Text

Initial Exam 2015-301 Final SRO Written Exam
	ML15222A548
Person / Time
Site:	Watts Bar
Issue date:	08/10/2015
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	50-390/15-301, 50-391/15-301
	Download: ML15222A548 (127)
	v • d • e

2015-301 NRC Exam Legend Times are presented as u U*LImm*Lii [ ((1:[1[:((1 :SE::S9] and appear in the DIGITAL font.

ALARM WINDOWS LIT DARK RADIATION MONITOR INDICATIONS LIT DARK PUSH PUSH TO RESET TO RESET HIGH ALERT ALERT OPERATE OPERATE

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1.

In accordance with 1-E-O, Reactor Trip or Safety Injection, which ONE of the following describes how the OAC ENSURES the turbine is tripped and the required action(s) if the OAC cannot ENSURE the Turbine Trip?

The OAC is required to ENSURE Turbine Trip using (1)

If the OAC cannot ENSURE Turbine Trip, 1-E-O directs them to (2)

A. (1) indication that all turbine stop valves are CLOSED (2) TRIP turbine locally B. (1) indication that all turbine stop valves are CLOSED (2) CLOSE MSIVs and bypasses C. (1) a GREEN light indication at 1-HS-47-24, Turbine Trip (2) TRIP turbine locally D. (1) a GREEN light indication at 1-HS-47-24, Turbine Trip (2) CLOSE MSIVs and bypasses

2.

Given the following conditions:

- Unit 2 is at 100% power.

Subsequently:

- PZR pressure is rapidly LOWERING.

- The Reactor was MANUALLY tripped.

- PZR level is rapidly RISING.

Which ONE of the following describes the accident in progress?

A. Ejected control rod B. SBLOCA on a RCS cold-leg C. Feedline break inside of containment D. PZR level detector condensing pot rupture

3.

Given the following conditions:

- Unit I has experienced a SBLOCA.

- RCS pressure is 1700 psig and STABLE.

- PZR level is 20% and slowly LOWERING.

- Containment pressure peaked at 1 .5 psig and is slowly LOWERING.

- Safety Injection Pump lA-A failed to AUTOMATICALLY start.

Which ONE of the following completes the statements listed below?

In accordance with 1-E-l, Loss of Reactor or Secondary Coolant, the control room staff will control SG NR levels between (1) and 50%.

To RAISE injection flow rate, the crew could (2)

A. (1) 29%

(2) LOWER the #2 SG PORV setpoint B. (1) 39%

(2) LOWER the #2 SG PORV setpoint C. (1) 29%

(2) MANUALLY start the Safety Injection Pump lA-A D. (1) 39%

(2) MANUALLY start the Safety Injection Pump lA-A

4.

Which ONE of the following describes the method used to remove decay heat 5 minutes after a LBLOCA has occurred?

A. Reflux boiling B. RCS Hot Leg recirculation C. Natural circulation and SG steaming D. ECCS injection and inventory loss from the break

5.

Given the following conditions:

- Unit 1 is at 100% power.

- 1-FCV-62-93, CHARGING HEADER FLOW is in AUTOMATIC.

- Letdown flow is 75 gpm.

Subsequently:

- A failure causes 1-HIC-62-93A, CHARGING FLOW PZR LEVEL CONTROL to output a FULLY CLOSED signal.

Which ONE of the following describes the MINIMUM indicated CHARGING FLOW AND the response of Annunciator CHARGING FLOW HI/LO (108-A)?

The MINIMUM which 1-Fl-62-93A, CHARGING FLOW, will read is (1) gpm.

Annunciator 108-A will alarm at (2) value as/than it would IF letdown flow HAD BEEN 45 gpm.

A. (1) 0 (2) the SAME B. (1) 0 (2) a DIFFERENT C. (1) 33.5 (2) the SAME D. (1) 33.5 (2) a DIFFERENT

6.

Given the following conditions:

- Tavg is 250°F and stable following a refueling outage.

- 1-PCV-68-334, PZR PORV 334, is INOPERABLE.

- Unit 1 RCS pressure is 350 psig and RISING uncontrollably.

- The operating crew is implementing 1-AOI-14, Loss of RHR Shutdown Cooling section 3.4, RCS High Pressure during RHR Shutdown Cooling.

/

PCV-68-340 U,

I 1000 0

U)

U 500 .___

Acceptable U

70 100 150 200 I

250 I

275 300 350 450 RCS Temp (degrees F)

Which ONE of the following completes the statement below?

RHR overpressure protection is A. NOT functioning as the RHR system is currently exposed to pressures greater than its design and must be immediately manually isolated B. FIRST provided because the RHR system will automatically isolate from the RCS at 370 psig C. FIRST provided because a relief valve located on the common suction line of the RHR system will lift and maintain pressure at 450 psig D. FIRST provided because 1-PCV-68-340, PZR PORV 340, will lift and maintain system pressure at 500 psig

7.

Given the following conditions:

- ONLY ONE SG is ruptured.

- The crew is implementing 1-ECA-3.3, SGTR Without PZR Pressure Control.

- Step 2(a), CHECK RCP(s) RUNNING to provide normal PZR spray, is in progress.

Which ONE of the following completes the statement below?

Step 2(a) of 1-ECA-3.3 PREFERENTIALLY starts A. EITHER the loop one or the loop two RCP because either, by itself, will provide adequate spray flow B. ONLY the loop two RCP because it, by itself, provides adequate spray flow C. ANY ONE intact loops RCP because hydraulic stresses will be minimized and adequate spray flow will be provided D. Three RCPs because ONLY by running a MINIMUM of three RCPs will adequate spray flow be provided

8.

Given the following conditions:

- Unit 1 is at 100% power.

RCP UV&UF RCP BOARD UNDERVOLTAGE OPTION #1 OPTION #2 With Unit 1 REMAINING at 100% power, which ONE of the following completes the statements listed below?

The MCR indication shown in (1) would indicate that an ATWS exists and would require that (2)

NOTE: 1-FR-S. 1, Nuclear Power Generation/A TWS A. (1) Option #1 BY ITSELF (2) 1-FR-S.1 be entered immediately B. (1) Option #2 BY ITSELF (2) 1-FR-S.1 be entered immediately C. (1) Option #1 BY ITSELF (2) 1-FR-S.1 be entered ONLY if a manual reactor trip is not successful D. (1) Option #2 BY ITSELF (2) 1-FR-S.1 be entered ONLY if a manual reactor trip is not successful

9.

Given the following timeline:

fiElliE 1-ES-3.3, Post-SGTR Using Steam Dump is in progress on Unit 1.

L1fl:E 1:fl The crew is depressurizing the ruptured SG to 400 psig using steam dumps.

HII1 Step 15. d. is currently being performed to STOP depressurization of the Ruptured SG.

EWH 1-FCV-1-103, CONDENSER A MAIN STEAM DUMP VLV, FAILS to CLOSE from the MCR.

E1 An AUO is dispatched to MANUALLY isolate the failed steam dump.

Which ONE of the following completes the statements listed below?

At U:L2:LU a MAXIMUM of (1) steam dump valves can be OPENED.

An AUO (2) manually isolate ONLY 1-FCV-1-103.

A. (1) 3 (2) can B. (1) 12 (2) can C. (1) 3 (2) can NOT D. (1) 12 (2) can NOT

10.

Given the following conditions:

- Unit 1 was at 100% power.

- Unit 1 has a faulted SG.

Which ONE of the following completes the statements listed below?

In accordance with the Westinghouse background document for 1-E-2, Faulted Steam Generator Isolation, a reason for ensuring that the MSIVs and bypass valves are CLOSEDisto (1)

Operators (2) REQUIRED to manipulate equipment to ensure that the MSIV bypass valves are CLOSED.

A. (1) prevent a sustained return to power (2) ARE B. (1) prevent a sustained return to power (2) ARE NOT C. (1) isolate the break and isolate the SGs from each other (2) ARE D. (1) isolate the break and isolate the SGs from each other (2) ARE NOT

11.

Given the following conditions:

- Unit 1 is at 100% power.

Subsequently:

- The #2, #3 and #4 S/Gs STM-FLOW & NR LEVEL recorders are STABLE AT VALUES EXPECTED FOR NORMAL 100% POWER OPERATIONS.

- The #1 SIG STM-FLOW & NR LEVEL recorder indicates as follows:

STM-FW FLOW & NR LEVEL SG1 LL (FEEN SFLC/ --

Which ONE of the following describes the event which caused the indications shown above?

A. Loss of control air to the MFW Reg Valve B. A feed line break in the steam vault room C. A failure of the main feed pump speed control D. A feed line break at the outlet of the A-I feedwater heater

12.

Which ONE of the following describes a potential implication if SG Pressure is reduced to 50 psig during depressurization of SGs in accordance with 1-ECA-0.0, Loss of All AC Power?

A. A RED Path on PTS may occur B. Natural Circulation may be impeded C. Unacceptable Upper Head Voiding may occur D. The integrity of the RCP seals may be challenged

13.

Given the following portion of the wiring diagram for the lA-A CCP:

+c. 4c cP 0 0 uvy uvX 1 lIE cP I 0

BOY BOX nNC 12 AX-laLØ CP INST : c AXlA 6

14 10262108A I -62X621 08-A Excerpt from 1-45W760-62-1 Which ONE of the following completes the statements below?

The BLACKOUT (BOX/BOY) contacts which are depicted in the print excerpt shown above are drawn in the state.

In accordance with NPG-SPP-31.1, Document Control, if l-45W760-62-1 were downloaded and printed from BSL (Business Support Library), the copy printed (2) be used for plant work WITHOUT further verification.

(1) (2)

A. BLACKOUT may B. BLACKOUT may NOT C. normal board energized may D. normal board energized may NOT

14.

Which ONE of the following describes the procedural guidance contained in the AOls AND the reason for the action?

For a loss of 120V AC Vital Instrument Power Board (1) the related AOl ALWAYS requires that the Unit I reactor be tripped.

This is based on the condition that (2) CANNOT be controlled.

A. (1) 1-I (2) SG level B. (1) 1-I (2) PZR level C. (1) 1-lV (2) SG level D. (1) 1-IV (2) PZR level

15.

Given the following conditions:

- Unit 1 is at 100% power.

- CCS Pump 2A-A is running.

- ALL 480V SDBDs have control power aligned to their NORMAL feeds.

Subsequently:

- 125V DC Vital Battery Board III is de-energized.

Which ONE of the following describes the response of CCS Pump 2A-A AND its handswitch indicating lights?

CCS Pump 2A-A WILL (1)

The indicating lights on 2-HS-70-59A, CCS PMP 2A-A are (2)

A. (1) TRIP (2) LIT B. (1) TRIP (2) NOT LIT C. (1) CONTINUE RUNNING (2) LIT D. (1) CONTINUE RUNNING (2) NOT LIT

16.

Given the following conditions:

- Unit 1 is at 100% power.

Subsequently:

- Unit 1 experienced a LBLOCA.

- The following VALID indications are noted:

RH RIOVCS PIPE BREAK STATUS RHR HX A RM BliP HX B PM RHR PMP PM A RHR PMP RM B LETOOWII HX PIPE BREAK PIPE BREAK PIPE BREAK PIPE BREAK PIPE BREAK 1-XI-30-5238A E E1-XI-3O-5239A 1-XI-3O-5236A 1-XI-3O-5237A 1-Xl-304235A

. 0 . .

RHR HX A RM RHR HX B RM RHRPMPRMA RHRPMPRMB LETLIOWII HX PIPE BREAK PIPE BREAK PIPE BREAK PIPE BREAK PIPE BREAK A 1-XI-30-5236B 1-XI-30-5237B 1-XI-30-5235B

. 0 . .

d

- ECA-1 .2, LOCA Outside Containment has been completed.

- RCS pressure is RISING.

Which ONE of the following completes the statements listed below?

The INCREASED (1) in the applicable room caused the indicated lights to illuminate.

After the completion of ECA-1 .2, RHR flow to (2) cold legs exists.

A. (1) TEMPERATURE (2) 2 B. (1) TEMPERATURE (2) 4 C. (1) PRESSURE (2) 2 D. (1) PRESSURE (2) 4

RHR/CVCS PIPE BREAK STATUS HuH lix A HM P11k HX BRM P11k P4P PM A PHR PMP RM B LETDflWTI HX PIPE BREAK PIPE BREAK PIPE BREAK PIPE BREAK PIPE BREAK i-XI-O-238A E11-XI-3O-s23A L:*:1 1-XI$O-S236A 1 -XIO-!7A 1-XI-3O-5235

. 0 . .

RHR HX A PM PHR HX B RM RHRFMPREIA RIIR PMP PM B LETIJOWII HX PIPE BREAK PIPE BREAK PIPE BREAK PIPE BREAK PIPE BREAK I1-XI-O-S238B Ai-XI-30-5239B i-XI-2O-236B A I-XI-3O-!37B A i-XI-3-S23SB

17.

Given the following conditions:

- The TDAFWP is TAGGED OUT for maintenance.

- Unit I experiences a LOCA.

- lA-A MDAFWP TRIPs.

- lB-B MDAFWP is steam bound.

- 1-E-1 is in progress WHEN 125-B, CNTMT ISOL PHASE B is received.

- BOTH CCPs TRIPPED and cannot be restarted.

- ALL SG WR levels are 38%.

Subsequently:

- The crew transitions to 1-FR-H.1, Loss of Secondary Heat Sink.

Which ONE of the following completes the statements listed below?

In accordance with 1-E-1, the RCPs (1) stopped.

Upon entering 1-FR-H.1, the FIRST crew action(s) taken is to (2)

NOTE: 1-E-1, Loss of Reactor or Secondary Coolant A. (1) are NOT (2) initiate RCS bleed and feed B. (1) are (2) initiate RCS bleed and feed C. (1) are NOT (2) vent the I B-B MDAFWP and establish MD AFW pump flow D. (1) are (2) vent the I B-B MDAFWP and establish MD AFW pump flow

18.

Given the following timeline:

no*nri*nn i I nIi I irips.

E:2WE1 A Small Break LOCA occurs.

U:5EE The crew transitioned to 1-ECA-1 .1, Loss of RHR Sump Recirculation.

EIi The crew is performing the Response Not Obtained (RNO) for 1-ECA-1 .1, Step 1 9.b, ESTABLISH minimum ECCS flow for decay heat removal.

Which ONE of the following describes the MINIMUM ECCS flow rate that satisfies the RNO AND the basis for this requirement in accordance with the Westinghouse Background Document?

In accordance with Figure 1 of 1-ECA-1 .1, the MINIMUM ECCS flow rate is (1) gpm.

This step satisfies an overall objective of 1-ECA-1 .1 to (2)

REFERENCE PROVIDED A. (1) 325 (2) delay depletion of the RWST B. (1) 325 (2) ensure adequate RVLIS level C. (1) 350 (2) delay depletion of the RWST D. (1) 350 (2) ensure adequate RVLIS level

REFERENCE FOR QUESTION 18 Figure 1 of 1-ECA-1. I

WBN Loss of RHR Sump Recirculation 1-ECA-1.1

Unit I Rev. 0003 Figure 1 (Page 1 of 1)

Minimum SI Flow for Decay Heat vs. Time After Trip 700.0 600.0 500.0 400.0 4-300.0 200.0 100.0 0.0 10 100 1000 10000 Time After Trip (Minutes)

Page 29 of 35

19.

Given the following conditions:

- Unit 1 is performing a power ascension from 60% to 100%.

- In accordance with the Reactivity Management Plan, the OAC is withdrawing control rods and notices that CBD rod D12 has stopped moving with its group.

Which ONE of the following completes the statements listed below?

T/S, LCO 3.1.5 would FIRST NOT be met when D12 is GREATER THAN A. 10 steps from the other rods in its group B. 10 steps from the group step counter demand position C. 12 steps from the other rods in its group D. 12 steps from the group step counter demand position

20.

Given the following conditions:

Unit I is performing FR-l.2, Low Pressurizer Level.

RCS Subcooling indicates 0 °F.

Subsequently:

- APzrPORVOPENS.

RCS Pressure LOWERS 300 psia.

Which ONE of the following describes the response of PZR Level AND the reason for this response?

ACTUAL PZR Level will IMMEDIATELY be (1) than INDICATED PZR Level due to (2)

(1) (2)

A. HIGHER the change in specific volume of the PZR water B. HIGHER containment temperature and pressure RISING C. LOWER the change in specific volume of the PZR water D. LOWER containment temperature and pressure RISING

21.

Given the following conditions:

- Unit 1 Core offload is in progress.

- Audible count rate IS available in the MCR and the containment.

- N31, Channel I SRNI FAILS.

- Audible count rate IS NO LONGER HEARD in both the MCR and the containment.

- 1-AOl-4, Nuclear Instrumentation Malfunctions is entered.

Which ONE of the following describes the requirements regarding Core Offload and the required operator action in accordance with 1-AOl-4?

Core offload (1)

Audible count rate in the containment (2) be restored SOLELY by manipulating the switch highlighted in RED in the following picture.

UD 0 COUNT RATE CHANNEL

,t.:

I CW2I4EL SELECTOR 12 CN N31 N32 PYnTR (N f

a. kLTtER a.

ID cc too I

\_* \_*_ ,. -. . .

MN

. :cE OCOC L::cE OSC * *2 Al *2 GtC N_C . I NO 2 OVtPJT IIPJt 4PIST CUPU7 WWUT A. (1) must STOP (2) can B. (1) may CONTINUE (2) can C. (1) mustSTOP (2) can NOT D. (1) may CONTINUE (2) can NOT

22.

Given the following conditions:

- Unit 1 is in MODE 2.

Subsequently:

- 120V AC Vital Instrument Board 1-Il de-energizes.

Which ONE of the following describes the Unit 1 response to the failure?

IMMEDIATELY after the failure, the Unit 1 Reactor will (1)

(2) of the IRNIs remain(s) energized.

A. (1) TRIP (2) BOTH B. (1) TRIP (2) ONLY ONE C. (1) REMAIN CRITICAL (2) BOTH D. (1) REMAIN CRITICAL (2) ONLY ONE

23.

Which ONE of the following describes the control room indications AND the AUTOMATIC actions (if any) IF O-RFV-77-743J, GAS DECAY TANK J RELIEF FAILS OPEN?

(1) will provide indication of this failure to the main control room staff AND (2) automatically ISOLATE the release once it reached its HIGH alarm setpoint.

NOTE: O-RM-90-1 18A, WGDT RELEASE LINE 1-RR-90-400, SHIELD BLDG VENT MON A. (1) 1-RR-90-400 (2) WILL B. (1) 1-RR9O-4OO (2) WILL NOT C. (1) O-RM-90-118A (2) WILL D. (1) O-RM-90-118A (2) WILL NOT

24.

Given the following conditions:

- a VALID HIGH radiation condition in the Decontamination Room Area exists.

Which ONE of the following completes the statements listed below?

The affected area radiation monitor (ARM) will produce (1)

When the high radiation condition clears, the input to the MCR annunciator may be cleared by (2)

A. (1) an input into ONE COMMON MCR annunciator which serves other ARMs (2) depressing the affected modules red HIGH pushbutton on O-M-12 B. (1) an input into ONE COMMON MCR annunciator which serves other ARMs (2) resetting the ARM locally in the Decontamination Room C. (1) a MCR annunciator SPECIFIC to the Decontamination Room ARM (2) depressing the affected modules red HIGH pushbutton on O-M-12 D. (1) a MCR annunciator SPECIFIC to the Decontamination Room ARM (2) resetting the ARM locally in the Decontamination Room

25.

Given the following conditions:

- A plant fire has occurred.

- The control room staff has donned AirHawk SCBAs.

The AirHawk SCBA provides indication to its wearer of its air cylinder status through which of the following devices:

1. A cylinder pressure gauge

2. An audible alarm

3. Colored lights on a heads-up -display A. ONLY 1 B. ONLY 1 and 2 C. ONLY2and3 D. 1,2and3

26.

Given the following timeline:

O:JL:LIL Unit 1 is at 100% power.

hH:iE A Steam Line Break occurs inside CNTMT.

E9: L S The 1 B-B MDAFWP shears its shaft.

1iiH:9S CNTMT Pressure is 3.0 psig and RISING.

LlliiS1ifl ALL MSIVs are OPEN and attempts to close the MSIVs have FAILED.

JLW9IiIi lA-A MDAFWP TRIPS due to a motor fault.

E101 1-FR-P.1, Pressurized Thermal Shock is entered.

LU: U:E SG Narrow Range levels are:

SG1 SG2 SG3 SG4 1% 4% 3% 3%

U :D Feed flow has just been adjusted per 1-FR-P.1, Step 3.

Which ONE of the following describes the status of AFW?

At Efl: I :LILI, the operating crew has aligned AFW to Feed A. ALLSGsat4lOgpm B. ALL SGs at MINIMUM detectable flow C. ONLY the SG supplying the TDAFWP at 410 gpm D. ONLY the SG supplying the TDAFWP at MINIMUM detectable flow

27.

Given the following conditions:

Unit 1 tripped.

Offsite power was lost.

ES-O.4, Natural Circulation Cooldown With Steam Void in Vessel (without RVLIS) is in progress.

RCS Subcooling is 88°F.

SG Pressures are 915 psig and controlled.

Thot is slowly dropping.

Incore T/Cs are STABLE.

Tcold is 536 °F and STABLE.

Which of the following completes the statement below?

In accordance with 1-ES-O.4, Natural Circulation (1) established; (2)

A. (1) IS (2) decay heat is being removed by the SG PORVs B. (1) IS (2) decay heat is being removed by the by the steam dumps C. (1) IS NOT (2) the crew must dump steam at a greater rate using the SG PORVs D. (1) IS NOT (2) the crew must dump steam at a greater rate using the steam dumps

28.

Given the following timeline:

E[flJ Unit 1 is at 100% power.

Offsite power is lost.

flfl:flEi:fl The #3 RCP is de-energized.

flhl*flflflLj Ln11 I I .1 I irips.

+

Which ONE of the following describes how DNBR is affected and the RCP design feature that assists in RCS heat removal?

In accordance with the Final Safety Analysis Report (FSAR), at Oiü, the departure from nucleate boiling ratio (DNBR) is (1)

The MINIMUM heat removal needed to prevent core damage after the Reactor Trip is DIRECTLY ensured by (2)

A. (1) RISING (2) a flywheel attached to each RCP B. (1) LOWERING (2) a flywheel attached to each RCP C. (1) RISING maintaining the AVAILABLE RCPs connected to the generator and 2

external network for 30 seconds D. (1) LOWERING maintaining the AVAILABLE RCPs connected to the generator and 2

external network for 30 seconds

29.

Given the following conditions:

- Unit 1 is at 40%.

Subsequently:

- The #1 RCP trips.

Which ONE of the following describes the effect the RCP trip will have on INDICATED secondary plant parameters?

SG #1 Steam Flow WILL IMMEDIATELY (1)

Assuming NO OPERATOR ACTION occurs:

FIVE MINUTES AFTER the RCP trip, Feed Flow WILL be provided to the SGs via (2) feedwater.

(1) (2)

A. RISE AUX B. RISE MAIN C. LOWER AUX D. LOWER MAIN

30.

Given the following print excerpt:

I.

I T6NK62239 __

0TAMK-62-243 62&

.0 TANK C BORIC ACID TANK A IS. *11*

100F I4 lESION PRESS. ATM ci1C lESION TEMP 200F -HK C,c 1APR-ISO 1050 IRA IN COURO Cfl 1621056 OESICA PRESS ISO POTS 3 11I TEl.

20OF lESION SR 100 P510 1 01662-237 1

2A2 162-10530 l621055A DRAIN I62I0SSA )- 1-62IOSAA 224 J H I-62-1053A 62-10534 762-3924 2-fl06O 102-10528 ROB IC ACID l62-1052A I-FLTR-62-10 TRANS POUR DESIGN PRESS. 50 P510 7623954 COP-OS coM.235roA BORIC

ç23311 2-23I FILTEF 207 207 lESION 7 lESION

.__l-PI62-232 _.1P4p-6223o j 1-621063 302 302 rn 762306* 1 1623044 76210318 I621051A ROTE 18 NOTE A 7-6210508 I-62-1050A NOTE 18 NOTE TN

-621049 SARAtE 00664 OTT 18 CONT ON SO

,-T l-62-10 1 *780254 3 UNION CR0 8-3 I &PLUC 1627009 NOTE 18 0621046

Which ONE of the following states the purpose of the flowpath highlighted in yellow in the print excerpt shown above?

The highlighted line A. is used to manually makeup to the BAT A in accordance with O-SOl-62.05, Boric Acid Batching, Transfer, And Storage B. automatically maintains level in the Boric Acid Tank (BAT) A through the automatic action of 1-FCV-62-237, BAT A RECIRC CONTROL C. provides miniflow protection to the Boric Acid Transfer Pumps as 1-FCV-62-237 is normally THROTTLED OPEN to 25%.

D. provides the required chemical mixing of the BAT A as I -FCV-62-237 is normally THROTTLED OPEN to achieve a flow rate specified by Chemistry

31.

In accordance with 1-SOI-74.01, Residual Heat Removal System, which ONE of the following completes the statements below?

The RHR PMP A MINI FLOW valve will FIRST be demanded OPEN if the lA-A RHR pump flow falls below (1) gpm AND will FIRST be demanded CLOSED when the flow INCREASES above (2) gpm.

A. (1) 250 (2) 1100 B. (1) 250 (2) 1400 C. (1) 750 (2) 1100 D. (1) 750 (2) 1400

32.

Given the following conditions:

- Unit 1 is at 100% power.

Which ONE of the following describes the physical location of 1-BKR-74-2A, LOOP 4 HOT LEG TO RHR SUCTION (1-FCV-74-2) AND the NORMAL position of this breaker?

1-BKR-74-2A is located on a (1) board AND is required to be (2)

A. (1) RxMOV (2) ON B. (1) RxMOV (2) OFF & Locked C. (1) C&AVent (2) ON D. (1) C&AVent (2) OFF & Locked

33.

Given the following conditions:

- Unit 1 has suffered a large break LOCA.

- The following indications exist on 1-M-CNTMT LEVEL RWST LEVEL -

Based on these conditions, it is expected that transfer to the containment sump WILL A. occur, due to all required conditions having been met B. NOT occur due to RWST level being too high C. NOT occur due to containment sump level being too low D. NOT occur due to an SI signal still being supplied to the RHR sump valves

34.

Which ONE of the following describes the operation of the Primary Relief Tank (PRT)?

The PRT is cooled by dispersing primary water into the PRT the quench water level.

As primary water is added to the PRT, 1-FCV-.68-310, PRT Drain to the RCDT (2) AUTOMATICALLY cycle to maintain PRT level.

A. (1) ABOVE (2) WILL B. (1) ABOVE (2) WILL NOT C. (1) BELOW (2) WILL D. (1) BELOW (2) WILL NOT

35.

Given the following conditions:

- Unit I is at 100% power.

- The following is observed:

ico UJO go ..Lii LP-E TANI<

M4JELP uv

-,.. ui sL:pc-E T.NK 50 BE49sO49 t Rl1ItWfl 1-HS7fl..

P AUTO A AUTO S CLOSE OPEN CLOSE OPEN 1

7 40 40 23 20 LI I SIJPGE TNK LI 5.JRGE L.N A SCiE LEvEL SIDE LE.EL 1.U.70.99A Which ONE of the following completes the statements listed below?

The status of the Unit I A train CCS surge tank indicates that NOTE: 1-AOl-15, Loss of Component Cooling Water (CCS) 0-AOl-lU, Loss of Control Air A. conditions are NORMAL and that NO further actions are required B. Control air has been LOST to 1-LCV-70-63 and 1-FCV-70-66; 0-AOl-b WILL be entered C. CCS in-leakage is probable and section 3.4, CCS In-Leakage of 1-AOl-15 WILL be entered D. because the valve alignment for the CCS surge tank is correct, a leak exists on the Unit I A train CCS and section 3.3, CCS Out Leakage of 1-AOI-15 WILL be entered

36.

In accordance with 1-AOl-i 5, Loss of Component Cooling Water, which ONE of the following describes the required actions for a Loss of Component Cooling Water (CCS) with Unit 1 operating at 100% power?

The operating crew will initiate a Unit 1 reactor trip if the (1) CCS train is lost.

RCPs can be operated for a MAXIMUM of (2) minutes after loss of CCS flow.

(1) (2)

A. 1A 5 B. 1A 10 C. lB 5 D. lB 10

37.

Which ONE of the following describes the power supply to the 1 C and I D PZR heaters?

A. 480V Unit Boards B. 6.9kV Unit Boards C. 480V Shutdown Boards D. 6.9kV Shutdown Boards

38.

Which ONE of the following describes the EAGLE 21 system response to a Channel I input failure and the effect on the systems ability to calculate a trip setpoint?

If the channel I input for (1) FAlLS, EAGLE-21 will be unable to calculate a VALID setpoint for the channel I (2) trip.

(1) (2)

A. the PRNI OPz\T B. Loop 1 Flow OPz\T C. PZR Pressure D. Turbine Impulse Pressure OThT

39.

Which ONE of the following describes the power supply to a Reactor Trip Breaker UV Trip Coil?

A Reactor Trip Breaker UV Trip Coil power is supplied by a Board.

A. 48V-DC Plant Battery B. 125V-Vital DC Battery C. 120V-AC Preferred Power D. 120V-AC Vital Instrument Power

40.

Given the following conditions:

- Unit 1 is at 100%

- Testing is in progress on 1-PT-68-340, Channel I PZR PRESS.

- The bistables for 1-PT-68-340 have been TRIPPED.

Which ONE of the following describes the SSPS response (if any) to 1-PT-68-322, Channel IV PZR PRESS SUBSEQUENTLY failing LOW?

SSPS will A. initiate a Reactor Trip ONLY B. initiate a Safety Injection ONLY C. NOT initiate ANY actuation signals D. initiate BOTH a Reactor Trip AND a Safety Injection

41.

Given the following conditions:

- Unit 1 is at 100% power.

- ALL Containment Cooling is FULLY Operational in accordance with the SOIs.

Which ONE of the following describes an event which causes the following containment pressure transient?

A. A RCS leak inside of containment B. Securing one of the running Glycol chiller packages C. Securing one of the running lower containment coolers D. A leak downstream of 1-FCV-32-80, AUX AIR TO RX BLDG TR A in which AUX AIR A pressure DOES NOT drop below 90 psig.

42.

Regarding the following hand-switches:

Located on 1-M-6 Which ONE of the following describes the logic for a MANUAL actuation of a phase B Isolation?

A. The operation of ANY ONE of the 4 hand-switches will actuate BOTH trains B. The SINGLE operation of either 1-HS-30-64A or 1-HS-30-68A will actuate ONLY the A train C. The SEQUENTIAL operation of one pair of hand-switches (either those on 1-M-5 or those on 1-M-6) will actuate BOTH trains D. The SIMULTANEOUS operation of one pair of hand-switches (either those on 1 -M-5 or those on 1-M-6) will actuate BOTH trains

43. Given the following timeline:

nrI.flrI.rIfl uuj-Ju.uu Unit I is at 100% power.

rirn *rln uu.u .uu A LOCA occurs.

The following are observed on 1-M-6:

CNTMT PRESS CNTMT PRESS CNTMT PRESS CNTMT PRESS 1 -PDI-30-42 I -PDI-30-43 1 -PD 1-30-44 1 -PD 1-30-45 psig psig psig psig flfl.n:.flfl UU.UL.LJU 1.4 1.8 1.8 1.4 nn.nJ.flfl uu.uJ.uu 1.9 1.9 1.9 1.4 flflflLIflfl uu.u UU 3.0 2.7 2.7 3.0 nn.n nfl uu.uzI.uu 3.1 2.7 3.0 3.1 From the times and indications listed above, which ONE of the following completes the statement listed below?

The MSIVs would FIRST be expected to AUTOMATICALLY CLOSE at A flflflJflfl

l. UU.UL.UU B uu.uJ.uu

, nn.riunn L.. UU.U .UU r

U.

nn*n*flri UU.UJ.UU

44.

Given the following timeline:

fin-fin-fin uu.uu.uu 1-SOl-2&3.01, Condensate and Feedwater System Section 5.7, Bypass Reg to Main Reg Transfer (Method 2) is IN-PROGRESS.

fifi.fin.fi The BOP Operator is performing step [3] CONTROL MFW Reg. in MANUAL to maintain SG level: [1-M-3].

fin-fl i-nn uu.u i.uu SG 1 MEW REG VLV is bound at 10% OPEN and is determined to be INOPERABLE.

Which ONE of the following completes the statements below?

At LILI:Li :LILI, T/S LCO 3.7.3 Main Feedwater Isolation Valves (MFIV5) and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves is (1)

Following a Reactor Trip, the valves described by T/S 3.7.3 will FIRST receive a closure signal when RCS Tavg drops to less than (2) °F.

(1) (2)

A. MET 550 B. MET 564 C. NOT MET 550 D. NOT MET 564

45.

Given the following conditions:

- Unit 1 is at 3% power.

- The MDAFWPs are in service supplying the SGs.

- 1-POS-3-164, positioner to 1-LCV-3-164, air output FAILS to 0 psig.

- 1-POS-3-164A, positioner to 1-LCV-3-164A, air output FAILS to 0 psig.

Which ONE of the following describes the response of the NORMAL AND BYPASS Level Control Valves?

The NORMAL level control valve 1-LCV-3-164 will (1)

The BYPASS level control valve 1-LCV-3-164A will (2)

NOTE: 1-LCV-3-164, MD AFW PUMP IA-A SG 1 LEVEL CONTROL 1-LCV-3-164A, SG 1 AUXFEEDWATER I-FCV-3-164 BYPASS (1) (2)

A. OPEN OPEN B. OPEN CLOSE C. CLOSE OPEN D. CLOSE CLOSE

46.

Given the following conditions:

- Unit 1 is at 100% power.

Subsequently:

- An electrical board fails.

- The following indications are observed:

I REACTOR COOLANT SYSTEM 1-M-5

/

/ -

/

I

-z / d STEM

RPS & ESF Which ONE of the following describes the electrical board that failed?

A (1) vital board has failed.

Given ONLY the conditions listed above, (2) would be observed.

(1) (2)

A. 125VDC MSIV S CLOSED B. I25VDC MSIV S CLOSED C. I2OVAC MSIV S CLOSED D. I2OVAC MSIV S CLOSED

47.

Given the following timeline:

UU.ULJ UU Unit 1 is at 100% power.

uu.uu IJ I The lA-A SDBD experiences a BLACKOUT.

/-41 flflflfl.I A

uuuu. 5, which ONE of the following combinations of alarms will be seen in the MCR?

A.

DG DG DG DG RUNNING RUNNING RUNNING RUNNING DIESEL GEN lA-A DIESEL GEN 1 B-B DIESEL GEN 2A-A DIESEL GEN 28-B O-XA-55-26A O-XA-55-26B O-XA-55-26A O-XA-55-26A B.

DG DG DG DG RUNNING RUNNING RUNNING RUNNING DIESEL GEN IA-A DIESEL GEN 18-B DIESEL GEN 2A-A DIESEL GEN 2B-B O-XA-55-26A O-XA-55-26B O-XA-55-26A O-XA-55-26A C.

DG DG DG DG RUNNING RUNNING RUNNING RUNNING DIESEL GEN lA-A O-XA-55-26A DIESEL DEN 18-B I DIESEL GEN 2A-A DIESEL GEN 28-B O-XA-55-26B j O-XA-55-26A O-XA-55-26A D.

DG DG DG DG RUNNING RUNNING RUNNING RUNNING DIESEL GEN lA-A DIESEL GEN 1 B-B DIESEL GEN 2A-A DIESEL DEN 2B-B O-XA-55-26A O-XA-55-26B O-XA-55-26A O-XA-55-26A

48.

Given the following conditions:

- The operating crew is directed to place Vital Battery V in service to Vital Battery Board II.

Which ONE of the following describes the Battery V voltage and which charger is in service?

PRIOR to Vital Battery V being placed in service, Vital Battery V voltage will be (1) than that of Vital Battery II.

In accordance O-SOl-236.05, AFTER Vital Battery V is placed in service on Battery Bd II, 125V VITAL BATTERY CHARGER (2) will be in service to Vital Battery Board II.

NOTE: O-SOI-236.05, 125V DC Vital Battery Board V (1) (2)

A. higher than II B. higher than V C. the same as II D. the same as V

49.

Given the following conditions:

- Unit 1 is at 100%.

EMERGENCY START HANDSWITCH ON O-M-26 Depressing the switch pictured above will start (1) EDG(s).

ERCW (2)

A. (1) ALL (2) AUTOMATICALLY aligns to the EDGs starting B. (1) ALL (2) is NORMALLY flowing to the EDGs C. (1) ONLY ONE (2) AUTOMATICALLY aligns to the EDG starting D. (1) ONLY ONE (2) is NORMALLY flowing to the EDGs

50.

Given the following timeline:

L:Li Unit 1 is at 100% power.

I :LIIJ 0-SOl-82.01, Diesel Generator (DG) 1A-A,Section 8.3.1, Removing DG from Service-DG Tied on to SD Bd is in progress.

f5:UiJ Offsite power has been paralleled to the lA-A 6.9kV SDBD.

II1: Ifl:flfl lA-A DG Megawatts are reduced to near zero.

lA-A DG Megavars are reduced to near zero.

Which ONE of the following completes the statements below?

In accordance with 0-SOl-82.01, the crew will (1)

Once 1-HS-82-14 is placed in STOP, the lA-A DG Engine speed will (2)

(1) (2)

A. OPEN Generator ACB 1912. drop to 0 rpm then PLACE 1-HS-82-14, START-STOP control switch, in STOP.

B. OPEN Generator ACB 1912. drop to approximately 450 rpm and hold this value for 10 minutes then PLACE 1-HS-82-14, START-STOP control switch, in STOP.

C. PLACE 1-HS-82-14, START-STOP drop to 0 rpm control switch, in STOP.

then CHECK that Generator ACB 1912 AUTOMATICALLY OPENS D. PLACE 1-HS-82-14, START-STOP drop to approximately 450 rpm and hold control switch, in STOP. this value for 10 minutes then CHECK that Generator ACB 1912 AUTOMATICALLY OPENS

51.

Given the following conditions:

- 185-C, SERV BLDG VENT O-RM-132 INSTR MALF is LIT.

- O-RM-90-132B indicates as follows:

SERVICE SLOG VENT GAS I O-RM-90-132E 1 OOe+O1 pUSH TO RESET HIGH ALERT

OPERATE IFET HIGH VOLTAGE SLOPE

ADJ GROSS j 01FF *TP6 SlAG METER AOJ

AOJ J

1 HV* ADJ ALERTS SET 015CR I SET HIGH* SET 015CR

SET ALARM* REF TPES*

OPERATE TP4 ALARM CHECK SOLIRCE\ ADJ

- ARC performs step [2.1] of ARI-185-C: PLACE function switch to CHECK.

Which ONE of the following completes the statements below?

A loss of power to O-RE-90-132, SB VENTILATION RAD MON (1) cause the alarm listed above.

In accordance with ARI-185-C, the MINIMUM indication required to satisfactorily complete a source check is (2)

A. (1) WILL (2) a rise on the radiation monitors meter B. (1) WILL (2) a LIT high alarm button C. (1) WILL NOT (2) a rise on the radiation monitors meter D. (1) WILL NOT (2) a LIT high alarm button

52.

Given the following conditions:

- Unit I is at 100%.

- All systems are in their NORMAL alignments.

- The following indication is observed on 0-M-27B.

CCS HX C TEMP & PMP PRESS 0- PITR-70-162 ne.J

HXC Which ONE of the following describes the cause of the above indications?

A Loss of the ERCW header.

A. IA B. lB C. 2A D. 2B

53.

Given the following timeline:

WH111E1 Unit 2 is at 100% power.

ULJ The stations Non-essential control air is lost and Non-essential air header pressure is 0 psig.

Which ONE of the following describes the response of the Unit 2 MSIVs to this condition?

A4. flflfl fl I 4L- I I 4. Ii I

,-i UU.II I.U I LI ie uflhi vi vS WI A. have CLOSED B. remain OPEN as the MSIVs are provided with essential control air C. remain OPEN until the MSIVs air accumulators are depleted D. remain OPEN as a N 2 backup is provided to the MSIVs instrument air supply

54.

Given the following conditions:

- Unit 1 is at 100% power.

- A leak develops on the Control Air system.

- Control air pressure LOWERS to 75 psig.

Which ONE of the following identifies a system response that occurred to maintain Train A Essential Air Header pressure?

A. 1-FCV-32-80, AUX AIR TO RX BLDG TR A, SHUTS B. 1-FCV-32-1 10, NON-ESS AUX AIR TO RX BLDG, SHUTS C. 0-PC V-33-4, SERVICE AIR RECEIVER ISOLATION VALVE, OPENED D. 0-FCV-32-82, ESSENT CONTROL AIR TR A NORM FLOW ISOL SHUTS

55.

Given the following timeline:

rlnnn.nn I I 4 4 flhi IS Ifl E1HL SOURCE RANGE HI FLUX AT SHUTDOWN (81-B) alarms and is acknowledged.

UU:W1 RISING counts are observed on both 1-Nl-131 and 1-NI-i 32.

Which ONE of the following describes if a horn can be heard and the required actions in accordance with 1-ARI-81-87, NIS & Rod Controls?

The conditions listed at O: :üü, will (1) activate an alarm horn which will be heard in upper containment.

At EO: El :E

, the crew is required to GO TO 1 (2)

A. (1) AUTOMATICALLY (2) 1-AOl-29, Dropped or Damaged Fuel or Refueling Cavity Seal Failure B. (1) AUTOMATICALLY (2) 1-AOI-34, Immediate Boration C. (1) require that an operator MANUALLY (2) 1-AOl-29, Dropped or Damaged Fuel or Refueling Cavity Seal Failure D. (1) require that an operator MANUALLY (2) 1-AOl-34, Immediate Boration

56.

Given the following timeline:

nn.nn.nn UU.UU.LJU Unit 1 is at 100% power.

Normal letdown is out-of-service.

Excess letdown is in-service in accordance with 1-SOl-62.01, CVCS Charging and letdown.

1-PDI-30-42, CNTMT PRESS is 0 psig and STABLE.

¶i;fliTh 1-Pl-77-2, RCDT PRESSURE is RISING.

1-Ll-77-1, RCDT LEVEL is 18% and RISING.

¶1: fl:flE 1-LI-77-1 is 45% and STABLE.

0-PIS-77-88, WASTE GAS VENT HEADER PRESSURE is 2.0 psig and STABLE.

Which ONE of the following completes the statements below?

The observed trend from E:flE : I to nfl: Ifl:EIfl is consistent with 1 -HS-62-59A, CVCS EXCESS LETDOWN DIVERT FLOW CNTL being positioned to (1)

Given ONLY the events listed in the timeline, at O: IO:CIJ, 1-PI-77-2, RCDT PRESSURE will indicate (2) psig.

A. (1) NORM (2) 0 B. (1) NORM (2) 2.0 C. (1) DIV (2) 0 D. (1) DIV (2) 2.0

57.

Which ONE of the following describes the bus power supply to the lA-A Centrifugal Charging Pump?

A. IA-A 480V SDBD B. 1A48OVUNITBD C. IA-A 6.9kV SDBD D. 1A6.9kVUNITBD

58.

Given the following indications:

Regarding the pictures shown above, which ONE of the following completes the statements below?

The information on the CERPI screen (1) consistent with the position of 1-RBSS.

The DEMANDED rod speed value is produced by the passive summer of the (2)

A. (1) is (2) Distributed Control System (DCS)

B. (1) is (2) CERPI Central Processing Units (CPUs)

C. (1) isNOT (2) Distributed Control System (DCS)

D. (1) sNOT (2) CERPI Central Processing Units (CPUs)

59.

Which ONE of the following describes the In-core Monitoring System?

The TIC Map Display of 1-XI-68-100, RVLIS-ICCM PLASMA DISPLAY will show for a BAD thermocouple input?

A.

0000 B.

9999 C.

BBBB D.

xxxx B

60.

Given the following conditions:

- Unit I is at 100%.

- The B train CNTMT Purge is in service to Lower CNTMT.

Subsequently:

- The following indications are noted:

MASTER ISOL SIGNAL STATUS PNL MASTER ISOL SIGNAL STATUS PNL UAC TSL 1 XX55-6C I2OVAC IrAL iv 1 XX556D Which ONE of the following describes the status of the CNTMT Purge Fans and the Purge Damper position indications?

The running supply and exhaust CNTMT Purge Fans will (1)

Purge Damper position indication is available (2)

A. (1) STOP (2) ONLY on 1-M-9 B. (1) STOP (2) BOTH on 1-M-9 and 1-M-6 C. (1) continue running (2) ONLY on 1-M-9 D. (1) continue running (2) BOTH on 1-M-9 and 1-M-6

61.

Given the following conditions:

- Preparations are in progress for Unit 1 Reactor Cavity flood up.

- The Unit I Reactor Cavity is EMPTY.

- O-GATE-79-5, Spent Fuel Pit and Fuel Transfer Canal Gate is INSTALLED.

- The transfer canal level is 725.

- SFP level is 749 1 1/4 and has been LOWERING 1/4 per day.

- The flange on the Unit 1 Containment side of the fuel transfer tube is REMOVED.

- NO fuel movement system activities are in-progress on Unit 2. All Unit 2 components are positioned normally.

Which ONE of the following completes the statements below?

IF 1-ISV-78-600, Fuel Transfer Tube Isol is OPENED, SFP level will LOWER (1)

Spent Fuel Pool Cooling level (2) be monitored on a meter on 1-M-6.

(1) (2)

A. more quickly can B. more quickly can NOT C. at the same rate can D. at the same rate can NOT

62.

Given the following timeline:

nfl.nn-nn uu.uu.uu Unit 1 is at 100% power.

During spent fuel movement an assembly is slightly bent.

The FH AREA EXH FAN A is RUNNING.

nn.Jn.nn UU.LU.UU 0-RM-90-102 and 0-RM-90-103 indicate as follows:

SPENT FUEL PiT AREA 0-RM-90-1 02 OU:2 :UL The control room staff enters 1 -AOl-29, Dropped or Damaged Fuel or Refueling Cavity Seal Failure section 3.4, Dropped or Damaged Irradiated Fuel Assembly in Spent Fuel Pit Area.

Which ONE of the following describes the status of FH AREA EXH FAN A AND the FIRST action the crew will implement in accordance with 1-AOl-29?

Upon entry into 1-AOI-29 and BEFORE any operator action is taken, the FH AREA EXH FAN A is (1)

The FIRST action which will be taken is to (2)

A. (1) running (2) CHECK Auxiliary Building Isolation (ABI) actuated B. (1) secured (2) CHECK Auxiliary Building Isolation (ABI) actuated C. (1) running (2) EVACUATE the affected area D. (1) secured (2) EVACUATE the affected area

63.

Given the following conditions:

- Unit 1 SG #1 is RUPTURED.

- Unit 1 has AUTOMATICALLY tripped and Safety Injection has AUTOMATICALLY actuated.

- In accordance with 1-E-0, heat sink has JUST been verified.

- SG #1 level is 20% and RISING.

In accordance with 0-TI-i 2.04, which ONE of the following identifies the PRUDENT action which may CURRENTLY be taken?

NOTE: 1-E-O, Reactor Trip or Safety Injection O-Tl-12.04, Users Guide for Abnormal and Emergency Operating Instructions A. SHUT the #1 MSIV B. ISOLATE AFW to the #1 S!G C. ADJUST the #1 S/G PORV to 87%

D. REALIGN the TDAFWP steam supply

64.

Which ONE of the following completes the statements listed below?

In accordance with 1-SOl-2&3.01, Condensate and Feedwater System, adequate condenser vacuum for turbine startup (1) be established following a refueling outage if no condenser vacuum pumps are available.

If all condenser vacuum pumps are lost with Unit 1 at 100% power, the value shown for RE9O-119 (2) continue to ACCURATELY register the activity levels existing in the condensers gas space.

0.10 RE9O-255 MR/HR I .OOOE-k2 0.0 RE9O 256 - MR/HR CFM El 256 I 0OOE÷:

RE9O-119 CPM TURBINE BLDG COND (1) (2)

A. CAN will B. CAN will NOT C. CANNOT will D. CAN NOT will NOT

65.

Given the following conditions:

- Unit 1 is in MODE 3.

- Offsite power has been lost.

- The 6.9kV Shutdown Boards have been reenergized by their respective EDGs.

- Control Air header pressure is 70 psig and LOWERING.

- The Unit 2 Construction Air receiver is 97 psig and STABLE and is supplied by a Diesel driven air compressor.

Which ONE of the following describes the response of the AUO?

In accordance with 0-AOl-i 0, section 3.3, an AUO will be dispatched to (1) 0-PCV-33-4, Service Air Isol Valve (2) AUTOMATICALLY RE-OPEN.

NOTE: 0-A 01-10, Loss of Control Air Section 3.3, Loss of Control Air in Mode 1,2,3 or 4 A. (1) START a Station Air compressor (2) does B. (1) START a Station Air compressor (2) does NOT

c. (1) ALIGN Unit 2 Construction Air Compressor to Unit 1 Control Air header (2) does D. (1) ALIGN Unit 2 Construction Air Compressor to Unit I Control Air header (2) does NOT

66.

Given the following conditions:

- The A-A ABGTS is about to be started in support of 0-Sl-30-8-A, Auxiliary Building Gas Treatment System Train A 10-Hour Operation.

- The commencement of 0-Sl-30-8-A was previously recorded in the narrative log.

In accordance with OPDP-1, Conduct of Operations, which ONE of the following completes the statements listed below?

A plant announcement (1) be made prior to starting the A-A ABGTS.

The start of the A-A ABGTS (2) be recorded in the narrative log.

A. (1) must (2) must B. (1) must (2) need NOT

c. (1) need NOT (2) must D. (1) need NOT (2) need NOT

67.

Given the following conditions:

WiHfl Unit 1 is reducing load.

At the times specified, ALL Excore channels indicate the following:

Rated Thermal Power (%) AFD (%)

Iuu.up.uu I 85 (-) 15.5%

nn. I.flfl uu.C ILIU 80 (-) 20.0%

Which ONE of the following completes the statements below?

The FIRST time that T/S LCO 3.2.3, AFD will be NOT MET is At Rated Thermal Powers less than 50%, the negative and positive limits of the acceptable region for AFD are (2)

REFERENCE PROVIDED A I1\ nrl*nI*nn f.. Ij LIU.UI.UU (2) no longer applicable nnnnri B I, UU.U .UU (2) still applicable and become constant values no longer changing with the power level C I4\ nn., i.nn L. k ) UU.1 I.UU (2) no longer applicable I f1\ flfl Iflfl Li. l I) UU.Z I.UU (2) still applicable and become constant values no longer changing with the power level

REFERENCE FOR QUESTION 67 Page A-I of the Nuclear Operating Book (NOB)

[REDA C TED]

WBN1 NUCLEAR OPERAT ING NOB SHEET A-i BOOK Revision 161 (NOB) Pagelofi Target Band vs. Power Level WBN Unit 1 Cycle 13 120 110 100 90 80 dP / I a) 70 0

H c1 60 a) 50 a) 4.)

40 30 20 10 jill C

3C 20 10 10 20 30 Axial Flux Difference (%)

CURRENT AED AND TARGET BAND CONSTANTS K2024X = 28%, K2C25X 12%, K2026X +7%, K2C27X +21%,

K2028 = 1.0%, K2C29 = 3.0, K2030 = 3.0

68.

Which ONE of the following describes the MCR Log Taking in accordance with 1-SI-O-2B-01, 0700-0900, Shift and Daily Surveillance Log Mode One?

The Reactor Operator will obtain data available in the MCR from (1)

This data will be compared to criteria which are (2) that contained in the Unit 1 Technical Specifications.

A. (1) ONLY the MCR board indications (2) ALWAYS identical to B. (1) ONLY the MCR board indications (2) SOMETIMES different than C. (1) the MCR board indications and the 105 (2) ALWAYS identical to D. (1) the MCR board indications and the lOS (2) SOMETIMES different than

69.

Which ONE of the following describes the Modes of Operation in accordance with the Unit I Technical Specifications?

Unit 1 will enter MODE 5 from MODE 4 when (1) is (2)

(1) (2)

A. Tavg 200 °F B. Tavg <350°F C. Tcold 200 °F D. Tcold <350°F

70.

Given the following conditions:

- Unit 1 is at 7% power In accordance with Tl-12.07A, Containment Access Modes 1-4, which ONE of the following tasks does NOT pose a radiological hazard requiring authorization for Special Access into containment?

A. Physically checking a lower ice condenser door shut B. Locally inspecting the RCP #2 oil reservoir sight glasses C. Isolating a leak on the letdown line by closing 1-ISV-68-580 (1C1705 AZ 221)

D. Venting the RHR suction header using 1-TV-74-504 and 1-TV-74-543 (716-AZ 301 #4 Accum Rm)

71.

Given the following:

- Unit 1 is at 100% power.

- The lA-A CCP is running.

- The lA-A CCP room is posted as a Radiation Area.

- The operator had been directed to enter the lA-A CCP room.

Which ONE of the following completes the statements below as related to the picture below?

The Electronic Dosimeter (ED) can indicate (1)

The picture below (2) illustrate the correct dosimetry to be worn in the IA-A COP room in accordance with RCI-153, Radiation Work Permits (RWP5), and the appropriate RWP.

(1) (2)

A. ONLY dose does B. ONLY dose does NOT C. dose and dose rate does D. dose and dose rate does NOT

72.

Which ONE of the following completes the statement below?

In accordance with 10 CFR 20.1201, Occupational dose limits for adults, individual workers total effective dose equivalent (TEDE) shall be maintained less than REM per year.

A. 0.5 B. 1.0 C. 3.0 D. 5.0

73.

Which ONE of the following completes the statements listed below?

There are (1) procedures in the EOP network which may be DIRECTLY entered.

The Immediate Actions listed in certain EOPs require that the operator perform from memory (2)

A. (1) three (2) BOTH columns B. (1) three (2) ONLY the left hand column C. (1) two (2) BOTH columns D. (1) two (2) ONLY the left hand column

74.

Given the following conditions:

- Unit I is at 100% power.

- A contract worker uses a plant phone and the x391 I line to report that a temporary pump located outside of the Unit 2 TDAFWP room has caught fire.

- Heavy smoke is present at the scene of the fire.

Which ONE of the following describes the appropriate response in accordance with I-AOl-30.l, Plant Fires?

The control room staff will (1)

The RO will announce ALL CLEAR when (2)

NOTE: O-SOI-13.O1, Fire Detection System O-M-29, Fire Detection System Control Room Console (Blue Goose)

A. (1) initiateanABi (2) the alarms on 0-M-29 clear B. (1) initiateanABl (2) directed by the Incident Commander C. (I) secure ventilation in accordance with 0-SOl-I3.0l (2) the alarms on 0-M-29 clear D. (1) secure ventilation in accordance with 0-SOI-13.01 (2) directed by the Incident Commander

75.

Given the following conditions:

- Unit I is at 100% power.

- Supplemental Condenser Circulating Water System (SCCW) has been placed in service in accordance with SOl-27.03, section 5.2.

Subsequently:

- COOLING TOWER BASIN LEVEL HI (164-D) is LIT.

Which ONE of the following describes the appropriate alarm response?

The control room staff (1) use ICS to validate this alarm.

In accordance with ARI-159-165, Sumps & CCW, the operator responding to this annunciator will ADJUST 0-FCV-27-1 12, SUPPLEMENTAL CCW SYSTEM SUPPLY FLOW CONTROL by (2)

NOTE: SOI-27.03, Supplemental Condenser Circulating Water System; Section 5.2, Placing SCCW In Service A. (1) can (2) operating the valve from 1-M-15 B. (1) can (2) dispatching an AUO to operate the valve from a local control C. (1) can NOT (2) operating the valve from 1-M-15 D. (1) can NOT (2) dispatching an AUO to operate the valve from a local control

76.

Given the following conditions:

- Unit 1 is at 28% power.

- RCP SEAL LEAK OFF FLOW HI (100-D) is LIT.

- 1-FR-62-24, SEAL LEAKOFF HI RANGE GPM reads 5.2 gpm.

Subsequently:

- 1-Tl-62-3, RCP I LWR BRG TEMP is 235°F and rising.

In accordance with BOTH 1-AOI-24 and O-Tl-12.04, which ONE of the following completes the statement below?

The Unit Supervisor will direct (1)

NOTE: 1-A 01-24, RCP Malfunctions During Pump Operation O-Tl-12.04, Users Guide for Abnormal and Emergency Operating Instructions ES-U. 1, Reactor Trip Response A. a Unit I shutdown in accordance with 1-GO-5, Unit Shutdown From 30% Reactor Power to Hot Standby B. a Unit I shutdown in accordance with 1-AOl-39, Rapid Load Reduction C. the OAC to trip the Unit 1 reactor and the CR0 to perform the remaining actions of 1-AOl-24 after the crew transitions to ES-0.1 D. the crew to maintain Unit 1 at power as a Unit Shutdown is NOT yet required and an operator to REFER TO 1-AOI-24, Attachment 2, Immediate Shutdown Criteria

77.

Given the following conditions:

- 1-FR-SI, Nuclear Power Generation/ATWS was entered.

- The Unit Supervisor has reached step 12, MONITOR reactor subcriticality:

In accordance with 1-FR-SI, which ONE of the following combinations of Power Range readings and Intermediate range SUR would allow emergency boration to be terminated?

Power Range Channels Intermediate Range SUR (dpm)

(%)

A. 6.0 -0.5 B. 5.1 -0.3 C. 4.0 0.0 D. 3.9 -0.3

78.

Given the following conditions:

- The Unit 1 #1 SG is ruptured.

- The RCPs are SECURED.

- In accordance with step 18 of 1-E-3, the crew has INITIATED RCS cooldown to the target incore temperature.

- An ORANGE path exists for 1-FR-P.1 based SOLELY upon the Tcold in Loop #1.

Which ONE of the following describes the procedure transition requirements in accordance with 1-E-3?

The Unit Supervisor WILL NOTE: 1-E-3, Steam Generator Tube Rupture 1-FR-P. 1, Pressurized Thermal Shock A. IMMEDIATELY transition to 1-FR-P.1 B. NOT transition to 1-FR-P.1 UNTIL 1-E-3 is completed C. transition to 1-FR-P.1 IF the ORANGE path still exists ONCE the cooldown to target incore temperature is completed D. transition to 1-FR-P.1 IF the ORANGE path still exists ONCE SI is terminated in accordance with 1-E-3

79.

Given the following conditions:

nn.nfl-fln UU.UU.UU Unit 1 is in MODE 3.

125V DC Vital Battery Bd II is lost.

AOl-21.02, Loss of 125V DC Vital Battery Bd II is entered.

fln.-Ifl-fln UUjZ U.UU In accordance with step 12 of AOl-21 .02, Work Order (WO) 113653359 has been placed in WORKING status.

fln*IJn*flr1 UU.U.UU In accorc following -- been placed:

e 9

-J 0

H

,J) 1) fl -

Ct I:,

z t) .: ..

0 r.

IC u:

C., _J

EU AUOs place 125V Vital Battery V on 125V Vital Battery Bd II.

Vital Battery Bd II voltage is 136 V.

L:UU AUOs place 125V DC Vital Battery Charger 8-S on 125V Vital Battery Bd II.

Vital Battery Bd II voltage is 138 V.

Which ONE of the following completes the statements listed below?

The condition observed at O:-J:LU indicate that T/S LCO 3.6.3, Containment Isolation Valves is (1)

T/S LCO 3.8.4 DC Sources Operating may FIRST be exited at (2)

(1) (2)

A. NOT met n I fl*flfl U .juuu B. NOT met fl.flfl.flfl UL.UUUU C. met fl *zIrI*flfl D. met n*nn*nn UL .UU.UU

80.

Given the following conditions:

- A perturbation on the 161 kV transmission grid caused the supply breaker for the CSST C Y-winding load tap changer to TRIP OPEN.

- The following indications are observed on 0-ECB-3:

I; Y-WINDING VOLTS CSST C LTC-Y REMQTE OPERATION 0

CSSTC LTC-X REMOTE OPERATION Which ONE of the following describes the operability of the offsite power supply AND how the CSST C Y winding voltage will be maintained?

In accordance with TIS [CO 3.8.1, AC Sources Operating, the offsite power supply described above (1) CURRENTLY operable.

In accordance with 1-PI-OPS-1-500KV, Main Control Room Voltage Monitoring, the associated SDBD will be maintained above the MINIMUM voltage requirement by (2)

A. (1) IS (2) placing the DG on the SDBD and then divorcing the SDBD from offsite B. (1) IS (2) notifying the Northeast Area Dispatcher (NEAD) to ensure that the 161 kV transmission alignments are adequate C. (1) IS NOT (2) placing the DG on the SDBD and then divorcing the SDBD from offsite D. (1) IS NOT (2) notifying the Northeast Area Dispatcher (NEAD) to ensure that the 161kV transmission alignments are adequate

81.

Given the following conditions:

UU:Eifl:Ei Unit 1 experienced a Large Break LOCA.

RCS pressure is 15 psig.

EEiD 1-ES-i .3, Transfer to Containment Sump is entered.

Step 1, 1. ENSURE both RHR pumps RUNNING. is being performed.

The crew notes the following STABLE indications:

HR PMP A RHR PMP A RHR PMP B RHR PMP B AMPS DISCH PRESS AMPS DISCH PRESS

-EI-74-5A 1-I-74-13 1-EI-74-17A 1-PI-74-2 rinjrnn uu.L_ I.uiJ Step 5, CHECK cntmt sump level is completed and ADEQUATE sump level exists.

flfl.D.flfl ULJ.LU.ULJ Step 6, ENSURE automatic switchover complete is COMPLETED.

The followinn

Which ONE of the following completes the statements below?

The conditions observed at flEi:2S:DD, show that the IA-A RHR pump (1)

In accordance with Emergency Procedures, the crew will (2)

NOTE: 1-ECA-1. 1, Loss of RHR Sump Recirculation (1) (2)

A. is cavitating continue in 1-ES-i .3 B. is cavitating transition to i-ECA-1.1 C. has sheared its shaft continue in 1-ES-i .3 D. has sheared its shaft transition to 1-ECA-1.1

82.

Given the following conditions:

- Unit I TRIPPED from 100% power.

- ES-0.1, Reactor Trip Response is entered.

- Four control rods REMAIN withdrawn.

- The Unit Supervisor is at the RNO for step 6:

IF two or more rods are NOT fully inserted, THEN INITIATE boration Which ONE of the following describes the appropriate response?

In accordance with step 6 of ES-0.1, an RCS boration will be initiated and will continue until is injected.

In accordance with 0-Tl-12.04, the US may assign the initiation of THIS BORATION to (2)

NOTE: O-Tl-12.04, Users Guide for Abnormal and Emergency Operating Instructions 1-SI-O-1O, Shutdown Margin A. (I) the value required by 1-Sl-0-10 (2) ONLYtheBOP B. (1) a fixed value DIRECTLY determined by ES-0.1 (2) ONLY the BOP C. (1) the value required by 1-Sl-0-10 (2) EITHER the BOP OR the OAC D. (1) a fixed value DIRECTLY determined by ES-0.1 (2) EITHER the BOP OR the OAC

83.

Given the following conditions:

- 1-AOl-34, Section 3.2, is in progress.

- I-HS-62-140A, VCT MAKEUP CONTROL has JUST been taken to START and released.

Subsequently:

- l-TANK-62-239, Boric Acid Tank A outlet piping RUPTURES.

- 1-Fl-62-139, BA TO BLENDER FLOW is 0 gpm.

- I-Ll-62-238, BAT A LEVEL is RAPIDLY LOWERING.

Which ONE of the following completes the statement below?

In order to borate the RCS, the US must NOTE: 1-AOI-34, Immediate Boration, Section 3.2, Boration of RCS with CVCS in Service 1-SOI-62.O1, CVCS-Charging and Letdown O-S0I-62.05, Boric Acid Batching, Transfer, And Storage 1-LCV-62-135 and 1-LCV-62-136, RWST TO CHARGING PMPS SUCTION A. place the C BAT in service to the UI CVCS blender in accordance with 0-SOI-62.05 B. continue in section 3.2 of l-AOI-34 and align the RWST to the charging pump suction C. alternate the charging pump suction to and from the RWST using 1-LCV-62-135 and 136 in accordance with 1-SOI-62.01 D. continue in section 3.2 of 1-AOl-34 and place the C BAT in service to the UI CVCS blender

84.

Given the following timeline:

nn*nrl-rln LI ni+ is in I I The shutdown rods are FULLY WITHDRAWN.

Eifl:U I :LILI Source Range Nuclear Instrument N-31 fails LOW.

The crew implements 1-AOI-4, Nuclear Instrumentation Malfunctions.

OJ: L:LU Source Range Nuclear Instrument N-32 fails LOW.

The OAC takes 1-RT-1, REACTOR TRIP to TRIP.

The US enters T/S LCD 3.3.1 condition L:

[I Required Source Range L.1 Suspend operations involving Immediately Neutron Flux channel positive reactivity additions.

inoperable.

AND L.2 Close unborated water source 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months isolation valves.

AND L.3 Perform SR 3.1.1.1. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafte DI:W: SR 3.1.1.1 is completed and reviewed SATISFACTORILY.

Which ONE of the following completes the statements below?

In accordance with O-Tl-12.04, 1-E-O (1) be entered to confirm the reactor trip.

In accordance with the Unit I T/S, the NEXT REQUIRED performance of SR 3.1.1.1 MUST be completed by (2)

NOTE: 1-E-O, Reactor Trip or Safety Injection T/S LCD, 3.3.1 Reactor Trip System (RTS) Instrumentation O-Tl-12.04, Users Guide for Abnormal and Emergency Operating Instructions A. (1) MUST f9\ [. fl.flfl lJ. I Li.UU B. (1) MUST iL) I. I U.LILJ C. (1) NEED NOT I . I flflfl IL) I .1. I U.UU D. (1) NEED NOT I I flflfl i,) I 0. u.uu

85.

Given the following conditions:

- The MAXIMUM observed Containment pressure was 0.1 psig.

- An overpressure condition exists on the #1 SG.

- The operating crew has completed steps 1 and 2 of FR-H.2.

- The crew CHECKS affected SG NR level and notes the following:

1 J 4.oo I

SG1 SG1 SG1 LEVEL LEVEL LEVEL

-LI-3-42 1-U-3-39 1-LI-3-3B 1-M-4 Indications In accordance with FR-H.2 and the associated basis document, which ONE of the following identifies the crew response?

The crew will identify that NOTE: FR-H. 2, Steam Generator Overpressure FR-H.3, Steam Generator High Level A. neither level shown above indicates that the SG is potentially filled solid with water and as such, the crew will REMAIN in FR-H.2 B. ONLY the level shown on ICS indicates that the SG is potentially filled solid with water but because ONLY the 1-M-4 indications may used for a decision point, the crew will REMAIN in FR-H.2 C. BOTH the levels shown on ICS and 1-M-4 indicate that the SG is potentially filled solid with water; the crew will TRANSITION to FR-H.3 D. ONLY the level shown on ICS indicates that the SG is potentially filled solid with water and because the ICS data may be used for a decision point, the crew will TRANSITION to FR-H.3

86.

Given the following conditions:

- Unit 1 is at 100% power.

- 1-Sl-99-10-A was completed.

- The following page requires SRO review.

- ALL OTHER PAGES of 1-Sl-99-10-A were reviewed with SATISFACTORY results.

WBN 62 DAY FUNCTIONAL TEST OF 1-SI-99-10-A Unit I SSPS TRAIN A AND Rev. 0059 REACTOR TRIP BREAKER A Page 94 of 122 Date -z/zgas 7.0 POST PERFORMANCE ACTIVITIES (continued)

ØE Power supply ripple values are taken for trending purposes and are NOT acceptance criteria. Notify the SIMF and responsible engineer if ripple values are exceeded.

rØi SET DMM to measure 2.0 Vac. Z

[] CONNECT 0MM temporarily to the following test jacks (i-) and POWER SUPPLIES GND (-) on LOGIC TEST PANEL [1-R-47], and RECORD As-Found mVac ripple voltages: /0 POWER SUPPLY DESIRED AS-FOUND AS-LEFT TEST JACK (mVac RMS) (mVac RMS) (mVac RMS)

+48Vdc#1 <353.5 375.0 3q0.o

+48Vdc#2 <353.5 3(,3.O 3541.0

+l5Vdc#1 <106.0 goq.o

+l5Vdc#2 <106.0 o,.o M&TE No.: j39 S Cal Due Date: 9/,/IS IF power supply As-Found voltages in Steps 7.0[53.2J and 0

7.O[53.4] are within tolerance, THEN

[50 RECORD the statement Left-As-Found in As-Left columns.

[50] GO TO Step 7.O[56].

Which ONE of the following completes the statement below?

Following the SRO review of the surveillance depicted above, in accordance with TIS LCO 3.3.1, RTS Instrumentation, REFERENCE PROVIDED A. NO impact to the OPERABILITY of A train SSPS exists B. ONLY TIS LCO 3.3.1 function 18 is rendered inoperable for the A train SSPS C. BOTH TIS LCO 3.3.1 functions 18 and 19 are rendered inoperable for the A train ssPs D. ONLY TIS LCO 3.3.1 function 19 is rendered inoperable for the A train SSPS

REFERENCE FOR QUESTION 86 Page 3.3-20 of the Unit I T/S (page 6 of 9 of Table 3.3.1-1 Reactor Trip System Instrumentation)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 9)

Reactor Trip System Instrumentation APPLICABLE MODES NOMINAL OR OTHER REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION SPECIFIED CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT CONDITIONS

17. ReactorTrip 1,2 2trains Q SR3.3.1.4 NA NA Breakers U) 3)a) 4)a) 5 2 trains C SR 3.3.1.4 NA NA

18. Reactor Trip 1,2 1 each T SR 3.3.1.4 NA NA Breaker per RTB Undervoltage and Shunt Trip 3, 4, 5 1 each C SR 3.3.1.4 NA NA Mechanisms per RTB

19. AutomaticTrip 1,2 2trains P SR3.3.1.5 NA NA Logic 3)a)4)a)5)a) 2trains C SR3.3.1.5 NA NA (a) With RTBs closed and Rod Control System capable of rod withdrawal.

(j) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.

Watts Bar-Unit 1 3.3-20

87.

Given the following conditions:

- Unit 1 was in MODE 3 when a Loss of 120v AC Vital Instrument Power Board 1-Ill occurs.

- 1-AOl-25.03, Loss of 120V AC Vital Instrument Power Boards 1-Ill or 2-Ill, directs use of 1-SOl-235.03, 120V AC Vital Power System 1-Ill, to restore the board Which ONE of the following describes the status of the system AND which procedure will allow exiting the T/S LCO?

During the loss of the vital board, (1) Unit I SSPS Train A ESF relays COULD be energized.

Implementing section (2) of 1-SOl-235.03 would re-energize the board and allows BOTH T/S LCOs 3.8.7, Inverters and 3.8.9, Distribution Systems Operating to be exited.

A. (1) ONLY the master (2) 8.1, Transferring 480V AC Vital Transfer Switch Ill to Alternate 480V Power Supply B. (1) BOTH the master and the slave (2) 8.1, Transferring 480V AC Vital Transfer Switch Ill to Alternate 480V Power Supply C. (1) ONLYthemaster (2) 8.3, Transfer 120V AC Vital Instrument Power Board 1-Ill to Spare 120V AC Vital Inverter 0-Ill D. (1) BOTH the master and the slave (2) 8.3, Transfer 120V AC Vital Instrument Power Board 1-Ill to Spare 120V AC Vital Inverter 0-Ill

88.

Given the following conditions:

- Unit 1 is at 100% power.

- Consider the following equipment items:

1. The TDAFWP rooms DC emergency exhaust fan.

2. The TDAFWP rooms AC emergency exhaust fan.

3. 1-LCV-3-164, MDAFWP SG I SUPPLY.

Of the THREE equipment items listed above, which ONE of the following lists the items that are required to be OPERABLE in accordance with T!S LCD 3.7.5, AFW System?

A. ONLY 3 B. ONLY2and3 C. ONLY 1 and 2 D. ONLY I and 3

89.

Given the following conditions:

- Unit 1 is at 100% power.

- A buzzer is heard from behind the Shift Managers desk.

- The following is observed:

SUP HOP

... 2ASUP j

os EPPA.

200 STOP 100 150 1D 1500 100, 0 0 so 50 511 ERcw P115 a-pa-a 0 PAPAS Sh 0<567255 EEi

.... fljp5 5-A

... Pc A..

TSP 000

/5 LEJ

00-01

- The crew enters 0-AOl-i 3, Loss of Essential Raw Cooling Water, Section 3.2, Loss of ERCW Pump.

Which ONE of the following describes T/S LCO 3.7.8, ERCW?

In accordance with T/S LCO 3.7.8, NOTE: OPDP-8, Operability Determination Process and Limiting Conditions for Operation Tracking A. a train of ERCW is INOPERABLE and will ONLY be restored OPERABLE when the failed pump is repaired and retested.

B. the failure does NOT impact the operability of the ERCW system and in accordance with OPDP-8, the crew will enter a TRACKING ONLY LCO for the ERCW system.

C. a train of ERCW is INOPERABLE and will be restored OPERABLE IMMEDIATELY after the crew performs step I of 0-AOI-13, START redundant trained ERCW Pump.

D. a train of ERCW is INOPERABLE and will be restored OPERABLE IMMEDIATELY after the crew performs step 4 of 0-AOl-I 3, ENSURE applicable emergency power selector switch selected away from failed pump.

90.

Given the following conditions:

- Unit 1 is at 100% power.

- Containment Pressure Transmitter 1-PDT-30-43 (Channel Ill) FAILED and is out of service with the channel bistables positioned as required by Tech Specs.

- The Surveillance Instruction for 1-PDT-30-44 (Channel II) is NOW due.

Which ONE of the following describes the required action for performing the Surveillance Instruction on 1-PDT-30-44 and the impact on Containment Spray actuation?

1-PDT-30-43 is required to be placed in the (1) position AND subsequent testing of 1-PDT-30-44 will (2) a valid AUTOMATIC Containment Spray actuation.

A. (1) BYPASS (2) ALLOW B. (1) BYPASS (2) PREVENT C. (1) TRIPPED (2) ALLOW D. (1) TRIPPED (2) PREVENT

91.

Given the following conditions:

- 1-ECA-O.O, Loss of Shutdown Power is in progress.

- The crew is performing step 26, CHECK maximum lncore T/Cs less than...

Which ONE of the following completes the statements below?

In accordance with 1-ECA-0.O, a maximum incore temperature of (1) °F and RISING will FIRST indicate that core damage cannot be prevented and will REQUIRE that the crew (2)

A. (1) 1200 (2) transition to SACRG-1, Severe Accident Control Room Guideline Initial Response B. (1) 1200 (2) continue in 1-ECA-0.0 and inject to the RCS using the FLEX equipment C. (1) 2200 (2) transition to SACRG-1, Severe Accident Control Room Guideline Initial Response D. (1) 2200 (2) continue in 1-ECA-0.0 and inject to the RCS using the FLEX equipment

92.

Given the following conditions:

- Unit 1 is at 100% power.

- The following page of 1-SI-30-701 requires SRO review.

- ALL OTHER pages of 1-SI-30-701, INCLUDING the Local Leak Rate test of Penetration X-6, UPPER COMPARTMENT PURGE AIR EXHAUST have been reviewed with SATISFACTORY results.

WBN Containment Isolation Valve 1-Sl-30-701 Unit 1 Local Leak Rate Test Rev. 0010 Purge Air Page 16 of 70 Table I (Page 1 of 1)

Test Connection Configuration Log Data Package: Page _j... of Date 7/2C15 TEST CONNECTION CONFIGURATION LOG AS FOUND TEST AS LEFT PENETRATION VALVE ID POSITION Initials POSITION Initials POSITION 1st CV UNLOCKED CLOSED X-4 1-TV-30-555 AJQ (.O<.O ,Q AND OPEN .0 AND LOCKED .Q ..-

LOO UNLOCKED CLOSED X-5 1-TV-30-554

..Q ANDOPEN ..7 ANDLOCKED zQ ,

c,E° UNLOCKED CLOSED X-6 1-TV-30-558 A&)O Lco f2 ANDOPEN ANDLOCKED

(.LDSEO UNLOCKED CLOSED X-7 1-TV-30-557 2 ANDOPEN ANDLOCKED V JJ J cKE 0

c.eoEL) UNLOCKED CLOSED X-9A 1-TV-30-563 0 L) co O ANDOPEN .Q ANDLOCKED UNLOCKED CLOSED X-9B 1-TV-30-562

,JO LO -0 ANDOPEN cZ ANDLOCKED W cL) UNLOCKED CLOSED X-1OA 1-TV-30-561 -0 ANDOPEN .O ANDLOCKED ,

.L) ct..cS UNLOCKED CLOSED X-1OB 1-TV-30-560

,JC) LOcKEO ANDOPEN ANDLOCKED -0 -

UNLOCKED CLOSED X-1 1 1 -TV-30-559 -° AND LOCKED AND OPEN -

IF any test connection valve in this list is found OPENED and/or UNLOCKED, THEN NOTIFY Test Director, and SM/US.

OPS O 1TV - 3c -55$

csivc rb LW JOT BEL(Eu& TH1 vcUE l C.OO 8EC/ué T/.E cjtv, CJJCr J o(

°- C/, io42s3I /Ajj7,rEO. i-7 7/7c4

In accordance with TIS LCO 3.6.3, Containment Penetrations, which ONE of the following identifies BOTH the status of penetration X-6 and the actions required to be taken within one week (if any)?

REFERENCE PROVIDED A. Penetration X-6 is OPERABLE. ONLY 1-FCV-30-50 and 1-FCV-30-51 are containment isolation valves; therefore, no further actions are required.

B. Penetration X-6 is INOPERABLE. 1-FCV-30-50 must be tagged shut within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

C. Penetration X-6 is INOPERABLE. BOTH 1-FCV-30-50 and 1-FCV-30-51 must be tagged shut within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

D. Penetration X-6 is INOPERABLE. 1-FCV-30-50 must be tagged shut within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

REFERENCES FOR QUESTION 92 Sheet 3 of 69 of Table 6.2.4-1 of the WBN UFSAR

[CROPPED]

T/S LCO 3.6.3, Containment Isolation Valves

[REDA C TED]

WATTS BAR NUCLEAR LANT CON TA I NMENT PENETRAT I ONS AND BARRIERS-TABLE 6.2 VALVE DETA I L UPPER 4786-1 COMPARTMENT PURGE AIR EXHAUST (30>

EL 7493 AZ 293

Containment Isolation Valves 3.6.3 3.6 CONTAINMENT SYSTEMS 3.6.3 Containment Isolation Valves CONDITION REQUIRED ACTION COMPLETION TIME A. NOTE A.1 Isolate the affected penetration 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Only applicable to flow path by use of at least one penetration flow paths with closed and de-activated two containment isolation automatic valve, closed manual valves. valve, blind flange, or check valve with flow through the valve secured.

One or more penetration flow paths with one AND containment isolation valve inoperable except for purge valve or shield building bypass leakage not within limit.

(continued)

Watts Bar-Unit I 3.6-8

Containment Isolation Valves 3.6.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 NOTES

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected penetration Once per 31 days for flow path is isolated. isolation devices outside containment AND Prior to entering MODE4from MODE 5 if not performed within the previous 92 days for isolation devices inside containment B. NOTE B.1 Isolate the affected penetration 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to flow path by use of at least one penetration flow paths with closed and de-activated two containment isolation automatic valve, closed manual valves, valve, or blind flange.

One or more penetration flow paths with two containment isolation valves inoperable except for purge valve or shield building bypass leakage not within limit.

(continued)

Watts Bar-Unit 1 3.6-9 Amendment 79

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. NOTE C.1 Isolate the affected penetration 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Only applicable to flow path by use of at least one penetration flow paths with closed and de-activated only one containment automatic valve, closed manual isolation valve and a closed valve, or blind flange.

system.

One or more penetration C.2 NOTES flow paths with one 1. Isolation devices in high containment isolation valve radiation areas may be inoperable, verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected penetration Once per 31 days flow path is isolated.

D. Shield building bypass not D.1 Restore leakage within limit. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months within limit.

E. One or more penetration E.1 Isolate the affected penetration 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months flow paths with one or more flow path by use of at least one containment purge valves closed and de-activated not within purge valve automatic valve, closed manual leakage limits, valve, or blind flange.

AND (continued) 3.6-10 Amendment 79 Watts Bar-Unit 1

Containment Isolation Valves 3.6.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. (continued) E.2 NOTES

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected penetration Once per flow path is isolated. 31 days for isolation devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment Once per 92 days AND E.3 Perform SR 3.6.3.5 for the Once per resilient seal purge valves 92 days closed to comply with Required Action E.1.

F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND F.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Watts Bar-Unit 1 3.6-11 Amendment 79

93.

Given the following timeline of events:

flU:OU - Unit us at 100% power.

- Unit 2 requests that SCOW be taken out of service to permit maintenance on the Unit 2 cooling tower (CT) basin.

U :UU:UU - The crew performs the following step of Section 7.1, Shutdown, of SOl-27.03:

CAUTION Watts Bar Hydro must be in service to provide 3500 cfs river flow for thermal mixing during alignment changes.

[1] COORDINATE with Watts Bar Hydro Operator to ensure at least one unit will be in service to maintain river flow requirement during shutdown.

U9UUUU - Section 7.1 of S0I-27.03 is complete.

I UiEUU - The Unit 2 CT basin is isolated and drained.

- Due to evaporative losses, the Unit 1 CT basin REQUIRES makeup.

the Which ONE of the following describes the document for which the MINIMUM Flow is a basis AND method for providing makeup to the Unit 1 CT?

The source of the MINIMUM flow requirement described in step [11 shown above is (1)

At :ULI:UI, the crew can provide makeup to the Unit I CT using (2)

NOTE: SOl-2 7.03, Supplemental Condenser Circulating Water System 0-SOl-24.01, Raw Cooling Water System SOl-2 7.03, Section 8.7, Cooling Tower Basin Makeup with SCCW Shutdown O-SOl-24.01 section 8.3.1, Unit I Bypass Strainer Operation-RCW Adjustment TIS LCO 3.7.9, Ultimate Heat Sink A. (1) the bases for T/S LCO 3.7.9 (2) ONLY the ROW system using section 8.3.1 of 0-SOI-24.01 B. (1) the NPDES permit for WBNP (2) ONLY the ROW system using section 8.3.1 of 0-SOl-24.01 C. (1) the bases for T/S LCO 3.7.9 (2) EITHER the SCCW supply using section 8.7 of SOl-27.03 OR the ROW system using section 8.3.1 of 0-S0I-24.01 D. (1) the NPDES permit for WBNP (2) EITHER the SCOW supply using section 8.7 of SOI-27.03 OR the ROW system using section 8.3.1 of 0-SOl-24.01

94.

Given the following timeline of events:

EiU:DU:Lif - In accordance with 1-GO-2, a reactor startup is in-progress.

- Chemistry is analyzing a RCS sample for DOSE EQUIVALENT 1-131 (DEl).

LInk i is in I-I flflflfl I I *4 *1

- Chemistry reports that DEl is 0.5 pCi/gm.

- Unit I enters AOI-28.

UB;UU;UU - Chemistry reports that DEl is 15 pCi/gm.

C:UD - Chemistry reports that DEl is 22 pCi/gm.

etes the In accordance with T/S LCO 3.4.16 and AOl-28, which ONE of the following compl statements below?

In accordance with the T/S at L :Lfl:L , Unit 1 (1) PROHIBITED from entering MODE 1.

The RCS Tavg must be less than 500°F NO LATER THAN (2)

NOTE: 1-GO-2, Reactor Startup A 01-28, High Activity In Reactor Coolant T/S LCO 3.4.16, RCS Specific Activity REFERENCE PROVIDED (1) (2)

IU11flflfl A I i.uu.uu 1\. iS ILJflflflfl B is I

Ifl.nfl.nfl

-,. is I I.UL.J.UU n*nnrin r

LI. i5 hi i I I.UU.LJU

REFERENCE FOR QUESTION 94 T/S LCO 3.4.16 RCS Specific Activity [REDACTED]

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT 1-131 NOTE iCi/gm.

> 0.265 1 LCO 3.0.4.c is applicable.

A.1 Verify DOSE EQUIVALENT 1-131 Once per4 hours pCi/gm AND A.2 Restore DOSE EQUIVALENT 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 1-131 to within limit.

B.1 Perform SR 3.4.16.2. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. Gross specific activity of the reactor coolant not within limit.

AND B.2 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Tavg < 500°F.

(continued) 3.4-39 Amendment 41,55,91 Watts Bar-Unit 1

RCS Specific Activity 3.4.16 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME Required Action and C.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months C.

associated Completion Time Tavg < 500°F.

of Condition A not met.

OR DOSE EQUIVALENT 1-131 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify reactor coolant gross specific 7 days SR 3.4.16.1 iCi!gm.

activity < 100! L 1 SR3.4.16.2 NOTE Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 1-131 specific 14 days activity 0.265 jiCi/gm.

AND Between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a THERMAL POWER change of 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period (continued) 3.4-40 Amendment 41, 91 Watts Bar-Unit 1

95.

d to service In accordance with Tech Spec LCO 3.0.5, INOPERABLE equipment may be returne under administrative control for the following reasons:

1. Demonstrate OPERABILITY of the equipment.

2. Demonstrate OPERABILITY of other Tech Spec required equipment.

3. Troubleshoot equipment to facilitate repair.

A. 1 ONLY B. 1 and 2 ONLY C. 1 and 3 ONLY D. 1,2and3

96.

In accordance with NPG-SPP-O1 .2.1, Interim Administration of Site Technical Procedures for Watts Bar 1 and 2, a MINORIEDITORIAL procedure change includes:

1. inserting a sign-off line to the right of a step

2. changing:

RECORD RCS temperature, psig to RECORD RCS temperature,

3. inserting Start of Critical Step(s) before and End of Critical Step(s) after a step which DID NOT change A. 2 ONLY B. 2 and 3 ONLY C. 1 and 2 ONLY D. 1,2and3

97.

In accordance with Tl-12.07A, Containment Access Modes 1 4, general access into either the containment or the annulus may be authorized provided that the incore flux detectors are in their normal storage location inside the crane wall (1) AND tagged with a (2)

A. (1) ONLY (2) Hold Order B. (1) ONLY (2) Caution Order C. (1) OR approximately ten feet below the bottom of the core limit in any core thimble (2) Hold Order D. (1) OR approximately ten feet below the bottom of the core limit in any core thimble (2) Caution Order

98.

Given the following timeline of events:

nn*nn*nn -

i nii i is in

- An AUO must be sent into the containment and inside of the polar crane wall.

- In accordance with TI-12.07A, Containment Access Modes 1-4, authorization for SPECIAL access to containment is granted.

fl EflU - In accordance with TI-i 2.07A, the AUO about to enter containment receives the following brief from RP:

You are to evacuate upon notification or occurrence of high rad dose or dose rate alarm, evacuation alarm, public address, or as directed by RP or Operations; your alternate evacuation route through the Personnel Hatch #2 (Subhatch, 757) in the event normal access/egress is unavailable.

Which ONE of the following completes the statements below?

The (1) authorized the entry listed at fl:DE:CL by signing the Appendix A, Containment/Annulus Entry Authorization.

Use of the alternate evacuation route described by the RP brief (2) impact the OPERABILITY of T!S LCO 3.6.13, Divider Barrier Integrity.

A. (1) SM (2) does B. (1) SM (2) does NOT C. (1) Operations Manager (2) does D. (1) Operations Manager (2) does NOT

99.

Given the following timeline:

flU:Ufl:flL Unit I is at 100% power.

The lA-A RHR pump is TAGGED OUT for a component outage.

flOli IIJLJ Unit 1 experienced a reactor trip.

NO Safety Injection occurred.

A FIRE occurs in the B train SDBD rooms.

mIus:flu The crew is responding in accordance with ES-0.1, Reactor Trip Response and 1 -AOI-30. 1.

RHR Pump lB-B is SPURIOUSLY starting and stopping.

NOTE: 1-A 01-30.1, Plant Fires 1-A 01-30.2, Fire Safe Shutdown Which ONE of the following describes the proper implementation of the AOIs and EOPs?

A. At flflfl :flfl, 1-AOI-30.2 would be entered and would take precedence over the EOP set, SOLELY because the fire occurred in the SDBD rooms.

B. :Lfl, 1-AOl-30.1 would continue to be in effect, because ONLY ONE train of safety At flU:flE 1

related equipment is at risk.

C. At Dfl:US:flfl, 1-AOI-30.2 would be entered and would NOT take precedence over the EOP set, because the Appendix R fire does not analyze for subsequent casualties.

D. At flfl:flS:flfl, 1-AOl-30.2 would be entered and would take precedence over the EOP set, because plant indications demonstrate that the ability of the plant to achieve and maintain safe shutdown is jeopardized.

100.

Which ONE of the following describes the Protective Action Recommendations (PARs)?

In accordance with EPIP-4, Site Area Emergency, the Site Area Emergency Initial Notification Form used to notify the State of Tennessee (1) provide the state with at least ONE Protective Action Recommendation.

In accordance with EPIP-1, Emergency Plan Classification Logic, (2) can assume the responsibility for PARs when the respective emergency center is staffed and operational.

A. (1) will (2) CECC director B. (1) will (2) TSC RP Manager C. (1) will NOT (2) CECC director D. (1) wilINOT (2) TSC RP Manager

76 77 78 79 80 81 82 83 I 84 I

( D D B B D B BIDI

92 I 94195 I 96 I 97 I 98 I 99 I 1001 IBIBIDICIAIDICI

ML15222A548

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