ML061240560
| ML061240560 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/01/2005 |
| From: | Operations Branch IV |
| To: | Southern California Edison Co |
| References | |
| 50-361/05-301, 50-362/05-301 | |
| Download: ML061240560 (101) | |
Text
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Group # 1 _____
K/A # A08/AK3.05 Importance Rating 4.0 _____
- 1. Given the following conditions for Unit 3:
-plant trip from 100% power due to pipe rupture upstream of PSV-200, safety valve
-All safeguards equipment responded per design
-The crew has just completed all procedural steps up to the floating step FS-7 for SI Throttle/Stop Actions for Procedure EOI SO23-12-3, Loss of Coolant Accident.
Of the steps required for SI Throttle/Stop criteria, what is the reason for verifying RCS sub-cooling with Core Exit Saturation Margin (REP CET)?
A. The QSPDS system is not physically wired to the HJTCs.
B. The REP CETs trend closer to Thot RTDs (used in accident analysis by CE owners group).
C. The range is too large in natural recirculation mode using RVUH RTDs.
D. The REP CETs are calculated in a manner that results in the lowest sub-cooling margin.
Proposed Answer: ___D___
Explanation (Optional):
The REP CETs are calculated by QSPDS using statistical analysis in order to provide a higher temperature and lower or more conservative sub-cooling margin. HJTCs and Thot RTDs are not used because of sub-cooling differences between loops and the vessel head area.
Technical Reference(s): EOI SO-23-12-11 (FS-7), EOI SO23-12-3, and CE Loss of Coolant Accident Recovery Guideline (bases), rev 6, attachment 1, page 9.
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam __N/A__
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis _ X _
10 CFR Part 55 Content: 55.41 __7__
55.43 _____
Comments:
A08/AK3.05 & 4.0 - Pressurizer Vapor Space Accident/Knowledge of the reasons for the following responses as they apply to the Pressurizer Vapor Space Accident: ECCS termination or throttling criteria
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Group # 1 _____
K/A # E09/EA1.14 _____
Importance Rating 3.4 _____
- 2. While performing a heat treat on Unit 3,
- A small break LOCA occurs and SIAS actuates
- All systems are responding as expected
- The condenser is in alarm for low vacuum as a result of the heat treat; main condenser backpressure is 5.8" Hg abs and steady EOI SO23-12-11 Attachment 3, Cooldown/Depressurization, is being implemented. Under the current plant conditions, Attachment 3 directs the RCS cooldown to be accomplished by A. allowing the ADVs to function in automatic mode B. overriding and operating the ADVs manually C. operating the SBCS manually D. allowing the SBCS to function in automatic mode Proposed Answer: __C___
Explanation (Optional): Attachment 3 directs use of SBCS for cooldown if condenser backpressure is less than the SBCS Interlock (which is 10" Hg).
Technical Reference(s): _________________________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New __ X___
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content: 55.41 _10__
55.43 _____
Comments:
E09/EA1.14 & 3.4 - Small Break LOCA/Ability to operate and monitor the following as they apply to a small break LOCA: Secondary Pressure Control.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Group # 1 _____
K/A # A15/17/AK1.05 ____
Importance Rating 2.7 _____
- 3. Given the following conditions for Unit 2 with power at 100%:
- LOCAL POWER DENSITY HI PRETRIP Alarm activates in the control room (Window 56A13)
- RCP 1B flow indicates slightly less than the other three RCPs
- COLSS is in service You have entered Procedure S023-2.30,Determination of Adequate Core Cooling, as directed from the Alarm Response Procedure. In this procedure you will need to compare actual data points to Acceptance Criteria in order to determine if:
A. Localized DNB exists and power should be reduced below the acceptance criteria in S023-2.30,Determination of Adequate Core Cooling.
B. Localized DNB exists and power should be reduced below the specified value in the Technical Specifications.
C. LPD margin from Tech Specs is zero and power should be reduced below the specified value in the Technical Specifications.
D. Azimuthal Tilt exceeds the limit specified in the Technical Specifications and should be reduced below the specified value in the Technical Specifications.
Proposed Answer: ___A__
Explanation (Optional): For a core flow imbalance above the reactor trip setpoint this alarm is one of many that indicates a DNBR problem as specified in Procedure S023-2.30. The worksheet has the RO complete comparisons in order to determine if Localized DNB exists and if so then power should be reduced below the specified acceptance criteria. B is incorrect because it does not yet meet a TS requirement (pre-trips are below safety settings) while C is incorrect because the LPD is taken from COLSS when it is operating, not TS. D is incorrect because Azimuthal tilt acceptance criteria come from CPC, not TS.
Technical Reference(s): Procedure S023-2.30,Determination of Adequate Core Cooling page 6.
Alarm Response Instruction S023-15-56.A, page 31.
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content: 55.41 8, 10_
55.43 _____
Comments:
A15/17/AK1.05 & 2.7 - RCP Malfunctions/Knowledge of the operational implications of the following concepts as they apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow): Effects of unbalanced RCS flow on in-core average temperature, core imbalance, and quadrant power tilt.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Group # 1 _____
K/A # A22/AA2.01 _____
Importance Rating 3.2 _____
- 4. Unit 2 is at 100% Power with all systems in their respective at-power configurations and all controllers in auto per station procedures. The following annunciators are actuated:
[57C43] RCS LEAKAGE ABNORMAL/RECIRC SYS VV MISALIGNED
[57C20] RCS LEAKAGE DETECTION ACTIVITY HI
[58A01] REGEN HX TSH 9267 LETDOWN TEMP HI
[58A31] REGEN HX TSH 0221 LETDOWN TEMP HI Pressurizer (PZR) level is 51% and dropping slowly Ion exchange bypass valve TV-0224B is in the VCT position Charging flow meter FI-0212 indicates 43gpm in the control room Letdown flow indicates 28gpm in the control room RCP seal injection and CBO flows are all within their normal bands The cause of the alarms is __________ .
A. A letdown line leak between the containment penetration and the letdown isolation valve TV-0221 B. A letdown line leak between the containment penetration and the containment isolation valve HV-9205 C. A charging line leak between the containment penetration and the Regen HX D. A charging line leak between the containment penetration and FE-0212 Proposed Answer: __C____
Explanation (Optional): C is correct because only a charging leak would provide larger charging flow than letdown flow and because the leak is adding coolant to the containment sump (alarms in stem) it is C and not D. A and B are incorrect because it is not a letdown leak.
Technical Reference(s): System description S023-390, page 80, Alarm response Instruction S023-15-57C, page 47 and 93, S023-13-14, S023-15-57, S023-15-58A, page 6.
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank #_______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X _
10 CFR Part 55 Content: 55.41 __3,7___
55.43 ____
Comments: A22/AA2.01 & 3.2 - Loss of reactor coolant make up/Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Pump Makeup: Whether a charging line break exists.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Group # 1 _____
K/A # A25/2.4.11 _____
Importance Rating 3.4 _____
- 5. Which of the following actions is the highest priority and thus performed FIRST in the Loss of Shutdown Cooling AOI?
A. Recover SDC Flow.
B. Recover RCS Inventory.
C. Ensure RCS dilutions are stopped.
D. Initiate Containment Closure and RCS Monitoring.
Proposed Answer: __D___
Explanation (Optional):
Technical Reference(s): __SO23-13-15_____________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _____55323_______________ (As available)
Question Source: Bank # _N4197_
Modified Bank # _______ (Note changes or attach parent)
New _______
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 __10___
55.43 _____
Comments: A25/2.4.11 & 3.4 - Loss of RHR System/Knowledge of abnormal conditions procedures.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __1__ _____
Group # __1__ _____
K/A # _ A26/AA1.05 _____
Importance Rating _3.1__ _____
- 6. Component Cooling Water System (CCW) loop A is lined up to provide cooling water to the non-critical loop with the CCW loop B non-critical loop isolation valves (HV-6213 and HV-6219) closed. A leak develops that results in a low-low level alarm for the CCW loop A surge tank (T-003). The operator should also observe a loss of CCW to the:
A. A Control Room Emergency Cooler.
B. Letdown Heat Exchanger.
C. CEDM Coolers.
D. Shutdown Cooling Heat Exchanger.
Proposed Answer: __C___
Explanation (Optional): With the CCW system in the stated configuration, a low low level alarm would also indication a closure of the non-critical isolation valves HV-6212 and HV-6218. This would result in a loss of CCW to all non-critical heat loads. All the answers provided are critical heat loads with the exception of the CEDM Coolers making C the only correct answer.
Technical Reference(s): __System Description SD-SO23-400, Revision 9, pages 4, 5, and 15.
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam __NA___
Question Cognitive Level: Memory or Fundamental Knowledge _X __
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 _(7)__
55.43 _____
Comments: A26/AA1.05 & 3.1 - Loss of Component Cooling Water/Ability to operate and/or monitor the following as they apply to the Loss of Component Cooling Water: The CCWS surge tank, including level control and level alarms, and radiation alarms.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _1___ _____
Group # _1___ _____
K/A # _ A27/AK1.01______
Importance Rating _3.1____ _____
- 7. With the plant operating at 50 percent power, a pressurizer pressure control malfunction has resulted in pressurizer pressure increasing while pressurizer temperature has remained constant. As pressurizer pressure increases, pressurizer saturation temperature will:
A. remain the same.
B. increase.
C. decrease.
D. depend on pressurizer spray enthalpy.
Proposed Answer: __B___
Explanation (Optional): As pressure goes up in a saturated water environment, saturation temperature also goes up making B the only correct answer.
Technical Reference(s): _Properties of Saturated and Superheated Steam Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New __X____
Question History: Last NRC Exam _NA____
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content: 55.41 __(5) 55.43 _____
Comments:
A27/AK1.01 & 3.1 - Pressurizer Pressure Control System/Knowledge of the operational implications of the following concepts as they apply to Pressurizer Pressure Control Malfunctions: Definition of saturation temperature.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _1___ _____
Group # _1___ _____
K/A # _E29/EA2.07_ _____
Importance Rating _4.2__ _____
- 8. The plant is operating at 100 percent power when the reactor operator receives several RPS annunciators. The operator also notices some of the RPS trip breakers have opened. If the plant is still at power, which of the following open trip breakers would indicate an ATWS is in progress?
A. Trip breakers 1, 2, 8, 9 indicate open.
B. Trip breakers 1, 2, 7, 8 indicate open.
C. Trip breakers 3, 4, 7, 8 indicate open.
D. Trip breakers 3, 4, 8, 9 indicate open Proposed Answer: __B___
Explanation (Optional): A combination of trip breakers must be open for a scram to occur.
Breakers 1 and 2 and breakers 7 and 8 must be open making B the correct answer.
Technical Reference(s): _System Description SD-SO23-710, Revision 4 Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content: 55.41 _(5) _
55.43 _____
Comments:
E29/EA2.07 & 4.2 - ATWS/Ability to determine or interpret the following as they apply to a ATWS:
Reactor trip breaker indicating lights.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _1___ _____
Group # _1___ _____
K/A # _A38/EK3.08________
Importance Rating _4.1__ _____
maintaining RCS pressure above the RCP NPSH trip criteria takes priority over reducing RCS pressure to within 50 psig of the ruptured SG. The reason for this change in priorities is that _______.
A. the SI Throttling Criteria; RCS inventory is assured.
B. the shutoff head of the SI pumps; pressurizer level can be recovered.
C. 1000 psia; the main steam safeties wont lift.
D. 1250 psia; the leak rate is within the capacity of the charging pumps.
Proposed Answer: ___C__
Explanation (Optional): The EOI bases document states maintaining RCS pressure above the NPSH trip criteria is more important than maintaining SG pressure within 50 psid of RCS pressure when RCS pressure reaches 1000 psia. This is because SG main steam safety valves will not lift. This makes answer C the only correct answer.
Technical Reference(s): _SO23-14-4, Revision 5, Attachment 1_
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam ___NA__
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 _(5) _
55.43 _____
Comments: Knowledge of the reasons for the following responses as they apply to SGTR: Criteria for securing RCP
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _1___ _____
Group # _1___ _____
K/A # _A40/2.3.2 ______
Importance Rating _2.5__ _____
- 10. A SG steam line rupture has occurred outside containment. The area around the steam line rupture is highly contaminated and has elevated dose rates. Consideration is being given to sending an individual into the area to close an important valve. Based on HP best estimates, the individual will receive the following doses:
Deep Dose Equivalent (DDE) = 750 mRem Total Organ Dose Equivalent (TODE) = 400 mRem Committed Effective Dose Equivalent (CEDE) = 250 mRem Committed Dose Equivalent (CDE) = 200 mRem Based on these estimates, the Total Effective Dose Equivalent (TEDE) for this job is:
A. 1600 mRem B. 1000 mRem C. 950 mRem D. 850 mRem Proposed Answer: __B___
Explanation (Optional): TEDE = DDE + CEDE = 750 + 250 = 1000 mRem Technical Reference(s): _10CFR20 Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New __X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content: 55.41 _____
55.43 _____
Comments: A40/2.3.2 - Steam Line Rupture - Excessive Heat Transfer /Knowledge of the facility ALARA program.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __1__ _____
Group # __1__ _____
K/A # _A54/AK3.01______
Importance Rating _4.1__ _____
- 11. The Unit 2 reactor was automatically tripped as a result of loss of both feedwater pumps. Which of the following was the cause of the loss of feedwater pumps?
A. Failure in the Three-Element Feedwater Control System.
B. Channel A CIAS actuation signal.
C. Failure of a single Second Point Heater.
D. Air supply failure to the condensate pumps suction valves.
Proposed Answer: __D____
Explanation (Optional):
Loss of air supply to the condensate pumps suction valves will cause the suction valves to close resulting in a trip of the condensate pumps and a loss of NPSH to the Main Feedwater Pumps causing a loss of feed and a reactor trip.
Technical Reference(s): __SO-23-240/250___ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __7___
55.43 _____
Comments: Knowledge of the reasons for the following responses as they apply to the Loss of Main Feedwater: Reactor and/or turbine trip, manual and automatic.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _1___ _____
Group # _1___ _____
K/A # _A55/EA2.03______
Importance Rating __3.9_ _____
- 12. The Station has experienced a station blackout. Which of the following is the preferred EOI method of powering the Unit 2 ESF 4160VAC buses?
A. A04 and A06 powered through breakers A0419 and A0616 B. A04 and A06 powered through breakers 2A0417 and 2A0619 C. A04 and A06 powered through breakers A0413 and A0613 D. A04 and A06 energized through breakers 3A0416 and 3A0603 Proposed Answer: ___C___
Explanation (Optional): If 220VAC offsite power source is lost, the DGs are the preferred power and lastly cross-tying to the opposite units DGs.
Technical Reference(s): SO23-12-11 Att 24; Att 6;SO23-12-8 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __10___
55.43 _____
Comments: Actions necessary to restore power.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _1___ _____
Group # _1___ _____
K/A # _A57/AA1.01______
Importance Rating _3.7__ _____
- 13. On a loss of vital AC, vital 120VAC power to panels Q062 and Q063 can be restored through which one of the following methods?
A. By transferring loads from the inverter to the line alternate source with switches YVS1, and YVS2.
B. By ensuring the unbalance between the sources is greater than 20 volts before operating the manual transfer switches.
C. By ensuring the sync monitor light is fully lit before operating the manual transfer switch.
D. By ensuring the solenoid in the manual transfer switch is de-energized.
Proposed Answer: __A____
Explanation (Optional):
Technical Reference(s): _____ SD-SO23-130________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __7___
55.43 _____
Comments: Ability to operate and/or monitor the following as they apply to the loss of vital AC bus:
Manual inverter swapping
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _1___ _____
Group # _1___ _____
K/A # _A58/AK3.01______
Importance Rating _3.4__ _____
- 14. A loss of 125VDC power (panel L160) has occurred for EDG 2G002. Which of the following best describes the operating condition of the emergency diesel?
A. The emergency diesel can be started locally.
B. The emergency diesel can be started but shutdown will be manual local action.
C. The emergency diesel can be started but will only have local governor control.
D. The emergency diesel should not be started and placed in maintenance lockout.
Proposed Answer: __D____
Explanation (Optional):
Technical Reference(s): ___ SO23-750/ SO23-5-2.35.1 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __7___
55.43 _____
Comments: Knowledge of the reasons for the following responses as they apply to the Loss of DC Power: Use of dc control power by D/Gs
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _1___ _____
Group # _1___ _____
K/A # _A62/2.1.27_______
Importance Rating _2.8__ _____
- 15. The Nuclear Service Water System serves which of the following functions?
A. Provides water to containment spray system during a Phase B actuation.
B. Provides demineralized water for normal fill of the CCW surge tanks.
C. Provides emergency makeup to the containment sumps and pumps.
D. Provides fire protection water source in case of fire in containment.
Proposed Answer: ___B___
Explanation (Optional):
Technical Reference(s): _________________________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __7___
55.43 _____
Comments: Knowledge of system purpose and or function.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __1__ _____
Group # __1__ _____
K/A # __A65/AA2.08_____
Importance Rating __2.9_ _____
- 16. Which of the following is a correct valve alignment for failure position upon a loss of air to the pneumatic valve operator?
A. Letdown flow control valve fails in the as-is position.
B. Letdown back pressure control valves fail open.
C. Spray valves PV-100A and PV-100B fail closed.
D. VCT inlet valve LV-0277A fails so flow goes to Radwaste.
Proposed Answer: __C____
Explanation (Optional):
Technical Reference(s): ____ SD SO23-390 ________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __7___
55.43 _____
Comments: Ability to determine and interpret the following as they apply to the Loss of Instrument Air:
Failure modes of air-operated equipment
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __1__ _____
Group # __1__ _____
K/A # __ 011-EK1.01 ___
Importance Rating _4.1__ _____
- 17. The plant has experienced a large break LOCA and all RCPs are currently tripped. Core cooling is currently being facilitated by natural circulation. According to EOI Loss of Coolant Accident, in order to establish shutdown cooling, T hot must be less than ______ degrees.
A. 260 B. 340 C. 350 D. 375 Proposed Answer: __D___
Explanation (Optional):
Technical Reference(s): _Loss of Coolant Accident, SO23-12-3, Revision 18, Step 20.
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New __X____
Question History: Last NRC Exam __NA___
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 _____
55.43 __(5)_
Comments: Knowledge of the operational implications of the following concepts as they apply to the Large Break LOCA: Natural Circulation and cooling, including reflux boiling.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _1___ _____
Group # _1___ _____
K/A # ___007-EK2.2 _
Importance Rating _3.5__ _____
- 18. According to the Standard Post Trip Actions emergency operating instruction, all reactor coolant pumps must be stopped if:
A. pressurizer pressure is less than 1430 psia.
B. containment pressure is greater than 3.4 psig.
C. loop differential temperature is less than 10 degrees.
D. both S/G levels are less than 21%.
Proposed Answer: __B___
Explanation (Optional): The referenced procedure requires ensuring all RCPs are stopped if containment pressure is greater than 3.4 psig.
Technical Reference(s): __SO23-12-1, Standard Post Trip Actions, Rev 19, step 8.a.3)
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam ___NA__
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 __(5)_
55.43 _____
Comments: Knowledge of the interrelations between the Reactor Trip Recovery and the following:
Facility heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __1__ _____
Group # __2__ _____
K/A # __051-A2.02___
Importance Rating _3.9_ _____
- 19. The main turbine trip setpoint associated with degraded condenser vacuum varies as a function of low pressure (LP) turbine load. With 100 percent LP load, the turbine would have to be tripped immediately if condenser vacuum degrades to:
A. 9.1 inches HgA B. 8.1 inches HgA C. 6.0 inches HgA D. 3.5 inches HgA Proposed Answer: __A___
Explanation (Optional): The operational limit for the turbine at 100 percent load is 9.1 inches HgA.
Technical Reference(s): Operating Instruction SO23-13-10, Loss of Vacuum, Revision 8, Attachment 3_
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 _(7) _
55.43 _____
Comments: Loss of Condenser Vacuum: Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum: Conditions requiring reactor and/or turbine trip.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __1__ _____
Group # __2__ _____
K/A # ____028-G2.2.23___
Importance Rating __2.6_ _____
- 20. A malfunction has developed in the pressurizer level control system and level is currently slowly increasing. What is the maximum pressurizer level for the pressurizer to be considered operable according to the technical specifications?
A. 48%
B. 57%
C. 61%
D. 65%
Proposed Answer: __B__
Explanation (Optional): The technical specifications state the maximum level is 57%.
Technical Reference(s): __TS 3.4.9.a (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 _____
55.43 _(5)__
Comments: Pressurizer Level Malfunction: Ability to track limiting conditions for operation.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __1__ _____
Group # __2__ _____
K/A # ____032-AK2.01___
Importance Rating _2.7__ _____
- 21. Startup Channel 1 will be lost if which of the following power supplies fail?
A. Q039 B. Y01 C. Q041 D. Y02 Proposed Answer: __A___
Explanation (Optional): The power supply for Startup Rate Channel 1 is Q039.
Technical Reference(s): _System Description SD-S023-470, Revision 6.
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam __NA___
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 _(7)__
55.43 _____
Comments:
032-AK2.01 Knowledge of the interrelations between the Loss of SRNI and the following: power supplies, including proper switch positions
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __1__ _____
Group # __2__ _____
K/A # ____037-AK1.01___
Importance Rating __2.9_ _____
- 22. A steam generator (SG) tube rupture has occurred and both SGs are being used to lower RCS temperature and pressure. All the RCPs have been stopped due to a saturation margin of 0 degrees.
Step 12 (Lowering Pzr Pressure) of EOI SO23-12-4, Steam Generator Tube Rupture, is being implemented. If ruptured SG pressure is currently 600 psig, then an acceptable initial target temperature for RCS T hot would be:
A. 530 degrees.
B. 490 degrees.
C. 475 degrees.
D. 450 degrees.
Proposed Answer: __B__
Explanation (Optional): The initial target is to reduce RCS pressure to within 50 psig of the ruptured SG. This means RCS pressure must be reduced so that it is between 600 and 650 psig. With T hot at saturation, it must be reduced to a saturation temperature for 600 to 650 psig. Using the provided steam tables, this corresponds to a saturation temperature of 486 to 495 degrees.
Technical Reference(s): Emergency Operating Instruction SO23-12-4, Steam Generator Tube Rupture, Revision 19, Step12, Note 1 Proposed references to be provided to applicants during examination: Properties of Saturated and Superheated Steam (Steam Tables)
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam _______
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 _(5)__
55.43 _____
Comments:
037-AK1.01 Knowledge of the operational implications of the following concepts as they apply to SGTL:
use of steam tables
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __1__ _____
Group # __2__ _____
K/A # ____061-AA2.01___
Importance Rating __3.5_ _____
- 23. When the "Nor-AD" pushbutton of the Condenser Air Ejector Radiation Monitor control module RE7818 is latched down:
A. The associated alarms are defeated.
B. The power to the control module can be turned off without any actuation of equipment.
C. The meter needle on the control module will move to the red triangle on the meter scale.
D. The artificial background will not function for this channel.
Proposed Answer: ___A___
Explanation (Optional):
Technical Reference(s): _(N3922) , Lesson Plan 2XRL07, Condenser Air Removal Radmonitor_
Proposed references to be provided to applicants during examination:
Learning Objective: ___52730______________________ (As available)
Question Source: Bank # _N3922_
Modified Bank # _______ (Note changes or attach parent)
New _______
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge __X___
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 __11___
55.43 _____
Comments:
061-AA2.01 Ability to determine and interpret the following as they apply to the Area Radiation Monitoring (ARM) System Alarms: ARM panel displays
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __1__ _____
Group # __2__ _____
K/A # ____068-AK2.07___
Importance Rating __3.3_ _____
- 24. Which of the following is taken to local control during the performance of SO23-13-2, Shutdown from Outside the Control Room?
A. P053, Condensate Pump B. HV9209, VCT Vent Valve C. P096, D/G Fuel Oil Transfer Pump D. HV9200, Regenerative Heat Exchanger Inlet Valve Proposed Answer: ___C___
Explanation (Optional):
SO23-13-2 directs taking all D/G controls to LOCAL (so A is correct); it also directs operation of several letdown valves, which makes them good distractors; Technical Reference(s): __ SO23-13-2 _________________ (Attach if not previously provided)
__(N40974) 13-2 local D/G fuel oil pump action_
Proposed references to be provided to applicants during examination:
Learning Objective: _____56663____________________ (As available)
Question Source: Bank # _N40974_
Modified Bank # _______ (Note changes or attach parent)
New _______
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge __X___
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 __10___
55.43 _____
Comments:
068-AK2.07 Knowledge of the interrelations between the Control Room Evacuation and the following:
ED/G
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __1__ _____
Group # __2__ _____
K/A # ____069-AA2.02___
Importance Rating __3.9_ _____
- 25. During core alterations with the personnel airlock door interlocks disabled, containment closure requirements are met if:
A. one of the personnel airlock doors remains operable and a designated individual is continuously available to close it if needed; this individual is free to move about inside the RCA.
B. one of the personnel airlock doors remains operable and a designated individual is continuously available to close it if needed; this individual must be stationed at the outer door.
C. neither of the personnel airlock doors remain operable, but a designated individual is continuously available to clear away hoses or cables that block them in order to close one if needed; this individual is free to move about inside the RCA.
D. neither of the personnel airlock doors remain operable, but a designated individual is continuously available to clear away hoses or cables that block them in order to close one if needed; this individual must be stationed at the outer door.
Proposed Answer: ___B___
Explanation (Optional): core alterations require containment closure which is satisfied by B; A and C are incorrect because the designated individual must be stationed at the outer door; D is incorrect because at least one of the doors must remain either closed or operable (not blocked by hoses/cables).
Technical Reference(s): __TSB 3.9.3_______________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __10___
55.43 _____
Comments:
069-AA2.02 Ability to determine and interpret the following as they apply to the Loss of Containment Integrity: verification of automatic and manual means of restoring integrity
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __1__ _____
Group # __2__ _____
K/A # ____074-EK1.07___
Importance Rating __2.8_ _____
- 26. Given the following plant conditions:
-A small break loss of coolant accident has occurred.
-Both Safety Injection and Containment High Pressure have initiated.
-HPSI Pump P-66A has failed to start.
-Actual Pressurizer pressure is 1060 psia and slowly lowering.
-Average of the Qualified CETs is 560 deg F and slowly lowering.
-There are no Reactor Coolant Pumps running.
-The accident initiated 30 minutes ago.
In implementing the applicable Floating Steps at this point, the procedure directs the operators to ENSURE maximum available CEDM cooling - operating in order to:
A. increase air turbulence to reduce the possibility of localized buildup of hydrogen to a level that could cause combustion.
B. enhance overall containment cooling and mitigate the challenge to containment integrity.
C. assist in eliminating voids by removing the upper reactor vessel heat.
D. minimize the thermal stresses on the CEDM shroud area.
Proposed Answer: ___C___
Explanation (Optional): S023-14-11 FS-10 indicates the reason for the action is C; normally, the CEDM cooling subsystem provides cooling to the CEDM shroud area for proper CEDM operation; hydrogen buildup is a concern in an earlier revision of the Containment Combustible Gas Functional Recovery Procedure.
Technical Reference(s): _____ S023-14-11 _________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __7,8,10___
55.43 _____
Comments:
074-EK1.07 Knowledge of the operational implications of the following concepts as they apply to the Inadequate Core Cooling: definition of saturated steam
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __1__ _____
Group # __2__ _____
K/A # ____076-AK3.06___
Importance Rating __3.2_ _____
- 27. A shutdown is required due to Dose Equivalent I-131 level of five microcuries/gram for the last 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. In this circumstance, why is Tcold required to be reduced to less than 500°F following the reactor shutdown?
A. Minimizes the magnitude of the iodine spiking phenomena caused by the unit shutdown.
B. Minimizes the release of noble gas to the reactor coolant, reducing the source term of the activity.
C. Minimizes the temperature related degradation of the CVCS demineralizers while RCS clean-up is in progress.
D. Minimizes the chances of a direct release of activity should a steam generator tube rupture occur.
Proposed Answer: __D___
Explanation (Optional): Reducing Tcold to <500F ensures that, in the event of a SGTR, the S/G pressure will not exceed the lift pressure settings of the atmospheric dump valves and main steam safety valves - thus minimizing the likelihood of a radioactive release to the environment.
Technical Reference(s): ____TSB 3.4.16____________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # __ N56506_____
Modified Bank # _______ (Note changes or attach parent)
New _______
Question History: Last NRC Exam ____2000________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __10___
55.43 _____
Comments:
076-AK3.06 Knowledge of the reasons for the following responses as they apply to the High Reactor Coolant Activity: actions contained in EOP for high reactor coolant activity
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ____003-K2.01____
Importance Rating _3.1__ _____
- 28. Given the following:
- A Loss of Coolant Accident has occurred at Unit 2
- SO23-12-3 is being implemented
- The ACO has been directed to STOP all Reactor Coolant Pumps (RCPs)
- RCP 2P001 fails to stop when the STOP pushbutton is depressed Which of the following is the appropriate action for stopping 2P001?
A. Dispatch an operator to open the breaker to 2P001 locally, at the bus.
B. Dispatch an operator to verify locally that DC power is aligned to 2P001 breaker.
C. Deenergize 2A01 by opening the supply breaker from the Reserve Auxiliary Transformer.
D. Deenergize Reserve Auxiliary Transformer 2XR3 by opening the breakers from the switchyard.
Proposed Answer: ___C___
Explanation (Optional):
Technical Reference(s): ____ SO23-0-46, SO23-6-1_ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _ N56831_
Modified Bank # _______ (Note changes or attach parent)
New _______
Question History: Last NRC Exam ___1999_____
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content: 55.41 _____
55.43 _____
Comments:
003/K2.01 & 3.1 - Reactor Coolant Pump/Knowledge of bus power supply to the following: RCPs.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ____003-A2.02____
Importance Rating _3.7_ _____
- 29. The plant has just tripped from 100% power operation, the SPTAs are being carried out and plant conditions are as follows:
- All CEAs are fully inserted.
- PZR level is 2%.
- RCS Subcooling is 90°F.
- RCS pressure is 1300 psia, SIAS has actuated.
- RCS cold leg temperature is 490°F, MSIS has actuated.
- CNTMT pressure is 3.5 psig, CIAS has actuated.
Concerning Reactor Coolant Pumps, which of the following is the required action in the SPTAs and why?
A. Stop one RCP in each loop to limit RCS inventory loss B. Stop all four RCPs to protect RCP seals and bearings due to isolation of CCW C. Maintain all four RCPs running to maximize heat removal capability with forced circulation o
D. Maintain all RCPs whose associated P002 Upward Thrust Bearing Temperature < 240 F running to ensure maximum heat removal capability while protecting the RCP bearings Proposed Answer: __B___
Explanation (Optional): Step 3.d of SO23-12-1 requires tripping all four RCPs if letdown has isolated (SIAS) and CIAS is actuated (loss of CCW) in order to protect the RCP seals and bearings (basis). A would have been required by step 5.a if the conditions for tripping all four on step 3.d had not been met.
Neither C nor D are appropriate for this condition.
Technical Reference(s): ___ Step 3.d of SO23-12-1___ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: ____56252___________________ (As available)
Question Source: Bank # __N3932*__
Modified Bank # _______ (Note changes or attach parent)
New _______
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __7,8,10___
55.43 _____
Comments: Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Conditions which exist for an abnormal shutdown of an RCP in comparison with a normal shutdown. *Minor changes were made, but not sufficient to qualify for modified status.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ___004-K1.01_____
Importance Rating __3.6_ _____
- 30. Which one of the following actions occur when the in-service Thot instrument fails low?
(Assume 100% power and all systems are operating normally)
L/D FLOW B/U HEATERS B/U CHARGING PUMPS A. Increases Energize OFF B. Increases Deenergize ON C. Decreases Deenergize ON D. Decreases Energize OFF Proposed Answer: ___A___
Explanation (Optional):
Technical Reference(s): ___ SO23-3.1.10__________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _______55219__________________ (As available)
Question Source: Bank # _N5743_
Modified Bank # _______ (Note changes or attach parent)
New _______
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __7___
55.43 _____
Comments: 004/K1.01 & 3.6 - Chemical and Volume Control/Knowledge of the physical connections and/or cause-effect relationships between the CVCS and the following systems: PZR LCS
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ____004-A3.10____
Importance Rating _3.9_ _____
- 31. Unit 2 is operating at 100% power. Pressurizer Pressure and Level Control is aligned as follows:
- Pressurizer Pressure Control is selected to Channel X.
- Pressurizer Level Control is selected to Channel Y.
- All three (3) Charging Pumps are in Auto and Letdown flow is matched with Charging flow.
What would cause the backup Charging Pumps to start and Letdown flow to go to minimum?
A. Channel Y LT-110-2 failed low.
B. Channel X PT-0100X failed low.
C. Channel Y LT-110-2 failed high.
D. Channel X PT-0100X failed high.
Proposed Answer: __C___
Explanation (Optional):
Technical Reference(s): SO23-3-1.10, SO23-15-50.A1, 50A23 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _____55219____________________ (As available)
Question Source: Bank # __ N5519__
Modified Bank # _______ (Note changes or attach parent)
New _______
Question History: Last NRC Exam __2000 Audit Exam__
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __7__
55.43 _____
Comments:
004/A3.10 & 3.9 - Ability to monitor automatic operation of the CVCS, including: PZR Lev. & press
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ____005-G2.1.32__
Importance Rating _3.4_ _____
- 32. SO23-3-2.6, Shutdown Cooling System (SDCS), cautions the operator to maintain the SDCS and interconnecting piping within the following limit:
A. < 340°F (normal operations)
B. < 340°F (post-accident)
C. < 350°F (normal operations)
D. < 350°F (post-accident)
Proposed Answer: __C___
Explanation (Optional): SO23-3-2.6 L&S 1.1 indicates that 350°F is the normal operations limit for the SDCS and interconnecting piping; Thot must be < 340°F to place SDC in service for normal operations and < 375°F for post-accident operations.
Technical Reference(s): __ SO23-3-2.6 L&S 1.1 _____ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: __55073___________________ (As available)
Question Source: Bank # __ N3191*_
Modified Bank # _______ (Note changes or attach parent)
New _______
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 __3,7,10___
55.43 _____
Comments:
005/2.1.32 & 3.4 - Residual Heat Removal/Ability to explain and apply all system limits and precautions.
- Changes were made, but not sufficiently to make this a modified question.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ____006-K5.02____
Importance Rating __2.8_ _____
- 33. During sampling, a purge of 165 gallons is taken from the SIT volume SO23-3-2.7.1 Safety Injection Tank Operation. Prior to the purge, the level and pressure of the SIT was 82.0% (NR) and 630 psia respectively. With no other operator action to modify SIT level and pressure, the post-sampling level and pressure would be:
A. 71.0% (NR) and 570 psia respectively.
B. 71.0% (NR) and 624 psia respectively.
C. 80.9% (NR) and 570 psia respectively.
D. 80.9% (NR) and 624 psia respectively.
Proposed Answer: __D___
Explanation (Optional): SO23-3-2.7.1 indicates that the 165 gallon sample purge will result in 1.1%
level drop and 6 psia pressure drop in the SIT.
Technical Reference(s): ___ SO23-3-2.7.1___________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __3,5,8___
55.43 _____
Comments: 006/K5.02 & 2.8 - Emergency Core Cooling/Knowledge of the operational implications of the following concepts as they apply to ECCS: Relationship between accumulator volume and pressure.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ____007-A4.10____
Importance Rating _3.6_ _____
- 34. The following stable plant conditions exist while with the reactor shutdown:
-PCS level = 52%
-PCS pressure = 1000 psia
-Quench Tank level = 50%
-Quench Tank pressure = 10 psig What tail pipe temperature would be expected for a leaking PZR code safety valve under these conditions?
A. 193 °F B. 234 °F C. 311 °F D. 545 °F Proposed Answer: __C___
Explanation (Optional): Isenthalpic process results in ~310 °F for 24.4 psia (must use absolute pressure on Mollier diagram vice gage pressure); 193, 234, and 545 are Tsat for 10 psia, 24.4 psia, and 1000 psia respectively.
Technical Reference(s): ___Steam Tables___________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination: Steam Tables Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __5,14___
55.43 _____
Comments: 007/A4.10 & 3.6 - Pressurizer Relief/Quench Tank/ Ability to manually operate and/or monitor in the control room: Recognition of a leaking PORV/safety.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ____008-K4.02____
Importance Rating _2.9_ _____
- 35. The in-service Train A CCW Surge Tank, T-003, has been over-filled, causing the normally dry reference legs for ALL level transmitters and switches to fill with water.
Which of the following will occur?
(Assume NCL aligned to Train "A")
A. Critical Loop isolation valves will close.
B. Non-Critical Loop isolation valves will close.
C. Automatic Makeup to the CCW System will terminate.
D. The CCW Pump on the Train "B" will automatically start.
Proposed Answer: __B___
Explanation (Optional):
Technical Reference(s): ___SD-SO23-400__________ (Attach if not previously provided)
___SO23-13-7_____________
Proposed references to be provided to applicants during examination:
Learning Objective: ______55542___________________ (As available)
Question Source: Bank # __N57589__
Modified Bank # _______ (Note changes or attach parent)
New _______
Question History: Last NRC Exam __1998_____
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content: 55.41 __7__
55.43 _____
Comments: 008/K4.02 & 2.9 - Component Cooling Water/Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following: Operation of the surge tank, including the associated valves and controls.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ____010-K6.01____
Importance Rating _2.7_ _____
- 36. What are the other TWO Reactor Trips that will be affected by the loss of a Narrow Range Pressurizer Pressure Instrument?
A. Local Power Density - High, and DNBR - Low.
B. Local Power Density - Low, and DNBR - High.
C. Pressurizer Pressure - Low (CCAS), and Pressurizer Pressure - Low (RPS).
D. Pressurizer Pressure - High (CIAS/CCAS), and Pressurizer Pressure - Low (RPS).
Proposed Answer: __A__
Explanation (Optional): .
Technical Reference(s): ___SO23-13-18 ___________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________55180________________ (As available)
Question Source: Bank # _N3205_
Modified Bank # _______ (Note changes or attach parent)
New _______
Question History: Last NRC Exam ___2000_____
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 _____
55.43 _____
Comments: 010/K6.01 & 2.7 - Pressurizer Pressure Control/ Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: Pressure detection systems.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ____010-K2.01_____________
Importance Rating _3.0_ _____
- 37. Which of the following Unit 2 Pressurizer heater groups are powered by 480V bus 2B04?
A. Backup heater group A (E128)
B. Backup heater group B (E129)
C. Proportional heater group A (E123)
D. Proportional heater group B (E124)
Proposed Answer: __A___
Explanation (Optional):
Technical Reference(s): _________________________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _______55417_____________ (As available)
Question Source: Bank # _N11003_
Modified Bank # _______ (Note changes or attach parent)
New _______
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 __7__
55.43 _____
Comments:
010/K2.01 & 3.0 - Pressurizer Pressure Control/Knowledge of bus power supplies to the following: PZR Heaters
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ____012-K4.09____
Importance Rating _2.8_ _____
- 38. Plant conditions are as follows:
- Unit 2 at 100% power
- Pressurizer Pressure detector PT-0101-1 output fails high
- Pressurizer Pressure detector PT-0100X output has also fails high
- All actions of SO23-13-18, Reactor Protection System Failure, have been completed What is the current high Pressurizer Pressure reactor trip coincidence logic status?
A. 1 out of 2.
B. 2 out of 3.
C. 2 out of 4.
D. The reactor is tripped on high Pressurizer Pressure.
Proposed Answer: __B__
Explanation (Optional): Only PT-0101-1 affects the RPS logic (PT-0100X is only used for control, not protection), and once it is bypassed per SO23-13-18, the coincidence shifts to 2 out of 3.
Technical Reference(s): ___SD-SO23-360__________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: ______56622______________ (As available)
Question Source: Bank # _______
Modified Bank # _N56867_ (Note changes or attach parent)
New _______
Question History: Last NRC Exam ____1999________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content: 55.41 __6,7___
55.43 _____
Comments: 012/K4.09 & 2.8 - Reactor Protection/Knowledge of RPS design feature(s) and/or interlock(s)which provide for the following: Separation of control and protection circuits.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ____012-K2.01____
Importance Rating _3.3_ _____
- 39. Which of the following describes what will be a result from a loss of Vital Bus Inverter 2Y001 per SO23-13-18, RPS Failure/Loss of Vital Bus Inverter?
A. CEAC 2 failure B. PPS Channel A Hi Log Power trip C. Only Reactor Trip Breakers 2 and 4 open D. RCP CBO to VCT isolation valve 2HV9218 fails closed Proposed Answer: __B___
Explanation (Optional):
Technical Reference(s): ___SO23-13-18____________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _______55180_____________ (As available)
Question Source: Bank # _N11159_
Modified Bank # _______ (Note changes or attach parent)
New _______
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 __6,7,10___
55.43 _____
Comments: 012/K2.01 & 3.3 - Reactor Protection/Ability to manually operate and/or monitor in the control room: Bistable, trips, reset and test switches.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ____013-A1.07____
Importance Rating _3.6_ _____
- 40. A LOCA has occurred and the following plant conditions exist:
- S/G E088 pressure has lowered to 725 psia.
- S/G E089 pressure is at 1000 psia.
- PZR pressure has lowered to 1600 psia and slowly lowering.
- Containment pressure is 12 psig and slowly lowering.
- Containment Radiation monitors are reading 43 R/hr and slowly lowering.
- Containment Temperature is 198°F and slowly lowering.
- All systems are operating as expected.
The crew is implementing SO23-12-3 Loss of Coolant Accident and step 12 (ESTABLISH Optimal Containment Atmosphere Conditions) has prompted them to refer to FS-14 TERMINATE Containment Spray Operation. Under the above conditions, FS-14 directs the SM/OL to evaluate keeping the CSS operating in order to:
A. reduce containment pressure B. maximize containment cooling C. remove radioactive iodine from the containment atmosphere D. circulate the Tri-Sodium Phosphate to minimize corrosion in containment Proposed Answer: __C___
Explanation (Optional): FS-14 of SO23-12-11 directs the SM/OL evaluate whether CSS is required for containment iodine removal and decay heat removal post-RAS; since containment pressure is below 14 psig and lowering and all systems are operating as expected (meaning at least two Containment emergency Cooling Units are operating), A and B are not reasons to keep CSS operating; CSS does circulate TSP to minimize corrosion from the liquid being sprayed by the CSS, but it is not a reason to keep CSS running.
Technical Reference(s): ___ FS-14 of SO23-12-11 _______ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content: 55.41 __8,10___
55.43 _____
Comments: 013/A1.07 & 3.6 - Engineered Safety Features Actuation/Ability to predict and/or monitor changes in parameters (to Prevent exceeding design limits) associated with operating the ESFAS controls including: Containment radiation
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ____022-A1.02____
Importance Rating _3.6_ _____
- 41. What parameters will automatically initiate a Containment Cooling Actuation Signal (CCAS)?
A. Containment NR Pressure or PZR NR Pressure.
B. Containment NR Pressure or PZR WR Pressure.
C. Containment WR Pressure or PZR NR Pressure.
D. Containment WR Pressure or PZR WR Pressure.
Proposed Answer: ___B___
Explanation (Optional):
Technical Reference(s): ___T.S. Table 3.3.5-1_______ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: ________56628____________ (As available)
Question Source: Bank # __N57476_
Modified Bank # _______ (Note changes or attach parent)
New _______
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 _8___
55.43 _____
Comments: 022/A1.02 & 3.6 - Containment Cooling/Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including:
Containment pressure.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ____022-A3.01____
Importance Rating _4.1_ _____
- 42. Which of the following Engineered Safety Features Actuation Systems (ESFAS) signals are generated by an AUTOMATIC Safety Injection Actuation Signal (SIAS) but NOT by a MANUAL SIAS?
A. Toxic Gas Isolation Signal (TGIS).
B. Main Steam Isolation Signal (MSIS).
C. Containment Cooling Actuation Signal (CCAS).
D. Non-Critical Loop CCW Isolation Signal (CIAS).
Proposed Answer: __C___
Explanation (Optional):
Technical Reference(s): ___ SD-SO23-720 P. 8______ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: ________56628____________ (As available)
Question Source: Bank # _N4019_
Modified Bank # _______ (Note changes or attach parent)
New _______
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 __8__
55.43 _____
Comments: 022/A3.01 & 4.1 - Containment Cooling/Ability to monitor automatic operation of the CCS, including Initiation of safeguards mode of operation.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ____026-K1.02____
Importance Rating _4.1_ _____
- 43. Failure of HV-6501 Shutdown Cooling Train A Heat Exchanger ME-004 CCW Return Isolation Valve to open on a valid CSAS after a valid SIAS will result in:
A. Shutdown HX Train A CCW Flow Lo alarm B. Containment Spray Pump P012 CCW Flow Lo alarm C. Failure to meet the 100% Containment heat removal capacity D. Inability of the Shutdown Cooling System to meet 100% of normal shutdown cooling requirements after the post-LOCA cooldown Proposed Answer: ___C___
Explanation (Optional): SD-SO23-740 (page 38-40) describes that both SDCHXs are required to meet 100% Containment heat removal capacity during CSS operation; only one SDCHX is required to meet 100% of normal shutdown cooling requirements in SDC mode (so D is wrong); cooling flow is not affected to the CS pump seals, so B is wrong; the Shutdown HX Train A CCW Flow Lo alarm would normally actuate for no-flow through the HX, but the alarm does not actuate if HV-6501 is shut (so A is wrong)(see SO23-15-64.A section 64A37).
Technical Reference(s): __ SD-SO23-740 __________ (Attach if not previously provided)
__ SO23-15-64.A section 64A37__
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content: 55.41 __7,8,10___
55.43 _____
Comments: 026/K1.02 & 4.1 - Containment Spray/Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: Cooling water
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ____039-K1.01____
Importance Rating _3.1_ _____
- 44. The plant was initially operating at 100% power. A complete Loss of Offsite Power occurred 5 minutes ago. NO operator actions have been taken and all systems functioned as designed.
How are the S/Gs maintaining RCS heat removal?
A. AFW supplying S/Gs; steaming using Main Steam Safety Valves.
B. MFW supplying S/Gs; steaming using Main Steam Safety Valves.
C. AFW supplying S/Gs; steaming using the Atmospheric Dump Valves.
D. MFW supplying S/Gs; steaming using the Atmospheric Dump Valves.
Proposed Answer: __A___
Explanation (Optional):
Technical Reference(s): ___SO23-12-1_____________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: ______56252______________ (As available)
Question Source: Bank # _N56790*_
Modified Bank # _______ (Note changes or attach parent)
New _______
Question History: Last NRC Exam __1999____
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content: 55.41 __4,5,7___
55.43 _____
Comments:
039/K1.01 & 3.1 - Main and Reheat Steam/Knowledge of the physical connections and/or cause-effect relationships between the MRSS and the following systems: S/G. *Modified slightly, but not enough to count as modified instead of bank.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __1__ _____
K/A # ____059-K3.04____
Importance Rating _3.6_ _____
- 45. Following a reactor trip, Standard Post Trip Actions have been completed. The CRS has diagnosed a loss of feedwater and entered SO23-12-6, Loss of Feedwater. The Loss of Feedwater EOI requires the operators to confirm the Loss of Feedwater diagnosis by verifying that Pressurizer Level is_______
before the operators__________.
A. Stable or Decreasing slowly; Trip all Reactor Coolant Pumps.
B. Stable or Increasing slowly; Trip all Reactor Coolant Pumps.
C. Stable or Decreasing slowly; Trip only one Reactor Coolant Pump in each loop.
D. Stable or Increasing slowly; Trip only one Reactor Coolant Pump in each loop.
Proposed Answer: __B___
Explanation (Optional): SO23-14-6 explains that PZR Level will be stable or slowly increasing and that all RCPs are tripped to minimize heat addition to the RCS.
Technical Reference(s): __ SO23-14-6 _____________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New __X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 __5,10__
55.43 _____
Comments:
059/K3.04 & 3.6 - Main Feedwater/Knowledge of the effect that a loss or malfunction of the MFW will have on the following: RCS.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _2__ _____
Group # _1__ _____
K/A # _061/K4.14________
Importance Rating _3.5__ _____
- 46. Given the following plant parameters,
-A reactor trip has occurred.
-Steam Generator 1: Pressure 735 psig and lowering Level 10%
-Steam Generator 2: Pressure 1040 psig steady Level 18%
Which of the following describes the feedwater flow to the steam generators:
A. P-140, P-141, and P-504 are running supplying feed to both steam generators.
B. P-141, and P-504 are running supplying feed to both steam generators.
C. P-140, and P-504 are running supplying feed to steam generator 2.
D. P-140, P-141, and P-504 are running supplying feed to steam generator 2.
Proposed Answer: __C___
Explanation (Optional):
Technical Reference(s): _SD-SO23-780 section 2.1.3, SSO23-720,_
Proposed references to be provided to applicants during examination: none Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New __X___
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content: 55.41 __4,7,8___
55.43 _____
Comments:
061/K4.14 & 3.5 - Auxiliary/Emergency Feedwater/AFW automatic isolation
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _2__ _____
Group # _1__ _____
K/A # _062/2.2.22 _______
Importance Rating _3.4_ _____
- 47. Minimum allowable starting air pressure for the Emergency Diesel Generator operability is:
A. 120 psig B. 175 psig C. 185 psig D. 210 psig Proposed Answer: __B__
Explanation (Optional):
Technical Reference(s): SD-SO23-750 and tech spec 3.8___
Proposed references to be provided to applicants during examination: none Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New __X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 __7,8___
55.43 _____
Comments:
062/2.2.22 & 3.4 - AC Electrical Distribution / Knowledge of limiting conditions for operations and safety limits
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _2__ _____
Group # _1___ _____
K/A # _063/K3.01________
Importance Rating _3.7__ _____
- 48. EDG 2G002 is being operated in parallel with normal power when an operator error results in the control power fuses being removed for the generators output breaker. In this configuration, the generator output breaker:
A. will immediately trip open.
B. can be opened from the control room.
C. will trip open on a loss of generator excitation.
D. can only be opened manually at the breaker cubical.
Proposed Answer: __D___
Explanation (Optional): On a loss of breaker control power the breaker cannot be operated remotely. It will not open on most generator trip signals. It will remain closed unless manually tripped from the breaker cubicle.
Technical Reference(s): _________________________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New __X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge __X___
Comprehension or Analysis ____
10 CFR Part 55 Content: 55.41 _(7)__
55.43 _____
Comments:
063/K3.01 & 3.7 - DC Electrical Distribution/Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: ED/G
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _2__ _____
Group # _1__ _____
K/A # _064/K6.07 ________
Importance Rating _2.7_ _____
- 49. A leak on one air receiver for EDG 2G002 requires one bank of air receivers be isolated for repairs.
With the discharge isolation valve closed for one bank of air receivers, a start signal for EDG 2G002 will result in:
A. all the air start valves will open and starting air will be provided to all the air start motors.
B. one-half the air start valves will open and air will be provided to one-half of the air start motors.
C. all the air start valves will open and starting air will be provided to one-half of the air start motors.
D. One-half the air start valves will open and air will be provided to all the air start motors.
Proposed Answer: ___C___
Explanation (Optional): On a start signal, all the air start valves will open. With only one bank of starting air in service, only one-half the air start motors will receive starting air making C the correct answer.
Technical Reference(s): _System Description SD-SO230750, Revision 11, Figure V-1 Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New __X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 _(7)__
55.43 _____
Comments: 064/K6.07 & 2.7 - Emergency Diesel Generator/Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: Air receivers
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _2__ _____
Group # _1___ _____
K/A # _064/A1.01________
Importance Rating _3.0__ _____
- 50. The EDG automatic trip on low low lube oil pressure is always; A. active.
B. active at all times except for the first 50 seconds of an engine startup.
C. active at all times unless there is a SIAS signal present.
D. active except for the first 50 seconds of an engine startup or if there is a SIAS signal present.
Proposed Answer: __B___
Explanation (Optional): The low low oil pressure is bypassed for the first 50 seconds of an engine start. Otherwise it is always active. This makes B correct.
Technical Reference(s): __System Description SD-SO23-750, Revision 11, page 60.
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New __X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 _(7)____
55.43 _____
Comments: 064/A1.01 & 3.0 - Emergency Diesel Generators/Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ED/G system controls including: ED/G lube oil temperature and pressure
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _2__ _____
Group # _1__ _____
K/A # __073/2.3.9 _____
Importance Rating _2.5_ _____
- 51. During a board walk-down, you notice the following lineup for the containment purge system:
Mini Purge supply isolation valve HV-9821 closed Mini Purge supply isolation valve HV-9823 open Mini Purge exhaust isolation valve HV-9824 open Mini Purge exhaust isolation valve HV-9825 closed Normal Purge inlet isolation valve HV-9948 closed Normal Purge inlet isolation valve HV-9949 open Normal Purge outlet isolation valve HV-9951 closed Normal Purge outlet isolation valve HV-9950 open Which of the following automatic isolation signals could have caused this lineup?
A. Containment Purge Isolation Signal B. High radiation detected by RE-7828 (purge stack radiation monitor)
C. Containment Purge Isolation Signal or High radiation detected by RE-7828 (purge stack radiation monitor)
D. Containment Isolation Actuation Signal Proposed Answer: __B___
Technical Reference(s): __SD-SO23-770 Section 2.0 Proposed references to be provided to applicants during examination: none Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New __X___
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge ____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __7,11___
55.43 _____
Comments: 073/2.3.9 & 2.5 - Process Radiation Monitoring/Knowledge of the process for performing a containment purge.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _2__ _____
Group # _1___ _____
K/A # __076/K3.05 ______
Importance Rating _3.0_ _____
- 52. Given the following plant conditions:
-Plant shutdown and cooldown from 100% power has just been completed.
-Shutdown Cooling has been established on Train A.
-The running component cooling water pump trips, and the standby pump fails to start.
Which of the following describes the shutdown Cooling System response?
A. All SDC flow is lost; the LPSI pumps will trip on low CCW flow.
B. No effect; CCW is not required by the Shutdown Cooling System.
C. SDC heat removal is lost and the Shutdown HX Train A CCW Flow Hi Lo alarm will actuate.
D. SDC flow will be degraded and the Shutdown HX Train A CCW Flow Hi Lo alarm will actuate.
Proposed Answer: __C__
Explanation (Optional):
Technical Reference(s): _________________________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __7___
55.43 _____
Comments: 076/K3.05 & 3.0 - Service Water/ Knowledge of the effect that a loss or malfunction of the SWS will have on the following: RHR components, controls, sensors, indicators, and alarms, including rad monitors
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _2___ _____
Group # _1__ _____
K/A # __078/A3.01 _______
Importance Rating _3.1_ _____
- 53. Unit 2 is operating at 100% power with the Instrument Air system lined up for normal operations when the Instrument Air Header Pressure Low alarm is received. Instrument Air header pressure is at 87 psig. The current status of the Instrument air system is:
A. Three air compressors are running fully loaded, the Nitrogen backup supply system is maintaining the instrument air header via a pressure-regulating valve.
B. Two air compressors are running fully loaded and one air compressor is running half loaded maintaining the instrument air header.
C. Two air compressors are running fully loaded and one air compressor is running half loaded, and the service air system is maintaining the instrument air header via a self-regulating pilot operated pressure control valve.
D. Three air compressors are running fully loaded, the service air system is maintaining the instrument air header via a self-regulating pilot operated pressure control valve.
Proposed Answer: __C___
Explanation (Optional):
Technical Reference(s): __SD SO23-570__section 2.2.10 and section 3.2___
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New __X_____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge ____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __4,7___
55.43 _____
Comments: 078/A3.01 & 3.1 - Ability to monitor automatic operation of the IAS, including: Air pressure
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _2___ _____
Group # _1__ _____
K/A # ____103/A2.05_____
Importance Rating _2.9_ _____
- 54. Which of the following conditions prevents containment Entry?
A. Containment Pressure is 3.4 psig.
B. Containment Humidity is 100%.
C. Only two egress paths exist from containment D. Containment atmosphere Oxygen level is unacceptable.
Proposed Answer: __A__
Explanation (Optional): The requirements are for pressure <3 psig and a minimum of 2 egress paths.
Technical Reference(s): _SO23-3-2.34___
Proposed references to be provided to applicants during examination: None Question Source: Bank # _N101330_
Modified Bank # _______ (Note changes or attach parent)
New _____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 __9,10___
55.43 _____
Comments: 103/A2.05 & 2.9 - Containment/Ability to (a) predict the impacts of the following malfunctions or operations on the containment system-and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operation: Emergency containment entry
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # _2___ _____
Group # _1___ _____
K/A # _103/A4.06________
Importance Rating _2.7__ _____
- 55. Given the following:
-Unit 2 is in a refueling outage.
-Fuel is being moved inside containment.
WHICH ONE (1) of the following is the MINIMUM required condition for the Personnel Air Lock (PAL) and Emergency Air Lock (EAL) doors and Equipment hatch?
A. The Equipment hatch must be closed and held in place by 4 bolts, both doors in the EAL must be closed, and one door of the PAL must be closed B. The Equipment hatch must be closed with all bolts installed; both doors in the PAL and EAL must be closed.
C. The Equipment hatch must be closed and held in place by 4 bolts, one door in the EAL must be closed, and one door in the PAL must be closed.
D. Both doors of the PAL and both doors of the EAL must be closed.
Proposed Answer: __C__
Explanation (Optional):
Technical Reference(s): Tech Spec 3.9.3 Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X____
Question History: Last NRC Exam ____________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 __9,12___
55.43 _____
Comments: 103/A4.06 & 2.7 - Containment/Ability to manually operate and/or monitor in the control room: Operation of the containment personnel airlock door
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __2__ _____
K/A # ___015-A1.04_____
Importance Rating _3.5_ _____
- 56. Reactor power is 80 percent and COLSS (Core Operating Limits Supervisory System) is out of service. Axial Shape Index (ASI) is being computed by the CPCs.
CEAs were driven in due to a transient and the following core power conditions exist:
Upper Half power is 45%.
Lower Half power is 55%.
With these conditions, the Axial Shape Index is equal to:
A. + 0.1, and outside the applicable technical specification limit.
B. - 0.1, and outside the applicable technical specification limit.
C. + 0.1, and within the applicable technical specification limit.
D. - 0.1, and within the applicable technical specification limit.
Proposed Answer: __C____
Explanation (Optional): The ASI is 55 - 45/55 + 45 = +0.1 making B and D incorrect. The limit with COLSS out of service is + 0.2. This makes C the only correct answer.
Technical Reference(s): _TS 3.2.5 & LCS 3.2.102_____ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: ___54674 ________________ (As available)
Question Source: Bank # _75630_
Modified Bank # _______ (Note changes or attach parent)
New _______
Question History: Last NRC Exam _2000__
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis _X___
10 CFR Part 55 Content: 55.41 __(5)_
55.43 _____
Comments: 015/A1.04 & 3.5 - Nuclear Instrumentation/Ability to predict and/or monitor changes in parameters to prevent exceeding design limits associated with operating the NIS controls including:
Quadrant power tilt ratio
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __2__ _____
K/A # ___028-k3.01______
Importance Rating _3.3_ _____
- 57. The power regulators in both hydrogen recombiners were replaced during the last outage with parts that contained a manufacturing defect that effectively reduced the heater output in both hydrogen recombiners. Several hours after placing both units in service, an operator notes the indicated heater temperature for the hydrogen recombiners is approximately 925 degrees rather than the expected 1150-1400 degrees.
With the post-LOCA hydrogen concentration at 2 percent and slowly rising, the operator should expect the hydrogen concentration in containment to:
A. increase as though the hydrogen recombiners were not in service.
B. increase at a slower rate than if the recombiners were not in service.
C. remain stable at approximately 2 percent.
D. decrease at a slower rate than expected.
Proposed Answer: ___A___
Explanation (Optional): For the hydrogen combiners to remove hydrogen from the containment atmosphere, heater temperature must be at least 1150 degrees (the reaction temperature for hydrogen recombination). With the heater temperature at 925 degree there will be no hydrogen recombination and the containment hydrogen concentration will increase as though the recombiners were not in service. Therefore the correct answer is A.
Technical Reference(s): _System Description SD-SO23-770, Revision 6, page 40_
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam __NA___
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 __(7)_
55.43 __ ___
Comments: 028/K3.01 & 3.3 - Hydrogen Recombiner and Purge Control/Knowledge of the effect that a loss or malfunction of the HRPS will have on the following: Hydrogen concentration in containment
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __2__ _____
K/A # ___029-K1.03_____
Importance Rating _3.6_ _____
- 58. Both CIAS and CPIS will close the following valves:
A. Containment mini-purge supply valves (HV-9821 & HV-9823) AND Containment mini-purge exhaust valves (HV-9824 & HV-9825)
B. Containment mini-purge supply valves (HV-9821 & HV-9823) AND Containment purge supply valves (HV-9948 & HV-9949)
C. Containment purge exhaust valves (HV-9950 & HV-9951) AND Containment mini-purge exhaust valves (HV-9824 & HV-9825)
D. Containment purge supply valves (HV-9948 & HV-9949) AND Containment purge exhaust valves (HV-9950 & HV-9951)
Proposed Answer: __A___
Explanation (Optional): CIAS only closes the mini-purge supply and exhaust valves, while CPIS closes purge and mini-purge supply and exhaust valves.
Technical Reference(s): _____System Description SD-SO23-270, Rev 6, page 71 and 80_
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam _____
Question Cognitive Level: Memory or Fundamental Knowledge __X _
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 _7,8,9___
55.43 _____
Comments: 029/K1.03 & 3.6 - Knowledge of the physical connections and/or cause-effect relationships between the Containment Purge System and Engineered Safeguards
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __2__ _____
K/A # ___035-A2.06_____
Importance Rating _4.5_ _____
- 59. The plant is operating at full power when a crack develops in a Steam Generator (SG) tube that results in a 30 GPM RCS leak rate. Pressurizer and VCT levels are stable.
This situation will require the operators to:
A. immediately trip the reactor and isolate the affected SG.
B. perform a rapid shutdown and isolate the affected SG.
C. immediately trip the reactor and cooldown the RCS to less than 200 degrees.
D. perform a rapid shutdown and then cooldown the RCS to less than 200 degrees.
Proposed Answer: __D___
Explanation (Optional):
Technical Reference(s): _Abnormal Operating Instruction SO23-13-14, Revision 9, step 4c and Technical Specification 3.4.13.
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam _NA____
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content: 55.41 _ (10) 55.43 _____
Comments: 035/A2.06 & 4.5 - Steam Generator/Ability to (a) predict the impacts of the following mal-functions or operations on the GS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Small break LOCA
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __2__ _____
K/A # ___002-K5.08_____
Importance Rating _3.4_ _____
- 60. If actual pressurizer water level is above the program level then:
A. a SIAS may occur on a rapid load change transient.
B. the pressurizer may empty following a reactor trip.
C. the pressurizer could go solid on a load reject event.
D. the energy release during a LOCA could exceed the containment design.
Proposed Answer: __C___
Explanation (Optional):
Technical Reference(s): _System Description DS-SO23-360, Revision 11, page 64._
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam _None__
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 _(5) _
55.43 _____
Comments: 002/K5.08 & 3.4 - Knowledge of the operational implications of the following concepts as they apply to the RCS: Why Pzr level should be kept within the programmed band.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __2__ _____
K/A # ___045-K4.13_____
Importance Rating _2.6_ _____
- 61. Unit 2 is at 45 percent power after coming out of an outage. A grid disturbance has resulted in grid frequency and turbine speed increasing. With turbine speed now at 1950 RPM, the response of the turbine and generator control systems should be to:
A. throttle the governor valves in the closed direction.
B. close the turbine stop and governor valves.
C. trip the generator output breaker on a high volts to hertz signal.
D. throttle open the steam bypass control valves.
Proposed Answer: __B__
Explanation (Optional): When turbine speed reaches 1950 RPM the overspeed setpoint has been exceeded and the turbine stop and governor valves should trip closed. The generator volts/hertz ratio should not be approached in this scenario so the generator breaker should remain closed until the turbine trips.
Technical Reference(s): __System Description SD-SO23-180, Revision 9, page 71._
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam _NA ___
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content: 55.41 _(7) _
55.43 _____
Comments: 045/K4.13 & 2.6 - Knowledge of MT/G system design feature(s) and/or inter-lock(s) which provide for the following: Overspeed protection
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __2__ _____
K/A # _011/A3.03________
Importance Rating __3.2_ _____
- 62. The reactor is at rated thermal power with all systems operable and in their normal configuration.
While performing a board walkdown, the reactor operator notes pressurizer level is slowly lowering. If the downward trend continues with no operator action, when pressurizer level deviates from program level by a negative:
A. 0.75%, the letdown flow control valve will have reached its minimum flow position.
B. 2%, the 1st backup charging pump will automatically start.
C. 3%, the 2nd backup charging pump will automatically start.
D. 6%, an alarm signal will provide a backup start signal to both charging pumps.
Proposed Answer: ___D__
Explanation (Optional): As level lowers, the percent of deviation from program increases. When deviation reaches -1.1 %, the flow control valve reaches minimum making a. incorrect.
When level reaches -2.5%, the 1st backup charging pump starts making b. incorrect.
When level reaches -3.9%, the 2nd backup charging pump starts making c. incorrect.
When level reaches -6%, an alarm signal will provide a backup start signal to both charging pumps making d. correct.
Technical Reference(s): _System Description SD-SO23-390, Revision 10, page 46._
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New __X____
Question History: Last NRC Exam _NA____
Question Cognitive Level: Memory or Fundamental Knowledge __X___
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 __(7)_
55.43 _____
Comments: 011/A3.03 & 3.2 - Pressurizer Level Control System/Ability to monitor the automatic operation of the PZR LCS, including charging and letdown.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __2__ _____
K/A # ___071-A4.30_____
Importance Rating _2.9_ _____
- 63. If actual pressurizer water level is above the program level then:
A. a SIAS may occur on a rapid load change transient.
B. the pressurizer may empty following a reactor trip.
C. the pressurizer could go solid on a load reject event.
D. the energy release during a LOCA could exceed the containment design.
Proposed Answer: __C___
Explanation (Optional):
Technical Reference(s): _System Description DS-SO23-360, Revision 11, page 64._
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam _None__
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 _(5) _
55.43 _____
Comments: 071/A4.30 & 2.9 - Waste Gas Disposal/Ability to manually operate and/or monitor in the control room: Water drainage from the WGOS decay tanks [Deleted]
002/K5.08 & 3.4 - Knowledge of the operational implications of the following concepts as they apply to the RCS: Why Pzr level should be kept within the programmed band.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __2__ _____
K/A # _ _072-K3.01______
Importance Rating _3.2_ _____
- 64. A malfunction of which Radiation Monitors could initiate a Containment Purge Isolation Signal (CPIS)?
A. RE-7807, Containment Airborne Radiation Monitor.
B. RE-7828C, Containment Purge Stack Radiation monitor.
C. RE-7820, In-Containment High Range Radiation Monitor.
D. RE-7822, Fuel Handling Building Ventilation Airborne Radiation Monitor.
Proposed Answer: __A__
Explanation (Optional):
Technical Reference(s): ___System Description SD-SO23-690, Revision 9, page 127-132.
Proposed references to be provided to applicants during examination: None.
Learning Objective: ____52758_____________________ (As available)
Question Source: Bank # _N4330_
Modified Bank # _______ (Note changes or attach parent)
New ______
Question History: Last NRC Exam _____
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 11 _
55.43 _____
Comments: 072/K3.01 & 3.2: Knowledge of the effect that a loss or malfunction of the ARM system will have on the following: Containment ventilation isolation.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __2__ _____
Group # __2__ _____
K/A # ___079-K1.01_____
Importance Rating _3.2_ _____
- 65. A weld failure on the instrument air (IA) header has resulted in instrument air header pressure slowly decreasing. Assuming the system is functioning as designed and no operator action, the correct sequence of events as pressure continues to decrease is the:
A. Service Air (SA) to IA cross connect valve opens and then the nitrogen backup supply comes into service.
B. backup nitrogen supply comes into service and then the SA to IA cross-connect valve closes.
C. backup nitrogen supply comes into service and then the SA to IA cross-connect valve opens.
D. SA to IA cross connect valve closes and then the nitrogen backup supply comes into service.
Proposed Answer: ___C_
Explanation (Optional): As IA pressure lowers, the N2 backup will begin to supply nitrogen. If pressure continues to lower, then the SA cross connect will begin to open to supply the IA with SA. Therefore the correct answer is C.
Technical Reference(s): _System Description SD-SO23-570, Revision 7, page 32.
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam __NA___
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X___
10 CFR Part 55 Content: 55.41 _(7) _
55.43 _____
Comments: 079/K1.01 & 3.0 - Station Air/Knowledge of the physical connections and/or cause-effect relationships between the SAS and the following systems: IAS
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __3__ _____
Group # _____ _____
K/A # _____G2.1.1______
Importance Rating _3.7_ _____
- 66. A maintenance supervisor arrives in the control room and asks permission to block open a non-security fire door to facilitate communications between two electricians. The supervisor also informs you both electricians will have a direct view of the door, the door can be quickly closed, and there will not be anything strung through the door.
According to the Conduct of Operations, what is the maximum amount of time the door be left open continuously without implementing a Barrier Impairment?
A. 30 minutes B. 45 minutes C. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Proposed Answer: ___B__
Explanation (Optional): According to the Conduct of Operations procedure the fire door can be left open for no longer than 45 minutes without implementing a Barrier Impairment.
Therefore, the correct answer is B.
Technical Reference(s): _Conduct of Operations, SO123-0-A1, Revision 1, step 6.4.9.1 Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New __X____
Question History: Last NRC Exam ______
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 _(10)_
55.43 _____
Comments: 2.1.1 & 3.7 - Knowledge of the Conduct of Operations
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __3__ _____
Group # _____ _____
K/A # ___G2.1.22_______
Importance Rating _2.8_ _____
- 67. The plant is shutdown and shutdown cooling (SDC) is in operation. Current plant conditions are as follows:
All CEAs are fully inserted Chemistry reported RCS boron is at the required concentration for shutdown Tave is 210 degrees with a 25 degree per hour cooldown rate LPSI Pump A is in service for SDC All vessel head closure bolts are fully tensioned According to the Technical Specifications, the plant is currently in Mode:
A. 3.
B. 4.
C. 5.
D. 6.
Proposed Answer: __B____
Explanation (Optional): Mode 4 is defined as Keff<0.99 and Tave between 350 and 200 degrees.
Mode 3 is Tave>350 degrees and Modes 5 and 6 require Tave to be either less than 200 degrees or at least one vessel head closure bolt not fully tensioned. Therefore, the only correct answer is B.
Technical Reference(s): _Technical Specifications Table 1.1-1 Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam __NA________
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 __(5) 55.43 _____
Comments: 2.1.22 & 2.8 - Ability to determine the mode of operation.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __3__ _____
Group # _____ _____
K/A # ___G2.1.31_______
Importance Rating _4.2_ _____
- 68. The plant is operating at 100 percent power with all systems operable and in their normal configuration with the exception of the Steam Bypass Control System (SBCS). The SBCS main calculator has failed high.
In this situation, for the SBCS to be in automatic operation (direct acting) an operator doing a board walkdown in the control room should observe the SBCS:
A. Master Control Station remote/local switch in the local position.
B. Master Control Station remote/local switch in the remote position.
C. Valve Control Station remote/local switch in the local position.
D. Valve Control Station remote/local switch in the remote position.
Proposed Answer: __A___
Explanation (Optional): If the SBCS has failed, the Master Control Station (MCS) no longer receives a signal to open the pressure control valves if in remote. The MCS must be put in the local position and the setpoint adjusted for continued automatic operation. The SBCS Valve Control Station does not have a remote/local switch in the control room.
Therefore the only correct answer is A.
Technical Reference(s): _System Description SD-SO23-175, Revision 5, page 18.
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New __X____
Question History: Last NRC Exam __NA___
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content: 55.41 _(7)__
55.43 _____
Comments: 2.1.31/4.2 - Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __3__ _____
Group # _____ _____
K/A # ___G2.2.11_______
Importance Rating _2.5_ _____
- 69. The process for controlling a procedure containing a Single Use TCN includes:
A. printing the procedure from NDMS, putting the unique number on it, and stamping it FOR SINGLE USE ONLY B. printing the procedure from NDMS, ensuring it has an expiration date of less than 30 days, and stamping it FOR SINGLE USE ONLY.
C. getting the procedure from the cognizant personnel and ensuring it is stamped CONTROLLED COPY.
D. getting the procedure from the cognizant personnel, ensuring it is uniquely numbered, and stamped FOR INFORMATION ONLY .
Proposed Answer: __D____
Explanation (Optional): A procedure designated for single use only may not be printed from NDMS but must be obtained from the cognizant personnel. It must be uniquely numbered and stamped FOR INFORMATION ONLY. Therefore the only correct answer is D.
Technical Reference(s): _Administrative Procedure SO123-VI-1.0.1, Revision 15, step 6.1.9.
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam __NA___
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 _ (10) 55.43 _____
Comments: 2.2.11 & 2.5 - Knowledge of the process for controlling temporary changes.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __3__ _____
Group # _____ _____
K/A # ___G2.2.13_______
Importance Rating _3.6_ _____
- 70. The proper location for placing tags associated with PULLED fuses on 4 KV buses (bus pot fuses) is on the:
A. threaded hole in the fuse drawer faceplate.
B. fuses with the fuses taped together and placed in the fuse drawer.
C. fuse clip inside the fuse drawer with the drawer remaining open.
D. breaker cubicle door handle.
Proposed Answer: __A____
Explanation (Optional):
Technical Reference(s):___ SO123-XX-5______
Proposed references to be provided to applicants during examination: None Learning Objective: ___55439________________ (As available)
Question Source: Bank # N57303 Modified Bank # _______(Note changes or attach parent)
New _______
Question History: Last NRC Exam Unknown Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 _(10)_
55.43 _____
Comments: 2.2.13 & 3.6 - Knowledge of the tagging and clearance procedures
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __3__ _____
Group # _____ _____
K/A # ___G2.2.22_______
Importance Rating _3.4_ _____
- 71. The plant is about to enter Mode 1 during a startup when a review of the as-left data contained in a surveillance for Pressurizer Pressure - High RPS trip setpoints was performed. The results of the review are tabulated below.
RPS Channel Setpoint A 2398 PSIA B 2355 PSIA C 2393 PSIA D 2362 PSIA According to Technical Specification 3.3.1, RPS Instrumentation - Operating (Attached), if no operator action is taken the plant may:
A. enter Mode 1, but must be in Mode 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if repairs are not made.
B. enter Mode 1, but must be in Mode 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> if repairs are not made.
C. not enter Mode 1 and must be in Mode 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if repairs are not made.
D. not enter Mode 1 and must be in Mode 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> if repairs are not made.
Proposed Answer: __B____
Explanation (Optional): According to Table 3.3.1-1 operability for this function is required in Modes 1 and 2. The action statement says 3.0.4 in not applicable so the startup may continue into Mode 1. Action statement 3.3.1.B is entered giving the operator 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to complete the actions (or repairs) with an additional 6 (Action statement G) hours to get to Mode 3. This makes answer B the only correct answer.
Technical Reference(s): __Technical Specification 3.3.1_
Proposed references to be provided to applicants during examination: Technical Specification 3.3.1 including Table 3.3.1-1.
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New __X____
Question History: Last NRC Exam _NA____
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content: 55.41 (5) __
55.43 _____
Comments: 2.2.22 & 3.4 - Knowledge of limiting conditions for operations and safety limits.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __3__ _____
Group # _____ _____
K/A # ___G2.3.4________
Importance Rating _2.5_ _____
- 72. While reviewing an RWP, an operator on tour of the plant notes one accessible area that may be entered has a dose rate of 1073 mrem/hour and contamination levels of 31,162 dpm/100 cm2 beta/gamma. This area should be posted as a:
A. contamination area and radiation area.
B. high contamination area and radiation area.
C. contamination and high radiation area.
D. high contamination and high radiation area.
Proposed Answer: __C___
Explanation (Optional): Dose rates greater than 1000 mrem/hour is a high radiation area, contamination levels in excess of 1000 dpm is a contamination area, and contamination levels in excess of 100,000 dpm is a high contamination area. Therefore this area should be posted as a contamination and high radiation area.
Technical Reference(s): _Health Physics Procedure SO123-VII-20.11.1, Revision 7.
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New __X____
Question History: Last NRC Exam __NA___
Question Cognitive Level: Memory or Fundamental Knowledge _X___
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 _(12)_
55.43 _____
Comments: 2.3.4 & 2.5 - Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __3__ _____
Group # _____ _____
K/A # ___G2.3.10_______
Importance Rating _2.9_ _____
- 73. Consideration is being given to a high dose job that needs to be performed by Operations. The general dose rate in the area is 500 mrem/hour but can be reduced to 200 mrem/hour if lead shielding is installed. It will take 2 individuals an hour and a half to install the shielding if desired.
In order to minimize the total dose to get the high dose work done; A. install the lead and send one operator in to do the work.
B. install the lead and send two operators in to do the work.
C. do not install the lead and use one operator to do the work.
D. do not install the lead and use two operators to do the work.
Proposed Answer: __D____
Explanation (Optional): It will take 1500 mrem to install the shielding and with two operators working it will cost another 600 mrem for a total of 2100 mrem. Without the shielding it will cost 1500 mrem for the same two operators to get the work done and 2000 mrem if one operator does the work. Therefore the lowest total dose will be 1500 mrem making answer D the only correct answer.
Technical Reference(s): _Health Physics Procedure SO123-VII-20.4_
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam _NA________
Question Cognitive Level: Memory or Fundamental Knowledge _____
Comprehension or Analysis __X__
10 CFR Part 55 Content: 55.41 _(12)_
55.43 _____
Comments: 2.3.10 & 2.9 - Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __3__ _____
Group # _____ _____
K/A # ___G2.4.20_______
Importance Rating _3.3_ _____
- 74. According to 10CFR20, Standards for Protection Against Radiation Protection, one of the requirements for a Planned Special Exposure (PSE) is that the dose from all PSEs and all doses in excess of the limits may not exceed _____ times the annual dose limits during an individuals lifetime.
A. 5 B. 10 C. 20 D. 25 Proposed Answer: __A____
Explanation (Optional): 10CFR20.1206 (e)(1) states the individual may not exceed 5 times the lifetime annual dose limits. This makes A the only correct answer.
Technical Reference(s): 10CFR20.1206 (e)(1)_
Proposed references to be provided to applicants during examination: None Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam __NA___
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 __12_
55.43 _____
Comments: 2.4.20 & 3.3 - Knowledge of 10 CFR 20 and related facility radiation control requirements.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0 Examination Outline Cross-
Reference:
Level RO SRO Tier # __3__ _____
Group # _____ _____
K/A # ___G2.4.24_______
Importance Rating _3.3_ _____
- 75. One of the steps in the process of performing a radioactive gaseous release is to verify the Plant Vent Stack (PVS) airborne radiation monitor (3RE-7865-1) is operable.
The PVS airborne radiation monitor would be inoperable if the:
A. red SUPV MODE LED is illuminated.
B. red KYBD LOCKOUT LED is extinguished.
C. key has been removed from the NORM/SUPV keyswitch.
D. green EFF level OPERATE LED is illuminated.
Proposed Answer: __A___
Explanation (Optional): According to the reference procedure, the PVS monitor is operable if (among other things) the red SUPV MODE and KYBD LOCKOUT LEDs are extinguished, the key has been removed from the NORM/SUPV keyswitch, and the green EFF level OPERATE LED is illuminated. This makes A the only correct answer.
Technical Reference(s): _Operating Instruction SO23-8-15, Revision 16, step 1.8_
Proposed references to be provided to applicants during examination:
Learning Objective: _________________________ (As available)
Question Source: Bank # _______
Modified Bank # _______ (Note changes or attach parent)
New ___X___
Question History: Last NRC Exam __NA___
Question Cognitive Level: Memory or Fundamental Knowledge __X__
Comprehension or Analysis _____
10 CFR Part 55 Content: 55.41 _(7/10)_
55.43 _____
Comments: 2.4.24 & 3.3 - Knowledge of the process for performing a planned gaseous radioactive release.
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 76. The Reactor has tripped and 4 Full-length CEAs are stuck out. After opening the Reactor Trip circuit breakers locally, 2 CEAs fall in.
What are the proper actions by the operating crew in response to this event?
A. Emergency borate the RCS, and immediately go to the Functional Recovery.
B. Emergency borate the RCS, and immediately go to the Reactor Trip Recovery.
C. Emergency borate the RCS, finish the Standard Post Trip Actions, and diagnose a Functional Recovery entry.
D. Emergency borate the RCS, finish the Standard Post Trip Actions, and diagnose a Reactor Trip Recovery event.
ANSWER: D QUESTION TYPE: SRO KA# & KA VALUE: EPE07/G.2.4.1 & 4.6 - Reactor Trip/Knowledge of EOP entry conditions and immediate action steps.
REFERENCE:
SO23-12-1 SOURCE: Tier 1, Group 1, SONGS BANK#N3927 LEARNING OBJECTIVE: 56252 COGNITIVE RATING: H ATTACHMENTS: None JUSTIFICATION:
10CFR55 BASIS: 10CFR55.43 (5)
COMMENTS: Q 76
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 77. SONGS experienced an earthquake that annunciated the Operating Basis Earthquake Detected alarm. Since then, Unit 2 has been in a transient involving a loss of RCS inventory.
Current plant status is:
T Reactor coolant average temperature is 480 degrees and lowering T Pressurizer pressure is 2000 psig and lowering T Pressurizer level is 30% and lowering T VCT level is lowering T Charging flow to the reactor has been maximized T Containment Pressure is 0.8 psig and rising T SG levels are approximately 40% and rising Based on the current conditions, this event should be classified as a(n):
A. Unusual Event B. Alert C. Site Area Emergency D. General Emergency ANSWER: C QUESTION TYPE: SRO KA# & KA VALUE: APE022/G2.4.29 & 4.0 - Loss of Reactor Coolant/Knowledge of the emergency plan.
REFERENCE:
SO123-VIII-1, EPIP, Revision 22, page 22 of 75.
SOURCE: New Question - Tier 1, Group 1 LEARNING OBJECTIVE:
COGNITIVE RATING: H ATTACHMENTS: Emergency Plan Classification Chart JUSTIFICATION: In Mode 3, with the RCS leak rate greater than the capacity of the charging pumps, this is EAL B3.1. This is a Site Area Emergency.
10CFR55 BASIS: 10CFR55.43 (5)
COMMENTS: Q 77
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 78. The plant is shutdown with one train of shutdown cooling (SDC) in service. The Control Room Supervisor observes:
T hot is 180 degrees and is beginning to trend up The reactor coolant pumps were shutdown an hour ago in preparation for an outage project Pressurizer and VCT levels are trending down Charging flow is greater than letdown flow SDC pump amps are fluctuating approximately + 20 amps Containment sump inlet flow (as indicated on CFMS) is increasing The SDC pump just tripped Of the following, the Control Room Supervisor should diagnose these symptoms as a loss of:
A. RCS inventory and enter EOI SO23-12-3, Loss of Coolant Accident.
B. Pressurizer level control and enter AOI SO23-13-27, Pressurizer Pressure and Level Malfunction.
C. SDC and enter AOI SO23-13-15, Loss of Shutdown Cooling.
D. RCS inventory and enter AOI SO23-13-14, Reactor Coolant Leak.
ANSWER: C QUESTION TYPE: SRO KA# & KA VALUE: APE025/AA2.03 & 3.8 - Loss of RHR/Ability to determine and interpret the following as they apply to the Loss of RHR System:
Increasing reactor sump level.
REFERENCE:
AOI SO23-13-15, Loss of Shutdown Cooling, Revision 15 SOURCE: New Question - Tier 1, Group 1 LEARNING OBJECTIVE:
COGNITIVE RATING: H ATTACHMENTS: None JUSTIFICATION: Answers A and D are incorrect because the entry conditions include SDC not initially in service. Answer B is incorrect because there is no indication of a problem with the pressurizer level control system. Answer C is correct because the stated conditions meet the entry conditions for the referenced procedure (loss of RCS inventory/loss of SDCS flow).
10CFR55 BASIS: 10CFR55.43 (5)
COMMENTS: Q78
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 79. With Unit 2 at rated thermal power, an 8 gpm leak develops in the RCP 1A seal cooler and CCW surge tank level is rising rapidly. The reactor operator mis-diagnosed the transient and he has just tripped the running CCW pumps resulting in a complete loss of CCW.
At this point the SRO should immediately enter procedure:
A. SO23-13-6, Reactor Coolant Pump Seal Failure, to shutdown the failed RCP.
B. SO23-13-7, Loss of CCW/SWC, to establish the system lineup necessary to restore CCW.
C. SO23-12-1, Standard Post Trip Actions, after tripping the reactor due to the loss of CCW.
D. SO23-13-14, Reactor Coolant Leak, to isolate the RCS seal cooler leak.
ANSWER: B QUESTION TYPE: SRO KA# & KA VALUE: APE026/AA2.03 & 2.9 - Loss of Component Cooling Water/The valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition.
REFERENCE:
SOURCE: New Question - Tier 1, Group 1 LEARNING OBJECTIVE:
COGNITIVE RATING: H ATTACHMENTS: None JUSTIFICATION:
10CFR55 BASIS: 10CFR55.43 (5)
COMMENTS: Q 79
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 80. Given the following plant conditions:
- Channel A RCS hot leg temperature TT-0122-1 has failed and the affected functional units have been bypassed
- Channel C RCS hot leg temperature TT-0122-3 has also failed and the affected functional units have been placed in trip
- A loss of vital bus inverter 2Y004 occurs and the Reactor does NOT trip
- All other plant conditions are normal Which of the following action is required?
A. Initiate a Rapid Downpower per SO23-5-1.7, Power Operations.
B. Initiate a normal plant shutdown per SO23-5-1.7, Power Operations.
C. Manually trip the reactor and enter SO23-12-1, Standard Post Trip Actions.
D. Vital bus 2Y04 must be placed on its alternate source within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per SO23-13-18, Reactor Protection System Failure / Loss of Vital Bus Inverter.
ANSWER: A QUESTION TYPE: SRO KA# & KA VALUE: APE057/AA2.03 & 3.9 - Ability to determine and interpret the following as they apply to the Loss of a Vital Inst. Bust: RPS panel alarm annunciators and trip indicators.
REFERENCE:
SO23-13-18 SOURCE: Tier 1, Group 1; SONGS BANK#N56791 LEARNING OBJECTIVE: 55183 COGNITIVE RATING: H ATTACHMENTS: None JUSTIFICATION:
10CFR55 BASIS: 10CFR55.43 (5)
COMMENTS: Q 80
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 81. Technical Specification 3.4.4 requires two RCS loops be operable and in operation when in Mode 1. If an RCP malfunction resulted in degraded flow in one RCS loop, the following technical specification limit could be exceeded during some transients:
A. Azimuthal Power Tilt (Tq)
B. Departure from Nucleate Boiling (DNB)
C. Axial Shape Index (ASI)
D. Linear Heat Rate (LHR)
ANSWER: B QUESTION TYPE: SRO KA# & KA VALUE: 000015/17/G2.2.25 & 3.7 - RCP Malfunctions/Knowledge of basis in technical specifications for limiting conditions of operation and safety limits.
REFERENCE:
Technical Specification Bases B 3.4.4.
SOURCE: New Question - Tier 1, Group 1 LEARNING OBJECTIVE:
COGNITIVE RATING: F ATTACHMENTS: None JUSTIFICATION: The TS reference states The pump flow rate has been sized to provide core heat removal with appropriate margin to departure from nucleate boiling (DNB) during power operation. This makes B the only correct answer.
10CFR55 BASIS: 10CFR55.43 (3)
COMMENTS: Q 81
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 82. The San Onofre technical specifications and plant operating procedures limit the cooldown rate imposed on the reactor coolant system. Specifically, with the plant in Mode 2, the technical specifications limit pressurizer cooldown rate to per hour and, if exceeded, require pressurizer temperature be restored to within limits within .
A. 100 degrees; 30 minutes B. 100 degrees; 60 minutes C. 200 degrees; 30 minutes D. 200 degrees; 60 minutes ANSWER: C QUESTION TYPE: SRO KA# & KA VALUE: CE/A11/AA2.2 & 3.4 - Ability to determine and interpret the following as they apply to the RCS overcooling: Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.
REFERENCE:
NEW, Technical Specification 3.4.3.1 SOURCE: Tier 1, Group 2 LEARNING OBJECTIVE:
COGNITIVE RATING: F ATTACHMENTS: None JUSTIFICATION: The referenced technical specification limits pressurizer cooldown to 200 degrees in any one hour and require restoration within 30 minutes if exceeded. This makes answer C the only correct answer.
10CFR55 BASIS: 10CFR55.43 (2)
COMMENTS: Q 82
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 83. After shift turnover, the on-coming crew discovers a trippable Group 5 CEA is stuck and is misaligned from the other Group 5 rods by 10 inches. The stuck CEA is at 90 inches and the remainder of the Group is at 100 inches. The misalignment has existed for 60 minutes with the reactor at 80% power.
According to Technical Specification 3.1.5, Control Element Assembly (CEA) Alignment (attached), the crew:
A. may remain at 80% power.
B. must reduce power to 78% power.
C. must reduce power to 75% power.
D. must reduce power to 70% power.
ANSWER: B QUESTION TYPE: SRO KA# & KA VALUE: 000005/G2.1.10 & 3.9 - Inoperable/Stuck Control Rod: Knowledge of conditions and limitations in the facility license
REFERENCE:
Technical Specification 3.1.5 and LCS 3.1.105.
SOURCE: New Question - Tier 1, Group 2 LEARNING OBJECTIVE:
COGNITIVE RATING: H ATTACHMENTS: Technical Specification 3.1.5 and LCS 3.1.105 (including Power Reduction Graphs)
JUSTIFICATION: According to the referenced TS, power must be reduced to the limits in the COLR within 15 minutes. LCS 3.1.105.D is in effect and directs power be reduced according to Figure 3.1.105-4.
According to this graph, after 60 minutes power must be reduced by 2% (or to 78%). Answer A is for a non-group 6 rod that is
>112.5 inches, Answer C and D are for a Group 6 rod. This makes answer B the only correct answer.
10CFR55 BASIS: 10CFR55.43 (1)
COMMENTS: Q 83
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 84. At 0200 this morning, a partial loss of grid caused a plant transient and a power reduction from 100% to 70% rated thermal power. Generator voltage and frequency have been restored to normal.
Following the transient the operating crew noted an increase in RCS identified leakage and at 0400 an 18 gpm RCS leak was confirmed. The leak rate now appears to have stabilized. In discussions with the dispatcher concerning the technical specification (attached) required shutdown, she indicated that due to current grid conditions, the loss of the SONGS generator would result in a loss of a large part of the grid (including power for SONGS, many hospitals, and 3 major airports). It is now 0900.
In this situation, the Control Room Supervisor:
A. must comply with the technical specifications and have the plant in Mode 3 by 1200.
B. may make the decision to remain at power under authority granted by NRC Regulation.
C. may keep the plant at power if a 50.59 Evaluation indicates there is no elevated safety risk.
D. may keep the plant at power if authorization is obtained from the SONGS Senior NRC Resident Inspector.
ANSWER: B QUESTION TYPE: SRO KA# & KA VALUE: CE/A16/AA2.2 & 3.7 - Excess RCS Leakage/Ability to determine and interpret the following as they apply to the (Excess RCS Leakage): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.
REFERENCE:
10CFR50.54 (x and y)
SOURCE: New Question - Tier 1, Group 2 LEARNING OBJECTIVE:
COGNITIVE RATING: F ATTACHMENTS: None JUSTIFICATION: 10CFR50.54 (x and y) authorize a licensed SRO to deviate from technical specifications if in the best interest of the public health and safety and no other resolution is viable. Therefore, answer C is correct (making answer A incorrect). The resident inspectors are not authorized to approve TS non-compliance making B incorrect and a 50.59 may not be used to approve TS non-compliance making D incorrect.
10CFR55 BASIS: 10CFR55.43 (5)
COMMENTS: Q 84
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 85. A Shutdown From Outside the Control Room is in progress. All control room immediate actions are complete and the operator actions outside the control room have not been started.
Plant conditions are:
T RCS pressure is 2050 psia and slowly lowering.
o T T- hot is 575 F and slowly lowering.
o T T-cold is 555 F and stable.
T Pressurizer level (actual) is 21% and slowly lowering.
T S/G E089 level (actual) is 58% narrow range.
T Off-site power is available.
Which of the following statements is correct for the current plant conditions?
A. Natural Circulation is not established and SO23-13-2, Shutdown from Outside the Control Room, should be in use.
B. Natural circulation is established and procedure SO23-13-2, Shutdown from Outside the Control Room, should be in use.
C. Forced circulation is in operation and procedure SO23-13-2, Shutdown from Outside the Control Room, should be in use.
D. Natural circulation is not established and FS-3, Monitor Natural Circulation Established, should be in use per procedure SO23-12-7, Loss of Forced Circulation/Loss of Offsite Power.
ANSWER: B QUESTION TYPE: SRO KA# & KA VALUE: CEA13/AA2.1 & 3.7 - Natural Circulation Operations/Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
REFERENCE:
SO23-13-2, Shutdown From Outside the Control Room, Revision 7
SOURCE: Modified Bank Question 73899 - Tier 1, Group 2 LEARNING OBJECTIVE:
COGNITIVE RATING: H ATTACHMENTS: None JUSTIFICATION: Per the referenced procedure, the plant condition satisfy the criteria for determining natural circulation is established making answers C and D incorrect. One of the immediate actions for evacuating the control room is to trip the RCPs making answer A incorrect. Answer B is correct because natural circulation is established and the SRO should be using SO23-13-2.
10CFR55 BASIS: 10CFR55.43 (5)
COMMENTS: Q 85
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 86. With the reactor at rated thermal power (RTP), the reactor operator reports pressurizer pressure has reached 2280 psig and is rising. The operator also reports:
-Pressurizer pressure for the selected channel (PT-100-X) indicates downscale.
-Pressurizer level is stable.
-All pressurizer heaters indicate energized.
-There is no indication of pressurizer sprays.
In this situation, the control room supervisor would implement procedure:
A. S023-3-1.10, Foxboro Alarm Response, to diagnose the controller failure.
B. S023-13-27, Pressurizer Pressure and Level Malfunction, in order to restore the quick open function of the steam bypass control valves.
C. S023-13-14, Reactor Coolant Leak, in order to determine if there is a reactor coolant leak.
D. S023-13-27, Pressurizer Pressure and Level Malfunction, in order to restore pressurizer pressure to the normal band.
ANSWER: D QUESTION TYPE: SRO KA# & KA VALUE: 010/A2.02 & 3.9 - Pressurizer Pressure Control/Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Spray Valve Failures.
REFERENCE:
SOURCE: New Question - Tier 2, Group 1 LEARNING OBJECTIVE:
COGNITIVE RATING: H ATTACHMENTS: None JUSTIFICATION:
10CFR55 BASIS: 10CFR55.43 (5)
COMMENTS: Q 86
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 87. An off-site agency has notified SONGS Security that they have a credible report stating five bombs have been planted on-site. An on-going search has discovered two bombs on the Unit 2 main steam lines just outside containment. In response, Security has just informed the control room they have declared a SECON RED.
According to procedure S023-13-25, Operator Actions During Security Events, the control room SRO should immediately direct:
A. the NRC be notified.
B. off-site law enforcement officials be notified.
C. an immediate evacuation of all non-essential personnel from the site.
D. both reactors be tripped.
ANSWER: D QUESTION TYPE: SRO KA# & KA VALUE: 039/G2.4.28 & 3.3 - Main and Reheat Steam/Knowledge of Procedures relating to emergency response to sabotage.
REFERENCE:
S023-13-25, Operator Actions During Security Events, Revision 2, TCN 2-2, steps 1 and 2.
SOURCE: New Question - Tier 2, Group 1 LEARNING OBJECTIVE: CAF COGNITIVE RATING: F ATTACHMENTS: None JUSTIFICATION: The reference procedure states that when a SECON RED is declared, both units reactors are to be tripped. Therefore, answer D is correct.
10CFR55 BASIS: 10CFR55.43 (5)
COMMENTS: Q 87
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 88. The plant is in Mode 2 with all CEAs fully inserted with the RPS trip breakers open. Several problems have recently developed during the shutdown. Currently, the plant situation is:
T RCS pressure and temperature are stable and being controlled by the pressurizer and atmospheric dump valves T Pressurizer level is stable T MSIVs are closed due to an unisolable steam leak downstream of the MSIVs T Steam generator levels are at 37% and 54%
T AFW pump P141 in service T AFW pump P504 tripped on overspeed and cannot be reset T The turbine driven AFW pump is tagged out of service T All other plant equipment is operable.
Currently the Shift Manager, Plant Manager, and Operations Manager are in a meeting discussing a recovery strategy for the current situation.
If AFW pump P141 is lost, the crew would eventually be forced to:
A. enter AOI - Loss of Feedwater and then trip the RCPs.
B. trip the RCPs and enter AOI - Loss of Forced Circulation/Loss of Offsite Power.
C. enter AOI - Loss of Feedwater and then transition to FR-5, Recovery - Heat Removal.
D. enter AOI - Loss of Feedwater and then implement EOI Attachment 3, Cooldown /
Depressurization.
ANSWER: A QUESTION TYPE: SRO KA# & KA VALUE: 061/A2.04 & 3.8 - Auxiliary/Emergency Feedwater/Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: pump failure or improper operation.
REFERENCE:
SO23-12-6, Loss of Feedwater, Revision 19 SOURCE: New Question, Tier 2, Group 1 COGNITIVE RATING: H ATTACHMENTS: None JUSTIFICATION: With the reactor trip breakers open, a loss of all feedwater will require the operators to directly enter EOI Loss of Feedwater.
The first action is to trip the RCPs. The procedure will direct the crew to depressurize and line up for injecting to the SGs using condensate pumps. This makes B the only correct answer. EOI Attachment 3, FRP - 5, and Loss of Forced Circulation will not be used/implemented making answers A, C, and D incorrect.
10CFR55 BASIS: 10CFR55.43 (5)
COMMENTS: Q 88
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 89. This morning at 0800, with the reactor in Mode 1, a maintenance supervisor reports that Technical Specification Surveillance SR 3.8.4.2, DC Sources - Operating (attached), has not been performed on the safety related batteries for Trains A and C. The supervisor also reports the special tool needed for the surveillance is off-site for calibration. Both surveillances are now beyond the 1.25 grace period allowed by the technical specification.
Without a risk evaluation, if the surveillances are not performed the plant must be in Mode 3 by:
A. 1500 today.
B. 1600 today.
C. 1500 tomorrow.
D. 1600 tomorrow.
ANSWER: C QUESTION TYPE: SRO KA# & KA VALUE: 063/G2.2.12 & 3.4 - D. C. Electrical Distribution/Ability to apply technical specifications for a system.
REFERENCE:
Technical Specifications SOURCE: New Question - Tier 2, Group 1 LEARNING OBJECTIVE: CAF COGNITIVE RATING: H ATTACHMENTS: Technical Specification 3.8.4, DC Sources - Operating including the SRs JUSTIFICATION: Technical Specification SR 3.0.3 states that if a surveillance is missed it must be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless a risk evaluation is performed. Therefore, without a risk evaluation, TS 3.8.4 would be entered for the two batteries being inoperable at 0800 tomorrow. Because there is no LCO condition addressing two inoperable batteries, LCO 3.0.3 would be entered requiring Mode 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> of entering the LCO. Therefore, C is correct (24 plus 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />).
10CFR55 BASIS: 10CFR55.43 (2)
COMMENTS: Q 89
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 90. Unit 2 is operating at 100 % power. All valves and controls in the Pressurizer Pressure and Level Control Systems are in automatic. Due to an break in the line around the air filter coincident with maintenance on the Nitrogen system, the alarms listed below annunciate, indicating a LOSS of INSTRUMENT AIR (IA) and its Nitrogen backup (N2). Efforts to restore these systems to service have been unsuccessful. Annunciated Alarms:
- 50A22, Pzr Level Error Hi
- 58A21, Letdown Backpressure Hi/Lo
- 61B58, Instrument Air Compressor Control Panel Trouble
- 61B59, Instrument Air Compressor OC
- 61B38, N2 Supply to Inst Air Header On The effect on Technical Specification system operability is:
A. AFW system remains operable since its steam supply valve fails open.
B. PZR is inoperable because the spray valves fail closed.
C. SITs are inoperable because the fill valves fail closed.
D. ADVs are inoperable due to loss of operating air.
ANSWER: A QUESTION TYPE: SRO KA# & KA VALUE: 078/A2.01 & 2.9 - Instrument Air/Ability to (a) predict the impacts of the following malfunctions or operations on the IAS; and (b) based on the those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Air dryer and filter malfunctions.
REFERENCE:
S023-13-5, Loss of Instrument Air, Revision 4, TCN 4-1, Attachment 2 and SO23-12-1, Standard Post Trip Actions, Revision 19.
SOURCE: New Question - Tier 2, Group 1 LEARNING OBJECTIVE: CAF COGNITIVE RATING: H ATTACHMENTS: None JUSTIFICATION: AFW steam supply valve fails open and it remains operable; the valves fail as indicated on the other systems, but they do not become inoperable.
10CFR55 BASIS: 10CFR55.43 (2)
COMMENTS: Q 90
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 91. A Loss of Coolant Accident is in progress and the following conditions exist:
T There is no AC power (station blackout).
T Pressurizer level has been below the indicating range for >1 hour.
T The reactor operator just reported a CET temperature of 713 degrees.
T EOI - Station Blackout is currently in use.
T One AFW pump is in operation.
Based on this situation, the SRO should conclude:
A. the RPV has just reached saturation conditions and Attachment 5, Core Exit Saturation Margin Control, should be implemented.
B. RPV water level is below the top of the core and FR-5, Recovery - Heat Removal Recovery, should be implemented.
C. RPV water level is below the top of the core and FR-3, Recovery - RCS Inventory Control, should be implemented.
D. core damage is in progress and recommend implementation of the SAMGs.
ANSWER: B QUESTION TYPE: SRO KA# & KA VALUE: 017/A2.02 & 4.1 - In-Core Temperature Monitor/Ability to (a) predict the impacts of the following malfunctions or operations on the ITM; and (b) based on the those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Core damage.
REFERENCE:
EOI SOURCE: New Question - Tier 2, Group 2 LEARNING OBJECTIVE:
COGNITIVE RATING: H ATTACHMENTS:
JUSTIFICATION: A CET temperature indicates water level is below the top of the core and is super heated making A incorrect. Because it just went over 700 degrees no core damage has yet occurred making D incorrect. According to the EOI exceeding 700 degrees sends to operator to FR-5 making answer C the only correct answer.
10CFR55 BASIS: 10CFR55.43 (5)
COMMENTS: Q 91
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 92. While operating at 90% power, a CEA DEVIATION alarm is received.
The ACO notes that a single CEA in Group 6 is misaligned from the remainder of the CEAs within that group by 15 inches.
It has been 60 minutes since the misalignment occurred, and no change in misalignment has been achieved yet. The MAXIMUM power level for plant operation at this time is:
A. 85%
B. 80%
C. 95%
D. 90%
ANSWER: A QUESTION TYPE: SRO KA# & KA VALUE: 001-A2.03 & 4.2 - CRDS: Ability to (a) predict the impacts of the following malfunction or operations on the CRDS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
effect of stuck rod or misaligned rod
REFERENCE:
Tech Spec LCS 3.1.105 SOURCE: Tier 2, Group 2; SONGS BANK N10962 LEARNING OBJECTIVE: 54876 COGNITIVE RATING: H ATTACHMENTS: Tech Spec LCS 3.1.105 JUSTIFICATION: using the graphs at the back of the LCS, 60 minutes of misalignment for a Group-6 rod requires a 5% power reduction, so 85% is correct.
10CFR55 BASIS: 10CFR55.43 (2)
COMMENTS: Q 92
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 93. Due to a failed pressure switch in the Firewater Supply System, a control room fire protection alarm was declared inoperable and an Alarm Compensatory Action (ACA) was initiated. The faulty pressure switch was replaced and successfully tested.
According to S023-6-29, Operation of Annunciators and Indicators, the discontinuation of the ACA must be approved by the:
A. Control Room Supervisor.
B. Shift Manager.
C. Fire Protection System Engineer.
D. SRO Operations Supervisor.
ANSWER: D QUESTION TYPE: SRO KA# & KA VALUE: 086/G2.4.33 & 2.8 - Fire Protection/Knowledge of the process to track inoperable alarms.
REFERENCE:
S023-6-29, Operation of Annunciators and Indicators, Revision 13, Step 6.3.12 SOURCE: New Question - Tier 2, Group 2 LEARNING OBJECTIVE: CAF COGNITIVE RATING: F ATTACHMENTS: None JUSTIFICATION: According to the referenced procedure, approval is obtained from the SRO Operations Supervisor prior to closing out the ACA.
Therefore the answer is C.
10CFR55 BASIS: 10CFR55.43 (3)
COMMENTS: Q 93
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 94. Reactor power has been reduced to 75 % and:
T The COLSS and COLSS Backup Computers are out of service T All COLSS out of service surveillances are satisfied T The ESI for this power level is -0.020 T ASI average is -0.0412 as read on the CPCs T Part Length CEAs are at 130" and Group 6 CEAs are ARO.
If it is desired to start ASI trending towards ESI, procedures should be implemented that will:
A. insert Part Length CEAs.
B. withdraw Part Length CEAs.
C. insert Group 6 CEAs.
D. withdraw Group 6 CEAs.
ANSWER: A QUESTION TYPE: SRO KA# & KA VALUE: G2.1.7 & 4.4 - Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation.
REFERENCE:
SOURCE: Bank Question 74295 - Tier 3 LEARNING OBJECTIVE:
COGNITIVE RATING: H ATTACHMENTS: None JUSTIFICATION: As per the licensee bank answer key 10CFR55 BASIS: 10CFR55.43 (5)
COMMENTS: Q 94
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 95. Fuel handling is in progress in both the Fuel Handling Building and Containment Refueling Area when voice communications with Containment is lost.
Without voice communications between the Control Room and Containment, the SRO in charge of refueling:
A. must stop all fuel movements.
B. may continue moving fuel in the Fuel Handling Building.
C. may continue moving fuel with the approval of the Shift Manager.
D. may continue moving fuel with the approval of the Refueling Engineer.
ANSWER: B QUESTION TYPE: SRO KA# & KA VALUE: G2.2.26 & 3.7 - Knowledge of refueling administrative requirements.
REFERENCE:
Procedure S023-X-7, Nuclear Fuel Movement for Refueling Cycles, Revision 11, Step 4.8.2.
SOURCE: New Question - Tier 3 LEARNING OBJECTIVE:
COGNITIVE RATING: H ATTACHMENTS: None JUSTIFICATION: The referenced procedure states fuel movement may continue in the unaffected area if voice communications are lost in one area.
There is no provision for continuing moving fuel after obtaining the approval of the Shift Manager or Refueling Engineer. Therefore, the correct answer is B.
10CFR55 BASIS: 10CFR55.43 (7)
COMMENTS: Q 95
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 96. The reactor is operating at rated thermal power. On April 1, the Turbine Driven AFW (TDAFW) pump was tagged out and declared inoperable at 1200 to allow maintenance to work on HV 8200, (TDAFW pump steam admission valve from E089 Main Steam Header). On April 3 at 1800, the supply breaker for motor driven AFW pump P141 was found in the tripped free position and cannot be reset. Also on April 3, the TDAFW pump was restored to an operable status at 2300.
If AFW pump P141 is not repaired, when does technical specification 3.7.5 (attached) require the reactor be in Mode 4?
A. April 5 at 0600 B. April 7 at 0600 C. April 7 at 1200 D. April 13 at 1800 ANSWER: B QUESTION TYPE: SRO KA# & KA VALUE: G2.2.24 & 3.8 - Ability to analyze the affect on maintenance on LCO status.
REFERENCE:
Technical Specification 3.7.5.
SOURCE: New Question - Tier 3 LEARNING OBJECTIVE: CAF COGNITIVE RATING: H ATTACHMENTS: Tech Spec 3.7.5.
JUSTIFICATION: When the TDAFW is returned to an operable status the only tech spec in effect is for the MDAFW pump. That clock started at 1800 on April 3. The spec allows 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (3.7.5.B) and then 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (3.7.5.E) for Mode 4. Therefore, answer B is correct.
10CFR55 BASIS: 10CFR55.43 (2)
COMMENTS: Q 96
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 97. It is 0300 in the morning and the Control Room Supervisor has been asked to authorize a work package for a specialized contract welder to perform work in a high radiation area (HRA).
The CRS notes that the welder is a qualified radiation worker and has accumulated 3.5 rem of exposure thus far this year (2.5 rem during the first quarter and 1.0 rem during the second quarter). The expected dose rate in the work area is 250 mrem/hr general background radiation. According to 10CFR20 - Standards For Protection Against Radiation; A. the work can not exceed 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
B. the work can not exceed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C. the work must be performed as a Planned Special Exposure.
D. the welder must be accompanied by a qualified health physics individual.
ANSWER: A QUESTION TYPE: SRO KA# & KA VALUE: G2.3.1 & 3.0 - Knowledge of 10CFR20 and related facility radiation control requirements.
REFERENCE:
10CFR20 SOURCE: New Question - Tier 3 LEARNING OBJECTIVE:
COGNITIVE RATING: H ATTACHMENTS: None JUSTIFICATION: The limit is 5 rem so the welder can work for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
10CFR55 BASIS: 10CFR55.43 (4)
COMMENTS: Q 97
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 98. It is desired to perform a gaseous radioactive release from Waste Gas Decay Tank T-083.
A release permit for this radioactive release:
A. would be generated by Chemistry.
B. would be generated by Health Physics.
C. is not required as long as at least one Waste Gas Compressor is operable.
D. is not required as long as the Plant Vent Stack Radiation Monitor remains operable.
ANSWER: A QUESTION TYPE: SRO KA# & KA VALUE: G2.3.8 & 3.2 - Knowledge of the process for performing a planned gaseous radioactive release.
REFERENCE:
Procedure S023-8-15, Radwaste Gas Discharge, Revision 16, Attachment 1, step 1.5.
SOURCE: New Question - Tier 3 LEARNING OBJECTIVE:
COGNITIVE RATING: F ATTACHMENTS: None JUSTIFICATION: For a release of WGDT T-083 a release permit is required to be obtained from Chemistry per the referenced procedure regardless of system operability. Radiation protection is not involved in this activity. Therefore, answer C is correct.
10CFR55 BASIS: 10CFR55.43 (4)
COMMENTS: Q 98
San Onofre Generating Station SRO Written Examination Key April 2005 - Revision 0
- 99. Following the declaration of a Site Area Emergency, an EMERGENCY RADIATION EXPOSURE exceeding 10CFR20 limits can be authorized by the:
A. Shift Manager.
B. Plant Manager.
C. Operations Manager.
D. Health Physics Manager.
ANSWER: A QUESTION TYPE: SRO KA# & KA VALUE: G2.4.40 & 4.0 - Knowledge of the SROs responsibilities in emergency plan implementation.
REFERENCE:
SO123-VIII-10 Precaution 4.3 SOURCE: Modified Exam Bank Question #N57501 - Tier 3 LEARNING OBJECTIVE: 55369 COGNITIVE RATING: F ATTACHMENTS: None JUSTIFICATION: Per licensee exam bank 10CFR55 BASIS: 10CFR55.43 (2)
COMMENTS: Q 99
SONGS RO Written Examination Key April 2005 - Revision 0 100. Given the following conditions:
- A S/G tube leak of 100 gpm is in progress on S/G E089
- Subsequently, a Steam Line Safety Valve sticks open on S/G E089, causing a reactor trip
- An MSIS has occurred
- A SIAS has actuated on low Pressurizer pressure
- No equipment is out of service, and all components have operated properly This event would be classified as meeting EAL:
A. A2-6 B. A3-3 C. B3-1 D. C4-2 ANSWER: B QUESTION TYPE: SRO KA# & KA VALUE: G2.4.41 & 4.1 - Knowledge of the emergency action level thresholds and classifications.
REFERENCE:
SO123-VIII-1 SOURCE: Bank #N57575 Question - Tier 3 LEARNING OBJECTIVE: 53165 COGNITIVE RATING: H ATTACHMENTS: EPIPs JUSTIFICATION: Per Exam Bank 10CFR55 BASIS: 10CFR55.43 (5)
COMMENTS: Q 100