ML16257A714
| ML16257A714 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 09/13/2016 |
| From: | NRC/RGN-II/DRS/OLB |
| To: | Tennessee Valley Authority |
| References | |
| Download: ML16257A714 (101) | |
Text
Question: 1 Points: 1.00 Given the following conditions:
Unit 2 is at 100%power Subsequently, A reactor trip occurs Which ONE of the following completes the statements?
[65-D] P-6 INTERM RANGE PERMISSIVE, will clear on 2-M-4 in ___(1)___ following the reactor trip.
Source Range NIs ___(2)___ energize automatically.
A. (1) < 9 minutes (2) will B. (1) < 9 minutes (2) will NOT C. (1) > 9 minutes (2) will D. (1) > 9 minutes (2) will NOT Watts Bar NRC Written Exam Page: 1 of 84 July 2016
Question: 2 Points: 1.00 Given the following conditions:
A LOCA has occurred on Unit 1 RCS pressure - 1450 psig and DROPPING Pressurizer level - 82% and RISING Containment pressure - 2.5 psig and RISING The following indications are observed:
Which ONE of the following completes the statements in accordance with 1-E-0, Reactor Trip or Safety Injection?
ALL RCPs ___(1)___ required to be tripped at this time.
RCPs are tripped during a SB LOCA to prevent ___(2)___.
A. (1) are (2) additional heat input from the RCPs to the RCS B. (1) are (2) high peak clad temperatures from a potential subsequent core uncovery C. (1) are NOT (2) additional heat input from the RCPs to the RCS D. (1) are NOT (2) high peak clad temperatures from a potential subsequent core uncovery Watts Bar NRC Written Exam Page: 2 of 84 July 2016
Question: 2 Points: 1.00 Question: 3 Points: 1.00 Given the following conditions:
Unit 2 has experienced a LOCA RCS pressure - 200 psig and STABLE ECCS is in recirculation mode Subsequently, CCS HX B OUTLET 2-RM-123 LIQ RAD HI [188-A], alarms Both Unit 2 CCS surge tank levels are RISING
[253-A] U2 SURGE TANK LEVEL HI/LO, is lit Which ONE of the following completes the statements?
2-FCV-70-66, UNIT 2 CCS SURGE TK VENT VLV, will indicate ___(1)___
The leak is in the ___(2)___ Heat Exchanger.
A. (1) open (2) RHR B. (1) open (2) Seal Water C. (1) closed (2) RHR D. (1) closed (2) Seal Water Watts Bar NRC Written Exam Page: 4 of 84 July 2016
Question: 4 Points: 1.00 Given the following conditions:
Unit 2 was manually tripped due to SG 2 PORV partially opening 2B DG is tagged for maintenance Two rods from Shutdown Bank B are stuck at 100 steps Step 4 of 2-E-0, Reactor Trip or Safety Injection , CHECK SI Actuated, is in progress Subsequently:
A Loss of Off-Site Power occurs MSIVs are closed RCS temperature - 550°F and STABLE SG pressures:
SG 1 - 1080 psig and STABLE SG 2 - 900 psig and LOWERING at 2 psig/minute SG 3 - 1080 psig and STABLE SG 4 - 1080 psig and STABLE RCS pressure - 2200 psig and slowly LOWERING Containment pressure - 0 psig and STABLE 2A Boric Acid Pump trips Which ONE of the following identifies the required action?
A. ACTUATE SI and continue in 2-E-0, no boration is required B. GO TO 2-ES-0.1, Reactor Trip Response, no boration is required C. GO TO 2-ES-0.1, Reactor Trip Response, and initiate normal boration D. GO TO 2-ES-0.1, Reactor Trip Response, and align RWST to CCP suction Watts Bar NRC Written Exam Page: 5 of 84 July 2016
Question: 5 Points: 1.00 Given the following conditions:
Unit 2 is in MODE 6 RCS level is being maintained within the mid-loop band in accordance with 2-GO-10, Reactor Coolant System Drain and Fill Operations RCS temperature - 135F and slowly RISING 2A RHR flow - 3000 gpm Subsequently, 2A RHR Pump begins to cavitate Which ONE of the following completes the statement in accordance with 2-AOI-14, Loss of RHR Shutdown Cooling?
The crew is required to ___(1)___, because cavitation was caused by ___(2)___.
A. (1) throttle 2A RHR pump flow (2) excessive RHR flow B. (1) throttle 2A RHR pump flow (2) inadequate NPSH due to high RCS temperature C. (1) secure the 2A RHR pump and start the 2B RHR pump (2) excessive RHR flow D. (1) secure the 2A RHR pump and start the 2B RHR pump (2) inadequate NPSH due to high RCS temperature Watts Bar NRC Written Exam Page: 6 of 84 July 2016
Question: 6 Points: 1.00 Given the following conditions:
Unit 1 is at 100% power 1-PT-68-340, PZR Press, Channel I, failed high and has NOT been bypassed in DCS 1-AOI-18, Malfunction of Pressurizer Pressure Control System, is in progress Subsequently,
[81-F] DCS CRITICAL LOOP and [82-F] DCS TROUBLE, alarm The following is viewed on DCS:
Which ONE of the following completes the statement?
With NO operator action over the next 30 minutes, RCS pressure will ___(1)___ until ___(2)___.
A. (1) RISE (2) the PORVs open. Pressure will then cycle on the PORVs B. (1) RISE (2) the reactor trips. Pressure will then be maintained at 2335 psig C. (1) LOWER (2) SI actuates. The pressurizer will then fill up and go solid D. (1) LOWER (2) SI actuates. Pressure will then cycle between 2220 psig and 2250 psig Watts Bar NRC Written Exam Page: 7 of 84 July 2016
Question: 6 Points: 1.00 Question: 7 Points: 1.00 Given the following conditions:
Unit 1 is at 100% power Reactor Trip Breaker A is OPEN for maintenance Reactor Trip Bypass Breaker A is CLOSED Reactor Trip Breaker B is CLOSED Subsequently, A Manual Reactor Trip is required The RO attempts to Trip the Reactor using the MCB hand switches The Reactor does NOT Trip Which one of the following completes the statements below?
The Reactor Trip Breaker B Shunt Trip Coil failed to ___(1)___.
The MINIMUM action required to initiate a Reactor Trip locally is to open Reactor Trip Bypass Breaker A ___(2)___ Reactor Trip Breaker B.
A. (1) energize (2) AND B. (1) energize (2) OR C. (1) de-energize (2) AND D. (1) de-energize (2) OR Watts Bar NRC Written Exam Page: 9 of 84 July 2016
Question: 8 Points: 1.00 Given the following conditions:
2-E-3, Steam Generator Tube Rupture, is in progress on Unit 2 ALL RCPs are running The following annunciators are lit:
[60-B] SG 1 LEVEL HI
[63-F] SG LEVEL DEVIATION
[77-D] PZR PRESS LO
[92-A] PZR LEVEL HI-LO Subsequently, The crew terminates high head ECCS flow
[91-C] RCS TEMP/PRESS APPROACHING SATURATION, alarms Which ONE of the following identifies the NEXT action(s) the crew is/are required to perform is to ______.
A. immediately trip ALL RCPs B. transition to 2-E-2, FAULTED STEAM GENERATOR ISOLATION C. start ECCS pumps and transition to 2-ECA-3.1, SGTR AND LOCA - Subcooled Recovery D. raise demand on 2-HIC-62-93 and 89, Charging Flow Controller, AND turn on ALL PZR heaters Watts Bar NRC Written Exam Page: 10 of 84 July 2016
Question: 9 Points: 1.00 Given the following conditions:
Unit 1 is at 100% power Subsequently, A large steam line break occurs inside containment All MSIVs fail to CLOSE Which ONE of the following MCR indications are expected for the current conditions?
NOTE: Readings are taken 1 minute after the reactor trip A. 1-NI-135A and 136A, INTERMEDIATE RANGE CH I AND II, on 1-M-4, RISING B. 1-FI-3-163A, 155A, 147A, and 170A, AFW TO SGs 1-4 FLOW on 1-M-3, indicating off scale LOW C. 1-RM-90-421A and 1-RM-90-424A, SG 1 and SG 4 DISCHARGE monitors on 1-M-30, indicating HI D. 1-RM-90-271 through 274, UPPER & LOWER CNTMT HI RANGE monitors on 1-M-30, indicating HI Watts Bar NRC Written Exam Page: 11 of 84 July 2016
Question: 10 Points: 1.00 Given the following conditions:
Unit 1 is at 100% power Subsequently, The following indications are observed for SG 1 SGs 2,3 and 4 remain at 60% Narrow Range level 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-1 feedwater heater Watts Bar NRC Written Exam Page: 12 of 84 July 2016
Question: 10 Points: 1.00 Watts Bar NRC Written Exam Page: 13 of 84 July 2016
Question: 11 Points: 1.00 Given the following conditions:
2-ECA-0.0, Loss of Shutdown Power, is in progress on Unit 2 The crew is performing step 21, Depressurize Intact SG to 300 psig Subsequently, Pressure in all SGs reaches 200 psig before the BOP stops the depressurization Which ONE of the following identifies the potential operational implications that could result from the excessive SG depressurization?
A. A transition to 2-FR-P.1, Pressurized Thermal Shock, could be required due to the excessive RCS cooldown B. Nitrogen injection from the accumulators may occur, causing natural circulation flow in the RCS to be interrupted C. A transition to 2-FR-S.2, Loss of Core Shutdown could be required if source range nuclear instruments indicate a positive startup rate D. Voiding may occur in the reactor vessel, causing the upper portion of the core to become uncovered and potentially causing core damage Watts Bar NRC Written Exam Page: 14 of 84 July 2016
Question: 12 Points: 1.00 Given the following conditions:
Unit 2 has experienced a Loss of Offsite Power and a Reactor Trip 2-ES-0.1, Reactor Trip Response, is in progress RCS pressure - 2045 psig RCS Hot leg temperatures - 574°F RCS Cold leg temperatures - 554°F CETs - 580°F Which ONE of the following identifies the RCS subcooling?
A. 58°F B. 60°F C. 66°F D. 76°F Watts Bar NRC Written Exam Page: 15 of 84 July 2016
Question: 13 Points: 1.00 Given the following conditions:
Unit 1 is at 100% power Subsequently, 120VAC Vital Instrument Power Board 1-I is de-energized due to a fault on the board 1-AOI-25.01, Loss of 120VAC Vital Instrument Power Boards 1-I or 2-I, is in progress Which ONE of the following completes the statements in accordance with 1-AOI-25.01?
CERPI Monitor ___(1)___ will be lost as a result of the failure.
Backup Rod Position Indication ___(2)___ available to verify all rod positions.
A. (1) A (2) is B. (1) A (2) is NOT C. (1) B (2) is D. (1) B (2) is NOT Watts Bar NRC Written Exam Page: 16 of 84 July 2016
Question: 14 Points: 1.00 Given the following conditions:
Unit 2 is at 100% power The following indications are observed:
[17-A] 125 DC VITAL CHGR/ BATT I ABNORMAL, is in alarm
[17-B] 125DC VITAL BATT BD1 ABNORMAL CKTS ISOLATED, is in alarm The position indicating lights for TDAFW pump 2A-S T&T Valve are NOT LIT on 2-M-4 Which ONE of the following completes the statement?
___(1)___ Diesel Generators are running and the Unit 2 steam dumps are ___(2)___.
A. (1) All 4 (2) unaffected B. (1) All 4 (2) failed closed C. (1) ONLY the 1A-A and 2A-A (2) unaffected D. (1) ONLY the 1A-A and 2A-A (2) failed closed Watts Bar NRC Written Exam Page: 17 of 84 July 2016
Question: 15 Points: 1.00 Given the following conditions:
Unit 2 is at 100% power Subsequently, A TOTAL Loss of Essential Raw Cooling Water (ERCW) occurs Which ONE of the following completes the statements in accordance with 0-AOI-13, Loss of Essential Raw Cooling Water?
Operators will ___(1)___ handswitch in STOP/PULL to LOCK to allow a connection of temporary cooling water to the secured pumps oil cooler.
LCO 3.0.3 ___(2)___ required to be entered.
A. (1) START CCP 2B-B, and PLACE CCP 2A-A (2) is B. (1) START CCP 2B-B, and PLACE CCP 2A-A (2) is NOT C. (1) START CCP 2A-A, and PLACE CCP 2B-B (2) is D. (1) START CCP 2A-A, and PLACE CCP 2B-B (2) is NOT Watts Bar NRC Written Exam Page: 18 of 84 July 2016
Question: 16 Points: 1.00 Given the following conditions:
2-ECA-1.2, LOCA Outside Containment, is in progress on Unit 2 RHR Train A cold leg injection valve 2-FCV-63-93, RHR TO CL 2&3, has just been CLOSED The following parameters are observed RCS Pressure is STABLE PZR level is off-scale LOW Safety Injection flow is STABLE Which ONE of the following completes the statement in accordance with 2-ECA-1.2, LOCA Outside Containment?
The leak is ___(1)___, as indicated by ___(2)___.
A. (1) isolated (2) STABLE RCS pressure B. (1) isolated (2) STABLE Safety Injection flow C. (1) NOT isolated (2) STABLE RCS pressure D. (1) NOT isolated (2) STABLE Safety Injection flow Watts Bar NRC Written Exam Page: 19 of 84 July 2016
Question: 17 Points: 1.00 Given the following conditions:
A Large Break LOCA has occurred on Unit 2 2-ECA-1.1, Loss of RHR Sump Recirculation, is in progress Containment pressure is 5 psig and slowly RISING Containment Spray (CS) pump suction is aligned to the RWST The following indications are observed:
Which ONE of the following completes the statements in accordance with 2-ECA-1.1?
Adequate level ___(1)___ exist in the containment sump to align the CS pumps to the sump.
Containment pressure ___(2)___ require at least one CS pump to be running.
A. (1) does (2) does B. (1) does (2) does NOT C. (1) does NOT (2) does D. (1) does NOT (2) does NOT Watts Bar NRC Written Exam Page: 20 of 84 July 2016
Question: 17 Points: 1.00 Question: 18 Points: 1.00 Given the following conditions:
A Reactor Trip and Safety Injection occurred on Unit 1 1-FR-H.1, Loss of Secondary Heat Sink, is in progress The crew is performing Appendix A, Establishing MFW Following Reactor Trip All standing SI signals have been blocked SI has NOT been reset Which ONE of the following completes the statement in accordance with 1-FR-H.1?
To reset the FWI signal, resetting SI ___(1)___ required AND cycling Reactor Trip Breakers
___(2)___ required.
A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Watts Bar NRC Written Exam Page: 22 of 84 July 2016
Question: 19 Points: 1.00 Given the following conditions:
12:00:00 Unit 2 is at 88% power Turbine Controls are in IMP IN The following indications are observed:
PRNIs - 88%
SG pressures - 998 psig Tavg - 584.4 F 2-PT-2-73, % HP TURBINE POWER TR B - 88%
12:02:00 A 200 gallon normal dilution is completed 12:05:00 The following indications are observed:
PRNIs - 91%
SG pressures - 1050 psig Tavg - 585.4 F 2-PT-2-73, % HP TURBINE POWER TR B - 88%
Which ONE of the following events could have caused the indications at 12:05:00?
A. Dilution taking effect B. SG safety valve lifting C. Continuous rod withdrawal D. Xenon concentration RISING Watts Bar NRC Written Exam Page: 23 of 84 July 2016
Question: 20 Points: 1.00 Given the following conditions:
Unit 1 is at 30% power A malfunction occurred and PZR level is 50%
Which ONE of the following completes the statement?
To restore PZR level to the program level, the operator ___(1)___ depress the AUTO/MAN button on 1-HIC-62-93A, CHARGING FLOW PZR LEVEL CONTROL and then will depress the ___(2)___.
A. (1) will (2) CLOSE (<<) button to LOWER output B. (1) will (2) OPEN (>>) button to RAISE output C. (1) will NOT (2) CLOSE (<<) button to LOWER output D. (1) will NOT (2) OPEN (>>) button to RAISE output Watts Bar NRC Written Exam Page: 24 of 84 July 2016
Question: 21 Points: 1.00 Given the following conditions:
Unit 1 and 2 are at 100% power A Gas Decay Tank release is in progress with ABGTS running for dilution air flow A leak develops on the running Waste Gas Compressor The following annunciator alarms:
Which ONE of the following describes the effect on the release AND the status of Auxiliary Building Isolation?
With NO operator actions, the Gas Decay Tank Release will ___(1)___ and an Auxiliary Building Isolation ___(2)___ occur.
A. (1) continue (2) will B. (1) continue (2) will NOT C. (1) terminate (2) will D. (1) terminate (2) will NOT Watts Bar NRC Written Exam Page: 25 of 84 July 2016
Question: 22 Points: 1.00 Given the following conditions:
A fire has started in the 2A-A Diesel Generator Room All thermal fire detectors in the area are in alarm on the Fire Detection panel Which ONE of the following identifies the automatic fire suppression system response?
A. CO2 suppression actuation B. AFFF suppression actuation C. Deluge suppression actuation D. Fixed water spray/fog suppression actuation Watts Bar NRC Written Exam Page: 26 of 84 July 2016
Question: 23 Points: 1.00 Given the following conditions:
Unit 1 is in Mode 3 The MCR has been evacuated in accordance with 1-AOI-27, Main Control Room Inaccessibility Control has been established from the Auxiliary Control Room (ACR)
RCPs are in service All Transfer Switches have been placed in AUX Subsequently,
[274-B] PZR PRESS LO, alarms 1-PI-68-336C, PZR PRESSURE, indicates 2207 psig and slowly RISING Which ONE of the following completes the statements in accordance with ARI-1-L-10 [274-B]?
The operator will ENSURE ___(1)___ PZR Backup heaters are ON.
When RCS pressure reaches 2225 psig, the PZR backup heaters ___(2)___ be energized.
A. (1) ALL (2) will B. (1) ALL (2) will NOT C. (1) 1A-A and 1B-B ONLY (2) will D. (1) 1A-A and 1B-B ONLY (2) will NOT Watts Bar NRC Written Exam Page: 27 of 84 July 2016
Question: 24 Points: 1.00 Given the following conditions:
Unit 1 is at 80% power A tube leak on SG 2 has been leaking at 25GPD for the past 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Subsequently, 1-RM-90-119, Vacuum Pump Exhaust, Lo Range, counts begin to RISE 1-RM-90-106, Lower Containment, counts begin to RISE Which ONE of the following identifies a possible cause for the indications in accordance with 1-AOI-33, Steam Generator Tube Leak?
A. A sudden fuel cladding defect develops B. A RCS leak develops inside containment C. A step increase in SG 2 leak rate to 50GPD D. A rise in reactor power above the current equilibrium level Watts Bar NRC Written Exam Page: 28 of 84 July 2016
Question: 25 Points: 1.00 Given the following conditions:
A large break LOCA has occurred on Unit 2 Containment Sump level - 55% and RISING at 2% per minute Which ONE of the following completes the statements in accordance with 2-FR-Z.2, Containment Flooding?
Entry conditions for 2-FR-Z.2, Containment Flooding, will be met in a MINIMUM of ___(1)___ minutes.
The Component Cooling System ____(2)_____ an UNEXPECTED source of water inside containment.
A. (1) 14 (2) is B. (1) 14 (2) is NOT C. (1) 18 (2) is D. (1) 18 (2) is NOT Watts Bar NRC Written Exam Page: 29 of 84 July 2016
Question: 26 Points: 1.00 Given the following conditions:
Unit 2 had a reactor trip A Loss of Offsite Power occurred 2-ES-0.4, Natural Circulation Cooldown With Steam Void in Vessel (Without RVLIS), is in progress PZR level - 92%
The crew is performing step 12 RNO: RAISE RCS pressure by 100 psi with PZR heaters Which ONE of the following completes the statement in accordance with 2-ES-0.4?
RCS pressure is raised by 100 psig to ________.
A. prevent the PZR from becoming water solid and maintain pressurizer pressure control B. promote heat removal from the upper head region of the vessel by collapsing the steam void C. maintain PZR level conditions that allow restarting the Reactor Coolant Pumps when power is restored D. provide an outflow from the pressurizer to maintain Pressurizer and RCS boron concentrations within 50 ppm Watts Bar NRC Written Exam Page: 30 of 84 July 2016
Question: 27 Points: 1.00 Given the following conditions:
A RED condition exists on 2-FR-0, Status Trees, for Pressurized Thermal Shock, FR-P Which ONE of the following completes the statements?
The permissives to ARM RCS Cold Overpressure Protection ___(1)___ LIT.
The parameter used for these permissives is ___(2)___.
A. (1) a r e (2) temperature B. (1) a r e (2) pressure C. (1) are NOT (2) temperature D. (1) are NOT (2) pressure Watts Bar NRC Written Exam Page: 31 of 84 July 2016
Question: 28 Points: 1.00 Given the following conditions:
Unit 2 is at 100% power Subsequently,
[97-C] RCP 3 STANDPIPE LEVEL HI/LO, alarms
[100-E] RCP SEAL LEAK-OFF FLOW LO, alarms The following RCP parameters are observed:
Lower Bearing #1 Seal Leak-off Temperature Flow RCP 1 137 ºF 1.5 gpm RCP 2 139 ºF 1.3 gpm RCP 3 138 ºF 0.7 gpm RCP 4 138 ºF 1.1 gpm The Radwaste operator reports RCDT level slowly RISING The crew fills the RCP 3 standpipe, but the alarms remain LIT Which ONE of the following completes the statements in accordance with 2-AOI-24, RCP Malfunctions During Pump Operation?
RCP 3 ___(1)___ seal has failed.
RCP 3 ___(2)___ meet Immediate Trip Criteria.
A. (1) #2 (2) does B. (1) #2 (2) does NOT C. (1) #3 (2) does D. (1) #3 (2) does NOT Watts Bar NRC Written Exam Page: 32 of 84 July 2016
Question: 29 Points: 1.00 Given the following conditions:
Unit 2 is at 100% power Subsequently, RCS loop 3 flow has LOWERED by 5% due to RCP 3 impeller degradation Which ONE of the following will result from the decreased flow rate in loop 3?
A. DNBR LOWERS B. SG 3 pressure RISES C. RCS loop 3 T LOWERS D. PZR variable heater demand LOWERS Watts Bar NRC Written Exam Page: 33 of 84 July 2016
Question: 30 Points: 1.00 Given the following conditions:
00:00:00 Unit 2 RCS temperature is 205 ºF 2B CCP is running 00:25:00 2A CCP breaker is racked in 00:30:00 2A CCP is running 00:34:00 2B CCP is stopped 00:48:00 2B CCP breaker is racked out 00:52:00 2B CCP breaker is tagged Which ONE of the following completes the statements in accordance with Technical Specifications?
At 00:48:00, LCO 3.5.3, ECCS - Shutdown, is ___(1)___.
For this evolution, LCO 3.4.12, Cold Overpressure Mitigation System (COMS), ___(2)___ required to be entered.
A. (1) met (2) was B. (1) met (2) was NOT C. (1) NOT met (2) was D. (1) NOT met (2) was NOT Watts Bar NRC Written Exam Page: 34 of 84 July 2016
Question: 31 Points: 1.00 Given the following conditions:
Unit 1 is preparing to place RHR in shutdown cooling mode in accordance with 1-SOI-74.01, Residual Heat Removal System RCS pressure is 350 psig RCS temperature is 340ºF Subsequently,
[142-D] RX MOV/VENT BD TRAIN B UNDERVOLTAGE, alarms Normal and alternate supply breakers are OPEN on 480V SD Boards 1B1-B and 1B2-B The OAC attempts to OPEN 1-FCV-74-1 and 1-FCV-74-2 NOTE: 1-FCV-74-1, LOOP 4 HL TO RHR SUCTION 1-FCV-74-2, LOOP 4 HL TO RHR SUCTION Which ONE of the following completes the statements in accordance with 1-SOI-74.01?
1-FCV-74-1 ___(1)___ OPEN from the Main Control Room.
1-FCV-74-2 ___(2)___ OPEN from the Main Control Room.
A. (1) will (2) will B. (1) will (2) will NOT C. (1) will NOT (2) will D. (1) will NOT (2) will NOT Watts Bar NRC Written Exam Page: 35 of 84 July 2016
Question: 32 Points: 1.00 Given the following conditions:
Unit 1 is preparing to place RHR Train A in service for shutdown cooling 1-SI-0-10, Shutdown Margin, minimum boron concentration (CB) is 1800 ppm RCS CB - 2160 ppm RHR Train A CB - 2050 ppm NOTE: 1-FCV-74-1, LOOP 4 HL TO RHR SUCTION 1-FCV-74-2, LOOP 4 HL TO RHR SUCTION Which ONE of the following completes the statements in accordance with 1-SOI-74.01, Residual Heat Removal System?
If RHR Train A is placed in service at its current CB, SRM counts will ___(1)___.
Once opened, 1-FCV-74-1 and 1-FCV-74-2 ___(2)___ close automatically if RCS pressure RISES to > 370 psig.
A. (1) RISE (2) will B. (1) RISE (2) will NOT C. (1) LOWER (2) will D. (1) LOWER (2) will NOT Watts Bar NRC Written Exam Page: 36 of 84 July 2016
Question: 33 Points: 1.00 REFERENCE PROVIDED Given the following conditions:
Unit 1 is conducting 1-SI-0-2A-03, 1900 - 0700 Shift and Daily Surveillance Log Mode Three RCS TC - 520 °F RCS Pressure - 1010 psig The following is observed on 1-M-6:
Which ONE of the following completes the statements?
There are ___(1)___ accumulators that meet the level and pressure requirements of LCO 3.5.1, Accumulators..
LCO 3.5.1, Accumulators ___(2)___ APPLICABLE.
A. (1) 2 (2) is B. (1) 2 (2) is NOT C. (1) 3 (2) is D. (1) 3 (2) is NOT REFERENCE PROVIDED Watts Bar NRC Written Exam Page: 37 of 84 July 2016
Question: 33 Points: 1.00 Question: 34 Points:
Given the following conditions:
12:00:00 Unit 1 has experienced a large break LOCA RWST level is 36% and LOWERING The following indications are observed:
1-M-4 1-M-6 12:05:00 RWST level is 32% and LOWERING Which ONE of the following completes the statements?
At 12:05:00, 1-FCV-63-72 CNTMT SUMP TO RHR PUMP A SUCTION, indicates ___(1)___.
At 12:05:00, 1-FCV-63-73 CNTMT SUMP TO RHR PUMP B SUCTION, indicates ___(2)___.
A. (1) OPEN (2) OPEN B. (1) OPEN (2) CLOSED C. (1) CLOSED (2) OPEN D. (1) CLOSED (2) CLOSED Watts Bar NRC Written Exam Page: 39 of 84 July 2016
Question: 34 Points: 1.00 1-M-4 1-M-6
Question: 35 Points: 1.00 Given the following conditions:
12:00:00 Unit 2 is at 100% power 12:01:00 Pressurizer PORV, 2-PCV-68-334, lifts inadvertently 12:02:00 Reactor Trip and SI occur 12:05:00 PRT parameters:
12:10:00 12:15:00 2-PCV-68-334 reseats Which ONE of the following describes the expected containment conditions at 12:20?
Containment radiation levels ___(1)___ LOWERING.
Containment temperature ___(2)___ LOWERING.
A. (1) are (2) is B. (1) are (2) is NOT C. (1) are NOT (2) is D. (1) are NOT (2) is NOT Watts Bar NRC Written Exam Page: 41 of 84 July 2016
Question: 35 Points: 1.00 12:05:00 12:10:00 Watts Bar NRC Written Exam Page: 42 of 84 July 2016
Question: 36 Points: 1.00 Given the following conditions:
Unit 1 is at 100% power A leak develops on the #3 RCP thermal barrier heat exchanger 1-AOI-15, Loss of Component Cooling Water, Section 3.4, CCS In-leakage, has been completed Which one of the following completes the statements in accordance with 1-AOI-15, Loss of Component Cooling Water?
Following the completion of 1-AOI-15, CCS flow through the Miscellaneous Equipment Header, will be
___(1)___ than it was prior to the leak.
A reactor trip ___(2)___ required.
A. (1) HIGHER (2) is B. (1) HIGHER (2) is NOT C. (1) LOWER (2) is D. (1) LOWER (2) is NOT Watts Bar NRC Written Exam Page: 43 of 84 July 2016
Question: 37 Points: 1.00 Given the following conditions:
Unit 1 is at 100% power PZR pressure is 2234 psig Subsequently,
[208-C] 6.9 SD BD 1B-B UV/OV/CONTROL PWR FAILURE, alarms
[205-A] DG START/RUN FAILURE, alarms on 0-M-26 for the 1B-B DG RCS pressure is 2205 psig and slowly LOWERING Which ONE of the following identifies the status of the PZR heaters?
A. ALL PZR heater groups are energized B. PZR control group 1D heaters are energized ONLY C. PZR backup 1A-A AND control group 1D heaters are energized ONLY D. PZR backup 1B-B AND control group 1C heaters are energized ONLY Watts Bar NRC Written Exam Page: 44 of 84 July 2016
Question: 38 Points: 1.00 Given the following conditions:
Unit 1 is at 100% power Subsequently, Power Range N-41 fails HIGH 1-AOI-4, Nuclear Instrumentation Malfunctions, is in progress Which ONE of following completes the statements in accordance with 1-AOI-4?
The Power Range N-41 failure ___(1)___ affect the OPT trip setpoint.
OPT provides protection against ___(2)___.
A. 1) will
- 2) DNB B. 1) will
- 2) high power density (kw/ft)
C. 1) will NOT
- 2) DNB D. 1) will NOT
- 2) high power density (kw/ft)
Watts Bar NRC Written Exam Page: 45 of 84 July 2016
Question: 39 Points: 1.00 Given the following conditions:
Unit 2 is at 100% power Containment pressure channel 2-PDI-30-42, has been declared INOPERABLE Subsequently, 2-PDS-30-42B, CNTMT PRESS HI, has been placed In TRIP 2-PDS-30-42A, CNTMT PRESS HI-HI, has been placed in BYPASS Which ONE of the following identifies the coincidences for ESF actuations from the remaining operable containment pressure channels?
___(1)___ for SI actuation.
___(2)___ for CS actuation.
A. (1) 1/3 (2) 1/3 B. (1) 1/2 (2) 1/3 C. (1) 1/2 (2) 2/3 D. (1) 2/3 (2) 2/3 Watts Bar NRC Written Exam Page: 46 of 84 July 2016
Question: 40 Points: 1.00 Given the following conditions:
Unit 2 has experienced a LOCA
ØB Containment Isolation has been actuated Which ONE of the following completes the statements regarding the effect of Containment parameters?
SG NR indicated level, 2-LI-3-38B is ___(1)___ than actual level.
PZR indicated level on 2-LI-68-320A is ___(2)___ than actual level.
A. (1) higher (2) higher B. (1) higher (2) lower C. (1) lower (2) higher D. (1) lower (2) lower Watts Bar NRC Written Exam Page: 47 of 84 July 2016
Question: 41 Points: 1.00 Given the following conditions:
Unit 1 is in MODE 4 Subsequently, Air Return Fan 1A-A is inadvertently started
[144-A] ICE COND INLET DOOR OPEN, alarms Which ONE of the following completes the statements?
Position indication for the Ice Condenser Lower Inlet Doors ___(1)___ available in the MCR.
After Air Return Fan 1A-A is stopped, the Ice Condenser Lower Inlet Doors will close automatically because of ___(2)___ .
A. (1) is (2) gravity B. (1) is (2) spring pressure C. (1) is NOT (2) gravity D. (1) is NOT (2) spring pressure Watts Bar NRC Written Exam Page: 48 of 84 July 2016
Question: 4231 Points: 1.00 Which ONE of the following completes the statement regarding 2-FCV-72-45, CNTMT SUMP TO CS PUMP B SUCTION?
2-FCV-72-45, CNTMT SUMP TO CS PUMP B SUCTION is interlocked with ___(1)___ to prevent
___(2)___.
A. (1) 2-FCV-72-2, CNTMT SPRAY HEADER B TO CNTMT (2) operation of 2B CS pump with no flow path B. (1) 2-FCV-72-2, CNTMT SPRAY HEADER B TO CNTMT (2) inadvertent transfer of RWST to the containment sump C. (1) 2-FCV-72-21, RWST TO CS PUMP B SUCTION (2) operation of 2B CS pump with no flow path D. (1) 2-FCV-72-21, RWST TO CS PUMP B SUCTION (2) inadvertent transfer of RWST to the containment sump Watts Bar NRC Written Exam Page: 49 of 84 July 2016
Question: 43 Points: 1.00 Given the following conditions:
A plant cooldown is in progress on Unit 2 in accordance with 2-GO-6, Unit Shutdown From Hot Standby To Cold Shutdown RCS pressure is 1850 psig RCS temperature is 505°F Subsequently, An event occurs:
RCS pressure - 1700 psig and LOWERING at 10 psi per second SG pressures - 700 psig and LOWERING at 25 psi per second Containment pressure - 1.2 psig and RISING Which ONE of the following completes the statement?
Safety Injection ___(1)___ actuated, and Main Steam Isolation ___(2)___ actuated.
A. (1) has (2) has B. (1) has (2) has NOT C. (1) has NOT (2) has D. (1) has NOT (2) has NOT Watts Bar NRC Written Exam Page: 50 of 84 July 2016
Question: 44 Points: 1.00 Given the following conditions:
Unit 2 is at 80% power The Standby Main Feedwater Pump is tagged for maintenance Subsequently, 2A Main Feedwater Pump trips Which ONE of the following completes the statements?
An automatic turbine runback ___(1)___ occur.
The 2B Main Feedwater Pump ___(2)___ accelerate to its high speed stop.
A. (1) will (2) will B. (1) will (2) will NOT C. (1) will NOT (2) will D. (1) will NOT (2) will NOT Watts Bar NRC Written Exam Page: 51 of 84 July 2016
Question: 45 Points: 1.00 Given the following conditions:
Unit 1 is in Mode 1 The TDAFW Pump is tagged out of service Subsequently, A Reactor Trip occurs due to a Loss of Feedwater 1B-B 6.9kV SD BD de-energizes on a differential fault Which ONE of the following accurately completes the statements?
All SGs ___(1)___ being fed.
SG 2 ___(2)___ being fed at approximately 220 gpm.
A. (1) are (2) is B. (1) are (2) is NOT C. (1) are NOT (2) is D. (1) are NOT (2) is NOT Watts Bar NRC Written Exam Page: 52 of 84 July 2016
Question: 46 Points: 1.00 Given the following conditions:
Unit 1 and Unit 2 are at 100% power CSST A has been removed from service The following switch positions are observed on 0-ECB-3:
Subsequently, Both Unit 1 and Unit 2 Main Generators trip due to a momentary grid disturbance Which ONE of the following completes the statements?
[6-F] LOAD SHED INITIATED, ___(1)___alarm on 1-M-1.
The purpose of the Load Shed Circuit is to prevent more than 4 RCPs from being powered from a single CSST by stopping ___(2)___.
A. (1) will (2) 2 RCPs on each Unit B. (1) will (2) ALL Unit 1 RCPs C. (1) will NOT (2) 2 RCPs on each Unit D. (1) will NOT (2) ALL Unit 1 RCPs Watts Bar NRC Written Exam Page: 53 of 84 July 2016
Question: 47 Points: 1.00 Given the following conditions:
125V VITAL BATTERY CHARGER I output breaker just tripped open Which ONE of the following completes the statements?
Annunciator 17-B ___(1)___ expected to alarm.
Indicator 1-EI-57-92, VIT Batt BD I AMPS, is expected to be indicating ___(2)___.
A. (1) is (2) upscale B. (1) is (2) downscale C. (1) is NOT (2) upscale D. (1) is NOT (2) downscale Watts Bar NRC Written Exam Page: 54 of 84 July 2016
Question: 48 Points: 1.00 Given the following conditions:
WBN experienced a Loss of Off-site Power Subsequently, Off-site power has been restored and the 1A-A Diesel Generator is being removed from service in accordance with Section 8.3.1 (Removing DG from Service-DG Tied on to SD Bd) of 0-SOI-82.01, Diesel Generator (DG) 1A-A Which ONE of the following completes the statements in accordance with 0-SOI-82.01, Diesel Generator (DG) 1A-A?
DG frequency must be adjusted so that the synchroscope is spinning in the ___(1)___ direction prior to synchronizing the Shutdown Board with off-site power.
1-HS-57-41B, 1716 - Normal From CSST C, will be taken to CLOSE when the synchroscope is at the
___(2)___ position.
A. (1) clockwise (2) 12 oclock B. (1) clockwise (2) 5 minutes before the 12 oclock C. (1) counter-clockwise (2) 12 oclock D. (1) counter-clockwise (2) 5 minutes after the 12 oclock Watts Bar NRC Written Exam Page: 55 of 84 July 2016
Question: 49 Points: 1.00 Given the following conditions:
A Loss of Offsite Power occurs on Unit 1 The following is observed on 0-M-26:
Which ONE of the following completes the statements?
1A-A EDG had a(n) ___(1)___ failure.
1A-A 6.9 kV Shutdown Board is ___(2)___ .
A. (1) differential (2) energized B. (1) differential (2) de-energized C. (1) electrical field (2) energized D. (1) electrical field (2) de-energized Watts Bar NRC Written Exam Page: 56 of 84 July 2016
Question: 50 Points: 1.00 Given the following conditions:
Unit 1 is at 100% power Subsequently,
[178-A] SG BLDN 1-RM-120/121 LIQ RAD HI, alarms Which ONE of the following describes the SGBD system response?
A. 1-FCV-15-43, SG BLOWDOWN FLOW CONTROL, CLOSES B. 1-FCV-15-6, SG BLOWDOWN DISCH TO CNDS DEMIN, OPENS C. 1-FCV-15-44, STM GEN BLWDN DISCH TO CTBD FLOW CNTL, OPENS D. 1-FCV-1-7/14/25/32, SG BLOWDOWN CONTAINMENT ISOLATION, CLOSES Watts Bar NRC Written Exam Page: 57 of 84 July 2016
Question: 51 Points: 1.00 Given the following conditions:
Unit 1 and Unit 2 are operating at 100% power Subsequently, The following annunciators are observed:
[223-A] ERCW HDR A SUP PRESS LO
[223-B] ERCW PMP A-A DISCH PRESS LO
[225-C] ERCW PMP C-A DISCH PRESS LO
[170-E] IPS VLV & STRNR ROOM A SUMP LEVEL HI ERCW headers 1A and 2A are indicating LOW flow Which ONE of the following completes the statement in accordance with 0-AOI-13, Loss of Essential Raw Cooling Water?
Section ___(1)___ is required to be performed, and it will direct the crew to
___(2)___.
A. (1) 3.5, Supply Header Rupture in IPS (2) stop and Lockout out all A Train ERCW pumps B. (1) 3.5, Supply Header Rupture in IPS (2) start additional ERCW pumps to maintain pressure C. (1) 3.4, Supply Header Rupture in the Yard/Downstream of Strainer (2) stop and Lockout out all A Train ERCW pumps D. (1) 3.4, Supply Header Rupture in the Yard/Downstream of Strainer (2) start additional ERCW pumps to maintain pressure Watts Bar NRC Written Exam Page: 58 of 84 July 2016
Question: 52 Points: 1.00 Given the following conditions:
Unit 2 experienced a reactor trip Unit 2 CST sustained damage resulting in a unisolable leak Which ONE of the following completes the statement?
The Unit 2 Auxiliary Feedwater (AFW) pumps will swap suction to the ___(1)___ based on ___(2)___.
A. (1) Unit 1 CST (2) Unit 2 CST level B. (1) Unit 1 CST (2) AFW suction pressure C. (1) ERCW system (2) Unit 2 CST level D. (1) ERCW system (2) AFW suction pressure Watts Bar NRC Written Exam Page: 59 of 84 July 2016
Question: 53 Points: 1.00 Given the following conditions:
A large air leak occurs in the plant 0-PI-32-105A, AUX AIR B PRESS - LOWERS to 75 psig Subsequently, 0-PI-32-105A, AUX AIR B PRESS - 83 psig and RISING slowly Which ONE of the following completes the statements?
0-PCV-33-4, Service Air Isolation, is ___(1)___.
1-FCV-32-102, Aux Air To Rx Bldg Train B, is ___(2)___ .
A. (1) open (2) open B. (1) open (2) closed C. (1) closed (2) open D. (1) closed (2) closed Watts Bar NRC Written Exam Page: 60 of 84 July 2016
Question: 54 Points: 1.00 Which ONE of the following completes the statements regarding 0-FCV-32-82, ESSENT CONTROL AIR TR A NORM FLOW ISOL?
0-FCV-32-82 ___(1)___ closed by a ØB Containment Isolation signal.
0-FCV-32-82 ___(2)___ closed by a Low Control Air header pressure.
A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Watts Bar NRC Written Exam Page: 61 of 84 July 2016
Question: 55 Points: 1.00 Which ONE of the following completes the statements regarding Containment Isolation?
A manual ØB Containment Isolation ___(1)___ directly initiate a Containment Ventilation Isolation (CVI).
To manually initiate a ØB Containment Isolation, the operator must place ___(2)___ ØB handswitches on panel 2-M-6 to ACTUATE.
A. (1) will (2) 1 of 2 B. (1) will (2) 2 of 2 C. (1) will NOT (2) 1 of 2 D. (1) will NOT (2) 2 of 2 Watts Bar NRC Written Exam Page: 62 of 84 July 2016
Question: 56 Points: 1.00 Given the following conditions:
A Small Break LOCA has occurred on Unit 1 1-ES-1.2, Post LOCA Cooldown and Depressurization, is in progress CETs - 546 ºF and LOWERING Tavg - 531 ºF and LOWERING RCS WR pressure - 1520 psig and LOWERING RCPs are stopped Which ONE of the following completes the statement in accordance with 1-ES-1.2, Post LOCA Cooldown and Depressurization?
If subcooling is lost during RCS depressurization, ___(1)___ AND the crew will ___(2)___.
A. (1) reactor upper head voiding may occur (2) re-initiate Safety Injection B. (1) reactor upper head voiding may occur (2) cooldown at 100 ºF/hour C. (1) loss of RCS thermal driving head will occur (2) re-initiate Safety Injection D. (1) loss of RCS thermal driving head will occur (2) cooldown at 100 ºF/hour Watts Bar NRC Written Exam Page: 63 of 84 July 2016
Question: 57 Points: 1.00 Given the following conditions:
Unit 1 is at 50% power Subsequently,
[82-F] DCS TROUBLE, alarms The following is observed on 1-M-5:
Which ONE of the following completes the statements?
A single loop 2 ___(1)___ RTD has instantly failed high.
Charging flow will ___(2)___.
A. (1) Thot (2) RISE B. (1) Thot (2) remain STABLE C. (1) Tcold (2) RISE D. (1) Tcold (2) remain STABLE Watts Bar NRC Written Exam Page: 64 of 84 July 2016
Question: 57 Points: 1.00 Watts Bar NRC Written Exam Page: 65 of 84 July 2016
Question: 58 Points: 1.00 Given the following conditions:
Unit 1 is LOWERING power from 100% to 90% power
[83-D] PLANT COMPUTER GENERATED ALARM (SEE ICS), alarms The following is observed on 1-M-4:
Which ONE of the following completes the statements in accordance with Technical Specifications and 1-AOI-2, Malfunction of Reactor Control System?
Control rod D8 ___(1)___ outside the limits of LCO 3.1.5, Rod Group Alignment Limits.
If the rod(s) is/are to be recovered within one hour, 1-RBSS, Rod Bank Select, will be positioned to ___(2)___.
A. (1) is (2) CBD B. (1) is (2) MANUAL C. (1) is NOT (2) CBD D. (1) is NOT (2) MANUAL Watts Bar NRC Written Exam Page: 66 of 84 July 2016
Question: 58 Points: 1.00 Question: 59 Points: 1.00 Given the following conditions:
Unit 1 is at 100% power Subsequently, A Core Exit Thermocouple (CET) fails to 780 ºF Which ONE of the following completes the statements describing the Inadequate Core Cooling Monitor (ICCM)?
The display on the ICCM will be ___(1)___.
CETs can be read on the ___(2)___.
A. (1)
(2) ICCM ONLY B. (1)
(2) ICCM and ICS C. (1)
(2) ICCM ONLY D. (1)
(2) ICCM and ICS Watts Bar NRC Written Exam Page: 68 of 84 July 2016
Question: 60 Points: 1.00 Given the following conditions:
Unit 1 RCS temperature - 150 ºF Fuel movements are in progress in the Auxiliary Building Upper Containment Purge is in progress The following handswitches are in the REFUEL position 1-HS-90-410-A, HI RAD ABSCE ISOL DURING REFUELING LOGIC SW (TR-A) 1-HS-90-415-B, HI RAD ABSCE ISOL DURING REFUELING LOGIC SW (TR-B)
Subsequently:
[174-A] CNTMT PURGE EXH 1-RM-130/131 RAD HI, alarms Which ONE of the following completes the statements?
Containment Vent Isolation (CVI) valves ___(1)___ CLOSED.
Auxiliary building gas treatment system (ABGTS) ___(2)___STARTED.
A. (1) have (2) has B. (1) have (2) has NOT C. (1) have NOT (2) has D. (1) have NOT (2) has NOT Watts Bar NRC Written Exam Page: 69 of 84 July 2016
Question: 61 Points: 1.00 REFERENCE PROVIDED Given the following conditions:
Date Time 9/20/2016 08:00 Unit 1 and Unit 2 are at 100% power Train A SFP Cooling is in service SFP HX B is isolated for maintenance Spent Fuel Pool (SFP) level - 749 2.5 SFP temperature - 115 ºF 10:00 [249-E] SFP HX A RETURN FLOW LO, alarms 0-AOI-45, Loss of Spent Fuel Pool Level or Cooling, is in progress Which ONE of the following completes the statements?
The time for the SFP to reach 200 ºF is approximately ___(1)___ hours.
With NO operator action, SFP CB will ___(2)___.
A. (1) 54 (2) RISE B. (1) 54 (2) remain the SAME C. (1) 65 (2) RISE D. (1) 65 (2) remain the SAME REFERENCE PROVIDED Watts Bar NRC Written Exam Page: 70 of 84 July 2016
Question: 62 Points: 1.00 Given the following conditions:
2-AOI-33, Steam Generator Tube Leak, is in progress on Unit 2 The crew is performing step 4:
The US determines that VCT level cannot be maintained Which ONE of the following completes the statements in accordance with 0-TI-12.04, User's Guide for Abnormal and Emergency Operating Instructions?
The US ___(1)___ delegate performance of 2-AOI-33 to the BOP.
2-AOI-33 will be performed ___(2)___ the completion of Steps 1 through 4 of 2-E-0.
A. (1) can (2) after B. (1) can (2) concurrently with C. (1) CANNOT (2) after D. (1) CANNOT (2) concurrently with Watts Bar NRC Written Exam Page: 71 of 84 July 2016
Question: 63 Points: 1.00 Which ONE of the following completes the statements describing the operation of the Steam Dumps?
The Load Rejection Controller (LRC) uses ___(1)___ Tref as an input.
The LRC HI Bistable DIRECTLY provides an OPEN signal to___(2)___ groups of steam dump valves.
A. (1) median select (2) two B. (1) median select (2) four C. (1) auctioneered high (2) two D. (1) auctioneered high (2) four Watts Bar NRC Written Exam Page: 72 of 84 July 2016
Question: 64 Points: 1.00 Given the following conditions:
Unit 1 is at 100% power Subsequently,
[175-B] VAC PMP EXH 1-RM-119 RAD HI, alarms 1-AOI-33, Steam Generator Tube Leak, is in progress on Unit 1 Which ONE of the following completes the statements?
1-RM-90-119, Vacuum Pump Exhaust Radiation Monitor, is considered the ___(1)___ indication of a SG tube leak.
Condenser vacuum pump exhaust___(2)___ automatically terminated venting to atmosphere.
A. (1) first (2) has B. (1) first (2) has NOT C. (1) backup (2) has D. (1) backup (2) has NOT Watts Bar NRC Written Exam Page: 73 of 84 July 2016
Question: 65 Points: 1.00 Given the following conditions:
[180-D] ERCW DISCH HDR A 0-RM-133/140 INSTR MALF, alarms Which ONE of the following completes the statements?
A possible cause of the alarm is ___(1)___.
ERCW discharge ___(2)___ automatically realign from the cooling tower basin to the yard holding pond.
A. (1) sample flow less than setpoint (2) will B. (1) sample flow less than setpoint (2) will NOT C. (1) a background radiation rise at the monitor (2) will D. (1) a background radiation rise at the monitor (2) will NOT Watts Bar NRC Written Exam Page: 74 of 84 July 2016
Question: 66 Points: 1.00 Which ONE of the following describes the shift turnover requirements in accordance with OPDP-1, Conduct of Operations?
The oncoming CRO ___(1)___ required to be informed of all LCO entries and exits performed the previous shift.
For a temporary relief of the OAC, the Unit Supervisor ___(2)___ required to be notified.
A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Watts Bar NRC Written Exam Page: 75 of 84 July 2016
Question: 67 Points: 1.00 Which ONE of the following completes the statement in accordance with OPDP-1, Conduct of Operations?
A plant-wide announcement ___(1)___ required for starting or stopping an AFW pump AND
___(2)___ required for abnormal procedure entry.
A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Watts Bar NRC Written Exam Page: 76 of 84 July 2016
Question: 68 Points: 1.00 Which ONE of the following completes the statement in accordance with 2-GO-7, Refueling Operations?
Before fuel movement begins, Refueling Cavity water level must be greater than or equal to 23 feet above ___(1)___ and ___(2)___ temperature must be maintained between 60F-120F.
A. (1) top of fuel (2) reactor coolant B. (1) top of fuel (2) containment air C. (1) vessel flange (2) reactor coolant D. (1) vessel flange (2) containment air Watts Bar NRC Written Exam Page: 77 of 84 July 2016
Question: 69 Points: 1.00 Which ONE of the following describes the Unit 1 and Unit 2 SRNI drawers?
On Unit 1, SRNI control power overcurrent protection is provided by ___(1)___ of the SRNI drawer.
On Unit 2, SRNI control power overcurrent protection is provided by ___(2)___ of the SRNI drawer.
A. (1) fuses on the front (2) fuses on the front B. (1) fuses on the front (2) circuit breakers on the rear C. (1) circuit breakers on the rear (2) fuses on the front D. (1) circuit breakers on the rear (2) circuit breakers on the rear Watts Bar NRC Written Exam Page: 78 of 84 July 2016
Question: 70 Points: 1.00 REFERENCE PROVIDED Given the following conditions:
Unit 1 is at 100% power 1-SI-68-35, Pressurizer Heater Capacity, is in progress Voltage on 1-EL-57-39, 6.9 SHTDN BD 1A-A indicates 6.9kV Backup Heater Group 1A-A is energized and indicates 15 amps on SD BD 1A-A, Compt 20 Which ONE of the following completes the statements in accordance with Technical Specifications?
Backup Heater Group 1A-A is ___(1)___.
___(2)___ groups of pressurizer heaters are required to be operable.
A. (1) OPERABLE (2) Two B. (1) OPERABLE (2) Three C. (1) INOPERABLE (2) Two D. (1) INOPERABLE (2) Three REFERENCE PROVIDED Watts Bar NRC Written Exam Page: 79 of 84 July 2016
Question: 71 Points: 1.00 Given the following conditions:
Unit 1 is at 70% power Subsequently, Reactor power ramps from 70% to 85% over a two minute period due to a governor valve malfunction Which ONE of the following completes the statements in accordance with LCO 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits?
DURING the power ramp, the LCO 3.4.1 Pressurizer Pressure limit ___(1)___ applicable, and the RCS Average Temperature limit ___(2)___ applicable.
A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Watts Bar NRC Written Exam Page: 80 of 84 July 2016
Question: 72 Points: 1.00 Given the following conditions:
Unit 2 is in MODE 5 Train A RHR Shutdown Cooling is in service Which ONE of the following completes the statement in accordance with 2-GO-6, Unit Shutdown from Hot Standby to Cold Shutdown?
______ will require the notification of Radiation Protection that Reactor Building radiation levels may increase to values greater than 100 mrem/hr and may require radiation posting to be upgraded to High Radiation Area or Locked High Radiation Area?
A. Flushing Train B RHR System B. Hydrogen peroxide addition to the RCS C. Swapping CVCS Mixed Bed Demineralizers D. Swapping Spent Fuel Pool Cooling Filter Demineralizers Watts Bar NRC Written Exam Page: 81 of 84 July 2016
Question: 73 Points: 1.00 Which ONE of the following completes the statements in accordance with Emergency Plan Procedures?
The ___(1)___ is responsible for dispatching Emergency Response Teams during a plant emergency A(n) ___(2)___ is the lowest level emergency that requires the emergency centers to be staffed.
A. (1) Technical Support Center (2) Alert B. (1) Technical Support Center (2) Site Area Emergency C. (1) Operations Support Center (2) Alert D. (1) Operations Support Center (2) Site Area Emergency Watts Bar NRC Written Exam Page: 82 of 84 July 2016
Question: 74 Points: 1.00 Given the following conditions:
A turbine runback occurred on Unit 2 Control rods are in AUTO and not moving Subsequently,
[94-A] TAVG-TREF DEVIATION, alarms Tavg is observed to be 7.5 ºF greater than Tref Which ONE of the following actions should be taken FIRST to respond to the alarm in accordance with 2-ARI-88-94, Reactor Coolant System?
A. Adjust turbine load to match Tavg with Tref B. Trip the reactor and enter E-0, Reactor Trip or Safety Injection C. Place control rods in MANUAL and Borate to restore Tavg to Tref D. Place control rods in MANUAL and restore Tavg to Tref using rods Watts Bar NRC Written Exam Page: 83 of 84 July 2016
Question: 75 Points: 1.00 Given the following conditions:
An ATWS occurred on Unit 1 Reactor power is 10% and LOWERING A ØB Containment Isolation signal is inadvertently initiated Which ONE of the following completes the statements in accordance with 1-FR-S.1, Nuclear Power Generation/ATWS?
MG set breakers ___(1)___ required to be OPENED .
RCPs ___(2)___ be stopped immediately.
A. (1) are (2) should B. (1) are (2) should NOT C. (1) are NOT (2) should D. (1) are NOT (2) should NOT Watts Bar NRC Written Exam Page: 84 of 84 July 2016
RO References
- 1-SI-0-2A-03, 1900 - 0700 Shift and Daily Surveillance Log Mode Three, DS 1, page 4 of 13
- WBN Unit 1 Nuclear Operating Book, Sheet A-15, Page 6
- 1-SI-68-35, pressurizer Heater Capacity
WBN 1900 - 0700 1-SI-0-2A-03 Unit 1 Shift And Daily Surveillance Log Rev. 0038 Mode Three Page 20 of 32 Data Sheet 1 (Page 4 of 13)
Mode 3 Surveillance Log: 1900-0700 Date ________
Ref Location Description Instrument # T S Limit Data Acc NOT Met CL Accum 1 1-FCV-63-118 OPEN Outlet (1-HS-63-118A) CLOSED CL Accum 2 1-FCV-63-98 OPEN Outlet (1-HS-63-98A) Valves Open-when CLOSED Contact SRO to 18 1-M-6 Pzr pressure consult Tech CL Accum 3 1-FCV-63-80 >1000 psig. OPEN Specs.
Outlet (1-HS-63-80A) CLOSED CL Accum 4 1-FCV-63-67 OPEN Outlet (1-HS-63-67A) CLOSED CL Accum 1 1-LI-63-129 gal Lvl 1-LI-63-119 7630 and 8000 gal gal and MCD 96 Check operability CL Accum 2 1-LI-63-109 gal by acceptable gal. Chemistry is to Lvl 1-LI-63-99 be notified to gal deviation between perform 1-SI-63-6 redundant level and CL Accum 3 1-LI-63-89 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> if tank gal pressure channels Lvl 1-LI-63-81 level is increased gal when pressurizer 75 gal and tank NOT pressure is above CL Accum 4 1-LI-63-82 filled from RWST.(1) gal 1000 psig. If Lvl deviation limit is 19 1-M-6 1-LI-63-60 gal exceeded, 1-PI-63-128 psig determine the CL Accum 1 channel inoper-able Press 1-PI-63-126 psig AND record only 1-PI-63-108 psig the operable CL Accum 2 channel. This Press 1-PI-63-106 610 and 660 psig psig channel check is and MCD 30 1-PI-63-88 psig NOT a technical CL Accum 3 psig (1) specification Press 1-PI-63-86 psig re-quirement.
CL Accum 4 1-PI-63-62 psig Press 1-PI-63-61 psig (1) When Pzr pressure greater than 1000 psig.
Initials INDICATE acc met OR action in Performers SROs Acc not Met column initiated. Initials Initials Remarks:
Watts Bar Nuclear Plant Unit 1 Surveillance Instruction 1-SI-68-35 Pressurizer Heater Capacity Revision 0008 Quality Related Level of Use: Continuous Use Effective Date: 12-19-2014 Responsible Organization: OPS, Operations Prepared By: P.R. Neu Approved By: Brian Joseph
WBN Pressurizer Heater Capacity 1-SI-68-35 Unit 1 Rev. 0008 Page 2 of 13 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of Revision/Change 2 9/9/97 All Major Revision to incorporate changes recommended by onshift personnel. Deleted Mode 3 & 4 performance sections because Tech Specs require Pzr heaters operable in Modes 1-4. Revised method to energize Pzr heaters A-A & B-B to obtain amp readings.
UNIC-1 6/7/99 2, 6, 8 Non-intent change. Change handswitch position from P-Auto to A-P Auto for 1-HS-68-341A and 341D.
3 6/10/99 All Non-intent change. Incorporate UNIC-1.
4 1/30/04 2, 3, 6-9 Non-intent change. Operator feedback items.
Revised method to energize heaters using master controller vs. spray valve to obtain amp reading. Prevents placing unit in DNB T/S parameter. Editorial - change decreasing to dropping. Rolled Section 6.2 to page 9 and added page to procedure. Updated TOC.
5 12/21/05 2, 7 Added IF/THEN statement to 6.1, [8], to prevent unnecessary controller manipulation.
6 08/01/06 All This procedure has been converted from Word 95 to Word 2002(XP) using Rev. 6 by Lorie Dake 8 Incorporated UC-1 (Corrected Step Number).
7 08/29/07 2, 9 Non-intent. Corrected note prior to Step 6.1.[3]
and 6.2.[3] to match Tech Spec value of 2214 psig.
8 12/19/14 2, 8, 10, 11 Corrected second party signoffs to IVs IAW NPG-SPP-22.206 [PER956258-001].
WBN Pressurizer Heater Capacity 1-SI-68-35 Unit 1 Rev. 0008 Page 3 of 13 Table of Contents
1.0 INTRODUCTION
.......................................................................................................... 4 1.1 Purpose ........................................................................................................................ 4 1.2 Scope............................................................................................................................ 4 1.2.1 Operability Tests to be Performed .................................................................. 4 1.2.2 Surveillance Requirements Fulfilled and Modes ............................................. 4 1.3 Frequency and Conditions ............................................................................................ 4
2.0 REFERENCES
............................................................................................................. 4 2.1 Performance References .............................................................................................. 4 2.2 Developmental References........................................................................................... 4 2.2.1 TVA Drawings ................................................................................................. 4 2.2.2 Other ............................................................................................................... 5 3.0 PRECAUTIONS AND LIMITATIONS ........................................................................... 5 4.0 PREREQUISITE ACTIONS .......................................................................................... 5 5.0 ACCEPTANCE CRITERIA ........................................................................................... 5 6.0 PERFORMANCE .......................................................................................................... 6 6.1 PZR BACKUP HEATER GROUP A-A AND CONTROL HEATER GROUP D (6.9 kV Shutdown Board 1A-A) ................................................................... 6 6.2 PZR BACKUP HEATER GROUP B-B AND BACKUP HEATER GROUP C (6.9 kV Shutdown Board 1B-B) .................................................................. 9 7.0 POST PERFORMANCE ACTIVITIES ........................................................................ 11 8.0 RECORDS .................................................................................................................. 12 8.1 QA Records ................................................................................................................ 12 8.2 Non-QA Records ........................................................................................................ 12 Source Notes............................................................................................. 13
WBN Pressurizer Heater Capacity 1-SI-68-35 Unit 1 Rev. 0008 Page 4 of 13
1.0 INTRODUCTION
1.1 Purpose This Instruction provides detailed steps to verify operability of the pressurizer (PZR) heaters.
1.2 Scope 1.2.1 Operability Tests to be Performed Measurement of the circuit current and verification that at least two groups of PZR heaters each have capacity of at least 150 kW.
1.2.2 Surveillance Requirements Fulfilled and Modes Performance of this Instruction satisfies the following Surveillance Requirements (SRs):
SURVEILLANCE APPLICABLE PERFORMANCE REQUIREMENT MODES MODES SR 3.4.9.2 1, 2, 3 1, 2, 3, 4 1.3 Frequency and Conditions This Instruction is to be performed every 92 days.
2.0 REFERENCES
2.1 Performance References None 2.2 Developmental References 2.2.1 TVA Drawings A. 45W724-1, -2.
B. 1-45W760-68-3, -4.
WBN Pressurizer Heater Capacity 1-SI-68-35 Unit 1 Rev. 0008 Page 5 of 13 2.2.2 Other A. Unit 1 Technical Specification Section 3.4.9.
3.0 PRECAUTIONS AND LIMITATIONS A. Pzr heatup rate should not exceed 50° F an hour and SHALL not exceed 100°F an hour.
B. This SI should not be performed with PZR water solid operations.
4.0 PREREQUISITE ACTIONS
[1] RECORD Start Date and time on Surveillance Task Sheet. ________
[2] OBTAIN SM/Unit SRO approval to perform this Instruction on Surveillance Task Sheet. ________
[3] RECORD present plant Mode: ________. ________
[4] ENSURE Pzr level is >17%. ________
5.0 ACCEPTANCE CRITERIA A. At least 2 groups of PZR heaters OPERABLE, each with a capacity of at least 150 kW.
B. If Acceptance Criteria not met, the SM/Unit SRO should be notified as soon as practical after observance of noncompliance, for possible entry into LCO 3.4.9.
WBN Pressurizer Heater Capacity 1-SI-68-35 Unit 1 Rev. 0008 Page 6 of 13 6.0 PERFORMANCE 6.1 PZR BACKUP HEATER GROUP A-A AND CONTROL HEATER GROUP D (6.9 kV Shutdown Board 1A-A)
[1] PLACE 1-XS-57-39, 6.9 SD BD 1A-A VOLTMETER SELECTOR, in SHTDN BD 1A-A position [1-M-1]. ________
[2] RECORD voltage from 1-EI-57-39, 6.9 SHTDN BD 1A-A
[1-M-1]:
________Volts NOTES
- 1) Dropping PZR pressure <2214 psig in Mode 1 requires entry into LCO 3.4.1
- 2) Pzr Backup group heaters energize at 2210 psig dropping pressure.
[3] RECORD position of 1-HS-68-341A, BACKUP HEATERS A-A (1-M-4].
OFF ON A-P-AUTO
[4] ENERGIZE Backup Heater Group A-A by HOLDING 1-HS-68-341A, BACKUP HEATERS A-A [1-M-4] to the ON position. ________
[5] RECORD Backup Heater Group A-A amperage from 6.9 kV SD BD 1A-A, Cmpt 20, PRESSURIZER HEATER BACKUP GROUP TRANSFORMER 1A-A:
Amps
[6] RETURN 1-HS-68-341A, BACKUP HEATERS A-A [1-M-4] to the position recorded in 6.1[3]. ________
WBN Pressurizer Heater Capacity 1-SI-68-35 Unit 1 Rev. 0008 Page 7 of 13 NOTE Pzr backup heaters energize at a controller output indication of 2210 psig dropping pressure, with Control Heater Group D full on at 2220 psig. Actual Pzr pressure should not change. The following step should be done slowly, monitoring the ammeter on Control Heater Group D rising, which indicates the heater is loading. Past performance history indicates readings of 14 to 34 amps have satisfied acceptance criteria. This can be accomplished without energizing the backup heaters if done slowly.
[7] DISPATCH operator to 6.9 kV SD BD 1A-A, Cmpt 21, to observe amp reading for Control Heater Group D. ________
[8] IF Control Group D is NOT sufficiently loaded, THEN PLACE 1-PIC-68-340A, Pzr Press Master Control, in MANUAL and very slowly bump output lower until local ammeter for Control Heater Group D rises. ________
[9] WHEN Control Heater Group D is at highest reading desired, THEN STOP lowering controller output. ________
[10] RECORD Control Heater Group D amperage from 6.9 kV SD BD 1A-A, Cmpt 21, PZR HEATERS CONTROL GROUP XFORMER 1D: ________
Amps
[11] SLOWLY RAISE 1-PIC-68-340A, Pzr Press Master Control, demand output until deviation meter indicates zero, THEN PLACE 1-PIC-68-340A in AUTO. ________
[12] ENSURE Pzr pressure remains normal (2218-2260 psig) and stable. ________
WBN Pressurizer Heater Capacity 1-SI-68-35 Unit 1 Rev. 0008 Page 8 of 13
[13] CALCULATE Backup Heater Group A-A heater capacity using the following formula (Acc Crit: 150 kW):
P = 1.732 x (E / 1000) x I Where: P = Heater Capacity (kW)
E = Shutdown Board Voltage from STEP 6.1[2]
I = Current (Amps) from STEP 6.1[5]
P = 1.732 x (________V /1000) X________Amps P = ________kW IV
[14] CALCULATE Control Heater Group D heater capacity using the following formula (Acc Crit: 150 kW):
P = 1.732 x (E / 1000) x I Where: P = Heater Capacity (kW)
E = Shutdown Board Voltage from STEP 6.1[2]
I = Current (Amps) from STEP 6.1[10]
P = 1.732 x (________V /1000) X________Amps P = ________kW IV
WBN Pressurizer Heater Capacity 1-SI-68-35 Unit 1 Rev. 0008 Page 9 of 13 6.2 PZR BACKUP HEATER GROUP B-B AND BACKUP HEATER GROUP C (6.9 kV Shutdown Board 1B-B)
[1] PLACE 1-XS-57-66, 6.9 SD BD 1B-B VOLTMETER SELECTOR, in SHTDN BD 1B-B position (1-M-1]. ________
[2] RECORD voltage from 1-EI-57-66, 6.9 SHTDN BD 1B-B
[1-M-1]. ________
Volts ________
NOTES
- 1) Dropping PZR pressure <2214 psig in Mode 1 requires entry into LCO 3.4.1.
- 2) Pzr Backup group heaters energize at 2210 psig dropping pressure.
[3] RECORD position of 1-HS-68-341D, BACKUP HEATERS B-B
[1-M-4].
OFF ON A-P-AUTO
[4] ENERGIZE Backup Heater Group B-B by HOLDING 1-HS-68-341D, BACKUP HEATERS B-B [1-M-4] to the ON position. ________
[5] RECORD Backup Heater Group B-B amperage from 6.9 kV SD BD 1B-B, Cmpt 20, PRESSURIZER HEATER BACKUP GROUP TRANSFORMER 1B-B:
________Amps ________
[6] RETURN 1-HS-68-341D, BACKUP HEATERS B-B [1-M-4] to the position recorded in STEP 6.2[3]. ________
WBN Pressurizer Heater Capacity 1-SI-68-35 Unit 1 Rev. 0008 Page 10 of 13
[7] ENERGIZE Backup Heater Group C by placing 1-HS-68-341H, BACKUP HEATERS C to the ON position. ________
[8] RECORD Backup Heater Group C amperage from 6.9 kV SD BD 1B-B, Cmpt 21, PRESSURIZER HEATERS CONTROL GROUP TRANSFORMER 1C:
Amps________ ________
[9] DEENERGIZE Backup heater groups as necessary AND ENSURE Pzr pressure returns to normal (2218-2260 psig) and stabilizes. ________
[10] CALCULATE Backup Heater Group B-B heater capacity using the following formula (Acc Crit: 150 kW):
P = 1.732 x (E/ 1000) x I Where: P = Heater Capacity (kW)
E = Shutdown Board Voltage from STEP6.2[2]
I = Current (Amps) from STEP6.2[5]
P = 1.732 x (________V /1000) X________Amps P = ________kW IV
WBN Pressurizer Heater Capacity 1-SI-68-35 Unit 1 Rev. 0008 Page 11 of 13
[11] CALCULATE Backup Heater Group C heater capacity using the following formula (Acc Crit: 150 kW):
P = 1.732 x (E / 1000) x I Where: P = Heater Capacity (kW)
E = Shutdown Board Voltage from STEP6.2[2]
I = Current (Amps) from STEP 6.2[8]
P = 1.732 x (________V /1000) X________Amps P = ________kW IV 7.0 POST PERFORMANCE ACTIVITIES NOTE If SI fails to meet the stated Acceptance Criteria, the SM/Unit SRO should be notified for possible entry into LCO 3.4.9.
[1] VERIFY Acceptance Criteria MET. ________
[2] NOTIFY SM/Unit SRO that this Instruction is complete. ________
[3] RECORD completion date and time on Surveillance Task Sheet. ________
WBN Pressurizer Heater Capacity 1-SI-68-35 Unit 1 Rev. 0008 Page 12 of 13 8.0 RECORDS 8.1 QA Records The Data Package is a QA record, is handled in accordance with the Document Control and Records Management Program, and contains the following:
A. Completed parts of Sections 4.0, 6.0 and 7.0.
B. Section 5.0.
C. Surveillance Task Sheet.
8.2 Non-QA Records None
WBN Pressurizer Heater Capacity 1-SI-68-35 Unit 1 Rev. 0008 Page 13 of 13 Source Notes (Page 1 of 1)
Implementing Requirements Statement Source Document Statement None
Watts Bar 2016-301 RO Exam Key
- 1. C 26. B 51. A
- 2. D 27. A 52. D
- 3. C 28. B 53. C
- 4. D 29. A 54. C
- 5. A 30. B 55. B
- 6. C 31. B 56. A
- 7. B 32. B 57. D
- 8. C 33. C 58. D
- 9. D 34. B 59. B
- 10. B 35. A 60. A
- 11. B 36. B 61. A
- 12. B 37. C 62. A
- 13. A 38. D 63. A
- 14. A 39. C 64. B
- 15. A 40. A 65. B
- 16. C 41. B 66. A
- 17. A 42. D 67. B
- 18. A 43. C 68. C
- 19. C 44. C 69. B
- 20. A 45. C 70. A
- 21. B 46. C 71. C
- 22. A 47. C 72. B
- 23. C 48. A 73. C
- 24. A 49. B 74. D
- 25. C 50. B 75. B