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(1 point) 1ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following plant conditions: Unit 1 has just reached 100% power following a refueling outage Unit 2 is at 100% power with 93 EFPD Which ONE of the following will result in the highest amount of Emergency Feedwater flow required to stabilize RCS temperature 5 minutes following the trip? | |||
A. Both Main Feedwater PumpsONLY trip on Unit 1 B. Both Main Feedwater Pumps ONLY trip on Unit 2 C. Loss of Offsite Power on Unit 1 D. Loss of Offsite Power on Unit 2 Page 1 of 75 Question: | |||
(1 point) 2ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor power = 100% 1RC-66 (PORV) is leaking past its seat Pressurizer temperature = 648 0F Quench tank pressure = 5 psig Reactor Building pressure = 0 psig Which ONE of the following describes the expected tailpipe temperature (°F) downstream of 1RC-66? | |||
A. 212 B. 228 C. 272 D. 648 Page 2 of 75 Question: | |||
(1 point) 3ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor tripped from 100% power due to SBLOCA 1A HPI Pump failed Subcooling Margin = 0°F stable Which ONE of the following is the reason the EOP directs increasing SG levels to the Loss of Subcooling Margin Setpoint level? | |||
A. Establish a large secondary side inventory in support of a rapid RCS cooldown. | |||
B. Establish a large secondary side inventory to ensure that a loss of coupling will NOT occur if a momentary loss of EFDW occurs. | |||
C. Ensure a secondary water level higher than the primary water level inside the SG tubes to establish boiler condenser mode heat transfe r D. Ensure a secondary side levelsufficient to minimize the consequences of a total loss of feedwater during boiler condenser mode heat transfer Page 3 of 75 Question: | |||
(1 point) 4ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor power = 50% stable 1B2 RCP is OFF Which ONE of the following would require immediate entry into AP/1/A/1700/016 (Abnormal Reactor Coolant Pump Operation)? | |||
A. OAC point O1A0061 (RCP 1A1 MTR INPUT POWER) in HI alarm B. OAC point O1A1579 (RCP 1A2 MTR LOWER AIR TEMP) in HI alarm C. 1SA-15/A5 (RC PUMP MOTOR 1B1 OIL POT LOW LEVEL) in alarm D. 1SA-6/D5 (PUMP 1B2 CAVITY PRESS HI/LOW | |||
) in alarm Page 4 of 75 Question: | |||
(1 point) 5ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor power = 100% | |||
Current conditions: | |||
LPI Flow Train A = 1800 gpm stable LPI Flow Train B = 1780 gpm stable Rule 2 (Loss of SCM) in progress. IMAs complete | |||
: 1) The SRO will direct actions from the __ (1) __ tab of the EOP. | |||
: 2) In accordance with Rule 2, performance of Rule 3 (Loss of Main or Emergency FDW) __ (2) __ required. | |||
Which ONE of the following completes the statements above? | |||
A. 1. LOSCM 2. is B. 1. LOSCM 2. is NOT C. 1. ICC 2. is D. 1. ICC 2. is NOT Page 5 of 75 Question: | |||
(1 point) 6ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Normal LPI decay heat removal in service Current conditions: Loss of offsite power occurs Power restored via CT-4 1A and 1B LPI Pumps NOT available Which ONE of the following describes the requirements to start the 1C LPI Pump? | |||
Manual reset of Load Shed is __(1)___ and starting of 1C LPI Pump is allowed after a MINIMUM of ___(2)__ seconds. | |||
A. 1. NOT required 2. 5 B. 1. required 2. 5 C. 1. NOT required 2. 30 D. 1. required 2. 30 Page 6 of 75 Question: | |||
(1 point) 7ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor trip has just occurred Total RCP seal injection flow = 0 gpm Running Component Cooling pump tripped Standby CC pump did not start Which ONE of the following describes the procedure whose performance is directed by the EOP and why? | |||
Initiate- | |||
A. AP/20 (Loss of CC) to restore Component Cooling B. AP/20 (Loss of CC) to ensure letdown is isolated C. AP/25 (SSF EOP) to align an alternate letdown flowpath D. AP/25 (SSF EOP) to align an alternate source of seal in jection Page 7 of 75 Question: | |||
(1 point) 8ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor power = 90% 1B Main Feedwater pump trips Current conditions: Reactor power = 70% decreasing RCS pressure = 2165 psig slowly decreasing Pressurizer level = 228 inches slowly decreasing Pressurizer temperature = 640°F slowly decreasing Pressurizer heater bank 1 (Group A and K) is ON Pressurizer heater banks 2, 3, and 4 are in AUTO and are OFF The pressurizer is ___(1)____ AND the pressurizer heater bank 2 ___(2)____. | |||
Which ONE of the following completes the statement above? | |||
A. 1. subcooled 2. will ener gize at 2145 psi g B. 1. subcooled 2. should be ener gized C. 1. saturated 2. will ener gize at 2145 psi g D. 1. saturated 2. should be energized Page 8 of 75 Question: | |||
(1 point) 9ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 2 conditions: Loss of all sources of Feedwater has occurred RCS Pressure = 2250 psig increasing Pressurizer level = 294 inches increasing ALL SCM's = 24°F slowly decreasing What is the: | |||
: 1) lowest RCS pressure (psig) that will require Rule 4 (Initiation of HPI Forced Cooling) to be performed? | |||
: 2) PRIMARY reason for reducing the number of operating RCP's in accordance with Rule 4? A. 1. 2300 2. Reduce the heat input to the RCS B. 1. 2300 2. Provide the ability to recover from HPI forced cooling and re-establish a Pressurizer bubble. | |||
C. 1. 2255 2. Reduce the heat input to the RCS D. 1. 2255 2. Provide the ability to recover from HPI forced cooling and re-establish a Pressurizer bubble. | |||
Page 9 of 75 Question: | |||
(1 point) 10ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 3 conditions: Reactor power = 100% | |||
Which ONE of the following will result in a Tech Spec LCO being NOT met? | |||
A. 3A SGTL rate = 160 gpd B. 3B Core Flood Tank level = 12.69 feet C. 3B Core Flood Tank pressure = 622 psig D. 4 gpm RCS leak identified as being through valve stem packing of 3HP-1 Page 10 of 75 Question: | |||
(1 point) 11ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: ALL sources of feedwater have been lost Rule 4 (Initiation of HPI Forced Cooling) is complete with outstanding IAAT's 1A HPI pump has failed HPI flow parameters are as indicated below In accordance with Rule 4, __(1)__ RCP('s) is/are operating and HPI flow __(2)__ required to be throttled. | |||
Which ONE of the following completes the statement above? | |||
A. 1. 1 2. is B. 1. 1 2. is NOT C. 1. 2 2. is D. 1. 2 2. is NOT Page 11 of 75 Question: | |||
(1 point) 12ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 Conditions:Initial conditions: Reactor Power = 100% ACB-4 closed Current conditions: Reactor trip CT-1 Locks out KHU-2 Emergency Lockout occurs Assuming no additional failures, which ONE of the following describes the first method used to restore power to Unit 1 MFB's? | |||
A. Automatically through ACB-3 B. Automaticall y through SL1 and SL2 C. Manually through ACB-3 in accordance with Enclosure 5.38 (Restoration of Power) of the EOP D. Manually through SL1 and SL2 in accordance with Enclosure 5.38 (Restoration of Power) of the EOP Page 12 of 75 Question: | |||
(1 point) 13ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Unit shutdown in progress Reactor power = 38% slowly decreasing LOOP (Switchyard Isolation) occurs | |||
: 1) Based on the conditions above, the status of the Main Turbine will be __(1)__ 5 minutes following the LOOP? | |||
: 2) ANYTIME the Main Turbine is tripped, ICS uses __(2)__ to control the Turbine Bypass Valves? | |||
Which ONE of the following completes the statements above? | |||
A. 1. tripped 2. Turbine Header Pressure B. 1. tripped 2. Steam Generator Outlet Pressure C. 1. NOT tripped 2. Turbine Header Pressure D. 1. NOT tripped 2. Steam Generator Outlet Pressure Page 13 of 75 Question: | |||
(1 point) 14ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions Reactor Power = 100% SASS in Manual while SPOC repairs Pressurizer Level 3 level transmitter 1HP-120 in AUTO selected to Pressurizer Level 1 Current conditions: Vital Power to ICCM Train A fails Which ONE of the following describes Pressurizer level control with 1HP-120? | |||
A. Selecting Pressurizer Level 2and depressing the AUTO pushbutton on 1HP-120 are required to restore automatic controlat setpoint B. Selectin g Pressurizer Le vel 2ONLY will restore automatic control at setpoint C. Manual control using 1HP-120 Bailey controller is all that is available D. Additional actions are NOT required since Automatic controlat setoint is retained Page 14 of 75 Question: | |||
(1 point) 15ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor power = 100% Instrument Air pressure = 85 psig decreasing AP/22 (Loss of Instrument Air) has been initiated Which ONE of the following | |||
: 1) is the higher Instrument Air pressure (psig) that would require an immediate manual Reactor trip in accordance with AP/22? | |||
: 2) states the reason AP/22 directs tripping the Main FDW pumps immediately after tripping the Reactor as described above? | |||
A. 1. 70 2. Controllin g FDW valves fail "as is" B. 1. 65 2. Controllin g FDW valves fail "as is" C. 1. 70 2. Controllin g FDW valves fail closed D. 1. 65 2. Controllin g FDW valves fail closed Page 15 of 75 Question: | |||
(1 point) 16ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: AP/34 (Degraded Grid) in progress Generator output = 850 MWe and 450 MVARs Generator Hydrogen Pressure = 60 psig Generator Output Voltage = 18.2 KV | |||
: 1) The Generator output __ (1) __ within the limits of the Generator Capability Curve. | |||
: 2) If the generator exceeds the Underfrequency Maximum Allowable Time given in AP/34 (Degraded Grid) the Main Turbine __ (2) __ automatically trip. | |||
Which ONE of the following completes the statements above? | |||
REFERENCE PROVIDED A. 1. is NOT 2. will B. 1. is NOT 2. will NOT C. 1. is 2. will D. 1. is 2. will NOT Page 16 of 75 Question: | |||
(1 point) 17ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 3 conditions: A brief loss of power has occurred Unit auxiliaries are being supplied from the switchyard via CT-3 Subsequent Actions tab in progress | |||
: 1) Subsequent Actions directs restarting __(1)__. | |||
: 2) The __(2)__ RCP will provide the best Pressurizer Spray. | |||
Which ONE of the following completes the statements above? | |||
A. 1. one RCP ONLY 2. 3A1 B. 1. one RCP ONLY 2. 3B1 C. 1. one RCP per loop 2. 3A1 D. 1. one RCP per loop 2. 3B1 Page 17 of 75 Question: | |||
(1 point) 18ILT44 ONS RO NRC Examination Oconee Nuclear Station In accordance with the EOP, which ONE of the following describes the instruments that are used when initially stabilizing RCS temperature following a Main Steam Line Break and states one of the reasons why they are used? | |||
A. Tcolds are used since Tech Specs specifies that Tcold is RCS temperature B. Tcolds are used since they are the coldest temperature and therefore most indicative of PTS issues C. CETC's are used since the resultant RCS cooldown may result in Tcold being off scale low D. CETC's are used since they are qualified instruments and are therefore more reliable in the hostile containment environment Page 18 of 75 Question: | |||
(1 point) 19ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Time = 1200 Reactor power = 100% 1A steam generator tube leak = 2.1 gpd stable RCS activity = 0.25 Ci/ml DEI increasing Current conditions: Time = 1400 NO change in 1A SG tube leak rate RCS activity = 0.65 Ci/ml DEI increasing Which ONE of the following describes the response of the radiation monitors between 1200 and 1400? | |||
A. 1RIA-59 (N-16 monitor) and 1RIA-40 (CSAE Off-gas) increased. | |||
B. 1RIA-16 (Main Steam Line Monitor | |||
) and 1RIA-40 increased. | |||
C. 1RIA-59 increased while1RIA-40 remained constant. | |||
D. 1RIA-16 increased while 1RI A-40 remained constant. | |||
Page 19 of 75 Question: | |||
(1 point) 20ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 2 condition:Initial conditions: Time = 0900 Reactor Startup in progress NI 1 & 2 = 370 cps NI 3 & 4 = 0 cps (out of service) ALL WR NI's = ~ 2.7 E-4% | |||
Current conditions: Time = 0901 NI 1 & 2 are inoperable Which ONE of the following describes: | |||
: 1) immediate actions required by Tech Spec 3.3.9 (Source Range Neutron Flux)? | |||
: 2) the reason for the actions described above? | |||
A. 1. Insert Control Rods to Group 1 at 50% withdrawn2. Prevents power increases when the primary power indication for the operator is not available. | |||
B. 1. Insert Control Rods to Group 1 at 50% withdrawn2. 2 dpm Startup Rate Control Rod Out Inhibit is no lon ger available C. 1. Fully insert all Control Rods2. Prevents power increases when the primary power indication for the operator is not available. | |||
D. 1. Fully insert all Control Rods2. 2 dpm Startup Rate Control Rod Out Inhibit is no longer available Page 20 of 75 Question: | |||
(1 point) 21ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor power = 92% decreasing Unit shutdown in progress per the SGTR tab | |||
: 1) In accordance with the SGTR tab and Enclosure 5.5 (Pzr and LDST Level Control), RCS makeup and letdown will be adjusted to maintain Pressurizer level betw een __ (1) __ inches. | |||
: 2) The reason for this Pzr level band is to provide adequate inventory to __ (2) __. | |||
Which ONE of the following completes the statements above? | |||
A. 1. 140 | |||
- 180 2. ensure Pzr heaters will remain covered if a subsequent reactor trip occurs B. 1. 140 | |||
- 180 2. accommodate system shrinkage during shutdown/cooldown from 18% power C. 1. 220 | |||
- 260 2. ensure Pzr heaters will remain covered if a subsequent reactor trip occurs D. 1. 220 - 260 2. accommodate system shrinkage during shutdown/cooldown from 18% power Page 21 of 75 Question: | |||
(1 point) 22ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor power = 100% | |||
Which ONE of the following will result in an AUTOMATIC trip of the Main Turbine? | |||
A. Bearing Oil Pressure = 5.5 psig B. Main Turbine speed = 1955 RPM C. EHC Hydraulic Oil pressure = 1210 psig D. EITHER Steam Generator Level = 93% OR Page 22 of 75 Question: | |||
(1 point) 23ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor power = 100% 1A GWD tank release in progress 1RIA-38 OOS Current conditions: Maintenance activities in the area result in an inadvertent loss of power to RM-80 skid of 1RIA-37 1SA8/B9 RM PROCESS MONITOR RADIATION HIGH in alarm 1SA8/B10 RM PROCESS MONITOR FAULT in alarm | |||
: 1) 1GWD-4 (A GWD TANK DISCHARGE) should __(1)__. | |||
: 2) The required Completion Time in SLC 16.11.3 (Radioactive Effluent Monitoring Instrumentation) for suspending the release by this pathway if not already isolated and both 1RIA-37 and 1RIA-38 become inoperable is __(2)__. | |||
Which ONE of the following completes the statements above? | |||
A. 1. remain open 2. immediatel y B. 1. automatically close 2. immediatel y C. 1. remain open 2. 1 hour D. 1. automatically close 2. 1 hou r Page 23 of 75 Question: | |||
(1 point) 24ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor power = 2% 1SA2/B11 (ICS AUTO POWER FAILURE) actuated 1SA2/B13 (ICS HAND POWER FAILURE) actuated Which ONE of the following describes: | |||
: 1) the level at which SGs will be maintained? | |||
: 2) how decay heat removal from the core is controlled? | |||
A. 1. 25 inches SUR 2. ADVs B. 1. 30 inches XSUR 2. ADVs C. 1. 25 inches SU R 2. TBVs D. 1. 30 inches XSUR 2. TBVs Page 24 of 75 Question: | |||
(1 point) 25ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Switchyard isolation occurs Current conditions: Shutdown of KHU's is desired Which ONE of the following states: | |||
: 1) if a Load Shed has occurred? | |||
: 2) the procedure that will be used to perform a remote shutdown of the KHU's? | |||
A. 1. Yes 2. OP/0/A/2000/041 (Keowee Modes of Operations | |||
) B. 1. No 2. OP/0/A/2000/041 (Keowee Modes of Operations | |||
) C. 1. Yes 2. OP/0/A/1106/019 (Keowee Hydro AtOconee | |||
) D. 1. No 2. OP/0/A/1106/019 (Keowee Hydro AtOconee | |||
) Page 25 of 75 Question: | |||
(1 point) 26ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: ES 1-8 have actuated LOCA CD tab in progress RCS pressure = 423 psig slowly decreasing 1A LPI Pump operating in the Piggyback alignment Which ONE of the following describes the: | |||
: 1) operational limitations on the operating LPI pump? | |||
: 2) pump(s) being protected by the above limitation? | |||
A. 1. Maximized to < 3100 gpm 2. LPI B. 1. Maximized to < 3100 gpm2. HPI C. 1. Maximized to < 2900 gpm2. LPI D. 1. Maximized to < 2900 gpm2. HPI Page 26 of 75 Question: | |||
(1 point) 27ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor trip from 100% due to a SBLOCA Reactor building pressure has peaked at 1.7 psig Subcooled margins are stable as indicated below Which ONE of the following describes how Feedwater will be used to mitigate this event? Steam Generator levels will be controlled at ________? | |||
A. 240 inches using Emergency Feedwate r B. 240 inches using Main Feedwater C. Loss of Subcooling Margin setpointusing Emergency Feedwate r D. Loss of Subcoolin g Margin setpointusin g Main Feedwate r Page 27 of 75 Question: | |||
(1 point) 28ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following describes: | |||
: 1) the design purpose of extending RCP coast down time with the flywheel? | |||
: 2) an expected core delta T (°F) 30 minutes following a lockout of 1TA and 1TB? | |||
A. 1. Helps prevent the core from reaching DNBR limits2. 35 B. 1. Helps prevent the core from reaching DNBR limits 2. 47 C. 1. Reduces the likelihood of a Reactor trip following a RCP trip at power 2. 35 D. 1. Reduces the likelihood of a Reactor trip following a RCP trip at powe r 2. 47 Page 28 of 75 Question: | |||
(1 point) 29ILT44 ONS RO NRC Examination Oconee Nuclear Station | |||
: 1) The Letdown Storage Tank contains approximately __(1)__ gallons of water per inch of level. | |||
: 2) The HIGHER Letdown Storage Tank level that will automatically open 1HP-24 and 1HP-25 is __(2)__ inches. | |||
Which ONE of the following completes the statements above? | |||
A. 1. 24 2. 38 B. 1. 24 2. 54 C. 1. 31 2. 38 D. 1. 31 2. 54 Page 29 of 75 Question: | |||
(1 point) 30ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 2 conditions: RCS Cooldown in progress 2B LPI cooler isolated due to cooler leak Which ONE of the following states the: | |||
: 1) LPI Decay Heat Removal mode that will be used for the INITIAL transition to LPI cooling? | |||
: 2) HIGHER RCS pressure (psig) that will allow aligning LPI in the Normal Decay Heat Removal alignment? | |||
A. 1. Switchover 2. 220 B. 1. High Pressure 2. 220 C. 1. Switchover 2. 115 D. 1. High Pressure 2. 115 Page 30 of 75 Question: | |||
(1 point) 31ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Rule 3 initiated Loss of Heat Transfer tab in progress Efforts underway to re-establish Steam Generator cooling 1SA-18/D1 (RC SYSTEM APPROACHING SATURATED CONDTIONS) in alarm 1SA-2/D3 (RC PRESS HIGH/LOW) in alarm Pressurizer level = 380" slowly increasing RCS pressure = 2240 psig slowly increasing SCM = 0°F Which ONE of the following states which additional EOP Rules (if any) should be initiated? | |||
A. NO additional rules required B. Rule 2 (Loss of SCM) ONLY C. Rule 4 (Initiation of HPI Forced Cooling) ONLY D. Rule 2 AND Rule 4 Page 31 of 75 Question: | |||
(1 point) 32ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 2 condition:Initial conditions: Unit startup in progress RCS temperature = 310°F slowly increasing Maintenance in progress in the area of 2DIB panelboard Current conditions: 2DIB breaker #24 (2RC-66 Pilot Valve DC solenoid power supply) is inadvertently opened Which ONE of the following describes: | |||
: 1) a Tech Spec Limiting Condition of Operation that is NOT met? | |||
: 2) the position of 2RC-66? | |||
A. 1. 3.4.9 (Pressurizer) 2. Open B. 1. 3.4.9 (Pressurizer) 2. Closed C. 1. 3.4.12 (LTOP) 2. Open D. 1. 3.4.12 (LTOP) 2. Closed Page 32 of 75 Question: | |||
(1 point) 33ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: | |||
Initial conditions Loss of all Feedwater HPI forced cooling initiated Quench Tank pressure = 40 psig increasing RCS activity indicates no fuel failures present Current conditions Quench Tank pressure = 3 psig stable Which ONE of the following describes the: | |||
: 1) reactor building RIA's response to the above conditions? | |||
: 2) valve(s) that will automatically close anytime 1RIA-49 reaches its HIGH alarm setpoint? | |||
A. 1. increases 2. 1LWD-1 AND 1LWD-2 B. 1. remains constant 2. 1LWD-1 AND 1LWD-2 C. 1. increases 2. 1LWD-2 ONLY D. 1. remains constant 2. 1LWD-2 ONLY Page 33 of 75 Question: | |||
(1 point) 34ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: 1SA-08/B-9 (PROCESS MONITOR RADIATION HIGH) 1RIA-50 in HIGH alarm CC Surge Tank level increasing | |||
: 1) The CC Surge tank __(1)__. | |||
: 2) If the RCS leakage threatens to overflow the associated waste tank, AP/1/A/1700/002 (Excessive RCS Leakage) will direct __(2)__. | |||
Which ONE of the following completes the statements above? | |||
A. 1. will overflow to the LAWT 2. trippin g the Reactor B. 1. will overflow to the LAWT2. initiatin g a shutdown usin g AP/1/A/1700/029 (Rapid Unit Shutdown | |||
) C. 1. will overflow to a floor drain which drains to the MWHUT2. trippin g the Reactor D. 1. will overflow to a floor drain which drains to the MWHUT 2. initiatin g a shutdown usin g AP/1/A/1700/029 (Rapid Unit Shutdown | |||
) Page 34 of 75 Question: | |||
(1 point) 35ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following states the automatic OPEN setpoints (psig) for 1RC-1 (Pzr Spray) and 1RC-66 (PORV) in Mode 1? | |||
1RC-1 1RC-66 A. 2205 2450 B. 2205 2500 C. 2255 2450 D. 2255 2500 | |||
Page 35 of 75 Question: | |||
(1 point) 36ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor power = 100% 1D RPS channel in Manual Bypass 1A RPS Thot RTD fails low Which ONE of the following: | |||
: 1) describes ALL 1A RPS functions affected by the failure? | |||
: 2) states if OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) requires tripping the 1A RPS channel? | |||
A. 1. RCS High Outlet Temperature ONLY2. yes B. 1. RCS High Outlet Temperature ONLY 2. no C. 1. RCS High Outlet Temperature and RCS Variable Low Pressure 2. yes D. 1. RCS High Outlet Temperature and RCS Variable Low Pressure 2. no Page 36 of 75 Question: | |||
(1 point) 37ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following describes how RCS Pressure signals are used to provide control signals to the Integrated Control System? | |||
A. Median Selected from one wide range pressure and two channels of RPS narrow range pressure (A and B) | |||
B. Median Selected from three channels of RPS narrow range pressure (A, B, and E) C. 2nd Max Selected from RPS narrow range pressures (A, B, C, & D) | |||
D. 2nd Min Selected from RPS narrow ran ge pressures (A, B, C, & D | |||
) Page 37 of 75 Question: | |||
(1 point) 38ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 2 conditions:Initial conditions: Reactor power = 100% | |||
Current conditions: MSLB occurs RCS pressure = 1580 psig slowly increasing RB peak pressure = 2.8 psig Which ONE of the following describes a valve that has received a signal to CLOSE? | |||
A. 2CC-7 B. 2HP-24 C. 2LWD-2 D. 2LPSW-1062 Page 38 of 75 Question: | |||
(1 point) 39ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following plant conditions:Time = 1200 Unit 1 Reactor power = 100% Unit 2 Reactor power = 100% ACB-4 closed Time = 1201 LOCA occurs on Unit 1 Switchyard Isolation occurs Which ONE of the following states the source of power being used to energize 1DIA at Time = 1202? | |||
A. Control Batteries B. KHU-1 C. KHU-2 D. CT-5 Page 39 of 75 Question: | |||
(1 point) 40ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 2 conditions:Time = 1200 Reactor in MODE 5 LPI aligned to normal Decay Heat Removal mode 2RIA-35 (Combined LPSW effluent leaving the Reactor Building and the Auxiliary Building) is isolated for repair Time = 1300 Large LPI Cooler leak in 2A LPI Cooler occurs Time = 1500 Actions to isolate the 2A LPI Cooler are initiated RCS temperature slowly increasing | |||
: 1) At Time = 1330 there __(1)__ an RIA alarm indicating the LPI Cooler leak? | |||
: 2) Entry into MODE 4 will occur when RCS temperature exceeds __(2)__°F? | |||
Which ONE of the following completes the statements above? | |||
A. 1. is 2. 200 B. 1. is 2. 250 C. 1. is NOT 2. 200 D. 1. is NOT 2. 250 Page 40 of 75 Question: | |||
(1 point) 41ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor is in MODE 5 RB Purge in progress Unit 1 vent activity increasing 1RIA-45 HIGH alarm fails to actuate at setpoint | |||
: 1) Automatic termination of RB Purge operation due to increasing activity __(2)__ available? | |||
: 2) Purge operation __(1)__ be allowed if the unit were in MODE 4. | |||
Which ONE of the following completes the statements above? | |||
A. 1. is 2. would B. 1. is 2. would NOT C. 1. is NOT 2. would D. 1. is NOT 2. would NOT Page 41 of 75 Question: | |||
(1 point) 42ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: 1A LPSW Pump trips Standby LPSW pump fails to start Which ONE of the following will begin to increase in temperature? | |||
ASSUME NO MANUAL ACTIONS ARE TAKEN A. Letdown B. Spent Fuel Pool C. Main Feedwater Pump oil temperature D. Primary Instrument Air Compresso rdischarge air temperature Page 42 of 75 Question: | |||
(1 point) 43ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following is the power supply for the Unit 2 Auxiliary Instrument Air System compressor? | |||
A. 2XD B. 2XF C. 2XP D. 2XS1 Page 43 of 75 Question: | |||
(1 point) 44ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor Power = 100% 1A MSLB inside containment | |||
Current conditions: Core SCM = 18°F stable RB Pressure = 17 psig slowly decreasing Which ONE of the following sets of actions is required by Enclosure 5.1 (ES Actuation) | |||
A. Take ES Channel 1 to manual AND open 1HP-20 B. Take ES Channel 1 to manual AND open 1HP-3 C. Override Odd Voters AND open 1HP-20 D. Override Odd Voters AND open 1HP-3 Page 44 of 75 Question: | |||
(1 point) 45ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor Power = 100% | |||
Which ONE of the following: | |||
: 1) describes the LOWER SG Operating Range level (%) that will result in an automatic trip of both Main Feedwater pumps? | |||
: 2) states if SG Operating Range level indications are temperature compensated? | |||
A. 1. 87 2. No B. 1. 87 2. Yes C. 1. 97 2. No D. 1. 97 2. Yes Page 45 of 75 Question: | |||
(1 point) 46ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor power = 50% slowly decreasing OAC Unavailable Computer Reactor Calculation Package NOT running Which ONE of the following: | |||
: 1) is the HIGHER power level (% Power) at which Tech Spec limits on Reactor Power Imbalance do NOT apply? | |||
: 2) describes how OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) directs the operator to determine if Imbalance limits specified in the COLR have been exceeded? | |||
A. 1. 35 2. by use of CR gages for Power Range NI's B. 1. 35 2. by performin g PT/1/A/1103/019 (Backup Incore Detector S ystem) C. 1. 15 2. by use of CR gages for Power Range NI's D. 1. 15 2. by performin g PT/1/A/1103/019 (Backup Incore Detector S ystem) Page 46 of 75 Question: | |||
(1 point) 47ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Mode 6 REFUELING is in progress All four SR NIs in service SR 1NI-1 and SR 1NI-3 are the designated NIs for Fuel Handling Current conditions: Power supply to SR 1NI-1 fails (0 vdc) | |||
Which ONE of the following describes the impact on refueling activities in accordance with OP/1/A/1502/007 (Operations Defueling/Refueling Responsibilities)? | |||
A. Allowed to continue because two other SR NIs remain in service B. Allowed to continue because SR NI-3 is still in service C. Required to be stopped until another SR NI is designated because other NIs are procedurall y allowed to be desi gnated D. Required to be stopped and cannot be resumed until SR 1NI-1 is returned to service because other NIs are NOT procedurally allowed to be designated Page 47 of 75 Question: | |||
(1 point) 48ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Time = 1200 Reactor Power = 40% stable following an instrument failure Turbine Header Pressure = 860 psig stable Feedwater, Reactor, and Main Turbine in Manual Time = 1300 ICS in Automatic Turbine Header Pressure = 860 psig stable Time = 1301 Reactor Trips prior to any additional Turbine Header Pressure setpoint adjustments Which ONE of the following is the pressure (psig) where the Turbine Bypass Valves will automatically control Steam Generator pressure? | |||
A. 885 B. 910 C. 985 D. 1010 Page 48 of 75 Question: | |||
(1 point) 49ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Time = 1200:00 Reactor power = 80% stable 1A and 1B CBP operating Time = 1201:00 1A CBP trips Feedwater Pump suction pressure = 225 psig slowly decreasing Time = 1203:00 Feedwater Pump suction pressure = 220 slowly increasing Which ONE of the following describes the: | |||
: 1) runback rate (%/min) inserted at Time = 1201:00 to ICS? | |||
: 2) procedure that will be directed by the CRS at Time = 1203:00? | |||
A. 1. 15 2. AP/1/A/1700/001 (Unit Runback | |||
) B. 1. 15 2. EOP C. 1. 20 2. AP/1/A/1700/001 (Unit Runback | |||
) D. 1. 20 2. EOP Page 49 of 75 Question: | |||
(1 point) 50ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor power = 100% Primary to Secondary leakage of 10 gpd has just been detected AP/1/A/1700/031 (Primary to Secondary Leakage) has been initiated | |||
: 1) In accordance with AP/31, opening the Turbine Building Sump (TSP) pump breakers prior to being ready to hang White Tags on the TBS pump breakers __(1)__ allowed. | |||
: 2) A sustained loss of power to 1RIA-54 will trip BOTH Turbine Building Sump Pumps __(2)__. | |||
Which ONE of the following completes the statements above? | |||
A. 1. is NOT 2. after a 2 minute time r B. 1. is NOT 2. immediatel y C. 1. is 2. after a 2 minute time r D. 1. is 2. immediatel y Page 50 of 75 Question: | |||
(1 point) 51ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Time = 1200 1A GWD tank pressure = 68 psig stable Current conditions: Time = 1205 1A GWD tank pressure = 18 psig rapidly decreasing Various Aux Building RIA's in alarm 1RIA-1 (Control Room Monitor) in HIGH alarm 1RIA-39 (CNTL RM Gas) in HIGH alarm AP/1/A/1700/018 (Abnormal Release of Radioactivity) in progress A and B Outside Air Booster Fans have been started Which ONE of the following: | |||
: 1) states if 1RIA-1 has a local alarm (do not count associated statalarm(s))? | |||
: 2) describes the areas being provided outside air via the Outside Air Booster Fans? | |||
A. 1. Yes 2. Control Room ONLY B. 1. No 2. Control Room ONLY C. 1. Yes 2. Control Room, Cable Rooms, and the Equipment Rooms D. 1. No 2. Control Room, Cable Rooms, and the Equipment Rooms Page 51 of 75 Question: | |||
(1 point) 52ILT44 ONS RO NRC Examination Oconee Nuclear Station 1RIA-59 setpoints are set by __(1)__ and the MINIMUM power level at which 1RI A-59is used to determine SGTL rate is __(2)__ (% power) in accordance with the EOP. | |||
Which ONE of the following completes the statement above? | |||
A. 1. I&E 2. 20 B. 1. I&E 2. 40 C. 1. ROs 2. 20 D. 1. ROs 2. 40 Page 52 of 75 Question: | |||
(1 point) 53ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following states all of the switchgear that can supply power to the B LPSW pump? | |||
A. 1TD ONLY B. 2TC ONLY C. 1TC or 2TD D. 1TD or 2TD Page 53 of 75 Question: | |||
(1 point) 54ILT44 ONS RO NRC Examination Oconee Nuclear Station Based on the graph above, which ONE of the following describes the EARLIEST time at which SA-141 (SA to IA Controller) will automatically open? | |||
A. 1207 B. 1210 C. 1212 D. 1215 Page 54 of 75 Question: | |||
(1 point) 55ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following describes what should be used in the case of a large Hydrogen leak to maintain Hydrogen concentration below the lower flammability limit in accordance with OP/1/A/1106/017 (Hydrogen System)? | |||
A. CO2 B. Water C. Halon D. Foam fire retardant Page 55 of 75 Question: | |||
(1 point) 56ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following is the LOWER limit on RCS activity that would require entry into AP/21 (RCS Activity)? | |||
A. Xe-133 = 0.25 µCi/gm B. Xe-133 = 1.0 | |||
µCi/gm C. DEI = 0.25 µCi/gm D. DEI = 1.0 µCi/gm Page 56 of 75 Question: | |||
(1 point) 57ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following activities complies withguidance contained in SOMP 1-2 (Reactivity Management)? A. Manual rod withdrawal during a Feedwater transient to stop a temperature decrease caused by an instrument failure B. Manually increasing Feedwater flow to stop an RCS pressure increase caused by an RCS temperature increase C. Manually raising one Loop FDW demand while lowering the other Loop FDW demand to control Tcold following an RCP trip D. Manually increasing turbine demand to adjust RCS temperature Page 57 of 75 Question: | |||
(1 point) 58ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following tags would be used ONLY for configuration control of 1HP-409 in accordance with NSD-500 (Red Tags/Configuration Control Tags)? | |||
A. White Tag B. MORT Ta g C. OORT Tag D. CORT Tag Page 58 of 75 Question: | |||
(1 point) 59ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 condition: Reactor in MODE 1 Which ONE of the following is the MINIMUM Pressurizer level (inches) that would require declaring Tech Spec 3.4.9 (Pressurizer) LCO NOT met in accordance with PT/1/A/0600/001 (Periodic Instrument Surveillance)? | |||
A. 240 B. 260 C. 285 D. 340 Page 59 of 75 Question: | |||
(1 point) 60ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor trip due to loss of both Main FDW pumps Instrument Air pressure = 0 psig Auxiliary Instrument Air pressure= 0 psig Which ONE of the following describes the status of 1FDW-315 and 1FDW-316? | |||
A. Available for Manual operation ONLYonce the air supply was lost B. Will be available for Automatic operation for a MINIMUM of 30 minutes from the loss of air supply C. Will be available for Automatic operation for a MINIMUM of 1 hou r from the loss of air suppl y D. Will be available for Automatic operation for a MINIMUM of 2 hours from the loss of air supply Page 60 of 75 Question: | |||
(1 point) 61ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 2 conditions:Initial conditions: Time = 1200 RCS temperature = 92°F stable RB Purge in progress 2RIA-45 HIGH alarm setpoint = 1520 cpm 2RIA-45 = 1342 cpm stable Current conditions: Time = 1205 2RIA-45 = 1520 cpm increasing Which ONE of the following describes: | |||
: 1) ALL valves that will CLOSE? | |||
: 2) 2RIA-46 reading (cpm) at time = 1200? | |||
A. 1. 2P R-1 through 2P R-6 2. Zero B. 1. 2P R-1 through 2P R-6 2. 1342 C. 1. 2PR-2 through 2PR-5 ONLY 2. Zero D. 1. 2P R-2 through 2P R-5 ONLY2. 1342 Page 61 of 75 Question: | |||
(1 point) 62ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following plant conditions: Venting the 1C LPI Pump in progress using the following RWP information: | |||
o Dose Alarm : 25 mrem o Dose Rate Alarm: 200 mrem/hr o Dose Alarm: Stop work - Exit Area - Notify RP o Unanticipated Dose Rate Alarm: Stop Work - Exit Area - Notify RP Which ONE of the following states the MAXIMUM time work can continue before complying with the RWP will require exiting the area? | |||
SEE PLAN VIEW PROVIDED Do NOT consider dose received while traveling to or from the job. | |||
A. 15 minutes B. 30 minutes C. 2 hours D. 4 hours Page 62 of 75 Question: | |||
(1 point) 63ILT44 ONS RO NRC Examination Oconee Nuclear Station Of the two tabs below, the __(1)__ tab of the EOP has a higher priority because __(2)__. | |||
Which ONE of the following completes the statement above? | |||
A. 1. LOSCM 2. prompt actions are required to ensure core coolin g is maintained B. 1. LOSCM 2. actions to initiate HPI injection are required prior to the RCS void fraction reaching 70%. | |||
C. 1. SGTR 2. a Reactor trip with a SGTR results in a direct release path for radionuclides to the environment D. 1. SGTR 2. actions to depressurize RCS to minimize SCM during a SGTR is a Time Critical Action that ma y not otherwise be met Page 63 of 75 Question: | |||
(1 point) 64ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor Power = 70% | |||
Which ONE of the following would require entry into the EOP? | |||
A. Condenser vacuum = 22.3" hg B. 1RIA-59 = 31.4 gpm C. 1B Main FDW pump trips D. 1A1 RCP trips Page 64 of 75 Question: | |||
(1 point) 65ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor power = 100% 1KVIA Panelboard de-energized Current conditions: MSLB inside the Reactor Building occurs Lowest RCS pressure = 1137 psig Reactor Building Pressure peaked at 32 psig Which ONE of the following describes ALL ES Actuation Logic Channels that have actuated? | |||
A. 1, 3, 5, 7 B. 2, 4, 6, 8 C. 1, 5, 7 ONLY D. 2, 6, 8 ONLY Page 65 of 75 Question: | |||
(1 point) 66ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Time = 1200 Reactor Power = 100% 1A MSLB inside the Reactor Building Current conditions: Time = 1201 Reactor Building Pressure = 3 psig increasing Which ONE of the following describes the operation of 1LPSW-18? | |||
A. It is NORMALLY fully open however it will receive a signal to open from ES-5 at 1201 B. It is NORMALLY throttled and will go fully open when it receives a signal to open from ES-5 at 1201 C. It is NORMALLY fully open however it will receive a signal to open from ES-5 at 1204 D. It is NORMALLY throttled and will go fully open when it receives a signal to open from ES-5 at 1204 Page 66 of 75 Question: | |||
(1 point) 67ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor power = 50% | |||
Current conditions: LBLOCA occurs 1TD de-energized 1B RBCU switch in OFF Which ONE of the following describes the status of the below listed Reactor Building Cooling Units five (5) minutes after ES actuates? | |||
ASSUME NO OPERATOR ACTIONS 1B RBCU 1C RBCU A. LOW LOW B. LOW OFF C. OFF LOW D. OFF OFF Page 67 of 75 Question: | |||
(1 point) 68ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following plant conditions: SBLOCA has occurred on Unit 1 Reactor Building Pressure = 11.2 psig slowly decreasing Unit 2 Reactor Power = 100% | |||
Which ONE of the following describes the actions directed (if any) by Enclosure 5.1 (ES Actuation) to ensure the required LPSW flow exists in the 1A LPI cooler? | |||
A. Place 1LPSW-251 in "Failed Open" ONLY B. Place 1LPSW-251 in "Failed Open" AND fully open 1LPSW-4 C. Place 1LPSW-251 in "Failed Open" AND Throttle LPSW flow to approximately 3000 gpm using 1LPSW-4 D. Place 1LPSW-251 in "Failed Open" AND Throttle LPSW flow to approximately 5200 gpm using 1LPSW-4 Page 68 of 75 Question: | |||
(1 point) 69ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor power = 100% Loss of offsite power occurs Current conditions: Main Feeder Buses remain de-energized | |||
: 1) The position of 1MS-112 (SSRH Control) is __(1)__. | |||
: 2) 1MS-77 (MS to MSRH) __(2)__ be operated from the control room switch. | |||
Which ONE of the following completes the statements above? | |||
A. 1. open 2. can B. 1. closed 2. can C. 1. open 2. can NO T D. 1. closed 2. can NO T Page 69 of 75 Question: | |||
(1 point) 70ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor Power = 50% 1A Turbine Bypass Valve fails OPEN Which ONE of the following describes the plant response? | |||
ASSUME NO OPERATOR ACTIONS Reactor power will... | |||
A. Increase then return to pre-transient level. | |||
B. Increase and stabilize at a higher power level. | |||
C. Decrease then return to pre-transient level. | |||
D. Decrease and stabilize at a lower power level. | |||
Page 70 of 75 Question: | |||
(1 point) 71ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor Power = 80% stable ICS in Manual 1B Main Feedwater Pump trips Which ONE of the following is the MAXIMUM power level allowed in accordance with AP/1 (Plant Runback). | |||
A. 74% B. 65% C. 60% D. 55% Page 71 of 75 Question: | |||
(1 point) 72ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 3 conditions: Initial conditions: Reactor tripped from 35% power due to 3TA lockout 3A Main FDW pump operating 3FDW-35 & 3FDW-44 (3A and 3B Startup FDW Control) in MANUAL 3A and 3B SG levels = 38" SU and stable Current conditions: 3FDW-35 & 44 are placed in Automatic Which ONE of the following describes the response of 3FDW-35 & 44? | |||
A. Travel open to increase SG levels to 240" XSUR. | |||
B. Travel open to increase SG levels to 50% on Operating level. | |||
C. Travel closed to decrease SG level to 30" on XSUR. | |||
D. Travel closed to decrease SG level to 25" on SU level. | |||
Page 72 of 75 Question: | |||
(1 point) 73ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following describes the: | |||
: 1) primary concern at ONS regarding Main Feedwater backleakage into the EFDW discharge piping? | |||
: 2) method used to determine if Main Feedwater backleakage into the EFDW discharge piping is occurring? | |||
A. 1. Vapor binding of the EFDWpumps2. locall y monitorin g EFDW pump dischar ge piping for increasin g temperature B. 1. Vapor binding of the EFDWpumps2. Monitorin g EFDW temperature OAC points fo rincreasin g temperature C. 1. Overpressurizing the EFDW system piping 2. locall y monitorin g EFDW pump dischar ge piping for increasin g temperature D. 1. Overpressurizing the EFDW system piping 2. Monitoring EFDW temperature OAC points for increasing temperature Page 73 of 75 Question: | |||
(1 point) 74ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following plant conditions: No Keowee Units are operating ACB-3 closed | |||
: 1) KHU 1X switchgear is being powered from __ (1) __. | |||
: 2) Keowee control power will be available for a MINIMUM of approximately __ (2) __ hour(s) following a loss of ALL AC power. | |||
Which ONE of the following completes the statements above? | |||
A. 1. 1TC 2. one B. 1. 1TC 2. four C. 1. the 230 KV switchyard 2. one D. 1. the 230 KV switch yard 2. four Page 74 of 75 Question: | |||
(1 point) 75ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following plant conditions: 3CA Battery Charger fails - output voltage = 0 VDC 3CA Battery voltage = 120 VDC 3DCB Bus voltage = 123 VDC Unit 1 DCA/DCB Bus voltage = 125 VDC Unit 2 DCA/DCB Bus voltage = 127 VDC Which ONE of the following will automatically supply power to 3DIA panelboard? | |||
A. 3CA Battery B. Unit 1 DC Bus C. 3DCB Bus D. Unit 2 DC Bus Page 75 of 75 Examination KEY for:ILT4 4 ONS RO NRC ExaminaQuestionNumberAnswer1B2B3C4C5B6A7D8B9A10A11A12C13D14C15B16C17D18D19B20C21D22A23B24B25DPrinted 12/19/2013 7:45:04 AMPage 1 of 3 Examination KEY for:ILT4 4 ONS RO NRC ExaminaQuestionNumberAnswer26A27C28A29C30D31D32D33C34A35A36C37B38C39C40A41B42A43C44A45D46A47C48C49D50DPrinted 12/19/2013 7:45:11 AMPage 2 of 3 Examination KEY for:ILT4 4 ONS RO NRC ExaminaQuestionNumberAnswer51B52B53D54D55B56C57C58A59B60D61C62A63A64B65B66B67B68B69D70A71B72D73A74A75BPrinted 12/19/2013 7:45:11 AMPage 3 of 3}} |
Revision as of 07:48, 3 July 2018
ML13364A335 | |
Person / Time | |
---|---|
Site: | Oconee |
Issue date: | 12/30/2013 |
From: | NRC/RGN-II |
To: | |
References | |
Download: ML13364A335 (78) | |
Text
Question:
(1 point) 1ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following plant conditions: Unit 1 has just reached 100% power following a refueling outage Unit 2 is at 100% power with 93 EFPD Which ONE of the following will result in the highest amount of Emergency Feedwater flow required to stabilize RCS temperature 5 minutes following the trip?
A. Both Main Feedwater PumpsONLY trip on Unit 1 B. Both Main Feedwater Pumps ONLY trip on Unit 2 C. Loss of Offsite Power on Unit 1 D. Loss of Offsite Power on Unit 2 Page 1 of 75 Question:
(1 point) 2ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor power = 100% 1RC-66 (PORV) is leaking past its seat Pressurizer temperature = 648 0F Quench tank pressure = 5 psig Reactor Building pressure = 0 psig Which ONE of the following describes the expected tailpipe temperature (°F) downstream of 1RC-66?
A. 212 B. 228 C. 272 D. 648 Page 2 of 75 Question:
(1 point) 3ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor tripped from 100% power due to SBLOCA 1A HPI Pump failed Subcooling Margin = 0°F stable Which ONE of the following is the reason the EOP directs increasing SG levels to the Loss of Subcooling Margin Setpoint level?
A. Establish a large secondary side inventory in support of a rapid RCS cooldown.
B. Establish a large secondary side inventory to ensure that a loss of coupling will NOT occur if a momentary loss of EFDW occurs.
C. Ensure a secondary water level higher than the primary water level inside the SG tubes to establish boiler condenser mode heat transfe r D. Ensure a secondary side levelsufficient to minimize the consequences of a total loss of feedwater during boiler condenser mode heat transfer Page 3 of 75 Question:
(1 point) 4ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor power = 50% stable 1B2 RCP is OFF Which ONE of the following would require immediate entry into AP/1/A/1700/016 (Abnormal Reactor Coolant Pump Operation)?
A. OAC point O1A0061 (RCP 1A1 MTR INPUT POWER) in HI alarm B. OAC point O1A1579 (RCP 1A2 MTR LOWER AIR TEMP) in HI alarm C. 1SA-15/A5 (RC PUMP MOTOR 1B1 OIL POT LOW LEVEL) in alarm D. 1SA-6/D5 (PUMP 1B2 CAVITY PRESS HI/LOW
) in alarm Page 4 of 75 Question:
(1 point) 5ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor power = 100%
Current conditions:
LPI Flow Train A = 1800 gpm stable LPI Flow Train B = 1780 gpm stable Rule 2 (Loss of SCM) in progress. IMAs complete
- 2) In accordance with Rule 2, performance of Rule 3 (Loss of Main or Emergency FDW) __ (2) __ required.
Which ONE of the following completes the statements above?
A. 1. LOSCM 2. is B. 1. LOSCM 2. is NOT C. 1. ICC 2. is D. 1. ICC 2. is NOT Page 5 of 75 Question:
(1 point) 6ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Normal LPI decay heat removal in service Current conditions: Loss of offsite power occurs Power restored via CT-4 1A and 1B LPI Pumps NOT available Which ONE of the following describes the requirements to start the 1C LPI Pump?
Manual reset of Load Shed is __(1)___ and starting of 1C LPI Pump is allowed after a MINIMUM of ___(2)__ seconds.
A. 1. NOT required 2. 5 B. 1. required 2. 5 C. 1. NOT required 2. 30 D. 1. required 2. 30 Page 6 of 75 Question:
(1 point) 7ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor trip has just occurred Total RCP seal injection flow = 0 gpm Running Component Cooling pump tripped Standby CC pump did not start Which ONE of the following describes the procedure whose performance is directed by the EOP and why?
Initiate-
A. AP/20 (Loss of CC) to restore Component Cooling B. AP/20 (Loss of CC) to ensure letdown is isolated C. AP/25 (SSF EOP) to align an alternate letdown flowpath D. AP/25 (SSF EOP) to align an alternate source of seal in jection Page 7 of 75 Question:
(1 point) 8ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor power = 90% 1B Main Feedwater pump trips Current conditions: Reactor power = 70% decreasing RCS pressure = 2165 psig slowly decreasing Pressurizer level = 228 inches slowly decreasing Pressurizer temperature = 640°F slowly decreasing Pressurizer heater bank 1 (Group A and K) is ON Pressurizer heater banks 2, 3, and 4 are in AUTO and are OFF The pressurizer is ___(1)____ AND the pressurizer heater bank 2 ___(2)____.
Which ONE of the following completes the statement above?
A. 1. subcooled 2. will ener gize at 2145 psi g B. 1. subcooled 2. should be ener gized C. 1. saturated 2. will ener gize at 2145 psi g D. 1. saturated 2. should be energized Page 8 of 75 Question:
(1 point) 9ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 2 conditions: Loss of all sources of Feedwater has occurred RCS Pressure = 2250 psig increasing Pressurizer level = 294 inches increasing ALL SCM's = 24°F slowly decreasing What is the:
- 1) lowest RCS pressure (psig) that will require Rule 4 (Initiation of HPI Forced Cooling) to be performed?
- 2) PRIMARY reason for reducing the number of operating RCP's in accordance with Rule 4? A. 1. 2300 2. Reduce the heat input to the RCS B. 1. 2300 2. Provide the ability to recover from HPI forced cooling and re-establish a Pressurizer bubble.
C. 1. 2255 2. Reduce the heat input to the RCS D. 1. 2255 2. Provide the ability to recover from HPI forced cooling and re-establish a Pressurizer bubble.
Page 9 of 75 Question:
(1 point) 10ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 3 conditions: Reactor power = 100%
Which ONE of the following will result in a Tech Spec LCO being NOT met?
A. 3A SGTL rate = 160 gpd B. 3B Core Flood Tank level = 12.69 feet C. 3B Core Flood Tank pressure = 622 psig D. 4 gpm RCS leak identified as being through valve stem packing of 3HP-1 Page 10 of 75 Question:
(1 point) 11ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: ALL sources of feedwater have been lost Rule 4 (Initiation of HPI Forced Cooling) is complete with outstanding IAAT's 1A HPI pump has failed HPI flow parameters are as indicated below In accordance with Rule 4, __(1)__ RCP('s) is/are operating and HPI flow __(2)__ required to be throttled.
Which ONE of the following completes the statement above?
A. 1. 1 2. is B. 1. 1 2. is NOT C. 1. 2 2. is D. 1. 2 2. is NOT Page 11 of 75 Question:
(1 point) 12ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 Conditions:Initial conditions: Reactor Power = 100% ACB-4 closed Current conditions: Reactor trip CT-1 Locks out KHU-2 Emergency Lockout occurs Assuming no additional failures, which ONE of the following describes the first method used to restore power to Unit 1 MFB's?
A. Automatically through ACB-3 B. Automaticall y through SL1 and SL2 C. Manually through ACB-3 in accordance with Enclosure 5.38 (Restoration of Power) of the EOP D. Manually through SL1 and SL2 in accordance with Enclosure 5.38 (Restoration of Power) of the EOP Page 12 of 75 Question:
(1 point) 13ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Unit shutdown in progress Reactor power = 38% slowly decreasing LOOP (Switchyard Isolation) occurs
- 1) Based on the conditions above, the status of the Main Turbine will be __(1)__ 5 minutes following the LOOP?
- 2) ANYTIME the Main Turbine is tripped, ICS uses __(2)__ to control the Turbine Bypass Valves?
Which ONE of the following completes the statements above?
A. 1. tripped 2. Turbine Header Pressure B. 1. tripped 2. Steam Generator Outlet Pressure C. 1. NOT tripped 2. Turbine Header Pressure D. 1. NOT tripped 2. Steam Generator Outlet Pressure Page 13 of 75 Question:
(1 point) 14ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions Reactor Power = 100% SASS in Manual while SPOC repairs Pressurizer Level 3 level transmitter 1HP-120 in AUTO selected to Pressurizer Level 1 Current conditions: Vital Power to ICCM Train A fails Which ONE of the following describes Pressurizer level control with 1HP-120?
A. Selecting Pressurizer Level 2and depressing the AUTO pushbutton on 1HP-120 are required to restore automatic controlat setpoint B. Selectin g Pressurizer Le vel 2ONLY will restore automatic control at setpoint C. Manual control using 1HP-120 Bailey controller is all that is available D. Additional actions are NOT required since Automatic controlat setoint is retained Page 14 of 75 Question:
(1 point) 15ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor power = 100% Instrument Air pressure = 85 psig decreasing AP/22 (Loss of Instrument Air) has been initiated Which ONE of the following
- 1) is the higher Instrument Air pressure (psig) that would require an immediate manual Reactor trip in accordance with AP/22?
- 2) states the reason AP/22 directs tripping the Main FDW pumps immediately after tripping the Reactor as described above?
A. 1. 70 2. Controllin g FDW valves fail "as is" B. 1. 65 2. Controllin g FDW valves fail "as is" C. 1. 70 2. Controllin g FDW valves fail closed D. 1. 65 2. Controllin g FDW valves fail closed Page 15 of 75 Question:
(1 point) 16ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: AP/34 (Degraded Grid) in progress Generator output = 850 MWe and 450 MVARs Generator Hydrogen Pressure = 60 psig Generator Output Voltage = 18.2 KV
- 1) The Generator output __ (1) __ within the limits of the Generator Capability Curve.
- 2) If the generator exceeds the Underfrequency Maximum Allowable Time given in AP/34 (Degraded Grid) the Main Turbine __ (2) __ automatically trip.
Which ONE of the following completes the statements above?
REFERENCE PROVIDED A. 1. is NOT 2. will B. 1. is NOT 2. will NOT C. 1. is 2. will D. 1. is 2. will NOT Page 16 of 75 Question:
(1 point) 17ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 3 conditions: A brief loss of power has occurred Unit auxiliaries are being supplied from the switchyard via CT-3 Subsequent Actions tab in progress
- 1) Subsequent Actions directs restarting __(1)__.
- 2) The __(2)__ RCP will provide the best Pressurizer Spray.
Which ONE of the following completes the statements above?
A. 1. one RCP ONLY 2. 3A1 B. 1. one RCP ONLY 2. 3B1 C. 1. one RCP per loop 2. 3A1 D. 1. one RCP per loop 2. 3B1 Page 17 of 75 Question:
(1 point) 18ILT44 ONS RO NRC Examination Oconee Nuclear Station In accordance with the EOP, which ONE of the following describes the instruments that are used when initially stabilizing RCS temperature following a Main Steam Line Break and states one of the reasons why they are used?
A. Tcolds are used since Tech Specs specifies that Tcold is RCS temperature B. Tcolds are used since they are the coldest temperature and therefore most indicative of PTS issues C. CETC's are used since the resultant RCS cooldown may result in Tcold being off scale low D. CETC's are used since they are qualified instruments and are therefore more reliable in the hostile containment environment Page 18 of 75 Question:
(1 point) 19ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Time = 1200 Reactor power = 100% 1A steam generator tube leak = 2.1 gpd stable RCS activity = 0.25 Ci/ml DEI increasing Current conditions: Time = 1400 NO change in 1A SG tube leak rate RCS activity = 0.65 Ci/ml DEI increasing Which ONE of the following describes the response of the radiation monitors between 1200 and 1400?
A. 1RIA-59 (N-16 monitor) and 1RIA-40 (CSAE Off-gas) increased.
B. 1RIA-16 (Main Steam Line Monitor
) and 1RIA-40 increased.
C. 1RIA-59 increased while1RIA-40 remained constant.
D. 1RIA-16 increased while 1RI A-40 remained constant.
Page 19 of 75 Question:
(1 point) 20ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 2 condition:Initial conditions: Time = 0900 Reactor Startup in progress NI 1 & 2 = 370 cps NI 3 & 4 = 0 cps (out of service) ALL WR NI's = ~ 2.7 E-4%
Current conditions: Time = 0901 NI 1 & 2 are inoperable Which ONE of the following describes:
- 1) immediate actions required by Tech Spec 3.3.9 (Source Range Neutron Flux)?
- 2) the reason for the actions described above?
A. 1. Insert Control Rods to Group 1 at 50% withdrawn2. Prevents power increases when the primary power indication for the operator is not available.
B. 1. Insert Control Rods to Group 1 at 50% withdrawn2. 2 dpm Startup Rate Control Rod Out Inhibit is no lon ger available C. 1. Fully insert all Control Rods2. Prevents power increases when the primary power indication for the operator is not available.
D. 1. Fully insert all Control Rods2. 2 dpm Startup Rate Control Rod Out Inhibit is no longer available Page 20 of 75 Question:
(1 point) 21ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor power = 92% decreasing Unit shutdown in progress per the SGTR tab
- 1) In accordance with the SGTR tab and Enclosure 5.5 (Pzr and LDST Level Control), RCS makeup and letdown will be adjusted to maintain Pressurizer level betw een __ (1) __ inches.
- 2) The reason for this Pzr level band is to provide adequate inventory to __ (2) __.
Which ONE of the following completes the statements above?
A. 1. 140
- 180 2. ensure Pzr heaters will remain covered if a subsequent reactor trip occurs B. 1. 140
- 180 2. accommodate system shrinkage during shutdown/cooldown from 18% power C. 1. 220
- 260 2. ensure Pzr heaters will remain covered if a subsequent reactor trip occurs D. 1. 220 - 260 2. accommodate system shrinkage during shutdown/cooldown from 18% power Page 21 of 75 Question:
(1 point) 22ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor power = 100%
Which ONE of the following will result in an AUTOMATIC trip of the Main Turbine?
A. Bearing Oil Pressure = 5.5 psig B. Main Turbine speed = 1955 RPM C. EHC Hydraulic Oil pressure = 1210 psig D. EITHER Steam Generator Level = 93% OR Page 22 of 75 Question:
(1 point) 23ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor power = 100% 1A GWD tank release in progress 1RIA-38 OOS Current conditions: Maintenance activities in the area result in an inadvertent loss of power to RM-80 skid of 1RIA-37 1SA8/B9 RM PROCESS MONITOR RADIATION HIGH in alarm 1SA8/B10 RM PROCESS MONITOR FAULT in alarm
- 1) 1GWD-4 (A GWD TANK DISCHARGE) should __(1)__.
- 2) The required Completion Time in SLC 16.11.3 (Radioactive Effluent Monitoring Instrumentation) for suspending the release by this pathway if not already isolated and both 1RIA-37 and 1RIA-38 become inoperable is __(2)__.
Which ONE of the following completes the statements above?
A. 1. remain open 2. immediatel y B. 1. automatically close 2. immediatel y C. 1. remain open 2. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D. 1. automatically close 2. 1 hou r Page 23 of 75 Question:
(1 point) 24ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor power = 2% 1SA2/B11 (ICS AUTO POWER FAILURE) actuated 1SA2/B13 (ICS HAND POWER FAILURE) actuated Which ONE of the following describes:
- 1) the level at which SGs will be maintained?
- 2) how decay heat removal from the core is controlled?
A. 1. 25 inches SUR 2. ADVs B. 1. 30 inches XSUR 2. ADVs C. 1. 25 inches SU R 2. TBVs D. 1. 30 inches XSUR 2. TBVs Page 24 of 75 Question:
(1 point) 25ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Switchyard isolation occurs Current conditions: Shutdown of KHU's is desired Which ONE of the following states:
- 1) if a Load Shed has occurred?
- 2) the procedure that will be used to perform a remote shutdown of the KHU's?
A. 1. Yes 2. OP/0/A/2000/041 (Keowee Modes of Operations
) B. 1. No 2. OP/0/A/2000/041 (Keowee Modes of Operations
) C. 1. Yes 2. OP/0/A/1106/019 (Keowee Hydro AtOconee
) D. 1. No 2. OP/0/A/1106/019 (Keowee Hydro AtOconee
) Page 25 of 75 Question:
(1 point) 26ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: ES 1-8 have actuated LOCA CD tab in progress RCS pressure = 423 psig slowly decreasing 1A LPI Pump operating in the Piggyback alignment Which ONE of the following describes the:
- 1) operational limitations on the operating LPI pump?
- 2) pump(s) being protected by the above limitation?
A. 1. Maximized to < 3100 gpm 2. LPI B. 1. Maximized to < 3100 gpm2. HPI C. 1. Maximized to < 2900 gpm2. LPI D. 1. Maximized to < 2900 gpm2. HPI Page 26 of 75 Question:
(1 point) 27ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor trip from 100% due to a SBLOCA Reactor building pressure has peaked at 1.7 psig Subcooled margins are stable as indicated below Which ONE of the following describes how Feedwater will be used to mitigate this event? Steam Generator levels will be controlled at ________?
A. 240 inches using Emergency Feedwate r B. 240 inches using Main Feedwater C. Loss of Subcooling Margin setpointusing Emergency Feedwate r D. Loss of Subcoolin g Margin setpointusin g Main Feedwate r Page 27 of 75 Question:
(1 point) 28ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following describes:
- 1) the design purpose of extending RCP coast down time with the flywheel?
- 2) an expected core delta T (°F) 30 minutes following a lockout of 1TA and 1TB?
A. 1. Helps prevent the core from reaching DNBR limits2. 35 B. 1. Helps prevent the core from reaching DNBR limits 2. 47 C. 1. Reduces the likelihood of a Reactor trip following a RCP trip at power 2. 35 D. 1. Reduces the likelihood of a Reactor trip following a RCP trip at powe r 2. 47 Page 28 of 75 Question:
(1 point) 29ILT44 ONS RO NRC Examination Oconee Nuclear Station
- 1) The Letdown Storage Tank contains approximately __(1)__ gallons of water per inch of level.
- 2) The HIGHER Letdown Storage Tank level that will automatically open 1HP-24 and 1HP-25 is __(2)__ inches.
Which ONE of the following completes the statements above?
A. 1. 24 2. 38 B. 1. 24 2. 54 C. 1. 31 2. 38 D. 1. 31 2. 54 Page 29 of 75 Question:
(1 point) 30ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 2 conditions: RCS Cooldown in progress 2B LPI cooler isolated due to cooler leak Which ONE of the following states the:
- 1) LPI Decay Heat Removal mode that will be used for the INITIAL transition to LPI cooling?
- 2) HIGHER RCS pressure (psig) that will allow aligning LPI in the Normal Decay Heat Removal alignment?
A. 1. Switchover 2. 220 B. 1. High Pressure 2. 220 C. 1. Switchover 2. 115 D. 1. High Pressure 2. 115 Page 30 of 75 Question:
(1 point) 31ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Rule 3 initiated Loss of Heat Transfer tab in progress Efforts underway to re-establish Steam Generator cooling 1SA-18/D1 (RC SYSTEM APPROACHING SATURATED CONDTIONS) in alarm 1SA-2/D3 (RC PRESS HIGH/LOW) in alarm Pressurizer level = 380" slowly increasing RCS pressure = 2240 psig slowly increasing SCM = 0°F Which ONE of the following states which additional EOP Rules (if any) should be initiated?
A. NO additional rules required B. Rule 2 (Loss of SCM) ONLY C. Rule 4 (Initiation of HPI Forced Cooling) ONLY D. Rule 2 AND Rule 4 Page 31 of 75 Question:
(1 point) 32ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 2 condition:Initial conditions: Unit startup in progress RCS temperature = 310°F slowly increasing Maintenance in progress in the area of 2DIB panelboard Current conditions: 2DIB breaker #24 (2RC-66 Pilot Valve DC solenoid power supply) is inadvertently opened Which ONE of the following describes:
- 1) a Tech Spec Limiting Condition of Operation that is NOT met?
- 2) the position of 2RC-66?
A. 1. 3.4.9 (Pressurizer) 2. Open B. 1. 3.4.9 (Pressurizer) 2. Closed C. 1. 3.4.12 (LTOP) 2. Open D. 1. 3.4.12 (LTOP) 2. Closed Page 32 of 75 Question:
(1 point) 33ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:
Initial conditions Loss of all Feedwater HPI forced cooling initiated Quench Tank pressure = 40 psig increasing RCS activity indicates no fuel failures present Current conditions Quench Tank pressure = 3 psig stable Which ONE of the following describes the:
- 1) reactor building RIA's response to the above conditions?
- 2) valve(s) that will automatically close anytime 1RIA-49 reaches its HIGH alarm setpoint?
A. 1. increases 2. 1LWD-1 AND 1LWD-2 B. 1. remains constant 2. 1LWD-1 AND 1LWD-2 C. 1. increases 2. 1LWD-2 ONLY D. 1. remains constant 2. 1LWD-2 ONLY Page 33 of 75 Question:
(1 point) 34ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: 1SA-08/B-9 (PROCESS MONITOR RADIATION HIGH) 1RIA-50 in HIGH alarm CC Surge Tank level increasing
- 1) The CC Surge tank __(1)__.
- 2) If the RCS leakage threatens to overflow the associated waste tank, AP/1/A/1700/002 (Excessive RCS Leakage) will direct __(2)__.
Which ONE of the following completes the statements above?
A. 1. will overflow to the LAWT 2. trippin g the Reactor B. 1. will overflow to the LAWT2. initiatin g a shutdown usin g AP/1/A/1700/029 (Rapid Unit Shutdown
) C. 1. will overflow to a floor drain which drains to the MWHUT2. trippin g the Reactor D. 1. will overflow to a floor drain which drains to the MWHUT 2. initiatin g a shutdown usin g AP/1/A/1700/029 (Rapid Unit Shutdown
) Page 34 of 75 Question:
(1 point) 35ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following states the automatic OPEN setpoints (psig) for 1RC-1 (Pzr Spray) and 1RC-66 (PORV) in Mode 1?
1RC-1 1RC-66 A. 2205 2450 B. 2205 2500 C. 2255 2450 D. 2255 2500
Page 35 of 75 Question:
(1 point) 36ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor power = 100% 1D RPS channel in Manual Bypass 1A RPS Thot RTD fails low Which ONE of the following:
- 1) describes ALL 1A RPS functions affected by the failure?
- 2) states if OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) requires tripping the 1A RPS channel?
A. 1. RCS High Outlet Temperature ONLY2. yes B. 1. RCS High Outlet Temperature ONLY 2. no C. 1. RCS High Outlet Temperature and RCS Variable Low Pressure 2. yes D. 1. RCS High Outlet Temperature and RCS Variable Low Pressure 2. no Page 36 of 75 Question:
(1 point) 37ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following describes how RCS Pressure signals are used to provide control signals to the Integrated Control System?
A. Median Selected from one wide range pressure and two channels of RPS narrow range pressure (A and B)
B. Median Selected from three channels of RPS narrow range pressure (A, B, and E) C. 2nd Max Selected from RPS narrow range pressures (A, B, C, & D)
D. 2nd Min Selected from RPS narrow ran ge pressures (A, B, C, & D
) Page 37 of 75 Question:
(1 point) 38ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 2 conditions:Initial conditions: Reactor power = 100%
Current conditions: MSLB occurs RCS pressure = 1580 psig slowly increasing RB peak pressure = 2.8 psig Which ONE of the following describes a valve that has received a signal to CLOSE?
A. 2CC-7 B. 2HP-24 C. 2LWD-2 D. 2LPSW-1062 Page 38 of 75 Question:
(1 point) 39ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following plant conditions:Time = 1200 Unit 1 Reactor power = 100% Unit 2 Reactor power = 100% ACB-4 closed Time = 1201 LOCA occurs on Unit 1 Switchyard Isolation occurs Which ONE of the following states the source of power being used to energize 1DIA at Time = 1202?
A. Control Batteries B. KHU-1 C. KHU-2 D. CT-5 Page 39 of 75 Question:
(1 point) 40ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 2 conditions:Time = 1200 Reactor in MODE 5 LPI aligned to normal Decay Heat Removal mode 2RIA-35 (Combined LPSW effluent leaving the Reactor Building and the Auxiliary Building) is isolated for repair Time = 1300 Large LPI Cooler leak in 2A LPI Cooler occurs Time = 1500 Actions to isolate the 2A LPI Cooler are initiated RCS temperature slowly increasing
- 1) At Time = 1330 there __(1)__ an RIA alarm indicating the LPI Cooler leak?
- 2) Entry into MODE 4 will occur when RCS temperature exceeds __(2)__°F?
Which ONE of the following completes the statements above?
A. 1. is 2. 200 B. 1. is 2. 250 C. 1. is NOT 2. 200 D. 1. is NOT 2. 250 Page 40 of 75 Question:
(1 point) 41ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor is in MODE 5 RB Purge in progress Unit 1 vent activity increasing 1RIA-45 HIGH alarm fails to actuate at setpoint
- 1) Automatic termination of RB Purge operation due to increasing activity __(2)__ available?
- 2) Purge operation __(1)__ be allowed if the unit were in MODE 4.
Which ONE of the following completes the statements above?
A. 1. is 2. would B. 1. is 2. would NOT C. 1. is NOT 2. would D. 1. is NOT 2. would NOT Page 41 of 75 Question:
(1 point) 42ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: 1A LPSW Pump trips Standby LPSW pump fails to start Which ONE of the following will begin to increase in temperature?
ASSUME NO MANUAL ACTIONS ARE TAKEN A. Letdown B. Spent Fuel Pool C. Main Feedwater Pump oil temperature D. Primary Instrument Air Compresso rdischarge air temperature Page 42 of 75 Question:
(1 point) 43ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following is the power supply for the Unit 2 Auxiliary Instrument Air System compressor?
A. 2XD B. 2XF C. 2XP D. 2XS1 Page 43 of 75 Question:
(1 point) 44ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor Power = 100% 1A MSLB inside containment
Current conditions: Core SCM = 18°F stable RB Pressure = 17 psig slowly decreasing Which ONE of the following sets of actions is required by Enclosure 5.1 (ES Actuation)
A. Take ES Channel 1 to manual AND open 1HP-20 B. Take ES Channel 1 to manual AND open 1HP-3 C. Override Odd Voters AND open 1HP-20 D. Override Odd Voters AND open 1HP-3 Page 44 of 75 Question:
(1 point) 45ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor Power = 100%
Which ONE of the following:
- 1) describes the LOWER SG Operating Range level (%) that will result in an automatic trip of both Main Feedwater pumps?
- 2) states if SG Operating Range level indications are temperature compensated?
A. 1. 87 2. No B. 1. 87 2. Yes C. 1. 97 2. No D. 1. 97 2. Yes Page 45 of 75 Question:
(1 point) 46ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor power = 50% slowly decreasing OAC Unavailable Computer Reactor Calculation Package NOT running Which ONE of the following:
- 1) is the HIGHER power level (% Power) at which Tech Spec limits on Reactor Power Imbalance do NOT apply?
- 2) describes how OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) directs the operator to determine if Imbalance limits specified in the COLR have been exceeded?
A. 1. 35 2. by use of CR gages for Power Range NI's B. 1. 35 2. by performin g PT/1/A/1103/019 (Backup Incore Detector S ystem) C. 1. 15 2. by use of CR gages for Power Range NI's D. 1. 15 2. by performin g PT/1/A/1103/019 (Backup Incore Detector S ystem) Page 46 of 75 Question:
(1 point) 47ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Mode 6 REFUELING is in progress All four SR NIs in service SR 1NI-1 and SR 1NI-3 are the designated NIs for Fuel Handling Current conditions: Power supply to SR 1NI-1 fails (0 vdc)
Which ONE of the following describes the impact on refueling activities in accordance with OP/1/A/1502/007 (Operations Defueling/Refueling Responsibilities)?
A. Allowed to continue because two other SR NIs remain in service B. Allowed to continue because SR NI-3 is still in service C. Required to be stopped until another SR NI is designated because other NIs are procedurall y allowed to be desi gnated D. Required to be stopped and cannot be resumed until SR 1NI-1 is returned to service because other NIs are NOT procedurally allowed to be designated Page 47 of 75 Question:
(1 point) 48ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Time = 1200 Reactor Power = 40% stable following an instrument failure Turbine Header Pressure = 860 psig stable Feedwater, Reactor, and Main Turbine in Manual Time = 1300 ICS in Automatic Turbine Header Pressure = 860 psig stable Time = 1301 Reactor Trips prior to any additional Turbine Header Pressure setpoint adjustments Which ONE of the following is the pressure (psig) where the Turbine Bypass Valves will automatically control Steam Generator pressure?
A. 885 B. 910 C. 985 D. 1010 Page 48 of 75 Question:
(1 point) 49ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Time = 1200:00 Reactor power = 80% stable 1A and 1B CBP operating Time = 1201:00 1A CBP trips Feedwater Pump suction pressure = 225 psig slowly decreasing Time = 1203:00 Feedwater Pump suction pressure = 220 slowly increasing Which ONE of the following describes the:
- 1) runback rate (%/min) inserted at Time = 1201:00 to ICS?
- 2) procedure that will be directed by the CRS at Time = 1203:00?
A. 1. 15 2. AP/1/A/1700/001 (Unit Runback
) B. 1. 15 2. EOP C. 1. 20 2. AP/1/A/1700/001 (Unit Runback
) D. 1. 20 2. EOP Page 49 of 75 Question:
(1 point) 50ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor power = 100% Primary to Secondary leakage of 10 gpd has just been detected AP/1/A/1700/031 (Primary to Secondary Leakage) has been initiated
- 1) In accordance with AP/31, opening the Turbine Building Sump (TSP) pump breakers prior to being ready to hang White Tags on the TBS pump breakers __(1)__ allowed.
Which ONE of the following completes the statements above?
A. 1. is NOT 2. after a 2 minute time r B. 1. is NOT 2. immediatel y C. 1. is 2. after a 2 minute time r D. 1. is 2. immediatel y Page 50 of 75 Question:
(1 point) 51ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Time = 1200 1A GWD tank pressure = 68 psig stable Current conditions: Time = 1205 1A GWD tank pressure = 18 psig rapidly decreasing Various Aux Building RIA's in alarm 1RIA-1 (Control Room Monitor) in HIGH alarm 1RIA-39 (CNTL RM Gas) in HIGH alarm AP/1/A/1700/018 (Abnormal Release of Radioactivity) in progress A and B Outside Air Booster Fans have been started Which ONE of the following:
- 1) states if 1RIA-1 has a local alarm (do not count associated statalarm(s))?
- 2) describes the areas being provided outside air via the Outside Air Booster Fans?
A. 1. Yes 2. Control Room ONLY B. 1. No 2. Control Room ONLY C. 1. Yes 2. Control Room, Cable Rooms, and the Equipment Rooms D. 1. No 2. Control Room, Cable Rooms, and the Equipment Rooms Page 51 of 75 Question:
(1 point) 52ILT44 ONS RO NRC Examination Oconee Nuclear Station 1RIA-59 setpoints are set by __(1)__ and the MINIMUM power level at which 1RI A-59is used to determine SGTL rate is __(2)__ (% power) in accordance with the EOP.
Which ONE of the following completes the statement above?
A. 1. I&E 2. 20 B. 1. I&E 2. 40 C. 1. ROs 2. 20 D. 1. ROs 2. 40 Page 52 of 75 Question:
(1 point) 53ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following states all of the switchgear that can supply power to the B LPSW pump?
A. 1TD ONLY B. 2TC ONLY C. 1TC or 2TD D. 1TD or 2TD Page 53 of 75 Question:
(1 point) 54ILT44 ONS RO NRC Examination Oconee Nuclear Station Based on the graph above, which ONE of the following describes the EARLIEST time at which SA-141 (SA to IA Controller) will automatically open?
A. 1207 B. 1210 C. 1212 D. 1215 Page 54 of 75 Question:
(1 point) 55ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following describes what should be used in the case of a large Hydrogen leak to maintain Hydrogen concentration below the lower flammability limit in accordance with OP/1/A/1106/017 (Hydrogen System)?
A. CO2 B. Water C. Halon D. Foam fire retardant Page 55 of 75 Question:
(1 point) 56ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following is the LOWER limit on RCS activity that would require entry into AP/21 (RCS Activity)?
A. Xe-133 = 0.25 µCi/gm B. Xe-133 = 1.0
µCi/gm C. DEI = 0.25 µCi/gm D. DEI = 1.0 µCi/gm Page 56 of 75 Question:
(1 point) 57ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following activities complies withguidance contained in SOMP 1-2 (Reactivity Management)? A. Manual rod withdrawal during a Feedwater transient to stop a temperature decrease caused by an instrument failure B. Manually increasing Feedwater flow to stop an RCS pressure increase caused by an RCS temperature increase C. Manually raising one Loop FDW demand while lowering the other Loop FDW demand to control Tcold following an RCP trip D. Manually increasing turbine demand to adjust RCS temperature Page 57 of 75 Question:
(1 point) 58ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following tags would be used ONLY for configuration control of 1HP-409 in accordance with NSD-500 (Red Tags/Configuration Control Tags)?
A. White Tag B. MORT Ta g C. OORT Tag D. CORT Tag Page 58 of 75 Question:
(1 point) 59ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 condition: Reactor in MODE 1 Which ONE of the following is the MINIMUM Pressurizer level (inches) that would require declaring Tech Spec 3.4.9 (Pressurizer) LCO NOT met in accordance with PT/1/A/0600/001 (Periodic Instrument Surveillance)?
A. 240 B. 260 C. 285 D. 340 Page 59 of 75 Question:
(1 point) 60ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor trip due to loss of both Main FDW pumps Instrument Air pressure = 0 psig Auxiliary Instrument Air pressure= 0 psig Which ONE of the following describes the status of 1FDW-315 and 1FDW-316?
A. Available for Manual operation ONLYonce the air supply was lost B. Will be available for Automatic operation for a MINIMUM of 30 minutes from the loss of air supply C. Will be available for Automatic operation for a MINIMUM of 1 hou r from the loss of air suppl y D. Will be available for Automatic operation for a MINIMUM of 2 hours from the loss of air supply Page 60 of 75 Question:
(1 point) 61ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 2 conditions:Initial conditions: Time = 1200 RCS temperature = 92°F stable RB Purge in progress 2RIA-45 HIGH alarm setpoint = 1520 cpm 2RIA-45 = 1342 cpm stable Current conditions: Time = 1205 2RIA-45 = 1520 cpm increasing Which ONE of the following describes:
- 1) ALL valves that will CLOSE?
- 2) 2RIA-46 reading (cpm) at time = 1200?
A. 1. 2P R-1 through 2P R-6 2. Zero B. 1. 2P R-1 through 2P R-6 2. 1342 C. 1. 2PR-2 through 2PR-5 ONLY 2. Zero D. 1. 2P R-2 through 2P R-5 ONLY2. 1342 Page 61 of 75 Question:
(1 point) 62ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following plant conditions: Venting the 1C LPI Pump in progress using the following RWP information:
o Dose Alarm : 25 mrem o Dose Rate Alarm: 200 mrem/hr o Dose Alarm: Stop work - Exit Area - Notify RP o Unanticipated Dose Rate Alarm: Stop Work - Exit Area - Notify RP Which ONE of the following states the MAXIMUM time work can continue before complying with the RWP will require exiting the area?
SEE PLAN VIEW PROVIDED Do NOT consider dose received while traveling to or from the job.
A. 15 minutes B. 30 minutes C. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> D. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Page 62 of 75 Question:
(1 point) 63ILT44 ONS RO NRC Examination Oconee Nuclear Station Of the two tabs below, the __(1)__ tab of the EOP has a higher priority because __(2)__.
Which ONE of the following completes the statement above?
A. 1. LOSCM 2. prompt actions are required to ensure core coolin g is maintained B. 1. LOSCM 2. actions to initiate HPI injection are required prior to the RCS void fraction reaching 70%.
C. 1. SGTR 2. a Reactor trip with a SGTR results in a direct release path for radionuclides to the environment D. 1. SGTR 2. actions to depressurize RCS to minimize SCM during a SGTR is a Time Critical Action that ma y not otherwise be met Page 63 of 75 Question:
(1 point) 64ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor Power = 70%
Which ONE of the following would require entry into the EOP?
A. Condenser vacuum = 22.3" hg B. 1RIA-59 = 31.4 gpm C. 1B Main FDW pump trips D. 1A1 RCP trips Page 64 of 75 Question:
(1 point) 65ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor power = 100% 1KVIA Panelboard de-energized Current conditions: MSLB inside the Reactor Building occurs Lowest RCS pressure = 1137 psig Reactor Building Pressure peaked at 32 psig Which ONE of the following describes ALL ES Actuation Logic Channels that have actuated?
A. 1, 3, 5, 7 B. 2, 4, 6, 8 C. 1, 5, 7 ONLY D. 2, 6, 8 ONLY Page 65 of 75 Question:
(1 point) 66ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Time = 1200 Reactor Power = 100% 1A MSLB inside the Reactor Building Current conditions: Time = 1201 Reactor Building Pressure = 3 psig increasing Which ONE of the following describes the operation of 1LPSW-18?
A. It is NORMALLY fully open however it will receive a signal to open from ES-5 at 1201 B. It is NORMALLY throttled and will go fully open when it receives a signal to open from ES-5 at 1201 C. It is NORMALLY fully open however it will receive a signal to open from ES-5 at 1204 D. It is NORMALLY throttled and will go fully open when it receives a signal to open from ES-5 at 1204 Page 66 of 75 Question:
(1 point) 67ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor power = 50%
Current conditions: LBLOCA occurs 1TD de-energized 1B RBCU switch in OFF Which ONE of the following describes the status of the below listed Reactor Building Cooling Units five (5) minutes after ES actuates?
ASSUME NO OPERATOR ACTIONS 1B RBCU 1C RBCU A. LOW LOW B. LOW OFF C. OFF LOW D. OFF OFF Page 67 of 75 Question:
(1 point) 68ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following plant conditions: SBLOCA has occurred on Unit 1 Reactor Building Pressure = 11.2 psig slowly decreasing Unit 2 Reactor Power = 100%
Which ONE of the following describes the actions directed (if any) by Enclosure 5.1 (ES Actuation) to ensure the required LPSW flow exists in the 1A LPI cooler?
A. Place 1LPSW-251 in "Failed Open" ONLY B. Place 1LPSW-251 in "Failed Open" AND fully open 1LPSW-4 C. Place 1LPSW-251 in "Failed Open" AND Throttle LPSW flow to approximately 3000 gpm using 1LPSW-4 D. Place 1LPSW-251 in "Failed Open" AND Throttle LPSW flow to approximately 5200 gpm using 1LPSW-4 Page 68 of 75 Question:
(1 point) 69ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions:Initial conditions: Reactor power = 100% Loss of offsite power occurs Current conditions: Main Feeder Buses remain de-energized
- 1) The position of 1MS-112 (SSRH Control) is __(1)__.
- 2) 1MS-77 (MS to MSRH) __(2)__ be operated from the control room switch.
Which ONE of the following completes the statements above?
A. 1. open 2. can B. 1. closed 2. can C. 1. open 2. can NO T D. 1. closed 2. can NO T Page 69 of 75 Question:
(1 point) 70ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor Power = 50% 1A Turbine Bypass Valve fails OPEN Which ONE of the following describes the plant response?
ASSUME NO OPERATOR ACTIONS Reactor power will...
A. Increase then return to pre-transient level.
B. Increase and stabilize at a higher power level.
C. Decrease then return to pre-transient level.
D. Decrease and stabilize at a lower power level.
Page 70 of 75 Question:
(1 point) 71ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 1 conditions: Reactor Power = 80% stable ICS in Manual 1B Main Feedwater Pump trips Which ONE of the following is the MAXIMUM power level allowed in accordance with AP/1 (Plant Runback).
A. 74% B. 65% C. 60% D. 55% Page 71 of 75 Question:
(1 point) 72ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following Unit 3 conditions: Initial conditions: Reactor tripped from 35% power due to 3TA lockout 3A Main FDW pump operating 3FDW-35 & 3FDW-44 (3A and 3B Startup FDW Control) in MANUAL 3A and 3B SG levels = 38" SU and stable Current conditions: 3FDW-35 & 44 are placed in Automatic Which ONE of the following describes the response of 3FDW-35 & 44?
A. Travel open to increase SG levels to 240" XSUR.
B. Travel open to increase SG levels to 50% on Operating level.
C. Travel closed to decrease SG level to 30" on XSUR.
D. Travel closed to decrease SG level to 25" on SU level.
Page 72 of 75 Question:
(1 point) 73ILT44 ONS RO NRC Examination Oconee Nuclear Station Which ONE of the following describes the:
- 2) method used to determine if Main Feedwater backleakage into the EFDW discharge piping is occurring?
A. 1. Vapor binding of the EFDWpumps2. locall y monitorin g EFDW pump dischar ge piping for increasin g temperature B. 1. Vapor binding of the EFDWpumps2. Monitorin g EFDW temperature OAC points fo rincreasin g temperature C. 1. Overpressurizing the EFDW system piping 2. locall y monitorin g EFDW pump dischar ge piping for increasin g temperature D. 1. Overpressurizing the EFDW system piping 2. Monitoring EFDW temperature OAC points for increasing temperature Page 73 of 75 Question:
(1 point) 74ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following plant conditions: No Keowee Units are operating ACB-3 closed
- 1) KHU 1X switchgear is being powered from __ (1) __.
- 2) Keowee control power will be available for a MINIMUM of approximately __ (2) __ hour(s) following a loss of ALL AC power.
Which ONE of the following completes the statements above?
A. 1. 1TC 2. one B. 1. 1TC 2. four C. 1. the 230 KV switchyard 2. one D. 1. the 230 KV switch yard 2. four Page 74 of 75 Question:
(1 point) 75ILT44 ONS RO NRC Examination Oconee Nuclear Station Given the following plant conditions: 3CA Battery Charger fails - output voltage = 0 VDC 3CA Battery voltage = 120 VDC 3DCB Bus voltage = 123 VDC Unit 1 DCA/DCB Bus voltage = 125 VDC Unit 2 DCA/DCB Bus voltage = 127 VDC Which ONE of the following will automatically supply power to 3DIA panelboard?
A. 3CA Battery B. Unit 1 DC Bus C. 3DCB Bus D. Unit 2 DC Bus Page 75 of 75 Examination KEY for:ILT4 4 ONS RO NRC ExaminaQuestionNumberAnswer1B2B3C4C5B6A7D8B9A10A11A12C13D14C15B16C17D18D19B20C21D22A23B24B25DPrinted 12/19/2013 7:45:04 AMPage 1 of 3 Examination KEY for:ILT4 4 ONS RO NRC ExaminaQuestionNumberAnswer26A27C28A29C30D31D32D33C34A35A36C37B38C39C40A41B42A43C44A45D46A47C48C49D50DPrinted 12/19/2013 7:45:11 AMPage 2 of 3 Examination KEY for:ILT4 4 ONS RO NRC ExaminaQuestionNumberAnswer51B52B53D54D55B56C57C58A59B60D61C62A63A64B65B66B67B68B69D70A71B72D73A74A75BPrinted 12/19/2013 7:45:11 AMPage 3 of 3