ML091320198

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301 Final SRO Exam (Part 1 of 2)
ML091320198
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 05/01/2009
From:
NRC/RGN-II
To:
Southern Nuclear Operating Co
References
Download: ML091320198 (61)
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  1. ID 0 1 201001K5.02 1 B 2 202001K4.07 1 A 3 20300002.4.8 1 C 4 204000A4.09 1 B 5 205000K2.011 A 6 206000K5.081 D 7 206000K6.02 1 D 8 209001A4.04 1 A 9 209001A4.05 1 A 10 211000K4.03 1 A 11 212000A1.07 1 C 12 215001A3.03 1 D 13 215002K6.04 1 D 14 215003A1.03 1 C 15 215004K6.01 1 B 16 21500502.1.201 D 17 21500502.4.11 1 D 18 217000K2.03 1 B 19 218000K1.06 1 A 20 223001K3.09 1 B 21 223002K3.11 1 B 22 226001K2.021 B 23 23300002.2.25 1 C 24 239001K5.09 1 B 25 239002A3.01 1 C 26 241000K1.251 A 27 259002A4.01 1 C 28 261000A2.12 1 D 29 262001K4.021 A 30 262001K4.05 1 A 31 262002K3.01 1 C 32 263000A2.021 A 33 264000K4.06 1 A 34 264000K5.061 B 35 268000A2.01 1 D 36 286000A1.01 1 C 37 295001AK2.03 1 A 38 29500302.4.34 1 D 39 295004AA1.03 1 D 40 295005AK3.04 1 C 41 295006AK1.01 1 D 42 29501002.2.22 1 D 43 295013AK2.01 1 A 44 29501502.2.421 A 45 295016AA2.011 D 46 295018AK3.03 1 D

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Page: 1 of3 5/1/2009 

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  1. ID 0 49 29502IG2.4.35 1 D 50 295023AAl.04 1 D 51 295024EA2.06 1 B 52 295025G2.I.23 1 A 53 295026EK2.0II D 54 295028EAl.03I C 55 295030EKl.02 1 D 56 29503IEAl.OI 1 C 57 295032EAl.03 1 C 58 295035EA2.02 1 D 59 295037EK2.I2I A 60 295038EKl.02I A 61 300000Kl.03 1 B 62 400000K3.0I 1 D 63 500000EK3.06 1 C 64 600000AKl.OI 1 C 65 700000G2.4.4 1 A 66 G2.1.27 1 B 67 G2.1.3II D 68 G2.1.391 A 69 G2.2.I5I A 70 G2.2.25I A 71 G2.2.39I C 72 G2.3.I4I D 73 G2.3.13 1 A 74 G2.4.II C 75 G2.4.9I A 76 2I2000G2.2.36I C 77 233000G2.1.28 1 B 78 239002G2.4.I8 1 D 79 259002G2.4.20 1 D 80 262002A2.0I 1 A 81 268000G2.4.2I 1 A 82 29000IA2.04 1 B 83 295006G2.I.27 1 A 84 295008G2.4.20 1 C 85 2950I4G2.2.40 1 C 86 295017 AA2.0I 1 A 87 29502IAA2.03I B 88 295023G2.4.45 1 B 89 295026EA2.03 1 D 90 295028EA2.04 1 D 91 295038G2.4.9 1 C 92 223002A2.06I A 93 600000G2.4.49 1 C 94 G2.1.20 1 B 95 G2.2.III C 96 G2.2.7I D Page: 20f3 5/112009

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ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination A~plicant Information Name: Date: April 30th , 2009 Facility/Unit: Plant E. I. Hatch Region: I D II X III D IV D Reactor Type: W D CE D BW D GE X Start Time: Finish Time: Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours to complete the combined examination, and 3 hours if you are only taking the SRO portion. Applicant Certification All work done on this examination is my own. I have neither given nor received aid. Applicant's Signature Results RO/SRO-OnlylTotal Examination Values / -- / -- Points Applicant's Scores / -- / -- Points Applicant's Grade / -- / -- Percent f- 

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1. Unit 2 was operating at 100% power when the reactor was manually scrammed. (Figure A) (Figure B) Which ONE of the following choices completes the following statement? The expected Control Rod Drive (CRD) Flow Controller flow indication IMMEDIATELY following the manual scram is shown on (1) and, based on this indication there is a potential for (2) to occur until the reactor scram is reset. A. (1) Figure A (2) CRD pump runout B. (1) Figure A (2) excessive reactor vessel bottom head cooldown

c. (1) Figure B (2) elevated CRDM temperatures D. (1) Figure B (2) low drive water differential pressure (dp)

Page: 1 of 100 4128/2009

2. Unit 1 is operating at 80% power. o Both Recirculation pumps are running at 78% speed o All Condensate and Condensate Booster Pumps are in service 

           - 4160 VAC Bus "lC" is inadvertently de-energized.

Which ONE of the following describes how the Reactor Recirculation system will be affected? o The" 1A" Recirc pump will (1) o The "lB" Recirc pump will (2) A. (1) automatically trip (2) automatically trip B. (1) automatically trip (2) be running at 61 % speed C. (1) be running at 61 % speed (2) be running at 61 % speed D. (1) be running at 78% speed (2) be running at 78% speed Page: 2 of 100 4/28/2009

3. Unit 2 was operating at 100% power when a Loss Of Coolant Accident occurred. These conditions exist: o The reactor has scrammed and all control rods fully inserted o RPV pressure .................. 960 psig, increasing at 4 psig/minute o Drywell (DW) pressure ... 7 psig (decreasing) o BOTH RHR loops ............ DW spray mode o RPV level ........................ -145 inches, decreasing at 2"/minute o 4160 VAC bus "2E" has de-energized and cannot be re-energized Given these conditions, IAW 34AB-R23-001-2, "Loss of 600 Volt Emergency Bus", energizing 600 VAC bus "2C" using the 4160/600V "2CD" Transformer is _ _ _ _ _ _ __ A. NOT allowed; the reactor must be in Mode 4 B. NOT allowed; the "IB" Emergency Diesel Generator would be overloaded C. allowed; ALL low pressure ECCS will NOT inject at rated flow when reactor pressure decreases to below the shutoff head D. allowed; but is NOT needed since all low pressure ECCS will inject at rated flow when reactor pressure decreases to below the shutoff head Page: 3 of 100 4128/2009

4. Unit 2 is at 2% power performing a reactor heatup and pressurization. The Reactor Water Cleanup (RWCU) system is aligned for vessel level control. o Reactor Water Level (RWL) begins to increase o Non-Regenerative Heat Exchanger (NRHX) Effluent temperature ......... 138°F Which ONE of the following completes both of these statements? NRHX Effluent temperature is monitored at panel2Hll- (1) IAW 34S0-G31-003-2, "Reactor Water Cleanup System," 2G31-R606, Manual Controller for 2G31-F033, "RWCU Blowdown Flow Control Valve" is required to be throttled (2) A. (1) P602, front panel (2) OPEN B. (1) P602, front panel (2) CLOSED C. (1) P614, back panel (2) OPEN D. (1) P614, back panel (2) CLOSED Page: 4 of 100 4128/2009

5. Unit 1 is in Mode 4 with "IC" and "ID" Residual Heat Removal (RHR) pumps running in Shutdown Cooling. o An over-current condition develops on Emergency Bus 4160VAC "IF" which causes it to de-energize. Which ONE of the following predicts the status of the" I C" and" ID" RHR pumps? A. "IC" RHR Pump has stopped "ID" RHR Pump has stopped B. "IC" RHR Pump is running "ID" RHR Pump has stopped C. "IC" RHR Pump has stopped "ID" RHR Pump is running D. "IC" RHR Pump is running "ID" RHR Pump is running Page: 5 of 100 4/28/2009

6. Unit 2 is operating at 100% power. o 34SV-E41-002-2, "HPCI PUMP OPERABILITY" has just been completed. o When the High Pressure Coolant Injection (HPCI) system is secured, BOTH HPCI Turbine Exhaust Vacuum Breaker check valves (2E41-F102 and F103) fail in the OPEN position. Which one of the following identifies the potential impact of these check valve failures during a subsequent HPCI auto-initiation on low reactor water level AND whether control room indication is available for these check valves? When the HPCI starts, a high potential for _.....l(...:::.1.L...)_ will exist. Position indication for these CHECK V ALVES _.....l(=2.L...)_ available in the Control Room. A. (1) water hammer (2) is B. (1) water hammer (2) is NOT C. (1) high Torus pressure (2) is D. (1) high Torus pressure (2) is NOT Page: 6 of 100 4/28/2009

7. Unit 2 is operating at 100%. o 2R24-S022, "250 VDC RX BLDG ESSEN. 2B" de-energizes (remains de-energized) o A transient results in a scram and a High Pressure Coolant Injection (HPCn automatic initiation signal. Which ONE of the following describes how the HPCI system will respond to the automatic initiation signal? HPCI will _ _ _ _ _ __ A. automatically start and operate normally B. automatically start; however, only local control will be possible C. NOT automatically start, but can be manually started D. NOT automatically start and can NOT be manually started Page: 7 of 100 4/28/2009

8. Unit 1 is at 100% power. o Both loops of Core Spray (CS) are in their normal standby lineup. o CS receives an automatic start signal Which ONE of the following completes BOTH of these statements? In their normal standby lineup, the CS Minimum Flow valves (2E21-F031A1B) are normally 0) The CS Minimum Flow valves (2E21-F031A1B) will remain in their standby lineup until (2) A. (1) open (2) discharge flow exceeds 950 gpm B. (1) open (2) the CS pump motor breaker is closed

c. (1) closed (2) discharge flow exceeds 950 gpm D. (1) closed (2) the CS pump motor breaker is closed Page: 8 of 100 4128/2009

9. Unit 2 is operating at 100% power, with HPCI tagged out for maintenance. A trip of both reactor feedwater pumps results in a low reactor water level with conditions occurring as indicated in the following time line: Time (minutes) 

           +0 min. Reactor scram, all rods fully insert
           +5 min. Drywell pressure:      0.7 psig.
           +5 min. Reactor water level: -110 inches, decreasing at 0.5 inch/minute.
           +5 min. Reactor pressure:      960 psig.
           +6 min. Both Core Spray (CS) systems are in their normal standby lineups.

Which ONE of the following describes the MINIMUM required operator actions (if any)? A. manually start both CS pumps (only) B. manually start both CS pumps and manually open discharge valves 2E21-F004A & F004B (only) C. manually start both CS pumps and manually open discharge valves 2E2l-F005A & F005B (only) D. no manual operation of CS is required at this time, continue to monitor until system operation is required Page: 9 of 100 4128/2009

10. Concerning the Unit 2 Standby Liquid Control (SLC) system: TANK LEVEL TANK LEVEL 2C41-R601 2C41-R601 100 80 60 40 20 o r Figure A Figure B Which ONE of the following completes both of these statements? During normal operation, the means by which Sodium Pentaborate is CONTINUOUSLY maintained in solution inside the SLC tank is by the use of (1) Given the two figures shown above, and that SLC has been initiated during an ATWS, (2) indicates the HIGHEST SLC tank level which ensures that Hot Shutdown Boron Weight has been injected into the RPV. A. (1) tank heaters (2) Figure A B. (1) an air sparger (2) Figure A C. (1) tank heaters (2) Figure B D. (1) an air sparger (2) Figure B Page: 10 of 100 4128/2009

11. Unit 2 was operating at 30% power. o Control rod 26-35 is at notch position 48 o The Rod Scram Switch for control rod 26-35, at 2HII-P61 0, is placed into the "DOWN (scram)" position o 2 seconds later, the switch is placed in the "UP (normal)" position. Which ONE of the following is the expected Rod Position fudication on the 4-Rod Display at 2HII-P603 panel for control rod 26-35 after these actions are performed? A. blank (over-travel beyond full in) B. full in C. intermediate D. position 46 Page: 11 of 100 4128/2009

12. Unit 1 is operating at 100% power with the "A" Traversing In-Core Probe (TIP) inserted in the core to perform 57CP-C51-010-0, "TIP Flux Probing Monitor". A transient occurs on Unit 1 with the following plant conditions: Reactor pressure ..................... 900 psig and stable Reactor level (lowest) ............ -20 inches and slowly increasing Drywell pressure .................... 1.5 psig and stable Drywell temperature.............. 129°P Which ONE of the following completes the statement below? The "A" TIP will withdraw to the _ _ _ _ _ _ and the Ball Valve position will be A. Indexer (Parked) position; open B. Indexer (Parked) position; closed C. In Shield position; open D. In Shield position; closed Page: 12 of 100 4128/2009

13. Unit 2 is operating at 100% power with a centrally located control rod selected. o The operator bypasses APRM channel "B" Which ONE of the following identifies the effect this action will have on the RBM "B" channel? The "B" RBM will automatically use the _ _ _ _ _ _ _ __ A. "C" APRM channel to monitor the neutron flux in the locality of the selected rod B. "C" APRM channel to determine one of the three upscale setpoints C. "D" APRM channel to monitor the neutron flux in the locality of the selected rod D. "D" APRM channel to determine one of the three upscale setpoints Page: 13 of 100 4128/2009

14. A Unit 1 Reactor Startup is in progress. IRMs read as follows: IRM Reading Range Reading Range A 38/125 8 B 35/125 8 Which ONE of the following predicts how the plant will respond to the following switch manipulations? o IRM "A" range switch is placed in the RANGE 7 position. o IRM "B" range switch is placed in the RANGE 7 position. The IRMs will _ _ _ _ _ __ A. NOT initiate any automatic action B. initiate a rod block (only)

c. initiate a rod block and a half scram (only)

D. initiate a full scram Page: 14 of 100 4/28/2009

15. Unit 1 is starting up. o All Intermediate Range Monitors (IRM) are on RANGE 4 (reading on-scale) o All Source Range Monitors (SRM) are all partially withdrawn and indicating 5 x 104 counts per second (cps) The "lA" SRM chassis at PanellHll-P606 experiences a failure that causes the voltage at the SRM detector to lower to 20 VDC. The SRM indication dropped to 10 cps. Which ONE of the following choices completes the following statement? A Control Rod Block (1) occur because (2) A. (1) will (2) the SRM count rate is at the downscale setpoint B. (1) will (2) the SRM Detector voltage is low

c. (1) will NOT (2) of the IRM range switch positions D. (1) will NOT (2) the SRM count rate is still reading 10 cps Page: 15 of 100 4128/2009

16. Unit 1 is operating at 100% power with all OPRMs inoperable when the "IB" Reactor Recirc Pump trips. Which ONE of the following actions is required, including the reason for this action? A. Manual Scram; all OPRMs are inoperable. B. Manual Scram; Reactor steam dome to bottom head delta-Twill be exceeded. C. The APRM simulated thermal power (STP) high trip setpoint must be changed; all OPRMs are inoperable. D. The APRM simulated thermal power (STP) high trip setpoint must be changed; Two Recirc Loops are not operating. Page: 16 of 100 4128/2009

17. Unit 1 is operating at 40% power when a scram signal is received. o Some control rods do NOT fully insert o APRMs ................. ........ ..... ........ ... ... ...... all indicating 2% (highest since scram 3%) o Reactor water level ................................ 37 inches (lowest since scram 9 inches) o Reactor pressure ................................... 930 psig (highest since scram 1050 psig) o Drywell pressure ........ ............ ..... .......... 0.3 psig (not changed since scram) o Both Reactor Recirculation pumps ....... 22% speed Which ONE of the following completes both of these statements lAW 34AB-C71-001-1, "Scram Procedure" and 34AB-C11-005-1, "Control Rod Insertion Methods"? Overriding of ALL automatic scram signals to insert control rods is _ _.....(;.,1)4--_ _ Tripping of the Reactor Recirculation pumps (2) required. A. (1) allowed (2) is B. (1) allowed (2) is NOT C. (1) NOT allowed (2) is D. (1) NOT allowed (2) is NOT Page: 17 of 100 4128/2009

18. Which ONE of the following is the power supply to the Unit 2 RCIC flow controller? A. Vital AC (2R25-S063) B. DC Cabinet "2A" (2R25-S001) C. Instrument Bus "2A" (2R25-S064) D. Reactor Bldg ESS MCC "2B" (2R24-S022) Page: 18 of 100 4128/2009

19. Unit 2 has experienced a Loss of Offsite Power (LOSP). The following conditions existed at 09:00 and remain unchanged for 5 minutes: o Reactor........................ All rods in o All 4160 VAC buses .......... De-energized o RPV Pressure........... ........... 700 psig o RWL ............................ -135 inches o Drywell Pressure.. . .. . . . ... .. 3 psig o ADS Inhibit Switches .......... "Normal" position An operator starts the "2A" Emergency Diesel and the following events occur at 09:05: 

             - "2A" Core Spray (CS) pump starts.
             - "2A" CS develops normal discharge pressure Which ONE of the following identifies the EARLIEST time when the ADS valves will automatically open?

A. 09:05 B. 09:07 C. 09:16 D. 09:18 Page: 19 of 100 4128/2009

20. Unit 2 scrammed from 90% power due to a complete loss of Drywell (D/w) Cooling. Immediately after the scram, a complete loss of high and low pressure feed occurred. o Reactor pressure.................. 900 psig o Reactor water level indications (all reading are uncompensated) o 2B21-R623A, Fuel Zone ..................... - 305 inches o 2B21-R623B, Fuel Zone ...................... - 295 inches o 2B21-R623A, Wide Range .................. - 145 inches o 2B21-R623B, Wide Range .................. - 135 inches o The following Drywell temperatures currently exist: RTD GROUP 1 indicators RTD GROUP 2 indicators 2T47-N001K .... 285°F 2T47-N001A ..... 290°F 2T47-NOlO 290°F 2T47-N002 ..... 288°F 2T47-N014 .... 287°F 2T47-N015 ..... 295°F IAW with EOP Caution 1, which ONE of the following identifies a Reactor Water Level (RWL) instrument that can be used to determine R WL ? REFERENCE PROVIDED A. 2B21-R623A, Fuel Zone B. 2B21-R623B, Fuel Zone C. 2B21-R623A, Wide Range D. 2B21-R623B, Wide Range Page: 20 of 100 4/28/2009

21. Unit 2 is at 100% power and the "2A" Reactor Protection System (RPS) MIG Set trips. Which ONE of the following completes both of these statements? After RPS MIG Set "2A" trips, the Main Control Room Environmental Control (MCREC) system will automatically align to the mode. fu this mode, outside air _ _ _ _ be drawn into the MCREC system. A. Isolation; will B. Pressurization; will C. Isolation; will NOT D. Pressurization; will NOT Page: 21 of 100 4/28/2009

22. Unit 1 was operating at 100% power with the Alternate Supply Breaker to 4l60VAC bus "IE" tagged out. A loss of Startup Transformer (SAT) "ID" occurred. o Torus Pressure reaches 3 psig during the transient. o "IA" and "IB" RHR pumps are running in the Torus Spray Mode. The power supply for the 4160 VAC bus to the "IA" RHR Pump is _-,-,0,,-<)__ and to the "IB" RHR Pump is (2) A. (1) SAT "IC" (2) SAT "IC" B. (1) its associated EDG (2) SAT "IC"

c. (1) SAT "IC" (2) its associated EDG D. (1) its associated EDG (2) its associated EDG Page: 22 of 100 4128/2009

23. Fuel movement is in progress in the Fuel Pool on Unit 1. IAW with Tech Spec Limiting Condition for Operation (LCO) 3.7.8, Spent Fuel Storage Pool Water Level, which ONE of the following is the LOWEST level that will still meet the LCO 3.7.8 requirements WITHOUT entering a Required Action Statement (RAS)? A. 23.1 feet B. 22.1 feet C. 21.1 feet D. 20.1 feet Page: 23 of 100 4/28/2009

24. Unit 2 was at 100% power when a reactor scram occurred. The operators have completed all steps of the following placards lAW 34AB-C71-001-2, "Scram Procedure." 

           - RC-l , IMMEDIATE SCRAM REACTIVITY CON1ROL ACTIONS
           - RC-2, FEEDWATER CON1ROL ACTIONS FOLLOWING SCRAM
           - RC-3, IMMEDIATE RPV PRESSURE CONTROL ACTIONS FOLLOWING A SCRAM
           - TC-l, IMMEDIATE TURBINE TRIP RESPONSE ACTIONS Which ONE of the following identifies a component that will still be contributing to the RPV cooldown?

A. Reactor feed pump low pressure steam supply. B. Reactor feed pump high pressure steam supply. C. Moisture Separator Reheater first stage steam supply. D. Moisture Separator Reheater second stage steam supply. Page: 24 of 100 4128/2009

25. Unit 1 has experienced a transient and the Automatic Depressurization System (ADS) automatically actuated. o Reactor pressure decreases from 1000 psig to 39 psig o No ADS control switches have been manipulated Which ONE of the following predicts which ADS valve light indications are ILLUMINATED at pane12HII-P602? A. ONLY the Red light is illuminated. B. ONLY the Red and Green lights are illuminated.

c. ONLY the Red and Amber lights are illuminated.

D. The Red, Amber, and Green lights are ALL illuminated. Page: 25 of 100 4/28/2009

26. Unit 2 was operating at 35% power, with the Main Generator at 7000 amps. At Time T = 0, the following alarms were received: 

           "GENERATOR PROTECTION CKT ENERGIZED" (651-206)
           "GENERATOR INLET PRESS LOW," (651-202)
           "GENERATOR OUTLET TEMP HIGH," (651-204)

At Time T =3.5 minutes, the Main Generator is at 6600 amps. Which ONE of the following identifies the component that began automatically closing to lower generator amps and predicts the Turbine status at time T =3.5 minutes? A. Turbine Control Valves; Turbine is Tripped B. Turbine Control Valves; Turbine remains on line C. Turbine Combined Intermediate Valves (CNs); Turbine is Tripped D. Turbine Combined Intermediate Valves (CNs); Turbine remains on line Page: 26 of 100 4/28/2009

27. Unit 2 is at 50% power, performing a Startup. o Reactor Feed Pump Turbine (RFPT) "2B" is in service in automatic control. Due to intermittent problems with the "2A" RFPT MIA station, 2C32-R601A, Maintenance has taken 2C32-R601A to the maintenance shop for repair. The Shift Supervisor directs placing the "2A" RFPT in service IAW 34S0-N21-007-2, "Condensate and Feedwater System", section 7.3.7, "RFPT Alternate Startup." Which ONE of the following choices completes the following statements for this mode of RFPT operation? The reason that the "2A" RFPT speed will initially be stopped at 1000 RPM is to (1) In this mode of operation the Speed Setter switch (2) allow speed to be raised above 2100 RPM. A. (1) slowly introduce feedwater into the RPV (2) will B. (1) slowly introduce feedwater into the RPV (2) willNOT C. (1) allow oil temperature to increase (2) will D. (1) allow oil temperature to increase (2) will NOT Page: 27 of 100 4128/2009

28. Unit 2 is in a Refueling Outage with fuel movement in progress. Minor damage to a fuel bundle results in an increase in Refueling Floor radiation levels. The "Refueling Floor Vent Exhaust" monitors are reading: o 2D 11-K634A - 19 mRemlhr o 2D11-K634B - 18 mRemlhr o 2DII-K634C - 15 mRemlhr o 2D 11-K634D - 14 mRemlhr Which ONE of the following predicts BOTH the impact of these conditions on the Unit 1 and Unit 2 Standby Gas Treatment Systems (SBGT) and the procedural requirements? The total number of SBGTs trains that will automatically start is (1) The operator is required to enter (2) A. (1) two (ONLY) (2) ONLY 34AB-J11-00l-1, "Irradiated Fuel Damage During Handling" B. (1) four (2) ONLY 34AB-J 11-001-1, "Irradiated Fuel Damage During Handling"

c. (1) two (ONLY)

(2) BOTH 34AB-JII-00l-l, "Irradiated Fuel Damage During Handling" AND 34AB-T22-003-2, "Secondary Containment Control" D. (1) four (2) BOTH 34AB-J11-00l-1, "Irradiated Fuel Damage During Handling" AND 34AB-T22-003-2, "Secondary Containment Control" Page: 28 of 100 4/28/2009

29. Unit 2 is at 90% power. o 4160 VAC bus "2A" is being powered from its alternate source due to maintenance activities. 

          - The "2G" 4160 VAC normal supply breaker trips open due to an internal breaker fault.
          - Two minutes later the Main Turbine Trips.

Which ONE of the following predicts the FINAL status of the "2A" and "2G" buses? A. ONLY 4160 VAC bus "2G" will be energized. B. ONLY 4160 V AC bus "2A" will be energized. C. BOTH 4160 VAC buses "2A" AND "2G" will be energized. D. NEITHER 4160 VAC bus "2A" NOR "2G" will be energized. Page: 29 of 100 4128/2009

30. Unit 1 is in Mode 3. The Shift Supervisor has directed that the "IA" EDG be paralleled to its associated bus IAW 34S0-R43-001-1, "Diesel Generator Standby AC System," Section 7.2.2 "Synchronizing Diesel Generator to an Energized Bus." Which ONE of the following choices completes this statement? In order to close the EDG output breaker, the "IA" EDG Mode Switch _ _ required to be in the "TEST" position and the synchroscope lights are approaching the point. A. is; dimmest B. is; brightest C. is NOT; dimmest D. is NOT; brightest Page: 30 of 100 4/28/2009

31. Unit 2 is at 100% power when a loss of 2R25-S063, "Vital AC" occurs. Which ONE of the following completes this statement? The Feedwater Master Controller _ _ _ lose power and the Feedwater Level Control system will _ _ __ A. will; remain in 3 element control B. will NOT; remain in 3 element control C. will; shift to single element control D. will NOT; shift to single element control Page: 31 of 100 4128/2009

32. Unit 2 is operating at 100% power, with the "2A" and "2B" 1251250VDC Station Service Batteries on equalize charge, when the Control Building ventilation is lost. Which ONE of the following predicts (1) a consequence of losing the Control Building ventilation and also (2) identifies a required action lAW 34AB-T4l-00l-2, "Loss Of ECCS, MCREC Or Area Ventilation Systems"? A. (1) Hydrogen concentration will rise in the battery rooms; (2) Start Emergency Exhaust Fans 2Z4l-C014 and 2Z41-C015. B. (1) Hydrogen concentration will rise in the battery rooms; (2) Open DC breakers to minimize loads on 2R22-S016 and 2R22-S017. C. (1) Battery Chargers will trip on high temperature; (2) Start Emergency Exhaust Fans 2Z41-C014 and 2Z41-C015. D. (1) Battery Chargers will trip on high temperature; (2) Open DC breakers to minimize loads on 2R22-S016 and 2R22-S017. Page: 32 of 100 4128/2009

33. Which ONE of the following knobs can be used to completely shut off the fuel supply to a running Plant Hatch Emergency Diesel Generator? A. LOAD LIMIT B. SYNINDICATOR C. SPEED DROOP D. SYNCHRONIZER Page: 33 of 100 4/28/2009

34. Following a LOCAILOSP on Unit 1, the following sequence occurs: o The "IA" and "IB" EDGs start o The" 1C" EDG fails to start When the EDG output breakers close, pumps start in this sequence: o Time = 0 sec "IA" Core Spray pump starts o Time =0.5 sec "IC" RHR pump starts o Time = 10 sec "ID" PSW pump starts o Time = 12 sec "IA" and "ID" RHR pumps start o Time = 22 sec "IA" PSW pump starts Which ONE of the following correctly completes both of the statements below concerning the proper load sequencing of the "IA" and "IB" EDGs? The "IA" EDG load sequence was (1) The "IB" EDG load sequence was (2) A. (1) correct (2) correct B. (1) correct (2) NOT correct C. (1) NOT correct (2) correct D. (1) NOT correct (2) NOT correct Page: 34 of 100 4/28/2009

35. Unit 2 experiences a rupture on the "2A" Core Spray (CS) suction piping in the Torus Area of the Reactor Building. The following annunciators are alarming (not a complete list of all alarming annunciators) o TORUS S-E AREA INSTR SUMP LVL HIGH (657-089-2) o RB S-E DIAGONAL FLOOR DRN SUMP LEVEL HIGH-HIGH (657-034-2) The following valve alignment exists: o 2T45-FOO2 "Torus N-E and S-E Outboard Sump Isol Valve" is open o 2T45-F003 "Torus N-E and S-E Inboard Sump Isol Valve" is open Which ONE of the following completes BOTH of these statements? If NO operator action is taken, the flow of water to the Radwaste facility (1) automatically isolate as Torus area water levels continue to increase. IAW 34AR-657-034-2, "RB S-E DIAGONAL FLOOR DRN SUMP LEVEL HIGH-HIGH", 2T45-F002, "Torus N-E and S-E Outboard Sump Isol Valve" is required to be (2) A. (1) will (2) open B. (1) will (2) closed C. (1) will NOT (2) open D. (1) will NOT (2) closed Page: 35 of 100 4/28/2009

36. A Turbine Building fire protection sprinkler system actuation causes the fire main header pressure to lower to 98 psig. Assuming that this is the LOWEST pressure achieved, which ONE of the following predicts how the fire pumps respond? A. Only the electric fire pump starts. B. Only the "A" and "B" diesel fire pumps start. C. Only the electric fire pump and the "A" diesel fire pump starts. D. "A" and "B" diesel fire pumps and the electric fire pump starts. Page: 36 of 100 4/28/2009

37. Unit 1 is operating at 63% power with both Reactor Feedwater pumps in service. o Recirculation pump speeds are both at 63% o Steam flow is 7.56 Mlbmlhr o The "IA" Condensate Booster pump (CBP) trips o The" 1C" CBP automatically starts. o The "IA" Reactor Feedwater pump trips due to low suction pressure. o The "IB" Reactor Feedwater pump continues to operate. o +23 inches is the lowest Reactor Water Level during the transient With no operator action, the final speed of the Reactor Recirculation pumps will be _ _. A. 33% B. 53% C. 61% D. 63% Page: 37 of 100 4128/2009

38. Unit 1 is experiencing a Loss of Offsite Power (LOSP). The following conditions exist: o The "lA" Emergency Diesel Generator (EDG) failed to start o An operator is dispatched to locally start the "lA" EDG o All "Control Power On" lights on lR43-P003A are illuminated Which ONE of the following choices completes the following statements for locally starting the EDG and flashing the generator field using the lR43-POO3A EDG Control Switch IAW 34AB-R43-00l-l, Diesel Generator Recovery. The "lA" EDG Control Switch must be placed in the (1) position prior to depressing the "START" push-button. The EDG Control Switch must be in the (2) position to enable the Generator Field Flash circuit. A. (1) "REMOTE" (2) "AT ENG" B. (1) "REMOTE" (2) "REMOTE" C. (1) "AT ENG" (2) "AT ENG" D. (1) "AT ENG" (2) "REMOTE" Page: 38 of 100 4128/2009

39. Unit 2 was operating at 100% power. o A loss of 2R22-S016 (125/250VDC flAfI) occurs o Subsequently a Main Turbine trip occurs Which ONE of the following completes both of these statements? The Main Generator PCBs (1) The station service 4160 VAC buses (2) transfer to their alternate source. A. (1) will still automatically open (2) will still automatically B. (1) must be manually opened (2) will still automatically C. (1) will still automatically open (2) will NOT automatically D. (1) must be manually opened (2) will NOT automatically Page: 39 of 100 4128/2009

40. Unit 1 is at 100% power. o The Main Turbine automatically trips due to a problem with the turbine lube oil system. When the Main Turbine trips, the Main Generator will trip (1) This Main Generator trip arrangement protects the turbine from (2) A. (1) immediately (2) overspeeding B. (1) immediately (2) bearing damage

c. (1) seconds later (2) overspeeding D. (1) seconds later (2) bearing damage Page: 40 of 100 4128/2009

41. Unit 2 was operating at 100% for one year when a spurious scram occurred due to surveillance testing. The following conditions exist five minutes after the scram: o All rods fully inserted o MSNs open o Auxiliary steam loads still in service Which ONE of the following is the expected main turbine bypass valve position and the corresponding inventory makeup that is required to maintain level constant within the normal level band? A. 1 bypass valve will be fully open. The required makeup is within the capacity of one CRD pump. B. 1 bypass valve will be fully open. The required makeup exceeds the capacity of one CRD pump. C. 1 bypass valve will be controlling, varying between 0 - 50% open. The required makeup is within the capacity of one CRD pump. D. 1 bypass valve will be controlling, varying between 0 - 50% open. The required makeup exceeds the capacity of one CRD pump. Page: 41 of 100 4/28/2009

42. Unit 2 is operating at 90% power o Unit 2 Drywell (DW) pressure is 0.5 psig. o At 10:00 DW pressure begins going up at 0.05 psiglminute Which ONE of the following completes the following statement IAW Tech Spec Limiting Condition for Operation (LCO) 3.6.1.4, Drywell Pressure? The EARLIEST time that an entry into a Required Action Statement (RAS) based on DW pressure is required is (1) and DW pressure is required to be restored to within limit no later than (2) from entering the RAS. A. (1) 10:03 (2) 15 minutes B. (1) 10:03 (2) 1 hour C. (1) 10:26 (2) 15 minutes D. (1) 10:26 (2) 1 hour Page: 42 of 100 4/28/2009

43. Unit 1 is operating at 90% power. o A Safety Relief Valve (SRV) inadvertently opened causing Suppression Pool water temperature to increase o Suppression Pool water temperature reaches 97°P before operators are able to close the SRV IAW 34AB-T23-003-1, "Torus Temperature Above 95°P, which ONE of the following describes the required Residual Heat Removal (RHR) Suppression Pool Cooling alignment? A. Place only one loop of RHR in Suppression Pool cooling, and the RHR heat exchanger is required to be isolated prior to starting the RHR pump. B. Place only one loop of RHR in Suppression Pool cooling, and the RHR heat exchanger is NOT required to be isolated prior to starting the RHR pump. C. Place all available RHR loops in Suppression Pool cooling, and the RHR heat exchanger is required to be isolated prior to starting the RHR pumps. D. Place all available RHR loops in Suppression Pool cooling, and the RHR heat exchanger is NOT required to be isolated prior to starting the RHR pump. Page: 43 of 100 4/28/2009

44. Unit 2 is in an Anticipated Transient Without a Scram (ATWS), with reactor water level (RWL) being controlled between -155 to -185 inches and reactor pressure is at 900 psig. Which ONE of the following identifies if a Safety Limit value has been exceeded and if adequate core cooling exists? A Tech Spec Safety Limit value (1) been exceeded and lAW Plant Specific Technical Guidelines (EOP Bases), adequate core cooling (2) exist. A. (1) has (2) does B. (1) has (2) does NOT C. (1) has NOT (2) does D. (1) has NOT (2) does NOT Page: 44 of 100 4128/2009

45. An evacuation of the Main Control room has occurred. o The Unit 1 reactor was not scrammed prior to leaving the Control Room. o SPDS is NOT available. Which ONE of the following choices completes both statements IAW 31 RS-OPS-OOl-l, "Shutdown From Outside Control Room," Guidance is given to locally scram the reactor by tripping the Scram Discharge Volume (SDV) (1) This procedure provides guidance to confirm Reactor shutdown by visually verifying that each (2) A. (1) Thermal Level Switches (2) SDV Vent and Drain valve is CLOSED B. (1) Thermal Level Switches (2) RCV Scram Inlet and Outlet valve is OPEN

c. (1) Float Level Switches (2) SDV Vent and Drain valve is CLOSED D. (1) Float Level Switches (2) RCV Scram Inlet and Outlet valve is OPEN Page: 45 of 100 4128/2009

46. Unit 2 has a loss of RBCCW that results in ONLY one pump running. Which ONE of the following identifies the reason that the 2P42-F033 and 2P42-F034 valves are directed to be closed IAW 34AB-P42-001-2, "Loss ofRBCCW"? Note: 2P42-F033, RBCCW Supply to 158' Elevation and Above Isolation" 2P42-F034, "RBCCW Supply to RBCCW Loads Below 158' Elevation Isolation" These actions are required to ensure that _ _ _ _ _ _ __ A. the Control Rod Drive pump has cooling B. the Reactor Recirculation pumps are adequately cooled C. the RBCCW Surge Tank is isolated D. the RBCCW pump is protected from run-out conditions Page: 46 of 100 4/28/2009

47. Unit 2 is operating at 100% power. o 2P52-F565, "Rx Bldg Inst N2 To Non-Int Air El185 Isol Vlv", has been tagged in the closed position. o Unit 2 experiences a loss of all Unit 2 Station Service Air Compressors. o The air cross-tie valve between Unit 1 and Unit 2 cannot be opened due to a bent stem. Which one of the following predicts the final MSIV positions with respect to the availability of a pneumatic supply? A. The Inboard and Outboard MSlVs will remain OPEN. B. The Inboard and Outboard MSlVs will eventually drift CLOSED. C. The Inboard MSlVs will remain OPEN; The Outboard MSlVs will eventually drift CLOSED. D. The Inboard MSlVs will eventually drift CLOSED; The Outboard MSlVs will remain OPEN. Page: 47 of 100 4128/2009

48. Unit 2 is operating at 100% power. o Nitrogen (N2) is being added to the Unit 2 Drywell (DW) from the Unit 1 N2 Storage Tank 34S0-T48-002-2, "Containment Atmosphere Control and Dilution System" section 7.3.1, "Alternate Primary Containment Nitrogen Makeup From CAD loop A, Unit 1 or Unit 2 N2 Storage Tank" is being used to add the N2. o 2T48-Fl13, "Nitrogen to DW isolation valve" is OPEN o 2T48-Fl14, "Nitrogen to DW isolation valve" is OPEN o DW venting using Standby Gas Treatment is in progress o A fault in 2C71-P001, "RPS Power Dist Panel" results in a loss ofthe"2A" Reactor Protection System (RPS) bus o It will take 8 hours to restore the "2A" RPS bus If the operator stationed at the 2H11-P657 panel does NOT take any action, which ONE of the following describes the operational implications for the DW? A. N2 addition to the DW will continue and a loss of DW cooling will eventually occur due to high DW pressure. B. N2 addition to the DW will continue and DW cooling will remain in operation indefinitely. C. N2 addition to the DW will automatically isolate and DW cooling will remain in operation indefinitely. D. N2 addition to the DW will automatically isolate and a simultaneous loss of DW cooling will occur. Page: 48 of 100 4128/2009

49. Unit 2 was in Mode 5 when a Loss of Shutdown Cooling (SDC) occurred. Which ONE of the following identifies a required local action from Attachment 4, "Shutdown Cooling Loop Preparation for hnmediate Service", of 34AB-E11-00l-2, "Loss of Shutdown Cooling" and the associated reason for that required action? (Assume the "2A" loop of RHR is being place in SDC) A. OPEN the breaker for 2E11-F007A, "Minimum Flow Valve" to ensure a minimum flow path is available during pump start-up. B. OPEN the breaker for 2E11-F007 A, "Minimum Flow Valve" to ensure that a flow path exists during the discharge piping flush. C. CLOSE the SDC Condensate flush supply valves, 2E11-F083 & 2E11-F084, when flow noise stops in the SDC suction pipe to ensure that the Suppression Pool level is NOT increased. D. CLOSE the SDC Condensate flush supply valves, 2E11-F083 & 2E11-F084, when flow noise stops in the SDC suction pipe because the suction piping is full of water. Page: 49 of 100 4128/2009

50. An irradiated fuel bundle is on the Unit 2 Refueling Bridge Main Grapple, which is in the "FULL-UP" position, and can NOT be lowered due to an equipment malfunction. o The Fuel Pool Transfer Canal seals deflate which causes Fuel Pool water level to decrease to its lowest possible level o Only the 2D21-K601A and 2D21-K601M Area Radiation Monitors (ARM) red TRIP lights illuminate and these two ARMs will not reset. Which ONE of the following predicts the Fuel Pool level and how the Main Control Room Environmental Control (MCREC) system is affected. Fuel Pool Water level will (1) the top of the Fuel Bundle and the MCREC system will (2) A. (1) remain above (2) remain in Normal Mode B. (1) remain above (2) align to the Pressurization Mode C. (1) go below (2) remain in Normal Mode D. (1) go below (2) align to the Pressurization Mode Page: 50 of 100 4128/2009

51. A steam line break inside containment has occurred on Unit 1. o Drywell pressure is steady at 10.5 psig o Drywell or Torus sprays have NOT yet been initiated Which ONE of the following describes the effect of the steam line break on Torus water temperature? A. The saturation temperature of the Torus water will be lower than at normal operating conditions because of the non-condensable gases. B. The Torus water temperature will initially heat up evenly throughout the Torus due to the design of the downcomers. C. The Torus water temperature will heat up directly under the area of the DW leak due to more energy is being distributed directly to the torus water in that area. D. The Torus water average temperature indication is unreliable until suppression pool cooling is established. Page: 51 of 100 4/28/2009

52. 31EO-EOP-107-2, "ALTERNATE RPV PRESSURE CONTROL" is in progress. o The HPCI system is being used to control reactor pressure. o The 2E41-R612, "HPCI flow controller," is in automatic, with the setpoint at 3000 gpm. To INCREASE the reactor cooldown rate (CDR), the operator is required to use _ __ and lAW 31EO-EOP-107-2. A. 2E41-R612, "HPCI flow controller," RAISE the setpoint B. 2E41-R612, "HPCI flow controller," LOWER the setpoint C. 2E41-FOll, "Test to CST VLV," throttle it in the CLOSE direction D. 2E41-FOll, "Test to CST VLV," throttle it in the OPEN direction Page: 52 of 100 4128/2009

53. A transient has occurred on Unit 2 with the following plant conditions: o RPV pressure .... .... ............ 960 psig o RWL ..... ...... ....... ............... -80 inches o Drywell Pressure. ......... .... 1.2 psig o Torus water temperature .. 1200 P IAW the EOP PC flowchart and 34S0-E11-01 0-2, "RHR System," which ONE of the following completes the following sentence? To place Suppression Pool Cooling in service, the Containment Spray Vlv Control (LOCA Override) switch required to be placed to the MANUAL position and the MAXIMUM required loop flow through the heat exchanger is _ __ A. is; 17,000gpm B. is; 11 ,500 gpm C. is NOT; 17,000 gpm D. is NOT; 11,500 gpm Page: 53 of 100 4/28/2009

54. Unit 2 was at 100% power when a pipe break occurred inside the Drywell (DW). The following conditions now exist: o Drywell Pressure: ...... ......... ................... 8 psig o Bulk Average Drywell Temperature: .... 245°P Which ONE of the following completes the following statement? IAW 31EO-EOP-IOO-2, "Miscellaneous Emergency Overrides", the"2A" DW Chiller _ __ A. is NOT allowed to be restarted because overriding the high DW pressure isolation has the potential for increased off-site release rates B. is NOT allowed to be restarted because at this DW temperature the potential for a rupture in the DW coolers exist C. is allowed to be restarted. The operator must first place the LOCA override switch to "BYPASS" and then reset the 86 Lockout relay at the DW Chiller breaker D. is allowed to be restarted. The operator must first reset the 86 Lockout relay at the DW Chiller breaker and then place the LOCA override switch to "BYPASS" Page: 54 of 100 4/28/2009

55. Unit 2 is operating at 100% power when a Loss of Coolant Accident occurs. o The High Pressure Coolant mjection system is being used to control RPV water level. o The "2A" RHR pump is placed in Suppression Pool Cooling o Torus level ..................................... 135 inches o "2A" RHR pump flow .................... 7,000 gpm o Torus temperature .......................... 225°P o Suppression Chamber Pressure ...... 8 psig Which ONE of the following choices completes this statement? 

             "2A" RHR pump operation is in the _ _ _ region of the RHR NPSH Limit graph and Reference provided A. safe; flow must be maintained at or below its current flow rate B. safe; flow is required be increased to maximize suppression pool cooling C. unsafe; reducing flow will NOT restore operation to the safe area of the graph D. unsafe; reducing flow to 5,000 gpm will restore operation to the safe area of the graph Page: 55 of 100                                                                                  4/28/2009

56. Unit 2 was operating at 100% power, when a Loss of Coolant Accident (LOCA) occurred. o Drywell pressure: 3.7 psig. o Reactor pressure has decreased to 285 psig. Which ONE of the following predicts the expected control panel flow indication IAW 31EO-EOP-01O-2, "RC Flowchart"? Based on these conditions, with no additional operator actions, _ _ _ _ will have indication of flow to the reactor vesseL A. NEITHER Core Spray nor RHR B. BOTH Core Spray and RHR

c. ONLY Core Spray D.ONLYRHR Page: 56 of 100 4128/2009

57. Unit 2 is operating at 100% power. The "A" Reactor Core Isolation Cooling (RCIC) Pump Room Cooler (2T41-B004A) is operating with its control switch in the "RUN" position. When will the "2T41-B004B" RCIC Pump Room Cooler automatically start? A. ONLY when RCIC is started. B. ONLY due to high RCIC room temperature. C. It requires EITHER, a high RCIC room temperature OR a RCIC start. D. It requires BOTH, a high RCIC room temperature AND a RCIC start. Page: 57 of 100 4128/2009}}

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