ML092290932
| ML092290932 | |
| Person / Time | |
|---|---|
| Site: | Summer  (NPF-012) |
| Issue date: | 07/09/2009 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 50-395/09-301 | |
| Download: ML092290932 (95) | |
Text
FACILITY NAME: Summer Section 8 REPORT NUMBER: 05000395/2009301 FINAL RO WRITTEN EXAM CONTENTS:
IXI Final RO Written Exam (75 'as given' questions with changes made during administration annotated)
~ Reference Handouts Provided To Applicants fi(] Answer Key Location of Electronic Files:
As given RO Written:
Attached
References:
Attached Answer Key:
Attached
~~
Submitted By: _--'~'---'=':::""-
Verified B)'~~~=~ ____ _
Name: ______________.2009 V.C. Summer RO NRC Exam - As Given
- 1. Which ONE (1) of the choices below completes the following statement?
Form: 0 Version: 0 After a Large Break LOCA, the crew must initiate Hot Leg Recirculation within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
., and to minimize boron precipitation in the ____ _
A. of the transfer to Cold Leg Recirculation; core B. of the transfer to Cold Leg Recirculation; cold leg nozzles C. after event initiation; core D. after event initiation; cold leg nozzles Thursday, July 09, 2009 8:08:34 AM 1
2009 V.C. Summer RO NRC Exam - As Given
- 2. A cooldown is in progress, in accordance with AOP-112.2, Steam Generator Tube Leak Not Requiring Sf, for tube leakage in Steam Generator 'B'.
Which ONE (1) of the following identifies the status of PVT-201 0, PWR RELIEF B, and MVG-2802A, MS LOOP B TO TO EFP?
PVT-2010 MVG-2802A A.
MAN/CLOSED CLOSED/ENERGIZED B.
MAN/CLOSED CLOSED/DE-ENERGIZED C.
AUTO/1150 PSIG CLOSED/ENERGIZED D.
AUTO/1150 PSIG CLOSED/DE-ENERGIZED Thursday. July 09. 2009 8:08:34 AM 2
2009 V.C. Summer RO NRC Exam - As Given
- 3. Given the following plant conditions:
Due to a LOCA, RB pressure peaked at 18 psig and is now 2.5 psig.
During the implementation of the EOPs, the crew completed actions in EOP-14.0, Response to Inadequate Core Cooling.
The crew is now performing actions in EOP-1.2, Safety Injection Termination.
Which ONE (1) of the choices below completes the following statement?
The RB spray pumps must be run for a MINIMUM of hours, and BOTH
.,----c--- push buttons must be depressed to secure the RB spray pumps and place in standby.
A. 8; RESET TRAIN A(B) RB SPRAY RESET B. 2; RESET TRAIN A(B) RB SPRAY RESET C. 8; PHASE B - TRAIN A(B) CNTMT ISOL D.2; PHASE B - TRAIN A(B) CNTMT ISOL Thursday, July 09. 2009 8:08:34 AM 3
2009 V.C. Summer RO NRC Exam - As Given
- 4. Given the following plant conditions:
100% power A LOCA has occurred in the Auxiliary Building.
A Reactor Trip and Safety Injection are manually actuated.
The crew has entered EOP-2.5, LOCA Outside Containment.
SI has NOT been reset.
Which ONE (1) of the following describes the MINIMUM action(s) required to CLOSE MVG-8888A, RHR LP A TO COLD LEGS?
A. Take the MVG-8888A Control Switch on the MCB to CLOSE ONLY.
B. RESET Train A of Safety Injection; AND Take the MVG-8888A Control Switch on the MCB to CLOSE.
C. Take the Train A Power Lockout Switch to ON; AND Take the MVG-8888A Control Switch on the MCB to CLOSE.
D. RESET both trains of Safety Injection; AND Take the MVG-8888A Control Switch on the MCB to CLOSE.
Thursday, July 09, 2009 8:08:34 AM 4
2009 V.C. Summer RO NRC Exam - As Given
- 5. Given the following plant conditions:
100% power Electrical grid disturbances on 230 KV Bus #1 have resulted in the operator making manual adjustments with the GEN FIELD VOLT ADJ (AUTO) Control Switch.
The EX2000 Voltage Regulator Core 1 fails electrically.
Which ONE (1) of the following describes how the operator's adjustments for the electrical grid disturbances affected the Main Generator AND how the Main Generator will respond to the Core 1 failure?
A. Main Generator reactive load will vary The Main Generator Breaker and Generator Field Breaker will remain CLOSED B. Main Generator reactive load will vary The Main Generator Breaker and Generator Field Breaker will OPEN C. Main Generator real load will vary The Main Generator Breaker and Generator Field Breaker will remain CLOSED D. Main Generator real load will vary The Main Generator Breaker and Generator Field Breaker will OPEN Thursday. July 09, 2009 8:08:34 AM 5
2009 V.C. Summer RO NRC Exam - As Given
- 6. Given the following plant conditions:
100% power The electric plant is in a normal, at-power lineup.
Annunciator 7.2 KV BOP BUSSES LOSS OF DC (XCP-635, 6-1) has actuated.
Electricians report that the supply breaker from DPN-1 HX3 to XSW-1A has tripped open.
Which ONE (1) of the following identifies the opening capability for the XSW-1A feeder breaker?
A. Can be opened manually using the trip pushbutton at the breaker ONLY.
B. Can be opened manually using the open contactor with a screwdriver at the breaker OR using the trip pushbutton at the breaker.
C. Can be opened manually using the trip pushbutton at the breaker OR automatically by protective relay actuation.
D. Can be opened manually using the open contactor with a screwdriver at the breaker OR automatically by protective relay actuation.
Thursday. July 09. 2009 8:08:34 AM 6
2009 V.C. Summer RO NRC Exam - As Given
- 7. Given the following plant conditions:
14% power A main turbine warmup is in progress.
Main Feedwater (MFW) Pump '8' is in service.
The normal feeder breaker for service bus XSW-1A tripped OPEN.
The alternate feeder breaker to XSW-1A failed to CLOSE.
Which ONE (1) of the choices below completes the following statement?
The 'A' S/G FRV will be operated in ______ to prevent a ____ _
A. MANUAL; High-High S/G level
- 8. AUTOMATIC; High-High S/G level C. MANUAL; Low-Low S/G level D. AUTOMATIC; Low-Low S/G level Thursday, July 09. 2009 8:08:34 AM 7
2009 V.C. Summer RO NRC Exam - As Given
- 8. Given the following plant conditions:
Power was being maintained at 12-15% while preparing to synchronize the Main Generator to the grid.
Main Feed Pump (MFP) 'A' was running.
MFPs 'B' and 'C' were tripped.
Main Feed Pump 'A' tripped for an unknown reason.
The Reactor tripped on S/G Low-Low level and the operating crew is now implementing EOP-1.1, Reactor Trip Recovery.
Which ONE (1) of the following describes the response of the MDEFP Flow Control Valves (FCVs) and the MINIMUM actions necessary to throttle the FCVs?
A. The FCVs receive an open signal due to the trip of MFP 'A';
Take the MD EFP RESET Switch to RESET, take the individual FCV control switch to MAN, adjust the Hagan controller.
B. The FCVs receive an open signal due to the trip of MFP 'A';
Take the individual FCV control switch to MAN, adjust the Hagan controller.
C. The FCVs receive an open signal due to the S/G Low-Low level; Take the MD EFP RESET Switch to RESET, take the individual FCV control switch to MAN, adjust the Hagan controller.
D. The FCVs receive an open signal due to the S/G Low-Low level; Take the individual FCV control switch to MAN, adjust the Hagan controller.
Thursday, July 09, 2009 8:08:34 AM 8
2009 V.C. Summer RO NRC Exam - As Given
- 9. Given the following plant conditions:
The unit was at 100% power when the turbine tripped.
All controllers were in the normal, full power alignment.
The crew is performing EOP-1.1, Reactor Trip Recovery.
Tavg is 55rF and rising.
Condenser pressure is 6.0" Hg abs.
The required operator action is to use the ___ to lower Tavg.
If this action is NOT taken, steam pressure will rise to ___ _
A. Steam line Power Reliefs; 1133 psig B. Condenser Dumps; 1133 psig C. Steam line Power Reliefs; 1176 psig D. Condenser Dumps; 1176 psig Thursday. July 09.20098:08:34 AM 9
2009 V.C. Summer RO NRC Exam - As Given
- 10. Given the following plant conditions:
90% power An instrument failure causes a plant transient. which results in a Reactor Trip.
On the trip. TWO (2) control rods remain at 6 steps. ONE (1) control rod remains at 12 steps. and ONE (1) control rod remains at 18 steps.
According to EOP-1.1. Reactor Trip Recovery. which ONE (1) of the following describes the required response and the MINIMUM amount of boric acid to be added?
A. Borate through the Boric Acid Blender and set the batch integrator to 2500 gallons.
B. Borate through the Boric Acid Blender and set the batch integrator to 5800 gallons.
C. Emergency borate 2500 gallons through MVT-8104. EMERG BORATE.
D. Emergency borate 5800 gallons through MVT-8104. EMERG BORATE.
Thursday. July 09, 20098:08:34 AM 10
2009 V.C. Summer RO NRC Exam - As Given
- 11. Given the following plant conditions:
A plant load increase at Y:.% per minute is in progress.
A malfunction in the Rod Control System results in Control Rods stepping out TEN (10) steps, at which point they are placed in MANUAL and stop moving.
The load increase is stopped 2 minutes after the rods are placed in MANUAL.
Control Rods are manually inserted to restore Tavg to Tref.
Considering ONLY the conditions stated, which ONE (1) of the choices below completes the following statement?
Total Power Defect has become _--:--=----;: __ negative, and Control Rods were inserted to restore Tavg to Tref.
A. less; less than 1 0 steps B. less; 10 steps C. more; less than 10 steps D. more; L-__
~1~0~s.tep~s~ ______________________________________________ ~
Thursday, July 09, 2009 8:08:34 AM 11
2009 V.C. Summer RO NRC Exam - As Given
- 12. Given the following plant conditions:
ALL oftsite power (ESF & BOP) is lost, resulting in a Reactor Trip following 30 days of operation at 100% power.
The operating crew is responding per EOP-1.1, Reactor Trip Recovery.
Both MDEFPs are running.
RCS pressure is 2085 psig.
ALL S/G pressures are 1035 psig.
The Core Subcooling Monitor is NOT available.
Which ONE (1) of the following combinations of RCS Thot and Tcold indicate that natural circulation is in progress?
STEAM TABLES PROVIDED Teold CF)
A.
615 557 B.
615 551 C.
585 557 D.
585 551 Thursday. July 09, 2009 8:08:34 AM 12
2009 V.C. Summer RO NRC Exam - As Given
- 13. Given the following plant conditions:
8% power The crew is making preparations to roll the Main Turbine to 1800 RPM.
Which ONE (1) of the following conditions REQUIRES the associated Reactor Coolant Pump(s) to be stopped IMMEDIATELY using SOP-101, Reactor Coolant System?
A. RCP 'C' #1 seal DP is 350 psid and decreasing.
B. MVG-9600, RCP THERM BAR ISOL, closes due to a failure in the control circuit.
C. Annunciator RCP 'B' UP OIL RESVR HilLa (XCP-617,1-4) actuates due to a HIGH level.
D. Annunciator RCP 'A' VIBR HI (XCP-617, 1-3) actuates. Shaft vibration is 15.1 mils and increasing at 0.1 mils I hr. Frame vibration is 5.1 mils and increasing at 0.1 mils I hr.
Thursday. July 09. 2009 8:08:34 AM 13
2009 V.C. Summer RO NRC Exam - As Given
- 14. Given the following plant conditions:
Mode 5 The RCS is solid with pressure being automatically maintained.
A licensed operator trainee inadvertently energized one set of PZR Backup Heaters.
Assuming NO operator action, which ONE (1) of the following describes the FIRST response to the rising RCS pressure?
A. Annunciator LP LTDN FLO/PRESS HI (XCP-613, 2-4) actuates.
B. Letdown flow increases as HCV-142, L TDN FROM RHR, opens.
C. Annunciator DEMIN FLO DIVERT TEMP HI (XCP-613, 1-2) actuates.
D. Letdown flow increases as PCV-145, Letdown Pressure Control Valve, opens.
Thursday, July 09, 2009 8:08:34 AM 14
2009 V.C. Summer RO NRC Exam - As Given
- 15. Which ONE (1) of the choices below completes the following statement?
LCV-115D, RWST TO CHG PP SUCT, is powered from ___ and MVG-8106, CHG PP, is powered from __ _
A. lOA2Z; lOB2Z B. 1 DB2Y; 1 DB2Z C. 1 DB2Y; 1 DA2Y D. lOA2Z; lOA2Y Thursday, July 09, 2009 8:08:35 AM 15
2009 V.C. Summer RO NRC Exam - As Given
- 16. Given the following plant conditions:
A cool down is in progress.
Mode 4 was just entered.
RHR Train 'A' was just started in the cooldown mode.
Which ONE (1) of the following describes the operability of RHR Train 'A' with respect to Technical Specification 3.5.3, ECCS SUBSYSTEMS - TAVG <350°F?
A. INOPERABLE until Thot is < 250°F because of RHR suction voiding concerns.
B. INOPERABLE because it is no longer in the injection alignment described in the surveillance.
C. OPERABLE because Train 'A' is capable of being manually realigned to RWST in the injection mode.
D. OPERABLE because Train 'A' is fulfilling the core cooling basis for the Limiting Condition for Operation.
Thursday, July 09. 2009 8:08:35 AM 16
2009 V.C. Summer RO NRC Exam - As Given
- 17. Given the following plant conditions:
A large break LOCA has occurred.
The operating crew has verified cold leg recirculation alignment per EOP-2.2, Transfer to Cold Leg Recirculation.
RHR Pump 'A' and 'B' are in service with 3750 gpm flow indicated on FI-602AIB.
RHR Pump 'A' amps have decreased and are oscillating.
RHR Pump 'A' flow and discharge pressure have begun to oscillate.
Which ONE (1) of the following is the FIRST required action(s) to stabilize RHR Pump
'A' amps?
A. Go to EOP-2.4, Loss of Emergency Coolant Recirculation.
B. Place Charging Pump 'A' in PULL TO LK NON-A; then evaluate RHR Pump amps.
C. Ensure HCV-603A, A OUTLET, is closed; then throttle closed FCV-605A, A BYP, as necessary D. Ensure FCV-605A, A BYP, is closed; then throttle closed HCV-603A, A OUTLET, as necessary.
Thursday. July 09. 2009 8:08:35 AM 17
2009 V.C. Summer RO NRC Exam - As Given
- 18. Given the following plant conditions:
55% power A Main Generator Field Failure (40 Relay) occurs.
Due to the transient, ALL Pressurizer PORVs opened for ONE (1) minute.
The NROATC notes that PRT pressure rises, then rapidly drops.
Which ONE (1) of the choices below completes the following statement?
Pressurizer Relief Tank (PRT) pressure will __ _ The crew will then initially implement ___ _
A. stabilize at a higher than nonnal pressure.
EOP-1.0, Reactor Trip/Safety Injection Actuation B. stabilize at a higher than normal pressure.
AOP-214.2, Response to Load Rejection/Runback C. stabilize at a lower than nonnal pressure.
EOP-1.0, Reactor Trip/Safety Injection Actuation D. stabilize at a lower than nonnal pressure.
AOP-214.2, Response to Load Rejection/Runback Thursday, July 09,20098:08:35 AM 18
2009 V.C. Summer RO NRC Exam - As Given
- 19. Given the following plant conditions:
100% power CCW Loop 'A' is the Active Loop.
The CCW Booster Pump alignment is as follows.
CCW Booster Pump (CCBP) 'A' is in AUTO and NOT running.
CCBP 'B' is in AUTO and running.
CCBP 'C' is in OFF.
A leak develops in the discharge header of CCBP Pump 'B' and discharge pressure drops to 40 psig.
Which ONE (1) of the following describes the resulting Component Cooling Booster Pump configuration?
A. No CCBPs are running.
B. ONLY CCBP 'A' is running.
C. ONLY CCBP 'B' is running.
D. CCBPs 'A' and 'B' are running.
Thursday. July 09. 2009 8:08:35 AM 19
2009 V.C. Summer RO NRC Exam - As Given
- 20. Given the following plant conditions:
100% power PZR level is 59% and slowly DECREASING.
Tavg is 5S7"F and stable.
RCS pressure is 2220 psig and slowly DECREASING.
RM-A2 gaseous and particulate radiation monitor indications are INCREASING.
RB pressure is 1.1 psig and slowly RISING.
Annunciators RBCU 1N2A (1 B/2B) DRN FLO HI (XCP-607 (60S) 2-2) actuated.
PZR PORV and safety valve tailpipe temperatures are slowly RISING.
PRT pressure is 7 psig and STABLE.
Which ONE (1) of the choices below completes the following statement?
The event in progress is a and charging flow will _____ prior to a subsequent automatic Reactor Trip/SI.
A. leaking PZR PORV; increase B. leaking PZR PORV; decrease C. PZR steam space leak; increase D. PZR steam space leak; decrease Thursday, July 09, 2009 8:08:35 AM 20
2009 V.C. Summer RO NRC Exam - As Given
- 21. Given the following plant conditions:
Backup Group 1 PZR heaters control switch is in NORMAL-AFTER-STOP.
Backup Group 2 PZR heaters control switch is in NORMAL-AFTER-START.
Control Group PZR heaters control switch is in NORMAL-AFTER-START.
The CNTRL GRP AMPs meter reads approximately 12 amps.
PZR pressure is 2235 psig and decreasing slowly.
The NROATC then notes the following:
BIU Group 1 Heaters:
BIU Group 2 Heaters:
Control Group Heaters:
Green Light ON ON OFF Amber Light OFF ON OFF Red Light OFF OFF ON The NROATC takes manual control of PK-444A, PZR PRESS MASTER CONTROL Which ONE (1) of the choices below identifies the alarm that should accompany these indications and the action that would mitigate the downward trend in PZR pressure?
A. PZR HTR CNTRL OR BU GRP 1/2 TRIP (XCP-616, 3-1);
Increase the MIA station output (% demand)
B. PZR HTR CNTRL OR BU GRP 1/2 TRIP (XCP-616, 3-1);
Decrease the MIA station output (% demand)
C. SCR OUTPUT LOSS (XCP-616,4-6);
Increase the MIA station output (% demand)
D. SCR OUTPUT LOSS (XCP-616,4-6);
Decrease the MIA station output (% demand)
Thursday. July 09, 2009 8:08:35 AM 21
2009 V.C. Summer RO NRC Exam - As Given
- 22. Given the following plant conditions:
A Small Break LOCA has occurred.
PZR pressure is stable at 1275 psig.
Containment temperature is 192°F.
Actual PZR level is 50%.
Which ONE (1) of the following describes the effect that the above plant conditions will have on LI-460, PZR LEVEL %?
A. Both containment temperature and PZR pressure will make LI-460 read HIGHER than actual.
B. Containment temperature will make LI-460 read HIGHER than actual, while PZR pressure will make LI-460 read LOWER than actual.
C. Both containment temperature and PZR pressure will make LI-460 read LOWER than actual.
D. Containment temperature will make LI-460 read LOWER than actual, while PZR pressure will make LI-460 read HIGHER than actual.
Thursday. July 09. 2009 8:08:35 AM 22
2009 V.C. Summer RO NRC Exam - As Given
- 23. Given the following plant conditions:
25% power Reactor Engineering is evaluating physics data prior to giving clearance to raise power.
L T -460, Pressurizer Level Channel, failed and has been removed from service and the associated bistables are tripped per AOP-401.6, Pressurizer Level Control and Protection Channel Failure.
According to Technical Specifications Table 3.3-1, Reactor Trip Instrumentation, the Pressurizer Water Level - High reactor trip is to be operable for these conditions.
The number of REMAINING channels necessary to initiate a PZR high water level trip would be __ _
A. NOT required; ONE (1)
B. required; ONE (1)
C. NOT required; TWO (2)
D. required; TWO (2)
Thursday. July 09. 2009 8:08:35 AM 23
2009 V.C. Summer RO NRC Exam - As Given
- 24. Given the following plant conditions:
Mode 3 The plant is being cooled down to Cold Shutdown per GOP-6, Plant Shutdown from Hot Standby to Cold Shutdown (Mode 3 to Mode 5).
The NROATC begins depressurizing the RCS to 900-950 psig.
At 1970 psig, the NROATC takes both PZR SI Train 'A', and Train 'B', Switches to BLOCK.
PT -457, PRESSURIZER PRESSURE TRANSMITTER, fails HIGH.
All remaining Pressurizer Pressure Transmitters read 1950 psig and slowly decreasing.
Which ONE (1) of the following identifies the result of this failure?
A. PZR PORV 445B block logic changes state.
B. The Pressurizer Pressure Safety Injection block is automatically reset.
C. PZR PORV 445B will automatically open.
D. The Pressurizer Pressure Safety Injection block is unaffected.
Thursday, July 09, 2009 8:08:35 AM 24
2009 V.C. Summer RO NRC Exam - As Given
- 25. Given the following plant conditions:
100% power IPT-951, Reactor Building Pressure Channel II, has failed HIGH.
IPT-951 was properly removed from service per Technical Specifications.
Which ONE (1) of the following indicates the number of OPERABLE channels required to initiate a HIGH-1 and a HIGH-3 RB pressure actuation signal?
REFERENCE PROVIDED HIGH -1 HIGH-3 A.
1 1
B.
1 2
C.
2 1
D.
2 2
Thursday, July 09, 2009 8:08:35 AM 25
INSTRUMENTATION 3143.2 ENGINEERED SAFETY FEAruRE AqruATlON SYSTEM INSTRUMENTATION UMmNG CONOmON FOR OPERATION 3.3.2 The EngfnMred SafeI¥ Feature Ach II'tion System (ESFASJ InIIrumentation channellrOl,!JC;f InlerIock:a shown In Table 3.3-3 shall be OPEFIABLE....... their trip setpoinls sat c;:oilslstant With the vatuaS shown iri !he Trip Settdllt coUm! of Table 3.3-4 and With RESPONSE TIMES as ehown in Table 3.3-5.
APPUCABll.fTY: As shown in Table 3.3-3.
AqI!ON:
- a.
WIth an ESFAS Instn.mentalion or Int9rtock Tr1J SeIpoint trip less consarvatiw than the value shown in the Trip Setpoint Column but more conservative than the value shown in the AItowabIe VeJue Column of Tabte 3.3-4. ~
the SeIpoint consistent with the Trip SeIpoint vatue.
- b.
WIth an ESFAS Insllunenlalion or InteJ10ck Tr1J SeIpclnI: teA conservallv9 !han the vaIue shown In the AlloWable Valle Cotumn of Table 3.~. declare the channel inopeIabIe and appIy the applicable ACTION statement requlnlmants of Table 3.3-3 until the c::hanneI ia;....... ed to its OPERABLE status with fIa seIpoInt ac/jUstec/
COI_tel'll with the Tr11 SeIpoint value.
- c.
WIth an ESFAS ~
cham.. or interlock inoperabIct take the AcnON shown In Tabla 3.3-3.
SURVElUANCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentallon channel and Interlock and the autcmatic actu8110n logic and relays shall be demonsIra1ecI OPERABlE by perfonnance of the engine ered II8Iety feature actuation sysIIIm insIrumentaiion surve/l1IJ1C(t raquiIemenIs specified In Table 4.3-2.
4.3.2.2 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS tuncIIon shall be verified to be Withln the limit at Iaast once per 18 months. Each veriI'IcaIIon I
shallnctu:le at least one lrairI such that boIh IJalns 81& verified at least once per 36 months and one channel per function such that aI channels are VIIriIIed at least cnce per N limes 18 months where N Is the total number of redundant channets In II specific ESFAS function as shown in the "Total No. of CItanneIs" Column of Table 3.3-3.
SUMMER - UNIT 1 3143-15 Amendment No. ~
78, 1Q'T 12Qj 146
I TABLE 3.3-3 ENGINEERED SAFETV FEATURE ACTUATION SYSTEM INSTRUHENTATION i
MINIMUM
~
TOTAL NO.
CHANNELS CHANNElS APPLICABLE
'1 FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
- 1.
SAFETY INJECTJON,REACTOlI TRIP, fEE~TER ISOLATIONf CONTROL ROOM ISOLATION, S ART DIESEL GENERATORS, COHTAINNENT COOLING FANS AHII ESSENTIAL SERVICE WATER.
a, Manull Initiation 2
1 2
1, 2, 3, 4 18 b
- Automatic Actuation 2
1 2
I, 2, 3, 4 14 LOfie.nd Actuation
~
'I' He ays t::
- c.
Reactor Building 3
2
- 2 I, 2, 3 24'"
Pressure
- Hlah-l
- d.
Pressurizer 3
2 2
1, 2, 3.
24111 Pressure
- Low
- 8.
Differential 3/.talJl lln.
2/stell line
- 21,team line I, 2, 3 24111 Pres lure Between twI CI and l/S Ste ** lines
- High
.teM H""
,I
~ t if 0...
e e
II>
. TABl~.3.~-3 (Continu~d)
I ENGINEERED SAFETY FEATURE ACTUATION SYST~M INSTR~ENTATION "j
MINIMUH c:
z TOTAL NO.
CHANNELS CflANNELS APPt.ICABlE
~ fUNCTIONAL UNIT Of CHANNELS TO TRIP OPEIWILE tmoES
~N
- f.
Ste~ Lin. Prelsur.-Low 1 prelSurel 1 pre55ure 1 pre&5ure I, :2, t' 24" loop and 2 loops and 2 loops
- 2.
REACTOR BUILDING SPRAY
- 8.
Manual Z sets - 2 1 5et 2 sets 1,:2,3,4 18 switches/set
- b.
Automatic Actuation 2
1 2
I, :.2, 3, 4 14
~.
logic and Actuation w
Relays c.
Reactor Building 4
2 3
- 1. 2. 3 16 Pr'lsure--Hlgh-3 (Phas. 'A' Iioletion aligns spr~
Iyst.. dl,c rge vllvee and NIOII tank suction VII".. )
I
~.
'm
'" i..
- z 0
0
,_,~-",~~."'~-~.'_-..... L.,-;.d TABLE 3.3-3 (Continued) j EHGIHEERED SAfETY fEATURE ACTUATION SYSTEM INSTRUMENTATION c::
z
!:I...
~
w
- t;;
(
'1
- 0...
FUNCTIONAL UNIT
- 3.
CONTAINMENT ISOLATION
- a.
Phlse "AD Isolation I)
Mlinual
- 2)
Safety InJection'
- 3)
Autollltic Adultion Logic and Actuation He lays
- b.
Phase Da* Isol.tlon
- 1)
Auto.Itlc Actuation Logic ud Actuation R. 1 1)'$
- 2)
RelCtor Building
'reS$ure--Hillh-3
- c.
Purge and EldIlU5t holatloll
- 1)
Safety Injection
- 2)
Contalnleftt Radio-activity-High
- 3)
Autolltlc Actuation Logic Ind Actuation RellYs
- z TOTAL HO.
OF ClWlKELS CHAHNELS TO TRIP HINIMUM CllAMlCELS OPERABLE APPLICABLE HODES j'.,
'1 ACTlOil 2.
1 2
I, 2 3,"
18 See 1 aboYe for all safety injection Initllting functions and requfrelents.
~ I z
4 I
I 2
2 1,2.3.4 14 2
I, 2, 3, 4 14 3
I, 2, 3 16 See 1 above for III sat.~ 'nl.et,on Initiating,unctions and requlreaent **
2*
l' Z
1~ 2, 3.1 4, 17 2
1 2
I I, 2, 3, 4 17
~
- Purge e~hlu5t monitor not required when purge exhaust Ii closed.
w
en C s:: s::
m D
c: z
=i -
~
It' -
<0
~
CD
=> f
=> -
~
~
~
Ul
.. ""'..,........ ~
e e
e TABLE 3.3-3 (Continued)
ENGINEERED SAFEIY FEATURE ACTUATION SYSTEM INSTRUMENTATION
'j
- ~
TOTAL NO.
MINIMUM i-OF CHANNELS CHANNELS AP~LlCABLE F!1NQIIQt:l~1. !.!~II CHAtlliEJ.S rolRlfl OEERABLE
_MODES ACTION
- 4. STEAM LINE ISOLATION
- a. Manual I.
Ono Switchlllno l/stoam line l/stoam line l/operatlng 1,2,3",j 23 steam line ii.
One Switchlallllnes 1
1 1
1,2,310 23
- b. Automatic Actuation Logic 2
1 2
'1. 2, 3~"
21 and Actuallon Relays
- c. Reactor Building Pressure--
3 2
2 l,2,3jj, 24' Hlgh-2
- d. Steam Flow In Two Steam 21steam line 1/steam line l/steam Hne
\\2,3IU 24' Lines-High any 2 steam lines
- 1 COINCIDENT WITH T ovg--Low-Low 1 T.dloop 1 T.vg any 1 T.,g any l,2,3'u 24' 2 loops 2 loops
CfJ c s::
s::
m JJ C
Z
-I
~
w -
.j>.
w,
I\\J 0
>> g
- J a.
3 11>
- a.
z 9
~
TABLE 3.3-3 (Con!lnued\\
ENGINEERED_SAFETY FEATURE ACTUATION SYSTEM INsmUMENTATION TOTAL NO.
MINIMUM OF CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT CHANNELS TO TRIP OPERABLE MODES ACTION
- e. Steam Une Pressure-Low 1 pressurel 1 pressure 1 pressure 1, 2, 3<1#**111 24" loop any 2 loops any 2 loops
- 5. TURBINE TRIP & FEEDWATER ISOLATION
- a. Steam Generator Water Level--
3/loop 21loop in any 21loop in 1,2 24" High-High operating each oper-loop atlng loop
- b. Automatic Actuation Logic and 2
1 2
1,2 25 I
Actuation Relay
e e
e VI TABLE 3.3-3 (Continued) j
~NGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM
'j c::
TOTAL NO.
CHANNELS CHANNELS APPLICABLE z....
FUNCTIONAL UNIT OF. CHANNELS TO TRIP OPERABLE MODES ACTION
-i 6.
EMERGENCY FEEDWATER r
- a.
Manual Initiation 1 per pump 1 per pump 1 per pump 1, 2, 3' 22
- b.
Auto~atic Actuation Logic and Actuation Relays 2
1 2
I, 2, 3 21
- c.
Stili. Gen. Water level-low-low
- i. Start Motor-w Driven Pumps 3/stm. gen.
U.tIn. gen.
Vstla. gen.
I, 2, 3 24*
any stD! gen.
ii. Start Turbi ne-I N
Driven PUIIIP 3/stm. gen.
2/stm. gen.
21stm. gen I, 2, 3 24-any 2 su.. gen.
- d. Undervoltage-both ESF Busses Sta rt Turbi ne-Driven Pump 2-l/bus 2
2 1, 2. 3,
19
- e.
S. I.
Start Motor-f Dri ven Pumps See 1 above (all S.I. initiating functions and reqbirements)
- J
- f. Undervoltage-one ESF bus i
Start Motor-Driven
§ PlIIIIPs.
2-lIbus 1
2 I, 2 22 z
- g. Trip of Main 0.
Feedwater Pumps
~
start Motor" Driven Pumps 3-l/PUllJl 3-lIpullip 3-1/pull1j)
I, 2 19
- h.
Suction Transfer on C>
Low Pressure 4
2 3
I, 2,. 3 16
en c TABI-E3.3-:3 _(Conti"-u~l s::
m
!iNgl~!i!;BED SAFliTY FE~I!JR5 ACT!,!ATlON SYSTEM INSTRUMENT6TlQN JJ c z
'j
=i
~
TOTAL NO.
MINIMUM OF CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT CHANNELS JOTRIP OEEAABLE
~ObES ACTION
- 7. LOSS OF POWER
- a. 7.2 kv Emergency Bus Undervoltage (loss of Voltage) 2*1/bus 1
2 1,2,3,4 18
~
- b. 7.2 kv Emergency Bus Undervoltage (Degraded Voltage) 2-1/bus 1
2 1,2,3,4 18
(,)
N
- 8. AUTOMATIC SWITCHOVER I\\l TO CONTAINMENT SUMP
- a. AWST level low-low 4
2 3
1.2.3 16 b.. Automatic Actuation logic and Actuation Relays 2
1 2
1,2,3 21
- 9. ENGINEERED SAFETY FEATURE ACTUATION SYSTEM
§'
INTERLOCKS
- a. Pressurizer Pressure, P-ll 3
2 2
1,2.3 20 111
- J C.
- b. Low-Low Ta"", P-12 3
2 2
1, 2, 3'"
20 I
3 111 a
- c. Reactor Trip. P-4 2
2 2
1.2,3 22 z
p ;
e:"
- TSR 1029 REVISION 0 Page 3/4 3-224 TECHNICAL SPEOFICAnON INFORMAnONIRELOCA nON FORM Tbls information Is provided as -REFERENCE om r and IS NOT pan of the formal. NRC approved Technical Specificatlqns.
,.=-.: :::.-..,-~ *,.,
I.
The Technical Specification was deleted by Amendment No. -.:.lN~/A;;>.... ___
TIS Number:
Title:
Reference Document to which requirements were relocated:
Document 10:
!.!Ni.:.'A~ __________________ _
TrtJe:
S~on: __________________________________________ __
fl.
A Regulatory Interpretation or other reference document provides amplifying information relative to this Technical Specification.
TIS Number:
3/4.3.2 ESFAS Instrumentation
REFERENCES:
TSR 1028 - inserted between pages 3'4 3-8 and 3/43-9 Approval:
Manager, Nudear Licensing & Operating Experience Issue Oate: __ 03='....
17:,.:'.:;9;::.5_
TSR 1029 REVISION 0 Page 3/4 3-22b Oocum ent Affected:
INTERPRETATION:
V. C. SUMMER NUCLEAR STATION REGULATORY INTERPRETATION Technical Specification 3/4.3.2 - Engineered Safety The following interpretatiqn refers to 15 Table 3.3-3. action statement 14.
This interpretation Is Identical to that ofTSR 1028 (inserted beiween 15 Dages 314 3-8 and 3143-9) related to SSPS surveillance testing on both the Reactor Trip Breaker lind the Automatic Actuation logic and Actuation Relll\\'5.
BASIS: None
REFERENCES:
..:N'-"o..,n...,e _____________________ _
Recommended Approval:
~~
I Supesor, u ear censlng & Operating EXperience Approval:
~~~
Gei'kra anager;tKeir plant Operations Issue Oate:_-'0""3:.:.1....
17""'.::;9""5 __
I~
TABLE 3.3-3 (Continued)
TABLE NOTATION Trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock) setpoint.
11#
Trip function may be blocked in this MODE below the P-12 (Low-Low T avg Interlock) setpoint.
Except when below P-12 with all MSIVs and bypasses closed and disabled.
The provisions of Specification 3.0.4 are not applicable.
ACTION STATEMENTS ACTION 14 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE reqUirement, restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.
ACTION 15 -
DELETED ACTION 16 -
With the number of OPERABLE channels one less than the Total Number of
'pha~s, operation may continue provided the inoperable channel is placed in r
~ypass 31Jd the Minimum Channels OPERABLE requirement is met. Restore theinoperable channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> otherwise; Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
One additional channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing per Specification 4.3.2.1.
ACTION 17 -
Wrth less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge supply and exhaust valves are maintained closed.
ACTION 18 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ACTION 19 -
With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
- a.
The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- b.
The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of other channels per Specification 4.3.2.1.
SUMMER - UNIT 1 3/43-23 Amendment No.1Q1, 1ae, 197, 177 I
I
TABLE 3.3-3 (Continued)
ACTION STATEMENTS (Continued)
ACTION 20 -
Wrth less than the Minimum Number of Channels OPERABLE, within one hour determine by observation of the associated permissive annunciator window(s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.
ACTION 21 -
Wrth the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status I within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.
ACTION 22 -
With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 23 -
Wrth the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5.
ACTION 24 -
Wrth the number of OPERABLE channels one less than the Total Number of
.-:" Channels, STARTUP and/or POVVER OPERATION may proceed provided the following conditions are satisfied:
- a.
The inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
I
- b.
The Minimum Channels OPERABLE requirement is met; however, the I
inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels per Specification 4.3.2.1.
ACTION 25 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable Channel to OPERABLE status I
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per SpeCification 4.3.2.1, provided the other channel is OPERABLE.
SUMMER - UNIT 1 3/43-24 Amendment No. Hl1, Hi7, 177
2009 V.C. Summer RO NRC Exam - As Given
- 26. Given the following plant conditions:
100% power The NROATC notes the following conditions exist on RCP 'A':
- 1 Seal Leakoff flow drops to 0.6 gpm.
RCP A STNDPIP LVL HIILO (XCP-617, 2-4) has NOT actuated.
The Lower Seal Water Bearing Temperature is 205'F and increasing at 3'F/minute.
The Seal Water Outlet Temperature is 200'F and increasing at 2'F/minute.
Which ONE (1) of the following identifies the malfunction that has occurred AND the required action?
A. The #1 Seal is NOT operating properly; Trip the reactor and stop RCP 'A'.
B. The #1 Seal is NOT operating properly; Reduce power to less than P-8 using GOP-4C, Rapid Downpower, stop RCP 'A',
and perform a controlled shutdown of the plant.
C. The #2 Seal is NOT operating properly; Trip the reactor and stop RCP 'A'.
D. The #2 Seal is NOT operating properly; Reduce power to less than P-8 using GOP-4C, Rapid Downpower, stop RCP 'A',
and perform a controlled shutdown of the plant.
Thursday. July 09.20098:08:35 AM 26
2009 V.C. Summer RO NRC Exam - As Given
- 27. Given the following plant conditions:
60% power An electrical fault occurs in the non safety-related circuit of the Turbine 1 st Stage Pressure PT -446.
Which ONE (1) of the following identifies a set of signals that are potentially affected by this fault?
REFERENCE PROVIDED A. High Steamline Flow coincident with Lo-Lo Tavg actuation; AND P-13 actuation.
B. High Steamline Flow coincident with Lo-Lo Tavg actuation; AND Steam Dump actuation.
C. AM SAC actuation; AND P-13 actuation.
D. AMSAC actuation; AND Steam Dump actuation.
Thursday, July 09, 2009 8:08:35 AM 27
FIRST STAGE TURBINE PRESSURE
,_----------__________________________ A _____________________________________,
PROTECTION S~REF. T Pg. 7
~~~: S::;T~
~~G;~ SpT:;T~
~
SET III SH.8 SET IV SH. g REF_ T Pg_ 7 PRQTlCTION SET IV PT 447 c0}
s/ 4-~0ppm/~1 W/L!M W/L!M 446 446
!"!:I%I R ~_
.. 4468,--.. ;~.474A TO rPPil_
~
mo
([SOL~P~~-:-
- ~A !
IRJ I FB.475t:!;81447BR !
f 446 I
<!SQLJ 1
I R
I 4468 R W/UM R:
R
~P/:
% ~
~
I ~p/
J 1-__
L.:!:...l..::..@1
__ I I
I 446C RL
\\oJ/LIM TO TO
~ __,_
PY J
447C R --
I
~: 448C i--~FB-484A FB.485A~1 447E lc::::::J I
I
~I
~
Rr~
I
~~Y/ __ -'
PP/
- E L.--~Y/_~
I I
4468 446E R R
I 4478 I
I I
I 1"% t +.1
\\,oJ/LIM I
R I
I I
I I
f+T::7l I
I I
I I
I I
~@' "
I I CLOSE ON L
___.... TO TO......
py J
CLOSE ON
]REACTOR TRIP I
FB-494A FB-'i95A-i 4470 REACTOR TR[P 1 J
,tREACTOR TRIP tffiJ
~ R (REACTOR TRIPI J
I Sv/ITCHGEAR PP/
PP/
SHlTCHGEAR t TRAiN A) 4460 R 4470 TRAr~l 8)
I I
R I
L--~----rT'-1 r~-r~----L __ ~
l r-l-]-]-*]----*-*-*-*-*--- ------->_._-- _._._.-:-!- !-!---:
I I
I I
I I
I J
I J
I J i::: U"Po/l.~REF_ S REF. 5.... f"PD/l~! ! i!.
J I
I
~~R P03<18A P03g9A ~! !
!! ~~@.-.--.-.-: :(;:;)-_.-@:-~.~,
~":. ;;:::"8 0,,:: '" I,,: ::~I" 'e';:~,~:,;; ;- --
J I
R I
I 1
AMSAC.... _._.J I
I
,.-----.~ ANSAe IL...... ROO SPEED CONiROL I
PY-445 SH.21
[
1
[
1 I
~- -.-.-.-.-.-.--.,
~
i*:*':.N':.R.':.L-*--*~@R
~
i
/
~~R 4460 i
~~
Ve-/~'!
i
/
,.~
I L._._. ___. _______.i I
L __________________, f------------------J II PERMISSIVE P-13 REF. A SH.13 SSPS FIGURE IC9.27 II IIC9*O I
2009 V.C. Summer RO NRC Exam - As Given
- 28. Given the following sequence of events:
100% power The following annunciators actuate:
VCT LVL HIILO VCT LCV-115A TO HU-TK LVL HI LI-112A, VCT LEVEL %, reads 0%
LI-115, VCT LEVEL %, reads 100%
PZR level starts to decrease.
The NROATC notes the following conditions:
Charging flow decreases to 0 gpm.
Charging Pump amps are at minimum and fluctuating.
Charging Pump discharge pressure is 15 psig and fluctuating.
The ABAO reports charging pump suction pressure at 15 psig.
Which ONE (1) of the following describes what happened to the Charging Pump (Charging Pump lineup)?
A. Gas binding of the pump has occurred.
B. LCV-115A did not divert flow to the RHT.
C. The suction to the pump has swapped to the RWST.
D. One phase of electrical power to the pump motor was lost due to overheating.
Thursday. July 09. 2009 8:08:35 AM 28
2009 V.C. Summer RO NRC Exam - As Given
- 29. On an Safety Injection, which ONE (1) of the following describes the response of the status lights on XCP-61 03, SAFETY INJECTION, and XCP-61 04, SAFETY INJECTION PHASE A ISOL, for the Train 'B' RBCUs when the ESFLS sequence is complete?
(XCP-61 03)
(XCP-6104)
SW TO RB IN B ISOl RBOUTB ISOl 3106B ClSD 3111B ClSD A.
DIM DIM B.
DIM BRIGHT C.
BRIGHT DIM D.
BRIGHT BRIGHT Thursday. July 09. 20098:08:35 AM 29
2009 V.C. Summer RO NRC Exam - As Given
- 30. Which ONE (1) of the following identifies the actions, per AOP-1 06.1, Emergency Boration, that must be taken to align the Charging Pump suction to the next PREFERRED boration source if the Boric Acid Filter will not pass flow?
A. Open BOTH Boric Acid Tank to Charging Pump Suction Header Isolation Valves (XVD-8329 and XVD-8331);
Isolate Makeup Water to the Blender B. Open BOTH Boric Acid Tank to Charging Pump Suction Header Isolation Valves (XVD-8329 and XVD-8331);
Isolate the VCT C. Open BOTH RWST to Charging Pump Suction Valves (LCV-11SB and LCV-11SD);
Isolate Makeup Water to the Blender D. Open BOTH RWST to Charging Pump Suction Valves (LCV-11SB and LCV-11SD);
Isolate the VCT Thursday. July 09, 2009 8:08:35 AM 30
2009 V.C. Summer RO NRC Exam - As Given
- 31. Which ONE (1) of the following places the plant in the action statement with the SHORTEST time in accordance with its associated Technical Specification?
A. The unit is in Mode 1 at 100% power. RHR Pump 'A' breaker trips during a surveillance test.
S. The unit is in Mode 4 with RCP 'A' and both RHR loops in operation. RHR Pump 'A' breaker trips.
C. The unit is in Mode 5 with the RCS loops filled. S/G Narrow Range levels are:
'A' - 27%; 'S' - 14%; 'C' - 26%. RHR Pump 'A' breaker trips. RHR Pump'S' is started.
D. The unit is in Mode 6 with water level maintained at 4 feet above the reactor vessel flange. RHR Pump 'A' breaker trips. RHR Pump'S' is started.
Thursday, July 09, 2009 8:08:35 AM 31
2009 V.C. Summer RO NRC Exam - As Given
- 32. Given the following plant conditions; 75% power A TOTAL loss of Component Cooling Water occurs.
Local temperature monitoring is in progress on Charging Pump 'A' with all temperatures within allowable limits.
In accordance with AOP-118.1, Total Loss of Component Cooling Water, which ONE (1) of the following describes the preferred action that must be taken in regard to subsequent operation of Charging Pump 'A'?
A. Trip Charging Pump 'A' if CCW is not restored within 10 minutes.
B. Trip Charging Pump 'A' if CCW is not restored within 20 minutes.
C. Establish altemate cooling using the Demin Water System.
D. Establish alternate cooling using the Chilled Water System.
Thursday. July 09, 2009 8:08:35 AM 32
2009 V.C. Summer RO NRC Exam - As Given
- 33. Given the following plant conditions:
100% power PZR pressure control is in AUTO at 2235 psig.
Group 1 Backup Heaters are ON.
Group 2 Backup Heaters are OFF.
PT -444, PZR Pressure Transmitter, starts to slowly drift HIGH.
The operator places the Master Pressure Controller in MANUAL when PT -444 reads 2275 psig, but does NOT adjust the output of the controller.
Which ONE (1) of the choices below completes the following statement?
When placed in MANUAL, the output on the Master Pressure Controller is than its original output, AND the PZR Spray Valves will be approximately open.
A. HIGHER; 80%
B. HIGHER; 30%
C. the SAME as; 80%
D. the SAME as; 30%
~~~------------------------------------------------------~
Thursday. July 09. 2009 8:08:35 AM 33
2009 V.C. Summer RO NRC Exam - As Given
- 34. Given the following plant conditions:
o Annunciator RB SPR NAOH STOR TK LVL HI/LO (XCP-608, 1-1) alarms on the MCB.
o LI-7356, NAOH TK LEVEL %, indicates 97%.
o The ABAO reports that the NaOH gauge glass reads approximately 450' 11 ".
Which ONE (1) of the following identifies the TOTAL volume in the tank per Curve Book Figure VI-27 AND the status of the Spray Additive System per Technical Specification 3.6.2.2 Spray Additive System?
REFERENCE PROVIDED A. 3085 gallons; OPERABLE.
B. 3085 gallons; INOPERABLE.
C. 3165 gallons; OPERABLE.
D. 3165 gallons; INOPERABLE.
Thursday. July 09, 20098:08:35 AM 34
105 Sodium Hydroxide Spray Addition Tank XTK0060 e
100 1"'1'
- l1**!~*~-*~* i**~****** J
~ ~"~i' '-m"
. ~~~
1 ~.~;~~~~~~=:~~~~~~~=c;:~.
95 901 3 ::
85*-
~=f;:-
80 75 70~
t-65 60 RI
~
.=.c...
55 'I-:~C-
.. 50 =t1~
45 40 36'=1=:
3O/=i1:
25 20 ~
151'::,.".
-p:
- F
':1*"*.
o *".::FEE o
500 F=
t::"
+/-=:
1000 1=',.,
-r n4 J'I.0
)',9" E:I ll',. I I I H2', 7" 1500 2000 2500 3600 3500 Gallons Percent Gallon!
o 6
Agure:
V/-27 5
159.04 10 318.09 RevisIon Date: 21-FetH)1 15 477,13 20 636.17 25 795,22 Prepared By: Steven A Scott !;~.q
/Y\\o, 30 954.28 35 1,113.30
~"./._t~
40 1,272.35 45 1.431.39 50 1,590.44 55 1.749.46 60 1.900.52 65 2,067.67 70 2.228,61 75 2,365.66 90 2,544.70 85 2.703.7<4 90 2,862.78 95 3,021.83 tOo 3,180,87 XTKOG60 This figure only Ille/nuu yoltlme lI~ove the (lump suction ccnterllne, Technlc.1 Spec/rtclI.lloulncludes the 10iAI volume of Ihe tank, (Volumc below pump luctloll conter/hlo 11 79.61 so.l1onl),
SIGIIT GLASS READINGS FOR TOTAL VOLUME OF TANK (Including Volume below Pump Suction) 451' 10"
= 3242.83 GAL 451' 8"
= 3230.00 GAL 451 '
= 317).98 OAL 450' 7 *3116" = 3140.00 OAL 450' 3"
= 3112.02 GAL NOTE: linch = 6.885 OAL 1-------1 OUTLIlT
/
~ 12',4-Tech Spec Rei:
3.6.2.2.a & 4.6.2.2,b.1 Procedurs RBI:
STp*112.Q{)9 FllJIlre Rei:
DC09820*018 & OC0962()'004
2009 V.C. Summer RO NRC Exam - As Given
- 35. Which ONE (1) of the following is the LOWEST Intermediate Range Startup Rate that will generate an ORANGE Path transition TO EOP-13.0, Response to Abnormal Nuclear Power Generation.
No CSF Red Path conditions exist.
A. + 0.2 DPM B.
0.0 DPM C. - 0.2 DPM D. - 0.33 DPM Thursday, July 09. 2009 8:08:35 AM 35
2009 V.C. Summer RO NRC Exam - As Given
- 36. Given the following plant conditions:
Mode 5 Reactor Building Integrity is established.
A Reactor Building Purge (36") is in progress with BOTH trains of RB Purge in service.
ONE (1) RB Purge exhaust fan trips.
Annunciator CONTAIN. DP HI (XCP-6210-LCB2, 4-9) actuates.
RB pressure is 1.1 psig.
The 36" Purge has been secured and the crew is monitoring for leakage.
Which ONE (1) of the following describes the impact these conditions have on Reactor Building pressure limits, and the NEXT action required to restore RB pressure to the normal band?
A. RB pressure is above the upper limit for normal operations.
Shift the cooling water supply to the RBCUs to Service Water per SOP-117.
B. RB pressure is above the upper limit for normal operations.
Start the alternate purge exhaust fan per SOP-114.
C. RB pressure is below the lower limit for for normal operations.
Start the alternate purge exhaust fan per SOP-114.
D. RB pressure is below the lower limit for for normal operations.
Shift the cooling water supply to the RBCUs to Service Water per SOP-117.
Thursday. July 09,20098:08:35 AM 36
2009 V.C. Summer RO NRC Exam - As Given
- 37. Given the following plant conditions:
7% power Power is being raised slowly in preparation for rolling the Main Turbine.
Intermediate Range Detector N-35 has failed LOW.
Which ONE (1) of the following is the required action and the MAXIMUM allowed power level increase in accordance with Technical Specification 3.3.1 Reactor Trip Instrumentation?
A. Place the N-35 LEVEL TRIP Switch in BYPASS.
Maintain power less than 10% until the channel is retumed to service.
B. Place the N-35 LEVEL TRIP Switch in BYPASS.
Maintain power less than 15% while the channel is repaired.
C. Direct I&C to trip the N-35 associated bistables.
Maintain power less than 10% until the channel is returned to service.
D. Direct I&C to trip the N-35 associated bistables.
Maintain power less than 15% while the channel is repaired.
Thursday, July 09, 2009 8:08:35 AM 37
2009 V.C. Summer RO NRC Exam - As Given
- 38. Given the following plant conditions:
100% power All Steam Generators are at programmed level.
Steam Generator '8' level is being controlled manually.
Subsequently, a Stator Cooling Turbine Runback occurs for 20 seconds and then stops.
Assuming NO operator action, which ONE (1) of the following describes the response of Steam Generator '8' level?
A. Initially decreases; SG High-High water level will occur.
- 8. Initially decreases; SG Low-Low water level will occur.
C. Initially increases; SG High-High water level will occur.
D. Initially increases; SG Low-Low water level will occur.
Thursday, July 09, 2009 8:08:35 AM 38
2009 V.C. Summer RO NRC Exam - As Given
- 39. Given the following plant conditions:
o The crew is responding to a tube rupture on SG 'B' lAW EOP-4.0, steam Generator Tube Rupture.
oRCS pressure is 1365 psig.
oRCS temperature is 552°F (Core Exit Thermocouples) o Steam pressures are as follows:
o 1005 psig on SG 'A' o 1085 psig on SG 'B' o 1045 psig on SG 'C'.
Which ONE (1) of the following values of core exit thenmocouples is the target temperature for RCS cooldown, with an allowance of 50°F for subcooling?
STEAM TABLES PROVIDED A. 49rF B. 501°F C. 506°F D. 535°F Thursday. July 09, 2009 8:08:35 AM 39
2009 V.C. Summer RO NRC Exam - As Given
- 40. Given the following plant conditions:
100% power Charging Pump 'A' is removed from service with its breaker racked down.
Charging Pump 'B' is in standby.
Charging Pump 'C' breaker is racked up onto Bus 1 DA and running.
ALL Offsite Power (BOP & ESF) is lost.
Both DG 'A' and 'B' start and restore power to their respective bus.
ESFLS status lights on the MCB are as follows:
TRAIN A:
TRN BLACKOUT SEQ INIT -lit STEP 1 through 5 START -lit STEP 6 through 8 START - off TRAIN B:
TRN BLACKOUT SEQ INIT -lit STEP 1 through 8 START - off TRN BLACKOUT SEQ COMPLETE - lit Which ONE (1) of the following describes which Charging Pump(s), if any, will be running?
A. NO Charging Pumps B. ONLY Charging Pump 'B' C. ONLY Charging Pump 'C' D. BOTH Charging Pumps 'B' & 'c' Thursday. July 09,20098:08:35 AM 40
2009 V.C. Summer RO NRC Exam - As Given
- 41. Given the following plant conditions:
2% power Nuclear Instrument Channel N44 is in TEST.
Power is lost to APN-5903 when the associated inverter normal AC input breaker opens and the inverter fails to swap to altemate power.
Which ONE (1) of the choices below completes the following statements?
The operator will use _______ to initially respond to the plant conditions.
Concurrently, will direct Electrical Maintenance to investigate and repair the breaker malfunction AND provide direction to restore power to the APN.
A. an Emergency Operating Procedure; an Annunciator Response Procedure B. an Emergency Operating Procedure; a System Operating Procedure C. an Abnormal Operating Procedure; an Annunciator Response Procedure D. an Abnormal Operating Procedure; a System Operating Procedure Thursday, July 09, 2009 8:08:35 AM 41
2009 V.C. Summer RO NRC Exam - As Given
- 42. Given the following plant conditions; 10-3% power The Train 'B' Class IE 125 VDC battery breaker is open for urgent battery maintenance.
Which ONE (1) of the choices below completes the following statement?
If the normal supply breaker to Bus 1 DB subsequently trips open, the Reactor __ _
automatically trip and DIG 'B' automatically start.
A. will will B. will will NOT C. will NOT will D. will NOT will NOT Thursday, July 09, 2009 8:08:35 AM 42
2009 V.C. Summer RO NRC Exam - As Given
- 43. Given the following plant conditions:
Mode 1 A LOCA occurs.
RM-G7, RB High Range Monitor, is in alarm and the alarm is determined to be valid.
RM-G17A & B, MANIP CRN, high radiation alarms have actuated.
Which ONE (1) of the following describes why the Annunciator Response Procedure for RM-G7 directs the operator refer to EOP-17.2, Response to High Reactor Building Radiation Levels?
EOP-17.2 will REQUIRE the operating crew to ___ _
A. Ensure Containment Ventilation Isolation; AND Verify that the RB Spray system is in service.
B. Ensure Containment Ventilation Isolation; AND Place both RBCU HEPA Filter trains in service.
C. Place both RB Charcoal Cleanup Units in service; AND Verify that the RB Spray system is in service.
D. Place both RB Charcoal Cleanup Units in service; AND Place both RBCU HEPA Filter trains in service.
Thursday, July 09, 2009 8:08:35 AM 43
2009 V.C. Summer RO NRC Exam - As Given
- 44. Given the following plant conditions:
At 0900, the Reactor tripped when a loss of ALL off-site power (ESF & BOP) occurred.
The crew has entered EOP-15.0, Response to Loss of Secondary Heat Sink.
Condenser pressure is 5.1" Hg absolute.
During the event, WIDE RANGE Steam Generator levels were noted as follows:
Which ONE (1) of the following describes the response of RCS temperature and pressure from 0905 to 0920?
A. RCS temperature is maintained by condenser steam dumps.
RCS pressure stabilizes below the PZR PORV setpoint.
B. RCS temperature is maintained by SG power reliefs.
RCS pressure stabilizes below the PZR PORV setpoint.
C. RCS temperature rises steadily as SG level lowers.
RCS pressure rises to the PZR spray 100% full open setpoint.
D. RCS temperature rises steadily as SG level lowers.
RCS pressure rises to the PZR PORV setpoint and cycles around this value.
Thursday. July 09, 2009 8:08:35 AM 44
2009 V.C. Summer RO NRC Exam - As Given
- 45. Given the following plant conditions:
100% power The following annunciators actuate simultaneously:
EMERG AUXXFMR XTF-31 TRBL (XCP-633,1-4)
XFMR XTF31 LCKOUT 86T31 (XCP-639, 4-2)
Which ONE (1) of the following identifies the condition than can cause the simultaneous actuation of these alarms, and describes the expected status of Bus 1 DB ONE (1) minute later?
A. SUDDEN PRESSURE at 5.5 psi/sec; Bus 1 DB deenergized B. SUDDEN PRESSURE at 5.5 psi/sec; Bus 1 DB powered from EDG 'B' C. WINDING OVERLOAD at 110°C; Bus 1 DB deenergized D. WINDING OVERLOAD at 110°C; Bus 1 DB powered from EDG 'B' Thursday, July 09, 2009 8:08:35 AM 45
2009 V.C. Summer RO NRC Exam - As Given
- 46. Which ONE (1) of the following describes the MINIMUM AC power sources required by GOP-9, Mid-Loop Operation, for mid-loop operations?
A. TWO independent sources of off-site power to the ESF buses.
B. ONE source of off-site power to the ESF buses and ONE Emergency Diesel Generator operable.
C. ONE source of off-site power to the ESF buses and BOTH Emergency Diesel Generators operable.
D. TWO independent sources of off-site power to the ESF buses and ONE Emergency Diesel Generator 0 erable.
Thursday. July 09.20098:08:35 AM 46
2009 V.C. Summer RO NRC Exam - As Given
- 47. Given the following plant conditions:
100% power Normal full power alignment Which ONE (1) of the following Bus 1DA conditions will cause the Emergency Safeguards Loading Sequencer (ESFLS) to actuate in the BLACKOUT mode?
With respect to bus 1DA:
A. A lightning strike causes a reduction in voltage to 5600V for 3 (THREE) seconds.
B. A transformer windings problem causes a voltage reduction to 6680V for 10 (TEN) seconds.
C. A degraded voltage sensor fails to ZERO while another degraded voltage sensor is being tested.
D. A CCW Pump 'A' motor failure causes voltage on two phases to drop to 6500V for 5 seconds before the pump breaker trips.
Thursday, July 09,20098:08:35 AM 47
2009 V.C. Summer RO NRC Exam - As Given
- 48. Given the following plant conditions:
100% power A pipe rupture in the Instrument Air System results in a sustained loss of system pressure.
The operating crew implements the appropriate procedures.
Remote control of the EFW Flow Control Valves has been lost.
Which ONE (1) of the following describes what is required, in accordance with AOP-220.1, Loss of Instrument Air, to prevent exceeding MDEFP operating limitations?
A. Expand the SG Narrow Range level control range.
Altemate starting the two MD EFW Pumps.
B. Expand the SG Narrow Range level control range.
Isolate blowdown and sampling from the Steam Generators.
C. Alternate steaming one Steam Generator at a time to control RCS temperature.
Alternate starting the two MD EFW Pumps.
D. Altemate steaming one Steam Generator at a time to control RCS temperature.
Isolate blowdown and sampling from the Steam Generators.
Thursday. July 09,20098:08:35 AM 48
2009 V.C. Summer RO NRC Exam - As Given
- 49. Given the following plant conditions:
o Following a Control Room Evacuation, the plant is being controlled in accordance with GOP-8, Plant Shutdown from Hot Standby to Cold Shutdown with the Control Room Inaccessible Mode 3 to Mode 5.
o The CRS directs the RO to perform calculations for Mode 5, Short Term Cold Shutdown conditions (bubble in the PZR) to raise boron concentration I2Y. 300 ppm.
o Present RCS boron concentration is 100 ppm.
o MVT-8104, Emergency BA Flow Control Valve, has been opened.
o Boric Acid Transfer Pump 'B' has been started.
Which ONE (1) of the following describes the CREP indication that will be used to monitor the amount of boron injected into the Reactor Coolant System AND the MINIMUM specific criteria which will be used to terminate the boration in accordance with GOP-8?
REFERENCES PROVIDED A. FI-122B, CHARGING FLOW GPM; 30 gpm for 127 minutes.
B. FI-122B, CHARGING FLOW GPM; 85 gpm for 34 minutes.
C. FI-110A, EMERGENCY BA FLOW GPM; 30 gpm for 127 minutes.
D. FI-110A, EMERGENCY BA FLOW GPM; 85 gpm for 34 minutes.
Thursday. July 09.20098:08:35 AM 49
FIGUREID*6 Revision Date: 11-11-9¥ Prepared By: ;a fkiii.
Verified By: ~
11'. ~.L..l Approved By:: ({iff ~
BORON CHANGE CORRECTION FACTORS Plant Conditions Correction Coolant Pressure Coolant Temperature Pressnrizer Level Factor N01E:
(psig)
(oF) 2,235 587.4 Normal Operating 2,235 557 No-Load 1,600 500 No-Load 1,200 450 No-Load 800 400 No-Load 400 350 No-Load 400 300 No-Load 400 250 No-Load 400 200 No-Load 400 300 Solid Water 400 250 Solid Water 400 200 Solid Water 400 150 Solid Water 400 100 Solid Water Correction Factors are applied as follows:
Boron Addition and Dilution Total Volume Figures V<_ = K x V<"-)
Coolant Boration and Dilution Rate Figures (de)
(~)fir
dt con=ted K
Tech. Spec. Ref.: N/A Procedure Ref.: N/A 0.)
1 1
1.06.
1.11 1.15 1.19 1.23 1.26 1.28 1.37 1.4 1.43 l.4S 1.47 Figure Ref: DC00040-068
Revision Dale: 11-JI- 'N Prepared By;,;(,f c,.'G.
Verified By: A'~~
ApprovedBy;;i(f ~
FIGURE m-l. RCS BORATION I
GALLONS (V,,) OF BORIC ACID REQUIRED VB =.JLIn (7000-Ci) _ 49640 In (7000-Ci) 8.33 7000-C, 7000-C, M = RCS Mass (413,500 Ibm)
C, = Initial ppm C, = Final ppm 7!j4 1,000 83 166 249 332 415 499 583 666 750 834 282
'2%1 383 673 867 964 293 391 489 587 686 785 884 983 299 399 1.003 305 407 509 612 714 817 920 1.024 104
'l!.Jl 624 m
834 106 212 318 424 531 638 745 852 960 1.068 108 216 325 434 543 652 761 871 981 1.091 110 221 332 443 555 778 890 1,003 1,.116 Note: See Figure ID-6 For Correction Factor Tech. Spec. Ref.: N/A Procedure Ref.: N/ A Figure Ref: DC00040-068 Rev 1.
Revision Dale: /0 - :U -'? 5 Prepaxed By:; L R Cm!in Verlfied By: P R Bovism AppwoedBy:: !d;IP~
FIGUREm*2. RCS BORATION GAlLONS (VJ OF BORIC ACID REQUIRED VB = ~1n(~) =496401n(~)
M = RCS Mass (4l3,5OOlbm)
C. = IDitiaI ppm C. = Final ppm Tech. Spec. Rei.: NJA Note: See Figmem-6 Far Co=ction Factor Inx:edme Ref~ NJA Figure Ref: DC00040-068 Rev 1.
"2
Rovisicn Dale: /1-11 ~ N-
. Pu,pazed By;:U f2..t;.
Verified By: <~
~
Appuved~l(f =;v ~
FIGURE m-l.
RCS BORATION T
GALLONS (VJ OF BORIC ACID REQUIRED v,.,.M...]n (70!l0-C')." 49640 ]n (70!l0-C')
B 8.33 70!l0-C, 70!l0-C, M = RCS Mass (413,500lbm)
C, = Initial ppm C, = Final ppm Tech. Spec. Ref.: N/A Note: See Figure m-6 For Correction Factor Proc:edme Ref.: N/A Figure Ref: DC00040-068 Rev!.
2009 V.C. Summer RO NRC Exam - As Given
- 50. Given the following plant conditions:
100% power A sudden double-ended shear of a tube (450 gpm) occurs in Steam Generator 'A'.
Which ONE (1) of the following radiation monitors will provide the FIRST indication of this event AND how will this monitor trend following the Reactor Trip and SI?
A. RM-G19A, Main Steam Line Monitor; Increase.
B. RM-G19A, Main Steam Line Monitor; Decrease.
C. RM-A9, Condenser Exhaust Monitor; Increase.
D. RM-A9, Condenser Exhaust Monitor; Decrease.
Thursday, July 09, 2009 8:08:35 AM 50
2009 V.C. Summer RO NRC Exam - As Given
- 51. Given the following plant conditions:
100% power A liquid waste discharge is in progress.
Annunciator MON TK DISCH RM-L5 TRBL (XCP-646, 2-6) has actuated.
Which ONE (1) of the following is the MINIMUM condition and/or action required to terminate the discharge?
A. Loss of power to the monitor ONLY.
B. Loss of power to the monitor AND the RML5 INTERLOCK Switch is THEN placed in ON.
C. Loss of power to the monitor AND the RML5 INTERLOCK Switch is THEN placed in OFF.
D. Radiation level increases to the WARNING setpoint.
Thursday, July 09.20098:08:35 AM 51
2009 V.C. Summer RO NRC Exam - As Given
- 52. With the plant operating at 35% power, which ONE (1) of the following conditions would require the plant to be placed in Hot Standby within ONE (1) hour per the associated Technical Specification.
A. A plant transient causes Tavg to rise to 590°F.
B. An electrical malfunction causes RCP 'C' flow to drop to 30%.
C. A plant transient causes t..1 to exceed 5% from the target value.
D. A instrument malfunction associated with the Master Pressure Controller causes Pressurizer pressure to drop to 2200 psig.
Thursday, July 09, 2009 8:08:35 AM 52
2009 V.C. Summer RO NRC Exam - As Given
- 53. Which ONE (1) of the following annunciators, when lit, indicates a condition which will prevent a Circulating Water Pump (CWP) from starting?
A. CW JOCKEY PP TRIP (XCP-628, 4-1)
B. CNDSR A VACUUM LO (XCP-628, 2-1)
C. CW INTAKE TRBL (XCP-628, 4-2)
D. CNDSR B CW OUT AlB LVL LO (XCP-628, 2-4)
Thursday, July 09,20098:08:35 AM 53
2009 V.C. Summer RO NRC Exam - As Given
- 54. Given the following plant conditions:
o 100% power o
Service Water (SW) Pump 'A' was isolated due to a leak and placed in PULL -TO-LOCK.
o The SW Pump 'A' breaker is still racked up.
o SW Pump 'C' has been racked up on Bus 1 EA but has not yet been started.
o A grid disturbance caused a loss of 115 Kv and 230 Kv offsite power (BOP &
ESF).
Which ONE (1) of the choices below completes the following statement?
If an automatic Safety Injection actuates TWO (2) minutes following the loss of offsite power, SW Pump 'B' __ _
A. will trip, then restart, and SW Pump 'C' will start B. will trip, then restart, and will be the only running SW Pump C. will continue to run and SW Pump 'c' will start D. will continue to run and will be the only running SW Pump Thursday, July 09,20098:08:35 AM 54
2009 V.C. Summer RO NRC Exam - As Given
- 55. Given the following plant conditions:
XSW -1 DA2 is OOS wh il e maintenance is working on the feeder breaker from the transformer.
A loss of ALL (ESF & BOP) offsite power occurred, resulting in a loss of BOP and ESF buses.
Both Emergency Diesel Generators started and restored power to their respective ESF buses.
ALL BOP buses remain de-energized.
Which ONE (1) of the following identifies the motor-driven air compressors with an available power supply?
A. XAC-3A, INSTR AIR CMPR A, ONLY B. XAC-3B, INSTR AIR CMPR B, ONLY C. XAC-3A and Supplemental Air Compressor D. XAC-3B and Supplemental Air Compressor Thursday, July 09, 2009 8:08:35 AM 55
2009 V.C. Summer RO NRC Exam - As Given
- 56. Given the following plant conditions:
100% power A fire occurs in the transformer to Bus XSW-1C2, causing the bus to de-energize.
The Fire Brigade responds 3 minutes after the event - routing, pressurizing, and using fire hoses to fight the fire.
Which ONE (1) of the following describes the FIRST response of the fire pumps to this event?
A. The Electric Fire Pump started within one minute of the fire.
B. The Diesel Fire Pump started within one minute of the fire.
C. The Electric Fire Pump started when the fire hoses were pressurized.
D. The Diesel Fire Pump started when the fire hoses were pressurized.
Thursday, July 09. 2009 8:08:35 AM 56
2009 V.C. Summer RO NRC Exam - As Given
Which ONE (1) of the following identifies the expected status of the specified indicating lights when performing EOP-1.0, Attachment 4 - Containment Isolation Valve Mea Status Light Locations?
XCP-6104 Status Light XCP-6106 Status Light "CROM CLG WTR ISOL "ACCUM N2 SPL Y ISOL 7502 CLSO" 8880 OPEN" A.
DIM DIM B.
DIM BRIGHT C.
BRIGHT BRIGHT D.
BRIGHT DIM Thursday, July 09,20098:08:35 AM 57
2009 V.C. Summer RO NRC Exam - As Given
- 58. Which ONE (1) of the following meets ALL entry conditions for entering EOP-1.5, Rediagnosis?
A. The crew has just entered EOP-15.0, Response to Loss of Secondary Heat Sink, following a Reactor Trip with NO SI and the CRS is NOT sure this is the appropriate procedure.
B. The crew has entered GOP-6, Plant Shutdown from Hot Standby to Cold Shutdown (Mode 3 to Mode 5) from EOP-1.1, Reactor Trip Response, and the CRS wants to verify that this is the correct procedure.
C. The crew is implementing EOP-4.0, Steam Generator Tube Rupture, and the CRS is NOT sure that this procedure is appropriate.
D. Due to a LOCA with NO SI in Mode 4, the crew has entered AOP-112.1, Shutdown LOCA, and the CRS is NOT sure this is the appropriate procedure.
Thursday. July 09. 2009 8:08:35 AM 58
2009 V.C. Summer RO NRC Exam - As Given
- 59. Given the following plant conditions:
After a LOCA. the crew has transitioned to EOP-2.1. Post-LOCA Coo/down and Depressurization. and is presently assessing the status of the Critical Safety Functions (CSFs).
Maximum total EFW Flow is 400 gpm.
The IPCS is unavailable.
Which ONE (1) of the following sets of conditions will result in an RED path to the Heat Sink CSF?
ASG BSG eSG Present RB Peak RB NR Level NR Level NR Level Pressure Rad Levels A.
12%
22%
32%
3 psig 105 mr/hr B.
31%
32%
12%
3 psig 104 mr/hr C.
28%
38%
48%
4 psig 105 mr/hr D.
28%
28%
51%
4 psig 104 mr/hr Thursday, July 09,20098:08:35 AM 59
2009 V.C. Summer RO NRC Exam - As Given
- 60. Given the following plant conditions:
o MODE 3, following a plant trip.
o A Red Path exists on Heat Sink and the crew has entered EOP-15.0, Response to Loss of Secondary Heat Sink, o
PZR Pressure is 2300 psig and increasing slowly.
o Steam Generator Levels are as follows:
o Steam Generator 'A' WIDE Range 6%
o Steam Generator '8' WIDE Range 12%
o Steam Generator 'C' WIDE Range 32%
Which ONE (1) of the following describes the action(s) in accordance with EOP-15.0 that is/are required NEXT?
A. Restore flow from the Main Feedwater System.
- 8. Restore flow from the Condensate System.
C. Trip RCPs, manually initiate Safety Injection, and allow the PZR PORVs to automatically open.
D. Trip RCPs, manually initiate Safety Injection, and manually open the PZR PORVs.
Thursday, July 09, 2009 8:08:35 AM 60
2009 V.C. Summer RO NRC Exam - As Given
- 61. Which ONE (1) of the following spoken statements meets the MINIMUM acceptable station requirements for proper communication in accordance with OAP-100A, Communications?
A. "Control rods are stepping IN."
B. "Tom, RCS Tavg is 557"F."
C. "Tom, Pressurizer pressure is 2205 psig, trending towards 2235 psig."
D. "Turbine Building Operator, Perfonm SOP-214, Steps 2.14 and Steps 2.15."
(procedure NOT available to the TBAO)
Thursday. July 09. 2009 8:08:35 AM 61
2009 V.C. Summer RO NRC Exam - As Given
- 62. Given the following plant conditions:
The unit is at 100% power.
MCB logs are in progress.
AUTO TOUR is not available.
ECCS Accumulator 'A' MCB indicator is reading 60%, which is out-of-limitlspec.
ECCS Accumulator 'A' indication on the computer is 75%.
In accordance with OAP-1 06.1, Operating Logs, which ONE (1) of the following are the MINIMUM required actions with respect to logging ECCS Accumulator 'A' level?
A. Record the reading as 60%, red circle, inform the CRS, explain actions taken in the Comments section.
B. Record the reading as 75%, red circle, inform the CRS, assign a number in the right margin, and explain actions taken in the Comments section.
C. Record the reading as 75%, red circle, inform the CRS, explain actions taken in the Comments section.
D. Record the reading as 60%, red circle, inform the CRS, assign a number in the right margin, and explain actions taken in the Comments section.
Thursday, July 09, 2009 8:08:35 AM 62
2009 V.C. Summer RO NRC Exam - As Given
- 63. Which ONE (1) of the following are the MINIMUM required actions per GOP Appendix A, Generic Operating Precautions, if it appears that criticality will be achieved below the LO-LO Rod Insertion Limit?
A. Suspend positive reactivity additions. Recalculate the Estimated Critical Condition (ECC). Dilute to criticality per REP-107.001, Controlling Procedure for Refueling Startup and Power Ascension Testing.
B. Borate (normal method) as necessary to achieve the required Shutdown Margin; shutdown the Reactor per GOP-5 and recalculate the ECC.
C. Emergency Borate through MVT-81 04, EMERG BORATE, to achieve the required Shutdown Margin and shutdown the Reactor per GOP-5.
D. Recalculate the ECC, adjust the RCS boron concentration. Continue the startup Thursday, July 09, 2009 8:08:35 AM 63
2009 V.C. Summer RO NRC Exam - As Given
- 64. Given the following plant conditions:
Mode 6 As part of scheduled outage work, IFV-3531-0-EF, OPER-SG A MTR DR EF PUMP FLOW CONT VLV, has been isolated to replace the actuator.
Which ONE (1) of the choices below completes the following statements?
Per SAP-205, Status Control and Removal and Restoration, an Removal and Restoration will be used to track the status of IFV--=3-=5"'3C"'1--=O""--=E=F:-. -
Per OAP-106.3, Locked Valve Program, a --,-____ chain will be installed when the valve is restored to the normal configuration.
A. ACTION; RED B. ACTION; SILVER C. OUTAGE; RED D. OUTAGE; SILVER Thursday. July 09. 2009 8:08:35 AM 64
2009 V.C. Summer RO NRC Exam - As Given
- 65. Given the following plant conditions:
100% power Charging/SI Pump 'B' is running The crew will be shifting to Charging/SI Pump 'C' running on Train 'B' in accordance with SOP-102, Chemical and Volume Control System.
Which ONE (1) of the following describes ECCS SubsystemITrain operability status while the procedure is performed?
A. INITIAL entry into the LCO for Train 'B' is required at the time when both Charging/SI Pumps 'B' and 'C' breakers are racked up AND closed.
B. INITIAL entry into the LCO for Train 'B' is required at the time when both Charging/SI Pumps 'B' and 'C' breakers are racked up ONLY.
C. BOTH trains remain OPERABLE because at least ONE pump is running throughout the procedure.
D. BOTH trains remain OPERABLE because the swing pump is available as the standby pump throughout the procedure.
Thursday, July 09, 2009 8:08:35 AM 65
2009 V.C. Summer RO NRC Exam - As Given
- 66. During preparation for a Waste Monitor Tank release, which ONE (1) of the following identifies how the HI RAD setpoint for RM-L5, LIQUID WASTE EFFLUENT MONITOR, is adjusted and where is the release setpoint found?
A. Set at 2X background; SOP-108, Liquid Waste Processing System, Attachment VA, Liquid Waste Release Worksheet - Control Room B. Set at 2X background; HPP-904, Use ofthe Radiation Monitoring System C. Based on tank sample; SOP-108, Liquid Waste Processing System, Attachment VA, Liquid Waste Release Worksheet - Control Room D. Based on tank sample; HPP-904, Use of the Radiation Monitoring System Thursday, July 09.20098:08:35 AM 66
2009 V.C. Summer RO NRC Exam - As Given
- 67. Which ONE (1) of the following describes how an active (in use) RWP is REQUIRED to be posted by HPP-151, Use of the Radiation Work Permit and Standing Radiation Work Permi(?
On the computers at the entrance to the RCA ____ _
A. ONLY.
B. and a hardcopy at the job site.
C. and a hardcopy in the dress out area of the AB 436'.
D. and a hardcopy outside of the east wall of the dressing room on the CB 412'.
Thursday, July 09. 2009 8:08:35 AM 67
2009 V.C. Summer RO NRC Exam - As Given
- 68. Which ONE (1) of the following identifies an event where the subsequent power change, as listed in AOP-21 0.3, Feedwater Pump Malfunction, requires notification of the Chemistry Department and identifies the sample required to be analyzed?
A. ONE of TWO running Main Feedwater Pumps trips at 65% power; Iodine isotopic analysis B. ONE of TWO running Main Feedwater Pumps trips at 65% power; 1 OO/E-bar determination C. ONE of THREE running Main Feedwater Pumps trips at 100% power; Iodine isotopic analysis D. ONE of THREE running Main Feedwater Pumps trips at 100% power; 1 OO/E-bar determination Thursday, July 09, 2009 8:08:35 AM 68
2009 V.C. Summer RO NRC Exam - As Given
- 69. Given the following plant conditions:
100% power A severe lightning storm has resulted in problems with many Main Control Board annunciator panels and individual annunciators.
One of the affected panels is XCP-615, which includes annunciator RCS LEAK DET >1 GPM (point 3-6) and several others.
Which ONE (1) of the choices below completes the following statements?
The crew will enter _____ in response to the loss of annunciators.
The crew will compensate for the loss of the RCS LEAK DET >1 GPM alarm using an attachment in
?
A. OAP-100.5, Guidelines for Configuration Control and Operation of Plant Equipment OAP-1 06.1, Operating Logs B. AOP-1 00.5, Loss of Main Control Board Annunciators OAP-1 06.1, Operating Logs C. OAP-100.5, Guidelines for Configuration Control and Operation of Plant Equipment GTP-702, Surveillance Activity Tracking and Triggering D. AOP-100.5, Loss of Main Control Board Annunciators GTP-702, Surveillance Activity Tracking and Triggering Thursday. July 09. 2009 8:08:36 AM 69
2009 V.C. Summer RO NRC Exam - As Given
- 70. Which ONE (1) of the following describes the limitation on Containment Air Temperature in Technical Specification 3.6.1.5, Containment Air Temperature?
A. The HIGHEST temperature reading cannot exceed 120°F.
B. The HIGHEST temperature reading cannot exceed 135°F.
C. The AVERAGE temperature reading cannot exceed 120°F.
D. The AVERAGE temperature reading cannot exceed 135°F.
Thursday, July 09, 2009 8:08:36 AM 70
2009 V.C. Summer RO NRC Exam - As Given
- 71. Given the following plant conditions:
A cooldown is in progress in accordance with GOP-6, Plant Shutdown from Hot Standby to Cold Shutdown.
Which ONE (1) of the following identifies the RCS temperature where the MOST restrictive cool down limit is in effect and the reason in accordance with Technical Specification 3.4.9 RCS PressurefTemperature Limits?
A. RCS temperature GREATER THAN 200°F to prevent a non-ductile component failure.
B. RCS temperature GREATER THAN 200°F to prevent bubble formation in the reactor vessel head.
C. RCS temperature LESS THAN 200°F to prevent a non-ductile component failure.
D. RCS temperature LESS THAN 200°F to prevent bubble formation in the reactor vessel head.
Thursday, July 09, 2009 8:08:36 AM 71
2009 V.C. Summer RO NRC Exam - As Given
- 72. Given the following plant conditions:
100% power A leak develops in the Main Condenser causing vacuum to decrease.
The crew enters AOP-206.1, Decreasing Main Condenser Vacuum.
Main Condenser pressure INCREASES at 1" Hg Absolute every five minutes.
The crew initiates a down power in accordance with GOP-4C, Rapid Downpower, at 5%/minute.
All control systems are in AUTO.
Which ONE (1) of the following conditions will REQUIRE the operator to trip the Reactor?
A. Pressurizer pressure approaches 1985 psig.
B. Main Condenser pressure rises above 5" Hg Absolute.
C. Tavg is 8°F greater than Tref and Control Rods are NOT moving in AUTO.
D. Tavg is 12°F greater than Tref and Control Rods are moving inward at 72 steps/minute.
Thursday. July 09. 2009 8:08:36 AM 72
2009 V.C. Summer RO NRC Exam - As Given
- 73. Which ONE (1) of the following describes a condition that will require the crew to transition out of EOP-6.0, Loss of All ESF AC Power prior to restoring power to at least one AC ESF Bus?
A. The Tcolds for all three RCS loops decrease to less than 280°F.
B. Both Intermediate and Source Range startup rates are positive.
C. Wide range levels in ALL 3 SIGs drop below 30%.
D. Core Exit TICs indicate greater than 1200°F and rising.
Thursday, July 09. 2009 8:08:36 AM 73
2009 V.C. Summer RO NRC Exam - As Given
- 74. Given the following plant conditions:
An AUTO SI actuated when a Pressurizer Safety Valve failed OPEN.
All Steam Generator (SG) Narrow Range levels are at 15%.
Tavg is 550°F, lowering.
Which ONE (1) of the following is the required action with respect to Emergency Feedwater flow in accordance with EOP-1.0, Reactor Trip/Safety Injection Actuation?
A. Maintain maximum available EFW flow until at least one SG narrow range level is greater than 26% [40%].
B. Reduce total EFW flow to no less than 380 GPM to stop the cooldown.
C. Reduce total EFW flow to no less than 450 GPM to stop the cooldown.
D. Reduce EFW flow to each SG to no less than 50 GPM to stabilize Tavg at the no load value.
Thursday, July 09, 2009 8:08:36 AM 74
2009 V.C. Summer RO NRC Exam - As Given
- 75. When restoring the vital buses to off-site power in accordance with SOP-306, Emergency Diesel Generator, the respective diesel generator speed and voltage droop circuits are placed in service when __ _
A. depressing the local TEST START pushbutton B. momentarily placing the MCB TEST Switch to START C. depressing the local EMERG START RESET pushbutton D. depressing the MCB EMERG START OVRRIDE pushbutton You have completed the testl Thursday. July 09. 20098:08:36 AM 75
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