ML14007A062
| ML14007A062 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/07/2014 |
| From: | Division of Nuclear Materials Safety II |
| To: | |
| References | |
| 50-327/13-302, 50-328/13-302 | |
| Download: ML14007A062 (29) | |
Text
76. 008 AG2.1.7 576/BANK/SQN/HlGIIERI/SRO/SEQUOYAH/1311/NO Given the following plant cond itions:
Unit 1 is at 100% RTP when a pressurizer safety valve failed open.
- The operator manually tripped the reactor and initiated a safety injection.
When the crew transitions to E-1 , "Loss of Secondary or Reactor Coolant",
the following plant cond itions are observed:
PZR pressure 1580 psig and lowering Containment pressure reached 2.6 psig and is now stable.
Just prior to performing step 14, "Initiate evaluation of plant status:" as PZR pressure reached 1280 psig (its lowest recorded value) the PZR safety valve has closed.
Current plant conditions are:
Pressurizer level is 100%
PZR pressure 1390 psig and rising RCS subcooling is 42°F
- All four SG levels at 33% narrow range and stable Containment pressure is 2.4 psig and slowly lowering Which ONE of the following identifies the required procedure implementation and operation of the RCPs for the above cond itions?
A. Transition from E-1 to ES-1.1, S l Termination ;
The RCPs wil l have remained running throughout the event.
B. Transition from E-1 to ES-1 .1, S l Termination; The RCP(s) would have been shutdown, but will be restarted in ES-1.1 , S l Termination.
C. Continue E-1 until a transition is directed to ES-1.2, Post LOCA Cooldown; The RCPs will have remained running throughout the event.
D. Continue E-1 until a transition is directed to ES-1.2, Post LOCA Cooldown; The RCP(s) would have been shutdown, but will be restarted in ES-1.2, Post LOCA Cooldown.
Monday, November 18, 20131:10:27 PM 76
- 77. 011 EA2.05 677/NEW//HIGHERJ/SRO/SEQUOYAH/1311/NO Given the following plant conditions:
Unit 1 was operating 100% RTP.
- The 1A-A CCP tagged for maintenance due to an oil leak.
- A LOCA occurred an hour ago.
During the performance of ES-1.3, "Transfer to RHR Containment Sump,"
containment sump valves 1-FCV-63-72 and 1-FCV-63-73 could not be opened.
- The crew entered ECA-1.1, "Loss of RHR Sump Recirculation."
- While performing step 20 "Monitor if ECCS flow should be terminated," the crew observes the following parameters:
- All RCPs are OFF
- RVLIS Low Range is 70% and stable
- Subcooling is 50°F and stable
- RCS pressure is 150 psig and stable
- RWST level is 20% and lowering
- CTMT pressure is 3.0 psig and slowly lowering Which ONE of the following identifies:
(1) in accordance with ECA-1.1, an action that you w ill direct the crew to take AND (2) if the 1B-B CCP tripped immediately after the start of the accident, the Design Basis for this accident being met?
A. (1) Stop and Start ECCS pumps as necessary to establish minimum ECCS flow.
(2) is B. (1) Reset Phase A and Phase B, and stop RHR pumps, Sl pumps and all but one CCP.
(2) is C. (1) Stop and Start ECCS pumps as necessary to establish minimum ECCS flow.
(2) is NOT D. (1) Reset Phase A and Phase B, and stop RHR pumps, Sl pumps and all but one CCP.
(2) is NOT Monday, November 18, 2013 1:10:27 PM 77
- 78. 025 AA2.01 578/NEW//HIGHER//SRO/SEQUOYAH/ 131 1/NO Given the following plant conditions:
Unit 1 is in Mode 6 with the reactor vessel head being de-tensioned.
- The following plant parameters:
RHR pump 1A-A is in service with flow at 3000 gpm.
1A-A RHR pump amps = 20 amps RHR discharge pressure= 80 psig RCS pressure 0 psig .
- An equipment malfunction occurs which results in the following plant parameters:
1A-A RHR pump flow= 0 gpm 1A-A RHR pump amps = 3 amps RHR discharge pressure= 20 psig Which ONE of the following identifies both; (1) the equipment malfunction that occurred AND (2) in accordance with Tech Spec 3.9.8, "Residual Heat Removal and Coolant Circulation", bases, the requirement for having two RHR loops OPERABLE?
A. 1A-A RHR pump shaft shear to ensure a single failure of an RHR loop does NOT result in a complete loss of residual heat removal capability.
B. 1A-A RHR pump shaft shear to ensure adequate time is provided to initiate emergency procedures to cool the core.
C. FCV-63-93, RHR Cold leg to ensure adequate time is provided to initiate injection to Loops 2 & 3 closed emergency procedures to cool the core.
D. FCV-63-93, RHR Cold leg to ensure a single failure of an RHR loop does injection to Loops 2 & 3 closed NOT result in a complete loss of residual heat removal capability.
Monday, November 18, 20131:10:27 PM 78
- 79. 056 AG2.2.40 679/NEW/IHIGHER//SRO/SEQUOYAH/13 11!NO Given the following plant conditions:
Unit 2 is at 100% RTP.
Unit 1 is at 547°F and 2250 psig, reactor trip breakers are OPEN.
- The A-A EGTS fan is tagged out for maintenance.
- CSST "B" is tagged out for tap changer maintenance.
- At 0800,on 11/18 a malfunction in the switchyard causes off-site power to be lost to CSST "A."
If the above conditions associated with CSST "A" remain unchanged, in accordance with Tech Spec, which ONE of the following identifies the latest time Unit 2 would be required to be shutdown?
REFERENCE PROVIDED A. 2000 on 11/18 B. 2100on11/18 C. 2200on 11/18 D. 0800 on 11/25 Monday, November 18,20131:10:27 PM 79
- 80. 065 AA2.06 580/BANK/SQN/HIGHER//SRO/SEQUOYAH/1311/NO Given the following plant conditions:
Unit 1 is at 12% RTP during a plant startup.
- A loss of Essential and Non-Essential Control Air has occurred.
- The crew is attempting to restore Control Air in accordance with AOP-M.02, "Loss of Control Air."
- RCS temperature is 555°F and rising.
- PZR level is 72% and rising.
- SG NR levels are 15% and lowering.
Based on the current plant conditions, in accordance with AOP-M.02, wh ich ONE of the following indentifies:
(1) the reason a reactor trip is required ,
AND (2) if the action(s) required to control RCS temperature in AOP-M.02 can be performed concurrently with E-0?
A. (1) loss of PZR level control (2) yes B. (1) loss of PZR level control (2) no C. (1) loss of SG level control (2) yes D. (1) loss of SG level control (2) no Monday, November 18, 2013 1:10:27 PM 80
- 81. W/E04 EG2.4.18 58 1/BANK/SQN!HlGHER//SRO/SEQUOYAH/1201/NO Given the following plant conditions:
- The Unit 1 crew enters ECA-1.2 , "LOCA Outside Containment."
- When ECA-1 .2 is complete the following conditions exist:
- CNMT pressure is 0.1 psig and stable.
RWST level is 70% and lowering.
- CETs are indicating 51 ooF and stable.
RCS pressure is 800 psig and lowering.
RVLIS is 46% and slowly rising.
Which ONE of the following completes the statements below?
The crew is required to tra nsition to (1)
AND The Emergency Plan Classification for this event is a(n) (2)
REFERENCE PROVIDED A. (1) E-1 , "Loss of Reactor or Secondary Coolant" (2) Site Area Emergency B. (1) ECA-1.1 , "Loss of RHR Sump Recirculation" (2) Alert C. (1) E-1, "Loss of Reactor or Secondary Coolant" (2) Alert D. (1) ECA-1.1, "Loss of RHR Sump Recirculation" (2) Site Area Emergency Monday, November 18,20131:10:27 PM 81
- 82. 069 AG2. 1.23 682/BANK/SQN/HIGHER//SRO/SEQUOYAH/ 131 J/NO Given the following plant conditions:
Unit 1 is at 100% RTP.
- At 0900 the local leak rate test on the lower containment air lock test was performed following a containment entry and was NOT satisfactory.
- System Engineering reports that U1 overall containment leakage rate acceptance criteria is NOT met.
- At 1800 Unit 1 remains at 100% RTP.
Which ONE of the following identifies:
(1) if you are in compliance with Tech Spec AND (2) the Tech Spec basis for the maximum allowed total containment leakage (La)?
REFERENCE PROVIDED A. (1) no (2) To prevent exceeding the design capability of the EGTS B. (1 ) yes (2) To prevent exceeding the design capability of the EGTS C. (1) no (2) To prevent exceeding 10CFR1 00 limits at the site boundary D. (1 ) yes (2) To prevent exceeding 10CFR1 00 limits at the site boundary Monday, November 18, 201 3 1:10:27 PM 82
- 83. 076 AG2.4.46 583/NEW/SQN/HIGHER//SRO/SEQUOYAH/1311/NO Given the following plant conditions:
Unit 1 is at 100% RTP.
- At 0800 a dropped rod occurred.
- At 1200 the rod was recovered and power was restored to 100% RTP.
- At 1215 the following alarms were received panel 1-M12-A:
1-RA-90-1A, "AUX BLDG AREA RAD MONITOR HIGH," (A-7) 1-RA-90-59A, "RX BLDG AREA RAD MON HIGH," (B-3)
- At 1300 on 11/25 RCS Activity was determined to be 28 microcuries/gram DOSE EQUIVALENT 1-131 .
Which ONE of the following completes the statements below?
In accordance with AOP-R.06, "High RCS Activity," 1-RA-90-1A annunciator in alarm (1) consistent with the given plant cond itions.
AND In accordance with Tech Spec 3.4.8, "Specific Activity," the unit is required to be placed in Mode 3, with Tave < 500°F, NO later than (2)
REFERENCE PROVIDED A. (1) is (2) 1900 on 11/27 B. ( 1) is (2) 1900 on 11/25 C. (1) is NOT (2) 1900 on 11/27 D. (1) is NOT (2) 1900 on 11/25 Monday, November 18,20131:10:27 PM 83
- 84. W/E03 EA2. 1 6R4/NEW//HIGHER//SRO/SEQUOYAH/13 11/NO Given the following plant conditions:
Unit 1 was tripped from 100% RTP due to a Small Break LOCA.
Containment pressure peaked at 2.9 psig.
- The crew is performing ES-1.2, "Post LOCA Cooldown and Depressurization."
- The crew is evaluating step 37, "Determine if RHR should be placed in service:"
- The following parameters exist:
Both RHR pumps are stopped.
Normal charging has been established.
PZR level is 28% and stable.
RCP #2 is the only RCP running.
RCS pressure- 290 psig and slowly trending down.
RCS temperature- 340°F and slowly trending down.
Containment pressure - 1.1 psig and slowly trending down.
RCS cooldown rate is 75°F/hr.
Which ONE of the following complete the statements below?
The maximum cooldown rate allowed during the performance of ES-1.2 (1) being exceeded.
AND With the above conditions, the SRO will direct the crew to _ _.(=2.~-)_with TSC concurrence.
A. (1) is (2) transfer to ES-1.4, "Transfer to Hot Leg Recirculation",
B. (1) is (2) place RHR in service in accordance with EA-74-1, "Placing RHR Shutdown Cooling in Service,"
C. (1) is NOT (2) transfer to ES-1.4, "Transfer to Hot Leg Recirculation",
D. (1) is NOT (2) place RHR in service in accordance with EA-74-1 , "Placing RHR Shutdown Cooling in Service,"
Monday, November 18,20131:10:27 PM 84
- 85. W/E07 EA2.2 585/BANK/WBN/HTGHER//SRO/SEQUOYAH/l 3l l/NO Given the following plant conditions:
While operating at 100% RTP, a small break LOCA occurred on Unit 1.
- The operating crew has progressed through the emergency instructions and has placed RHR Train A in service in accordance with EA-74-1, "Placing RHR Shutdown Cooling In Service," during performance of ES-1.2, "Post LOCA Cooldown and Depressurization."
- The STA identifies a YELLOW path to FR-C.3, "Saturated Core Cooling,"
and the SRO makes the transition.
Which ONE of the following completes the statements below?
The basis of FR-C.3 is to (1)
AND After entering FR-C.3, a transition to AOP-R.03, "RHR System Malfunctions,"
(2) be directed.
ill ill A. establish RCS cooling via SGs will B. establish RCS coo ling via SGs will NOT C. restore subcooling using ECCS wi ll D. restore subcooling using ECCS will NOT Monday, November 18 , 2013 1:10:27 PM 85
- 86. 005 A2 .0 I 586/NEW//HIGHER//SRO/SEQUOYAli/1311/NO Given the following plant conditions:
- Unit 1 is performing a plant shutdown in accordance with 0-G0-7, "Unit Shutdown From Hot Standby To Cold Shutdown."
- When the 1B-B RHR pump was started for boron sampling, it experienced excessive vibration and is tagged out of service.
- Current plant conditions are:
RCS temperature= 260°F RCS pressure = 290 psig
- SG conditions:
- 1 #2 #3 #4 5% Wide Range 20% Narrow Range 8% Narrow Range 15% Wide Range RCP Tagged RCP Running RCP available RCP Tagged
- During post work review, I&C technicians report to the WCC SRO that the flow transmitter for 1-FCV-74-12A, RHR Pump 1A Mini-flow valve, has failed high.
Which ONE of the following completes the statements below?
Prior to taking any operator action the 1A-A RHR pump is (1)
AND in accordance with Tech Spec 3.4.1.3, "Reactor Coolant System- Shutdown," bases, the LCO requirements for this specification (2) being met.
A. ( 1) OPERABLE (2) are B. (1) OPERABLE (2) are NOT C. (1) INOPERABLE (2) are D. (1) INOPERABLE (2) are NOT Monday, November 18, 201 3 1:10:27 PM 86
- 87. 008 G2.4.30 387/NEW//LOWERJ/SRO/SQN/1311/NO Given the fo llowing plant cond itions:
- Both Units are at 100% RTP.
Due to a potential breaker failure , the C-S CCS pump has been powered from its alternate power supply (1 A2 480V SDBD) in accordance with 0-S0-70-1 ,"
Component Cooling Water System "B" Train."
- The Train B power supply fo r the C-S CCS pump will not be available for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
In accordance with NPG-SPP-03.5 , "Regulatory Reporting Requirements," which ONE of the following identifies the Unit(s), if any, whose operating conditions, is/are required to be reported to the NRC within 4 hrs?
REFERENCE PROVIDED A. Neither Unit B. Unit 1 ONLY C. Unit 2 ONLY D. Both Unit 1 & Unit 2 Monday, November 18,20131:10:27 PM 87
- 88. 026 G2.2.25 588/NEW/IHIGHER!/SRO/SQN/l311/NO Given the following plant conditions:
Unit 1 is being shutdown for refueling.
=
RCS Tavg 250°F
=
PZR pressure 290 psig
- #2 RCP is running
- The "1 B" train of RHR is being placed in service per 0-S0-74-1, "Residual Heat Removal System."
In accordance with Tech Spec 3.6.2.1, "Containment Spray Subsystems,"
(1) RHR spray operability _ _ _ required for this plant condition AND (2) the action(s) that is/are required by 0-S0-74-1, to comply with Tech Spec 3.6.2.1, bases?
A. (1) is (2) Close FCV-74-3, RHR Pump A suction isolation.
B. (1) is (2) Ensure RHR pump A is aligned for auto start or an operator is standing by panel M6 to manually start the pump if required.
C. (1) is NOT (2) Close FCV-74-3, RHR Pump A suction isolation.
D. (1) is NOT (2) Ensure RHR pump A is aligned for auto start or an operator is standing by panel M6 to manually start the pump if required .
Monday, November 18, 2013 1:10:27 PM 88
- 89. 062 A2.07 589/NEW//HIGHER//SRO/SQN/ 131 !/NO Given the following plant conditions:
Units 1 and 2 are operating at 100% RTP.
- The intertie transformer is OOS.
- While removing the Widow's Creek 500 kV line from service, a human performance error results in a complete loss of the 500kV switchyard.
Which ONE of the following completes the statements below?
In accordance with Tech Spec 3.8.1, "AC Sources and Onsite Power Distribution Systems" bases, Offsite power is Operable for ( 1)
AND The procedure that you will direct the crew to use to mitigate the event on Unit 1 is (2)
A. (1) Unit 2 ONLY (2) AOP-P.01, "Loss of Offsite Power" B. (1) both Unit 1 and Unit 2 (2) ES-0.1, "Reactor Trip Response."
C. (1) Unit 2 ONLY (2) ES-0.1, "Reactor Trip Response."
D. (1) both Unit 1 and Unit 2 (2) AOP-P.01, "Loss of Offsite Power" Monday, November 18, 2013 1:10:27 PM 89
- 90. 063 G2.4.31 590/BANK/SQN/HIGHER//SRO/SEQUOYAH/ 1311/NO Given the following plant conditions:
- Unit 1 is in Mode 3.
- The following alarms are received in the control room panel1 M-C:
- "125V DC VITAL CHGR II FAILURE OR VITAL BAT II DISCHARGE" (B4)
- "125V DC VITAL BAT BD II ABNORMAL" (B5)
- Battery Board II Voltage indicates 119 VDC.
Based on the above conditions, in accordance with Tech Spec 3.8.2.3, "D.C. Distribution- Operating," Battery Board II is (1)
AND in accordance with 0-S0-250-1 , "125 Volt de Vital Battery Boards" (2)
A. (1) INOPERABLE (2) align the Spare Charger B. ( 1) INOPERABLE (2) Reduce Battery loading C. (1) OPERABLE (2) Align the Spare Charger D. (1) OPERABLE (2) Reduce Battery loading Monday, November 18, 201 3 1:10:27 PM 90
1311 ILT SRO EXAM 91 . 002 G2.2.37 59 1/BANK/SQN/HJGHER//SRO/SEQUOY AHJ l/2009 RETAKE/NO Given the following plant conditions:
Unit 1 is in Mode 3 following a planned shutdown for maintenance.
- The unit is being cooled down in accordance with G0-7, "Unit Cooldown from Hot Standby to Cold Shutdown."
Current RCS temperature is 465°F and pressurizer pressure 1535 psig.
- A pressurizer PORV spuriously opened.
Which ONE of the following identifies:
(1) the procedure required to be entered to address the failure, AND (2) in accordance with Tech Spec 3.4.3 "Safety and Relief Valves- Operating,"
bases, assuming the PORV can be opened and closed using its control switch, the PORV is ?
( 1) (2)
Proced ure PORV Status A. AOP-R.05, "RCS Leak and Operable Leak Source Identification" B. AOP-R.05, "RCS Leak and Inoperable Leak Source Identification" C. AOP-1.04, "Pressurizer Instrument Operable and Control Malfunctions" D. AOP-1.04, "Pressurizer Instrument Inoperable and Control Malfunctions" Monday, November 18,2013 1:10:27 PM 91
13111LTSROEXAM
- 92. 028 G2.1 .32 592/I3ANK/SQN/HIGI IER//SRO/SEQUOYAI I/ 1311/NO Given the following plant conditions:
- A vapor space LOCA occurred on Unit 1.
Some fuel damage was experienced during the accident.
- The LOCA has been stopped and the Safety Injection has been terminated.
The operating crew has transitioned to FR-1.3, "Voids in Reactor Vessel," and is currently addressing the steps to prepare for and execute venting the reactor vessel.
The following conditions are reported to exist:
PRT pressure is 5 psig Containment hydrogen concentration is 6.3%
Containment Pressure is 0.29 psid Neither Air Return Fan is available Which ONE of the following identifies .. .
(1) the actions directed by the procedure relative to Hydrogen Recombiner operation AND (2) the action that would be directed associated with reactor vessel venting?
Hydrogen Reactor Vessel Recombiner Venting A. Would be placed Vent the vessel before transitioning in service. from FR-1.3.
B. Would be placed Return to procedure and step in effect without in service. venting the reactor vessel.
C. Would NOT be Vent the vesse l before transition ing placed in service. from FR-1.3.
D. Would NOT be Return to procedure and step in effect without placed in service. venting the reactor vessel.
Monday, November 18,2013 1:10:27 PM 92
- 93. 079 A2.0 1 593/BANK/SQN/LOWER//SRO/SEQUOY Al I/1 311/NO Given the following plant conditions:
Unit 1 in Mode 3 with the RCS at normal operating temperature and pressure preparing for reactor startup.
- Alarm "PS-32-104 TRAIN A AUX CONTROL AIR PRESS LOW" (M15-B) is actuated.
- Control Air pressure indications are:
- P l-32-200 Control Air Header pressure is 65 psig and lowering .
Pl-32-1 04 Aux Bldg Control air header A pressure is 65 psig and lowering.
Pl-32-105 Aux Bldg Control air header B pressure lowered to 82 psig and is now rising.
Which ONE of the following completes both statements?
AOP-M.02 , "Loss of Instrument Air," directs the crew to ensure _ ......(....:..1.~.--)_ are closed.
AND In accordance with Tech Spec, the Turbine Driven AFW pump _ _.(=2.._)_ required to be declared INOPERABLE.
Note:
0-FCV-32-82, Aux. Compsr. A-A Aux. Bldg /sol.
0-FCV-32-85, Aux. Compsr. 8-B Aux. Bldg /sol.
1-FCV-32-80, Unit 1 Train A Rx Bldg /sol.
1-FCV-32-102, Unit 1 Train B Rx Bldg /sol.
A. ( 1) 0-FCV-32-82 and 0-FCV-32-85 (2) is NOT B. (1) 1-FCV-32-80 and 1-FCV-32-102 (2) is C. (1) 0-FCV-32-82 and 0-FCV-32-85 (2) is D. ( 1) 1-FCV-32-80 and 1-FCV-32-1 02 (2) is NOT Monday, November 18,20 13 1:10:27 PM 93
- 94. G 2.1.42 094/BANK/SQN/LOWERI/SRO/SEQUOYAH/13 11/NO In accordance w ith FHI-3, "Movement of Fuel," which ONE of the following identifies the maximum number of NEW and IRRADIATED fuel assemblies within the areas listed below that can be located out of approved storage locations?
New Fuel Assemblies Irradiated Fuel Assemblies within the fuel-handling area within the refueling cana l A. 1 2 B. 1 3 C. 2 2 D. 2 3 Monday, November 18,2013 1:10:27 PM 94
- 95. G 2.2.15 295/NEW//LOWER//SRO/SQN/ 1311/NO Which ONE of the following completes the statements below (consider each statement separately)?
In accordance with NPG-SPP-1 0.1, "System Status Control," the _ _.(-'-1._)_ is responsible for authorizing the relaxation of status control.
Maintenance requests that an additional drain valve be opened, which is located inside a clearance isolation boundary. The NPG-SPP-1 0.1, Attachment 3, "Deviation Tracking Sheet," (2) an allowable method to track the drain valve position.
A. (1) Plant Manager (2) is B. (1) Plant Manager (2) is NOT C. (1) Operations Superintendent (2) is D. (1) Operations Superintendent (2) is NOT Monday, November 18,2013 1:10:27 PM 95
13111LT SROEXAM
- 96. G 2.2.20 196/BANK MOD/SQN/IIIGHER//SRO/SEQUOYAH/ 131 1/NO Given the following conditions:
Unit 2 is coming out of a refueling outage.
0-SI-SXV-074-203.2 , "Full Stroking of RHR Va lves 2-FCV-74-1 and 2-FCV-74-2" is being performed.
Personnel are in position and monitoring valve operation locally.
- 2-FCV-74-1 took 118.8 second s to open on first cycle.
- 2-FCV-74-1 took 87.5 seconds to close on first cycle.
- Valve operated smoothly and all indication worked properly.
Which ONE of the following identifies the current status of the valve?
REFERENCE PROVIDED A. Valve opening tim e is in the ALERT range.
Va lve is INOPERABLE .
B. Valve opening time is in the ALERT range.
Valve is OPERABLE .
C. Valve closing time is in the ALERT range.
Va lve is OPERABLE .
D. Valve closing time is in the ALERT range.
Valve is INOPERABLE .
Monday, November 18, 20131:10:27 PM 96
- 97. G 2.3.4 097/BANK/SQN/LOWERI/SRO/SQN/13 11/NO Given the following plant conditions:
A LOCA occurred on Unit 1 .
A Site Area Emergency has been declared.
The Containment Barrier is intact (i.e. no loss or potential loss of containment).
The Containment Critical Safety Function Status Tree (FR-Z) is Yellow due to high radiation in containment.
Containment pressure is 2.1 psig and decreasing.
There is no release to the environment in progress.
The "A" train of containment spray is operating normally for plant conditions.
The "B" containment spray pump tripped, 25 minutes ago, after pump amps were observed to be oscillating.
Authorization has been given for an emergency responder to receive an emergency exposure of 11 Rem TEDE in order to restore "B" train containment spray.
Which ONE of the following completes the statement below?
The emergency exposure authorization (1) the requirements of EPIP-15, "Emergency Exposure Guidelines," because _ _.(=2...._)_
ill ill A. met emergency exposure limits can always be authorized during any Site Area Emergency REP classification B. violated emergency exposure limits can only be authorized during a General Emergency REP classification C. met the emergency exposure was necessary to maintain critical safety functions D. violated the emergency exposure was NOT necessary to maintain critical safety functions Monday, November 18, 20131:10:27 PM 97
- 98. G 2.3.7 398/BANK// LOWERJ/SRO/SEQUOYAH/ 13 11 /NO Given the following plant conditions:
- A diving operation in the Spent Fuel Pit is planned to commence later in the shift.
Which ONE of the following completes the statements below?
The dive (1) the requirements of NPG-SPP-07.3, "Work Activity Risk Management Process," to be classified as a HIGH risk activity.
AND If the rad level in the area of the dive is estimated at 20 Rad/hr, in accordance with RCI-14, "Radiation Work Permit (RWP) Program," the RWP would be required to be approved by (2) ill A. meets Radiation Protection Manager only B. meets Radiation Protection Manager and Plant Manager C. does NOT meet Radiation Protection Manager only D. does NOT meet Radiation Protection Manager and Plant Manager Monday, November 18,20 131 :10:27 PM 98
- 99. G 2.4.35 599/BANKJDC COOK/IIIGHER//SRO/SEQUOYAH/131 1/
Given the following plant conditions:
0200 - Unit 2 is operating at 100% RTP when implementation of AOP-C.04, "Shutdown from Auxiliary Control Room," was required.
0204 - All main control room actions have been completed and the main contro l room is evacuated.
0212 - All transfer switches are placed in the requ ired position in accordance with AOP-C.04, Checklist 2, Unit 2 Auxiliary Control Room.
0218 - AUO reports 6.9Kv Shutdown Board equipment is configured in accordance with Checklist 4.
Which ONE of the following completes the statements below?
The cond itions require the declaration of a/an _.....~.(....:...
1 .L.. ) _ in accordance with the Radiological Emergency Plan.
AND (2) control is/are available for Pressurizer Backup Heaters 2A-A.
REFERENCE PROVI DED A. (1 ) Alert (2) ONLY manual B. (1) Alert (2) BOTH manual and automatic C. (1) Site Area Emergency (2) ONLY manual D. ( 1) Site Area Emergency (2) BOTH manual and automatic Monday, November 18,20131:10:27 PM 99
1311 ILT SRO EXAM 100. G 2.4.38 200/BANK MOD/SQN/liiGHER//SRO/SQN/ 13 11/NO Given the following plant conditions:
- A General Emergency has been declared due to a plant event that resu lted in a radiation release .
- The duration of the release is estimated to be 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- Wind Direction is from 181 degrees@ 10 mph.
Dose projections and surveys have not yet been performed Which ONE of the following identifies the Protective Action Recommendations required in accordance with EPIP-5, "General Emergency?"
REFERENCE PROVIDED A. Shelter the entire 10 mile EPZ, consider issuance of Kl in accordance with the State Plan.
B. Evacuate A1-B1-C1-01 , A2, A3 and 82. Shelter the remainder of the 10 mile EPZ.
C. Evacuate A 1-B1-C1 -01, A2 and 82. Shelter the remainder of the 10 mile EPZ.
D. Evacuate A1-B1-C1-D1, A2, -5, -6, 82, -3, -4. Shelter the remainder of the 10 mile EPZ.
You have completed the test!
Monday, November 18, 2013 1:10:27 PM 100
ANSWER KEY REPORT for 1311 ILT SRO EXAM Test Form: 0 Answers
- ID Points Type 0 007 EK2.02 501 1.00 MCS A 2 009 EA2.11 602 1.00 MCS c 3 015 AK1.01 503 1.00 MCS A 4 025 AK3.02 504 1.00 MCS A 5 026 AA1.01 205 1.00 MCS D 6 027 AK1.02 106 1.00 MCS D 7 038 EG2.4.31 507 1.00 MCS D 8 055 EA2.03 8 1.00 MCS A 9 056 AG2.1.20 609 1.00 MCS A 10 057 AA1.04 410 1.00 MCS B 11 058 AK3.01 211 1.00 MCS B 12 062 AA2.06 512 1.00 MCS B 13 065 AK3.04 13 1.00 MCS c 14 077 AG2.2.42 214 1.00 MCS A 15 W/E04 EK2.2 15 1.00 MCS D 16 W/E05 EK1.3 516 1.00 MCS D 17 W/E11 EA1.3 517 1.00 MCS A 18 W/E12 EK2.1 118 1.00 MCS A 19 001 AA1.04 119 1.00 MCS D 20 036 AK3.02 520 1.00 MCS c 21 037 AKI.02 621 1.00 MCS A 22 051 AA2.02 522 1.00 MCS D 23 068 AA2.05 623 1*.oo MCS B 24 076 AK2.0 1 524 1.00 MCS c 25 W/E02 EG2.2.44 625 1.00 MCS A 26 W/E03 EK2.2 26 1.00 MCS D 27 W/E08 EK3.3 527 1.00 MCS A 28 003 K6.14 628 1.00 MCS B 29 004 K2.02 29 1.00 MCS A 30 004 K3.06 30 1.00 MCS D 31 005 K5 .03 531 1.00 MCS B 32 006 A4.01 32 1.00 MCS B 33 007 K5 .02 633 1.00 MCS A 34 008 K3.03 534 1.00 MCS B 35 010 Kl.08 35 1.00 MCS A 36 012 A2.05 636 1.00 MCS D 37 013 K2.01 537 1.00 MCS D 38 022 A3.01 38 1.00 MCS D 39 022 K3 .01 39 1.00 MCS B 40 025 A3.02 40 1.00 MCS c 41 026 G2.2.36 541 1.00 MCS c 42 039 A4.04 42 1.00 MCS D 43 059 A2.11 43 1.00 MCS B 44 059 K4.16 44 1.00 MCS B 45 061 Kl.07 45 1.00 MCS A 46 061 K6.01 146 1.00 MCS D Friday, December 20, 2013 2:28:11 PM 1
ANSWER KEY REPORT for 1311 ILT SRO EXAM Test Form: 0 Answers
- ID Points Type 0 47 062 Al.Ol 547 1.00 MCS c 48 063 Al.Ol 348 1.00 MCS c 49 063 A2.0149 1.00 MCS B 50 064 G2.4.4 550 1.00 MCS B 51 073 K4.01 551 1.00 MCS c 52 076 A3 .02 552 1.00 MCS A 53 076 K2 .04 53 1.00 MCS B 54 078 Kl.04 54 1.00 MCS D 55 103 K4.04 655 1.00 MCS B 56 001 K4.23 556 1.00 MCS c 57 011 K6.04 557 1.00 MCS B 58 015 Al.Ol 558 1.00 MCS D 59 028 K5 .04 59 1.00 MCS A 60 041 K2.02 560 1.00 MCS B 61 045 K3 .01 661 1.00 MCS A 62 055 A3 .03 562 1.00 MCS A 63 056 A2 .04 63 1.00 MCS A 64 072 A4.01 564 1.00 MCS A 65 075 G2.4.1 665 1.00 MCS D 66 G 2.1.32 566 1.00 MCS D 67 G 2.1.45 467 1.00 MCS A 68 G 2.2.14 568 1.00 MCS A 69 G 2.2.22 569 1.00 MCS c 70 G 2.2.38 70 1.00 MCS B 71 G 2.3 .13 571 1.00 MCS D 72 G 2.3.14 672 1.00 MCS ..-IV' c ~ i 2../-:l-o fo A k:., ~ t2/SI jfj 73 G 2.3.4 573 1.00 MCS B 74 G 2.4.20 574 1.00 MCS D 75 G 2.4.25 575 1.00 MCS c SECTION 1 ( 75 items) 75.00 Friday, December 20, 2013 2:28:11 PM 2
ANSWER KEY REPORT for 1311 ILT SRO EXAM Test Form: 0 Answers
- ID Points Type 0 008 AG2 .1.7 576 1.00 MCS A 2 011 EA2.05 677 1.00 MCS c 3 025 AA2 .01 578 1.00 MCS A 4 056 AG2 .2.40 779 1.00 MCS c 5 065 AA2.06 680 1.00 MCS A 6 W/E04 EG2.4.18 581 1.00 MCS D 7 069 AG2 .1.23 682 1.00 MCS c 8 076 AG2.4.46 583 1.00 MCS B 9 W/E03 EA2.1 684 1.00 MCS D 10 W /E07 EA2.2 585 1.00 MCS c 11 005 A2.01 586 1.00 MCS c 12 008 G2.4.30 487 1.00 MCS c 13 026 G2.2.25 588 1.00 MCS c 14 062 A2.07 589 1.00 MCS B 15 063 G2.4.31 590 1.00 MCS A 16 002 G2.2.37 591 1.00 MCS c 17 028 G2.1.32 592 1.00 MCS D 18 079 A2.01 593 1.00 MCS A 19 G 2.1.42 94 1.00 MCS B 20 G 2.2.15 295 1.00 MCS c 21 G 2.2.20 196 1.00 MCS B 22 G 2.3.4 97 1.00 MCS D 23 G 2.3.7 498 1.00 MCS A 24 G 2.4.35 599 1.00 MCS B 25 G 2.4.38 200 1.00 MCS c SECTION 1 ( 25 items) 25.00 Friday, December 20, 2013 2:28:43 PM 1
References for 1311 NRC SRO Exam
- 1. Steam Tables
- 2. Mollier Diagram
- 3. Unit 1 Tech Spec LCO 3.6.1.8 Emergency Gas Treatment System - EGTS -
Cleanup Subsystem, Amendment 263 (2 pages - 3/4 6-13 and 3/4 6-14)
- 4. Sequoyah EPIP-1 Emergency Plan Classification Matrix, rev 50 (2 pages 11 and 12 of 49)
- 5. Unit 1 Tech Spec 3/4.4.8 Specific Activity, Amend 301 (page 3/4 4-19)
- 6. ASME Code Valve Testing 0-SI-SXV-074-266.0, Rev 0021 (pages 1 - 19)
- 7. SQN Unit 0 EPIP-5 General Emergency, Rev 0044 Appendix A (page 1 of 1) and Appendix H (2 pages 1 & 2 of 2)
- 8. NPG-SPP-3.5, Regulatory Reporting Requirements, rev 0008 Appendix A (pages 19-33)
- 9. Sequoyah EPIP-1 Emergency Plan Classification Matrix, rev 50 Sect 4 (pages 25-32)