QlD: 0131 Rev: 000 Point: 1.00 2202.001 " Standard Post Trip Actions" step 7.E states, " Check RCS Tave 540 degrees F to 555 , !, degrees F". Which one of the following desenbes the basis for this step? j

A. Ensures RCS heat removal through the steam generators.

i l B. Demonstrates proper operation of the reactor regulating system.

C. Demonstrates proper operation of the safety injechon system.

D. Maintains adequate SDM given a posibve moderator temperature coefficient.

< i ~ QUESTION:

QlD: 0134 Rev: 000 Point: 1.00 > 2- ,i Which one of the following states the required action (s) for pressurizer pressure reaching 2790 psia

when operating at full power? ! ! A. Restore to within limits within 15 minutes or be in HOT SHUTDOWN within the next six (6) O ' -

B. Restore to within limits within one (1) hour or be in HOT SHUTDOWN within the next six (6) j hours.

C. Be in Hot Standby with RCS Pressure within its limit within one (1) hour.

D. Perform an engineenng evaluation on the out-of-limits condition within 24 hours.

. ! O Page 30 . I' ' '. - ,, . _.. ,,, , -,, .-..__r..m ,. _ _ -

. .. .. _...... _ _ _. _ _. _ _ _ _ - _. _ _. _. _ _ _ _ _ _ _ _ _ _. - ., t ANO UNIT 2 - SRO EXAM - l QUESTION:

QlD: 0135 Rev: 000 - Point: 1.00 - !' Assuming two Atmospheric Dump valves are out of service. Which one of the following best L approximates the remairung total steam flow capacdy of the Steam Dump and Bypass Control ' System? I A. 25%

B. 30% , C. 40% i i i D. 50%

- QUESTION:

QlD: 0136 Rev: 001 Point: 1.00

I

Given the followng con &tions: Unit is operating at 100% power.

i l E-bar is 5.3 microcuries/ gram.

RCS sample shows specific activity of 25 microcuries/ gram.

Which one of the following states the required action (s) for this con & bon? A. Restore RCS activity to within limits vnthin 1 hour or be in at least hot standby in the followng six (6) hours.

B. Be in at least HOT STANDBY with T-ave less than 500 degrees F within six (6) hours.

C. No acbons required due to LCO conditions being satisfied.

D. Perfrxm sampling of RCS activity within the next six (6) hours.

l , , t i O , I I Page 31 l I ' . . ..,. ,, ..., _.. _- , -.... _

. _ ._ _ _ __ _._ _ _ _. _. _ _ _._. _ _ _ _... _ __ _ _ _..__ _ _ _._..._ _ __. _ i-a i Q ANO UNIT 2 - SRO EXAM . l QUESTION:

QlD: 0138 Rev: 000 Point: 1.00

All of the followmg components / subsystems can be discharged into the Quench Tank EXCEPT: ! l A. RCP Vapor Seal Leakoff.

B. PressurizerVent.

<

. C. RCP Control Bleedoff relief.

! D. Reactor Vessel Head Vent.

j QUESTION:

QlD: 0140 Rev: 001 Point: 1.00 Which one of the following is a condition requiring emergency borsten eccein.g to AOP 2203.032, Emergency Boration? A. CEA Group P inserted to 138 inches vnthdrawn with Unit at 90% power.

B. Loss of all CEA Reed Swhch Posstion indication at 5% power.

C. Reactor enbcal and CEAs inserted below the Transient insertson Limits.

D. Loss of Plant Monitoring System computer during a reactor startup.

QUESTION:

QlD: 0141 Rev: 000 Point: 1.00 While performing a natural circulation cooldown following a Steam Generator Tube Rupture, pressurizer level is varying by large amounts inconsistent with the cooldown and depressurization of the RCS. Which one of the following statements correctly describes the cause of wide deviations from the expected pressurizer level? A. Pressurizer level instrument reference leg flashing.

B. Automabc opersbon of charging pumps.

C. Contrachon of the RCS during the cool down.

D. Voiding in the Reactor Vessel Head area.

O Page 32

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QiD: 0146 Rev: 000 Point: 1.00

With a Control Element Assembly misaligned less than 19 inches, Technical Specificetions allow the operator one hour to take corrective action. The one hour time limit will: A. preclude a decrease of available shutdown margin.

B. minimize the effects of Xenon redistnbution C. preclude large effects on power distnbution.

D. preserve assumed worth of an ejected rod.

QUESTION:

QlD: 0149 Rev: 001 Point: 1.00 Verification of Containment Spray System operation is required when Refueling Water Tank level decreases to < 6% dunng a Loss of Coolant Accident in order to: i A. provide long term post-accident core coolmg O B. remove lodme from the containment atmosphere.

C. provide mixing of the sodium hydroxide.

D. provide flow to reduce electrolytic corrosion.

QUESTION:

QiD: 0153 Rev: 000 Point: 1.00 Following the determination that a CEA in Shutdown Bank "A" is misaligned by four (4) inches and mechanically bound, shutdown margin is calculated to be 4.9%. Which one (1) of the following actions should be taken? A. Continue plant operation without restnchon B. Reduce power to less than or equal to 81%. C. Start a plant shutdown and be in Mode 3 within 6 hours.

D. Initiate Emergency Boration.

O Page 33 c.

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.- .. - ~ - . - . -. - _ - -.. - - _ - - -.. - - - _. - -. - _. - -. - -. _. - - llQ - ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0154 Rev: 000 Point: 1.00 The following plant condebons exist

  • Plant is in Mode 3.
  • Trip from 100% power occurred five (5) minutes ago.
  • CEAs 40 and 41 are stuck fully withdrawn.

i

  • Charging pump trips on a loss of suchon pressure
  • Operators unable to start other cheiv;,,g pumps.

, l Which one (1) of the following operator schons is procedurally required under these condstions? -l A. Lower RCS pressure and emergency borate via HPSI.

, i B. Emergency borate via gravity feed suction path, i i C. Lower RCS temperature and initiate SIAS.

D. Use auxdiary spray and emergency borate.

i l ! - QUESTION:

QlD: 0156 Rev: 000 Point: 1.00 The following condebons exist I

  • A small break Loss of Coolant Accident has occurred.

l

  • High Pressure Safety injechon (HPSI) Pump 2P89A has tripped on over current.

l

  • The crew has aligned and started HPSI Pump 2P89C. (Red Power)
  • Two charging pumps are running.

L

  • Pressurizer pressure is 1500 psia and steady.
  • HPSI Pumps 2P898 and 2P89C have been stopped upon meeting SI Termination Criteria.

l The CBOR reports that Pressurizer Level is now 20% and slowly dropping. Determine which one (1) i of the following actions is appropriate.

A. Start HPSI Pump 2P898 and throttle open enough HPSI Injechon valves to raise Pressurizer level to greater than 28% l' B. Start HPSI Pump 2P898 and the third Charging Pump and fully open all HPSI Injection valves.

i-L C. Start HPSI Pumps 2P898 and 2P89C and Nily open enough HPSI Injechon valves to raise Pressurizer level to greater than 28% i ! D. Start HPSI Pumps 2P898 and 2P89C and fully open all HPSI Injection valves.

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! jQ ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0157 Rev: 000 Point: 1.00 ! The unit is at 50% power during a ramp to full power, when a reactor and turbine trip occur. Which

one (1) of the following statements describes the immediate response of the atmospheric dump

valves (ADVs) and Bypass Control valves? J

A. ADVs receive a " quick-open" signal and bypass valves modulate to control main steam ! pressure.

i B. Bypass valves and one' ADV receive " quick open" signal then modulate to control main steam ) pressure.

- C. ADVs modulate to control RCS temperature and bypass valves receive a " quick-open" signal.

l-D. Reactor trip theks all " quick open" signals then ADVs and bypass valves receive modulate signal from the master controller to control RCS temperature.

QUESTION:

QlD: 0160 Rev: 000 Point: 1.00 Given the followmg plant conddions:

  • Plant shutdown and cooldown just completed from 100% power.

'

  • Shutdown Cooling has JUST been established.
  • A Loss of instrument Air occurs.

Which of the following describes the Shutdown Cooling System response? A. All SDC flow is lost.

B. SDC heat removalis lost.

C. SDC flow is degraded.

D. No significant effect.

. O Page 35 C . _ _

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... _... _ . _. _ _. _ _.... _ _.. _. ... . _. _... _ _ _ _ _ _ _.. _ _ _.. _. _ _ _ _ _ _. _ _. _ l i ] ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0161 Rev: 000 Point: 1.00 i Given the following conditions: i

  • A small break Loss of Coolant Accident is in progress.
  • RCS pressure is 1600 psia.

. - * Containment pressure is 16 psia and slowly increasing.

  • Containment Hi Range Radiation Morntors read 13 R/Hr and increasing.
  • No operator actions have been performed.

Which one (1) of the following schons should be performed? A. Isolate letdown.

B. Manually actuate SIA51.

C. Manually actuate CIAS.

D. Manually actuate CSAS.

l , , QUESTION:

QlD: 0164 Rev: 000 Point: 1.00 Which is the maximum temperature expected as measured downstream of a leaking Pressurizer Code Safety valve on 2TI-4694, Quench Tank Temperature indicated on 2C047 A.- 212 degrees F.

B. 300 degrees F.

C. 375 degrees F.

D. 650 degrees F.

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ANO UNIT 2 - SRO EXAM

QUESTION: 7g QlD: 0167 Rev: 000 Point: 1.00 ' Given the followmg condsbons:

  • Safety injection actuated.
  • Emergency Diesel Generator 2DG1 Trouble Alarm actuates.
  • Emergency Diesel Generator 2DG1 trips.

Which one of the f*;i g identifies the cause of the 2DG1 trip? A. Loss of Field.

i B. Phase Differential.

' C. Anbmotoring.

l D. Crankcase pressure high.

a ' . QUESTION:

QlD: 0168 Rev: 000 Point: 1.00 O ' Which of the following describes the effect of a loss of green DC Bus,2D26 will have on the operation of Emergency Feedwater Pump 2P7A? A. All 2P7A dischage valves to both Steam generators will fail open.

' . B. All 2P7A discharge valvea to both Steam generators will fail closed.

C. 2P7A will overspeed.

D. 2P7A will go to minimum speed.

Page 37

... - . -.. -. . - - -.. - -.. -. - -.. -. - - -. _ _ -. - -.. , ' ] ANO UNIT 2 - SRO EXAM QUESTION:

QiD: 0169 Rev: 000 Point: 1.00 The following plant condsbons exist '

  • CCW Pump 2P33A is supplying Loop 1 CCW.
  • CCW Pump 2P338 is supplying Loop 11 CCW.

'

  • CCW Pump 2P33C is tagged out for maintenance.
  • 2K12-F6, PUMP 2P33A/B/C LOCKED, is actuated.

Which of the following describes what would happen to the CCW Loop Crossover valves if 2P33A Tripped? A. Loop 1 Crossover valves automatically open and Loop ll Crossover valves automatically close.

- L D. Loop 1 Crossover valves automatically open and Loop ll Crossover valves stay open so that 2P330 can supply both loops.

i . C. The Control Board operator will have to manually open the Loop 1 Crossover valves and throttle closed Loop ll Crossover valves to balance loop flows.

D. The Loop I and Loop 11 Crossover valves will remain in the posebon they were in prior to { 2P33A trip.

O ' QUESTK)N:

QlD: 0170 Rev: 000 Point: 1.00 What would the initial pnmary plant temperature and pressure response be for a 100% turbine load rejection? A. RCS temperature and pressure constant due to GDBCS valves opening to controlling SG pressure.

B. RCS temperature and pressure constant due to main spray valves opening.

C. RCS temperature and pressure increasing even with SDBCS valves and main spray valves opening.

D. RCS temperature and pressure decreasing due to SDBCS valves and main spray valves opening.

O Page 38 L . - , ._

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'

! iQ ANO UNIT 2 - SRO EXAM l QUESTION:

QlD: 0173 Rev: 001 Point: 1.00

4 . Given the following plant condations: !'

  • Full power Mode 1.

l

  • Cire Water Pump 2PSA trips.

Which of the following best desenbos why turbine load must be reduced for the given conditions? t' A. Prevent condenser overpressurization.

B. Prevent cavitatum of Cire Water Pump 2P38.

.

C. Prevent exceedmg 40F circ water delta T across condensers j-i D. Prevent exhaust hood temperature from exceedmg 200F.

, i i i QUESTION:

QlD: 0174 Rev: 000 Point: 1.00 j_ The 90% limit switch on the MSlVs (2CV-1010A and 2CV-1060A) causes the:

A. Exercise valve (2HS-1011 and 2HS-1061) green light to illuminate.

{ . B. Exercise valve (s) to open to prevent inadvertent MSIV closure.

! j C. Intermediate position indication on the MSIV hand-switches (2HS-1010-1 and 2HS-1060-2).

D. MSIV bypass valve to close when opening the MSIV.

. , m O Page 39 . , -

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1- , i { ANO UNIT 2 - SRO EXAM ] QUESTION:.

QlD: 0175 Rev: 000 Point: 1.00 t j What effect would a decreasing Spent Fuel Pool Level from Elevation 401' 6" to Elevation 401' 1" j have on the operation of the Spent Fuel System or the working area adjacent to the Spent Fuel Pool? A. Complete loss of NPSH to SFP coolmg pumps.

. B. Humidsty levels will increase to greater than Tech Spec limit.

C. Boron concentration will decrease

D. Radiation levels willincrease.

QUESTION:

QlD:' 0176 Rev: 000 Point: 1.00 Given the following plant condebons:

  • Mode 5
  • Equipment hatch is to be opened

.O - Which of the following actions should be used to property align the Containment Purge System? A. Place Purge Supply Fan,2VSF-2, in HAND then secure Purge Exhaust Fan,2VEF-15.

B. Place Purge Exhs ust Fan,2VEF-15, in HAND then secure Pe3 Supply Fan,2VSF-2.

C. Manually close one Purge Exhaust Damper, then secure Purge Exhaust Fan,2VEF-15.

D. Manually close one Purge Supply Damper, then secure Purge Supply Fan,2VSF-2.

. O Page 40 L'. .. _ . -

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QlD: 0179 Rev: 000 Point: 1.00 i Given the following plant condetions:

  • FullPowerOpersbons

' * Condensate Pumps 2P2A,2P2B and 2P2C running j

  • Condensate Pump 2P2A trips Which of the following automatic actions should occur?

A. Heater Drain Pump 2P8A will auto start.

B. Condensate Pump 2P2D will auto start.

C. Recirculation valve for Condensate Pump 2P2B will auto close.

D. Main Feed Water Pump 2P1 A will trip on low suchon flow.

. QUESTION:

QlD: 0180 Rev: 000 Point: 1.00 O Given the following plant conditions:

  • Mode 5
  • Pressurtzer Manway removed
  • LPSI Pump 2P60A through Shutdown Cooling Heat Exchanger 2E35A
  • High alarm actuated on Radiation Monitor 2RITS-1453 (SW From SDN Ht Exch 2E-35A)

Which of the following actions would be required? A. Secure 2P60A, dose SDC RCS isolation MOVs and start RCPs for RCS heat removal via SGs.

l B. Secure 2P60A, close SDC RCS isolation MOVs and steam both SGs in Natural Circulation for heat removal.

, C.1 Align SW and RCS to 2E358 and isolate SW and RCS to 2E35A.

D. Start Containment Spray Pump 2P358 and align to 2E35B and secure 2P60A and isolate SW and RCS to 2E35A.

O Page 41 e...

.. _ _ _. _ _. - -. _ _ _ _ _ _ _ _ . _ _. _. _.... _ _.. -. _ _ _. _ _ _ _. _ _. _ _.. _ _. _. _ _ _.. _ _ _. _ _ _.. _ _. _, l ~ Q ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0181 Rev: 000 Point: 1.00 l Given the following conditums: . '

  • Mode 3 post trip from full powsr.
  • EFAS signal present with EFW Pumps 2P7A and 2P7E ianning.
  • 2P75 feeding SG's via 2CV-0762 (AFW to EFW).

Which of the following descnbos why flow should be limited to 1200 gpm for the given conditions? l A. Limit flow velocities.

B. Prevent binding of EFW block valves.

C. Prevent thennal shock to SGs.

D. Prevent AFW pump runout.

l QUESTION:

QlD: 0182 Rev: 000 Point: 1.00 Which of the following indications will be observed on a Loss of Inverter 2Y-11 ( Red )? A. Half Leg Trip.

B. ReactorTrip.

C. All Red ESFAS components will actuate.

D. NO Red ESFAS components will actuate.

t l _ l l O Page 42 J.. . Q ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0183 Rev: 000 Point: 1.00 Given the followng conditions:

  • Mode 2 operatens.
  • Reactor Power 5E-5% and stable.
  • Annunciator 2K04-G9, MSSV Valve Open actuates and will not clear.
  • No operator actions taken Which of the f="c;3g conditions will result in the highest power for the conditions given above?

A. Initial CEA height.

B. Initial RCS Tave.

C. BOL Core.

D. EOL Core.

QUESTION:.

QlD: 0184 Rev: 000 Point: 1.00 Given the followng plant conditions:

  • Mode 6.

-

  • Fuel assembly in mast over upender.
  • CEA change tooljammed in personnel hatch.

Which of the followmg actens must be performed for the above conditions? )' A. No actions requered.

B. Evacuate Containment Building.

C. Move fuel assembly to Spent Fuel Pool.

D. Suspend fuel movement in Spent Fuel Pool.

O Page 43 . . . . . .

> ! Q . ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0185 Rev: 000 Point: 1.00 Given the following plant condsbons:

  • RCS pressure 1000 psia.
  • RCS CET's 556F.
  • Tcold 544F and increasing rapidly.
  • Loss of Offsite Power
  • SIAS actuated.
  • CCAS actuated.
  • 2DG1 tripped on overspeed.
  • HPSI Pump 2P89C abgned to Red bus.

Which of the ic"c;i,g schons should be performed for the above conditions? A. Open ECCS vents (2CV-4698-1 and 2CV-4740 2).

B. Open LTOP relief isolations (2CV-4731-2,2CV-4741-1 and 2CV-4730-1).

C. Swap HPSI Pump 2P89A to Green bus.

D. Depressunze using auxiliary spray to dump SITS.

O QUESTION:

QlD: 0186 Rev: 000 Point: 1.00 Given the following plant condebons:

  • Loss of Offsite Power for two (2) hours.
  • 30 gpm LOCA in progress.
  • Mode 3

'

  • MSIS reset.
  • Steam Generatorlevels 23% narrow range.

Which of the following should be utilized to cool the core frorn the control room for the above condebons? ' A. Use upstream AOVs (2CV-1001 and 2CV-1051).

B Use upstream MOVs (2CV-1002 and 2CV-1052).

C. Uso downstream AOVs (2CV-0301 and 2CV-0305).

D. Go to HR-4 and utilize once through coohng O , Page 44

. _ _. . -. _.. _.. _ _.. _.. - _ - _. -. _. _ -. _ _. _.. _ . _ _ -.. _ _.. - _. -. _. _ . - _. _ _... _. _. - - l i i ANO UNIT 2 - SRO EXAM l _ l' QUESTION:

QlD: 0187 Rev: 000 Point: 1.00 Given the following plant conddions: , l

  • Full power operation.
  • Instrument Air Header Pressure decreases to 60 psig, i
  • Instrument Air Header Cross-tie valves 2CV-3004 and 2CV-3015 are opened.
  • Instrument Air Header Pressure continues to decrease to 30 psig.
  • Report from Unit 1 that their instrument Air pressure is 50 psig.

l l Which of the following actions would apply? l . l.

A. Bypass Instrument Air Dryers.

' L B. Crosstie instrument Air and Service Air Systemd.

! ! C. Open coalescing profilter bypass.

i D. Close crosstie valves 2CV-3004 and 2CV-3015.

l QUESTION:

QlD: 0188 Rev: 000 Point: 1.00

l Given the following conditions: l

  • Reactor has tripped fmm full power.

l.

  • 110 gpm SGTR.
  • 60 gpm LOCA.
  • RCS cooldown and depressurization in progress.

l

  • RCS pressure 1200 psia.
  • RVLMS level 4 indicates wet.
  • RCS Thot 530F Which of the following acbons should be performed for the above conditions?

, A. Stop depressurization until RVLMS level 1 indicates wet.

B. Stop cooldown.

C. Secure one (1) RCP in each loop.

D. Open Reactor Vessel High Point vents to Containment Atmosphere.

- , LO . Page 45 .-. - __ .. - - .

_ _-. - _. __ _ .. _ _ _. _.. _. _ _ _ _ _ _._. _ _ _. _ _. _. - _ _ _._ _ , O ' ^"o ua'T 2 - Sao =x^= l . QUESTION:

QlD: 0189 Rev: 001 Point: 1.00 Given the following plant conditions: ,

  • SGTR in progress.
  • 2RITS-8907 (Elv 372 Conidor by EDGs) roads 4 mr/hr.

'

  • 2RITS-8911 (Elv 386 by HP Office) roads 6 mr/hr.
  • 2RITS-8924 (Elv 354 CCW Pump Room) roads 11mr/hr.
  • HP unevaluated Tutt>ine Building air sample reads 10E-10 microcuries/cc.
  • HP unevaluated Outside air sample reads 1E-20 microcuries/cc.
  • Projected dose at site boundary is.5 mr/hr.

Which of the followmg schons should be performed for the given condstx>n? A. Declare a General Emergency (GE) and evacuate all personnel in the ten (10) mile radius.

B. Declare a Site Area Emergency (SAE) and evacuata all personnel within the five (5) mile radius.

C. Declare an Alert and perform a Plant Evacuation.

D. Declare an (NUE) and perform a localized evacuation of the CCW pump room.

QUESTION:

QlD: 0190 Rev: 000 Point: 1.00 Which of the following describes why RCS pressure is maintained within 100 psia of RCP NPSH during a primary to secondary leak of 20 gpm? A. Ensures margin to saturation is greater than SOF.

B'. To minimize RCS Break flow.

C. Ensures sealinjechon can be maintained.

D. Prevents lifting primary code safeties.

O

, Pape 46

- - _.. _..... _ - _ _.... _ _ _ _. _ _ _ _. _ _ _. _._._ - _. _ _ _. _ _ _ _ l l Q ANO UNIT 2 - SRO EXAM QUESTION:

QlD: 0192 Rev: 000 Point: 1.00 Given the following plant conddions: ,

  • Plant power at 100%.
  • Group 6 CEAs at 150" wnthdrawn.
  • RSPT #1 for CEA 46 updata to CEAC #1 roads 140".
  • RSPT #1 for CEA 46 next update to'CEAC #1 roads 150" What alarm would be actuated from CEAC #17 l

A. CEAC #1 CEA Deviation.

) i ' B. CEAC #1 Fadure.

C. CEAC INOP light on CPCJCEAC Operator's Module.

D. CEAC #1 Sensor Fadure.

O QUESTION: 100 QlD: 0193 Rev: 000 Point: 1.00 ' b

A large feedwater line break upstream of check valve 2FW-5A has occurred. What post trip operator actions are required? . A. Trip all MRN and Condensate pumps and close all FW block valves.

.. B. Verify MSIS automatically actuated.

- j C. Verify EFW not feeding "A" SG.

D. Verify EFW not feeding "B" SG.

I b .

i O I Page 47

,, -, , --,

- _ _ . .- _.. ___ _ __ _ . _ _ _ p, ANO UNIT 2 - SRO EXAM ANSWER KEY QUESTION: 1 QlD: 0002 Point: 1.00 A. Tave willincrease.

QUESTION: 2 QlD: 0003 Point: 1.00 C. ECCS pumps will restart in time delayed sequence.

QUESTION: 3 QlD: 0004 Point: 1.00 j B. Annunciator 2K12-A1," LETDOWN RADIATION Hl/LO".

QUESTION: 4 QlD: 0005 Point: 1.00 A. Reactor power will rise, Tave will be unaffected.

QUESTION: 5 QlD: 0010 Point: 1.00 ' C. Ensure containment atmosphere is isolated fmm the outside environment in the event of radioactive release or pressurization.

QUESTION: 6 QlD: 0011 Point: 1.00 D. Component Cooling Water Flow is lost for over 10 minutes.

QUESTION: 7 - QlD: 0012 Point: 1.00 A. Emergency borate until adequate shutdown margin is demonstrated.

I QUESTION: 8 QlD: 0018 Point: 1.00 C. Stop one (1) RCP in each RCS loop.

QUESTION: g QlD: 0020 Point: 1.00 B. RCS pressure may remain so hi0h that cooling fmm the injection flow alone is inadequate.

QUESTION: 10 QlD: 0021 Point: 1.00 - C Radiation Levels.

QUESTION: 11 QlD: 0025 Poirt: 1.00 B. Within three (3) minutes.

QUESTION: 12 QlD: 0027 Point: 1.00 A. Level is NOT an accurate indication of inventory. RCS voiding may result in a rapidly increasing pressurizerlevel.

QUESTION: 13 QlD: 0028 Point: 1.00 C. Trip the turbine before exceeding 7 inches HQ absolute.

QUESTION: 14 QlD: 0031 Point: 1.00 D. Steamline safety valves are removed for bench testing of lift setpoint.

QUESTION: 15 QlD: 0033 Point: 1.00 B. To avoid possible entrainment of Si flow through the break due to a substantial amount of steam flow present before two (2) hours.

Ob Page1

- ._.

. _ _ ... .-- . . n ANO UNIT 2 - SRO EXAM ANSWER KEY I QUESTION: 16 QlD: 0034 Point: 1.00 l C. Fuelintegrity, j QUESTION: 17 QlD: 0036 Point: 1.00 D. Apply to the step immediately following the CAUTION.

QUESTION: 18 QlD: 0037 Point: 1.00

C. Connecting cables from 480V Motor Control Center (MCC) to a temporary power panel for outage maintenance support.

QUESTION: 19 QlD: 0038 Point: 1.00 B. Immediately notify the Shift Superintendent.

QUESTION: 20 QlD: 0040 Point: 1.00 B. Changing a tolerance to an operating parameter.

QUESTION: 21 QlD: 0042 Point: 1.00 A. Cannot drop below the minimum due to a relief being absent. Remain on watch until relieved.

QUESTION: 22 QlD: 0043 Point: 1.00 C. 1440.

QUESTION: 23 QlD: 0044 Point: 1.00 [] A.1 hour.

QUESTION: 24 QlD: 0045 Point: 1.00 C. Perfom every 15 minutes.

QUESTION: 25 QlD: 0046 Point: 1.00 D. Install locking pins for MSIVs.

, QUESTION: 26 QlD: 0049 Point: 1.00 l l D. RCS Tave.

QUESTION: 27 QlD: 0052 Point: 1.00 B. Indicated level will be HIGHER than actual level because the reference leg fluid density l decreases.

QUESTION: 28 QlD: 0056 Point: 1.00 A. High Log Power Trip.

QUESTION: 29 QlD: 0061 Point: 1.00 C. 2RITS-8916,404 Spent Fuel Pool General Area monitor.

QUESTION: 30 QlD: 0066 Point: 1.00 , , A. A spent fuel assembly is damaged while being withdrawn from the core.

Page 2

. -. _. _.... ... _ _ _ _ _. ._ ____m - _ _ _ _ _ _. _ _.. _ _.... _ _..____ __ _ L ANO UNIT 2 - SRO EXAM ANSWER KEY j QUESTION: 31 QlD: 0067 Point: 1.00 D.120 minutes.

QUESTION: 32 QlD: 0069 Point: 1.00 C. Main Foodwater and Emergency Feedwater to "A" Steam Generator is secured.

QUESTION: 33 QlD: 0070 Point: 1.00 D. Restore power to Component Cooling Water Pump 2P33C and 480V MCCs.

QUESTION: 34 QlD: 0071 Point: 1.00 B. To prevent steam formation in the Reactor Vessel head from pressurtzin0 the RCS, leading to , core uncovery.

j QUESTION: 35 QlD: 0072 Point: 1.00 A. Start an allemale charging pump after verifying its suction path.

QUESTION: 36 QlD: 0077 Point: 1.00 A. Safety Parameter Display System (SPDS) point P4624-2.

QUESTION: 37 QlD: 0078 Point: 1.00 A. Making preliminary reportability venfication.

QUESTION: 38 QlD: 0079 Point: 1.00 ~ A. Breakers 1 and 5.

QUESTION: 39 Q!D: 0061 Point: 1.00 l S. Maintain spbcooling margin between 30F and 200F.

! QUESTION: 40 QlD: 0084 Point: 1.00 , 8. RCP seal cooler heater exchanger, j QUESTION: 41 QlD: 0089 Point: 1.00 D. Uponder is completely horizontal.

QUESTION: 42 QlD: 0092 Point: 1.00 C. Perform an independent verification of proper Unit 1 Circ Water Flow.

QUESTION: 43 QlD: 0093 Point: 1.00 B. Reactive load increases and KW increases.

QUESTION: 44 QlD: 0094 Point: 1.00 l A. Breakers will remain in their "as is" condition and operation would only be possible by local manual means.

' QUESTION: 45 QlD: 0095 Point: 1.00

B. Inverter input is auctioneered between the rectifier output and a DC Battery Bus supply.

! ! Page 3

. .. . - _.. -.. ... - - -...---. - ~ _. -.. - _.. -.. -. -.. -... - _.. - - l ANO UNIT 2 - SRO EXAM ANSWER KEY QUESTION: 46 QlD: 0096 Point: 1.00 A. An uncontrolled cool down of the RCS, resulting in less shutdown margin.

j QUESTION: 47 QlD: 0097 Point: 1.00 D; Roset the Steam Generator low pressure trip setpoints QUESTION: 46 QlD: 0099 Point.' 1.00 l B. By otr:aving a trip light without the associated protrip light.

QUESTION: 49 QlD: 0103 Point: 1.00 D. Between 275 and 270 degrees F RCS Temperature.

QUESTION: 50 QlD: 0104 Point: 1.00 D. SG "A" Level = 5% NR & Press = 500 pois SG "B" Level = 10% NR & Press = 370 pela.

QUESTION: 51 QlD: 0105 Point: 1.00 D. Main Foodwater Leak in Containment.

QUESTION: 52 QlD: 0107 Point: 1.00

C. 590 degrees Farenhei0ht with RCS Pressure equal to 1350 psia.

QUESTION: 53 QlD: 0110 Point: 1.00-D.CSAS QUESTION: 54 QlD: 0111 Point: 1.00 B. The selected Pressurizer Level Control Channel has failed high.

QUESTION: 55 QlD: 0114 Point: 1.00 D. To limit core uplift.

QUESTION: 56 QlD: 0115 Point: 1.00 C. Upper seal.

QUESTION: 57 QlD: 0121 Point: 1.00 D. Suspend core alterations until the inoperable channel is retumed to operable status.

QUESTION: 58 QlD: 0123 Point: 1.00 C. one week.

QUESTION: 59 QlD: 0124 Point: 1.00 l D. a person working on safety-related system or component.

QUESTION: 60 QlD: 0125 Point: 1.00 8. 5 hours, l QUESTION: 61 QlD: 0127 Point: 1.00 ! l D. High Linear Power, High Local Power Density and Low DNBR trips and pretrips.

Page 4 I . ,_

_.

. _ _ _ _. -. __ _ __ _.

O ANO UNIT 2 -SRO EXAM ANSWER KEY QUESTION: 62 QlD: 0128 Point: 1.00 B.1200 on 11/13.

QUESTION: 63 QlD: 0131 Point: 1.00 A. Ensures RCS heat removal throu0h the steam generators.

QUESTION: 64 QlD: 0134 Point: 1.00 C. Be in Hot Standby with RCS Pressure within its limit within one (1) hour.

QUESTION: 65 QlD: 0135 Point: 1.00 D. 50%

QUESTION: 66 QlD: 0136 Point: 1.00 B. Be in at least HOT STANDBY with T ave less than 500 degrees F within 6 hours.

QUESTION: 67 QlD: 0138 Point: 1.00 A. RCP Vapor Seal Leakoff.

QUESTION: 68 QlD: 0140 Point: 1.00 C. Reactor critical and CEAs inserted below the Transient insertion Limits.

QUESTION: 69 QlD: 0141 Point: 1.00 D. Voiding in the Reactor Vessel Head area.

V QUESTION: 70 QlD: 0146 Point: 1.00 B. mir#mize the effects of Xenon redistribution.

QUESTION: 71 QlD: 0149 Point: 1.00 A. provide long term post-accident core cooling.

QUESTION: 72 QlD: 0153 Point: 1.00 D. Initiate Emergency Boration.

^ QUESTION: 91 QlD: 0154 Point: 1.00 l A. Lower RCS pressure and emergency borate via HPSI.

QUESTION: 74 QlD: 0156 Point: 1.00 D. Start HPSI Pumps 2P898 and 2P89C and fully open all HPSI Injection valves.

QUESTION: 75 QlD: 0157 Point: 1.00 B. Bypres valves and one ADV receive " quick open" then modulate to control main steam pressure.

QUESTION: 76 QlD: 0160 Point: 1.00 B. SDC heat removalis lost.

OV Page5 i i ! i

. - - . _ . _ _ -. - - _. _ -.. . _ _. - ._ __ - - - ! l ,e ANO UNIT 2 - SRO EXAM ANSWER KEY QUESTION: 77 QlD: 0161 Point: 1.00 ' l C. Manually actuate CIAS.

QUESTION: 78 QlD: 0164 Point: 1.00 B. 300 degrees F.

QUESTION: 79 QlD: 0167 Point: 1.00 l B. Phase Differential.

QUESTION: 80 QlD: 0168 Point: 1.00 C. 2P7A will overspeed.

QUESTION: 81 QlD: 0169 Point: 1.00 D. The Loop I and Loop ll Cmssover valves will remain in the position they were in prior to 2P33A trip.

QUESTION: 82 QlD: 0170 Point: 1.00 C. RCS temperature and pressure increasing even with SDBCS valves and main spray valves

opening.

j QUESTION: 83 QlD: 0173 Point: 1.00 D. Prevent exhaust hood temperature from exceeding 200F.

QUESTION: 84 QlD: 0174 Point: 1.00 A. Exemise valve (2HS-1011 and 2HS-1061) green light to illuminate.

' QUESTION: 85 QlD: 0175 Point: 1.00 D. Radiation levels willincrease.

QUESTION: 86 QlD: 0176 Point: 1.00 B. Place Purge Exhaust Fan,2VEF-15,in HAND then secure Purge Supply Fan,2VSF-2.

QUESTION: 87 QlD: 0179 Point: 1.00 B. Condensate Pump 2P2D will auto start.

QUESTION: 88 QlD: 0180 Point: 1.00 C. Align SW and RCS to 2E358 and isolate SW and RCS to 2E35A.

QUESTION: 89 QlD: 0181 Point: 1.00 A. Limit flow velocities.

QUESTION: 90 QlD: 0182 Point: 1.00 A. Half Leg Trip.

QUESTION: 73 QlD: 0183 Point: 1.00 D. EOL Core.

l ' OQ Page 6

.-. . -. . ._.- ,. ._ .. ._ - -. -. .- ..... _. ANO UNIT 2 - SRO EXAM ANSWER KEY O.

QUESTION: 92 QlD: 0184 Point: 1.00 C. Move fuel assembly to Spent Fuel Pool.

QUESTlON:, 93 QlD: 0185 Point: 1.00 A. Open ECCS vents (2CV498-1 and 2CV-4740-2).

QUESTION: 94 QlD: 0188 Point: 1.00 B. Use upstream MOVs (2CV-1002 and 2CV-1052).

QUESTION: 95 QlD: 0187 Point: 1.00 D. Close cmsstie valves 2CV-3004 and 2CV-3015.

QUESTION: 98 QlD: 0188 Point: 1.00 A. Stop depressurization until RVLMS level 1 indicates wet QUESTION: 97 QlD: 0189 Point: 1.00 C. Declare an Alert and perform a Plant Evacuation.

QUESTION: 98 QlD: 0190 Point: 1.00 B. To minimize RCS Break flow.

QUESTION: 99 QlD: 0192 Point: 1.00 D. CEAC #1 Sensor Failure.

QUESTION: 100 QlD: 0193 Point: 1.00 A. Trip all MFW and Condensate pumps and close all FW block valves.

. , l

. ! Pa0e7 l }}

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