Text

Initial Exam 2012-302 Draft SRO Written Exam
	ML13025A025
Person / Time
Site:	Oconee
Issue date:	01/22/2013
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1LT42 ONS SRO NRC Examination QUESTION 76 761 APEOO8 AA2.lO Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck Open)

Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: (CFR: 43.5 / 45.13)

High-pressure injection valves and controllers Given the following Unit 1 conditions:

Time 0400

Reactor power = 100%

1HP-410 closed with breaker tagged open for maintenance Time = 0405

Transient occurs

1 RC-67 opens

1 SA-i 8/A-i (Pressurizer Relief Valve Flow) actuated Time = 0425

SCM=0°F

1HP-26 failed closed

LOSCM tab in progress

300 gpm EFDW flow established to each SG

1) BOTHSGswillbe (1).

2) The next action directed by the LOSCM tab will be to (2)

Which ONE of the following completes the statements above?

A. 1. fully depressurized

2. increase EFDW flow to 1000 gpm per SG B. 1. fully depressurized

2. throttle EFDW flow to maintain RCS cooldown rates within limits

C. 1. depressurized to not less than 250 psig

2. increase EFDW flow to 1000 gpm per SG D. 1. depressurized to not less than 250 psig

2. throttle EFDW flow to maintain RCS cooldown rates within limits Friday, October 12, 2012 Page 152 of 212

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1LT42 ONS SRO NRC Examination QUESTION 76 General Discussion Answer A Discussion Correct. Due to HPI flow in one header only, BOTH SGs will be fully depressurized and EFDW floww will be increase to 1000 gpm per heaj Answer B Discussion Incorrect. First part is correct. Second part is plausible because it would be correct without degraded HPI flow.

Answer C Discussion Incorrect. First part is plasuible because with only the TDEFDW pump operating it would be correct. Second part is correct.

Answer D Discussion Incorrect. First part is plasuible because with only the TDEFDW pump operating it would be correct. Second part is plausible because it would be correct without degraded HPI flow.

Basis for meeting the KA Question requires knowledge of the effeect of a loww of HPI injection valves have during a vapor space accident and action taken as a result.

Basis for Hi Cog Basis for SRO only Per Clarification Guidance for SRO-only Questions Rev 1 Question requires: Assessing plant conditions (normal, abnormal, or emergency) and then selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed Have to asses plant conditions and determine how the SG will be used to mitigate the event.

Can the question be answered solely by knowing systems knowledge, i.e., how the system works, flow path, logic, component location? NO

Can the question be answered solely by knowing immediate operator actions? NO Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? NO Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? NO Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided LOSCM tab Rule 7 APEOO8 AA2.10 - Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck Open)

Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: (CER: 43.5 / 45.13)

High-pressure injection valves and controllers 401-9 Comments: RemarkslStatus Friday, October 12, 2012 Page 153 of 212

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1LT42 ONS SRO NRC Examination QUESTION 77 APEO15/017 AA2.lO - Reactor Coolant Pump (RCP) Malfunctions Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): (CFR 43.5 /45.13)

When to secure RCPs on loss of cooling or seal injection Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 75%

AP/20 (Loss of Component Cooling) in progress Current conditions:

1A1 RCP Radial Bearing Temperature 248°F stable In accordance with AP/20:

1) The 1A1 RCP(1) required to be secured.

2) If the RCP is required to be secured the reactor (2) be tripped first.

Which ONE of the following completes the statements above?

A. 1.is

2. will B. 1.is

2. will NOT C. 1. is NOT

2. will D. 1. is NOT

2. will NOT Friday, October 12, 2012 Page 154 of 212

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1LT42 ONS SRO NRC Examination QUESTION 77 A 7

General Discussion Answer A Discussion Correct. Per AP/20 IAAT RCP radial bearing temp exceeds 225 then the RCP must be secured. Because Reactor power is above 70%, AP/20 directs tripping the reactor and then the RCP.

Answer B Discussion Incorrect. First part is correct. Second part is plausible because if reactor power were below 70% then it would be correct.

Answer C Discussion Incorrect. First part is plausible because AP/1 6 list other immediate RCP trips above 248 degrees. le MTR STATOR if 295 degrees. Second part is correct.

Answer D Discussion Incorrect. First part is plausible because AP/16 list other immediate RCP trips above 248 degrees. le MTR STATOR if 295 degrees. Second part is plausible because if reactor power were below 70% then it would be correct.

Basis for meeting the KA uestion requires knowledge of when a RCP must be secured with a loss Component Cooling.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions Rev I:

This question requires the following:

Assessing plant conditions (normal, abnormal, or emergency) and then selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed Requuires asses the plant conditions and determining if the reactor will be tripped or not prior to securing the RCP.

Knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event specific sub procedures or emergency contingency procedures.

Can the question be answered solely by knowing systems knowledge, i.e., how the system works, flow path, logic, component location? NO Can the question be answered solely by knowing immediate operator actions? NO Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? NO Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? NO Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided AP/20 AP/l6 APEO 15/017 AA2. 10 - Reactor Coolant Pump (RCP) Malfunctions Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): (CFR 43.5 / 45.13)

When to secure RCPs on loss of cooling or seal injection 401-9 Comments: marksIStatus Friday, October 12, 2012 Page 155 of 212 a

FOR REVIEW ONLY DO NOT DISTRIBUTE 1LT42 ONS SRO NRC Examination QUESTION 77 Friday, October 12, 2012 Page 156 of 212

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1LT42 ONS SRO NRC Examination QUESTION 78 L 78 N/A - N/A Never Assigned to a K/A Given the following Unit 2 conditions:

Refueling in progress

FTC level = 22 feet stable

No water additions are being made to the system

2A LPI train is operable and in service Current conditions:

Refueling SRO desires stopping the 2A LPI Pump to aid in inserting a fuel assembly

2A LPI pump has been in continuous operation for the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Which ONE of the following describes whether the 2A LPI pump may be stopped in accordance with OP/2/AJ1 502/007 (Operations Defueling /Refueling Responsibilities) and the bases for this action?

A. 2A LPI Pump may be stopped FTC provides adequate backup decay heat removal B. 2A LPI Pump may be stopped Spent Fuel Cooling system provides adequate backup decay heat removal C. 2A LPI Pump may NOT be stopped FTC does NOT provide adequate backup decay heat removal.

D. 2A LPI Pump may NOT be stopped Spent Fuel Cooling does NOT provide adequate backup decay heat removal Friday, October 12, 2012 Page 157 of 212

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1LT42 ONS SRO NRC Examination QUESTION 78 L 78j General Discussion Answer A Discussion Correct. TS 3.9.4 (Refueling Ops- DHR and Coolant Circulation (High Water Level) is in effect as water level is 3 21.34 ft. This condition requires only I DHR loop to be operable and in service since the water can provide adequate backup decay heat removal. TS and Refueling procedures limits & precautions allow SRO to grant permission for the operating loop to be secured for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months with adequate level.

Answer B Discussion Incorrect: First part is correct. 2nd part is incorrect but plausible since Spent Fuel Cooling (SFC) helps to provide decay heat removal but is not the basis for allowing the pump to be secured for up to an hour.

Answer C Discussion Incorrect: First part is incorrect but plausible if TS 3.9.5 criteria are misapplied to this situation. TS3.9.5 (DHR and Coolant Circulation Low Water Level) requires 2 operable DHR loops with one loop in service (no time is allowed for a pump to be secured). 2nd part is wrong but plausible in that it would be true if level was below the refueling level of 21.34 ft.

Answer D Discussion Incorrect: First part is incorrect but plausible if TS 3.9.5 criteria are misapplied to this situation. TS3.9.5 (DHR and Coolant Circulation Low Water Level) requires 2 operable DHR loops with one loop in service (no time is allowed for a pump to be secured). 2nd part is incorrect but plausible since Spent Fuel Cooling (SFC) helps to provide decay heat removal but is not the basis for allowing the pump to be secured for up to an hour.

Basis for meeting the KA Requires knowledge of SRO duties during fuel handling. Including the provision to cause a temporary loss of DHR under certain conditions.

Basis for Hi Cog Basis for SRO only Requires knowledge of procedures and limitations involved in core alterations (43.6), TS and Bases (43.2). Requires knowledge of the bases of TS 3.9.4.

Job Level Cognitive Level QuestionType Question Source SRO Memory BANK ONS 2009A Q95 Development References Student References Provided OP/0/AIl 506/001 OP/2/A/l 5 02/007 TS 3.9.4 TS B3.9.4

TS 3.9.5 ONS 2009A Q95 1

N/A - N/A Never Assigned to a K/A 401-9 Comments: I RemarkslStatus Friday, October 12, 2012 Page 158 of 212

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1LT42 ONS SRO NRC Examination QUESTION 79 APEO54 AA2.06 Loss of Main Feedwater (MFW)

Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW): (CFR: 43.5 / 45.13)

AFW adjustments needed to maintain proper T-ave. and SIG level Given the following Unit 1 conditions:

Time = 0400

Reactor power = 100%

2SA-1 8/A-i 1 (TurbineBSMT Water Emergency High Level) actuates Time = 0402

BOTH Main FDW Pumps trip Time 0407

Both SGs level 30 inches XSUR stable In accordance with the TBF tab:

1) EFDWflowwill be (1)

2) Subsequently if, ALL EFDW is lost (2)

Which ONE of the following completes the statements above?

A. 1. adjusted to increase BOTH SGs to 95% O.R.

2. HPI Forced Cooling will be initiated B. 1. adjusted to increase BOTH SGs to 95% O.R.

2. SSF-ASW flow will be established to BOTH SGs C. 1. controlled in accordance with the guidance in Rule 7 (SG Feed Control),

Table 4 (SG Level Control Points)

2. HPI Forced Cooling will be initiated D. 1. controlled in accordance with the guidance in Rule 7 (SG Feed Control),

Table 4 (SG Level Control Points)

2. SSF-ASW flow will be established to BOTH SGs Friday, October 12, 2012 Page 159 of 212

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1LT42 ONS SRO NRC Examination QUESTION 79 79j General Discussion Answer A Discussion Incorrect. First part is correct. Second part is plausible because HPI F/C would normally be the next choice for decay heat removal.

Answer B Discussion Correct. Per notes in the TBF tab:

Feeding to 95% OR. in Step 1 supersedes guidance in Rule 7 (SG Feed Control), Table 4 (SO Level Control Points)

For long term cooling, maintenance of stable shutdown conditions from the SSF is preferred over the initiation of HPI forced cooling.

Answer C Discussion Incorrect. First part is plausible because Rule 7 normally provides guidance on how to feed the SOs. Second part is plausible because HPI F/C would normally be the next choice for decay heat removal.

Answer D Discussion Incorrect. First part is plausible because Rule 7 normally provides guidance on how to feed the SGs. Second part is correct.

Basis for meeting the KA Question requires knowledge how EFDW will be controlled during a loss of Main FDW during a turbine building flood.

Basis for Hi Cog 1

Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions Rev 1:

Question requires detailed knowledge of EOP during a loss of MFDW along with a turbine building flood.

This question requires the following:

Assessing plant conditions (normal, abnormal, or emergency) and then selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed Can the question be answered solely by knowing systems knowledge, i.e., how the system works, flow path, logic, component location? NO Can the question be answered solely by knowing immediate operator actions? NO Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? NO Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? NO Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided TBF tab APEO54 AA2.06 Loss of Main Feedwater (MFW)

Ability to determine and interpret the following as they apply to the Loss of Main Feedvater (MFW): (CFR: 43.5 / 45.13)

AFW adjustments needed to maintain proper T-ave. and S/G level 401-9 Comments: RemarkslStatus Friday, October 12, 2012 Page 160 of 212

FOR REVIEW ONLY DO NOT DISTRIBUTE 1LT42 ONS SRO NRC Examination QUESTION 79 79 Friday, October 12, 2012 Page 161 of 212

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1LT42 ONS SRO NRC Examination QUESTION 80 80L EPEO55 2.2.37 Loss of Offsite and Onsite Power (Station Blackout)

EPEO55 GENERIC Ability to determine operability andlor availability of safety related equipment. (CFR: 41.7 / 43.5 / 45.12)

Given the following Unit 1 conditions:

Time = 0400

Reactor power = 100%

TDEFDW pump OOS Time = 0445

Station blackout

Reactor trip

Control Rod Group 2 Rod 3 position = 90% withdrawn

AP/25 (SSF EOP) initiated Time = 0550

iTO, 1TD, and iTEde-energized

Standby Buses energized from CT-5

1) At 0550, the Blackout tab will direct using (1) to feed the SGs.

2) When feed to the SGs is established the Blackout tab will direct (2) .

Which ONE of the following completes the statements above?

A. 1. SSFASW

2. stabilizing CETCs 550°F B. 1. SSFASW

2. initiating a cool down to 450°F C. 1. Station ASW

2. stabilizing CETCs < 550°F D. 1. Station ASW

2. initiating a cool down to 450°F Friday, October 12, 2012 Page 162 of 212

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1LT42 ONS SRO NRC Examination QUESTION 80 General Discussion Answer A Discussion Correct. Although power is available to the station ASW pump, the SSF ASW pump will be used to feed the SG. The RCS will be stabilized at 550 degrees. A cooldown will not be performed.

Answer B Discussion Incorrect. First part is correct. Second part is plausible because it a cooldown plateau used in the SGTR tab.

Answer C Discussion Incorrect. First part is plausible because it does have power and would be used if the SSF-ASW pump were not available. Second part is correct.

Answer D Discussion Incorrect. First part is plausible because it does have power and would be used if the SSF-ASW pump were not available. Second part is plausible because it a cooldown plateau used in the SGTR tab.

Basis for meeting the KA Question requires knowledge of available equipment during a blackout and what will be used to stabilize the unit.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions Rev 1:

Detailed knowledge of the Blackout tab is required to answer this question. Must asses plant conditions and determine which source of feed will be used and decide whether to stabilize or cooldown the RCS.

This question requires the following:

Assessing plant conditions (normal, abnormal, or emergency) and then selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed Knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event specific sub procedures or emergency contingency procedures.

Can the question be answered solely by knowing systems knowledge, i.e., how the system works, flow path, logic, component location? NO Can the question be answered solely by knowing immediate operator actions? NO Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? NO Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? NO Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided EAP-BO R3 BO tab SGTR tab EPEO55 2.2.37 Loss of Offsite and Onsite Power (Station Blackout)

EPEO55 GENERIC Ability to determine operability and!or availability of safety related equipment. (CFR: 41.7 / 43.5 / 45.12) 401-9 Comments: Remarks/Status Friday, October 12, 2012 Page 163 of 212

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1LT42 ONS SRO NRC Examination QUESTION 81 L si BWE04 2.4.30 Inadequate Heat Transfer BWEO4 GENERIC Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10 / 43.5 / 45.11)

In accordance with the Site Emergency Plan, which ONE of the following would require notifying the State and Counties of plant status?

A. An RCSleakof4gpm B. SG tube leakage of 19 gpm C. An instrument failure results in ES Channels 1 2 actuation D. A loss of heat transfer requires feeding the SG with the SSF ASW pump Friday, October 12, 2012 Page 165 of 212

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1LT42 ONS SRO NRC Examination QUESTION 81 General Discussion Answer A Discussion Incorrect. Plausible because this would require a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months notification of the NRC per OMP 1-14 (Notifications) due to a TS required SD.

Answer B Discussion Incorrect. Plausible because this would require a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months notification of the NRC per OMP 1-14 (Notifications) due to a TS required SD.

Answer C Discussion Incorrect. Plausible because this would require a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months notification of the NRC per OMP 1-14 (Notifications) due to ECCS discharge intoi1 RCS.

Answer D Discussion Correct. Feeding the SGs with SSF ASW pump results in a Site Area Emergency Eplan classification. This will require notification of the State and Counties.

Basis for meeting the KA Question requires knowledge of when the Sate and Counties must be notified in accordance with plant procedures.

Basis for Hi Cog Basis for SRO only Question requires knowledge of implementing the Site Emergency Plan and Notification procedures (OMP 1-14). RP/0/B/l 000/002 (Control Room emergency Coordinator Procedure) requires notii,ing the State and Counties within 15 minutes of an Eplan declaration. Both are SRO tasks.

Job Level Cognitive Level QuestioriType Question Source SRO Memory NEW Development References Student References Provided OMP 1-14 RP 1000/001 RP 1000/002 BWE04 2.4.30 Inadequate Heat Transfer BWEO4 GENERIC Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10 /43.5 / 45.11) 401-9 Comments: Remarks/Status I___

Friday, October 12, 2012 Page 166 of 212

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1LT42 ONS SRO NRC Examination QUESTION 82 82 APEOO3 AA2.03 Dropped Control Rod Ability to determine and interpret the following as they apply to the Dropped Control Rod: (CFR: 43.5 / 45.13)

Dropped rod, using in-core/ex-core instrumentation, in-core or ioop temperature measurements Given the following Unit 1 conditions:

Initial Conditions:

Reactor power = 85% slowly increasing

Delta Tc in HAND Current conditions:

ICS runback in progress

Reactor power as indicated below Which ONE of the following describes:

1) the reason for the ICS runback?

2) a concern that would result from extended operation with skewed Power Range NI indications as described above?

A. 1. DroppedControl Rod

2. Brittle fracture of the reactor vessel wall could occur B. 1. DroppedControl Rod

2. Peak fuel cladding temperatures could be exceeded C. 1. RCP trip

2. Brittle fracture of the reactor vessel wall could occur D. 1. RCP trip

2. Peak fuel cladding temperatures could be exceeded Friday, October 12, 2012 Page 167 of 212

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1LT42 ONS SRO NRC Examination QUESTION 82 82j General Discussion Answer A Discussion Incorrect. First part is correct. Second part is plausible since the reactor vessel wall is affected by exposure to neutron flux. Since neutron embrittlement of the vessel wall is a concern and increased QPT results in increased exposure of the RV wall to neutron flux it is plausible to associate elevated QPT levels with concerns over neutron embrittiement of the RV wall and therefore concerns over Brittle Fracture of the RV.

Answer B Discussion Correct. A dropped control rod will result in depressed power production in the quadrant in which the rod has dropped and depending on the proximity of the rod to other quadrant, it can cause slightly misaligned power production in other quadrants as well. QPT is a common issue that will arise in a dropped rod situation. The COLR provides 3 levels of QPT limits. Although the lowest limit is named steady state limit, it applies at all times the spec is applicable (even if the unit is not at steady state).

Answer C Discussion Incorrect. First part is plausible for two reasons: I. There is an RC Flow Runback in ICS that would attempt to perform an ICS runback on loss of a RCP at power. Reactor power is low enough in this question so that there would not be a Rx trip on fluxlflow when the RCP was lost. With Delta TC in hand there would be no automatic re-ration of feedwater which adds to plausiblility of unbalanced Excore NI indications 2. Since there are 4 pumps (one in each cold leg) it is plausible to associate a RCP with a quadrant of the core and therefore believe that a RCP trip could result in skewed power production in each core due to the flow and temperatures being believed to be different in each quadrant. With Delta TC

i hand there would be no automatic re-ration of feedwater which adds to plausiblility of unbalanced Excore NI indications. Second part is plausible since the reactor vessel wall is affected by exposure to neutron flux. Since neutron embrittlement of the vessel wall is a concern and increased QPT results in increased exposure of the RV wall to neutron flux it is plausible to associate elevated QPT levels with concerns over neutron embrittlement of the RV wall and therefore concerns over Brittle Fracture of the RV.

Answer D Discussion

mnco1ct. First part is plausible for two reasons: 1. There is an RC Flow Runback in ICS that would attempt to perform an ICS runback on loss of a RCP at power. Reactor power is low enough in this question so that there would not be a Rx trip on flux/flow when the RCP was lost. With Delta TC in hand there would be no automatic re-ration.offeedwater which adds to plausiblility of unbalanced Excore NI indications 2. Since there are 4 pumps (one in each cold leg) it is plausible to associate a RCP with a quadrant of the core and therefore believe that a RCP trip could result in skewed power production in each core due to the flow and temperatures being believed to be different in each quadrant. With Delta TC in hand there would be no automatic re-ration of feedwater which adds to plausiblility of unbalanced Excore NI indications. Second part is correct.

Basis for meeting the KA Requires the ability to determine that a Control Rod has been dropped into the core based on excore power range NIs and requires an understanding of the implications of opening with a dropped rod that skews neutron flux and results in Quadrant Power Tilt issues.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions:

This question requires knowledge from the basis of TS 3.2.3 that is not systems knowledge.

It cannot be answered by knowing 1 hr or less TS/TRM Action It cannot be answered solely with above the line information.

It cannot be answered solely by knowing Safety Limits Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK ONS NRC TLT4O #83 Development References Student References Provided ADM-TSS R5 ONS NRC ILT4O #83 APEOO3 AA2.03 Dropped Control Rod Ability to determine and interpret the following as they apply to the Dropped Control Rod: (CFR: 43.5 / 4513)

Dropped rod, using in-core/ex-core instrumentation, in-core or loop temperature measurements 401-9 Comments: Remarks/Status Friday, October 12, 2012 Page 168 of 212

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1LT42 ONS SRO NRC Examination QUESTION 83 83j APEO69 2.4.41 Loss of Containment Integrity APEO69 GENERIC Knowledge of the emergency action level thresholds and classifications. (CFR: 41.10 / 43.5 / 45.11)

Given the following Unit 1 conditions:

Time = 0400

Reactor power = 70% decreasing

Unit shut down in progress due to a 140 gpm RCS leak Time = 0420

Core SCM 0°F

RCS temperature = 550°F decreasing

Reactor building pressure = 6 psig increasing

1RIA-58 l5RIhr increasing Time = 0445

Reactor building pressure = 18 psig increasing

Tremor felt in the control room

Seismic trigger actuates Time = 0450

Reactor building pressure 4 psig decreasing

1 RIA-58 = 55RIhr decreasing

Little River Dam has failed

1) The Emergency Classification at 0420 is (1)

2) The Emergency Classification at 0450 is (2)

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A. 1. Alert

2. Site Area Emergency B. 1. Alert

2. General Emergency C. 1. Site Area Emergency

2. Site Area Emergency D. 1. Site Area Emergency

2. General Emergency Friday, October 12, 2012 Page 170 of 212

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- DO NOT DISTRIBUTE 1LT42 ONS SRO NRC Examination QUESTION 83 831 General Discussion Answer A Discussion Incorrect. First part is correct. Second part is plausible because it would be correct if the unexplained decrease in RB pressure were not accounted for in the Fission Product Barrier Matrix.

Answer B Discussion Correct. Loss of SCM gives 5 points on the matrix. This is an Alert. At 0450 LOSCM 5 points, RIA-58 reading at 50 minutes is 5 points, and unexplained_RB_pressure decrease 3 points. 13 total points which is a General_Emergency.

Answer C Discussion Incorrect. First part is plausible because if the candidate had the misconception that they should add the 4 points for the RCS leak rate. 160 gpm (4 points) and LOSCM (5 points) this would be 9 points and a SAE. Second part is plausible because the failure of the Little River Dam is a SAE.

Answer D Discussion Incorrect. First part is plausible because if the candidate had the misconception that they should add the 4 points for the RCS leak rate. 160 gpm (4 points) and LOSCM (5 points) this would be 9 points and a SAE. Second part is correct.

Basis for meeting the KA Question requires knowledge of how a loss on containment will affect an emergency classification.

Basis for Hi Cog Basis for SRO only Emergency Clssification is an SRO only task.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided RP/loooIool RP/1000/OO1 End. 4.1 - 4.9 APEO69 2.4.41 Loss of Containment Integrity APEO69 GENERIC Knowledge of the emergency action level thresholds and classifications. (CFR: 41.10 / 43.5 / 45.11) 401-9 Comments: Remarks/Status Friday, October 12, 2012 Page 171 of 212

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1LT42 ONS SRO NRC Examination QUESTION 84 84 BWEO3 2.1.32 Inadequate Subcooling Margin BWEO3 GENERIC Ability to explain and apply system limits and precautions. (CFR: 41.10 / 43.2 / 45.12)

Given the following Unit I conditions:

Initial conditions:

Time= 0400

Reactor power = 100%

1BHPIOOS Current conditions:

TimeO4lO

ES Channels 1 8 actuated

CoreSCM=0°F

EOP Enclosure 5.1 (ES Actuation) in progress

Seal Inlet HDR Flow = 25 gpm

HPI Flow Train A flow = 456 gpm

HPI Flow Train B flow = 482 gpm

LPI FlowTrainAflow= 1820 gpm

LPI Flow Train B flow = 1730 gpm

1) (1) exceeding the HPI pumps flow limits in accordance with Rule 6 (HPI Pump Throttling Limits).

2) If the HPI pump(s) exceeding the flow limit is/are secured, the ECCS equipment required to mitigate this event in accordance with the Safety Analysis (2) be operating.

Which ONE of the following completes the statements above?

A. 1. BOTH HPI headers are

2. will B. 1. BOTH HPI headers are

2. will NOT C. 1. ONLY the lB HPI header is

2. will D. 1. ONLY the lB HPI header is

2. will NOT Friday, October 12, 2012 Page 172 of 212

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1LT42 ONS SRO NRC Examination QUESTION 84 8 General Discussion Answer A Discussion Correct. Both headers have only one HPI pump operating and both are exceeding 475 gpm. The A header must include Seal Inlet Flow. Both HPI pumps will be secured. However no HPI pumps are credited for a Large Break LOCA.. Since both LPI header flow together exceeds 3400 gpm, this would be a LBLOCA.

Answer B Discussion Incorrect. First part is correct. Second part is plausible because if not a LBLOCA this would be correct.

Answer C Discussion Incorrect. First part is plausible because if Seal Inlet Flow not added in to the A header this would be correct. Second part is correct.

Answer D Discussion Incorrect. First part is plausible because if Seal Inlet Flow not added in to the A header this would be correct. Second part is plausible because if not a LBLOCA this would be correct.

Basis for meeting the KA This question requires knowledge about HPI system limits and how to apply them during a LOSCM.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions Rev 1:

This question requires knowledge of TS 3.5.2 bases.

Can question be answered solely by knowing. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months TS/TRM Action? NO Can question be answered solely by knowing the LCO/TRM information listed above-the-line? NO Can question be answered solely by knowing the TS Safety Limits? NO Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided ADM-TSS EOP Rule 2 and 6 TS B3.5.2 BWEO3 2.1.32 Inadequate Subcooling Margin BWEO3 GENERIC Ability to explain and apply system limits and precautions. (CFR: 41.10 / 43.2 / 45.12) 401-9 Comments: RemarkslStatus Friday, October 12, 2012 Page 173 of 212

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1LT42 ONS SRO NRC Examination QUESTION 85 85]

BWE14 EA2.l - FOP Enclosures Ability to determine and interpret the following as they apply to the (EOP Enclosures)

(CFR; 43.5 /45.13)

Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Given the following Unit 1 conditions:

Time = 0400

Reactor has been tripped due to SGTR in the 1A SG Time = 0500

1A SG level = 293 inches XSUR increasing Time = 0530

1A SG reaches the Water in Steam Line Level In accordance with the SGTR tab:

1) At 0500, EOP Enclosure 5.22 (SG Blowdown) (1) be used to reduce 1A SG level.

2) At 0530, stop steaming (2)

Which ONE of the following completes the statements above?

A. 1. will NOT

2. BOTH SGs and initiate HPI Forced Cooling B. 1. will NOT

2. the affected SG and continue to steam the unaffected SG C. 1.will

2. BOTH SGs and initiate HPI Forced Cooling D. 1. will

2. the affected SG and continue to steam the unaffected SG Friday, October 12, 2012 Page 174 of 212

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1LT42 ONS SRO NRC Examination QUESTION 85 General Discussion L

Answer A Discussion Incorrect. First part is plausible because the candidate may have the misconception that blow down does not occur until Water in the Steam Line level is reached. Second part is plausible because it would be correct if both SG were at the Water in Steam Line Level.

Answer B Discussion Incorrect. First part is plausible because the candidate may have the misconception that blow down does not occur until Water in the Steam Line level is reached. Second part is correct.

Answer C Discussion Incorrect. First part is correct. Second part is plausible because it would be correct if both SG were at the Water in Steam Line Level.

Answer D Discussion Correct. Per the SGTR tab when level exceeds 285 inches then level will be reduced by using SG Blowdown. The SG with Water In Steam Line Level will not be steamed and the other SG will be.

Basis for meeting the KA Question requires knowledge of the EOP and when a specific enclosure would be perfonned.

Basis for Hi Cog Basis for SRO only In Accordance with Clarification Guidance for SRO-only Questions Rev Question requires Assessing plant conditions (normal, abnormal, or emergency) and then selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed. In this must determine when an EOP enclosure (End. 5.22) must be performed and what action to

,take when water reaches a certain level. This is detailed procedure knowledge.

Can the question be answered solely by knowing systems knowledge, i.e., how the system works, flowpath, logic, component location? NO Can the question be answered solely by knowing immediate operator actions? NO Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? NO Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? NO Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided

,EAP=SGTR SGTR tab BWE14 EA2.1 EOP Enclosures Ability to determine and interpret the following as they apply to the (EOP Enclosures)

(CFR: 43.5 / 45.13)

Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

401-9 Comments: arksIStatus Friday, October 12, 2012 Page 175 of 212

FOR REVIEW ONLY DO NOT DISTRIBUTE 1LT42 ONS SRO NRC Examination QUESTION 85 Friday, October 12, 2012 Page 176 of 212

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1LT42 ONS SRO NRC Examination QUESTION 86 SYSOO4 A2.lO Chemical and Volume Control System Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/ 43/5 / 45/3 / 45/5)

Inadvertent boration/dilution Given the following Unit 1 conditions:

Initial conditions:

Reactor power 85%

Control rod group 7 = 93% withdrawn

Makeup to LDST in progress Current conditions:

Reactor power 85%

Control rod group 7 = 30% withdrawn

1) In accordance with the bases of TS 3.2.1 (Regulating Rod Position Limits) continued operation in the current plant configuration is NOT allowed because (1)

2) Restoring rods to within the acceptable region by (2) will satisfy the requirements of TS 3.2.1.

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A. 1. SDM is not adequate and ejected rod worth is too high

2. boration ONLY B. 1. SDM is not adequate and ejected rod worth is too high

2. boration OR reducing reactor power C. 1. this configuration is in violation of the assumptions made in the safety analysis

2. boration ONLY D. 1. this configuration is in violation of the assumptions made in the safety analysis

2. boration OR reducing reactor power Friday, October 12, 2012 Page 177 of 212

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1LT42 ONS SRO NRC Examination QUESTION 86 General Discussion Answer A Discussion Incorrect. First part is plausible because it would be correct if it were in the unacceptable region of the curve. Second part is plausible and if in the unacceptable region boration would be required within 1 5 minutes to restore SDM.

Answer B Discussion incorrect. First part is plausible because it would be correct if it were in the unacceptable region of the curve. Second part is correct.

Answer C Discussion Incorrect. First part is correct. Second part is plausible and if in the unacceptable region boration would be required within 15 minutes to restore SDM.

Answer 0 Discussion Correct. In accordance with the basis of TS 3.2.1 operation in the restricted region is a violation of the assumptions made in the safety analysis.

Borating or reducing power will satisfy TS3.2. I.

Basis for meeting the KA Question requires knowledge of the results of a deboration and the TS required actions to correct.

Basis for Hi Cog L_________

Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions Rev I:

Question requires Knowledge of TS bases that are required to analyze TS required actions and terminology. TS Basis 3.2.1.

Can question be answered solely by knowing 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months TS/TRM Action? NO Can question be answered solely by knowing the LCO/TRM information listed above-the-line? NO Can question be answered solely by knowing the TS Safety Limits? NO Job Level Cognitive Level QuestionType Question Source -__________

SRO Comprehension NEW Development References Student References Provided ADM-TSS TS 3.2.1 TS 3.2.1 Unit 1 COLR IS B3.2.1 Unit I COLR SYSOO4 A2. 10 Chemical and Volume Control System Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 4 1.5/ 43/5 / 45/3/45/5)

Inadvertent boration/dilution 401-9 Comments: .emarks/Status Friday, October 12, 2012 Page 178 of 212

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1LT42 ONS SRO NRC Examination QUESTION 87 87 SYSOO6 2.4.47 Emergency Core Cooling System (ECCS)

SYSOO6 GENERIC Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. (CFR: 41.10

/43.5 /45.12)

Given the following Unit 1 conditions:

BWST Level 0) 0)

-J 1200 1300 1400 1500 Time

1) In accordance with PTIIIAJO600IOO1 (Periodic Instrument Surveillance) and referring to the chart of control room indicated BWST level above, the latest time that the BWST surveillance is satisfied is (1)

2) A bases for the minimum BWST level in accordance with the basis of TS 3.5.4 isto (2)

Which ONE of the following completes the statements above?

A. 1. 1300

2. ensure adequate NPSH for the LPI and RBS pumps after suction is swapped to the RBES B. 1. 1300

2. reduce post fuel handling accident dose released by providing proper refueling canal level C. 1. 1400

2. ensure adequate NPSH for the LPI and RBS pumps after suction is swapped to the RBES D. 1. 1400

2. reduce post fuel handling accident dose released by providing proper refueling canal level Friday, October 12, 2012 Page 179 of 212

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8 1LT42 ONS SRO NRC Examination QUESTION 87 General Discussion Answer A Discussion Correct. Per PT/600/OOl the BWST level limit is 47 feet. This is the error corrected value. The TS value is 46 feet.

Per the basis of TS 3.5.4: A second factor that affects the minimum required BWST volume is the ability to support continued LPI pump operation after the manual transfer to recirculation occurs. When LPI pump suction is transferred to the sump, there must be sufficient water in the sump to ensure adequate net positive suction head (NPSH) for the LPI and reactor building spray pumps.

Answer B Discussion Incorrect. First part is correct. Second part is plausible because the TS bases discuss the maximum BWST level ensures adequate volume for refueling and the bases for the refueling canal level is to reduce post fuel handling accident dose.

Answer C Discussion Incorrect. First part is plasuible because it is the TS non instument corrected value. Second part is correct.

Answer D Discussion Incorrect. First part is plasuible because it is the TS non instument corrected value. Second part is plausible because the TS bases discuss the maximum BWST level ensures adequate volume for refueling and the bases for the refueling canal level is to reduce post fuel handling accident dose.

Basis for meeting the KA Question requires ability to monitor a control room trend and determine that TS requirements are not met.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions Rev 1:

Question requires Knowledge of TS bases that are required to analyze TS required actions and terminology. TS Basis 3.5.2.

Can question be answered solely by knowing 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months TS/TRM Action? NO Can question be answered solely by knowing the LCO/TRM information listed above-the-line? NO Can question be answered solely by knowing the TS Safety Limits? NO Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided PT/600100 I TS B3.5.4 SYSOO6 2.4.47 Emergency Core Cooling System (ECCS)

SYSOO6 GENERIC Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. (CFR: 41.10

/43.5 / 45.12) 401-9 Comments: RemarkslStatus Friday, October 12, 2012 Page 180 of 212

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1LT42 ONS SRO NRC Examination QUESTION 88 88]

SYSO61 A2.07 Auxiliary I Emergency Feedwater (AFW) System 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 malfi.inctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.13)

Air or MOV failure Given the following Unit 1 conditions:

Reactor power 100%

1FDW-368 is discovered closed and will NOT open

1) In accordance with TS 3.7.5 (Emergency Feedwater) basis the (1) is inoperable.

2) If NOT repaired, the MAXIMUM time allowed to be in MODE 3 is (2) hours Which ONE of the following completes the statements above?

REFERENCE PROVIDED A. 1. TDEFDW pump

2. 84 B. 1. TDEFDW pump

2. 252 C. 1. associated EFW flow path

2. 84 D. 1. associated EFW flow path

2. 252 Friday, October 12, 2012 Page 181 of 212

FOR REVIEW ONLY - DO NOT DISTRIBUTE 1LT42 ONS SRO NRC Examination QUESTION 88 88 General Discussion Answer A Discussion Correct:. Per the DBD ifFDW-368 or 369 is closed the TDEFDW pump is inoperable. Condition B completeion time is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Conditions D give an additional 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to be in MODE 3. Total time is 84 houirs.

Answer B Discussion Incorrect:. First part correct. Second part plausible if you misapply the 10 days from failure to met the LCO in Condition B. 10 days plus 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be a total of 252 hours0.00292 days 0.07 hours 4.166667e-4 weeks 9.5886e-5 months .

Answer C Discussion Incorrect. First part is plausible because the candidate could have the misconception that a valve in the flow path would make the flow path inoperable. Second part is correct.

Answer D Discussion Incorrect. First part is plausible because the candidate could have the misconception that a valve in the flow path would make the flow path inoperable. Second part plausible if you misapply the 10 days from failure to met the LCO in Condition B. 10 days plus 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be a total of 252 hours0.00292 days 0.07 hours 4.166667e-4 weeks 9.5886e-5 months .

Basis for meeting the KA This question requires knowledge of how a valve failure would affect the EFW system and the TS consequences.

Basis for Hi Cog Basis for SRO only Question requires knowledge of the DBD to determine EFDW pump operability and application of TS. Both of which is SRO knowledge.

1 Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided ADM-TSS R5 TS 3.7.5 TS 3.7.5 TS 3.7.5 Bases SYSO61 A2,07 Auxiliary / Emergency Feedwater (AFW) System 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: (CFR: 41.5 /43.5/45.3 /45.13)

Air or MOV failure 401-9 Comments: Remarks/Status Friday, October 12, 2012 Page 182 of 212

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1LT42 ONS SRO NRC Examination QUESTION 89 SYSO63 2.2.25 DC ElectricaL Distribution System SYSO63 GENERIC Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 / 41.7 / 43.2)

Which ONE of the following sets of 125 VDC Vital l&C power panelboards are required for Unit 2 in accordance with TS 3.8.8 (Distribution Systems Operating) and why?

A. 1DIAand1DIB They provide power to SK and SL breakers B. 1DIAand1DIB They provide power to the Switchyard Isolation circuitry C. 1DICand1DID They provide power to SK and SL breakers D. 1D1Cand1D1D They provide power to the Switchyard Isolation circuitry Friday, October 12, 2012 Page 183 of 212

FOR REVIEW ONLY - DO NOT DISTRIBUTE 1LT42 ONS SRO NRC Examination QUESTION 89 89j General Discussion Answer A Discussion Incorrect: First part is plausible since Condition F is entered if either KVIC or KVID is inoperable and has a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months completion time for either panelboard therefore it would be plausible to determine that 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to restore one of the panelboards would be allowed. Additional plausibility is from having to determine that the loss of the 3DIC panelboard would cause 3KVIC to de-energize. If this is not recognized then this is the correct choice. Second part is correct.

Answer B Discussion Incorrect: : First part is plausible as described in A. Second part is plausible since SK and SL breakers protective relaying is signaled out in the electrical specs as unique. It is unique because unit ls DIC and DID panelboards provide power to these breakers that all 3 units rely on. The fact that the power for SK and SL breakers comes from a units power panelboards and is signaled out as unique in the electrical specs combine to make this a plausible distractor since Condition F is itself unique for other reasons. Additionally, the breakers are getting power from the c and d strings of panelboards however it is from the DC panelboards instead of the AC panelboards.

Answer C Discussion CORRECT: When 3DIC is de-energized then 3KVIC would also de-energize. With both 3KVIC and 3KVID de-energized there is no TS Condition in TS 3.8.8 that allows for multiple Vital Instrumentation power panelboards to be inoperable therefore immediate entry into LCO 3.0.3 would be required. TS 3.8.8 Condition F allows 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to restore KVIA and KVIB and then allows 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to restore KVIC and KVID.

The difference is due to the fact that KVIA and KVIB provide power to the odd and even ES digital channels respectively therefore a loss of either panelboard would render all of the Odd or Even digital channels unable to trip since they fail in the untripped state when de-energized.

Answer D Discussion Incorrect: First part is correct. Second part is plausible as described in B.

Basis for meeting the KA K/A MATCH ANALYSIS Requires tracking previously entered TS LCOs and then correctly applying that to a subsequent inoperability to determine the correct actions required by Tech Specs.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions Rev 1:

Question requires Knowledge of TS bases that are required to analyze TS required actions and terminology. TS Basis 3.8.8 Can question be answered solely by knowing 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months TS/TRM Action? NO Can question be answered solely by knowing the LCO/TRM information listed above-the-line? NO Can question be answered solely by knowing the TS Safety Limits? NO Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Development References Student References Provided EL-DCD TS 3.8.8 and bases SYSO63 2.2.25 DC Electrical Distribution System 5Y5063 GENERIC Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 / 41.7 / 43.2) 401-9 Comments: arks/Status Friday, October 12, 2012 Page 184 of 212

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1LT42 ONS SRO NRC Examination QUESTION 90 90 SYSO78 2.4.18 Instrument Air System (lAS)

SYSO78 GENERIC Knowledge ofthe specific bases for FOPs. (CFR: 41.10 / 43.1 / 45.13)

Given the following Unit 2 conditions:

Reactor power = 100%

1) The IA pressure setpoint which will cause the Diesel Air Compressors to automatically start is (1) psig.

2) The bases for 2AP122 (Loss of IA) ensuring that the Diesel Air Compressors are operating if IA header pressure decreases below the setpoint is to (2)

Which ONE of the following completes the statements above?

A. 1.88

2. ensure operability of 2FDW-315/316 during a subsequent blackout B. 1.88

2. prevent exceeding RB design pressure during a subsequent MSLB/LOOP C. 1.90

2. ensure operability of 2FDW-315/316 during a subsequent blackout D. 1.90

2. prevent exceeding RB design pressure during a subsequent MSLB/LOOP Friday, October 12, 2012 Page 186 of 212

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1LT42 ONS SRO NRC Examination QUESTION 90 General Discussion Answer A Discussion Incorrect. First part plausible because 88 psig is the setpoint for the AlA compressor. Second part is plausible because the Diesel Air Compressors could provide air to FDW-3 15/316. However this is not the reason that they are started on low IA header pressure.

Answer B Discussion Incorrect. First part plausible because 88 psig is the setpoint for the AlA compressor. Second part is correct..

Answer C Discussion Incorrect. First part is correct. Second part is plausible because the Diesel Air Compressors could provide air to FDW-3l5/316. However this is not the reason that they are started on low IA header pressure.

Answer D Discussion Correct. The Diesel Air Compressors will start at 90 psig IA header pressure. The reason they are started is to prevent exceeding RB design pressure during a subsequent MSLB/LOOP. This is done by ensuring the the FDW valves have enough air pressure to close because they fail as-is on loss of IA.

Basis for meeting the KA We have no quidance to IA in our EOP. It is in the AP. This question requires knowledge of bases for actions contained in the Loss of IA AP.

Basis for Hi Cog Basis for SRO only This question requires knowledge of the bases for steps in an AP. This is SRO knowledge. The question cannot be answered using system knowledge alone.

Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Development References Student References Provided 555-IA R27

2Ap/22 I_____________________________________________

SYSO78 2.4.18 Instrument Air System (lAS) 5Y5078 GENERIC Knowledge of the specific bases for EOPs. (CFR: 41.10 / 43.1 / 45.13) 401-9 Comments: RemarkslStatus Friday, October 12, 2012 Page 187 of 212

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1LT42 ONS SRO NRC Examination QUESTION 91 SYSO 16 2.2.36 Non-Nuclear Instmmentation System (NNIS)

SYSO16 GENERIC Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations. (CFR:

41.10/43.2/45.13)

Given the following Unit 1 conditions:

Initial conditions:

Unit is returning to power after a short maintenance outage

Main Turbine has just been placed on-line

Reactor power = 25% increasing

1A LPI Train piping insulation removal for weld inspection in progress Current conditions:

Power to the IA LPI Train Flow gage disconnected Which ONE of the following states:

1) the equipment that must be declared inoperable in accordance with the basis of Tech Specs 3.5.3 (LPI) and 3.6.5 (RB Spray and Cooling Systems)?

2) if Unit 1 can continue with the power escalation to 100% in accordance with Tech Specs?

A. 1. 1ALPITrainONLY

2. can continue B. 1. 1ALPITrainAND1ARBSTrain

2. can continue C. 1. 1ALPITrainONLY

2. can NOT continue D. 1. 1ALPITrainAND1ARBSTrain

2. can NOT continue Friday, October 12, 2012 Page 188 of 212

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1LT42 ONS SRO NRC Examination QUESTION 91 9l General Discussion Answer A Discussion Incorrect. First part is plausible because the instrument is on the LPI train. Second part is correct.

Answer B Discussion Correct. In accordance with the basis of TS 3.5.3 the LPI header flow instrument is required for both the LPI and the RBS trains. Power increase can continue because there is not a MODE change.

Answer C Discussion Incorrect. First part is plausible because the instrument is on the LPI train. Second part is plausible because the candidate may have the misconception that LCO 3.0.4 applies. Because a MODE change would not be allowed.

Answer D Discussion Incorrect. First part is correct. Second part is plausible because the candidate may have the misconception that LCO 3.0.4 applies. Becaus]

MODE change would not be allowed.

Basis for meeting the KA Question requires knowledge of how loss of power to an NN1 (LPI Train Flow Gauge) would affect limiting conditions for operations.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions Rev I:

Question requires Knowledge of TS bases that are required to analyze TS required actions and terminology. TS Basis 3.5.3 and 3.6.5.

Can question be answered solely by knowing S 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months TS/TRM Action? NO Can question be answered solely by knowing the LCO1TRIvI information listed above-the-line? NO Can question be answered solely by knowing the TS Safety Limits? NO Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided ADM-TSS TS 3.5.3 TS B3.5.3 TS 3.6.5 TS B3.6.5 SYSO16 2.2.36 Non-Nuclear Instrumentation System (NNIS)

SYSO16 GENERIC Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations. (CFR:

41.10/43.2/45.13) 401-9 Comments: Remarks/Status Friday, October 12, 2012 Page 189 of 212

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1LT42 ONS SRO NRC Examination QUESTION 92 92j SYSO 17 A2.02 In-Core Temperature Monitor (ITM) System Ability to (a) predict the impacts of the following malfunctions or operations on the ITM system; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 /43.5 / 45.3 / 45.5)

Core damage Given the following Unit 1 conditions:

Initial conditions:

Time = 0400

ICCtabinprogress

CETC5 = 650°F increasing Current conditions:

Time=1100

CETCs = 1250°F stable

1) At 0400, with TSC approval, the ICC tab (1) direct starting RCPs.

2) At 1100, the (2) will provide mitigation guidance.

Which ONE of the following completes the statements above?

A. 1.will

2. OSAG ONLY B. 1. will

2. OSAGandthelCCtab C. 1. will NOT

2. OSAG ONLY D. 1. will NOT

2. OSAG and the ICC tab Friday, October 12, 2012 Page 190 of 212

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1LT42 ONS SRO NRC Examination QUESTION 92 General Discusson Answer A Discussion Incorrect. First part is plasuible because it would be correct if CETCs were between 700 and 1200 degrees. Second part is correct.

Answer B Discussion Incorrect. First part is plausible because it would be correct if CETCs were between 700 and 1200 degrees. Second part is plausible because the candidate could have the misconception that the EOP and the OSAG were performed at the same time.

Answer C Discussion Correct. The ICC tab will not direct starting a RCP until CETCs read > 700 degrees. The ICC tab directs going to the OSAG when CETCs reach 1200 degrees.

Answer D Discussion Incorrect. First part is correct. Second part is plausible because the candidate could have the misconception that the EOP and the OSAG were performed at the same time.

Basis for meeting the KA Question requires how CETC indication affect the mitigation strategy.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions Rev 1 Question requires evaluating plant data and determining which procedure will be used to mitigate this event. OSAG and/or ICC tab. Also detailed information of the ICC tab on when a RCP will be started.

This question requires the following:

Assessing plant conditions (normal, abnormal, or emergency) and then selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed.

Knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event specific sub procedures or emergency contingency procedures.

Can the question be answered solely by knowing systems knowledge. i.e., how the system works, flow path, logic, component location? NO Can the question be answered solely by knowing immediate operator actions? NO Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? NO Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? NO Job Level Cognitive Level QuestionTyp Question Source SRO Comprehension NEW Development References Student References Provided EAP-ICC R7 ICC tab SYSO17 A2.02 In-Core Temperature Monitor (ITM) System Ability to (a) predict the impacts of the following malfunctions or operations on the ITM system; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.5)

Core damage 401-9 Comments: RemarkslStatus Friday, October 12, 2012 Page 191 of 212

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Friday, October 12, 2012 Page 192 of 212

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1LT42 ONS SRO NRC Examination QUESTION 93 93 SYSO33 2.4.46 Spent Fuel Pool Cooling System (SFPCS)

SYS033 GENERIC Ability to verify that the alarms are consistent with the plant conditions. (CFR: 41.10 / 43.5 / 45.3 / 45.12)

Given the following Unit 1 conditions:

SFP level (-) 0.7 feet stable

1SA-9/A-5 (Spent Fuel Pool Level High/Low) actuated

ALL SF Cooling Pumps have tripped OFF

ALL SF Cooling Pump switches green lights are illuminated

1) The LOW SFP Level interlock (1) functioned as designed.

2) AP/35 (Loss of SEP Cooling and/or Level) will require (2)

Which ONE of the following completes the statements above?

A. 1. has

2. making up to the SEP using DW B. 1. has

2. making up to the SEP using 1A BHUT C. 1. has NOT

2. aligning SEP ventilation D. 1. has NOT

2. bypassing the SEP Low Level Interlock Friday, October 12, 2012 Page 193 of 212

FOR REVIEW ONLY - DO NOT DISTRIBUTE 1LT42 ONS SRO NRC Examination QUESTION 93 93 General Discussion Answer A Discussion Incorrect. First part plausible because the SFP high level setpoint is +0.7 feet. Also level is low but theywill not trip until -2.5 feet. Second part is plausible because DW can be used to makeup to the SFP.

Answer B Discussion Incorrect. First part plausible because the SFP high level setpoint is +0.7 feet. Also level is low but theywill not trip until -2.5 feet. Second part is plausible because lA BHUT can be used to makeup to the SFP.

Answer C Discussion Incorrect. First part is correct. Second part is plausible because per AP/35 if SFP temp is expected to reach 180 degrees then SFP ventilation is aligned by the TSC.

Answer D Discussion Correct. 1SA-9/A-5 should not be in alarm on low level and the SF pumps should not have tripped off. The SF pumps will trip at -2.5 feet in the FP. AP/35 will direct bypassing the interlock and restarting a SF Cooling Pump.

Basis for meeting the KA Question requires knowledge of the SFP level alarm and the low level interlock with the SFP cooling pumps.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions Rev 1:

Question requires detailed knowledge of AP/35 that is not entry conditions or major mitigation strategy.

This question requires the following:

Assessing plant conditions (normal, abnormal, or emergency) and then selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed Knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event specific sub procedures or emergency contingency procedures.

Can the question be answered solely by knowing systems knowledge, i.e., how the system works, flow path, logic, component location? NO Can the question be answered solely by knowing immediate operator actions? NO Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? NO Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? NO Job Level Cognitive Level QuestionType Question Source j

SRO Comprehension NEW Development References Student References Provided I SA-9/A-5 AP/35 SYSO33 2.4.46 Spent Fuel Pool Cooling System (SFPCS) 5Y5033 GENERIC Ability to verify that the alarms are consistent with the plant conditions. (CFR: 41.10 / 43.5 / 45.3 / 45.12) 401-9 Comments: RemarkslStatus Friday, October 12, 2012 Page 194 of 212

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1LT42 ONS SRO NRC Examination QUESTION 94 94J GEN2.1 2.1.20 GENERIC Conduct of Operations Conduct of Operations Ability to interpret and execute procedure steps. (CFR: 41.10 / 43.5 / 45.12)

Given the following Unit 1 conditions:

Initial conditions:

Time= 0400

LOCA CD tab in progress

ALL SCM 5°F stable

RCS pressure = 870 slowly decreasing

RB pressure peaked at 2.4 psig and is now decreasing

HPI aligned for piggyback operation

LPI suction source is the RBES

1LP-15 failed CLOSED Current conditions:

Time= 0405

RCS pressure = 855 psig stable

1SA-07/E-6 (ES LPI BYP PERMIT) actuates

1) At 0405, the LPI ES channels (1) allowed to be manually bypassed in accordance with the LOCA CD tab.

2) The MAXIMUM allowed HPI flow is (2) gpm.

Which ONE of the following completes the statements above?

A. 1. are

2. 750 B. 1. are NOT

2. 750 C. 1. are

2. 500 D. 1. are NOT

2. 500 Friday, October 12, 2012 Page 196 of 212

FOR REVIEW ONLY DO NOT DISTRIBUTE 1LT42 ONS SRO NRC Examination QUESTION 94 94 General Discussion Answer A Discussion Correct: LPI will be bypassed under these conditions. le SCM > zero. RCS pressure controllable. Permissive statalarm received. While aligning LPI in the piggyback mode per End 5.12 (also addressed in LOCA CD tab), if either LP-l5 or LP-l6 do not open then total LPI flow is limited to 750 gpm.

Answer B Discussion Incorrect. First part is plausible because the candidate may have the misconception that with SCM so low ES would not be bypassed. Second part is correct.

Answer C Discussion Incorrect: First part is correct. Second part is plausible since total HPI flow is required to be maintained> 500 gpm if 2 LPIPs operating to ensure mm flow requirements for the LPIPs are met. Additionally, the LOCA CD tab limits LPI flow to 500 gpm during certain conditions.

Answer D Discussion Incorrect: First part is plausible because the candidate may have the misconception that with SCM so low ES would not be bypassed. Second part is plausible since total HPI flow is required to be maintained> 500 gpm if 2 LPIPs operating to ensure mm flow requirements for the LPIPs are met. Additionally, the LOCA CD tab limits EN flow to 500 gpm during certain conditions.

Basis for meeting the KA This question requires knowledge of procedure steps in the LOCA CD tab and how to execute them. This includes the ability to interpret information provided in steps related to bypassing LPI ES channels.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions Rev 1:

This question requires the following:

Assessing plant conditions (normal, abnormal, or emergency) and then selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed.

Can the question be answered solely by knowing systems knowledge, i.e., how the system works, flow path, logic, component location? NO Can the question be answered solely by knowing immediate operator actions? NO Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? NO

Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? NO Job Level Cognitive Level QuestionType Question Source SRO Comprehension MODIFIED ONS 2009A Q83 Development References Student References Provided EOP LOCA CD tab, End 5.12 JONS NRC 2009A Q83 GEN2.1 2.1.20 GENERIC Conduct of Operations Conduct of Operations Ability to interpret and execute procedure steps. (CFR: 41.10 / 43.5 / 45.12) 401-9 Comments: RemarkslStatus Friday, October 12, 2012 Page 197 of 212

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1LT42 ONS SRO NRC Examination QUESTION 95 9 GEN2.2 2.2.11 GENERIC Equipment Control Equipment Control Knowledge of the process for controlling temporary design changes. (CFR: 41.10 / 43.3 / 45.13)

In accordance with NSD 301 (Engineering Change Program):

1) A temporary design change is required to have a plan for removal no longer than (1) from installation.

2) The Operational Control Group (Operations) is responsible for (2)

Which ONE of the following completes the statements above?

A. 1. thirty days

2. maintaining a log of installed changes B. 1. thirtydays

2. insuring blue tags are hung on the affected equipment C. 1. oneyear

2. maintaining a log of installed changes D. 1. one year

2. insuring blue tags are hung on the affected equipment Friday, October 12, 2012 Page 199 of 212

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1LT42 ONS SRO NRC Examination QUESTION 95 95 General Discussion Answer A Discussion Incorrect. First part is plausible because 30 days is an often used surveillance time. Second part is correct.

Answer B Discussion Incorrect. First part is plausible because 30 days is an often used surveillance time. Second part is plausible because blue tags are hung on OPS Test Group electrical items that are out of their normal positions. Such as leads, links, etc.

Answer C Discussion Correct. Per NSD-301 a plan for removal within one year must be in place before temporary design change will be installed. The operational control group (OPS in this case) is required to maintain a log of installed changes.

Answer D Discussion Incorrect. First part is correct. Second part is plausible because blue tags are hung on OPS Test Group electrical items that are out of their normal positions. Such as leads, links, etc.

Basis for meeting the KA The question requirs knowledge of the process for controlling Temporary Design Changes.

Basis for Hi Cog Basis for SRO only Per the Clarification Guidance for SRO-only Questions Rev. 1:

Facility licensee procedures required to obtain authority for design and operating changes in the facility. [10 CFR 55.43(b)(3)]

Some examples of SRO exam items for this topic include:

Administrative processes for temporary modifications.

Also Oconee has SRO only objectives for this owledge.

Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Development References Student References Provided ADM-SD R20, R21 NSD-301 GEN2.2 2.2.11 GENERIC Equipment Control Equipment Control Knowledge of the process for controlling temporary design changes. (CFR: 41.10 / 43.3 / 45.13) 401-9 Comments: RemarkslStatus Friday, October 12, 2012 Page 200 of 212

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1LT42 ONS SRO NRC Examination QUESTION 96 96]

GEN2.2 2.2.23 - GENERIC Equipment Control Equipment Control Ability to track Technical Specification limiting conditions for operations. (CFR: 41.10 / 43.2 / 45.13)

Given the following conditions on Unit 1:

Reactor Power 100%

1A MDEFWP was declared inoperable at 13:00 on 05/01

lB MDEFWP was declared inoperable at 14:00 on 05/06

1A MDEFWP was returned to service at 01:00 on 05/07 Which ONE of the following describes when the 1 B MDEFWP is required to be returned to service?

REFERENCE PROVIDED A. 13:00 on 05/08 B. 13:00 on 05/11 C. 14:00 on 05/13 D. 13:00 on 05/09 Friday, October 12, 2012 Page 201 of 212

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1LT42 ONS SRO NRC Examination QUESTION 96 96 General Discussion Answer A Discussion Incorrect, Plausible because this is 7 days from entering Condition A which has a completion time of 7 days.

Answer B Discussion Incorrect. Plausible because this is the 10 days from failure to meet LCO rule.

Answer C Discussion Incorrect. Plausible because this is 7 days for one pump in Condition A.

Answer D Discussion Correct. 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months extension rule (TS 1.3) applies to original 7 days.

Basis for meeting the KA Question requires the ability to track TS LCOs to ensure equipment returned to service as required by the TS rules.

Basis for Hi Cog Basis for SRO only In accordacne with Clarification Guidance for SRO-only Questions Rev 1:

The question requires application of Required Actions (Section 3) in accordance with rules of application requirements (Section 1). (TS 1.3 in this case)

Can question be answered solely by knowing 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months TS/TRM Action? NO Can question be answered solely by knowing the LCO/TRM information listed above-the-line? NO Can question be answered solely by knowing the TS Safety Limits? NO Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK ONS Bank CF022901 Development References Student References Provided ADM-ITS TS 3.7.5 TS 3.7.5 TS 1.3 ONS Bank CF022901 GEN2.2 2.2.23 GENERIC Equipment Control Equipment Control Ability to track Technical Specification limiting conditions for operations. (CFR: 41.10 /43.2 / 45.13) 401-9 Comments: RemarkslStatus Friday, October 12, 2012 Page 202 of 212

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1LT42 ONS SRO NRC Examination QUESTION 97 GEN2.3 2.3.11 GENERIC Radiation Control Radiation Control Ability to control radiation releases. (CFR: 41.11 / 43.4 /45.10)

Given the following plant conditions:

Time = 0400

Reactor power = 100%

1A GWD tank release in progress at 1/3 Station Limit Time = 0415

3B GWD tank release initiated at 1/3 Station Limit Time = 0430

Loss of power to RM-80 skid of 1 RIA-45 (Norm Vent Gas)

1SA8/B-9 RM PROCESS MONITOR RADIATION HIGH in alarm

ISA8/B-10 RM PROCESS MONITOR FAULT in alarm

1) In accordance with OP/i -2/NI 104/018 (GWD System) the release at 0415 is required to be approved by (1)

2) At 0430 and in accordance with the ARGs, an RO will (2)

Which ONE of the following completes the statements above?

A. 1. any SRO

2. manually close GWD-4 B. 1. anySRO

2. verify GWD-4 has automatically closed C. 1. onlytheOSM

2. manually close GWD-4 D. 1. onlytheOSM

2. verify GWD-4 has automatically closed Friday, October 12, 2012 Page 203 of 212

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1LT42 ONS SRO NRC Examination QUESTION 97 97 General Discussion Answer A Discussion Incorrect. First part is plausible because it would be correct if the release was at 1/3 limit and only one release was in progress. Second part is correct.

Answer B Discussion Incorrect. First part is plausible because it would be correct if the release was at 1/3 limit and only one release was in progress. Second part is plausible because 1GWD-4 would close on a loss of power to IRIA-37/38. -____________

Answer C Discussion Correct:. A release greater than 1/3 the station limit requires OSM approval. IRIA-45 does not automatically terminate GWD releases. It does monitor the release via the station vent stack the required action in the ARG and AP/1 8 is to stop releases in progress. This done by closing GWD-4.

Answer D Discussion Incorrect: First part is correct. Second part is plasuible because IGWD-4 would close on a loss of power to IRIA-37/38.

Basis for meeting the KA Question requires knowledge of the process for releasing a GWD gas tank and who has to approve the release.

Basis for Hi Cog Basis for SRO only Per Clarification Guidance for SRO-only Questions:

Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions.

Process for gaseous/liquid release approvals, i.e., release permits.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension MODIFIED ONS 2009 Q93 Development References Student References Provided OP/i 104/018 I 5A8/B-9, I 5A8/B-i 0 AP/18 ONS 2009 Q93 GEN2.3 2.3.11 GENERIC Radiation Control Radiation Control Ability to control radiation releases. (CFR: 41.1 1 / 43.4 / 45.10) 401-9 Comments: RemarkslStatus Friday, October 12, 2012 Page 204 of 212

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1LT42 ONS SRO NRC Examination QUESTION 98 GEN2.3 2.3.5 GENERIC Radiation Control Radiation Control Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR: 41.11 / 41.12 / 43.4 / 45.9)

Given the following Unit 1 conditions:

Initial conditions:

Time = 0400

Reactor power = 100%

1RIA-590.1 gpm

1RIA-60=35 gpm Current conditions:

Time = 0430

Reactor power = 38%

1AMSLB

1) At 0400, in accordance with the bases of TS 3.4.13, RCS Pressure Boundary LEAKAGE (1) occurring.

2) Without Station Management approval the (2) SG will be used to cooldown to LPI.

Which ONE of the following completes the statements above?

A. 1.is 2.1A B. 1.is

2. lB C. 1. is NOT 2.1A D. 1. is NOT

2. lB Friday, October 12, 2012 Page 205 of 212

FOR REVIEW ONLY - DO NOT DISTRIBUTE 1LT42 ONS SRO NRC Examination QUESTION 98 General Discussion Answer A Discussion Incorrect. First part is plausible because a SG tube is part of the RCS pressure boundary but is not considered as such in this TS. Second part is plausible because with Station management approval using the SO with the MSLB would be correct.

Answer B Discussion Incorrect. First part is plausible because a SO tube is part of the RCS pressure boundary but is not considered as such in this TS. Second part is correct.

Answer C Discussion Incorrect. First part is correct. Second part is plausible because with Station management approval using the SO with the MSLB would be correct.

Answer D Discussion Correct. In accordance with the bases of TS 3.4.13, SG tube leakage is not considered pressure boundary leakage. In accordance wit the SGTR the SO with the tube rupture will be used for the cooldown unless management Approval is given.

Basis for meeting the KA Question requires the use of radiation monitors to be used to determine how the plant will be cooled down during a SGTR and a MSLB.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions Rev I:

Must asses plant conditions including RIA readings to determine with SO will be used for the CD.

TS Basis knowledge is also required to answer the question.

This question requires the following:

Assessing plant conditions (normal, abnormal, or emergency) and then selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed.

Knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event specific sub procedures or emergency contingency procedures.

Can the question be answered solely by knowing systems knowledge, i.e., how the system works, flow path, logic, component location? NO Can the question be answered solely by knowing immediate operator actions? NO Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? NO Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? NO Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided EAO-SGTR R27 SGTR tab TS B3.4.l3 GEN2.3 2.3.5 GENERIC Radiation Control Radiation Control Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR: 41.11 / 41.12 / 43.4 / 45.9)

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1LT42 ONS SRO NRC Examination QUESTION 99 GEN2.4 2.4.26 GENERIC Emergency Procedures / Plan Emergency Procedures / Plan Knowledge of facility protection requirements, including fire brigade andportable fire fighting equipment usage. (CFR: 41.10 / 43.5 / 45.12)

Given the following Unit 1 conditions:

Initial conditions:

All 3 Units reactor power = 100%

1SA-3/B6 (FIRE ALARM) actuated rd 3

NEDs dispatched to the Turbine Building Floor (1TA and 1TB area)

Current conditions:

NEC reports the fire on 1TB with heavy smoke and rolling flames

Fire Brigade is dispatched

1) In accordance with the Fire Plan a water fog (1) be used on the switchgear to fight the fire.

2) An (2) is allowed to serve as a leader in accordance with the bases of SLC 16.13.1 (Minimum Station Staffing Requirements).

Which ONE of the following completes the statements above?

A. 1. can

2. SRO ONLY B. 1. can

2. SRO OR an NED with appropriate qualifications C. 1. can NOT

2. SRO ONLY D. 1. can NOT

2. SRO OR an NEO with appropriate qualifications Friday, October 12, 2012 Page 208 of 212

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1LT42 ONS SRO NRC Examination QUESTION 99 99j General Discussion Answer A Discussion Incorrect: First part is correct. Second part is plausible since under normal conditions the SRO is the Fire Brigade leader.

Answer B Discussion Correct. In accordance with the Fire Plan a water fog can be used to fight this fire. In accordance with SEC 16.13.1 an SRO or a quilified NEO can be the Fire Brigade Leader.

Answer C Discussion Incorrect. First part is plasuible because a water stream cannot be used on this fire. Second part is plausible since under normal conditions the SRO is the Fire Brigade leader.

Answer D Discussion Incorrect. First part is plasuible because a water stream cannot be used on this fire. Second part is correct.

Basis for meeting the KA Requires knowledge of fire brigade staffing and using water to fight an electrical fire.

Basis for Hi Cog Basis for SRO only Requires knowledge of the fire plan and the bases of SEC 16.13.1 regarding who can serve as fire brigade leader.

Job Level SRO Cognitive Level Memory QuestionType MODIFIED J Question Source ONS NRC 2009A Q99 Development References Student References Provided Fire plan SLC 16.13.1 bases ONS NRC 2009A Q99 GEN2.4 2.4.26 GENERIC Emergency Procedures / Plan Emergency Procedures / Plan Knowledge of facility protection requirements, including fire brigade andportable fire fighting equipment usage. (CFR: 41.10 / 43.5 / 45.12) 401-9 Comments: Remarks/Status Friday, October 12, 2012 Page 209 of 212

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1LT42 ONS SRO NRC Examination QUESTION 100 io GEN2.4 2.4.6 GENERIC Emergency Procedures / Plan Emergency Procedures / Plan Knowledge of EOP mitigation strategies. (CFR: 41.10 / 43.5 /45.13)

Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 68% decreasing

RCS leak rate = 50 gpm

AP/2 (Excessive Leakage) in progress Current conditions:

1TA and 1TB lockout

Subsequent Actions tab in progress

RCS leak rate = 125 gpm

Station has determined that a natural circulation cooldown is desired

1) The (1)_tab will be used to cool down the RCS.

2) In accordance with the above EOP tab, the MAXIMUM allowable cooldown rate is (2)

Which ONE of the following completes the statements above?

A. 1. Forced Coo ldown

2. <25°F/%hr B. 1. Forced Cooldown

2. <50°F/%hr C. 1. LOCA Coo Idown

2. <25°F/

hr 2

/

1 D. 1. LOCACooldown

2. <50°F/%hr Friday, October 12, 2012 Page 210 of 212

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1LT42 ONS SRO NRC Examination QUESTION 100 io General Discussion Answer A Discussion Correct. Leak rate is less than normal makeup capacity so no transfer is made to the LOCA CD tab. FCD will be used because no RCP are operating.. FCD tab will limit the cooldown rate to less than or equal to 25 degrees per half hour.

Answer B Discussion Incorrect. First part is correct. Second part is plausible because it would be correct if it were not a NC cooldown.

Answer C Discussion Incorrect. First part is plasuible because it would be correct if the RCS leak was greater than Normal Makeup Capacity (160 gpm with letdown isolated). Second part is correct.

Answer D Discussion Incorrect. First part is plasuible because it would be correct if the RCS leak was greater than Normal Makeup Capacity (160 gpm with letdown isolated). Second part is plausible because it would be correct if it were not a NC cooldown.

Basis for meeting the KA Question requires knowledge of FOP mitigation strategies for an RCS leak and a NC cooldown.

Basis for Hi Cog Basis for SRO only In accordance with Clarification Guidance for SRO-only Questions Rev I This question requires the following:

Assessing plant conditions (normal, abnormal, or emergency) and then selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed Must evaluate plant data and determine which EOP tab will be used to perform the CD.

Knowledge of diagnostic steps and decision points in the EOPs that involve transitions to event specific sub procedures or emergency contingency procedures.

Can the question be answered solely by knowing systems knowledge, i.e., how the system works, tiow path, logic, component location? NO Can the question be answered solely by knowing immediate operator actions? NO Can the question be answered solely by knowing entry conditions for AOPs or plant parameters that require direct entry to major EOPs? NO Can the question be answered solely by knowing the purpose, overall sequence of events, or overall mitigative strategy of a procedure? NO Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided SA Tab LOCA CD tab GEN2.4 2.4.6 GENERIC Emergency Procedures I Plan Emergency Procedures / Plan Knowledge of EOP mitigation strategies. (CFR: 41.10 / 43.5 / 45.13) 401-9 Comments: RemarkslStatus Friday, October 12, 2012 Page 211 of 212

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