ML13008A554
| ML13008A554 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/03/2013 |
| From: | NRC/RGN-II |
| To: | Progress Energy Carolinas |
| References | |
| ES-401 | |
| Download: ML13008A554 (85) | |
Text
ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:
Date: Facility/Unit:
Region: I El II El III El IV El ReactorType: WE] CE El BWEI GEE1 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. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicants Signature Results Examination Value Points Applicants Score Points Applicants Grade Percent
- - - - - - - - - - (0 0 0 N) - Z N) N) N) N) 4 () N) - C) (00) -40) O 3 () N) -
C z
Co Cfl - 4 . 4 4 . . -c. .. 4 (A) (A) (A) (A) (A) (A) (A) (A) (A) N) N) N) N)
- 0) 0) 0) 0) 0) 0) 0) 0) 0) (3) (3) (31 (3) (3) (31 (31 (31 (31 1 --4 4 4 0) 0(00) 40) (3) . (A) N)
(3) N) P (00) 0) (31 4 (A) N) -
- 1. Unit Two is operating at rated power when the 2A CRD pump trips.
The 2B CRD pump has been started.
The following CRD conditions exist:
CRD CHARGING WTR PRESS HI is in alarm CRD flow rate is at 30 gpm Cooling water differential pressure is 18 psid Which one of the following choices completes the statements below?
The CRD CHARGING WTR PRESS HI annunciator setpoint is set to alarm when charging water pressure is (1) lAW 20P-08, Control Rod Drive Hydraulic System Operating Procedure, to clear this alarm the procedure will direct (2)
A. (1) 1510 psig (2) throttling closed C12-FOI4B, CRD Pump 2B Discharge Isolation Valve B. (1) 1510 psig (2) throttling closed C12-PCV-F003, Drive Pressure Vlv C. (1) 275 psid above reactor pressure (2) throttling closed C12-FOI4B, CRD Pump 2B Discharge Isolation Valve D. (1) 275 psid above reactor pressure (2) throttling closed C12-PCV-F003, Drive Pressure Vlv Page 1 of 75
- 2. Which one of the following identifies the power supply to 2C RHR Pump?
A.E1 B. E2 C.E3 D.E4 Page 2 of 75
- 3. RHR Loop A is operating in the Shutdown Cooling mode of operation with the following parameters:
RHRSW Pump 2A Operating RHRSW Flow 2000 gpm RHR Pump 2A Operating RHR Loop A Flow 6000 gpm Which one of the following choices completes the statements below?
The required operator action to lower the cooldown rate lAW 20P-17, Residual Heat Removal System Operating Procedure, is to (I)
The effect of this action is that heat exchanger shell to tube differential pressure will (2)
A. (I) throttle open El l-F048A, HX 2A Bypass Valve (2) rise B. (1) throttle open El l-F048A, HX 2A Bypass Valve (2) lower C. (1) throttle closed El l-PDV-F068A, HX 2A SW Disch Vlv (2) rise D. (1) throttle closed Ell-PDV-F068A, HX 2A SW Disch Vlv (2) lower Page 3 of 75
- 4. Unit Two is in Mode 3 with shutdown cooling in service when a loss of 2D RHRSW Booster pump occurs.
Both RHR pumps and 2B RHRSW pump continue to operate.
The operator observes annunciator RHR HXA/B Disch Cig Wtr Temp Hi in alarm and the RHR HX service water outlet temperature is indicating 185°F.
Which one of the following choices completes the statements below?
Continued operation with this alarm in will cause (1) lAW the APP, the operator is required to (2)
A. (1) overheating of the RHR Pumps (2) raise RHRSW flow B. (1) overheating of the RHR Pumps (2) throttle open E11-FOO3B, HX2B Outlet Vlv C. (1) short term seismic qualification concerns with the RHRSW system (2) raise RHRSW flow D. (1) short term seismic qualification concerns with the RHRSW system (2) throttle open El 1-FOO3B, HX 2B Outlet Vlv Page 4 of 75
- 5. Unit Two is operating at rated power when the circuit breaker on I 20V Distribution Panel 32A to the NUMAC Steam Leak Detection Monitor B21-XY-5948A and 5949A trips.
Which one of the following identifies the effect of this condition on the HPCI system?
A. E41-F002, HPCI Inboard Steam Line Isolation Valve, will immediately auto-isolate.
B. E41-F003, HPCI Outboard Steam Line Isolation Valve, will immediately auto-isolate.
C. The area temperature isolation signal is disabled for the E41-F002, HPCI Inboard Steam Line Isolation Valve. E41-F002 remains open.
D. The area temperature isolation signal is disabled for the E41-F003, HPCI Outboard Steam Line Isolation Valve. E41-F003 remains open.
Page5of75
- 6. A transient has occurred on Unit One causing the following plant conditions:
Drywell pressure 12 psig Reactor water level 65 inches Reactor pressure 360 psig Which one of the following choices completes the statement below?
E21-FOO5A, Core Spray A Inboard Injection Valve, is (1) , and E21-FO3IA, Mm Flow Bypass Valve, is (2)
A. (1) open (2) open B. (1) open (2) closed C. (1) closed (2) open D. (1) closed (2) closed Page6of75
- 7. An ATWS has occurred on Unit One and reactor water level deliberately lowered lAW LPC. The following conditions exist:
Reactor Water Level maintained between LL4 and TAF Reactor Power 9%
Reactor Pressure 960 psig SLC Tank Level 2800 gallons SLC Pumps Both operating Which one of the following choices completes the statements below?
Adequate mixing of the boron with reactor water (1) assured at this level.
Under the current conditions the time for the SLC tank to reach 0% would be approximately (2) minutes.
A. (1) is (2) 32 to 34 B. (1) is (2) 65 to 68 C. (1) is NOT (2) 32to34 D. (1) is NOT (2) 65 to 68 Page 7 of 75
- 8. Unit Two is in a hydraulic ATWS with the following plant conditions:
Reactor power 31%
Mode Switch RUN Which one of the following additional conditions will prevent the operator from resetting RPS and inserting a manual scram prior to the LEP-02, Section 3 jumper installation with the given conditions?
A. SDV HI-HI LEVEL RPS TRIP annunciator sealed in.
B. Reactor water level is at 170 inches.
C. IRM A UPSCALE/INOP and IRM B UPSCALE/INOP annunciators sealed in.
D. B21-F022A, Inboard MSIV and B21-F028D, Outboard MSIV, closed.
Page 8 of 75
- 9. Unit One is at rated power. Reactor Engineering has completed performance of OPT-UI .9, LPRM Calibration. The TIPs are currently located at the indexer.
Which one of the following choices completes the statements below?
The TIPS Indexer is located in the (I)
While the TIPS are being withdrawn to the inshield position the expected control room annunciator(s) is(are) (2)
A. (I) TIP Room (2) Area Rad Rx Bldg High and Tip Room High Rad B. (1) TIP Room (2) Tip Room High Rad ONLY C. (I) Drywell (2) Area Rad Rx Bldg High and Tip Room High Rad D. (I) Drywell (2) Tip Room High Rad ONLY Page 9 of 75
- 10. Which one of the following choices completes the statements below?
The (1) varies the sensitivity levels as the IRM range switches are operated.
The IRM Channel Range Correlation Adjustment is required to be performed prior to range (2)
A. (1) voltage preamplifier (2) 3 B. (1) voltage preamplifier (2) 7 C. (1) pulse height discriminator (2) 3 D. (1) pulse height discriminator (2) 7 Page 10 of 75
- 11. Unit Two is in the process of a reactor startup lAW OGP-02, Approach to Criticality and Pressurization of the Reactor, following a refueling outage.
The followin SRM readin3 are indicated:
All IRMs are on range 4.
Which one of the following identifies the expected plant response with the shorting links installed?
A. Alarm ONLY.
B. Alarm and rod block ONLY.
C. Alarm, rod block and 1/2 scram.
D. Alarm, rod block and full scram.
Page 11 of 75
An operator is preparing to bypass another LPRM on APRM 1.
Which one of the following predicts the expected annunciator(s) that will alarm after bypassing this LPRM?
A. APRM Trouble ONLY.
B. APRM Upscale Trip/mop ONLY.
C. APRM Trouble and Rod Out Block.
D. APRM Upscale Trip/lnop and Rod Out Block.
Page 12 of 75
- 13. Unit One is operating at rated power.
Which one of the following identifies the impact of a loss of DC Switchboard IA, if any, on Reactor vessel level control using RCIC?
RCIC (1) automatically initiate on a subsequent low level signal.
The E51-F045, Turbine Steam Supply Vlv, (2) auto-close on a subsequent high level signal.
A. (1) will (2) will B. (1) will (2) will NOT C. (1) will NOT (2) will D. (1) will NOT (2) will NOT Page 13 of 75
- 14. Unit Two operating at rated power when a small break LOCA occurs simultaneously with a Loss of Off-site Power to both units.
Reactor water level 35 inches Reactor pressure 600 psig and stable DGI, DG2 and DG3 Tied to their respective busses DG4 Locked out 2A RHR pump failed to auto-initiate 2D RHR pump failed to auto-initiate 2A Core Spray pump tripped on overcurrent 2B Core Spray pump Under clearance ADS Inhibit Switches in AUTO Based on the conditions above, which one of the following identifies:
(1) the current status of Auto Depress Timers Initiated annunciator and (2) a subsequent operator action that will result in the ADS valves opening?
A. (1) The annunciator is in alarm (2) Starting 2A RHR Pump.
B. (1) The annunciator is in alarm (2) Starting 2D RHR Pump.
C. (1) The annunciator is NOT in alarm (2) Starting 2A RHR Pump.
D. (1) The annunciator is NOT in alarm (2) Starting 2D RHR Pump.
Page 14 of 75
- 15. Unit Two is operating at rated power with B Loop Suppression Pool Cooling in service with cooling maximized.
A plant transient results in the following stable conditions:
DW pressure 3 psig Reactor pressure 400 psig Reactor water level 50 inches Which one of the following choices completes the statement below?
In order to re-establish Suppression Pool Cooling lAW the SPC hard card, (1) must be restarted and the use of RHR SW Booster Pumps B & D LOCA Override Switch (2) be required.
A. (1) the 2BID RHR and 2BID RHR SW pumps (2) will B. (1) the 2BID RHR and 2BID RHR SW pumps (2) will NOT C. (1) ONLY the 2BID RHR SW Pumps (2) will D. (1) ONLY the 2B/D RHR SW Pumps (2) will NOT Page 15of75
- 16. A LOCA has occurred on Unit Two. Subsequently a steam line leak occurs on the RCIC system. The following plant conditions are present 10 minutes after the steam line leak occurred:
Reactor water level 95 inches Drywell pressure 3.5 psig Reactor pressure 900 psig RCIC Steam Line Tunnel Ambient Temp 170°F The CRS orders the RO to manually isolate RCIC.
Which one of the following describes the effect when the RCIC Manual Isolation System B pushbutton is depressed on the E51-F007 and F008, Inboard and Outboard Steam Supply Isolation valves?
A. E51-F007 and F008 auto-close.
B. ONLY E51-F008 auto-closes.
C. ONLY E51-F007 auto-closes.
D. E51-F007 and F008 remain open.
Page 16of75
- 17. Unit I is operating at rated power.
An operator is performing the valve operability checks portion of OPT-08.2.2B, LPCI/RHR System Operability Test Loop B, and is preparing to stroke the El I -FOl 6B, Drywell Spray Otbd lsol VIv, and El I -F021 B, Drywell Spray lnbd Isol Vlv.
Which one of the following completes the statements below lAW OPT-08.2.2B?
The El l-FO16B and El l-FO2IB (1) both be opened at the same time during the performance of this test.
When Ell-FO2IB is stroked during this portion of the test, some water (2) enter the Drywell through the spray header.
A. (1) can (2) may B. (1) can (2) will NOT C. (1) can NOT (2) may D. (I) can NOT (2) will NOT Page 17 of 75
- 18. Which one of the following choices completes the statements below lAW PCCP and 001-37.8, Primary Containment Control Procedure Basis Document?
In the PC/P leg, suppression pool spray must be initiated before (1) pressure reaches 11.5 psig.
If suppression pool spray is NOT initiated before reaching 11 .5 psig, then (2)
A. (1) drywell (2) a crack could occur at the junction of the downcomer and the vent header B. (1) drywell (2) air will be drawn in through the vacuum relief system to deinert the primary containment C. (1) suppression chamber (2) a crack could occur at the junction of the downcomer and the vent header D. (1) suppression chamber (2) air will be drawn in through the vacuum relief system to deinert the primary containment Page 18 of 75
- 19. During Unit Two power operation, a power supply loss results in a reactor scram. The operator notes the following MSIV indications immediately after the scram:
Inboard DC solenoid white light OUT Inboard AC solenoid white light LIT Outboard DC solenoid white light OUT Outboard AC solenoid white light OUT Which one of the following identifies the power supply that has been lost?
A. Division I AC Power B. Division I DC Power C. Division II AC Power D. Division II DC Power Page 19 of 75
- 20. Which one of the following identifies the valves that can be operated from the RSDP and identifies the effect that a loss of MCC IXDB will have on the Unit One SRVs operations from the RSDP?
The control switches for SRVs B, E, and (1) are located on the RSDP.
These valves (2) be operated from the RSDP following a loss of MCC IXDB.
A. (1) F (2) can B. (1) F (2) can NOT C.(1)G (2) can D.(1)G (2) can NOT Page 20 of 75
- 21. Unit Two is operating at rated power with no activities in progress.
A leaking SRV has resulted in rising Suppression Pool temperature.
Which one of the following choices completes the statement below?
When Suppression Pool temperature first exceeds (1) entry into (2) is required.
A. (1) 95°F (2) PCCP ONLY B. (1) 105°F (2) PCCP ONLY C. (1) 95°F (2) PCCPandRSP D. (1) 105°F (2) PCCP and RSP Page 21 of75
- 22. Unit Two is at 20% power with main turbine roll in progress lAW 20P-26, Turbine System Operating Procedure. Turbine speed is 900 RPM and slowly rising.
The following turbine journal bearing vibration readings are observed on TSI-XR-640:
Bearing #1 5 mils Bearing #6 10 mils Bearing #2 5 mils Bearing #7 11 mils Bearing #3 6 mils Bearing #8 13 mils Bearing #4 7 mils Bearing #9 11 mils Bearing #5 8 mils Bearing #10 10 mils Which one of the following:
- 1) predicts the plant response and
- 2) identifies required operator action(s), if any, lAW 20P-26?
A. (1) An automatic turbine trip will occur.
(2) Manually scram the reactor.
B. (1) An automatic turbine trip will occur.
(2) The reactor is NOT required to be manually scrammed.
C. (1) An automatic turbine trip will NOT occur.
(2) Manually scram the reactor and then trip the turbine.
D. (1) An automatic turbine trip will NOT occur.
(2) Manually trip the turbine, the reactor is NOT required to be manually scrammed.
Page 22 of 75
- 23. Unit Two is operating at 35% power.
Which one of the following choices completes the statements below concerning the CO-FV-49, SJAE Condensate Recirculation Valve?
On a loss of the pneumatic supply to CO-FV-49, condensate system flow will (1)
On a loss of control power to the CO-FV-49, condensate system flow will (2)
A. (1) increase (2) increase B. (1) increase (2) remain the same C. (1) remain the same (2) remain the same D. (1) remain the same (2) increase Page 23 of 75
- 24. Unit Two is operating at 60% power with Reactor Feed Pump (REP) 2A running and REP 2B unavailable. REP A Manual/DECS selector switch is in the DECS position.
The operator observes the following:
RFP A Control Trouble alarm is received DECS Control light for REP A on XU-1 is out Which one of the following choices completes the statements below?
REP 2A speed will (1)
The operator can control REP speed by (2)
A. (1) lower to 2550 rpm (2) operating the REP Raise/Lower control switch on XU-1 B. (1) lowerto 2550 rpm (2) placing the REP A Speed Controller in Manual and adjusting the output demand C. (1) NOT change (2) operating the REP Raise/Lower control switch on XU-1 D. (1) NOT change (2) placing the REP A Speed Controller in Manual and adjusting the output demand Page 24 of 75
- 25. Unit One drywell pressure is slowly rising and venting of the suppression chamber is being performed lAW lOP-I 0, Standby Gas Treatment System Operating Procedure.
SBGT system valve status:
1-CAC-V172, Supp Pool Purge Exh Vlv Open 1-CAC-V22, Torus Purge Exh Vlv Open 1-VA-I D-BFV-RB, Reactor Building SBGT Train IA Inlet Valve Closed 1-VA-I H-BFV-RB, Reactor Building SBGT Train I B Inlet Valve Closed Which one of the following choices completes the statements below concerning the predicted plant response if drywell pressure reaches 1 .5 psi 9 and reactor water level lowers to 160 inches and then stabilizes?
Both I-CAC-V172 and I-CAC-V22 valves (I)
Both I-VA-i D-BFV-RB and 1-VA-i H-BFV-RB valves (2)
A. (1) auto-close (2) remain closed B. (I) auto-close (2) auto-open C. (I) remain open (2) remain closed D. (I) remain open (2) auto-open Page 25 of 75
- 26. Unit One is operating at rated power with Standby Gas Treatment (SBGT) system controls aligned as follows:
Train A in PREF A Train B in STBY B Off-Site Power is lost.
DGI and DG2 tie to their respective busses.
RPV water level lowers to 115 inches and then stabilizes.
Containment parameters and radiation levels are normal.
Which one of the following identifies how SBGT Train A and B will respond?
A. SBGT Train A only will start.
B. SBGT Train B only will start.
C. Both SBGT Train A and B will start.
D. Both SBGT Train A and B remain off.
Page 26 of 75
- 27. Unit Two is operating at rated power when a 230 kV Transformer Bus Lockout occurs.
Which one of the following identifies the electrical bus that will remain de-energized with no operator actions?
A. 4160 Bus 2B B. 480 V MCC WTA C. 4160 Bus Common B D. 480 V MCC CWA-Bus A Page 27 of 75
- 28. Unit Two is operating at rated power when a Primary UPS Inverter malfunction results in an overvoltage on the inverter output.
Which one of the following choices completes the statements below?
The UPS Distribution Panel 2A (1) lAW the APPs, the required operator action is to place the UPS Distribution Panel 2A on (2)
A. (1) remains energized (2) MCC2CA B. (1) remains energized (2) the standby UPS inverter C. (1) is de-energized (2) MCC2CA D. (1) is de-energized (2) the standby UPS inverter Page 28 of 75
- 29. Which one of the following completes the statements below regarding 125/250 VDC Station Distribution?
During an equalize charge, the charger output voltage to the battery will be at a (1) voltage than when in the float mode.
The 125 VDC batteries are sized to supply emergency power at a 150 amp rate for (2) hours.
A. (1) lower (2) 8 B. (1) lower (2) 10 C. (1) higher (2) 8 D. (1) higher (2) 10 Page 29 of 75
- 30. DGI was running in Control Room Manual for the performance of OPT-I 2.2A, No. I Diesel Generator Monthly Load Test, and loaded to 2100 KW.
Subsequently off-site power was lost.
Which one of the following choices completes the statements below after the system has stabilized?
The current mode of DGI governor is in (1) mode of operation.
DGI frequency is slightly (2) 60 Hz.
A. (1) droop (2) less than B. (I) droop (2) greater than C. (I) isochronous (2) less than D. (1) isochronous (2) greater than Page 30 of 75
- 31. A loss of offsite power occurs on Unit Two.
Unit One is at rated power.
Which one of the following choices completes the statements below?
If DG3 failed to auto-start and additional power is needed to support the EOPs the required operator action isto crosstie (1) lAW OAOP-36.1, Loss of Any 4160V Buses or 480V E-Buses.
If a low lube oil pressure occurs on DG4, it (2) trip.
A. (1) EltoE3 (2) will B. (1) E4toE3 (2) will C. (1) EltoE3 (2) will NOT D. (1) E4toE3 (2) will NOT Page 31 of75
- 32. Unit One was operating at rated power with AOG-HCV-102, AOG System Bypass Valve, control switch in AUTO.
Subsequently, several annunciators began alarming, including:
UA-03 4-2, Process Off-Gas Rad Hi-Hi UA-03 5-4, Process OG Vent Pipe Rad Hi-Hi UA-48 5-2, AOG System Disch Rad High UA-48 6-2, AOG Building Radiation High Which one of following annunciators is also triggered by the same radiation monitor that will prevent the AOG System Bypass Valve from being manually opened?
A. UA-03 4-2 B. UA-03 5-4 C. UA-48 5-2 D. UA-48 6-2 Page 32 of 75
- 33. Which one of the following identifies the power supply to the Main Stack Radiation Monitor?
A. Powered from Unit One UPS ONLY.
B. Powered from Unit Two UPS ONLY.
C. Normally powered from Unit One UPS, can be transferred to Unit Two UPS.
D. Normally powered from Unit Two UPS, can be transferred to Unit One UPS.
Page 33 of 75
- 34. Unit Two is operating at rated power when a large unisolable steam leak occurs in the turbine building. Annunciator TURB BLDG VENT RAD HIGH has been received.
Which one of the following choices completes the statements below?
The required action lAW RRCP is to (1) lAW 001-37.10, Radioactivity Release Control Procedure Basis Document, the basis forthisactionisto (2)
A. (1) place Turbine Bldg Ventilation in the recirculation line-up (2) ensure the Turbine Building envelope is maintained at a negative pressure B. (1) place Turbine Bldg Ventilation in the recirculation line-up (2) terminate a large unfiltered volume discharge flow path C. (1) start an additional Turbine Building Ventilation Exhaust Fan (2) ensure the Turbine Building envelope is maintained at a negative pressure D. (1) start an additional Turbine Building Ventilation Exhaust Fan (2) terminate a large unfiltered volume discharge flow path Page 34 of 75
- 35. The control room receives annunciator Rx Bldg Static Press Duff-Low due to a microburst thunderstorm.
The operator observes that the VA-Pl-1 297, Reactor Bldg Neg Pressure, on Panel XU3 is reading 0 inches H20.
Which one of the following predicts the system response?
Reactor Building ventilation:
A. supply and exhaust fans will auto trip, SBGT system does NOT auto-start.
B. supply and exhaust fans will auto trip, SBGT system auto-starts.
C. exhaust fan vortex dampers will throttle open.
D. supply fan vortex dampers will throttle closed.
Page 35 of 75
- 36. Unit One is at rated power.
Unit Two is at 48% power in single recirculation loop operation.
Which one the following choices completes the statement below concerning the Minimum Critical Power Ratio (MCPR) safety limit for Unit One and Unit Two?
MCPR shall be greater than or equal to (1) for Unit One.
MCPR shall be greater than or equal to (2) for Unit Two.
A. (I) 1.11 (2) 1.12 B. (1) 1.11 (2) 1.13 C. (1) 1.12 (2) 1.12 D. (1) 1.12 (2) 1.13 Page 36 of 75
- 37. Unit Two is at rated power with the following plant conditions:
SJAE Train A is in full load operation CWIPs A, B, and D are in operation CW Isol Valves Mode Selector switch is in the B position The following annunciators are received:
CW Screen A Duff-High or Stopped CW Screen Duff Hi-Hi Exhaust Hood A Vacuum Low Exhaust Hood B Vacuum Low Then CW Pump A Trip is received and CW Screen A Duff-High or Stopped annunciator clears.
The AC verifies that the screens are in fast mode of operation.
Which one of the following identifies the required action(s) lAW OAOP-37.O, Low Condenser Vacuum?
A. Ensure CW Isol Valves Mode Selector switch is in the C position.
B. Place SJAE A and B Trains in half load operation.
C. Start CWIP C which is limited to two consecutive attempts.
D. Restart CWIP A which is limited to two consecutive attempts.
Page 37 of 75
- 38. Unit Two as ooersn at ra: ower e an eecnca fault occurred.
The ope itor pem ad the immde:e opera or actions and observes the following eectricaI rcication a r the tran&ent:
Which one of the foFo ing ident as the cause of the &ectrical transient?
A. UAT ockout B. SAT Lockout C. 2B Bus Lockout D. Main Generator Lockout Page 38 of 100
- 39. The following conditions exist on Unit Two:
Bus E4 125 VDC control power normal supply breaker has tripped If a severe overcurrent condition subsequently occurs on 2B CRD pump motor windings, which one of the following identifies the breaker(s) that will trip?
(Assume no operator action taken)
A. 2-E4-AK8, CRD pump 2B breaker.
B. 2-E4-AJ9, BOP to E Bus slave breaker ONLY.
C. 2C-AC8, BOP to E Bus master breaker ONLY.
D. Both 2C-AC8, BOP to E Bus master and 2-E4-AJ9, BOP to E Bus slave breakers.
Page 39 of 75
- 40. Unit Two is operating at rated power.
At 12:15:00 the following annunciators are received:
Stat Coolant Inlet Flow-Low Loss of Stat Coolant Trip Ckt Ener Reactor power has been lowered lAW OENP-24.5, Reactivity Control Planning.
At 12:16:00 Main Generator amperes are 17,814 amps.
Assuming no further operator action, which one of the following indicates the expected plant response?
The Main Generator will trip at:
A. 12:17:00.
B. 12:18:00.
C. 12:18:30.
D. 12:19:30.
Page 40 of 75
- 41. Which one of the following conditions meet the definition of Shutdown Under All Conditions Without Boron?
All rods inserted except:
A. nine rods at position 02.
B. two rods which are at position 04.
C. one rod at position 02 and one rod at position 24.
D. ten rods at position 02 and one rod at position 48.
Page 41 of 75
- 42. Unit Two is at rated power when the following conditions are observed:
Reactor water level is 180 inches Steam Flow indicates 12.76 Mlbs/hr Feed Flow indicates 12.05 Mlbs/hr RFPT speed indications are:
[2 RFAS I725 2RFBSI732 RFPA *RFPB With conditions continuing to degrade, which one of the following actions is required to restore and maintain normal level lAW OAOP-23.0, Condensate/Feedwater System Failures?
A. Place the Master Feedwater Controller in MANUAL and restore normal level.
B. Place the A REP Feedwater Controller in MANUAL and restore normal level.
C. Place the B RFP MANUAL/DFCS switch in MANUAL and restore normal level.
D. Place both REP Feedwater Controllers in MANUAL and balance the REP speed.
Page 42 of 75
- 43. A LOOP has occurred on Unit Two with the following plant conditions:
HPCI Failed RCIC Under Clearance SLC Injecting with Demin Water CRD Flow maximized lAW SEP-09 ADS Inhibited Reactor Water Level 36 inches and stable Reactor Pressure 950 psig and stable Suppression Pool Level -26 inches Drywell Pressure 2 psig and rising slowly Drywell Temperature 200°F and rising slowly (Reference Provided)
Which one of the following choices identifies the required action lAW PCCP?
A. Initiate Drywell Sprays ONLY lAW SEP-02.
B. Start all available DW Coolers lAW SEP-10.
C. Perform Emergency Depressurization lAW RVCP.
D. Initiate Suppression Pool Sprays ONLY lAW SEP-03.
Page 43 of 75
- 44. Which one of the following completes the statement below lAW OAOP-32.O, Plant Shutdown From Outside Control Room?
The reason that OAOP-32.O includes steps to open all RPS EPA breakers in the cable spreading area is:
A. to ensure that all PCIS group isolations occur and SBGT is running during the performance of the procedure.
B. for a situation where a manual scram could not be performed prior to exiting the control room.
C. to ensure RPS components are not damaged from an RPS Bus electrical perturbation.
D. for protection against over feeding the RPV.
Page 44 of 75
I:: - -
45.
On SPDS Screen 500, Radioactivity Release Control, the Off-Site Whole Body Dose Rate limit will first be exceeded (a red Alarm condition) at which one of the following values?
A. 450 mRem I Yr B. 500 mRem / Yr C. 2700 mRem I Yr D. 3000 mRem/Yr Page 45 of 75
- 46. Unit One is performing a reactor startup.
The following events occur prior to rolling the main turbine:
Bus I D experiences a fault and trips Unit One NSW header ruptures in the Service Water Building All Unit One Service Water pumps supplying the NSW Header are manually tripped lAW OAOP-18.O, Nuclear Service Water System Failure.
The crew has completed all actions of OAOP-18.O.
Which one of the following identifies the status of the Diesel Generator(s) and the cooling water supply?
A. ONLY DGI is running with cooling water supplied from the Unit Two NSW Pumps.
B. ONLY DGI is running with cooling water supplied from the Unit One CSW Pumps.
C. Both DGs I & 3 are running with cooling water supplied from the Unit Two NSW Pumps.
D. DGI is running with cooling water supplied from the Unit One CSW Pumps and DG3 is running with cooling water supplied from the Unit Two NSW Pumps.
Page 46 of 75
- 47. Which one of the following completes both statements lAW OAOP-20.O, Pneumatic (Air/Nitrogen) System Failures?
Backup nitrogen system will automatically initiate when the non-interruptible air header pressurefirstlowersto (1) psig.
One reason that the Backup Nitrogen system automatically initiates is to ensure a pneumatic supply will be maintained to the (2)
A. (1) 105 (2) MSIVs B. (1) 105 (2) Hardened Wetwell Vent Valves C. (1) 95 (2) MSIVs D. (1) 95 (2) Hardened Wetwell Vent Valves.
Page 47 of 75
- 48. Unit Two is in Cold Shutdown and the following conditions existed:
Loop A of SDC in service RWCU in service Subsequently all offsite power is lost.
The operators are executing OAOP-15.O, Loss of Shutdown Cooling.
The E11-F009, RHR Shutdown Cooling lnbd Isol Vlv, cannot be re-opened.
Reactor water level is being maintained between 200-220 inches.
Which one of the following parameters is allowed to be used for vessel coolant temperature monitoring lAW OAOP-15.0?
A. Reactor vessel pressure.
B. Vessel Bottom Drain Temperature.
C. Reactor recirculation loop temperature.
D. Bottom head metal temperature.
Page 48 of 75
- 49. Which one of the following choices completes the statement below lAW OAOP-02.O, Control Rod Malfunction/Misposition, for a loss of CRD pumps?
If reactor pressure is (1) and CRD pressure cannot be restored to greater than or equal to 940 psig, immediately insert a manual reactor scram upon the receipt of the (2) HCU low pressure alarm.
A. (1) less than 950 psig (2) first B. (1) less than 950 psig (2) second C. (1) greater than or equal to 950 psig (2) first D. (1) greater than or equal to 950 psig (2) second Page 49 of 75
- 50. A core shuffle is in progress on Unit Two. After releasing a fuel assembly in the spent fuel pool the operator raises the main hoist to a safe elevation to pass through the transfer canal. The following indications on the refuel bridge are observed:
- Grapple Normal Up light is NOT illuminated.
- Hoist Loaded light is NOT illuminated.
- Boundary Zone Bypass light is illuminated.
While moving the refueling bridge to the core the refueling bridge movement abruptly stops.
Which one of the following identifies the reason the refueling bridge motion has automatically stopped?
A. Air has been lost to the refueling bridge.
B. Rod select power has been turned on.
C. A refuel floor ARM alarm has been received.
D. One full in (green) reed switch has failed.
Page 50 of 75
- 51. During an accident, Unit One plant conditions are:
Reactor pressure 500 psig Drywell pressure 20 psig Suppression chamber pressure 19 psig Suppression pool level - 42 inches Suppression pool temperature 160°F (Reference provided)
Which one of the following is the reason emergency depressurization is required?
A. Steam exists in the suppression chamber air space, which indicates that the pressure suppression feature is being bypassed.
B. The combination of high suppression chamber level and pressure is threatening the design boundary loading of the torus.
C. Suppression chamber level has lowered to the point of the downcomer elevations.
D. The suppression chambers heat capacity is being exceeded.
Page 51 of 75
- 52. Given the following plant conditions with RCIC in pressure control mode:
RCIC controller output 70%
E51-F022, Bypass to CST VIv Throttled RCIC Flow 300 gpm RCIC Discharge Pressure 1050 psig RPV pressure 810 psig, slowly lowering RCIC controller Automatic set @ 300 gpm Which one of the following identifies two independent actions that will stabilize RPV pressure?
Throttle the E51-F022 in the (1) direction, or by (2) the RCIC Flow Controller auto setpoint.
A. (1)open (2) lowering B. (1)open (2) raising C. (1)closed (2) lowering D. (1)closed (2) raising Page 52 of 75
SUPPRESSION POOL TEMP REACHES lOP ESTABLISH CTMT COOLING REQUIREMENTS PER TABLE 3, REDUCING LPCI INJECTION FLOW IF NECESSARY 53 RCL-44 lAW 01-37.4, Reactor Vessel Control Procedure Basis Document, which one of the following identifies why the step RCIL-44 is performed?
A. To prevent exceeding the Heat Capacity Temperature Limit.
B. To prevent exceeding primary containment design temperature.
C. To maintain NPSH to low pressure ECCS pumps.
D. To maintain cooling to HPCI and RCIC.
Page 53 of 75
- 54. Which one of the following identifies a consequence of DW average air temperature reaching 341°F lAW 001-37.8, Primary Containment Control Procedure Basis Document?
A. SRVs may not operate B. Drywell High Range Monitors are no longer reliable C. Hardened Wetwell Vent Valves may not operate D. CAC 4409 and 4410 Hydrogen Analyzers are no longer reliable Page 54 of 75
The following conditions exist:
Drywell Pressure 4.5 psig Reactor Water Level 95 inches and rising with Core Spray Reactor Pressure 280 psig Suppression Chamber level 5.5 inches CST level 20 feet Which one of the following identifies an injection source that must be secured lAW PCCP? (Assume no circuit alterations have been performed)
A. CRD B. RCIC C. HPCI D. Core Spray Page 55 of 75
Reactor water level 55 inches and rising Reactor pressure 150 psig Torus temperature 220°F Suppression Chamber pressure 10.5 psig Torus level - 43 inches 2A Core Spray pump flow 5000 gpm 2B Core Spray pump flow 2000 gpm 2A RHR Loop flow 17000 gpm (Reference provided)
Which one of the following identifies the ECCS pump(s) that is/are operating within the associated NPSH limit(s)?
A. 2B CS Pump ONLY B. 2A CS Pump and 2A RHR Loop ONLY C. 2ARHRLoopONLY D. 2B CS Pump and 2A RHR Loop ONLY Page 56 of 75
- 57. The plant has experienced a level transient which has caused the Reactor Recirculation Pumps to trip. Level stabilized at Reactor Recirculation Pump trip setpoint.
Which one of the following choices completes the statement below?
Under these conditions, natural circulation in the entire vessel (1) occurring because reactor water level is (2)
A. (1) is (2) above the jet pump suction B. (1) is (2) above the steam separator return to the downcomer region C. (1) is NOT (2) below the jet pump suction D. (1) is NOT (2) below the steam separator return to the downcomer region Page 57 of 75
- 58. A primary system is discharging into the reactor building with the following plant conditions:
1005 Main Condenser Vacuum is 24.5 inches HG One Circ Water Pump is running MSIVs remain open Reactor Building 20 temperature is 205°F Reactor Building 50 temperature is 165°F 1030 Reactor Building 20 temperature is 180°F.
Reactor Building 50 temperature is 165°F 1105 Engineering determines that the Reactor Building 50 has exceeded EQ envelopes.
(Reference provided)
Which one of the following is required by SCCP at 1105?
A. Perform emergency depressurization.
B. Operate bypass valves to coold own the reactor SI 00°F/hour.
C. Operate SRVs to cooldown the reactor at 100°F/hour.
D. Operate bypass valves to cooldown the reactor >100°F/hour, emergency depressurization is NOT required.
Page 58 of 75
- 59. An ATWS has occurred on Unit One.
The following ATWS actions have been performed:
Terminate and prevent actions have been completed Reactor water level has been lowered to 90 inches Table 3 conditions have NOT been met.
Reactor water level band of 60 to 90 inches has been established Which one of the following identifies why reactor water level was deliberately lowered to 90 inches lAW 001-37.5, Level/Power Control Procedure Basis Document?
A. Raise feedwater subcooling.
B. Increase the core boron concentration.
C. Reduce heat input to primary containment if the MSIVs close.
D. Minimize the possibility of large scale core oscillations.
Page 59 of 75
- 60. Which one of the following alarms is an entry condition into RRCP?
A. Service Wtr Effluent Rad High.
B. Area Rad RX Bldg High.
C. RBCCW Liquid Process Rad High.
D. Process Reactor Building Vent Rad High.
Page 60 of 75
- 61. Unit Two is at rated power with the plant air systems not crosstied.
The Unit Two air compressors have failed causing the following plant conditions:
U
-20u RB INSIR JR 4: RECEIVER 2A lnAlarm
-150 E:
-150 PRESS LOW 0
C N
RB INST JR In Alarm A 100 HOD RECEIVER 26 R HZ PRESS LOW 0
K R
-50 In Alarm 0
SERVICE AIR PRESS LOW InAlarm INSTRUMENT Ri1CE iR HEADER .4R HEADER PRESSURE PRESSURE
%-A-724-I Which one of the following identifies the required operator action lAW OAOP-20.O, Pneumatic (Air/Nitrogen) System Failures?
A. Insert a manual reactor scram.
B. Close lntrpt Air Isol Vlvs, lA-PV-722-1 &2 C. Open RNA-SV-5482, Div I Backup N2 Rack Isol VIv.
D. Open PNS-Cross-tie Valve PNS-SV-5804A, PNS-CS-5804B Page 61 of75
- 62. Which one of the following choices completes the statements below?
The Service Water to TBCCW MOVs (SW-V3 and V4) are powered from (1)
The Service Water to RBCCW MOVs (SW-V103 and V106) are powered from (2)
A. (1) 2F12E (2) 2F12E B. (1) 2F12E (2) E8/E7 C. (1) E8/E7 (2) 2F12E D. (1) E81E7 (2) E81E7 Page 62 of 75
- 63. Unit Two is at rated power with the following alignment for RBCCW:
2A RBCCW control switch in ON 2B RBCCW control switch in ON 20 RBCCW control switch in AUTO The 2D to E3 master breaker tripped spuriously and DG3 failed to auto-start.
Which one of the following identifies the expected response of the RBCCW pumps?
A. No RBCCW pumps are running.
B. ONLY the 2B RBCCW pump is running.
C. ONLY the 2C RBCCW pump is running.
D. 2B and 20 RBCCW pumps are running.
Page 63 of 75
- 64. The CRS has declared the Control Room Envelope Boundary inoperable.
A fire external to the control room has resulted in smoke intrusion into the control room.
The CRS has determined that control room evacuation is not necessary and has ordered the donning of Scott Air-Pak SCBAs by control room personnel.
Which one of the following indicates the approximate length of time each SCBA bottle will last lAW 001-01 .01, BNP Conduct of Operations Supplement?
A. 10 minutes B. One hour C. Two hours D. Four hours Page 64 of 75
- 65. Unit Two is operating at rated power when small oscillations due to unstable voltage regulation is observed.
Which one of the following choices completes the statements below lAW 20P-27, Generator and Exciter System Operating Procedure?
The first action required is to (1)
This action must be reported to the (2)
A. (1) place the generator voltage regulator in Manual (2) System Load Dispatcher B. (1) place the generator voltage regulator in Manual (2) Plant Transmission Activities Coordinator (PTAC)
C. (1) disable the Power System Stabilizer (PSS)
(2) System Load Dispatcher D. (1) disable the Power System Stabilizer (PSS)
(2) Plant Transmission Activities Coordinator (PTAC)
Page 65 of 75
- 66. Following a seven day break in work schedule an operator is assigned to an operating unit with the following work schedule.
Dayl 12 hours Day2 12 hours Day3 12 hours Day4 12 hours Day5 0 hours Day6 12 hours Day7 13 hours Day8 14 hours Day9 0 hours Which one of the following choices will ensure compliance lAW ADM-NGGC-0206, Managing Fatigue and Work Hour Limits, without requiring a waiver?
A. Take day I off.
B. Take day7 off.
C. Work only 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on day 7.
D. Work only 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> on day 8.
Page 66 of 75
- 67. Which one of the following identifies the reason lop-I 0, Standby Gas Treatment System Operating Procedure, prohibits venting the drywell and the suppression pool chamber simultaneously with the reactor at power?
This would cause the:
A. unnecessary cycling of torus to drywell vacuum breaker.
B. pressure suppression function to be bypassed.
C. unnecessary cycling of reactor building to torus vacuum breakers.
D. SBGT Train water seal to blow out of the trough.
Page 67 of 75
- 68. Unit One is in a refueling outage and the initial loading of fuel bundles around each SRM is complete.
Which one of the following completes both statements below lAW OFH-1 1, Refueling?
Fuel movement must be suspended when an SRM reading rises by a factor of (1) upon insertion of any single bundle OR if an SRM rises by a factor of (2) relative to the SRM baseline count rate.
A. (1) two (2) two B. (1) two (2) five C. (1) five (2) two D. (1) five (2) five Page 68 of 75
- 69. lAW OAI-147, Systematic Approach to Troubleshooting, which one of the following identifies the trouble shooting activities that must be approved by the Plant General Manager?
A. ONLY high risk activities (anytime).
B. ONLY those high risk activities that are performed during max/safe/gen periods of operation.
C. ALL medium and high risk activities that are performed during maxlsafe/gen periods of operation.
D. ALL high risk activities (anytime) and ONLY those medium risk activities that are performed during max/safe/gen periods of operation.
Page 69 of 75
- 70. Which one of the following meets the conditions required to be in MODE 4 lAW Technical Specifications?
A. Reactor Mode Switch in either Shutdown or Refuel and one reactor head bolt has been fully tensioned.
B. Reactor Mode Switch in either Shutdown or Refuel and all reactor head bolts have been fully tensioned.
C. Reactor Mode Switch in Shutdown and one reactor head bolt has been fully tensioned.
D. Reactor Mode Switch in Shutdown and all reactor head bolts have been fully tensioned.
Page 70 of 75
- 71. Unit Two is operating at rated power. Drywell leakage calculations are being performed lAW the CO DSR.
The 0800 drywell leakage calculations were:
Floor Drain Leakage 1.3 gpm Equipment Drain Leakage 3.5 gpm These leakage values have been constant for several days.
At 1200 the difference in integrator readings is:
Floor Drain 816 gallons Equipment Drain 960 gallons Which one of the following choices completes the statement below?
The calculated unidentified leakage is (1) which (2) within the limits of Technical Specifications LCO 3.4.4, RCS Operational Leakage.
A. (1) 3.4gpm (2) is B. (1) 3.4gpm (2) is NOT C. (1) 4.Ogpm (2) is D. (1) 4.Ogpm (2) is NOT Page 71 of75
- 72. Drywell pressure is 30 psig Suppression Pool Level is 4 feet Which one of the following completes the statement below?
lAW PCCP, when venting the primary containment, the (1) UNLESS (2)
A. (1) suppression pool is required to be vented first (2) alternate source term actions cannot be performed B. (1) suppression pool is required to be vented first (2) PCPL-A is reached C. (1) offsite release rates must be maintained below the ODCM release rate limit (2) alternate source term actions cannot be performed D. (1) offsite release rates must be maintained below the ODCM release rate limit (2) PCPL-A is reached Page 72 of 75
- 73. Access is required to a Unit One plant area for inspection.
Radiation levels in the area are 1100 Mrem/hr at 30 cm and 510 Rads/hr at one meter from the radiation source.
Which one of the following choices completes the statements below lAW OE&RC-0040, Administrative Controls for High Radiation Areas, Locked High Radiation Areas, and Very High Radiation Areas?
This area is required to be posted as a (1)
The MINIMUM approvals required to enter this area are the E&RC manager (or designee), Rad Protection Supervisor, and (2)
A. (1) Very High Radiation Area (2) Plant General Manager B. (1) Very High Radiation Area (2) Shift Manager C. (1) Locked High Radiation Area (2) Plant General Manager D. (1) Locked High Radiation Area (2) Shift Manager Page 73 of 75
74.
Which one of the following identifies the EOP flowchart symbol above lAW OEOP-O1-UG, EOP Users Guide?
A. Action Step B. Caution Step C. Critical Step D. Decision Step Page 74 of 75
- 75. Which one of the following choices completes the statements below lAW OFPPO31, Fire Brigade Staffing Roster and Equipment Requirements?
The Fire Brigade Advisor position (1)
The Fire Brigade Advisor (2) be diverted from supporting the Fire Brigade during OASSD-02 implementation.
A. (1) must be filled by an SRO (2) can B. (1) can be filled byan RO (2) can C. (1) must be filled by an SRO (2) can NOT D. (1) canbefilledbyanRO (2) can NOT Page 75 of 75
RO Written Exam Reference Index
- 1. OEOP-O1-UG, Users Guide, Attachment 5, Figure 1, Drywell Spray Initiation Limit
- 2. OEOP-O1-UG, Users Guide, Attachment 5, Figure 3, Heat Capacity Temperature Limit
- 3. OEOP-O1-UG, Users Guide, Attachment 5, Figure 5, Core Spray NPSH Limit
- 5. OEOP-O1-UG, Users Guide, Attachment 5, Figure 7, Pressure Suppression Pressure
- 6. OEOP-O1-UG, Users Guide, Attachment 10, Figure 22, Secondary Containment Area Temperature
ATTACHMENT 5 Page 16of28 FIGURE 1 Drywell Spray Initiation Limit 450 -a- r L1 400 zz 0
w 350 300 250 SAFE 200 150 100 50 5 15 25 35 45 55 65 75 0 10 20 30 40 50 60 70 DRYWELL PRESSURE (PSIG)
DRYWELL AVERAGE AIR TEMPERATURE MAY BE DETERMINED USING ATTACHMENT 4.
OEOP-O1-UG Rev. 60 Page 75 of 151
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ATTACHMENT 5 Page 22 of 28 FIGURE 6 RHR NPSH LJmit Li 290 0
LU 280 270 I
260 250 240 230 220 210 200 190 180 170 160 0 5,000 10,000 15,000 20,000 RHR PUMP FLOW (GPM)
SUBTRACT 0.5 PSIG FROM INDICATED SUPPRESSION CHAMBER PRESSURE FOR EACH FOOT OF WATER LEVEL BELOW A SUPPRESSION POOL WATER LEVEL OF -31 INCHES (-2.6 FEET).
- SUPPRESSION CHAMBER PRESSURE (CAC-PI-1257-2A OR CAC-PI-1 257-2B)
OEOP-01-UG Rev. 60 Page 81 of 151
ATTACHMENT 5 Page 23 of 28 FIGURE 7 Pressure Suppression Pressure
+2 I
0 Ui
> jZZZEEEZZEEZEEEE LU SAFE
-2 o_. -
z o
U) EZZZZZ_EE:UNSAFE U) -
LU - -
D 0
-8 0 10 20 30 40 SUPPRESSION CHAMBER PRESSURE (PSIG)
OEOP-O1-UG Rev. 60 Page 82 of 151
ATTACHMENT 10 Page 2 of 5 Secondary Containment Temperature and Radiation Limits FIGURE 22 Secondary Containment Area Temperature TABLE I AREA TEMPERATURE LIMITS PLANT PLANT STEAM LEAK INSTRUMENT MAX NORM MAX SAFE AUTO AREA LOCATION DETECTION NUMBER? OPERATING OPERATING GROUP DESCRIPTION CHANNEL? WINDOW VALUE (°F) VALUE (°F) ISOL LOCATION (NOTE 1)
N CORE N CORE PANEL XU-3 VA-TI-1603 120 175 N?A SPRAY SPRAY ROOM SCORE SCORE PANELXU-3 VA-TI-i604 120 175 N/A SPRAY SPRAY ROOM RWCU PUMP B21 -XY-5949A G31 -TE-NOl 6A ROOM A B21-XY-5949B G31-TE-NOI6B CH. Al-i RWCU PUMP B21-XY-5949A G31-TE-NOI6C RWCU G31-TE-NOI6D 140 225 3 ROOM B B21-XY-5949B CH. A2-i RWCU HX B21-XY-5949A G31-TE-NO16E ROOM B21-XY-5949B G31-TE-NO16F CH. A3-l N RHR B21-XY-5948A El 1-TE-NOO9A N RHR EQUIP ROOM CR A5-4 175 295 N/A PANEL XU-3 VA-TI-i 601 S RHR B21-XY-5948B El1-TE-NOO9B EQUIP ROOM CH. A5-4 175 295 N/A PANEL XU-3 VA-TI-1602 S RHR RCIC EQUIP B21-XY-5949A E51-TE-N023A ROOM B21-XY-5949B E5l-TE-N023B 165 295 5 CH. Ai-3 HPCI HPCI EQUIP B21-XY-5948A E41-TE-NO3OA ROOM B2i-XY-5948B E41-TE-NO3OB 165 4 CH. Al-i NOTE 1: MAX NORM OPERATING VALUE IS THE ANNUNCIATOR/GROUP ISOLATION SETPOINT WHERE APPLICABLE OEOP-01-UG Rev. 60 Page 140 of 151
ATTACHMENT 10 Page 3of5 Secondary Containment Temperature and Radiation Limits FIGURE 22 Secondary Containment Area Temperature (Cont)
TABLE 1 AREA TEMPERATURE LIMITS PLANT PLANT STEAM LEAK INSTRUMENT MAX NORM MAX SAFE AUTO AREA LOCATION DETECTION NUMBER! OPERATING OPERATING GROUP DESCRIPTION CHANNEL! WINDOW VALUE (°F) VALUE (°F) ISOL LOCATION (NOTE 1)
RCIC STM B21-XY-5949A E51-TE-N025A TUNNEL B21-XY-5949B E51-TE-N025B 190 295 5 STEAM CH. A3-3 TUNNEL HPCI STM B21-XY-5948A E51-TE-N025C TUNNEL B21-XY-5948B E51-TE-N025D 190 295 4 CH. A5-1 20 FT NORTH B21-XY-5948A B21-TE-5761A CH. A1-4 20 FT 20 FT SOUTH B21-XY-5948B B21-TE-5763B 140 200 N/A CH. A1-4 50 FT 50 FT NW B21-XY-5948A B21-TE-5762A CH. A2-4 140 200 N/A 50 FT SE B21-XY-5948B B21-TE-5764B CH.A2-4 REACTOR MULTIPLE ANNUNCIATOR WINDOW ALARM N/A 3,4, BLDG AREAS PANEL A-02 5-7 SETPOINT AND/OR 5
REACTOR MSIV ANNUNCIATOR WINDOW ALARM N/A 1 BLDG PIT PANEL A-06 6-7 SETPOINT NOTE 1: MAX NORM OPERATING VALUE IS THE ANNUNCIATOR/GROUP ISOLATION SETPOINT WHERE APPLICABLE OEOP-01-UG Rev. 60 Page 141 of 151