Text

June 05000390/2008301 Exam Final RO Written Exam & References
	ML081900145
Person / Time
Site:	Watts Bar
Issue date:	06/03/2008
From:	; NRC/RGN-II
To:	;
References
	Download: ML081900145 (110)
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Final Submittal

(Blue Paper)

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FINAL RO

WRITTEN EXAMINATION

AND REFERENCES

Watts Bar Nuclear Plant

NRC Initial License Written Examination - 2008

Master Examination

Please note: The following 100 pages are the Master Examination copy.

Questions 1 through 75 were administered to the RO candidates and to the

SRO candidates.

Questions 76 through 100 were administered only to the SRO candidates.

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 1

Given the following plant conditions:

A reactor trip has occurred.

Off-Site power is lost.

All other equipment has functioned as designed.

The crew is entering ES-O.1, REACTOR TRIP RESPONSE.

Upon entenng ES-O.1, Step 3 directs the operators to monitor for RCS temperature trending to

55TF.

Which temperature indication will the operators use and why?

A. Tavg, to ensure adequate RCS heat removal is occurring.

B. Tavg, to check for natural circulation established.

C Tcold, to ensure adequate RCS heat removal is occurring.

D. Tcold, to check for natural circulation established.

1 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 2

Given the following plant conditions:

A 200 gpm RCS leak is in progress.

Containment pressure is stable at 3 psig.

For these plant conditions, what is the MINIMUM S/G water level required in at least one S/G

and why?

A. 29%. Ensures adequate feedwater flow or S/G inventory to ensure a secondary heat sink.

B. 39%. Ensures S/G tubes are covered in order to promote reflux cooling.

C. 29%. Ensures S/G tubes are covered in order to promote reflux cooling.

D. 39%. Ensures adequate feedwater flow or S/G inventory to ensure a secondary heat sink.

2 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 3

Given the following:

Unit 1 at 22% reactor power.

RCP #1 trips due to a bearing failure.

Which ONE of the following identifies the immediate effect that the RCP trip will have on Loop 1

\T AND on SG #1 level?

Loop 1 L'. T SG #1 Level

A. Decreases Increases

B. Increases Increases

C. Decreases Decreases

D. Increases Decreases

3 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 4

Given the following plant conditions :

The Unit is at 45 % .

Letdown is in service at 120 gpm per Chemistry request.

The OAC observes the following ind ication s on 1-M-6:

VCT level is 38% and decreasing.

Annunciator Window 109-A, VCT LEVEL HIILO, is LIT.

1-LCV-62-118 indicating light is LIT for Divert to Holdup Tank.

Assuming NO operator actions , and based on these indications, actual VCT level will lower to...

A. a level which will ca use eventual loss of CCP suction .

B. a level which will cause a swapover to the RWST.

C. 20% and cause auto makeup flow to maintain 20 % level.

D. 20 % and cause auto makeup flow to return level to 41 %.

4 of 100

Watts Bar Nuclear Plant

2008 Initial License Wr itten Exam

SENIOR REACTOR OPERATOR

Question Number: 5

Given the fo llowing plan t conditions:

!.\-~

Unit is in fv1 od e~on RHR cooling with Train A in service in normal alignment.

RC S condi tions initially are :

Temp er ature at 220°F.

Pressure at 330 psig .

Pressurizer level at 30% .

A transient occurs causing the RCS pressure to sta rt rising and the crew ente rs AOI -14 ,

Loss of Shutd ow n Cooling. The cre w also notes the followi ng annunciator is LIT:

Annunciator 113E, RHR SUCT FCV- 74- 1, 2 , 8, 9 OPE N & HI PRE SS .

In response to increasing RCS pressu re , which ON E of the foll ow ing identifies:

(1) W hy the Hot leg Lo op 4 RHR suction va lves, 1-F CV-74-1 an d 1-FCV- 74 -2 , are directed

to be closed?

AND

(2) Wh at are the imp lications of Annun ciator 113E bei ng LIT ?

A. (1) To protect the RHR low pressure suction piping .

(2 ) At least one of the valve s failed to close au tomaticall y wh en pressure reac hed setpoint.

B. (1) To protect the RHR low pres sure suction pipin g.

(2) With th e valve s clos ed, at least one of the valves could NOT be reop en ed .

C. (1) To en su re availab le ECCS ma keu p capaci ty is not exceed ed if sucti on re lief valve

op ens .

(2) At least one of the valves fa iled to close automa tic ally when pressure reach ed setpoint.

D. (1 ) To ensure availab le ECC S makeup capaci ty is no t exceeded if su ctio n relief va lve

opens .

(2) W ith the va lves closed, at least one of the va lve s could NOT be reope ned .

5 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 6

Given the following plant conditions :

Unit 1 is operating at 100% power.

The Component Co oling System (CCS) is in its norma l full power alignment.

W hich of the following indications is abnormal and requires ch an ging plant conditions to

compensate for the con dition?

A. #4 RCP Th ermal Barrier Flow - 40 gpm .

B. #4 RCP Lowe r Oil Coo ler Flow - 9 gpm .

C. 1A ES F Header Supply Flow - 1500 gpm .

D. 1B ES F Header Supply Flow - 5500 gp m.

6 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 7

Given the following plant conditions:

A power esc alation is in progres s.

Plant is currently holding pow er at 30 % for a secondary chemistry ho ld .

Pressurizer Pressure Channel Sele ctor Switch 1-XS-68-340D is in the "PT-68-340 & 334"

position .

Pressurize r Pressure Transmitter 1-PT-68-340 fails HIGH .

(1) What action is required to stabilize RCS pressure at its normal value?

AND

(2) If that ac tion wa s unsuccessful, what will ensure that ade qu ate de parture from nucleate

boilin g ratio (DNBR) is maintain ed ?

A. (1) Manually increasing the master controller output.

(2) Autom atic Reactor trip when Pressurizer pressure lowers to SI initiation setpoint.

B. (1) Manually increasing the master controller output.

(2) Automatic Reactor trip when Pre ssur izer pressure lowers to RPS tri p setp oint.

C. (1) Manu all y decrea sing the master controller output.

(2) Autom atic Reactor trip when Pressurizer pressure lowers to SI initiation setpo int.

D. (1) Manu ally decreasing the master controller output.

(2) Autom atic Reactor trip when Pressurizer pressure lowers to RPS trip setpo int.

7 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 8

Given the following plant cond itions :

A steam generator tube rupture is in prog ress .

The Chemistry Lab has just informed the crew that the activ ity levels in #1 SG are high, and

that sample values have been confirmed.

The crew is implementing E-3, STEAM GENERATOR TUBE RUPTURE.

As a result of actions directed by E-3, which ONE of the following requires entry into a Techni cal

Specification Action statement?

A. Adjusting the #1 SG PORV controll er setpo int to 90%.

B. Closing the #1 SG MSIV.

C. Closing the TO AFW pump steam suppl y valve from #1 SG.

O. Cooling down to target incore temperatu re of 479°F at the maximum rate .

8 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 9

Given the fol lowin g plant con ditio ns:

Unit 1 is initially in Mode 3 preparing for a reactor startup .

A steam lea k dow nstream of the MSIVs requiring safety injection has occurred .

Operators are unable to close any MSIV from the Control Room .

Th e applicable EOP has directed MSIV closure .

Attempts to isol ate an MSIV from the Au xil iary Co ntro l Room have bee n unsu ccessful.

Whi ch ONE of the following describes :

(1) Th e ac tio ns requ ired by th e pro cedure in effect,

AND

(2) W hen that ac tion has been taken , how will the control room operator know it was

successful?

A. (1) Dispatch operator to locally isol ate and bleed off the control air to the MSIVs.

(2 ) Require s local verification of MSIV closure .

B. (1) Dispatch opera tor to locall y isolate and bleed off the control air to the MSI Vs .

(2) Main control room operator notes GREEN light abov e MSIV co ntro l sw itch es is LIT .

C. (1) Dispat ch ope rato r to att empt MSIV clo su re by pulling co ntrol pow er fuses .

(2) Requ ires local verification of MSIV closure.

D. (1) Dispatch operator to attempt MSIV closure by pull ing control power fuses .

(2) Main control room operator notes GREEN light above MSIV control swi tch es is LIT .

9 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 10

Unit 1 is in Mode 3 followi ng a loss of offsite powe r and the failu re of both the Unit 1 diesel

genera tors to start.

Which ONE of the following identifies how the MCR crew will mon itor Core Exit The rmocouples

and the effect on the post accide nt monito ring (PAM) instrumentation Tech Spec LCO for Core

Exit Temperature?

A. Plasma displays on the control board .

PAM Tech Spec LCO entry is required .

B. Plasma displ ays on the control board .

PAM Tech Spec LCO entry is NOT required.

C. Integrated Computer System (ICS) since the plasma displays on the control board will be

unavail able.

PAM Tech Spec LCO entry is required .

D. Integrated Co mputer System (ICS) sinc e the plasma displays on the control board will be

unavailable.

PAM Tech Spec LCO entry is NOT required.

10 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 11

Given the following plant conditions :

Unit 1 is at 100% power.

Alarms received indicate that an electrical board has failed .

All trip status lights are OFF on PaneI1-XX-55-5 (on 1-M-5) .

Which ONE of the following identifies (1) which electrical board failed and (2) the reason that

manipulation of controls in the Auxiliary Control Room (ACR) is required?

(1) (2)

A. 120 VAC Vital Instrument Board 1-1. ACR Auxiliary Feedwater Controllers for S/G 3

and 4 have swapped to MANUAL and require

adjustment to ensure an operable heat sink is

maintained .

B. 120 VAC Vital Instrument Board 1-11. ACR Auxiliary Feedwater Controllers for S/G 1

and 2 have swapped to MANUAL and requi re

adjustment to ensure an operable heat sink is

maintained.

C. 120 VAC Vital Instrument Board 1-1. 1-FCV-62-93 and 1-FCV-62-89 have failed

OPEN and related controls must be taken to

the AUX position to reestablish charging and

RCP seal flows.

D. 120 VAC Vital Instrument Board 1-11. 1-FCV-62-93 and 1-FCV-62-89 have failed

OPEN and related controls must be taken to

the AUX position to reestablish charging and

RCP seal flows .

11 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 12

Given the follow ing plant cond itions :

Unit 1 is at 100% power with no Tech Spec LCO Actions in effect.

The 125 V DC Power System is normal ly aligned with the exce ption of the 6-S

Vital Battery Charger being aligned to the 125v Vital Battery Board II due to

scheduled maintenance on the 125v Vital Charger II.

Offsite power is lost.

All diesel gen erato rs start and load except for the 2B-B dies el ge nerator whic h

FAILS to start.

Whi ch ON E of the following identifies the condition of the 125V Vital DC batteries II and

IV?

(Ass ume NO operator act ion is taken.)

A. Battery II is being maintained at norm al voltage.

Batte ry IV is discharging.

B. Battery IV is being maintained at normal volta ge.

Battery II is disc harging .

C. Both batteries are being main tained at norma l voltage .

D. Both batter ies are discharging .

12 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 13

Given the follo wing plant conditions:

The Unit is at 100% power .

ERCW system is in normal alignment.

ERCW headers 1A and 2A are indicating low flow.

The following MCR alarms are LIT on 1-M-27 A:

Window 223-A, "ERCW HDR A SUP PRESS LO" .

Window 223-C, "ERCW HDR 1A STRAINER 6 P HI".

Window 223-B, "ERCW PMP A-A Discharg e Pressure Low ".

Window 226-B, "ERCW PMP D-A Discha rge Pressure Low ".

Which ONE of the following describes what has occurred in the 1A ERCW header?

A. Supply header has ruptured in the Auxiliary Build ing .

B. Discharge header has ruptured in the Auxiliary Building .

C. Supply heade r has ruptured upstream of the 1A strainer.

D. Supply header has ruptured between the IPS and Au xiliary Bldg.

13 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 14

Complete the following statement:

The reason a backup nitrogen supply is provided to the SG PORVs is to ensure that during

_ _ _(1) the crew has the capability to operate them for a minimum number of cycles,

and the alignment is initiated (2) _

ill 11l

A. an Appendix R Fire automatically on low control air pressure.

B. a Loss of Offsite Power manually.

C. an Appendix R Fire manually.

D. a Loss of Offsite Power automatically on low control air pressure.

14 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 15

When performing ECA-1.2, LOCA OUTSIDE CONTAINMENT, why are RHR components

addressed BEFORE other ECCS components?

A. To maintain suction to CCPs if containment sump swapover has already occurred.

B. This allows the CCPs to maintain RCP seal injection.

C. Isolation of RHR components requires manipulations outside the MCR.

D. The leak is most likely to occur in the RHR system.

15 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 16

Given the following plant conditions :

A Large Break LOCA has occurred .

Containment pressure is 10.5 psig .

RWST level is 20%.

Containment sump level is 68%.

1A RHR pump tripped due to severe damage to its motor.

1-FCV-63-73, CNTMT SUMP TO RHR PMP B SUCT failed to open automatically and

attempts to open it manually have failed.

Which ONE of the following describes the proper alignment of the Containment Spray (CS)

pumps for the existing plant conditions while the CS pumps suction is aligned to the RWST?

A. Stop both CS pumps and place the control switches in P-T-L (Pull-To- Lock) .

B. Stop both CS pumps and place the control switches in A-Auto.

C. Stop ONE CS pump and place its control switch in P-T-L (Pull-To- Lock ).

D. Stop ONE CS pump and place its control switch in A-auto .

16 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 17

Which ONE of the following is an adverse consequence of delaying bleed and feed

cooling if the conditions for initiating bleed and feed are met in FR-H.1, "Response to

Loss of Secondary Heat Sink"?

A. An over pressure challenge to the reactor vessel.

B. Inability to refill the S/Gs without damage from high thermal stresses.

C. Inability to provide sufficient injection for core cooling prior to core uncovery.

D. Steam formation in the hot legs will accelerate the degradation of natural circulation

flow.

17 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 18

Given the following conditions:

Plant is at 100 % power.

All systems normally aligned.

The Transmission Operator has notified the plant that system grid voltage is high and

forecasted to go higher.

If the Transmission Operator requests the plant to take in the maximum value of MVARs to help

stabilize the grid, what is the maximum allowed MVAR incoming value, and how is the

adjustment made in accordance with 1-PI-OPS-1-MCR, Main Control Room?

MAX INCOMING VALUE METHOD OF ADJUSTMENT

A. 100 MVARs Exciter Voltage Adjuster

B. 100 MVARs Exciter Base Adjuster

C. 200 MVAR s Exciter Voltage Adjuster

D. 200 MVARs Exciter Base Adjuster

18 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 19

Given the following plant conditions:

Unit 1 is at 50% power.

Rod control is in AUTO with Bank D at 176 steps.

Tavg auctioneering unit fails LOW.

Bank D group 2 step counter fails to move.

As a result, rods will _ _(1)_ _ and the Bank D control rod CERPI indications must be

matched within _(2)_ _.

(1) (2)

A. Insert +/- 12 steps of each other (highest to lowest rod).

B. Insert +/- 12 steps of the of the Group 1 step counter.

C Withdraw +/- 12 steps of each other (highest to lowest rod).

D. Withdraw +/- 12 steps of the of the Group 1 step counter.

19 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 20

Given the following plant conditions:

1-XS-68-339E PRZ LVL CTRL CHAN SELECT is in the 339/335 position .

With actual pressurizer level at 50%, 1-LT-68-339 Pressurizer Level Transmitter develops a

slow leak in the reference leg.

What IS the effect on Pressurizer level and charging flow?

A. Actual level in the Pressurizer will be increasing, causing charging flow to lower.

B. Actual level in the Pressurizer will be decreasing, causing charging flow to rise.

C. Indicated level on 1-LT-68-339 will be increasing, causing charging flow to lower.

D. Indicated level on 1-LT-68-339 will be decreasing, causing charging flow to rise.

20 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 21

Which ONE of the following describes the Reactor Protection System response to a loss of

control power versus a loss of instrument power to N-31 Source Range Monitor with the "TRIP

BYP ASS SWITCH" in the "BYPASS" position ?

Control Power Loss Instrument Power Loss

A. Reactor trip No trip

B. Reactor trip Reactor trip

C. No trip No trip

0 No trip Reacto r trip

21 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 22

Given the following plant conditions:

Operators are responding to an unexpected annunciator, 182-B tlTB SUMP

DISCH O-RM-212 L10 RAD HI.

The station sump pumps discharge is currently aligned to the Low Volume

Waste Pond.

Which ONE of the following identifies the effect the high radiation condition has on the Station

Sump pumps and how the pumps' discharge should be aligned as a result of the alarm in

accordance with AOI-31, Abnormal Release of Radioactive Material?

Effect on Station Sump Pump

Station Sump Pumps Discharge Aligned to

A. Pumps stop Unlined Chemical Holdup Pond

automatically.

B. Pumps stop Lined Chemical Holdup Pond

automatically.

C. Requires operator action Unlined Chemical Holdup Pond

to manually stop pumps.

D. Requires operator action Lined Chemical Holdup Pond

to manually stop pumps.

22 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 23

If a local fire panel has a TROUBLE lit after being reset , which ONE of the following identifies

how the main control room panel (O-M-29) will indicate a subsequent trouble AND a fire alarm

on the same local panel?

Subsequent Trouble Alarm

Trouble condition would clear, Alarm

A. Would be indicated . would be indicated .

Trouble condition would mask alarm

B. Would be indicated . cond ition.

Trouble condition would clear, Alarm

C. Wou ld NOT be indicated. would be indicated .

Trouble cond ition would mas k alarm

D. Would NOT be indicated. condition.

23 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 24

A large break LOCA is in progress . Wh ich ONE of the following ide ntifies conditio ns that req uire

ent ry into FR-Z.1 High Containment Pressure ?

Containment Pressure Containment Spray Pumps

A. 3.0 psig No pumps running

B. 6.0 psig 1 pum p runn ing

C. 9.0 psig 1 pum p runnin g

D. 12.0 psig 2 pum ps run ning

24 of 100

...... . -~~------

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 25

Unit 1 is at 100% power. Which ONE of the following is the HIGHEST of the belo w listed values

for Dose Equivalent Iodine -1 31 (1-131) without requ iring entry into the Acti on Stat ement for

LCO 3.4 .16, RCS Specific Activity?

A. 0.1 ~C ilgm.

B. 0.2 ~Cilgm.

C. 0.3 ~Ci/gm.

D. 0.4 ~C ilgm .

25 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 26

Given the following plant conditions:

The Unit was at full power when a Small Break LOCA occurred.

The crew has transitioned to ES-1.1, "SI TERMINATION."

The crew has just stopped one of the charging pumps.

What is the reason for checking RCS pressure stable or rising at this point in ES-1.1?

A. To determine if the residual heat removal (RHR) pumps should be secured.

B. To confirm that a secondary heat sink is required.

C. To confirm that flow from one charging pump is adequate to maintain pressure.

D. To determine if the safety injection (SI) pumps should be secured.

26 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 27

Given the following plant cond itions :

A react or trip concurrent with a loss of offs ite power has occurred .

The crew has entered FR-H .2, Steam Generator Overpressure based on a YELLOW

condition on the Heat Sink CSF Statu s Tree.

#2 SG pressure is 1230 psig.

#1 , #3, and #4 SG pressu res are at 1210 psig.

#2 SG level is 85 % and slowly rising .

#1, #3 , and #4 SG level s are 65 % and slow ly rising.

Wh ich ONE of the following actions will mitig ate the SG overpressure cond ition ?

A. Initiate blowdown flow from #2 SG .

B. Open the condenser ste am dum ps.

C. Open the steam supply to the Turbine Driven AFW pump .

D. Initiate minimum AFW flow to #2 SG .

27 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 28

Which ONE of the following failures associated with RCS flow transmitters causes a reactor trip

signal?

A. A single high pressure tap fails when operating at 50 % reactor power.

B. A single low pressure tap fails when operating at 50 % reactor power.

C. Two high pressure taps fail when operating at 5% reactor power.

D. Two low pressure taps fail when operating at 5% reactor power.

28 of 100

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_ **

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 29

On a rising VCT level the Divert Valve is designed to ...

A. fully op en at 63% and fully close when level has lowered to 41 %.

B. begin modulating open at 63% and if level continues to rise, will be fully open at 93%.

C. fully open at 93 % and will begin modulating closed when level drops to 63 % .

D. begin modulating open at 41 % and will be fully open when level reaches 63%.

29 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 30

Given the following plant conditions :

The plant is on RHR cooling following a natural circulation cooldown .

RCS temperature is 150°F.

Pressurizer pressure is 340 psig.

Pressurizer level is 25%.

Preparat ions for return ing to Mode 4 are in progress.

In accordance with SOI-68 .02, Reactor Coolant Pumps, which ONE of the following requires an

action plan to be developed with Reactor Engineering prior to start ing the first RCP?

A. Shutdown and control rods have been withdrawn 5 steps to ensure no therm al bindi ng.

B. Pressur izer boron concentration is 45 ppm less than RCS boron .

C. Steam Generator metal temperature is 105°F .

D. An RCS boration occurred during the cooldown.

30 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 31

Given the following plant conditions :

Plant startup is in progress.

During performance of GO-1 , Unit Startup from Cold Shutdown to Hot Standby, the CLA

isolation valves were left CLOSED with power on the valves as pressurizer pressure was

raised from 900 psig to 1900 psig .

A manual safety inj ection (SI) is initiated .

Which ONE of the following identifies the position of the CLA isolation valves before the SI is

initiated and how the MANUAL Safety injection will affect the valves?

Before 51 Effect of the 51 signal

A. Valves will have An open signa l will be generated to the valves .

automatically opened.

B. Valves will have An open signal will NOT be generated to the valves.

automatically opened .

C. Va lves will have An open signal will be generated to the valves.

remained clo sed .

D. Val ves will have An op en signal will NOT be gene rated to the valves.

remained closed .

31 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 32

Given the following plant conditions:

The plant is at 100% power.

Annunciator 88C PRT PRESS HI is received.

PRT pressure is 8.5 psig and RISING SLOWLY.

PRT level is 67% and STABLE.

If allowed to continue, which ONE of the following describes (1) the LOWEST PRT pressure at

which the rupture disc operates, AND (2) the action required to restore PRT pressure?

A. (1) 50 psig.

(2) Vent the PRT to the Waste Gas Header.

B. (1) 85 psig.

(2) Vent the PRT to the Waste Gas Header.

C. (1) 50 psig.

(2) Drain the PRT to the RCDT to reduce level and pressure.

D. (1) 85 psig.

(2) Drain the PRT to the RCDT to reduce level and pressure.

32 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 33

Given the following plant conditions :

The Unit is at 100% power.

1-M-27C. Annunciator 249A "U1 SURGE TANK LEVEL HI/LO" is in alarm.

The CRO reports that Surge Tank level is 73% on both 1-L1-70-63A and 1-L1-70-99A and

level is rising.

The CRO reports that 1-LCV-70-63 , U1 SURGE TANK MAKEUP LCV, is closed .

-1-FC V-70- 66A U1 Surg e Tank Vent is closed .

-1 -PT-70-24A, CCS HX A SUP PRESS, ind icates 100 psig and stable .

- All systems are in normal operational alignment.

For the above cond itions, a leak in which ONE of the following components accounts for the

above cond itions, and what is the effect of isolating that component?

A. RCS Sample heat exchanger.

Suspension of RCS sampling which leads to the inab ility to determine if RCS chemistry

limits are met.

B RC P seal water return heat exc hange r.

Manual isolation of RCP seal return line results in lifting of the seal return relief valve to the

PRT.

C. CVC S letd own heat exchanger.

Manual isolation of normal letdown flow results in loss of cleanup and leads to exceed ing

RCS chemistry limits.

D. RCP thermal barrier.

Manual isolation of the thermal barr ier heat exchangers results in lifting of the relief valve.

33 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 34

Given the following plant conditions:

Unit 1 at 100% power.

1-SI-68-901-A, Valve Full Stroke Exercising During Plant Operation: Reactor Coolant A-

Train, is in progress.

1-FCV-68-333A, Block Valve for PORV 340A, has been closed and the stroke time

recorded.

When the block valve is reopened, an increase is seen in PRT pressure and

temperature.

Which ONE of the following identifies a condition that will cause the change in PRT conditions

and the action required in accordance with 1-SI-68-901-A?

A. A PORV opened due to the rapid pressure RISE between the PORV and the block valve

when the block valve was reopened;

Place the PORV control handswitch to CLOSE prior to opening the block valve, then return

to AUTO after the block valve has been opened.

B. A PORV opened due to the rapid pressure RISE between the PORV and the block valve

when the block valve was reopened;

Place the PORV Block Valve control handswitch to CLOSE.

C. The PORV opened due to the pressure REDUCTION which occurred between the PORV

and the block valve while the block valve was closed;

Place the PORV control handswitch to CLOSE prior to opening the block valve, then return

to AUTO after the block valve has been opened.

D. The PORV opened due to the pressure REDUCTION which occurred between the PORV

and the block valve while the block valve was closed;

Place the PORV Block Valve control handswitch to CLOSE.

34 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 35

Given the following plant conditions:

The unit is at 100% power.

Pressurizer Level Control is selected to 1-LT-68-339/335 on 1-XS-68-339E.

If 1-LT-68-335 fails low, what is the impact on the Pressurizer Pressure/Level Control System?

A. Pressurizer Heaters de-energize and Letdown isolates.

B. Pressurizer Heaters de-energize and Letdown does NOT isolate.

C Pressurizer Heaters remain available and Letdown isolates.

D. Pressurizer Heaters remain available and Letdown does NOT isolate.

35 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 36

Given the following plant co nditio ns :

The plant is operat ing at 100 % power.

An nun ciator 114-A, SS~A G,t:t;JERAL WARNING is LIT.

.s ~.

Wh ich ONE of the following (1) lists a cond ition that will cause the alarm and (2) describes what

indic ation the ope rator disp atched local ly will use to determine the cau se of the alarm, in

acc ordance with the ARI ?

(1) (2)

A. Reactor Trip Bypa ss Breaker A is Board-edge LED lights on the Semi-Automatic

rac ked in. Tester.

B. Blown Ground Return Fus e. Board-edge LED lights on the Semi -Automatic

Test er.

c. Reacto r Tri p Bypass Brea ker A is Status Lights on the outside of the Local Panels .

racked in.

D. Blown Ground Return Fuse . Status Lights on the outside of the Local Pan els .

36 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OP ERATOR

Question Number: 37

Given the following plant conditions :

An inadvertent Safe ty Injec tion (SI) has occu rred on Unit 1, and the crew is terminating

the Safety Injection.

The OAC has pressed the SI Reset pushbuttons .

Assuming no additional ope rato r action , what is the status of the following ESF signa ls?

Low Steam Line Pressure

Automatic SI Main Steam Isolation Signal

A. Enabled Disabled

B. Disabled Enabled

C. Disabled Disabled

D. Enabled Enabled

37 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 38

Given the following plant conditions:

A ma in steam line rupture has occurred insid e containme nt.

Con tainm ent pressur e peaked at 3.6 psig .

All engineered safety features have actuated per de sig n.

W hat is the expected status of the conta inment Upper Compartment Cooling Fans (UCCF) and

Lower Compartment Cooling Fans (LCCF) 10 minutes after the event?

UCCF LCCF

A. Runn ing Tr ipp ed

B. Trip ped Runnin g

C. Ru nn ing Runn ing

D. Trippe d Tripped

38 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 40

While perfo rming ES-1.3 Transfer to Conta inment Sump, the Containment Spray Pump

hand switches are required to be placed in Stop-PULL-TO-LOCK at which ONE of the

followi ng setpoints?

A. Containment Sump level rises to 83%.

B. Containme nt Sump level rises to 34%.

C. Refue ling Water Storage Tank level drops to 16.1 %.

D. Refue ling Water Storage Tank level drops to 8%.

40 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 41

Given the following plant conditions:

At EOL , a reactor startup is in progress following a 6-day outage .

The Reactor Engineer has provided an ECP which predicts the reactor going critical at 120

steps on Control Bank D.

Which ONE of the following conditions will result in the critical rod height being HIGHER than

the value predicted by the ECP ?

A. A dilution of 500 gallon s is performed .

B. Feedwater flow is increased to all SGs due to a controller malfunction .

C. Steam Dump Controller 1-PIC-1-33 fails , resulting in a pressure decrease of 50 psig .

D. An improperly performed step in the Post Maintenance Test procedure results in the closure

of all MSIVs.

41 of 100

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[

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 42

Given the following plant conditions :

The unit is at 100 % power.

Unidentified lea kage is 0.03 gpm .

Steam Generator #3 has a 17 gpd tub e leak.

AOI-33 , Steam Generator Tube Leakage, Appendix A for Steam Generator Tub e Leak

Mon itor ing, is in prog ress.

Sub sequ ently, the activity in the RCS increased significa ntly due to fuel failure s.

NOTE: Radiation Mon itor Identificat ion Numbers:

1-RM-90-106 - Lower Containment Rad iation Monitor

1-RM-90-119 - Condenser Vacuum Pump Exhaust

1-RM-90-423 - #3 Steam Line Radiation Mon itor

Whi ch ONE of the following describes how 1-RM-90-1 06 and 1-RM-90-423 will respond as a

result of the fai led fuel without a change in the amount of steam generator tube leaka ge and the

action directed in AOI-33 , Append ix A, for using rad iation mon itors to quantify tub e lea kage ?

RAD Monitor Response Action to Quantify

A. 1-RM-90-106 and 1-RM-90-423 Recal culate values for correlating 1-RM-90-11 9 to

increase. SG tube leakage .

B 1-RM-90-106 and 1-RM-90-4 23 Stop using 1-RM-90-119 as the preferred indication

increas e. for SG tube leak rate monitoring .

C. 1-RM -90-106 rema ins constant. Recalculate va lues for correlating 1-RM -90-119

1-RM-90-423 increases . to SG tube lea kage.

D. 1-RM-90-106 rem ai ns constant. Stop usin g 1-RM-90-119 as the preferred indication

1-RM-90-4 23 increases . for SG tube leak rate monitoring .

42 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 43

Given the following plant conditions:

The Unit is at 50% load , steady state.

All Feedwater valves/pumps are in automatic.

Both Main Feedwater Pumps are runn ing.

Stand by Feed Pump is off with its control handswitch in "auto".

The controlling steam flow (SF) transm itter on #1 S/G fails LOW .

Which ONE of the follow ing des cribes the response of the Feedwater Control System to the

given conditions?

A. MFP speed RISES ; #1 S/G Feedw ate r regula ting valve closes initially to match feedwater

flow to the failed SF input.

B. MFP speed RISES ; #1 S/G Feedwater regulating valve closes initially due to the level error

signal present.

C. MFP speed LOWERS ; #1 S/G Feedw ater regulating valve closes initially to match

feedwater flow to the failed SF input.

D. MFP speed LOWERS ; #1 S/G Feedwater regulating valve close s initially due to the level

error signal presen t.

43 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 44

Given the following plant conditions :

The un it is at 100 % power.

The TO AFW pu mp is out of serv ice to re pair the Trip-an d- T hrott le val ve

linkage .

6.9 KV Shutdo w n Board 1B trips due to a differential relay ac tuation .

An inadvertent Safety Injection oc curs .

W hich O NE of th e followi ng describ es the SG s th at are recei ving A FW flow and wh ich

SG blowdown isolation va lves are closed, as a resu lt of the above conditions? (Assume

no ope rator ac tion .)

SGs Receiving AFW flow SG SLOWDOWN Isolated

A. On ly SG 1 and 2 AL L SGs

B. Only SG 1 and 2 Only SG 1 and 3

c. Onl y SG 1 an d 3 Only SG 1 and 2

O. On ly SG 1 and 3 AL L SGs

44 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 45

Given the following plant conditions:

The unit is at 100% power.

All secondary condensate and feedwater pumps are in service .

The 1D Unit Board develops a fault and trips due to relay operation .

Whi ch ONE of the following pumps is lost as a result of this failure ?

A. 1B Hotwell Pump.

B. 1A Condensate Booster Pump .

C. 1B #3 Heater Drain Tank Pump .

D. Standby Main Feed Pump .

45 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 46

Given the following plant cond itions :

1A-A and 1B-B SI Pump breakers are "Racked Up" .

A fuse blows in the NORMAL DC Trip circuit for the 1A-A SI Pump.

A safe ty injec tion (S I) actuation occurs.

Which ONE of the following describes the response of the SI Pumps to the SI signal ?

A. 1B-B SI Pump will auto start, but 1A-A SI Pump will not auto sta rt until the control power

supply is transferred.

B. 1B-B SI Pump will auto start, but 1A-A SI Pump will not auto start and must be

started from the MCR handswitch .

C. Both SI Pumps will auto start, but 1A-A SI Pump cannot be stopped from the

MC R

D. Both SI Pum ps will auto start, but 1A-A SI Pump will immedia tely trip du e to the blown fuse.

46 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 47

Which ONE of the following is the power supply for the 2A-A Diesel Generator Fuel Oil Priming

pump?

A. 480v AC from Diesel Generator Auxiliary Board 2A 1-A.

B. 480v AC from Diesel Generator Auxiliary Board 2A2-A.

C. 125v DC from the 125v DC Vital Battery Board 2-1.

D. 125v DC from the 125v DC 2A-A Diesel Battery Distribution Panel.

47 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 48

Aft er a reactor trip and safety injection on Unit 1, the following conditions are observed for 1A-A

Diesel Generator (DG) :

1-M-26A, Window 198A , "DG START/RUN FAILURE" alarm - LIT.

Green "DG Run" light - ON .

Red "DG Run" light - OFF.

Red "DG Above 40 rpm" light - ON .

Diesel Generator 6.9 KV breaker - OPEN .

Diesel Generator voltage - ZERO .

From the abo ve indications, the operating crew knows that 1A-A Diesel Generator started and

A. shutdown after 10 seconds .

B. engine speed did not rise above 550 rpm .

C. engin e speed exceeded 550 rpm but did not rise above 850 rpm .

D. shutdown due to insuffici ent air in the recei ver.

48 of 100

- .0*":' - *..

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 49

The Turbin e Building NAU O has placed 1-HS-1 5-44 , SG Blowdown Disch to CTBD , (Cooling

Towe r Blowdown), in OPEN per SOI-15 .01, in order to direct SGBD flow to CTBD .

Wh ich ON E of the following will occur if radiat ion monitor 1-RM-90-120 loses flow through the

mon itor?

A. Blowdown will be isolated to the CTBD result ing in loss of blowdown flow .

B. Blowdown will be isolated to the CTBD and automatically be redirected to the condensate

header.

C. Blowdown will cont inue to the CTBD but will isola te if 1-RM-90 -121 reached the HI RAD

setpoint.

D. Blowdown will cont inue to the CTBD and will NOT isolate if 1-RM-90-121 reached the HI

RAD setpoint.

49 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 50

Given the following plant conditions :

Unit 1 experienced a Reactor Trip/Safety Injection due to a LOCA inside containment.

When checking annunciators following the trip and SI, the CRO notes that the follow ing

annunciators are in alarm:

o 173B , LWR CNTMT AIR 1-RM-106 RAD HI.

o 173E , LWR CNTMT AIR 1-RM-106 INSTR MALF.

Assum ing all components respond as designed, which ONE of the following actions will the

NAUO take due to the above conditions?

A. Reopen the radiat ion monitor isolation valve which restores flow through the monitor to

restore Tech Spec operabil ity.

B. Restart the radiation monitor pump which restores flow through the monitor to restore Tech

Spec operability.

C. Stop the radiation monitor pump to prevent damage to the pump due to the monitor being

isolated as a result of the safety injection.

D. Close the radiation monitor isolation valves to isolate mon itor due to the pump being tripped

as a result of the safety injection.

50 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 51

Reactor trip and sa fety inj ectio n sig nals have been manually initiated. Which ONE of the

following describes the required pos itions for the listed ERCW valves in accordance with E-O ,

App endi x A . Equ ipment Verifica tion ?

O-FCV-67-144, O-FCV-67 -152,

"CCS Heat Exchanger 'C' "CCS Heat Exchanger 'C'

Disch to Hdr A" Alt Disch to Hdr S"

A. CL OSED OPEN to Pos ition A

8 THR OTTLED CLOSED

C. THROTTLED OPEN to Pos ition A

D. OPEN CLOSED

51 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 52

Given the following plan t conditions:

The plant is operating at 100% power with 1B CCP in service.

The Control Room Operator shutdowns down the C-A ERCW pump in preparation for a

test on the 2A 6.9 KV Shutdown Board .

Which ON E of the following describes the impa ct of shutting down the pump on the listed

parameters?

(Assume no oth er operato r action. )

18 CCP Oil Seal Water Return Heat

Temperature Exchanger Temperature

A. Rises Rises

B. Rises Remains constan t

C. Remains constan t Rises

D. Remains constan t Remains const ant

52 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Ques tion Number: 53

Which ONE of the following identifies both of the follow ing?

(1) The lowest of the listed cont ainment pressures that resu lts in 1-F CV-32-80, Au x Air to

Rx Bldg Train B, being automatically isolated , and

(2) The lowest of the listed air pressures sensed downstre am of the valve tha t allows the

va lve to RE MAIN OPEN after the valve was opened an d the control sw itch on 1-M-15

placed to A-A uto after the isolation signa l was reset.

ill ill

A. 2.0 psid 68 psig

B. 2.0 psid 78 psig

C 3.0 psid 68 psig

D. 3.0 psid 78 psig

53 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 54

Given the following plant conditions :

Plant is in Mode 4.

Lower containment air lock is broken and inner door is jammed and will not open.

If conditions were to require an emergency entry into lower containment by opening the sub-

hatch , which ONE of the followin g is REQUIRED to be contacted prior to opening the sub-h atch ,

and what action is requ ired as a result of the sub-hatch being open ed ?

A. Shift Manager;

Perform 1-SI-88-24 , Containment Divider Barrier Personnel Acce ss Hatches & Equipment

Hatches . within one (1) hour.

B. Shift Manag er;

Perfo rm 1-SI-88-24 , Containment Divider Barrier Personnel Acce ss Hatche s & Equipment

Hatches . prior to Mode 3 entry .

C. Work Week Manager ;

Perform 1-SI-88-24 , Containment Divider Barrier Personnel Access Hatches & Equipment

Hatches. within one (1) hour.

D. Work Week Manager;

Perform 1-SI-88-24, Containment Divider Barrier Personnel Access Hatches & Equipment

Hatches , prior to Mode 3 entry.

54 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 55

Which ONE of the following identifies the NORMAL pressure band controlled by the

Containment Annulus Vacuum System and the required method of controlling pressure if 1-M-

27B Window 232-B , ANNULUS l1P LOIDAMPER SWAPOVER is LIT?

Annulus Pressure Band Method of Controlling Pressure

A. -6.0 to -6.2" WC Dispatch a NAUO to RESE T the dampers loca lly.

B. -6.0 to -6.2" WC Swap the dampers using handswiches on 1-M-27B.

C. -4.3 to -4.5" WC Dispatch a NAUO to RESET the dampers locally.

D. -4.3 to -4.5 " WC Swap the dampers using handswiches on 1-M-27B .

55 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 56

Given the following plant conditions :

The unit is at 100% power.

1-M-1 B, Window 17-D , 120 AC VITAL PWR BD 1-1 UV/C KT TRIP, is LIT .

Which ONE of the following desc ribes the impact on the Computer Enhanced Rod Pos ition

Indication (CERPI) System and what is req uired to ensure that Tech Spe c Rod Group Alignm ent

Limits are met?

Rod position indication Actions Reguired for Rod Group alignment

A. Availa ble Use the "ALL RODS " funct ion on the operating display.

B. NOT Availab le Flux map is requi red to confirm rod position .

C. Available Flux map is required to confirm rod position .

D. NOT Available Use the "ALL RODS " function on the operating display .

56 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 57

Wh ich ONE identifies BOTH of the following for Hydrogen Recombiner operations?

(1) The MAXIMUM Hydrogen Recombiner temperature allowed when operating?

AND

(2) The HIGHEST of the listed containment hydrogen concentrations allowed when placing the

recombine r in service?

(1) Maximum Temperature (2) H2 Concentration

A. 6%

B. 4%

c. 6%

D. 4%

57 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 58

Following a refueling outage , the follow ing cond itions exist:

Unit 1 is in Mode 3 prepa ring for Mode 2 entry .

Fuel shuffles are being conducted in the Spent Fuel Pit.

Spent Fuel Poo l Cooling pump A is the only Spent Fuel Pool Coolin g pump in service.

The 2A-A Shutdown Board normal feeder breake r is inadvertentl y opened durin g testing.

The DG start s and reen ergizes the shutdown board.

Which ONE of the following describ es the initial effect on the Spent Fuel Pool Cooling system ,

and the requ ired action, if any , per Spent Fuel Pool Tech Specs?

A. The Spent Fuel Cooling Pump strips from the board, and then sequences back on to the

shutdown board .

Spent Fuel Pool Tech Specs requires that movement of irradiated fuel assemb lies in the fuel

storage pool be immediately suspended .

B. The Spent Fuel Cooling Pump strips from the board , and then sequences back on to the

shutdown board .

Spent Fuel Pool Tech Specs does NOT requ ire that movement of irradiated fuel assembli es

in the fuel storage poo l be suspended .

C. The Spent Fuel Cool ing Pump strips from the board , and remains off .

Spent Fuel Pool Tech Specs requ ires that movement of irradiated fuel assemblies in the fuel

storage pool be immediately suspended.

D. The Spent Fue l Coo ling Pump strips from the board , and remains off .

Spent Fuel Pool Tech Specs does NOT require that mov ement of irradia ted fuel assembli es

in the fuel storage pool be suspended.

58 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 59

Which ON E of the follow ing identifies (a) how main steam header pressure responds as turbin e

load is raised from 25 % to 65 %, and (b) which method of mainta ining Tavg matched with Tref

results in the value for MTC being the MOST negative as turbine load is raised ?

A (a) Main steam header pressure lowers

(b) Rods are withdrawn to maintain Tavg on program , with Boron con cent ration held

const ant.

B. (a) Main steam header pressure rises.

(b) Rods are withdrawn to mainta in Tavg on program , with Boron concentration held

cons tant.

C. (a) Main steam header pressure lowers.

(b) Rod position is held constant, while Boron concentra tion is low ered to maintain Tavg

on program .

D. (a) Main steam header pres sure rises.

(b) Rod position is held constant, while Boron concentration is lowered to maintain Tavg

on program .

59 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 60

Which ONE of the follow ing iden tifie s monitors asso ciated with Conde nser Vacu um Pump

discharge which are Post Accident Monitors (PAM), in accordance with SOI-90 .05, Post

Acc ident Radiation Monitors?

A. Both 1-RM-90-11 9 and 1-RM- 90-404 .

B. Neither 1-RM-90-11 9 nor 1-RM-90-404 .

C. 1-RM-90-119 is a PAM, but 1-RM-90-404 is NOT.

D. 1-RM-90 -404 is a PAM , but 1-RM-90-119 is NOT .

60 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 61

Which ONE of the follow ing occurs automatically if the "8" MFP trips due to thru st bearing wear

with the plant initially at 100% power? (Assume no other equipment failures .)

A. The motor driven AFW Pumps start.

8. The Condensate 01 pumps trip if feedwater flow drops to <80%.

C. The "8" MFPT condenser condensate inlet and outlet valves go closed.

O. The short cycle valve , 1-FCV-2-35, modulates open to dump excessive condensate flow.

6 1 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 62

Which ONE of the following identifies a condition that causes an instrument malfunction ala rm

on O-RM-90-1 22 , WDS Liquid release rad iation monitor, and the effect the instru ment

malfunction ala rm has on valve O-RCV-77-43, CT BLDN LN RAD RELEASE CNTL?

Cause of the alarm Effect on O-RCV-77-43

A. Loss of signal from detector Auto closes O-RCV-77-4 3 if the valve was open.

B. Loss of sign al from detector Prev ents O-RCV-77-43 from opening if the valve 's

local control handswitch was placed to OPEN .

C. Loss of flow through the mon itor Auto closes O-RCV-77-43 if the valve was open .

D. Loss of flow through the monitor Prevents O-RCV-77-43 from opening if the valve 's

local control handswit ch was placed to OPEN .

62 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 63

A release of the Monitor Tank is in progress through the Liquid Radwaste System . Which ONE

of the following conditions directly results in automatic closure of 0-FCV-77-43, Liquid Radwaste

Release Flow Control Valve?

A. High radiation signal on 0-RM-90-225, Condensate Demineralizer Release Liquid Radiation

Mon itor.

B. River flow drops to less than 3500 cfs after a 1 minute time delay.

C. Cooling Tower Blowdown flow drops below 25 ,000 gpm .

D. SG Blowdown flow exceeds 150 gpm .

63 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 64

Given the follow ing plant cond itions :

Unit 1 is operating at pow er when control air pressu re starts to drop .

Annunciator 42-F , SERVICE AIR PCV-33-4 CLOSED, alarms.

The CRO responds in accordance with the Annunciator Response Instruction (ARI ).

Which ONE of the following identifies the decreasing Control Air system pressure that causes

this alarm to occur and whether the Auxiliary Air compressors would have started if the air

press ure dropped low enough to cau se the alarm , but then recovered without dro pping any

lower?

Pressure to Cause Alarm Aux Air Compressors

A. 83 psig Will have started

B. 83 psig Will NOT have started

C. 80 psig Will have started

D. 80 psig Will NOT have started

64 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 65

Given the following plant conditions:

Unit 1 is currently at 100%.

A fire occurs in the Cable Spreading Room.

The crew was unable to start the HPFP pumps .

The incident Commander also reports that due to multiple fire damper failures the fire is

spread ing quickly.

The crew has entered AOI-30 .2, Fire Safe Shutdown .

In accordance with AOI-30 .2, which ONE of the follow ing failures results in a loss of a Control

Function required to place the Plant in Hot Standby?

REFERENCE PROVIDED

A. Moto r Driven AFW Pumps will not start.

B. RCS Thermal Barrier Boost er Pumps trip.

C. One Main Steam Isolation Valve fails to close.

D Letdow n Isolation Valve 1-FCV-62-69 fails closed.

65 of 100

'::'. ' " ..,

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 66

For Mode 1 operation, which ONE of the follow ing describes the MINIMUM number of Licensed

Operator positions to man a shift, AND the MAXIMUM time requ irement to restore if the

minimum shift manning for Licensed Operators is not met per OPDP-1, Conduct of Operations

and Tech Spec 5.2 .2, Unit Staff?

Minimum Shift Manning Time Requirement

A. 2 ROs , 2 SROs Restore within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

B. 2 ROs , 1 SRO Restore within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

C 2 ROs, 1 SRO Restore within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

D. 2 ROs, 2 SROs Restore within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

66 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 67

With the Steam Dump Mode switch in the Tavg mode , what determines whether the load

reject ion controller or the Rx trip controller will be in serv ice?

A. Loss of Load (C-7) Interlock.

B. LO-LO Tavg Interlo ck (550°F) .

C "A" Train Reactor Trip breaker position.

D. "B" Train Reactor Trip breaker position .

67 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 68

Given the following plant cond itions:

Unit is in Mode 6.

15 fuel assemblies have been reloade d after a complete core off-load .

Sourc e Range N-13 1 indicates 10 cps and is selected for audible count rate indication.

Source Range N-132 indicates 5 cps.

In accordance with FHI-7 , "Fuel Handling and Movement" , which ONE of the follow ing

unanticipated changes in count rate requires suspension of core alterations?

A N131 indica tes 25 cps and N132 indicates 8 cps .

B. N131 indicates 15 cps and N132 indicates 20 cps .

C. N131 indicates 40 cps and N132 indicates 8 cps.

D. N131 indicates 20 cps and N132 indicates 15 cps.

68 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 69

A Power Range chann el has failed requiring the crew to implement AOI-4, NIS Malfunctions.

The US has entered the appro priate Technical Specifi cations and states that a flux map will be

required per Surveillance Requirement 3.2.4.2.

SR 3.2.4.2 directs the operators to verify OPTR is within limits using moveable incore detectors

once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereaft er.

Wh at is the maximum time for the initial performance of the flux map and the maximum time for

sub sequent performances?

Initial Performance Subsequent Performances

A. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

B. 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

c. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months

D. 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months

69 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 70

Given the fo llow ing co nditio ns:

Un it 1 shutdow n is in progress.

Reactor power is 14% and de creasing .

Intermed iate Rang e NI-36 fails HIGH.

Which ONE of the fo llowing identifi es how the failure of the NI wi ll affec t the reactor trip system

and the effect the failure will have on the Source Rang e Nls?

Reactor Trip System Effect on Source Range Nls

A. Reacto r trip will occur at the time of Source Ran ge Nls will have to be

failure . MANUALLY reinstated.

B. Reactor trip will occur at the time of Sou rce Range Nls will

failure . AUTOMATICALLY reinstate.

C. Reactor trip will occur if power Source Ran ge Nls will ha ve to be

reduction is continued . MANUALLY reinstated.

D React or trip will occur if power So urce Range Nls will

reduction is continued . AUTOMATICALLY reinstate .

70 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 71

An individ ual enters a Radiological Co ntro lled Area (RCA) covered by a General RWP to

perform equipment inspections .

Which ONE of the following identifies an ar ea within the RCA wh ere a Job Sp ecific RWP is

requ ired be fore ent ry is allowed , in accordance wi th RCI - 153 , Radiation W ork Perm its?

A. Ar ea wh er e whole body dose rates ex cee ds 100 mr em /hr.

B. Are a posted as Hot Parti cle Area .

C. Area w ith ge ne ra l co ntami na tion lev els gr eat er than 200 dprn /f Oucrn".

D. Area where total expected dose is greater than 5 mrem .

7 1 o f 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 72

Given the follo wing plant conditions :

Following an accident, both Trai ns of Cont rol Room Isolation have been initiated .

Seve ral Auxiliary Buildin g Area Radiation Monitors rise to the alarm setpoint.

Which ONE of the following MCR air inta ke radiation monitors will detect and alert the crew of a

radiation hazard entering the control room and what actions will the ARI direct the crew to

perform?

A. O-RM-90-125 , Stop MCR Emergency Pressurization Fans .

B. O-RM-90-1 25 , Align Emergen cy Pressurization Fan suct ion to alternate sourc e.

C. O-RM-90-205, Stop MCR Emergency Pressurization Fans .

D. O-RM-90-205, Align Emergency Pressurization Fan suction to alternate source .

72 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 73

The Operator-at-the -Controls (OAC) is respondin g to an accident. He recognizes that he must

take actions which are NOT cont ained in the emergency operating procedure in effect and are

NOT covered by prud ent operator actions . Which ONE of the following describes the proper

action to be taken?

A. The OAC shall take no action until a procedure is developed or revised.

B. The OAC shall obtain approval from a licens ed SRO prior to taking action .

C. The OAC should obtain concurrence from another licensed RO prior to taking action.

D. The OAC should immediately take appropriate actions necessary and inform the SRO when

time permits.

73 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 74

Given the follow ing:

A Site Area Emergency (SAE) has been declared on Un it 1.

Two hours after the SAE declaration , an individual is to be authorized to rec eive an

Emergency Exposu re rad iation dose above the TVA who le body dose lim it during the

mitigation of the emergency situat ion.

In acco rdance with EP IP-15 , Em erg ency Exposur e Guideline s, whose app rova l is requ ired for

the individual to rece ive the dose?

A. TSC Radcon Mana ger.

B. Onshift Sh ift Manager.

C. Site Emergency Director.

D. Site Vice President.

74 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Quest ion Number: 75

Which ONE of the follow ing identifies where a Portable Satellite Telephone , available for use

during an emergency , is located?

A. Main Control Room

B. Technical Support Cen ter

C. Joint Informatio n Center

D. Operations Support Center

75 of 100

AOI-30.2

WBN FIRE SAFE SHUTDOWN Rev. 27

Paqe 17 of 129 1

4.5 Safe Shutdown Logic Diagram

~'

.,......

..

l

i.J

i.J:J

~!\J

I'~

~

()

~

'6!

{\j

C;

IV

(t\

~I

~<t:\

NOTES

(1) INITIATING EVENT IS AN AP PEND IX R FIRE

(2) REFER TO SECTION 4.3 FOR A COMPLETE

DESCR IPTION OF THE SHUTDOW N KEYS , THEIR

FUNCTIONS AND COMPO NENTS.

(3) LEGEND FOR DIAGRAM SYMBOLS A S FOLLOWS '

DESCR IPTION OF KEY

I ,.~ "oo~""w,m'",,, KEY NUMBER

< ~ SAFETY FUNCTlON OR E.ND

STATE TO BE AnAINE D

(4) OFFSITE POWER NOT CREDITED FOR ALTERNA TIVE SHUTDOW N.

(5) RCP THERMA L BARR IER COO LING REQUIRES SUPPORT OF

ERCW (KEY 1C ) & CCS (KEY 1B)

Final Submittal

(Blue Paper)

FINAL SRO

WRITTEN EXAMINATION

AND REFERENCES

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 76

Given the following conditions :

Unit 1 is at 100% power. Solid State Protection System (SSPS) Train 'B' Actuation Logic testing

is being performed using 1-SI-99-1 OB with :

Tra in 'B' SSPS Mode Se lector switch in the 'TEST' pos ition .

Train 'B' SSPS Input Error Inhibit switch in the "INHIBIT" pos ition .

A unit trip occurs due to the loss of one of the two 48v DC power supplies on TRAIN 'A' SSPS.

The following "First Out" annunciators are lit:

1-XA-55-4C. Turbine Trip First 1-XA-55-4D Reactor Trip First Out

Window 73C - "RX TRIP BKRS RTA & BYA OPEN" Window 76B "TURBINE TRIP"

Window 74C - "RX TRIP BKRS RTB & BYB OPEN"

Window 74B - "MFPT A&B TRIPPED"

Wh ich ONE of the following identifies both the sequence of events of the unit trip , and the time

allowed to make the required NRC 50.72 notification ?

Sequence of Events NRC Notification Required Within

A. Turbine trip caused the Reactor trip . Four Hours

B. Turbine trip caused the Reactor trip . Eight Hours

C. Reactor trip caused the Turbine trip . Four Hours

D. Reactor trip caused the Tu rbine trip . Eight Hours

76 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 77

Given the following plant conditions :

Core burnup is 1200 MWO/MTU .

Indicated reactor power is stable at 100%.

VCT low level alarm annunciates.

Auto makeup has failed .

Actual VCT level had lowered to 5% before the crew completed the appropriate

corrective action.

Reactor power has stabilized at approximately 97% power.

If this event had occurred with core burnup at 16600 MWO /MTU, the magnitude of the change

in reactor power would be (1) , and the Significance Level of the Reactivity

Management Event classification would be recorded on the PER (Problem Evaluation Report)

by (2) _

(1) (2)

A. less Reactor Engineering.

B. greater Reactor Engineering.

C. less the Management Review Committee .

D. greater the Management Review Committee .

77 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 78

Given the following:

Unit 1 is in Mode 5 following a refueling outag e.

RHR pump 1A-A is in serv ice.

The operating crew is drawi ng vacuum on the Reacto r Coo lant System .

The RHR pum p begins to show signs of cavitation.

Wh ich ONE of the following identi fies both how the RHR pump motor amps are affected when

the pump is cavitating , and the mitigating strategy that will be implemented if the cavitation

cann ot be terminated ?

Motor Amps Mitigating Strategy

A. Unstabl e and fluctuating. Break vacuum per GO-1 0, Reactor Coolant System

Drain and Fill Operations, then enter AOI-14, Loss of

RHR Shutdown Cooling.

B. Unstable and fluctuatin g. Immed iately enter AOI-14, Loss of RHR Shutdown

Cooling . Break vacuum as directed by the AOI.

C. Stab le but reduced. Break vacuum per GO-1 0, Reactor Cool ant System

Drain and Fill Operations , then enter AOI-14, Loss of

RHR Shutdown Cooling .

D. Stable but reduced. Immediately ente r AOI-14, Loss of RHR Shutdown

Cooling . Brea k vacuum as directed by the AO I.

78 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 79

Given the following conditions:

The plant is operating at 100% power steady state conditions.

All systems are aligned normally.

A failur e of the Pressurizer Spray Valve PCV-68-340D caus es it to go full OPEN .

The OAC has attempted to take manua l contro l of the Spra y Valve, but is unable to

close it.

Pressu rizer pressure continues to LOWER.

Wh at is the appropriate mitig ation strategy and which procedure (s) will be used to impleme nt

the strategy ?

A. Enter AOI -18, Malfunction of Pressurizer Pressure Control System, initiate a Reactor Trip,

trip RCP #1 , then enter E-O, Reactor Trip or Safety Injection.

B. Refer to ARI-90-B , PZR PRESS LO DEVN BACKUP HTRS ON, isolate Train B Essenti al Air

to Conta inment to fail the Pressurizer Spray Valve closed, and then ent er AOI-1 8.

C. Refer to ARI 90-B, PZR PRESS LO-DEVN BACKUP HTRS ON, isolate Train A Essent ial Air

to Containment to fail the Pressurizer Spray Valve clos ed, and then enter AOI-1 8.

S~ ~

D. Enter AOI- 18, Malfunction of Pressurizer Pressure Control~initiate a Reactor

Trip AND SI, trip RCP #1 , then enter E-O, Reactor Trip or Safety Injection .

79 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 80

Given the following:

The plant is operating at 100% pow er .

The 125 V DC VITAL CHGR III fails and its output brea ker opens.

A report is received that ther e is arc ing occurring on Vital Battery III.

The Sh ift Manager direct s that 0-BKR-236-3/109 125V Vital Battery III Breaker, between

Vital Battery III and Vital Batt ery Boa rd III be ope ned .

The Unit Supervisor has determined that power to Vital Battery Board III will be restored

using Vital Battery V, in conjunction with the Spare Battery Charger.

Vital Battery V is currentl y in service to Battery Boa rd V .

Whic h ONE of the follow ing describes the expected indication on 1-EI-57-94 , Vita l Batt BD III

AMPS wh ich will confirm that power has been restored to Battery Board III, AND what is the

oper ability status of Vital Battery Board III?

1-EI-57-94 (Satt SO III Amps) Indication Operability Status of Vital Satt. SO III

A. Indicating UPSCALE from zero. Can NOT be conside red op erable with

both Vital Battery V and the spare charger

connected concurrently.

B. Indicating DOWNSCALE from ze ro. Can NOT be considered operable with

both Vital Battery V and the spare charg er

connected concurrently .

C. Indicating UPSCALE from zero. Operable with the spare charger and Vital

Battery V connected to the Battery Board

and with all ap plicable sur vei llanc es on

Vital Battery V satisfied .

D. Ind icating DOWNSCALE from zero . Operable with the spare charger and Vital

Battery V connected to the Battery Board

and with all applicable surveillances on

Vital Battery V satisfied .

80 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 81

With the plant at full power, and during the Shift Turnover for the 1900 shift , the Unit Supervisor

is informed of the follow ing :

1-LS-63-50A (RWST Low Level) was declared inoperable at 1000 that day.

It was placed in the configuration required by Technical Specifications at 1400 , and is

expected to rema in inoperable until 2300.

A requ ired surveillance instruction on 1-LS-63-51A (RWST Low Level ) must be

completed by 2330 today to prevent being out of frequency due to exceed ing the NRC

late date.

The surveillance involves having 1-LS-63-51 A in the required configuration for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

If the surv eillance is completed by 233 0, wh ich ONE of the following describes the expected

effect on the automatic sw itchover to containment sump function while 1X63-51A is out of

. ?.

service ~~A ~_.....

A. Functiona l. Even though two level switches are TRIPPED and are inoperable, the

remaining operable level switches are sufficient for switchover to be functional.

B. Functional. Even though two level sw itches are BYPASSED, the remaining level

switches are sufficient for switchover to be functional.

C. Not fun ctional , because two level swit ches are TRIPPED and at least thre e level

switches are required for switch over to be functional.

D. Not functional, because two level switches are BYPASSED , and at least three level

switches are required for switchover to be functional.

81 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 82

Given the following :

The unit is at 100% powe r and all equipment is available.

A planned Cask Decont amin ation Collector Tan k (CDCT) release is in progress when

the following occurs :

Annunciator 181-A "WDS RELEASE LINE 0-RM-90-122 L1Q RAD HI" alarms.

The Monitor Tank level is 70% and lowering.

Which ONE of the following identifies wheth er the relea se permit was violated and the releas e

permit requirements to allow the CDCT release to continue , in acco rda nce with SOI-77.01,

Liquid Waste Dispo sal?

Permit Violated Release of CDCT

The release perm it would be

A. violated because the liquid The same release perm it can be used

releas ed was not sampled follow ing independent verification of

~---I--------+----------J

. prior to the release . correct valve lineup .

The release permit would be

l B. ! violated becau se the liquid A new release permit must be generated .

i released was not sample d I

i I, prior to the release.

The release permit was NOT

C. violated because the release The same release permit can be used

was terminated by the high following independent ver ification of

rad signa l. correct valve lineup .

The release permit was NOT

, D. violated because the releas e A new release perm it must be generated .

, . was terminat ed by the high

I rad signal.

I I I

i

82 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 83

Given the followi ng plant conditions:

Unit 1 was at 100% power when a Main Contro l Room (MCR) evacuation was requ ired.

The crew entered AOI -27, Main Cont rol Room Inaccessibilit y.

The crew performed ES-0.1, Reactor Trip Response, prior to leav ing the MCR.

While perform ing actions from the ACR a Safety Injection occurs.

Which ONE of the following will be the status of the MSIVs when the crew establishes control

from the Aux Control Room and describes the correct proced ure usage?

MSIV Status Procedure Usage

A. Open AOI-27 will be the controll ing procedure because it is written with

mitigatin g actions to respond to a Safety Injection.

B. Open E-O, Reactor Trip or Safety Injection, would be used because

AOI -27 is written assuming no other accident is occurring .

C. Closed AOI-27 will be the controll ing procedure because it is written with

mitigating actions to respond to a Safety Injec tion.

D. Closed E-O , Reactor Trip or Safety Injection , would be used because

AOI-27 is written assuming no other accident is occurring .

83 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 84

Given the follow ing:

The crew is perform ing FR-H.2 , Steam Generato r Overpressure, for an overpressure

condition on SG #2.

Wh en the step is addressed to check affec ted SGs NR level it is noted that the SG #2

level is indicating 94% narrow range.

Whic h ONE of the follo wing identifies the correc t crew act ions as a result of the SG leve l

morcatm q 94% ?

A. Continue in FR-H .2, but do not initiate any steam release unt il TSC evaluation is comp lete.

B. Continue in FR-H .2, steam release may continue until NR level indicates 100%.

C Transition to FR-H .3, Steam Generator High Level, but do not initiate any steam release

unt il TSC evaluation is complete .

D. Tran sition to FR-H .3, Steam Generator High Level, steam release may continu e unt il NR

level ind icates 100%.

84 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 85

Given the follow ing:

Unit 1 experien ced a Reacto r Trip and Safety Inject ion.

The crew tran sitione d to FR-Z.1 , High Conta inment Pressure, from E-1, Loss of

Reactor or Second ary Cool ant.

Whil e FR-Z.1 was being performed , the crew transitioned to FR-P .1, Pressurized

Thermal Shoc k.

The STA reports the conta inment pressure has dropped and the cont ainment status

tree is GREEN and that no other RED or ORANGE paths exist.

Which ONE of the follow ing identifies the basis of the FR-P.1 step for checki ng RCS pressure

greater than 150 psig, and the procedure the crew will implement if a transition is made from

FR-P .1 during performance of the step?

A. To preclude the need to perform FR-P .1 actions, since pres surized therm al shock is not a

serious concern for a large-break LOCA ;

Transition is made back to E-1.

B. To preclude the need to perform FR-P .1 actions, since pressurized thermal shock is not a

serious concern for a large-brea k LOCA ;

Transition is made back to FR-Z .1.

C. To avoid delays cause d by unnecessary soak periods requ ired by FR-P .1.

Transiti on is made back to E-1.

D. To avoid dela ys caused by unnecessary soak periods required by FR-P .1.

Transition is made back to FR-Z.1 .

85 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 86

Given the follo wing:

Unit 1 was in Mode 2 with startup in progress when a loss of off-s ite power occurred .

The decision was made to place the plant in Mode 5.

The crew implemented ES-O .2, Natural Circulation Cooldown , and started cool ing the

plant down .

Four (4) hours after the cooldown was initiated both trains of offsite power were rest ored

to the plant.

The crew determines all criteria to restart the RCPs are met except for the #1 seal

leak off flow on RCP #2 which is lower than the normal operating band .

Whi ch ONE of the following identifies a change that causes an increase in the # 2 RCP seal

leakoff flow and the act ions to be taken and procedure to be used if the seal lea koff flow cannot

be established within the normal operating band ?

A. Lower PRT pressure ;

Start RCP #1, continue performing ES-O. 2 until all RCS temperatu res are less than 200°F,

then tran sition to GO-6 , Unit Shutd own From Hot Standby To Col d Shutdown .

B. Lower PRT pressu re ;

Start the other 3 RCPs and immediate ly tran sitio n from ES-O.2 to GO- 6, Unit Shutdown

From Hot Standby To Cold Shutdown .

C. Lower VCT pressure ;

Start RCP #1 , continue performing ES-O.2 until all RCS temperatures are less than 200°F,

then transition to GO-6 , Unit Shutdown From Hot Standby To Cold Shutdown .

D. Lower VCT pressure ;

Start the other 3 RCPs and imm ed iatel y tran sition from ES-O .2 to GO- 6, Unit Shutdown

From Hot Standby To Cold Shutdown .

86 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 87

Given the following:

Unit 1 is at 100% power.

1-SI-99-10-B, 31 Day Functional Test of SSPS Train B and Reactor Trip Breaker B, is in

progress with Reactor Trip bypass breaker (BYB) closed.

Appendi x F, Reactor Breaker Repla cement. of 1-SI-99-1 O-B is in progress with Reactor

Trip Breaker B (RTB) racked out.

A feedwater transient occurs due to an electrical power loss , resulting in the MCR

operator MANUALLY tripping the reactor.

When Tavg , Pressurizer Pressure, and SG leve ls are stabi lized post trip , the following

conditions are observed :

All 4 Diesel Generators running but NOT connected to the shutdown boards.

All Reactor Trip Breaker and Reactor Trip Bypass breaker indicating lights on 1-M-4 are

DARK except for the GREEN light on the Reactor Trip Bypass Breaker B (BYB) which is

LIT .

Which ONE of the following identifies both the position of Reactor Trip Breaker A (RTA) and the

correct SRO decision relative to completing 1-SI-99-10-B following the stabilization of the plant

and the electrical power restoration?

RTA Position 1-51-99-10-8 Status

A. Closed The surveillance is required to be completed.

B. Closed The surve illance is NOT required to be completed with the plant

in this Mode .

C. Tripped The surveillance is required to be completed .

D. Tripped The surveillance is NOT required to be completed with the plant

in this Mode.

87 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 88

Give n the following :

Following a reactor trip the plant experienced a total loss of fee dwater .

The condition ca used the crew to initiate RCS bleed and feed .

SUbseque ntly the TDAFW pump was restored to service and the crew is ready to

est ablish AFW flow to the selected steam generator.

Other plant co nditions includ e:

o Selected SG Wi de Ran ge level is 4% .

o RCS loop hot leg temperature at 558 °F.

o Core exit thermocouple temperatures are RISING.

In acc ordanc e with FR-H .1, Loss of Secondary Heat Sin k, fe edwater flow will be re-establish ed

to the sele cted SG at ...

A. the minimum detectable flow gpm .

B. less than 100 gpm unti l WR level >15%.

C. a rate that causes wide range leve l to rise and RCS hot leg to drop.

D. a maximum rate .

88 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 89

Given the following conditions:

The plant is shutdown In Mode 4 with all safety related equipment operabl e.

During the perfo rmance of surveillance 0-SI-215-21-A, DIESEL GENERATOR 1A-A

BATTERY QUARTERLY INSPECTION, it is reported that the Float Voltage values for

three (3) connected cells are as follows:

Cell 17 = 2.09 v

Cell 34 = 2.06 v

Cell 39 =2.12 v

ALL othe r conn ected cells have Float Voltage values greater than 2.13 v.

AL L other parameters measured during the above surve illance are norm al.

Which ONE of the following describes the status of DG 1A-A battery AND of the DG 1A-A?

REFERENCE PROVIDED

Status of Battery Status of DG 1A-A

A. Battery is degraded but it can NO Tech Spec or tracking only entry

be considered operable for 31 days. requir ed for DG.

B. Battery is degraded but it can Tech Spec tracking only entry requ ired for DG.

be cons idered operable for 31 days.

C. Battery is inoperable. DG is inoperable and Tech Spec tracki ng only

entry is required .

D. Battery is inoperable . DG is inoperable and Tech Spec entry

is requ ired .

89 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 90

Given the following conditions:

Unit 1 is operating at 100% power.

ERCW strainer 28 -8 plugs.

It is determined that the strainer must be isolated.

Which ONE of the following identifies the action direc ted by AOI-13 , Loss of Essential Raw

Cooling Water, to mitigate the isolation of the 28 strainer and the PSA risk status the plant will

be in due to the strainer isolation?

AOI-13 actions PSA risk

A. Realign cool ing water to the A train diesel generators. Orange

8. Crosstie the 28 heade r with the 1A header until strainer is repaired . Orange

C. Realign cooling water to the A train diesel generators. Red

D. Crosstie the 28 header with the 1A header until strainer is repaired . Red

90 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 91

Given the following plant condit ions :

During a startup, the plant is in Mode 4.

GO-1, Appendix C, Mode 4-to-Mode 3 Review and Approval, has been completed up to

the last step , Operations Superintendent Hold Point , for granting approval to enter Mode

3.

During scaffolding removal activ ities, a worker contacts the air line to 1-FCV-62-93,

Charging Flow Control Valve , resulting in pulling the air line loose from the valve

operator, such that the air system remains intact, due to crimp ing of the line on the air

supply side of the break .

Which procedures will the Unit Supervisor use to respond to this event and the basis for taking

quick action to limit the effects?

A. The Unit Supervisor will use AOI-1 0, Loss of Control Air to direct actions to prevent

Pressu rizer level from excee ding 92% in order to maintain the presence of a steam

bubble in the pressurizer.

B. The Unit Supervisor will use AO I-10, Loss of Control Air, and direct actions to prevent the

level decrease to less than 17% to ensure subcooling margin can be maintained.

C. The Unit Sup ervisor will use SOI-62.01, CVCS-Charging and Letdown and direct actions

to prevent the level decrease to less than 17% to ensure subcooling margin can be

maintained.

D. The Unit Supervisor will use SOI-62 .01, CVCS -Charging and Letdown , to direct actions to

prevent Pressurizer level from exceeding 92% in order to maintain the presence of a

steam bubble in the pressurizer.

91 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 92

Given the following :

Unit 1 wa s operating in Mode 1 at 14% reactor power.

A loss of condenser vacuum occurs resulting in an automatic turbine trip .

The operating crew stabilizes the plant.

Which ONE of the following identifies both how the conden ser circulating water box t:. Ts wi ll be

affec ted and the notifica tions requ ired due to the turb ine trip in accordance with SPP-3.5 ,

Regulatory Reporting Requirements?

Water Box t:.T Notifications required

A. Rises Internal TVA not ifications only

B. Rises NRC and Internal TVA not ificat ions

C Lowers Internal TVA notifications only

D. Lowers NRC and Internal TVA notifications

92 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 93

Give n the following :

At0100 Unit 1 entered Mode 3 dur ing shutdown for a refueling outage .

At0200 AOI-7 .01, Maximum Probable Flood , was implemented due to extremely

heavy rainfall in the upstream watershed .

At 1100 The plant is in Mode 4 on RHR with cooldown in progress with the RCS

pressu re 320 psig and temperatu re 22 0 0 F.

At 1200 River Syst em Op eration s (RSO) confirms the flood leve l at the plant is

predicted to crest at EI. 730' within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Which ONE of the follo wing identifies both the Flood Stage Preparation level(s) that is/are

req uired to be compl eted . and how the cooling of the core will be maintained in accorda nce with

AOI-7 after the preparations are complete ?

A. Only the proc edure for Stage 1 Preparations is required to be completed .

Core cooling will be mainta ined by the steam generators with water being supplied by high

pre ssur e fire protection with the RHR system removed from service .

B. Only the procedure for Stage 1 Preparations is required to be completed .

Core cooling will be maintained by the Spent Fuel Pool coo ling system crosstied with the

RHR system .

C. Both Stage 1 and Stage 1/ Preparations procedures are required to be completed.

Core cooling will be mainta ined by the steam generators with water being supplied by high

pressure fire protection with the RHR system removed from service.

D. Both Stage 1 and Stage II Preparations procedures are required to be completed.

Core coo ling will be maintained by the Spent Fuel Pool cool ing system crosstied with the

RHR system .

93 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 94

Which ONE of the following satisfies the require ment of FHI- 7 for the maximum numb er of fuel

assembl ies allowed outside of approved storage ?

A. Two unirradiated assembl ies within the fuel-handling area .

B. Two irradiated assemblies within the spent fuel storage pool boundary.

C. One assembly in the transfer cart, two assemblies in the RCCA fixture and one assembl y in

the refuel ing machine mast over its proper location in the reactor vessel.

D. One assembly in the transfer cart , two assemblies in the RCCA fixture and one assembl y in

the refuel ing machine mast over the reactor side upender.

94 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 95

With the plant at full power, the Chem istry Lab has just informed the Unit Supervisor that the

RCS chlori de level is 1650 ppb and that the SG chlo ride level is 200 ppb . The source of any

impurity ingress has NOT yet been identified.

Based on the reported values, (1) what is the MOST restrictive Action Level that must be

entered and (2) the impact on plant opera tions caused by the Action Level entry?

ill

A. Action Level 3 for RCS chloride level Initiate actions to take the reactor sub-critical

as quickly as practicable in a controlled

manner and reduce RCS temp erature to

< 250* F.

B. Action Level 3 for SG chloride level Initiate actions to take the reactor sub-critical

as quickly as practicable in a controlled

mann er and reduc e RCS tem peratu re to

< 250* F.

C. Action Level 2 for RCS Chloride level Restore parameter to below Action Level 1

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or reduce reactor power to less

than 5%.

D. Action Level 2 for SG Chloride level Restore param eter to below Act ion Level 1

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or reduce reactor power to less

than 5%.

95 of 10 0

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 96

Given the following

Unit 1 at 100% power.

Diesel Generator (DG) 2A-A is to be removed from service for a maintenance outage

with a planned out of service of 102 hours0.00118 days 0.0283 hours 1.686508e-4 weeks 3.8811e-5 months .

Which ONE of the following identifies Unit 1 equipment that is listed in Tech Spec 3.8.1, AC

Sources Operating , Bases Cont ingency Actions , as equipment that is to remain in servic e

concurrently during the DG 2A-A outage maintenance to be in compl iance with the Tech Spec?

A. Reactor trip breaker A (RTA ).

B. TDAFW pump.

C. RHR Pump 1B-B .

D. Any S/G AFW level control valve .

96 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 97

Which ON E of the following identifies BOTH the minimum decay time required to allow the

conten ts of a Gas Decay tank to decay prio r to release and who can waive the minimum time in

accordance with SOI-77 .02, Waste Gas Dispos al system?

Decay Time Required Who Can Waive

A. 60 days Chemistry Duty Manager

B. 60 days Rad iation Prote ction Manag er

C. 8 days Chem istry Duty Manager

D. 8 days Radiation Protection Manager

97 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 98

Giv en the following plant conditions:

Unit 1 is in Mode 4 with preparations being made for fuel moves.

As part of performing the Channel Operational Test (COT) for 0-RM-90 -102, Spent Fuel

Pool Pit Area Monitor, a source check is to be performed.

What is the effect of performing the source check portion of this test , and what is the SRO 's

responsibility for Tech Spec/LCO Tracking Sheet ent ry?

A. This will result in an automatic actuation of Train A of ABGTS . The SRO will mak e an entry

on the LCO Trac king Sheet that Tra in A of ABGTS is inoperable.

B. RM-90-102 output will be blocked during the source check, the SRO will make an entry on

the LCO Tra cking Sheet that Tra in A of ABGTS is inoperable.

C. RM-90- 102 outp ut will be blocked during the source check , the SRO will make an entry on

the LCO Tracking Sheet that RM-90-1 02 is inoperable.

D. This will result in an automatic actuation of Train A of ABGTS . The SRO w ill make an entry

on the LCO Tracking She et that RM-90-102 is inoperable.

98 of 100

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 99

Given the follow ing:

Unit 1 experiences a Safety Injection due to a steam generator tube ruptu re on SG #1.

All Reactor Coolant Pumps were remov ed from service due to loss of support systems .

RCS cooldow n at maximum rate to target incore temperature is in progress .

The STA reports that a RED path for FR-P .1, Pressurized Thermal Shock, exists on

RCS Loop 1 on the FR-O, Status Trees .

Which ONE of the following identifies when the transition to FR-P.1 should be made?

A. Immediately trans ition to FR-P .1 from E-3 because FR-P .1 prov ides actions to limit

cooldown and repressurization of the RCS.

B. Remain in E-3 until the cooldown is complete and then transition to FR-P .1 only if the RED

path still exists because the cooldown is needed to allow depressurization of the RCS.

C. Remain in E-3 until the cooldown is complete and then transition to FR-P .1 even if the RED

path no longer exists becau se the cooldown is needed to allow depressurization of the RCS .

D. Remain in E-3 until the safety injection is terminated, then trans ition to FR-P.1 only if the

RED path still exists because FR-P .1 provides actions to limit cooldown and repressurization

of the RCS .

99 of 10 0

Watts Bar Nuclear Plant

2008 Initial License Written Exam

SENIOR REACTOR OPERATOR

Question Number: 100

Given the following conditions:

The plant is at full power.

A report was received of a tornado being sighted over the Wa tts Bar Training Center,

movin g in a northwest direction . The torn ado continued to move across Highway 68 and

then dissipated without touching down onsite.

The MCR crew has just entered AOI -8, Tornado Watch or Warning .

Confirmation was received that no vis ible dam age had been received to any structu res

or equipment on site.

The Shift Manager evaluates the Rad iological Emerg ency Plan (REP ) and determines

the conditions for an NOUE were initially met but are now fully resolved .

Whi ch ONE of the following identifies the ODS and NRC notification requirements in

acc ordance with the REP ?

ODS notification NRC Notification required within:

A. Report but not declare 15 minut es.

the event.

B. Report but not declare 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

the event.

C. Declare and terminate the 15 minutes .

event at the same clock time.

D. Declare and terminate the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

event at the same cloc k time.

100 of 100

Battery Ce ll Parameters

3.8.6

3 .8 ELECTRI CAL POWER SYSTEMS

3.8.6 Battery Cell Parameters

LCO 3 .8 .6 Battery c el l parameters f or 1 25 V v i t a l ba tteries and 125 V

diesel g ener at o r (DG) batteries shall b e within the lim its

of Table 3.8 .6 -1 .

APPLICABILITY : When associated DC electrical p o we r su bsystems and DGs are

required to be OPERABLE .

ACTI ONS

--- -- - -- -- -- - -- - -- --- - - -- - - - - -- - - --- -NOTE -- - - - - - - -- - - - - -- - - -- - - - - --- - - - -- -----

Separate Conditi on entry is all owed for each battery bank.

CONDI TI ON REQUIRED ACTION COMPL ET ION T IME

A. One or more A .I Ve r ify pilo t cells 1 h our

batt e ries with one e lectro lyte level and

o r more battery f loa t v o l t a g e meet

ce ll parameters n ot Table 3 . 8 . 6 - 1

within Category A Ca t e g o r y C l i mi t s .

or B limits .

AND

A.2 Ve r i f y batter y cel l 2 4 h ours

parameters meet

Ta ble 3 .8. 6-1 AND

Category C limits .

Once p e r 7 days

thereaft e r

AND

A .3 Restore battery c e l l 31 d a y s

parame ters t o

Ca t e g o r y A and B l i mi t s

o f Table 3 .8 .6 - 1 .

(c ontinu ed)

Wat t s Ba r - Un i t 1 3 .8 -33

Batter y Ce l l Paramet e rs

3.8 .6

ACTI ONS (cont i n ued )

CONDIT IO N REQUIRED AC T IO N COMP LETIO N TIME

B. Re q ui re d Acti o n B.1 De clare as s o ci ate d I mme d i a t e l y

and a ss o ci at e d battery i nop erab le.

Comp l e t i o n Time o f

Co nd i t i o n A no t

met .

OR

One o r mo r e

batter i e s with

average

ele ctr ol yt e

t emperat ure o f the

repr esentati ve

c e l l s < 60 °F f or

v it al b a tt e r i e s

and < 5 0°F f o r DG

ba t t eries.

OR

On e o r mo r e

bat teries wit h one

or more ba t te r y

ce ll paramet ers

no t wit hi n

Categ ory C v a l ue s .

SURVE I LLANCE REQUIREMENTS

SURVEI LLANC E FREQUENC Y

SR 3 . 8 .6 .1 Ve r i f y batter y cel l paramet e r s me e t 7 da ys

Table 3 .8 .6 - 1 Ca te g o ry A lim it s.

(c o ntin u e d)

Wa tts Ba r-Un i t 1 3 .8 -3 4

Batt er y Ce l l Pa r amet er s

3.8.6

SURVEIL LANC E REQUI REMENTS (c ontinu e d)

SURVEILLANCE FREQUEN CY

SR 3 .8 .6 .2 Ve r i fy batt er y c e l l p ar a me t ers meet 92 days

Table 3 .8 . 6- 1 Categor y B l imits .

AND

On c e wi thin

2 4 h ours after a

ba t tery

disc harge

< 11 0 V f or

v i t a l batterie s

(113 . 5 V f o r

v i t a l battery Vi

o r 1 0 6. 5 V f or

DG batt eries

AND

On c e wi t h i n

24 h ours a f ter a

batter y

ove rc ha r ge

> 1 5 0 V f or

v i t a l batt eri e s

(1 5 5 V f o r v it a l

batte r y V) o r

1 45 V f or DG

b att e ri e s

SR 3 .8 .6.3 Ve r i fy a verage el e ctrol yt e t e mp e r a t u r e 92 d a ys

o f repres entati v e c e l ls is ~ 60 °F f or

v it a l batt eries and ~ 50°F f or the DG

batter ie s.

Wa tts Ba r - Un i t 1 3 .8 -35

Batte r y Cell Pa r a me te r s

3 .8 .6

Tabl e 3 . 8.6 - 1 (p age 1 o f 1 )

Battery Ce l l Parameters Requi rements

CATEGORY A: CATEGORY B: CATEGORY C :

PARAMETER LI MITS FOR EACH LI MITS FOR EACH ALLOWAB LE LIMIT

DESI GNATED PILOT CONNECTED CELL FOR EACH

CELL CONNECTED CELL

El ectr o l y t e Leve l > Min imum level > Min imum l e vel Above t op o f

in dicati on mark, indi cati on mark, plat e s, an d n ot

and s: 1 /4 inch and s: 1 /4 inch ove r flo wi ng

ab ove max imum a bove ma x i mum

l e vel indicati on l evel in d ic ati on

mark (a) ma rk (a)

Fl oat Vol t a g e ~ 2 . 13 V ~ 2 .13 V > 2 .07 V

Sp e c i fi c Gr avity ~ 1 . 200 ~ 1 .195 Not more than

(b ) (c) 0. 02 0 b e l o w

AND a ve ra g e of all

- - c on nected c e l l s

Average o f all

connected cells AND

> 1 . 205

- -

Aver age o f all

c onn ec t ed c ell s

~ 1.195

(a ) It is a c ceptable f or t he electrol yte level to tempora rily increase abo ve

the specified max i mum level during e q u a l i z i ng c ha r g es pr o vi ded i t i s not

ove r f lo wi n g .

(b) Co r rec t e d f or ele ctr ol yte t e mpe ratu r e and le ve l . Lev el co r rect ion i s

no t r e q u i r e d , h o we v e r, when batter y c h a r g in g is < 2 amps when on fl oat

charge f o r v i t a l batteries and < 1.0 amp f or DG batte rie s.

(c ) A batt er y c ha r g i ng c u r r e n t o f < 2 amps when o n f l o a t c h a r g e f o r v it al

bat t e r ies an d < 1. 0 amp f or DG b att e r i es i s a c cept a b le f o r me etin g

s p eci f i c gravi ty lim its f o l l o wi ng a batt e ry r e c h a r g e , f or a max i mum o f

3 1 da y s . When c h a rg i ng cur rent i s use d t o sa ti sf y spec i fic g ravi ty

requi remen ts , specif ic g ra vity o f ea ch c on nected c e l l shal l b e measured

p r i o r t o expirati on o f t h e 31 da y a llowanc e .

Watt s Bar-Unit 1 3 .8 -3 6

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Watts Bar 2008-301 Written Examination Key:

RO EXAM

1 C

2 0

3 C

4 A

5 B

6 C

7 0

8 C

9 0

10 B

11 C

12 A

13 0

14 C

15 0

16 C

17 C

18 A

19 C

20 C

21 A

22 C

23 C

24 A

25 B

26 C

27 A

28 A

29 B

30 0

31 C

32 B

33 C

34 B

35 A

36 B

37 B

38 0

39 A

40 0

41 0

42 A

43 C

44 A

45 0

46 C

47 0

48 B

49 C

50 C

51 A

52 C

53 0

54 A

55 A

56 A

57 0

58 0

59 C

60 0

61 C

62 A

63 C

64 C

65 0

66 A

67 0

68 0

69 C

70 C

71 B

72 0

73 B

74 C

75 B

SRO EXAM

76 C

77 B

78 A

79 0

80 0

81 B

82 B

83 0

84 C

85 B

86 0

87 C

88 0

89 0

90 0

91 0

92 C

93 C

94 C

95 A

96 A

97 A

98 C

99 0

100 B

ML081900145

Text

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