ML20210K747

Informs That Util Reviewed SRO Licensing Exam Administered by NRC at Plant on 970414.Util Comment on Exam,According to Requirements Specified in Operator Licensing Examiners Std Encl

ML20210K747
Person / Time
Site:	Fort Calhoun
Issue date:	05/07/1997
From:	Gates W OMAHA PUBLIC POWER DISTRICT
To:	Pellet J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20210K753	List: ML20210K747 ML20217M052
References
FC-T-009-97, FC-T-9-97, NUDOCS 9708200073
Download: ML20210K747 (107)

Text

euppo Omatu Pubhc Power Destnct 444 South 16th Street Mall Otnah3 M 68102 2247 May 7,1997

' (FC-T-009 97)

Mr. John L. Pellet Chief, Operations Licensing Section .

U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plata Drive, Suite 1000 Arlington,TX 76011

Reference:

Docket No. 50 285

SUBJECT:

Technical Review of the Senior Reactor Operator Licensing Examination Omaha Public Power District (OPPD) has reviewed the Senior Reactor Operator licensing examination administered by the NRC at Fod Calhoun Station on April 14,1997. Enclosed is OPPD's comment on the examination, according to the requirements speciGed in the Operator Licensing Examir.ers Standant, NIJREG 1021. These comments were provided to your examiners on April 17,1997.

If you should have any questions, please contact me.

Sjacopt A% w ,

\ '. bary Gates ice President - Nuclear WGG:mkm Enclosure .

e: R. G. Conner 9700200073 970014 PDR ADOCK 05000285 V POR 45 5174 Employment eth EqwloppocMy

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OPPD COMMENT SRO Examination

. Question 11:

llow wi!! the CVCS system automatically respond to high level in the VCT due to a sustained 20 gpm mismatch between letdown How and charging Dow?

A. Letdown will isolate and VCT level will stabilire.

B. Letdown will isolate but VCT level will continue to increase.

C. Letdown will divert to waste and VCT level will stabilize.

"Il Letdown will divert to waste but VCT level will continue to increase.

Question: 11 Answer: D

Reference:

LP 07-11-02 Facility Comment / Recommendation:

As currently written, Question 11 does not possess a correct answer.

It is recommended that the question be deleted from the exam.

Facility Justification:

Normally, Charging Pump suction is from the Volume Control Tank (VCT). At a high level of 94.4%, VCT Inlet valve, LCV-218-1, repositions to divert letdown to waste.

Charging Pump suction is not affected by the letdown diversion and continues to remain on the VCT. In such a case, VCT level would lower as Charging Pump suction would continue to use the VCT as its source.

To choose the desired response, D, the student would have to make the assumption that Charging Pump suction is from the Safety Injection Refueling Water Tank. This assumption, however, would be in conflict with nomial system lineup. The question does not provide any information that would lead the student to the conclusion that the system lineup is anything but normal.

None of the other responses would be a correct attemative, because under the normal alignment, VCT level would decrease. Therefore, no correct response is provided for the

students to choose from, a-,

/cY W Form ES-401 ES-401 -Site-specific Written Examination Cover Sheet U. S. NUCLEAR REGULATORY COMMISSION SITE SPECIFIC WRITTEN EXAMINATION APPLICANT INFORMATION Name: Region: I/II'/III/h/V Date:

/ 77 Facility / Unit:

7 g License level: R0 / Reactor Type:

RO) W/h/BW/GE INSTRUCTIONS Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires a final grade of at least 80 percent. Examination papers will be picked up 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the examination starts.

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

Applicant's Signature RESULTS Examination Value 9i Points Applicant's Score Points Applicant's Grade Percent Examiner Standards 6 of 7 Rev. 7, January 1993

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4 D 5 C 6 A 7 -B H C 9 A

-10 A Deleted 12 D 11- A 14 C 15 C 16 D 17- D IM D 19 D 20 D t.

21 A 22 A 23 D j 24 C 25 11 26 B 27 C 1

itort Callioun - SRO Exam Key (Juntlem,_ Anmyr 28 D-29 C 30 D 3' A 32 A 31 A 34 0 35 B 36 11 37 A 38- A 39 A 40 A 41 C 42 Il 43 C 44 B 45 A 46 D 47 11 48 D 49 0 50 A 51 A 52 D 53 A 54 D

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Fort Calhoun - SRO Euim Key

@8tition. Answyr 55- B 56 Il 57 11

$M /.

$9 D 60 C 01 D 62 f3 61 C 9

64 C 65 A 66 D 67 C 6M . Il 69 C 70 D 1

71 A 72 11 73 A 74 11 75- D 76 D 77 11 78 - D 79 11 80 C 81 C 3

e Fort Calhoun - SRO Exam Key

. Quc3tion Antwer M2 D M3 D M4 C X$ -C M6 11 M7 D MH D M9 0 90 C 91- D 92 D 93 D 94 C 95 B 96 D 97 D 98 C 99 C l(M) D

p F6rt Calhoun - SRO Written Exam nundon: 1-The reactor trips from a normal full power condition. Following the trip,-all- !

fast transfer to 161 KV falls. What combination or reactor coolant pumps ,

-would continue to operate in this situation?

A.- RC-3A and RC-3B -

B. -- RC-3A and RC-3C C. RC-3C and RC-3D-  !

- D. RC-38 and RC-3D -

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.x Fort Calhoun ~- SRO Written Exam

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. Questlon: ' 2 -

A reading of 300*F on the discharge piping of an idle AFW pump is an indication of which one of.the following7; A The. pump is properly warmed up for rapid start.

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.B. :The pump may be steam bound.

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• - C. The pump discharge valve is open, o . D. AFW turbine steam seals are leaking.

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Fort Calhoun - SRO. Written Exam i

Question:- 3- ,

Within 15 minutes following a station blackout, DC loads.were minimized in accordance with EOP attachments. The following breakers were placed in "OFF"' ,

• EE-8G-CB12, ~400 CYCLE INVERTER EE-21" EE-BG-C98, " EMERGENCY LIGHTING PNL ELP 2 TRANSFER SWITCH"

• - EE-8F CB11. " EMERGENCY LIGHTING PNL ELP-1 TRANSFER SWITCH"

• -- BKR 15 EMERG. LIGHTING PANEL NO. 5 (DC-PNL-1 125 VDC PANEL) .

Which one'of the following instruments will not provide indication in this condition?

Al Emergency Feedwater Storage Tank Level.

B. Primary Rod Position Indication.

C. Pressurizer Steam Space Temperature.

D. Volume Control Tank Pressure.

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4 Fort Calhoun - SRO Written Exam -. ,

Jucationi: -41

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r The reactor is operating at 100% power during the middle'of an operating cycle when power is lost to all 41_60 V buses. Which one of the following statements is 4

,  : true concerning the response of the CEDMs?

A: T he CEDMs will fall immediately due to a loss of power to the clutches.

B.- The CEDMs will not fall until a variable overpower trio signalis generated and

- power to the clutches is interrupted.

C. The CEDMs will not fall until a low steam generator pressure trip signal is generated -

and power to the clutches is interrupted:

D. : The CEDMs will not fall until a low reactor coolant system flow trip signal is generated and power.to the clutches is interrupted.

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+ Fort Calhoun - SRO Written Exam

- Queuinn: With the plant in hot shutdown, the-Shrft. Technical Advisor slipped on a stairway-and injured his ankle. An off-duty Shift Supervisor leaving the site has taken him to the emergency room; Which one of the following actions should be taken due to this event?

A. - Make a four hour report to the NRC.

B. Have a System Engineer who is training to be an STA fill the position.

C Have a qualified STA on site within two hours.

D. Declare a Notification of Unusual Event based on transport of an injured person.

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Fort Calhoun - SRO Written Exam l

Question: -L6 - t i

- Under which one of the following conditions is it acceptable to release a waste gas decay tank with RM-052 and RM-062 inoperable? -

- A. Grab samples are taken prior to and during the release.

B. ; RM-057 is operable and condenser offgas and the gas decay tank are both lined up-to the hydrogen purge filters.

. C. LThe Waste gas decay tank being released has been isolated and all of it's contents -

allowed to decay for 30 days.

D. It is not acceptable to release a waste gas decay tank with both RM-052 and RM-062 inoperable, N

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i Quenn: .. :7

' .rl During solid plant operation, PT-115 fails such that it provides a high indication. How

- will operation of the LTOP system be affected?

A? One PORV wdl open immediately following the instrument failure and remain open..

.: BJ .: Both PORVs will open immediately following the instrument failure and remain open. -

Cl - One PORV will open immediately following the instrument failure but will reclose .

when system pressure drops.

D. Both PORVs will open immediately fol'owing the instrumeit failure but will reciose i

- when system pressure drops, s

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The bistables for channel "A" trip units 1, 9 and 12 have been placed in the

" tripped" condition None of the trips are bypassed Which one of thefollow ing instrunnent failures wi!! result in a reactor trip? -

AU ' "A" channel NIS power range input to RPS fails high. j B. "B" channel pressurizer pressure input to'the RCS fails high.

- C. "C"_ channel cold leg temperature input to the RPS fails low,'

D. *D". channel RCS flow input to the RPS fails low.

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l*' ort Calhoun - SRO Written Euim Question: 9 What is the INITIAL offect that a loss of detector well cooling will have on operation of the nuclear instrumentation systems during power operation?

A. Power Rango indication will become erratic.

B. Startup Rato indication will becomo erratic.

C. The Sourco Range indication will drift low.

D. The Wide Range indication will dnft high.

9

Fort Calhoun - Sl(O Written Exain Quotion: 10 Which one of the following conditions will result in isolation of component cooling water to the reactor coolant pumps?

A. CIAS and low component cooling water pressure.

B. CIAS and high component cooling water radiation lovels.

C. CRHS and lov component cooling water pressure.

D. CRHS and high component cooling water rcdiation levels.

10 i

Fort Calhoun - SRO Written Exam QVtSiiol) DelCfec]

we.ia : n How will CVCS system automatically re d to high level in the VCT due to a sustained 2 pm mismatch between I wn flow and charging flow ?

A. Letdown williso e and VCJ vel will stabilize.

/

D. Letdown willisolatt t VCT level will continue to increase,

/

C. Letdown w(divert to wa and VCT level will stabilize.

D. will divert to waste b VCT level will continue to increase.

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Fort Calhoun - SRO Written Euim Ountion: 12 While tounng the turbine building during an outage, you observe an unconscious person 3 feet inside the upper manway of the main condenser. What action should you take af ter notifying the control room? -

A. Pull the person out and give mouth to mouth rocositation.

B. Locate an SCBA, Don it and pull the person out.

C. Leave the area, toxic gas may be present.

D. Standby to direct rescue tearn to location of person.

I:

Fort Calhoun - SitO Written Exain Question: 13 During a reactor startup, the brake on one of regulating group 2 CEAs fails to release preventing motion of the CEA. The CEAs are being withdrawn in the manual sequential mode. The stuck CEA is not selected as the target CEA in the group. When will a SCEAPIS rod block signal be generated?

A.' When any CEA in group 2 is withdrawn 8 inches above the stuck CEA.

B. When any CEA in group 2 is withdrawn 18 inches above the stuck CEA.

C. When any CEA in group 1 reaches the upper rod stop.

D. When any CEA in group 3 begins to withdraw. ,

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Fort Calhoun - SitO Written Exam (Juention: 14 Which one of the following area radiation monitors provides indication on the Qualified Safety Parameter Display System Computer.

A. RM-073 B. RM-085 C. RM-091A D. RM497 14

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.t Fort Calhoun - SRO Written Exam  !

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Which one of the following statements is true concerning the Containment Pressure

.High Signal (CPHS) lockout relays 7 A. They normally reset automatically and only require manual reset after a loss of ,

voltage. l i

' B. They allow manual reset so that containment spray act.!ation can be overridden l with a CPHS signal present. l

C. They allow manual reset of the CPHS signal after containment pressure drops below the CPHS setpoint. t i

D.' They allow manual reset of the CPHS so that containment spray pumps can be ,

restarted following RAS.

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Fort Calhoun - SRO Written Exam Questiont 16 Which one of the following instrumentation failures would cause steam generator  :

level to rise with the main feedwater regulating valves closed and the bypass valves in automatic control?

A. Steam flow instrument fails high.

B. Steam Generator pressure instrument falls high.

C. Feedwater flow instrument fails low.

D, Steam Generator levelinstrument fai!s low.

16

l' art Calhoun - SRO Written Exam Question; 17 Which one of the following conditions will cause the containment cooler inlet and outlet valves to close following receipt of a CIAS signal?

A. CCW pump discharge pressure is less than 40 psig.

B. A containment presure high signal (CPHS)is not present.

C. The fan associated with the containment cooling unit failed to start.

D. There is low CCW flow from the cooler outlet.

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Fort Calhoun - SRO Written Euim Quniion: la 1

OPPD Electnc Operations Division (EOD) personnel have notified you, the Shift Supervisor, that they will be entenng the swithyard with a company vehicle to perform prescheduled activities. W1at action should you take per NOD-OP 36,

" Control of Switchyard Activities at Fort Calhoun Station?

A. Inform the EOD personnel that vehicles are not allowed inside the FCS switchyard when the unit is operating.

D Contact the Secunty Shift Supervisor to provide a Secunty Escort for the EOD personnel while they are in the switchyard.

C. Have the EOD personnel contact the Plant Manager or Duty Supervisor for permission to enter the switchyard.

D. Notify the Production Operations Division System Operator when personnel are inside the switchyard.

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Fort Calhoun SRO Written iham

- Quosion: 19 All CEAs are fully inserted and preparations are being made to perform a reactor startup by CEA withdrawal. According to the Estimated Critical Condition calculation, the boron concentration shoulo be reduced by 250 ppm prior to the startup. According to OP 2A, which one of the following sequences of steps is

- acceptable?

A Withdraw the non tnppable CEAs, dilute to the ECC boron concentration, withdraw the shutdown CEAs, withdraw the regulating CEAs, B. Dilute to the ECC boron concentration, withdraw the shutdown CEAs, with draw the non trippable CEAs, withdraw the regulating CEAs.

C. Withdraw the shutdown CEAs, withdraw the non trippable CEAs, withdraw the regulating CEAs, dilute to the ECC boron concentration.

D.- Withdraw the shutdown CEAs, dilute to the ECC boron concentration, withedraw the non-trippable CEAs, withdraw the regulating CEAs.

19

Fort Calhoun - S110 Written Exam Question! 70 What is the basis for the technical specification operability requirements for the core exit thermoucouples (CETs)?

A. To monitor core peaking factors dunng power operation.

B. To adjust the Thermal Margin / Low Pressure trip setpoint.

C To calibrate the reactor vessellevel monitoring system.

D. To monitor for inadequato core cooling.

20

Fort Calhoun - Sl(O Written Euini Quntion: 21 White conducting rounds, the EONT iniorms you of the following conditions:

. The voltmeters on EE-22 indicate 30 and 90 VAC.

. Both hghts on EE 22 are dimly lit:

What would you conclude from these indications?

A. A ground is developing in the rod drive ctreuits.

B. A ground is developing in the core mimic bus.

C. A ground is developing which affects both the rod drive circuits and the core mimic bus.

D. These are normalindications for power operations.

C

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- Fort Calhoun - SRO Written Exam i

i Quotiem: 22  :

An alarm on effluent radiation monitor / RM 055, will cause which one of the ,

t following to happen?

2 r A. HCV491 and HCV-692 (overboard discharge control valves) will close and the  ;

monitor tank pumps will trip. [

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. B. HCV472 and HCV 678 (monitor tank inlet valves) will close and the monitor tank l

- pumps will trip.  ;

C. IlCV491 and HCV-692 (overboard' discharge control valves) will close and the j f

monitor tank pumps will continue to operate.

D. HCV472 and HCV-678 (monitor tank Inlet valves) will close and the monitor tank '

, pumps will continue to operate; [

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i Fort Callioun - Sl(O Written Euim (Juntion: 21 i

RVLMS must be 43% or greater pnor to performing HPSI stop and throttle during a LOCA. Maintaining RVLMS 43% or greater assures that:

A. . any steam void in the reactor vessel head will not be largo enough to cause a significant increase in pressunzer love!,

B. the core exit thermocouple are covered with water and will respond proper 1y.

C. the reactor vessellevelis above the entical vessel welds reducing the likelihood of Pressurized Thermal Shock D. The hot logs are covered providing sufficient inventory to support natural circulation if the S/G's are providing a heat sink.

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Fort Calhoun - SRO Written Esam Qantion: 24 AC 3A has been tagged out for repairs. A Temporary /Tosting Release was done to allow testing. Following the testing, it was determined that additional repairs were required. Identify the propor sequence for removing the Temporary / Testing Roloaso.

A. Removo the Temporarytrosting Release tags, independently verify equipment positions, and rehang the Danger tags.

B. Remove the Tempora:y/ Testing Release tags and rehang the Danger tags.

C. Remove the Temporaryffesting Release tags, reposition equipment as necessary, Rehang Danger tags, and Independently venfy equipment positions.

D. Reposition equipment as necessary, Rohang Danger tags, independently verify equipment positions, and Remove the Temporary / Testing Release tags.

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y Fort Calhoun - SRO Written Exam own6on: :23 A Safety injection Actuation Signal (SIAS) actuation occurs following a loss of coolant accident. 30 minutes into the accident, the water level in the Safety injection and Refueling Water Tank (SIRWT) lowers to the SIRWT Tank Low Signal (STLS) setpoint. Assuming all systems operate as designed, which of the following valves will close.

A. The LPSI injection valves, HCV 327,329,331,333.

B. The SIRWT recirculation valves, HCV 335,386 C. The SIT loop isolation valves, HCV 2914, 2934, 2954, 2974.

D. The containment spray header discharge valves, HCV 344,345.

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Fort Callinun - Sito Written Euirn QLarsfiert: 2(#

The plant experienced a loss of all ofisite power. D/G #1 started normally but D/G #

2 fr.lled to start. Assuming that no action is taken to cross tie busses, what is the maximum evailable charging flow capccity in this condition?

A. 0 Opm B. 40 gpm C. 80 gpm.

D. 120 gpm.

6

Fort Calhoun SRO Written Esam Quntion: 27 Which of the following is true regarding the Diverse Scram System upon a loss of the 120 VAC poVver supply to either Al.196 or Al 1987 A. To bypass the failed channel, you must place the TEST / BYPASS switch on the affected panel to the bypass position.

B. To bypass the failed channel, you must place the TEST / BYPASS switches on both panels to the bypass position.

C. It is not possible to bypass a single sensor channel on loss of 120 VAC power.

D. It is not required to bypass a channel upon loss of the 120 VAC power because the DSS requires power to generate a trip signal. ,

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Fort Calhoun - SRO Written Eum Quotion: n if one turbine stop valve and one turbine control valve remain open following a reactor inp/ turbine inp, which one of the following automatic actions will be delayed A. Closure of the combined-intermediate valves.

B. Ramp down of the feedwater regulating valves.

C. Loss of load tnp generation by the RPS.

D. Opening of breakers 34514 and 34515.

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I Fort Calhoun - SRO Written Exam i

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Que.iion: :9 i

Which one of the following desenbes the response of the steam dump and bypass valves to an unccmplicated reactor trip if PT 010 fails such that it indicates "O psig?  ;

Assume all systems are in automatic.

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A. All steam dump and bypass valves will open. RCS average temperature will be restored to and maintained between 530*F and 535'F.

B. Only the steam dump valves (TCV 909-14) will open. RCS average temperature will be restored to and maintained between 530*F and 535'F.

C. All steam dump and bypass valves will open. RCS average temperature will be resored to and maintained between 535'F and 540*F, D. Only the steam dump valves (TCV-9091-4) will open. RCS average temperature will be resored to and maintained between 535'F and 540*F. 5

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Fort Callioun - SRO Written E. sam Quntion: in What is the purpose of the mini purge fans in the containment purgo system?

A. To provide reduced flow operation of the containment purge system dunng power operations.

B. To provido direct purge of the containment area inside the biological shield.

C. To allow operation of the containment purgo system during specific electrical bus outages.

D. To allow operation of the containment purge system while minimizing the potential for airbome contamination in containment, i

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mee.skm: 31 I

A fire has been discovered in the drum storage area of the radweste building. All  !

personnel have been evacuated. The Blair fire department has been requested to 4 respond to help fight the fire,  :

l What parsonnel should make up the fire brigade responding to the fire?  ;

- A. LO*, EONA, EONT, Security (2), and RP Tech. j B. LSO, LO*, EONA, Security (2), and Shift Chemist. j!

C. LO*, EONA, AON, and Secunty(2),  :

1 D. LO*, EONA, EONT, and Secunty(3). .

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Fort Callioun - Sl(O Written Euini ouniton: n Makeup to the spent fuel pool for normal evaporative losses is:

A. From the SIRWT via the Fuel Transfer Canal Drain Pumps.

O, From the SIRWT via tne Reactor Coolant Drain Tank Pump.

C, From the CVCS using the Bonc Acid Pumps, Domin Water Pumps and the blending tee.

D. From the Safety injection System via the LPSI pumps.

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Fort Calhoun - SRO Written Exani nunilon: n Hydrogen concentration within containment was found to be 2.6%, four hours after a small break loss of coolant accident with sustained core uncovery. Which one of the following was responsib!e for production of the majority of the hydrogen?

A. The Zircalloy Water reaction.

B. Corrosion of aluminum.

C. Radiofysis.

D. De gassing of the RCS coolant.

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. v Fort Calhoun - SRO Writtra Exam . i 7

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t During refueling, a fuel bundle has been remove 1 from the core and the fuel hoist box on FH.1 has been retumed to its up limit. What action must be takc.n to enable  ;

l the bridge and trolley to be moved? i i

k A. The empty hoist bypass switch must be tumed to OFF. .

B. The bridge trolley lockout pushbutton must be depressed. l 1

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Ci The mast bump ovemde button must be depressed.

D. The mast detent switch must be placed in DISENGAGE.

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Fort Calhoun SRO Written Exam )

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Quotiono 3.4 l i

Followines detection of a high chlorine concentration by the detectors in the control '

toom ventilation system, which of the following statements is true?

A. The control room ventilation system will isolate. Air conditioning units will continue to operate.

l B. The control room ventilation system will isolate, The air conditioning units will trip - j and can not be restarted unless the chlorine signal is overridden.

C. The control room ventilation system will go into the " Filtered Air" mode of 1

- operation. Air conditioning units will continue to operate. .

D. The control room ventilation system will go into the " Filtered Air" mode of i operation. The air conditioning units will trip and can not be restarted unless the -t chlorine signalis overridden. ,

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Fort Calhoun - SitO Written Exam Quntion: %

Assuming all fast transfer permissives are made up, which of the following will result in a fast bus transfer of Bus 1 A3 from the 161KV to the 22 KV source?

A. OPLS lock-out relay actuation.

B. Manualinp of the 69 switch on breaker 1 A33.

C. Overcurrent lockout of breaker 1A33.

D. Undervoltage on bus 1A3.

36

Fort Calhoun - SitO Written Exam Question: 17 Which one of the following conditions is addresed by AOP-32, " LOSS OF 4160 VOLT OR 480 VOLT BUS POWER'?

, A. Loss of MCC-4A2.

B. Loss of instrument bus #1.

C. Loss of busses 1A3 and 1A4.

D. Loss of DC bus #2.

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Fort Calhoun - SRO Written Exam ouestion:: n a-The reactor is operating at 6% power during a plant startup Turturn speed is 1500 -

• rpm and increasing when an inadvertant turbine trip occurs. "% re setor does not .;

trip.~ What is the expected response of the D/G's to this. event?

'A. The D/G's will remain shutdown.

- B; The D/G's will start and come to idle speed.

C. The D/G's will start and go to full speed. The D/G breaker will close.

D. The D/G's will start and go to full speed. The D/G breaker will not close.

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Fort Calhoun - SRO Written Exam Question: 39 Which one of the following sets of heat stress symptoms is indicatve of heat stroke?

A. Dry skin and small pupils B. Heavy sweating and thirst C. Headache and cool skin D. Nausea and dilated pupils 39

' Fort Calhoun - SRO Written Exam l Question: :f 40 What is the purpose of waiting a minimum of_72 hours prior to initiating fuel -

movement after a shutdown from a power level greater than 2%7

- A.- It allows time for the decay of short lived fission products and allows for any failed fuel to purge itself.-

8, 'It allows time for the containment ventilation system to clean up the containment atmosphere to prevent a release in excess of technical specification limits C. It allows time for the containment purge system to reduce activity in containment to

-levels required for habitability.

Dc 11 allows time to cooldown and depressurize the RCS to assure no steam will be formed and minimizes the potential for a containment pressure buildup should a RCS rupture occur.

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Fort Calhoun". SRO Written Exam -

- (A cation: 41-

'A fire has been discovered in the main transformer, T-1. What would be the correct sequence for automatic starting of the fire pumpfe)?

- Assume the fire protection system is fully operable.

._ A. Deluge valve . opening would cause only the electric fire pump to start on low system pressure.

B. Deluge valve opening would cause both fire pumps to start on low system pressure.

C. Actuation of the T-1 deluge system will generate a direct start signal to both fire pumps.-

D. A T 1 fire will not result in automatic starting of the fire pumps until the pull stations are operated in the service building.

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L Fort Calhoun - SRO Wfitten Exam.

- Question: - 42 1

With the unit operating at 100% power, the_following parameters were observed: i e ~ VCT levelis lowenng ,

. - CCW surge tank level and pressure are rising 1

e. RM-053 countrate is rising 4 Which one of the following could produce these indications?

. A.- A tube leak in one of the CCW heat exchangers.

2 B. A leak in one of the RCP seal coolers.

C, A tube leak in the spent fuel pool heat exchanger.

D. A coil leak in one of the containment cooling and filtering units. >

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. Which one of the following is a responsibility of the OCC LSOs according to_.OPD- l 4-167:

-!- A; Schedule and review all surveillence tests.-

B. - Attend all ALARA briefings for scheduled work.

C. Perform the weekly tagout audit.

10. Approve all temporary procedure changes,- ,

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- The plant is at 100% power when during maintenance activities a containment electrical penetration is damaged to the point that noticeable air is leaking from it.

What action should be taken in accordance with AOP 12. " Loss of Containment - -

Integrity"?:

A. Perform an emergency shutdown using AOP-05.

- B. Terminate any positive reactivity changes and allow reactor power to coast while repairs can be initiated. ,

- C, Initiate a containment pressure reduction to decrease the pressure differential ,

across the penetration.

D. Ensure all containment cooling and filtering units are in operation to provide maximum filtration of the containment atmosphere.

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Fort Calhoun - SRO Written Exam i .

Question: 1 45 .}

t l Which one of the'following functions will occur because of a CIAS?

A. Containment air cooling coil (VA-8A) valves HCV-402A/8/C/D'open.

B. - RCP & CEDM cooler containment isolation valves HCV-438A/8/C/D open.

! C. I Detector well cooling containment isolation valves HCV-467A/B/C/D open.

' D; . Storage pool heat exchanger outlet valve HCV-478 opens.

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Fort Calhoun - SRO Written Exam

. Qmtion: 40 Dunng which one of the following conditions is the CCW heat load the greatest?

A. During full power operation.

B. While shutting down the reactor from 100% to 0% power.

C. While cooling down the RCS from 500 F to 400 F.

D. While cooling down the RCS from 300 F to 200 F.

46

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Fort Calhoun - SRO Written Exam l Question 47

. What effect will a total loss of instrument air header pressure have on SIRWT level indication? - ,

Assume that there is no actual change in SIRWT level and that the loss of pressure is  ;

of short enough duration that local air accumulators maintain pressure.

A. Low level will gol be indicated, low level alarms will Dol be received, STLS actuation will agj occur. ,

B. . Low level will be indicated, low level alarms will be received STLS actuation will aqt  ;

occur.

C? Low level will be indicated, low level alarms will Dol be received, STLS actuation will 1 Dot occur.'

.D. ; Low level will be indicated, low level alarms will be received, STLS actuation will occur.

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q Que War. 48:.

Technical Specification requirements for. operability of the raw water pumps, valves

. and piping are based on which one of the following?

LA/. RCS and CVCS cooling loads during shutdown to cold shutdown.

= B. RCS and CVCS cooling loads during accident conditions.

. C. Containment cooling loads during shutdown to cold shutdown.

4 D; Containment cooling loads during accident conditions.

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Fort Calhoun - SRO Written Exam Quntion: 49 Evaluate the information below for each safety injection tank and determine what action is required poor to taking the plant from mode 3 to mode 2.

LfVEL PRfiSEVEE SI-6A 67.2 % 245 psig SI-6B 69.5% 241 psig SI-6C 72.2 % 265 psig Sl4D 74.6 % 258 psig A. Raise the level in Sl4A.

B. Raise the pressure in SI-68.

C. Lower the pressure in SI-6C.

D. Lower the levelin SI-6D.

49

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Fort Calhoun - SRO Written Exam Quosion: 50 While operating at 100% power, a group 4 CEA dropped into the core. While stabilizing plant conditions, an instrument malfunction caused RCS pressure to - ,

decrease rapidly. When the plant was stabilized a review of the charts indicated that the following - coaditions existed at one point during the transient:

• ' Reactor power was 95%

• RCS pressure was 1750 psia

• RCS Le was 551*F

' Based on the parameters above, which of the f> wing actions shall be taken?'

A. The pf ant shall be placed in hot shutdown within one hour.

- B. Reactor power shall immediately be lowered to 90% and peaking factors evaluated.

C. Power shall be reduced to 70% within one hour to recover the dropped rod.

D. The reactor shall be tripped and RCS T,. should immediately be reduced to less than 510*F. ,

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Fort Calhoun - SitO Written Exam Quntion: $i With the reactor shutdown, puwer was lost to bus 1 A3. If bus 1 A3 remains deenergized, which one of the following statements concerning power supply to the charging pump VCT suction MOV (LCV-218-2) and the charging pump SIRWT suction MOV (LCV-218 3) is correct?

Asswne normal alignment of 480V breakers.

A. Power will not be available to either LCV-218 2 or LCV-218-3.

B. Power wili be available to LCV 218-2 but not to LCV-218-3.

C. Power will be available to LCV 218-3 but not to LCV-218-2.

D. Power will be available to both LCV 218-2 and LCV-218-3.

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I l Fort Calhoun - SRO Written Exam

- Quncioni is2 ,

The plant is in mode'4: Which one of the following will be designated by the use of ,

placards to ensure RCS makeup capability as a prerequisite for initiating shutdown cooling?

A. One LPSI pump with a backup power supply.

' B. One Boric Acid pump with a backup power supply.

_ C. One Charging pump with a backup power supply.

L D. One. Containment Spray pump with a backup power supply..  :

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Fort Calhoun - SRO Written Exam Quntion: 53 The technical specification limiting conditions for operation on RCS activity are based on the eaalysis of which one of the following accidents?

.A . Sieam generator tube rupture.

B. Reactor coolant pump siezed rotor.

C. Boron dilution accident.

D. Loss of coolant accident.

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53

Fort Calhoun - SRO Written Exam Quntion: 54 The reactor is being diluted to cnticality for the initial startup following a refueling outage. The source range count rate is 8 times the baseline count rate but a positive sustained startup rate has not been achieved. During this evolution CEA #1 falls into the core. Which one of the following directions should you give to the RO7 A. Terminate the boron dilution until the dropped CEA can be recovered.

B. Begin emergency boration.

C. Manually reinsert all trippable CEAs.

D. Manually inp the reactor.

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Fort Calhoun'- SRO Written Exam Question: E55

- What actions are taken to trip the reactor and turbir a dunng an AOP-06 control-room evacuation?

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JA. - Prior to evacuation, the reactor and the main generator are manually tripped. The turbine is tripped from the front standard.

B. Prior to' evacuation, the reactor is manually tripped and the clutch power supply.

t - _ breakers are opened. The turbine is tripped from the front standard.

i C.' Prior to evacuation, the reactor is manually tripped and the EHC pumps are placed in pull-out. .

-- D. Prior to evacuation, the reactor is manually tripped and the MSIVs and the MSIV  ;

bypass valves are closed.

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. Alarge break LOCA has occurred All safeguards components are operating as.

i required. The primary operator informs you that he has just received lo-lo level;

. alarms on both boric acid tanks.

SIAS actuated 26 minutes ago and the present SIRWT level is 52 inches. .

What action should you direct the primary RO to take?

f - A.--- Place two charging pumps in puff stop, open LCV 218-2, close LCV-218-3, close -

HCV's 265; 268_and 258. l

- - B. Place all charging pumps in pull stop, close HCV-238, 239,240, and 249, open HCV 247,248 and 308.

C. Close HCV's-265,258 and 268, open HCV-308 or HCV-2988.

- Dc Continue Emergency Boration until at least 30 minutes have elapsed.

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Fort Calhoun - SRO Written Exam Question: 57

-What is the purpose of closing the VCT outlet valve (LCV-218-2) during an ATWS event?

A. To prevent gas binding of the charging pumps.

B. To allow gravity feed from the boric acid tanks.

C. To prevent overpressurization of the VCT.

D. To prevent VCT low level from opening LCV ?.18-3.

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+  : Fort Calhoun - SRO. Written Exam L $

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. Questlon: ~ $X -- ~

. During a refueling outage, an individual working on the S/G tube inspection has -

- exceeded his _ stay tirne inside the S/G. After reading his TLD, it was found that he t

< received a dose equivalent of 26 rem.

.Which one of the following actions is required?

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A. Make a one hour notification to the NRC. .

f B. Make a four hour notification to the NRC.-

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C.- Make a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the NRC.

= 0. Declare a Notification of Unusual Event,-

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s 3)uestion: l59-

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lt is 1000 on Apnl 14,1997. A plant startup is in progress. Reactor power is 17%. .

. The tutt>ine generator was synchronized to the grid at 0940. Both ils6on chambers on the *D" wide range log channel and the power supply for the "B" wide rarge log -

channel have just failed. How will continued plant operation be affected if these

~

channels can not be repaired?  !

. A. : Power operations may continue indefinitely but reactor power must remain above

15%

- B. Power operations may continue indefinitely but reactor power must remain below 70%.

C. The reactor must be in hot shutdown by 1000 on April 16,l1997.

D. : The reactor must be in hot shutdown by 1000 on April 21,1997, t

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y I? ort Calh' oun - SRO. Written Exam i

Question: ra ,

With the plant oporating at 25% power, the " Inverter A trouble" alarm annunciated; Just prior to the alarn., the ERF indicated inveder "A" was at 117 volts and 25 amps.

Which one of the following combination of indications would confirm that Al-40A is being supplied by the bypass transformer?

A'. Inverter output voltage zero, inverter output current zero, instrument bus current zero.

B; Inverter output voltage zero, inverter output current 25 amps, instrument bus voltage 117 V,

. C. Inverter output voltage 117 V, inverter output current zero, instmment bus voltage 120 V.

D. Inverter output voltage 117 V, instrument bus voltage zero, instrument bus current zero.

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Fort Calhouit- SRO Written Exam -

t-c Question: P t

. A loss of offsite power occured with the plant in mode 3. The LSO noted the following' ,

conditions: .-i D/G 1'and D/G 2 will not start FW 54 is not available

- FW-10 is supplying 125 gpm to each S/G  :

EFWST levelis 100%

If the present rate of feed is to be maintaine for two hours and then be reduced to 25 gpm

- to each S/G, how much TOTAL time will it take to empty the EFWST7 A. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

- B. 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> C; 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> .

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

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Auestion: '; 62_

s Wnich one of the following conditions could result due to operating with a vacuum

- less than or equal to 23.85 inches Hg with reactor power less than 30%7 AdOverheating of the condenser bootL  :

B. Overheating the final stages of the' turbine blading.

'C LC,JOverpressurizing the condenser hotwell.

D. _ Inducing vibration problems in the turbine.

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4 Fort Calhoun - SRO Written Exam 4

.- (Junilon:- ra

. The plant is operating at 65% power and all systems are aligned for normal operation.

The "CCW Surge Tank Hi/ Low" alarm is received and the Auxiliary Building operator reports that he hears a loud rumbling noise from AC-3A. The primary RO reports fluctuating current and discharge pressure for AC 3A (The operating CCW pump) .

- The CCW surge tank level is 8 toches and decreasing.

Which one of the following actions should you direct the pnmary RO to perform in addition to the standard post tria actions once the reactor is tripped?

A; Altemately run one RCP at a tirje pntil cooling water is restored.

B. Establish raw water backup cooling to the RCP'S within 5 minutes.

C. Shutdown all RCP's within 5 minutes.

D. Trip one RCP in each loop initially. Trip the remaining RCP's when high temperature alarms are received.

b 63

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Fort Calhoun - SRO Written Exam - ,

Quotion: 64 Which one of the following operations is used to fill the main generator wth hydrogen followng a refueling outage?

Ai The generator is filled wth nitrogen through the bottom header as air is vented through the top header. Then hydrogen is introduced through the top header as nitrogen is vented from the bottom header.

- B. The generator is filled wth nitrogen through the bottom header as air is vented through the

. top header. Then hydrogen _is !ntroduced through the bottom header as nitrogen is vented 4 from the top header,- ,

C. The generator is filled with. carbon dioxide through the bottom header as air is vented .

through the top header. Then hydrogen is introduced through the top header as carbon dioxide is vented from the bottom header.

.D. The generator s filled with carbon dioxide through the bottom header as air is vented through the top header. Then hydrogen is introduced through the bottom header as carbon dioxide is vented from the top header, i

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I j The plant has been operating at 50% power for the last 10 days. A group *A" CEA I drops into the core. Tne teactor continues to operate. Which one of the ollowing i statements is correct concerning the Azimuthal Power Tilt factor (quadrant tilt) due  !

i to this event?  !

l A. The Azimuthal Power Tilt To , will rise immediately following the CEA drop and will l

continue to nse for several hours,

_D. - The Azimuthat Power Tilt. To , will rise immediately following the CEA drop and then }

willlou for several hours.  !

C, The Azimuthal Power Tilt, To , wiillower immediately following the CEA drop and will continue to lower for several hours. j o

D. The Azimuthal Power Tilt, To , willlower immediately following the CEA drop and j then will rise for several hours.

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Fort Calhoun - SRO Written Exarn 1

Question: 66 Of the following, v.hich response applies to the cooldown indicated on the attached chart?

A. All allowable RCS pressure / temperature combinations were met beteen 1100 1200.

B l.ow Yemperature Overpressure Protection was in effect between 1000-1100.

C, The RCP NPSH requirements were vioiated.

D. The alloweble RCS cooldovm rate was exceeded. .

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ltort Calhoun - Sl(O Written thum Quntion sa Dunng natural circulation, which one of the following temperature indications should be used with the 20F subcooled and saturation curves of attachment 2 RCS Pressuro Temperature Limits.

A. Tw B. T ..

C. CETs D. T,,,

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Fort Calhoun - Sito Written Faum  !

Qurtlion: M With the reactor in Mode 3, hot shutdown, the following conditions exist:

. Circulating Water Pump. CW 1 A is running

. Circulating Water Pumps, CW.18 & 1C are secured

. Raw water Pump, AC 10A is operating

. Waste Monitor Tank *B" is being released Which one of the following actions should you direct to be taken if CW 1 A inps?

A One of the other Circulating Water Pumps should be started immediately.

B. The Waste Mon: tor Tank Release should be terminated imediately.

C. An additional Raw water Pump should be started immediately.

D. No immediate action is required as long as one Raw Water Pump remains in sofVice.

(d

Fort Calhoun - SitO Written Enim f

Quttlinn! 69 A CEA position deviation will be indicated on the SCEAPIS CRT display by:

A. Steady, green bar graph indication of the group with the deviation.

B. Flashing, green bar graph indication of the group with the deviation.

C. Steady, red bar graph indication of the group with the deviation.

D Flashing rod bar graph indication of the group with the indication. ,

69

Irort Cailhoun - SRO Written Euim Question: to During power operations, which one of the following valves may be opened intermittently under administrativo control?

A. Containment Purgo Valvo, PCV 742A.

B. Hydrogen Purgo valvo, VA.280.

C, Containment Purgo Valvo, PCV 742D as long as PCV 742C remains closed.

D. Hydrogen Purgo Valvo, HCV 882.

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Fort Callmun - SRO Written Esam nunnoin 7i What is the basis for minimizing DC loads during a station blackout?

A. To assure that instrumentation and controls toquared to monitor plant safety functions operato for the required timo penod.

B. To assure that instrumentation and controls required to start FW.54 operato for the required timo period.

C. To assure that it will be possible to utilize a source of off sito power that becomes available.

D. To atsure that it will bo possible to start a diosol generator that t' mmes available.

1

Fort Calhoun S110 Written Fxam nocinion: 7; The 183 MES switch for DG 1 has boon placed in the EMERGENCY position.

Assuming all other conditions for closing the Diesel-Generators output breaker are mot, the output breaker can be closed:

A. Automatically, if low bus voltage exists.

B. Manually from Al.133A.

C. Manually from CB 20.

D. Manually from Al.30A.

l' ort Callioun Si(O Written Euim Quotion: 71 Dunng physics testing, with the CEAs being operated in the Manual Sequential mode, the operator is directed to move CEAs so that group 3 CEAs are inserted from 51' to 50". Motion of all group 3 CEAs continues when the RO releases the IN.

OUT HOLD switch. Which one of the following alarms would be received first?

A. "PDIL"

8. " Continuous Red Motion" C. " Rod Position Deviation Low Limit" D. " Rod Position Deviation Reed Switch'

~3

6 Fort Calhoun - SRO Written Exam  :

Question: 74 i

Dunng a source check of a process radiation monitor performed in the control room

- per OP ST RM 0002: ,

A. The monitor is considered operable due to the short time that it takes to do a source check.  ;

4 B; The monitor is considered inoperable, however no physical logging of inoperability is required provided the operator is stationed at the monitor dunng the check.

I C. - The monitor is considered operable provided the operator is stationed at the monitor during the check.

D. The monitor is considered inoperab!e and formal logging of monitor inoperability is i required when perfonning this check.  ;

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Fort Calhoun - SRO Written Exam ownikm: 75 Which one of the following sets of signals will be sent to the control room HVAC fans if a fire detection signalis generated?

A. T All fans (VA46A, VA-468, VA43A, and VA 638) will receive a start signal.

B. . VA46A and VA-46B will receive a start signal. VA 63A and VA43B will receive a trip signal.

C.. VA 46A and VA468 will receive a trip signal. VA 63A and VA 638 will receive a start signal,_

D. All fans (VA46A, VA468, VA 63A, and VA438) will receive a trip signal.

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Fort Calhoun - SRO Written Esain QucHion: 76 The technical specification requiroment for maximum allowable closure timo of the main steam isolation va!vos is based on the analysis of:

A. A steam generator tube rupture from full power.

B. A steam generator tubo rupture from zero power.

C. A steam line break inside containment.

D. A steam lino break outsido containmont.

~6

Fort Ctilhoun - SRO Written Exuni 1

Question: 77 You are supervising the performance of Ol RC-3A, *RCS Cold Hydrostatic Test'.

During conduct of this test, you are required to assign a dedicated operator to:

A. Ensure that shutdown cooling is not lost.

B. Ensure pressure temperature limits are not exceeded.

C. Monitor RCS and pressunzer cooldown rates.

D. Monitor RCS leakrate using the ERF computer, b

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l' ort Calhouri- SRO Written Euni (Jurttiott: 7M Eight hours following a large loss of coolant accident which resulted in RAS, the .

HPSI injection flow is split between the cold legs and the pressunzer auxilliary spray. Why is this done?

A To minimize the temperature difference between the pressurizer and the RCS loops.  ;

B. To maintain the RCS pressure low to minimize break flow.

C, To equalize boron concentration between the pressurizer and the loops.

O. To prevent boron precipitation on the fuel assemblies.

d 4

l' ort Calhoun - Sl(O Written Euini puntion: 79 According to Ol AFW4 in a local start of engino-dnven AFW pump FW 54, you should:

A. Place the Run-Stop switch to Run first.

B. Place the Run Stop switch to Stop first.

C. Place the Local Resel-Romoto switch to Local first.

D. Place the Local-Rosot Romoto switch to Roset first.

• 9

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t Fort Calhoun - SRO Written Exam  !

l Question: x0 [

i.

i Charging pump CH-1 A is disassembled for replacement of the block. Charging l pump CH 18 is disassembled for packing and plunger replacement.

A reactor inp occurs and control rods 2 25 and 2 20 stick at 12 inches withdrawn.

All attempts to insert these two rods have been unsuccessful. Charging pump CH-

' 1C is running.

Which one of the following actions should you direct the RO to perform?

A. Rapidly depressurize the RCS to below HPSI shutoff head to allow more rapid l injection of boric acid. j B. Emergency borate with CH 1C until reactor power is less than 10"% power.

t C. Emergency borate with CH 1C until the reactor has achieved a calculated 4% ['

shutdown margin.

I D. Emergency borate with CH 1C until 20 minutes have elapsed.

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Fort Calhoun SRO Written Exam nuncion 81

' A plant startup is in progress. Cnticality has just been achieved at 5 x 10 s %.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> pnor to startup, "A" wide range was removed due to a failed fission

- chamber. "B" and *D' wide range channels have just failed low due to a voltage Spike on DC bus #2.

The roactor must be tripped because;

~A. *D' channel must be operable for Al 212 during entical operations.

B. SCEAPIS requires at least 2 wide range channels giuster than 10'd % to enable the rod block function.

C. Startup rate protection will be inadequate with 3 of the 4 wide range channels failed low.

D. APD trip requires at least 2 wide range channels greater than 10'd to be enabled.

81

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Fort Cathoun - SRO Written Euini Quntion! N2 ,

l Following a steam generator tubo rupture. 20'subcooling was maintained as the RCS was cooled down to a hot leg temperature of 480'F while pressure in the ruptured steam generator was 800 psia. One RCP in each loop continued to operato. What is the potential consequonse of maintaining these conditions? ,

A. Pressurtzed thermal shock of the reactor vessel.

B. Overfilling the ruptured steam generator.

C. Formation of a void in the reactor vessel head. .

D. Reduction of the reactor coolant boron concentration.

n

Fort Calhoun SRO Written Exam Quoiken: si A refueling is in progress. The source range indication portion of WR NI channel B is inoperable. A fuel assembly is being inserted into the core when the power supply to source / wide range channel C falls. What action snould be taken?

A.- Refueling operations must be terminated immediately. The fuel assembly being inserted, must be withdrawn and placed in a safe location.

B. Refueling operations must be terminated immediately. The fuel assembly being inserted must be held in its current position.

C. Refueling operations must be terminated following placement of the fuel assembly into the core, D. Refueling operations may continue as long as the other SR/WR channels remain operable, n

Foit Calhoun - SRO Written Esain ,

Quotion: 84 The reactor inpped 20 minute 5 ago. The following conditions are observed:

• PRESSURIZER PRESSURE OFF NORMAL Hi LO" channel X and Y are in alarm.

• PRC 103X (controlling channel) indicates 2160 psia and stable

• All backup heater in auto and energized

• LRC 101Y (controlling channel) indicates 60% and stable

• LRC 101X indicates 43% and increasing slowly

• LI 106 indicates 28%

• Letdown flow is 26 gpm

• One charging pump is running

• T,.w indicates 533*F. Tw indicates 534*F, both are stable Select the probable cause and the action you should direct ,; RO to take to restore RCS pressure:

A. Low level on LRC 101X is maintaining the B/U heaters on, place the pressurizer heater cutout channel select switch in channel Y.

B. The bistable for the B/U heaters needs to be reset, place the control switches for all B/U heaters to reset and back to auto.

C. LRC 101Y has malfunctioned causing the B/U heaters to remain on, place LRC-101X in service.

D. PRC 103X has malfunctioned causing the B/U heaters to remain on, place PRC-103Y in service.

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Fort Calhoun - SRO Written Exam l s

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'f You are supervising a tusoine startup in accordance with Ol ST 2. )

Which one of the following statements is correct concerning required sequence of l prerequisites and procedural steps?

i A. - Prerequisites and procedural steps must be satisfied or completed in sequence  :

unless the procedure states otherwise.

i B. Prerequisites must be satisfied in sequence but procedure steps are not required to be completed in sequence unless specified in the procedure.

i C, Prerequisites are not required to be satisfied in sequence but procedure steps must be completed in sequence unless the procedure states otherwise.

D. Prerequisites and procedure steps are not required to be satisfied or completed in sequence unless the procedure states o',herwise.  ;

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Fort Calhoun - SRO Written Exam i i

i Questkm: 86 i

Following a 10 week run at 100% power, the reactor has tripped due to a small  ;

break LOCA, The plant responds as designed and no operator action is taken.

Offsite power continues to be supplied. RCS pressure has stabilized at 1350 psia i and HPSI flow is 85 gpm.15 minutes have elapsed since the initiation of the event, i RCS T... is 495'F. How would you expect T . to respond over the next 30 minutes with no operator action?

j A. T..w will stabilize at 495'F due to a balance between decay heat and heat removal f

, - by the break.

8. T .w will rise to 530 540*F because the heat removal by the break is less than the

, decay heat being produced.

C. T w will rise to 540 550*F because the heat removal by the break is less than the

- decay heat being produced.

.D. T w will steadily lower because the heat removal by the break is greater than the decay heat being produced s

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l' ort Calhoun - SRO Written Exam Quntion: M7 Due to excess leakage of PORV PCV 1021. HCV-151 was closed. Which one of the following statements is true concoming operability of HCV-1517 A. HCV 151 is considered operable anytime that it is closed. -

B. HCV 151 is considered operable as long as power is available to its motor operator.

C. HCV 151 is considered inoperable when closed due to potential boric acid buildup.

D. HCV-151 is considered inoperable when closed due to potential thermal binding.

87

Fort Calhoun - SRO Written Exam i a

Qwwk n: 88

I t

Channel 7 news has arrived for a tour of the plant. The group consists of 5 i newspeople and 2 cameramen You have been assigned as their escort. l Which one of the following areas of the plant will require additional escorts? - [

i A. Warehouse,-

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- 8. Switchyard.

1 C. Mezzaninelevelof theTurbine Building.  ;

D. Room 81.

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5 Fort Calhoun - SRO Written Exam j l

. Qwillon: 89 A RCS leak wth a coincident loss of offsite power has been diagnosed and the proper i procedure steps are balng performed. Plant conditions are as follows:  !

TIME 0000 0010 0020 0030  !

PZR pressure, psia 2100- 1700 1500 1300 j CETs,*F 552 555 556 557 i

- Tw. *F 552 555 556 557 l Tg *F 542 547 544 543 l S/G prest As, psia 990 1020 1000 1000  !

S/G WR levels, % 70 % 60 % 50 % 50 % i Has subcooled natural circulation developed? - l A. No, RCS subcooling criteria have not been met. i B, No, RCS temperature trends enteria have not been met.  !

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i C. No, S/G level criteria have not been met.  ;

D. Yes, all enteria for subcooled natural circulation have been met.  !

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Fort Calhoun - SRO Written Fxam i

i Quncion: . w I

Which one of the folowing statements correctly describes the cooling flowpath to be used in a loss of shutdown cooling caused as a result of an inoperable LPSI header >

downstream of FCV 326.

A. Spent fuel pool cooling pumps take a suction from the discharge of the LPSI pumps  ;

and discharge through the spent fuel pool heat exchanger to the suction of a HPSI pump. The HPSI pump discharge flows back to the RCS. t B. HPSI pumps take a suction from the RCS loop and discharge through the shutdown  ;

cooling heat exchanger back to the RCS.

C. Both a containment spray pump and a HPSI pump take a suction on the LPSI pump suction. The containment spray pump discharges through the shutdown cooling heat  ;

exchanger back to the HPSI pump suction. The HPSI pump discharge flows back to t

the RCS.

D. Both a enntainment spray pump and a HPSI pump take a suction on the LPSI pump suction. The HPSI pump discharges through the shutdown cooling heat exchanger hack to the containment spray pump suction. The containment spray pump discharge flows back to the RCS.

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l' ort Calhoun - Sl(O Written Euun Ounilon: 91 An event occured in the plant 15 minutos ago. No operator actions have boon taken Given the followng plant conditions, what is the most probable cause?

• RCS pressure is 2050 psia and. decreasing

• PZR lovel is SG% tnd decreasing

• Lotdown flow is 20 gpm

• Charging flow is 120 gpm

• Reactor power is 99.5% and constant

• T,a is 542*F and constant Tu is 594'F and constant

• RM 054A/B indicato 500 cpm / 700 cpm both are constant

• Containment sump is 18' and constant

• VCT level is 47% and decreat.ing A. A steam generator safety valve fal!ad pon.

B. An RCS leak insido containment.

C. A S/G tubo look in the "B" S/G.

D. A charging header leak in room 13.

91

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Fort Calhoun'- SRO Written Exam Quotion! 92 i

Why does AOP 09 direct that only one Auxiliary Building exhaust fan and no  ;

Auxiliary Building supply fans be operated when high radioactivity is detected in the Auxiliary Building? -1 A. - To achieve the maximum available negative pressure in the Auxiliary Building.  ;

8. To minimize the radiation release to the environment. .

C. To prevent exceeding the flow capacity of VA-66.

. D. To assure a negative pressure while allowing doors in and out of the Auxiliary

. Building to be opened,

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Fort Calhoun - SRO Written Exam 1

93'

- Question:

- With the plant initially operating at 100% power. Which one of the_following events-

%vuld produce a SIAS actuation w:th a lowering of SIRWT level but would NOT

. produce a significant rise in containment sump level.

'A; R/P-102 fails low after D/P-102 placed in trip by l&C.

- B. A rupture of a main feedwater line,' just upstream of one of the steam generators, C Significant leakage through reactor vessel head vent valves..

n D.' significant leakage tnrough SDC loop suction valves HCV-347 and HCV-348.

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Fort Calhoun - SRO Written Exam Question: 94_

The plant tripped due to a loss of 161KV and failure of fast transfer. At the time of the inp, CA-1B was the only major equipment tagged out, ,

Following the performance of the standard post trip actions,'the followir i w liitons exist:

e D-1 failed to start.

. D-2 supplying bus 1 A4 e e instmment air pressure is 80 psig and dropping

. W1 Battery charger trouble alarm, in alarm -

. All other safety functions are satisfied

'- Which one of the following actions should you, as LSO, take?

A Enter EOP-07 to restore power to the #3 botto y charger.

B. Enter EOP 20, MVA-DC to restore a battery charger to DC bus #1, C. Enter EOP-20, MVA IA to restore an air compressor.

D Enter EOP-02, energize bus 1A3 to restore an air compressor, I

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Fort Calhoun - SRO. Written Exam ,

it

,- Queeni 95-

Which one of the following practices concerning ~ compressed gas cylinders violate l

. Fort Calhoun safety procedures?

- A. qStoring a compressed gas cylinder within 3 feet of another compressed gas cylinder.

- B. Stonng a compressed gas cylinder.in a horizontal position.

C.' Storing a compressed gas cylinder outsidec D. Storing a compressed gas cylinder in an area with a temperature greater than 90*F.

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i Fort Calhoun - SRO Written Exam Quistion: 96

. The plant experienced a loss of instrument air pressure. Air to the operators for the feedwater regulating valves,' FCV-1101 and 1102, was automatically isolated. What action,if any, is required to reestablish automatic operation of the regulating valves following restoration of normalinstrument air pressure?_

A. No action is required. Automatic operation wil be regained when pressure is restored.-

- B. Automatic operation can be restored by operation of the reset switch.

C. Automatic operation can be restored by placing the SPEC-200 controller in manual and then back to auto.

D; Automatic operation can be _restorkd by placing the auxiliary controller in manual and then back to auto.

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s 96

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- Fort Calhoun - SRO Written Eum l

Question; . 97 The reactor coolant system is being cooled down and depressurized for a refueling '

outage. I&C technicians have placed a dummy signal on channel 101X . The following indications exist: ,

LI-101Y indicates 45%

LI 101X indicates 48%

- Ll-106 indicates 33%

TI 108 (pressurizer liquid) indicates 300*F.

_.Which one of the following statements is true: ,

- A. Channel Ll-101Y and Channel Ll-106 both indicate that the actual pressurizer level

~ is above the heater cutoff level.

B. Channel LI 101Y indicates that ' actual level is above the heater cutoff level but channel LI-106 indicates actual level below the cutoff level.

C. Channel LI 101Y indicates that actual level is below the heater cutoff level but channel LI 106 Indicates actual level above the cutoff level.

D. Channel LI 101Y and Channel LI-106 both indicate that the actual level is below the E heater cutoff level.

97

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4 Fort Calhoun - SRO 3Vritten Exam  ;

. Que.alen: 98 -

5 The reactor has tripped 15 minutes ago. The operators completed EOP-00 and are

now in EOP 20 DG1 is carrying 2375 KW and 395 amps and is the only available ;

- AC power source. Outside temperature is 102*F. A bearing water pump has been

restarted and it is now desired to restart an air compressor. Which one of the .

following actions should you direct to be taken?

c A. L Do not start the compressor because the current draw for the compressor would -

overload DG-1 by exceeding its'2500 KW rating. .

~ B. - Do not start the compressor because the starting current will exceed the maximum

-instantaneous amp rating on DG 1.

C. _ Start the. compressor, because the running load is within the acceptable range on F the DG's loading curves.

i D. Start the compressor, because the totalload with the compressor running is below the maximum load rating of 2625 KW for the DG's.

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Fort Calhoun - SitO Written Exam Quntion: w The plant is in a refueling outage with the containment purge system operating. Fuel inspection is in progress in the spent fuel pool. A spent fuel bundle has been dropped and damaged resulting in RM 062 going into high alarm Which one of the following statements correctly describes the response of the containment purge isolation valves to this event?

A. The inboard containment isolation valves only would close.

B. The outboard containment isolation valves only would close.

C. Both the inboard and the o"tocard containment isolation valves would close.

D. Neither the inboard nor the outboard containment isolation valves would close.

4 99

t Fort Calhoun - SRO Written Exam Question: ,1(X) '

As Shrft Supervisor,-you have assumed the role'of Emergency Director during the

+

early stages of an event. While serving as the Emergency Director, which one of the .

following responsibilities are you allowed to delegate? -

A. Ensuring that proper classification of the event has been made.

- B. Ensuring all required notifications are made to appropriate state, local and federal officials.-

C. Ensuring that Protective Action Recommendations are provided to offsite officials.

D. ' Ensuring that the pant is in compliance with Technical Specifications and other licensee conditions.

1 100 i