Text

Initial Exam 2015-301 2015-301 Draft SRO Written Exam
	ML15247A401
Person / Time
Site:	Oconee
Issue date:	09/04/2015
From:	; NRC/RGN-II
To:	; Duke Energy Carolinas
References
	Download: ML15247A401 (66)
	v • d • e

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 76 EPE009 EA2.11 - Small Break LOCA 76 B Ability to determine or interpret the following as they apply to a small break LOCA: (CFR 43.5 / 45.13)

Containment temperature, pressure, and humidity .....................

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 ºF RCS temperature = 550 ºF decreasing Reactor building pressure = 6 psig increasing 1RIA-58 = 15 R/hr increasing Time = 0445 Reactor building pressure = 18 psig increasing Tremor felt in the control room Seismic trigger actuates Time = 0455 Reactor building pressure = 4 psig decreasing 1RIA-58 = 55 R/hr 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 Wednesday, April 01, 2015 Page 180 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 76 76 B General Discussion Answer A Discussion First part is correct. Loss of SCM gives 5 points on the matrix. This is an Alert.

Second part is incorrect because a General Emergency is the correct classification. It 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 First part is incorrect because an Alert is the correct classification. It 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 incorrect because a General Emergency is the correct classification. It 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 D Discussion First part is incorrect because an Alert is the correct classification. It 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.

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.

Basis for meeting the KA Question requires knowledge of how to base an emergency classification based on plant conditions including containment pressure. This question requires interpreting Containment Pressure indications as they relate to determining the correct EAL.

Basis for Hi Cog Basis for SRO only This question is SRO only based on being an emergency classification.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK ILT42 Q83 Development References Student References Provided ILT42 Q83 RP 1000 001 RP 1000 001 EAP SEP EPE009 EA2.11 - Small Break LOCA Ability to determine or interpret the following as they apply to a small break LOCA: (CFR 43.5 / 45.13)

Containment temperature, pressure, and humidity .....................

401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 181 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 76 76 B Wednesday, April 01, 2015 Page 182 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 77 APE025 2.2.44 - Loss of Residual Heat Removal System (RHRS) 77 A APE025 GENERIC Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5 / 43.5 / 45.12)

Unit 1 initial conditions:

Reactor in MODE 6 Fuel Transfer Canal full SF-1 and SF-2 are open Current conditions:

Operator reports Fuel Transfer Canal level slowly decreasing RBNS level increasing Control Room indicates Spent Fuel Pool level decreasing Based on the above conditions, which ONE of the following:

1) actions would be performed first in accordance with AP/26 (Loss of Decay Heat Removal)?

2) states the reason for the action?

A. 1. Secure ALL LPI Pumps

2. Determine if leak is on discharge of LPI Pumps B. 1. Secure ALL LPI Pumps

2. Preparation for closing 1SF-1 and 1SF-2 C. 1. Secure SF Cooling pump used for Refueling Cooling Mode

2. Determine if leak is on discharge of SF Cooling Pump D. 1. Secure SF Cooling pump used for Refueling Cooling Mode

2. Preparation for closing 1SF-1 and 1SF-2 Wednesday, April 01, 2015 Page 183 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 77 77 A General Discussion Answer A Discussion 1st part is correct. Once you make your way to the correct section of AP/26 , it will direct securing all LPI pumps in an effort to determine the location and isolability of the leak.

2nd part is correct. If securing the pumps do not change the leak rate then they will be restarted.

Answer B Discussion First part is correct because the first action performed is to secure ALL LPI pumps.

Second part is incorrect because the reason is for leak determination. It is plausible plausible since the current SFC alignment in the refueling mode provides for taking a suction off the fuel transfer canal via the decay heat drop line and discharging to the SFP. That alignment must be secured prior to closing SF-1 and 2 to prevent pumping FTC to SFP however it is the B SF pump being used in this alignment and not the LPI pumps.

Answer C Discussion Incorrect because this is not the first action directed. It is plausible since the B SFC Pump is being used in the Refueling Mode alignment and securing the pump and monitoring leak rate could help determine if the source of the leak is on the discharge of SFC pump. Since the Fuel Transfer Canal is full, securing the pump is plausible. Additionally, this action is actually directed by AP/26 although it is a later action after transferring to the condition specific section of the AP. It is the LPI pumps that are initially secured.

Answer D Discussion Incorrect because it is not the first action directed. It is plausible since the SFC pumps are secured later in AP/26 prior to closing SF-1 and 2 to prevent pumping FTC to SFP.

Basis for meeting the KA Requires ability to interpret CR indications to determine status of the system and use that knowledge to take appropriate actions per AP/26. It also requires the reasons/affects that those actions have on the system Basis for Hi Cog Basis for SRO only This first part of this question requires detailed knowledge of specific procedure steps in AP/26. Knowledge of these steps are used to select which section of the procedure is to be performed. There are several sections of Subsequent Actions that could be performed based on the conditions requiring entry into the AP and using knowledge of the entry conditions and assessing the different sections of Subsequent actions is required to determine the appropriate steps to perform. Additionally, this question requires detailed knowledge of specific steps that need to be taken prior to transfer to section 4D. In this specific case, the LPI pumps are secured to assess the impact on the decreasing fuel transfer canal level. In this situation it is after these steps are performed that you make the transfer to section 4D which will direct stopping the SF Pump. This path through the AP means that to get to the appropriate actions you must assess plant conditions and determine a section of the procedure with which to proceed.

This question cannot be answered bases solely on systems knowledge since when in MODE 6 with fuel transfer canal full it would be normal to have LPI pumps running AND the B Spent Fuel Cooling pump aligned in the Refueling Cooling mode. Also, neither reason given for securing pumps would eliminate either answer based on system knowledge.

This question cannot be answered bases solely on knowledge of entry conditions.

None of the operator actions are Immediate Operator Actions of the AP.

The knowledge needed is more detail than just the major mitigation strategy of the AP.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK 2009B NRC Exam Q78 Development References Student References Provided 2009B Q78 EAP-APG R8 AP/26 APE025 2.2.44 - Loss of Residual Heat Removal System (RHRS)

Wednesday, April 01, 2015 Page 184 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE APE025ILT 47- Loss 2.2.44 APE025 GENERIC ONS SROHeat of Residual NRC Examination Removal System (RHRS) QUESTION 77 77 A Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5 / 43.5 / 45.12) 401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 185 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 78 APE027 2.2.25 - Pressurizer Pressure Control System (PZR PCS) Malfunction 78 B APE027 GENERIC Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 / 41.7 / 43.2)

Given the following Unit 1 conditions:

Reactor in MODE 5 ALL LTOP requirements established in accordance with Tech Spec 3.4.12 (LTOP) 1HP-120 demand signal fails to 100%

Which ONE of the following describes the reason the failure will NOT result in exceeding RCS brittle fracture pressure limits?

A. LTOP requires the HPI system to be deactivated therefore no HPI pumps will be injecting B. Mechanical Travel Stop on 1HP-120 limits flow such that the operator has 10 minutes to identify and mitigate the event C. The PORV will act as a backup to the failed Administrative Control and prevent exceeding the brittle fracture limits D. The dedicated LTOP operator is credited with identifying the failure and responding within 10 minute of the event initiation Wednesday, April 01, 2015 Page 186 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 78 78 B General Discussion Answer A Discussion Incorrect: Plausible since TS 3.4.12 does specify in the LCO statement that both trains of HPI must be deactivated however the bases goes on to explain that it is referring to HPI ES actuation. HPI pump operation is allowed as long as associated train valves are deactivated.

Answer B Discussion Correct: There are two trains of LTOP protection. The primary train is the Admin Controls train. This train requires that makeup flow be controlled. The basis of TS 3.4.12 goes on to specify that for the Admin Controls to be established, there must be a travel stop on HP-120 which will limit flow to a max of 98 gpm. The PORV is a backup to the Admin controls.

Answer C Discussion Incorrect: Plausible since the PORV does act as a backup however there is no failed administrative control since the travel stop is in place and therefore the PORV would not be required to mitigate the event.

Answer D Discussion Incorrect: Plausible since the dedicated LTOP operator can be credited with mitigating an LTOP event however the LTOP operator is only established if one or more of the required Admin controls are not in place.

Basis for meeting the KA Requires knowledge of the LTOP LCO as it relates to HP-120 and the PORV, both of which are part of the Pressurizer pressure control system. The malfunction portion of the KA is satisfied by the failure of the 1HP-120 demand signal.

Basis for Hi Cog Basis for SRO only This question requires knowledge from the basis of TS 3.4.12 and the Safety Limits that is not systems knowledge. While the LTOP lesson plan does require an RO to know that there are administrative limits on makeup flow during LTOP, it is only specifically out of the TS bases that we describe how that requirement is satisfied. Additionally requires SRO only knowledge of HPI deactivation requirements.

Job Level Cognitive Level QuestionType Question Source SRO Memory BANK ILT40 (Q79) NRC Exam Development References Student References Provided CP-017 Pg 14, 15 TS 3.4.12 bases ILT40 Q79 APE027 2.2.25 - Pressurizer Pressure Control System (PZR PCS) Malfunction APE027 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: Remarks/Status Wednesday, April 01, 2015 Page 187 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 79 EPE055 2.2.44 - Loss of Offsite and Onsite Power (Station Blackout) 79 A EPE055 GENERIC Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5 / 43.5 / 45.12)

Given the following Unit 1 conditions:

Initial conditions:

Reactor power = 100%

ACB-4 closed Switchyard Isolation occurs Current conditions:

Keowee Unit 2 emergency lockout 230 KV Yellow Bus Differential lockout Blackout Tab is in progress

1) The Blackout tab will direct the performance of ___(1)___ to energize 1TC, 1TD and 1TE.

2) The MFB will be re-energized from ___(2)___ in accordance with the procedure directed in part 1.

Which ONE of the following completes the statements above?

A. 1. Enclosure 5.38 (Restoration of Power)

2. CT-4 B. 1. Enclosure 5.38 (Restoration of Power)

2. CT-5 C. 1. AP/11 (Recovery from Loss of Power)

2. CT-4 D. 1. AP/11 (Recovery from Loss of Power)

2. CT-5 Wednesday, April 01, 2015 Page 188 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 79 79 A General Discussion Answer A Discussion 1st part is correct. Encl 5.38 will be used to restore power to TC, TD and TE.

2nd part is correct. EOP enclosure 5.38 (Restoration of Power) will align power to the MFBs from Keowee Unit 1 via CT-4 since it is operating.

Answer B Discussion 1st part is correct. Encl 5.38 will be used to restore power to TC, TD and TE.

2nd part is incorrect because power will come through CT-4. It is plausable because CT-5 would be used if Keowee Unit 1 were not available.

Answer C Discussion 1st part is incorrect because power is restored to TC, TD and TE with Encl 5.38. It is plausible because AP/11 is used to restore power to equipment after power is restored to TC, TD or TE and it is directed by the Blackout Tab.

2nd part is correct. EOP enclosure 5.38 (Restoration of Power) will align power to the MFBs from Keowee Unit 1 via CT-4 since it is operating.

Answer D Discussion 1st part is incorrect because power is restored to TC, TD and TE with Encl 5.38. It is plausible because AP/11 is used to restore power to equipment after power is restored to TC, TD or TE and it is directed by the Blackout Tab.

2nd part is incorrect because power will come through CT-4. It is plausable because CT-5 would be used if Keowee Unit 1 were not available.

Basis for meeting the KA Question matches the KA by requiring knowledge of control room indications to determine status of electrical system and knowing how power will come back in to the busses.

Basis for Hi Cog Basis for SRO only This question is SRO only because it requires assessing plant conditions and then selecting a procedure to recover or proceed.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided EAP-BO Pg 10, 12 Blackout Tab AP 11 SRO Only Guidance Encl 5.38 Elec Dwg EPE055 2.2.44 - Loss of Offsite and Onsite Power (Station Blackout)

EPE055 GENERIC Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5 / 43.5 / 45.12) 401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 189 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 79 79 A Wednesday, April 01, 2015 Page 190 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 80 APE058 AA2.01 - Loss of DC Power 80 B Ability to determine and interpret the following as they apply to the Loss of DC Power: (CFR: 43.5 / 45.13)

That a loss of dc power has occurred; verification that substitute power sources have come on line ..........................

Given the following Unit 1 conditions:

Time = 1200:

Reactor power = 100%

1SA6/B2 INVERTER 1DID SYSTEM TROUBLE actuated Time = 1205 AO reports:

o 1SA13/A8 INVERTER 1DID INPUT VOLTAGE LOW actuated o Inverter 1DID output voltage low

1) The status of 1KVID at Time = 1205 is __(1)__.

2) The MINIMUM action(s) required to restore the 1DID inverter to OPERABLE in accordance with Tech Spec 3.8.6 (Vital Inverters-Operating) is/are to restore DC input voltage __(2)__.

Which ONE of the following completes the statements above?

A. 1. NOT energized

2. ONLY B. 1. NOT energized

2. AND re-connect to 1KVID C. 1. Energized

2. ONLY D. 1. Energized

2. AND re-connect to 1KVID Wednesday, April 01, 2015 Page 191 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 80 80 B General Discussion Answer A Discussion First part is correct. The Vital inverter panelboards (KVIA, KVIB, KVIC, and KVID) do have an alternate source of power that can be aligned from Regulated power (KRA) however the swap requires manual alignment since there is no Auto swap to Regulated power for the vital power panelboards.

Second part is incorrect because to be operable, DID is required to connected KVID. It is plausible since restoring the DC input voltage would return the inverter to a functional status however it would not meet TS bases requirement for operability since it is not aligned to its panelboard.

Answer B Discussion First part is correct. The Vital inverter panelboards (KVIA, KVIB, KVIC, and KVID) do have an alternate source of power that can be aligned from Regulated power (KRA) however the swap requires manual alignment since there is no Auto swap to Regulated power for the vital power panelboards.

Second part is correct. The bases of TS 3.8.6 requires the inverter to be powering its associated panelboard to be Operable.

Answer C Discussion First part is incorrect. First part is plausible since the essential inverter [panelboards (KI, KU, and KX) do have an auto swap function to provide them power from regulated power automatically on loss of the inverter therefore this would be a correct choice if asking about one of the essential power panelboards.

Second part is incorrect because to be operable, DID is required to connected KVID. It is plausible since restoring the DC input voltage would return the inverter to a functional status however it would not meet TS bases requirement for operability since it is not aligned to its panelboard.

Answer D Discussion Incorrect, First part is plausible since the essential inverter [panelboards (KI, KU, and KX) do have an auto swap function to provide them power from regulated power automatically on loss of the inverter therefore this would be a correct choice if asking about one of the essential power panelboards.

Second part is correct. The bases of TS 3.8.6 requires the inverter to be powering its associated panelboard to be Operable..

Basis for meeting the KA This question requires the ability to interpret given plant indications and determine if they indicate a loss of one of the vital instrument power panelboards. Then determination of the status of the panelboard following the loss of DC demonstrates the ability to verify that substitute power sources have responded correctly.. At the SRO level the question requires interpreting the loss of DC input to the inverter and its impact on the actions required to restore the inverter to Operable.

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

This question requires making operability determinations on TS related equipment. The first part of the question requires knowledge of operability requirements for the DID inverter found only in the Bases of TS 3.8.6 (that it be connected to its associated panelboard to be considered Operable) and can not be answered by system knowledge only. The second part is RO knowledge since it can be answered based on system knowledge.

It cannot be answered solely by1hr or less memory items.

It cannot be answered solely by above the line knowledge It cannot be answered solely by knowing TS Safety Limits It does require knowledge of TS basis that is not systems knowledge Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK ILT44 Q80 Wednesday, April 01, 2015 Page 192 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 80 Development References Student References Provided 80 B ILT44 Q80 ADM TSS TS 3.8.6 B APE058 AA2.01 - Loss of DC Power Ability to determine and interpret the following as they apply to the Loss of DC Power: (CFR: 43.5 / 45.13)

That a loss of dc power has occurred; verification that substitute power sources have come on line ..........................

401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 193 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 81 APE062 AA2.02 - Loss of Nuclear Service Water 81 B Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: (CFR: 43.5 / 45.13)

The cause of possible SWS loss ....................................

Given the following plant conditions:

Initial plant conditions:

Unit 1 AND Unit 2 Reactor power = 100%

A and C LPSW pumps are operating 1LPSW-2 (A LPSW Pump Suction) is inadvertently closed Current plant conditions:

1SA-09 / A-9, LPSW HEADER A PRESS LOW alarms and clears LPSW header pressure is fluctuating between 75 psig and 85 psig A LPSW pump amps are erratic AP/24, LOSS OF LPSW is initiated In accordance with AP/24:

1) the Standby LPSW Pump auto start circuitry ____(1)____ disabled prior to securing the A LPSW pump.

2) the A LPSW pump can be restarted____(2)____.

Which ONE of the following completes the statements above?

A. 1. is

2. as soon as 1LPSW-2 has been re-opened B. 1. is

2. ONLY after the A LPSW pump has been filled and vented C. 1. is NOT

2. as soon as 1LPSW-2 has been re-opened D. 1. is NOT

2. ONLY after the A LPSW pump has been filled and vented Wednesday, April 01, 2015 Page 194 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 81 81 B General Discussion Answer A Discussion 1st part is correct. AP/24, step 4.3 directs disabling the Unit 1/2 STBY LPSW PUMP AUTO START CIRCUIT. Step 4.4 stops the affected pump.

2nd part is incorrect because with indications of cavitation, a note prior to step 4.7 states the pump must be filled and vented prior to start. It is plausible because the source of the problem has been both identified and corrected.

Answer B Discussion 1st part is correct. AP/24, step 4.3 directs disabling the Unit 1/2 STBY LPSW PUMP AUTO START CIRCUIT. Step 4.4 stops the affected pump.

2nd part is correct because there is a note in AP/24 prior to step 4.7 (to start LPSW pumps) that states if the pump was stopped due to cavitation, it is NOT available until filled and vented.

Answer C Discussion 1st part is incorrect because the the Unit 1/2 STANDBY LPSW PUMP AUTO START CIRCUIT is placed in DISABLE prior to stopping the affected pumps. It is plausible because cavitation was not taking place, it would be correct.

2nd part is incorrect because with indications of cavitation, a note prior to step 4.7 states the pump must be filled and vented prior to start. It is plausible because the source of the problem has been both identified and corrected.

Answer D Discussion 1st part is incorrect because the the Unit 1/2 STANDBY LPSW PUMP AUTO START CIRCUIT is placed in DISABLE prior to stopping the affected pumps. It is plausible because cavitation was not taking place, it would be correct.

2nd part is correct because there is a note in AP/24 prior to step 4.7 (to start LPSW pumps) that states if the pump was stopped due to cavitation, it is NOT available until filled and vented.

Basis for meeting the KA The question matches the KA by requiring knowledge of the indications of pump cavitation (cause of possible SWS loss). This will determine the actions taken in the AP for this loss (switch taken to disable) andrequirements for restart.

Basis for Hi Cog Basis for SRO only This question is SRO only because it requires in-depth knowledge of abnormal procedures and operability requirements of LPSW system components.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided AP/24 TS 3.3.28 TS 3.7.7 B EAP APG SSS-LPW Pg 10, 19 APE062 AA2.02 - Loss of Nuclear Service Water Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: (CFR: 43.5 / 45.13)

The cause of possible SWS loss ....................................

401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 195 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 81 81 B Wednesday, April 01, 2015 Page 196 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 82 APE037 AA2.03 - Steam Generator (S/G) Tube Leak 82 C Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak: (CFR: 43.5 / 45.13)

That the expected indication on main steam lines from the S/Gs should show increasing radiation levels ......................

Given the following Unit 1 conditions:

Time = 0800:

Reactor power = 80% stable 1RIA-40 Alert and High Alarm actuated AP/31, PRIMARY TO SECONDARY LEAKAGE is initiated 1RIA-59 = 20 gpm increasing 1RIA-60 = 0.4 gpm increasing Time = 0805:

1RIA-59 = 30 gpm increasing 1RIA-60 = 0.6 gpm increasing SGTR tab is entered Maximum Runback is initiated Time = 0809 Reactor power = 15%

Auxiliaries have been transferred

1) If there is no primary to secondary leak on the 1B SG, the increased indication on 1RIA-60 is most likely due to radiation____(1)____.

2) At 0809, the SRO should____(2)____, then continue in the SGTR tab.

Which ONE of the following completes the statements above?

A. 1. from the B steam header due to cross contamination

2. trip the Main Turbine ONLY B. 1. from the B steam header due to cross contamination

2. trip the Main Turbine AND the Reactor C. 1. from the A SG header reaching 1RIA-60 due to the close proximity of the steam lines

2. trip the Main Turbine ONLY D. 1. from the A SG header reaching 1RIA-60 due to the close proximity of the steam lines

2. trip the Main Turbine AND the Reactor Wednesday, April 01, 2015 Page 197 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 82 82 C General Discussion Answer A Discussion 1st part is incorrect because N-16 will have decayed away by the time it has passed through the system and back down the B steam line. It is plausible because some cross contamination will occur.

2nd part is correct. Criteria to trip the turbine is power ~ 15% and auxiliaries transferred. The reactor will not be tripped until power is < 5%.

Answer B Discussion 1st part is incorrect because N-16 will have decayed away by the time it has passed through the system and back down the B steam line. It is plausible because some cross contamination will occur.

2nd part incorrect because the reactor is not tripped at this time. It is plasusible because if less than or equal to 5%, it would be correct.

Answer C Discussion 1st part is correct. Per the caution statement prior to step 12 in the SGTR tab, shine can account for up to 2% of the value of the opposite header.

2nd part is correct. Criteria to trip the turbine is power ~ 15% and auxiliaries transferred. The reactor will not be tripped until power is < 5%.

Answer D Discussion 1st part is correct. Per the caution statement prior to step 12 in the SGTR tab, shine can account for up to 2% of the value of the opposite header.

2nd part incorrect because the reactor is not tripped at this time. It is plasusible because if less than or equal to 5%, it would be correct.

Basis for meeting the KA This question matches the KA by requiring knowledge of the effects radiation shine on steam line detectors during a SGTR and how they could increase without a SGTR on that particular SG.

Basis for Hi Cog Basis for SRO only This question is SRO only because it requires "Assessing plant conditions and then selecting a procedure or section of a procedure with which to proceed".

Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided EAP-APG SGTR Tab AP 31 AP 2 RAD-RIA Pg 30-32 APE037 AA2.03 - Steam Generator (S/G) Tube Leak Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak: (CFR: 43.5 / 45.13)

That the expected indication on main steam lines from the S/Gs should show increasing radiation levels ......................

401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 198 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 82 82 C Wednesday, April 01, 2015 Page 199 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 83 APE051 2.4.20 - Loss of Condenser Vacuum 83 A APE051 GENERIC Knowledge of the operational implications of EOP warnings, cautions, and notes. (CFR: 41.10 / 43.5 / 45.13)

Given the following Unit 3 conditions:

Reactor power = 100%

Condenser vacuum = 26Hg decreasing Steam pressure to the CSAEs = 240 psig stable

1) Per 3AP/27, steam pressure to the CSAEs ____(1)____ required to be increased.

2) Guidance to address aligning the Main Vacuum Pumps to Unit 3 is contained in

____(2)____.

Based on the given plant conditions, complete the above statements.

A. 1. is

2. 1AP/27 B. 1. is

2. 3AP/27 C. 1. Is NOT

2. 1AP/27 D. 1. Is NOT

2. 3AP/27 Wednesday, April 01, 2015 Page 200 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 83 83 A General Discussion Answer A Discussion 1st part is correct. Per step 4.6, Ensure Stm to Stm Air Eject A, B, C > 255 psig.

2nd part is correct. A procedure note in 1/AP/27 Encl 5.1 states that this enclusire will be used to align vacuum pumps on ANY Oconee Unit.

Answer B Discussion 1st part is correct. Per step 4.6, Ensure Stm to Stm Air Eject A, B, C > 255 psig.

2nd part is incorrect because guidance to align the Main Vacuum Pumps is contained in Unit 1's AP/27. A procedure note in 1/AP/27 Encl 5.1 states that this enclusire will be used to align vacuum pumps on ANY Oconee Unit. It is plausible because the Vacuum loss is on Unit 3.

Answer C Discussion 1st part is incorrect because step 4.6 states to Ensure SJAE pressure is > 255 psig. It is plausible because 250 psig is a number used to ensure the TD EFDW pump remains operable.

2nd part is correct. A procedure note in 1/AP/27 Encl 5.1 states that this enclusire will be used to align vacuum pumps on ANY Oconee Unit.

Answer D Discussion 1st part is incorrect because step 4.6 states to Ensure SJAE pressure is > 255 psig. It is plausible because 250 psig is a number used to ensure the TD EFDW pump remains operable.

2nd part is incorrect because guidance to align the Main Vacuum Pumps is contained in Unit 1's AP/27. A procedure note in 1/AP/27 Encl 5.1 states that this enclusire will be used to align vacuum pumps on ANY Oconee Unit. It is plausible because the Vacuum loss is on Unit 3.

Basis for meeting the KA This question matches the KA by requiring knowledge of cautions contained in the EOP pertaining to a loss of vacuum.

Basis for Hi Cog Basis for SRO only This question is at the SRO level based on additional knowledge of a procedures content beyond the overall mitigation strategy (SJAE requiring to be > 255 psig). Also, the question requires enough knowledge to select the correct procedure to mitigate consequences to this event.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided 1/AP/27 3/AP/27 EAP-APG APE051 2.4.20 - Loss of Condenser Vacuum APE051 GENERIC Knowledge of the operational implications of EOP warnings, cautions, and notes. (CFR: 41.10 / 43.5 / 45.13) 401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 201 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 84 APE059 AA2.03 - Accidental Liquid Radioactive-Waste Release 84 D Ability to determine and interpret the following as they apply to the Accidental Liquid Radwaste Release: (CFR: 43.5 / 45.13)

Failure modes, their symptoms, and the causes of misleading indications on a radioactive-liquid monitor .................

Unit 1 plant conditions:

Reactor power = 100%

50 gpd tube leak 1A Steam Generator for approximately 1 week An increase in activity is reported in Chemical Treatment Pond (CTP) #3 Which ONE of the following:

1) describes an event which would cause this increase?

2) states the LOWEST Steam Generator tube leak rate that would require initiating a power decrease in accordance with AP/31 Primary to Secondary Leakage?

A. 1. 1RIA-31 (LPI Cooler) activity is increasing and this will increase activity levels in CTP #3.

2. 65 gpd B. 1. 1RIA-33 (LW Release) interlock has failed and a Waste Monitor Tank release continues from the Radwaste Building.

2. 125 gpd C. 1. 1RIA-42 (RCW) activity is increasing and this will increase activity levels in CTP #3.

2. 65 gpd D. 1. 1RIA-54 (TBS) interlock has failed and the Turbine Building Sump is being continually pumped.

2. 125 gpd Wednesday, April 01, 2015 Page 202 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 84 84 D General Discussion Answer A Discussion 1st part is incorrect. LPSW goes to the discharge not to #3 CTP. Isolating the cooler would not stop the release.

2nd part is incorrect. AP/31 directs that if leak rate reaches 100 gpd, then initiate a power reduction. It is plausible because if > 60 gpd AND both continious primary to secondary leakage monitoring methods are inoperable, it would be correct. This however, it not the situation.

Answer B Discussion 1st part is incorrect. Waste monitor tanks discharge to the Keowee tailrace, not CTP # 3.

2nd part is correct. AP/31 directs that if leak rate reaches 100 gpd, then initiate a power reduction.

Answer C Discussion 1st part is incorrect. RCW is a closed system. The RCW cooler is cooled by CCW which goes to the discharge, not CTP #3.

2nd part is incorrect. AP/31 directs that if leak rate reaches 100 gpd, then initiate a power reduction. It is plausible because if > 60 gpd AND both continious primary to secondary leakage monitoring methods are inoperable, it would be correct. This however, it not the situation.

Answer D Discussion 1st part is correct. TBS pumps to CTP #3. Due to the S/G tube leak, activity could be high in the sump. If the interlock failed it could pump high activity to CTP #3.

2nd part is correct. AP/31 directs that if leak rate reaches 100 gpd, then initiate a power reduction.

Basis for meeting the KA Requires knowledge that failure of the 1RIA-54 (Turbine Building Sump monitor) automatic isolation function will require manual action to terminate a liquid radwaste release.

Basis for Hi Cog Basis for SRO only

.The second part of the question requires detailed knowledge of the content of AP/31 that is not just major mitigation strategy. The major strategy would require knowledge that there are thresholds of leakage rates that you can reach before reaching the leak rate that would require enter into the EOP that would require power reduction. It is detailed knowledge of the content to know what those specific leak rate threshold values are.

Additionally, knowledge of the threshold values for shutdown demonstrate the ability to determine that Enclosure 5.1 (Unit Shutdown Requirements) becomes applicable and therefore demonstrates assessing plant conditions and determining a section of a procedure with which to proceed.

Job Level Cognitive Level QuestionType Question Source SRO Memory MODIFIED ILT43 Q64 / 2009B Q92 Development References Student References Provided RAD-RIA Pg 26 ILT43 Q64 2009B Q92 AP 31 APE059 AA2.03 - Accidental Liquid Radioactive-Waste Release Ability to determine and interpret the following as they apply to the Accidental Liquid Radwaste Release: (CFR: 43.5 / 45.13)

Failure modes, their symptoms, and the causes of misleading indications on a radioactive-liquid monitor .................

401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 203 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 84 84 D Wednesday, April 01, 2015 Page 204 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 85 BWE09 2.2.4 - Natural Circulation Operations 85 A BWE09 GENERIC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (CFR: 41.6 / 41.7 / 41.10 / 45.1 / 45.13)

Unit 3 plant conditions:

Time = 0800 A main steam line break occurred inside containment The EHT tab was performed The crew transferred to the Forced Cooldown (FCD) Tab Time = 0830 The decision has been made to perform a natural circulation cooldown Time = 1500 RCS temperature = 240 OF RCS pressure = 250 psig

1) At this point in the cooldown, the FCD tab directs using the ____(1)____ to complete the RCS cooldown.

2) Transition to OP/3/A/1102/010 (Controlling Procedure for Unit Shutdown) is done

____(2)____.

A. 1. Normal Decay Heat Removal Mode

2. ONLY after the LPI alignment in (1) above is made B. 1. Normal Decay Heat Removal Mode

2. to perform the alignment directed in (1) above C. 1. LPI Series Mode

2. ONLY after the LPI alignment in (1) above is made D. 1. LPI Series Mode

2. to perform the alignment directed in (1) above Wednesday, April 01, 2015 Page 205 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 85 85 A General Discussion Answer A Discussion 1st part is correct. This is true for Unit 3.

2nd part is correct. As directed in the FCD tab, the transition is made to 1102/010 after LPI DHR is established and temperature is 150 to 180 degrees.

Answer B Discussion 1st part is correct. This is true for Unit 3.

2nd part is incorrect but plausible since this procedure does contain directions required to align LPI cooling and under other conditions the OP is what is used to perform aligment to LPI cooling.

Answer C Discussion 1st part is incorrect because you are directed by the Unit 3 FCD tab to line up for normal decay heat removal mode. It is plausible because if it were Unit 1, it would be correct.

2nd part is correct. As directed in the FCD tab, the transition is made to 1102/010 after LPI DHR is established and temperature is 150 to 180 degrees.

Answer D Discussion 1st part is incorrect because you are directed by the Unit 3 FCD tab to line up for normal decay heat removal mode. It is plausible because if it were Unit 1, it would be correct.

2nd part is incorrect but plausible since this procedure does contain directions required to align LPI cooling and under other conditions the OP is what is used to perform aligment to LPI cooling.

Basis for meeting the KA Chief agreed that using the transition to LPI at end of cooldown would meet intent of KA as long as it is done from a NC cooldown.

This question matches the KA by requiring knowledge of the differences in Units procedural actions when perform a natural circulation cooldown.

Basis for Hi Cog Basis for SRO only This question is SRO only because it requires assessing plant conditions and determining a procedural path to address those conditions.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK Development References Student References Provided FCD tab U1 FCD tab U3 EAP FCD PNS LPI Pg 21, 28 SRO Only Guidance BWE09 2.2.4 - Natural Circulation Operations BWE09 GENERIC (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (CFR: 41.6 / 41.7 / 41.10 / 45.1 / 45.13)

Wednesday, April 01, 2015 Page 206 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 85 401-9 Comments: Remarks/Status 85 A Wednesday, April 01, 2015 Page 207 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 86 SYS005 2.1.30 - Residual Heat Removal System (RHRS) 86 B SYS005 GENERIC Ability to locate and operate components, including local controls. (CFR: 41.7 / 45.7)

Given the following Unit 2 conditions:

Reactor in MODE 6 LPI aligned to Normal DHR mode

1) The MINIMUM LT-5 level which allows LPI to be aligned to the purification IX is

__(1)__ inches.

2) The valve used to make this alignment (2LP-96) is a(n) __(2)__ operated valve.

Which ONE of the following completes the statements above.

A. 1. 50

2. electrically B. 1. 50

2. manually C. 1. 80

2. electrically D. 1. 80 2.. manually Wednesday, April 01, 2015 Page 208 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 86 86 B General Discussion Answer A Discussion Incorrect.

First part is correct since the LPI procedure initial conditions for the enclosure used to align LPI to purification requires that LT-5 level be 50" or greater.

Second part is incorrect but plausible since there are a large nunber of LPI valves that are electric valves operated from the control and there are valves in the purification alignment that are electric valves, Answer B Discussion Correct First part is correct since the LPI procedure initial conditions for the enclosure used to align LPI to purification requires that LT-5 level be 50" or greater.

Second part is correct since 1LP-96 is a manual valve.

Answer C Discussion Incorrect First part is plausible since 80" is a threshold level for Rx vessel level for many things It is also the approximate level of where the Rx Vessel level is maintained to prevent flooding the transfer canal which occurs at 84".

Second part is incorrect but plausible since there are a large nunber of LPI valves that are electric valves operated from the control and there are valves in the purification alignment that are electric valves, Answer D Discussion Incorrect First part is plausible since 80" is a threshold level for Rx vessel level for many things It is also the approximate level of where the Rx Vessel level is maintained to prevent flooding the transfer canal which occurs at 84".

Second part is correct since 1LP-96 is a manual valve.

Basis for meeting the KA This question requires knowledge of local components related to the operation of the RHR system. 1LP-96 is a manual valve and therefore a local control. KA is met at the SRO level since the question also requires knowledge of when the local control can be operated.

Basis for Hi Cog Basis for SRO only This question is SRO only because it requires assessing plant conditions and determining a section of a procedure which will be utilized and is not entry conditions to an AP or EOP.

Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Development References Student References Provided TS 3.4.7 basis PNS-LPI SYS005 2.1.30 - Residual Heat Removal System (RHRS)

SYS005 GENERIC Ability to locate and operate components, including local controls. (CFR: 41.7 / 45.7)

Wednesday, April 01, 2015 Page 209 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 86 401-9 Comments: Remarks/Status 86 B Wednesday, April 01, 2015 Page 210 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 87 SYS012 A2.05 - Reactor Protection System (RPS) 87 B Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; 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)

Faulty or erratic operation of detectors and function generators .........

Given the following Unit 1 conditions:

Time = 1200:00 Reactor startup in progress Reactor power = 3% stable The operating Main Feedwater Pump trips Time = 1200:15 The SRO directs the OATC to perform IMAs Time = 1202 Reactor power = 3% stable

1) The reactor ____(1)____ have automatically tripped at Time = 1200 when the operating FDW pump tripped.

2) The SRO should ____2____.

Which ONE of the following completes the statements above?

A. 1. should

2. perform actions in the Subsequent Actions tab to shut down the reactor B. 1. should

2. GO TO the UNPP tab to perform actions to shut down the reactor C. 1. should NOT

2. perform actions in the Subsequent Actions tab to shut down the reactor D. 1. should NOT

2. GO TO the UNPP tab to perform actions to shut down the reactor Wednesday, April 01, 2015 Page 211 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 87 87 B General Discussion Answer A Discussion 1st part is correct. The automatic reactor trip due to no running MFWPs automatically "enables" when > 1.75% power. Therefore, the reactor should have tripped.

2nd part is incorrect because the SRO should transfer to the UNPP tab from the Subsequent Action Tab Parallel Action Page before performing any actions in the Subsequent Action Tab. It is plausible because

1) the criteia to stay in the SA tab is power < 5% (true) and decreasing (false) with the RNO directing you to GO TO the UNPP tab. You are <

5%.

2) there are actions in the SA tab to shut down the reactor if not ALL control rods inserted. The RNO for step one includes opening HP-24 &

25, inserting control rods manually and tripping CRD breakers.

Answer B Discussion 1st part is correct. The automatic reactor trip due to no running MFWPs automatically "enables" when > 1.75% power. Therefore, the reactor should have tripped.

2nd part is correct.UNPP is plausible even if Rs should hot have Automatically tripped since the RP attempted to perform IMA's and the Rx is still at power. This would mean the Rx Trip pushbutton has been depressed and the Rx still did not trip.

Answer C Discussion 1st part is incorrect because the reactor should have automatically tripped. It is plausible because if power were < 1.75%, it would be correct.

2nd part is incorrect because the SRO should transfer to the UNPP tab from the Subsequent Action Tab Parallel Action Page before perform any actions in the Subsequent Action Tab. It is plausible because

1) the criteia to stay in the SA tab is power < 5% (true) and decreasing (false) with the RNO directing you to GO TO the UNPP tab. You are <

5%.

2) there are actions in the SA tab to shut down the reactor if not ALL control rods inserted. The RNO for step one includes opening HP-24 &

25, inserting control rods manually and tripping CRD breakers.

Answer D Discussion 1st part is incorrect because the reactor should have automatically tripped. It is plausible because if power were < 1.75%, it would be correct.

2nd part is correct.UNPP is plausible even if Rs should hot have Automatically tripped since the RP attempted to perform IMA's and the Rx is still at power. This would mean the Rx Trip pushbutton has been depressed and the Rx still did not trip.

Basis for meeting the KA The question matches the KA by requiring the ability to predict the impact of reaching reactor trip setpoints (or in this case that it failed), and using the correct procedure to mitigate the event.

Basis for Hi Cog Basis for SRO only This question is SRO only because it requires the ability to assess plant conditions and select the appropriate procedure to mitigate the event.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided Digital RPS Pg 44 IMA SA EAP IMA Pg 8 SYS012 A2.05 - Reactor Protection System (RPS)

Wednesday, April 01, 2015 Page 212 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE SYS012ILT A2.0547- Reactor ONSProtection SRO NRC Examination QUESTION 87 System (RPS) 87 B Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; 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)

Faulty or erratic operation of detectors and function generators .........

401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 213 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 88 SYS013 A2.02 - Engineered Safety Features Actuation System (ESFAS) 88 A Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based Ability 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)

Excess steam demand .............................................

Given the following Unit 1 conditions:

Initial conditions:

Reactor tripped at 0600 AFIS header B initiated 1A S/G pressure = 800 psig and slowly decreasing ES 1 & 2 actuated RB pressure = 2 psig and increasing Core SCM = 0º F Rule 2 (Loss of SCM) is in progress Current conditions:

Time = 0608 Core SCM = 15º F Rule 5 is complete EHT Tab has been initiated Tcold = 460º F Pressurizer level = 136 slowly increasing RCS makeup flow = 130 gpm

1) Rule 8 (PTS) ____(1)____ required to be initiated.

2) In accordance with the EHT Tab, the ____ (2) ____ Tab will be initiated.

At 0608, which ONE of the following completes the statements above?

A. 1. is

2. FCD B. 1. is

2. LOCA CD C. 1. is NOT

2. FCD D. 1. is NOT

2. LOCA CD Wednesday, April 01, 2015 Page 214 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 88 88 A General Discussion Answer A Discussion First part is correct because HPI operated in the injection mode with no RCPs operating.

Second part is correct since required makeup flow is < RCS normal makeup capability Answer B Discussion 1st part is correct. Rule 8 (PTS) is required if HPI operated in the injection mode while no RCPs were operating or a cooldown <400 degrees F at >100 degrees F/hr occurred.

2nd part is incorrect but plausible since it can be made correct by changing the value of makeup flow to > 160 gpm which is normal makeup capability.

Answer C Discussion First part is incorrect because HPI operated in the injection mode with no RCPs operating. Second part is incorrect, but is plausible Second part is correct since required makeup flow is < RCS normal makeup capability Answer D Discussion First part is incorrect because HPI operated in the injection mode with no RCPs operating. Second part is incorrect, but is plausible 2nd part is incorrect but plausible since it can be made correct by changing the value of makeup flow to > 160 gpm which is normal makeup capability.

Basis for meeting the KA The question matches the KA by requiring knowledge of the impact of an excessive steam demand event and the procedures used to adress the event.

Basis for Hi Cog Basis for SRO only The question is SRO only because it requires the ability to evaluate plant conditions and make a procedure selection in the EOP accordingly.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK ILT43 (Q 79) NRC Exam Development References Student References Provided EHT Tab ILT43 Q79 EAP-EHT Pg 7 SYS013 A2.02 - Engineered Safety Features Actuation System (ESFAS)

Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based Ability 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)

Excess steam demand .............................................

401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 215 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 89 SYS026 A2.08 - Containment Spray System (CSS) 89 B Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; 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)

Safe securing of containment spray when it can be done) ...............

Given the following Unit 1 conditions:

Time = 0800 Reactor power = 100%

LOCA occurs Time = 0815 RB pressure peaks at 12 psig Building Spray pump 1B fails to start Time = 0830 LOCA CD tab is in progress RB pressure = 8 psig decreasing

1) The operating BS train ____(1)____ meet the minimum requirement for Iodine removal assumed in the safety analysis for this accident.

2) At 0830, RB pressure ____(2)____ meet the criteria to secure Reactor Building Spray pumps.

Which ONE of the following completes the above statements?

A. 1. does

2. does B. 1. does

2. does NOT C. 1. does NOT

2. does D. 1. does NOT

2. does NOT Wednesday, April 01, 2015 Page 216 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 89 89 B General Discussion Answer A Discussion 1st part is correct. Per TS3.6.5 bases, one train of BS is credited for Iodine removal following a LOCA.

2nd part is incorrect because during a LOCA (in the LOCA CD tab) RB pressure is required to be < 3 psig to secure RB spray pumps. It is plausible because if RB spray were initiated by a steam line break, it would be correct (criteria in the EHT tab is RB pressure < 10 psig).

Answer B Discussion 1st part is correct. Per TS3.6.5 bases, one train of BS is credited for Iodine removal following a LOCA.

2nd part is correct. RB pressure is required to be < 3 psig to secure RB spray.

Answer C Discussion 1st part is incorrect because one train does meet the safety analysis criteria for Iodine removal during a LOCA. It is plausible because in mode 1, 2 BS trains are required to be "operable" and for this event, 2 RBC trains are required to mitigate the containment pressure increase. Building Spray and Reactor Building Cooling are combined in TS 3.6.5.

2nd part is incorrect because during a LOCA (in the LOCA CD tab) RB pressure is required to be < 3 psig to secure RB spray pumps. It is plausible because if RB spray were initiated by a steam line break, it would be correct (criteria in the EHT tab is RB pressure < 10 psig).

Answer D Discussion 1st part is incorrect because one train does meet the safety analysis criteria for Iodine removal during a LOCA. It is plausible because in mode 1, 2 BS trains are required to be "operable" and for this event, 2 RBC trains are required to mitigate the containment pressure increase. Building Spray and Reactor Building Cooling are combined in TS 3.6.5.

2nd part is correct. RB pressure is required to be < 3 psig to secure RB spray.

Basis for meeting the KA This question matches the KA by requiring knowledge of the criteria for securing RBS pumps, how the criteria is different depending on the reason for the RB pressure and the procedures that contain the criteria.

Basis for Hi Cog Basis for SRO only This question is SRO only because it requires:

1) procedure knowledge beyond that of major mitigation strategies (when to secure BS pumps).

2) bases for accident analysis Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided LOCA CD Tab Step 29 EHT Tab Step 48 TS 3.6.5 B PNS-BS Obj: R1, R11 EAP EHT Pg 23 SYS026 A2.08 - Containment Spray System (CSS)

Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; 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)

Wednesday, April 01, 2015 Page 217 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 89 Safe securing of containment spray when it can be done) ...............

89 B 401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 218 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 90 SYS103 2.2.38 - Containment System 90 B SYS103 GENERIC Knowledge of conditions and limitations in the facility license. (CFR: 41.7 / 41.10 / 43.1 / 45.13)

Unit 1 plant conditions:

Reactor startup is in progress Reactor in MODE 3 1LPSW-1061 (RB AUX COOLERS RETURN BLOCK) is declared INOPERABLE and is deactivated to satisfy TS 3.6.3 (Containment Isolation Valves) Condition A

1) The Unit 1 startup ____(1)____ continue into MODE 2.

2) If administrative controls are established to open 1LPSW-1061, the time that it is allowed to be open ____(2)____ limited to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A. 1. may

2. is B. 1. may

2. is NOT C. 1. may NOT

2. is D. 1. may NOT

2. is NOT Wednesday, April 01, 2015 Page 219 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 90 90 B General Discussion Answer A Discussion 1st part is correct. Since TS 3.6.3 allows for unlimited operation once the Required Action is satisfied entry into MODE 2 is allowed. LCO 3.0.4 states that:

When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time.

Since continued operation is allowed, Mode change is allowed 2nd part is incorrect. When under administrative controls, the time that 1LPSW-1061 is open is not limited to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . It is plausible because if administrative controls were not in place , the required action for condition A would have to be completed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Answer B Discussion 1st part is correct. Since TS 3.6.3 allows for unlimited operation once the Required Action is satisfied entry into MODE 2 is allowed. LCO 3.0.4 states that:

When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time.

Since continued operation is allowed, Mode change is allowed 2nd part is correct. The amplifying note allows "intermittent" operation which is not limited to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ..

Answer C Discussion 1st part is incorrect because the startup may continue to Mode 2. It is plausible because there is not a note saying LCO 3.0.4 does not apply.

2nd part is incorrect. When under adminestrative controls, the time that 1LPSW-1061 is open is not limited to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . It is plausible because if adminestrative controls were not in place , the required action for condition A would have to be completed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Answer D Discussion 1st part is incorrect because the startup may continue to Mode 2. It is plausible because there is not a note saying LCO 3.0.4 does not apply.

2nd part is correct. The amplifying note allows "intermittent" operation which is not limited to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Basis for meeting the KA This question matches the KA by requiring knowledge of how an inoperable containment isolation valve (containment) affects the condition and limitation of the plant license (TS).

Basis for Hi Cog Basis for SRO only This question is SRO only because it requires knowledge of the TS Bases to analyze plant conditions in order to deterime required actions and requires application of the generic rules of TS per section 3.0.

Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided TS 3.6.3 TS 3.6.3 TS 3.6.3 B LCO 3.0.4 Wednesday, April 01, 2015 Page 220 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 90 SYS103 2.2.38 - Containment System 90 B SYS103 GENERIC Knowledge of conditions and limitations in the facility license. (CFR: 41.7 / 41.10 / 43.1 / 45.13) 401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 221 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 91 SYS011 A2.11 - Pressurizer Level Control System (PZR LCS) 91 D Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; 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)

Failure of PZR level instrument - low ...............................

Given the following Unit 1 conditions:

Initial conditions:

Time 0600 Reactor power = 100%

Pressurizer (PZR) Level 3 selected SASS in MANUAL ICCM Train "1B" experiences a total loss of power

1) Due to the loss of power, 1HP-120 will __ (1) __.

2) If power cannot be restored, TS 3.3.8 (Post Accident Monitoring Instrumentation)

__ (2) __require a shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A. 1. close

2. does B. 1. close

2. does NOT C. 1. open

2. does D. 1. open

2. does NOT Wednesday, April 01, 2015 Page 222 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 91 91 D General Discussion Answer A Discussion 1st part is incorrect. ICCM Train "A" feeds Pzr level 1 and 2. Train B feeds Pzr level 3. A loss of power to 1B ICCM Train will cause Pzr Level 3 to fail low and cause 1HP-120 to fully open. It is plausible because if power were lost to 1HP-120, it could be correct. Air operated valves failure position on a loss of power typically occur because air is vented off. Numerous valves in the HPI system (5, 6 & 21) fail closed if air pressure to the valve goes away.

2nd part is incorrect because TS 3.3.8 will not require a shutdown. It is plausible because if the applicant goes directly to the Table in TS 3.3.8 for Pzr level, it states that 2 channels are required. If 2 channels are not available, it directs you to condition H. Condition H requires a shutdown to M-3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months if the condition cannot be corrected (2 trains are required and Level 3 (ICCM Tr B) is one of those trains).

Answer B Discussion 1st part is incorrect. ICCM Train "A" feeds Pzr level 1 and 2. Train B feeds Pzr level 3. A loss of power to 1B ICCM Train will cause Pzr Level 3 to fail low and cause 1HP-120 to fully open. It is plausible because if power were lost to 1HP-120, it could be correct. Air operated valves failure position on a loss of power typically occur because air is vented off. Numerous valves in the HPI system (5, 6 & 21) fail closed if air pressure to the valve goes away.

2nd part is correct. TS 3.3.8 Condition A applies which allows 30 days to restore to operable status. Unless both channels are inoperable, you do not reference the table 3.3.8-1.

Answer C Discussion 1st part is correct because Pzr level 3 fails low, causing 1HP-120 to open in response.

2nd part is incorrect because TS 3.3.8 will not require a shutdown. It is plausible because if the applicant goes directly to the Table in TS 3.3.8 for Pzr level, it states that 2 channels are required. If 2 channels are not available, it directs you to condition H. Condition H requires a shutdown to M-3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months if the condition cannot be corrected (2 trains are required and Level 3 (ICCM Tr B) is one of those trains).

Answer D Discussion 1st part is correct because Pzr level 3 fails low, causing 1HP-120 to open in response 2nd part is correct. TS 3.3.8 Condition A applies which allows 30 days to restore to operable status. Unless both channels are inoperable, you do not reference the table 3.3.8-1.

Basis for meeting the KA This question matches the KA by requiring knowledge of the impact of Pzr level indication failing low on system operation.

Basis for Hi Cog Basis for SRO only The question is SRO only because it requires knowledge of TS bases and information "below the line".

Job Level Cognitive Level QuestionType Question Source SRO Comprehension NEW Development References Student References Provided PNS-PZR Pg 30 TS 3.3.8 TS 3.3.8 TS 3.3.8 B Pzr Instrument Dwg SYS011 A2.11 - Pressurizer Level Control System (PZR LCS)

Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; 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)

Failure of PZR level instrument - low ...............................

Wednesday, April 01, 2015 Page 223 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 91 401-9 Comments: Remarks/Status 91 D Wednesday, April 01, 2015 Page 224 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 92 SYS014 A2.06 - Rod Position Indication System (RPIS) 92 A Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those 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)

Loss of LVDT ...................................................

Given the following Unit 1 conditions:

Time = 1200 Reactor power = 100%

Relative Position Indication (RPI) inoperable for ALL Control Rods Time = 1230 Absolute Position Indication (API) inoperable for Group 1 Rod 7 Control Rod Current Conditions:

Tech Spec 3.1.4 Required Action A.2.1.1 (SDM Verification) has just been completed and shutdown margin requirements of the COLR have been determined to be NOT met Which ONE of the following:

1) is the LATEST time that Group 1 Rod 7 Control Rod must be declared inoperable in accordance with Tech Specs?

2) should be used to restore shutdown margin requirements in accordance with Tech Spec bases?

A. 1. 1230

2. CBAST and BWST ONLY B. 1. 1230

2. CBAST, BWST and A BHUT C. 1. 1330

2. CBAST and BWST ONLY D. 1. 1330

2. CBAST, BWST and A BHUT Wednesday, April 01, 2015 Page 225 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 92 92 A General Discussion Answer A Discussion 1st part is correct. TS 3.1.7 required declaring a rod with no operable position indication inoperable immediately (1230).

2nd part is correct. The basis of TS 3.1.7 says that if borating to restore SDM, the boration should occur IAW guidance in basis of TS 3.1.1 (SDM). The basis of TS 3.1.1 says the boration should occur from a highly borated source of water such as CBAST or BWST.

Answer B Discussion 1st part is correct. TS 3.1.7 required declaring a rod with no operable position indication inoperable immediately (1230).

Second part is incorrect because the TS bases requires a highly borated source to restore SDM. While the A BHUT is borated > the RCS (which is what makes it plausible), it is not considered a highly borated source.

Answer C Discussion 1st part is incorret because the Control Rod must be declared inoperable immediately. It is plausible becaue there are many Tech Specs that allow 1 hr as a competition time and the 1 hr CT would mean that this would still be a required memory item.

2nd part is correct. The basis of TS 3.1.7 says that if borating to restore SDM, the boration should occur IAW guidance in basis of TS 3.1.1 (SDM). The basis of TS 3.1.1 says the boration should occur from a highly borated source of water such as CBAST or BWST.

Answer D Discussion 1st part is incorret because the Control Rod must be declared inoperable immediately. It is plausible becaue there are many Tech Specs that allow 1 hr as a competition time and the 1 hr CT would mean that this would still be a required memory item.

Second part is incorrect because the TS bases requires a highly borated source to restore SDM. While the A BHUT is borated > the RCS (which is what makes it plausible), it is not considered a highly borated source.

Basis for meeting the KA Chief agreed that since we do not have LVDT's that question that asked about a loss of one of the CR position indication systems impact on the other one would meet KA.

Requires predicting the impact of inoperable RPIS (declaring the control rod inoperable) and using procedures to mitigate the consequences (restoring SDM).

Basis for Hi Cog Basis for SRO only This question requires assessing plant conditions and selecting a boration source to restore shutdown margin that discussed in the TS bases and is beyond system knowledge. Knowing which boration choices are available to use will aid in making the correct procedure selection.

Job Level Cognitive Level QuestionType Question Source SRO Memory BANK ILT44 Q92 Development References Student References Provided Admin-ITS TS 3.1.4 TS 3.1.7 TS 3.1.1 B ILT44 Q92 SYS014 A2.06 - Rod Position Indication System (RPIS)

Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those 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)

Loss of LVDT ...................................................

Wednesday, April 01, 2015 Page 226 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 92 401-9 Comments: Remarks/Status 92 A Wednesday, April 01, 2015 Page 227 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 93 SYS035 2.2.22 - Steam Generator System (S/GS) 93 B SYS035 GENERIC Knowledge of limiting conditions for operations and safety limits. (CFR: 41.5 / 43.2 / 45.2)

Unit 1 plant conditions:

Reactor power = 100%

A SGTL occurs on the 1A SG AP/31 (Primary to Secondary Leakage) is initiated

1) While in AP/31, EOP Enclosure 5.5 __(1)__ allowed to be utilized to maintain Pressurizer at desired level.

2) The Tech Spec limit on primary to secondary leakage is that amount assumed in the safety analysis for a ____(2)____ which will ensure that dose consequences are less than the limits defined in 10 CFR 100.

Which ONE of the following completes the statements above?

A. 1. is

2. Reactor Trip from 100 percent power B. 1. is

2. Steam Line Break C. 1. is NOT

2. Reactor Trip from 100 percent power D. 1. is NOT

2. Steam Line Break Wednesday, April 01, 2015 Page 228 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 93 93 B General Discussion Answer A Discussion 1st part is correct since OMP 1-18 says it can be used during abnormal events.

2nd part is incorrect because the leak rate limit (150 gpd/SG) is part of the analysis for a steam line break accident. It is plausible because on a trip from 100% power, the steam generator saftey valve will lift, releasing steam to the atmosphere.

Answer B Discussion 1st part is correct since OMP 1-18 says it can be used during abnormal events.

2nd part is correct. Per TS 3.4.13 Bases, 150 gpd/SG leak rate is assumed as an initial conditions for a steam line break accident.

Answer C Discussion 1st part is incorrect. Plausible since this is an enclosure from the EOP and the EOP entry conditions are not met.

2nd part is incorrect because the leak rate limit (150 gpd/SG) is part of the analysis for a steam line break accident. It is plausible because on a trip from 100% power, the steam generator saftey valve will lift, releasing steam to the atmosphere.

Answer D Discussion 1st part is incorrect. Plausible since this is an enclosure from the EOP and the EOP entry conditions are not met.

2nd part is correct. Per TS 3.4.13 Bases, 150 gpd/SG leak rate is assumed as an initial conditions for a steam line break accident.

Basis for meeting the KA This question matches the KA by requiring knowledge of bases for the limit associated with leakage through the SG tubes.

Basis for Hi Cog Basis for SRO only This question is SRO only because:

1) It requires knowledge of the bases for TS limitations (RCS leakage)

2) It requires the ability to assess plant conditions and select a procedure to mitigate the event.

Job Level Cognitive Level QuestionType Question Source SRO Memory NEW Development References Student References Provided AP/31 TS 3.4.13 B OMP 1-18 SRO Only Guidance SYS035 2.2.22 - Steam Generator System (S/GS)

SYS035 GENERIC Knowledge of limiting conditions for operations and safety limits. (CFR: 41.5 / 43.2 / 45.2) 401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 229 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 94 GEN2.1 2.1.40 - GENERIC - Conduct of Operations 94 B Conduct of Operations Knowledge of refueling administrative requirements. (CFR: 41.10 / 43.5 / 45.13)

Given the following Unit 3 conditions:

Shutdown for refueling in progress Reactor in MODE 4 Component Handling in progress in the Spent Fuel Pool A fuel assembly is currently in the mast and being moved 3RIA-6 (SFP Area Monitor) shows an observable increase, approximately one half (1/2) decade above background 3SA-8/B-9 (RM Process Monitor Radiation High) in alarm due to 3RIA-32 Auxiliary Building Gas Monitor Spent Fuel Pool level = minus (-) 2.7 feet decreasing Enter __(1)__ to mitigate the event and the required Technical Specification entry and basis is __(2)__.

Which ONE of the following completes the statement above?

A. 1. AP/35 (Loss of SFP Cooling and/or Level)

2. TS 3.10.1 (SSF) - Ensures the RC Makeup pump can maintain all three Oconee Units in MODE 3 for a minimum of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. 1. AP/35 (Loss of SFP Cooling and/or Level)

2. TS 3.7.11 (Spent Fuel Pool Water Level) - Ensures adequate iodine removal during a fuel handling accident C. 1. AP/18 (Abnormal Release of Radioactivity)

2. TS 3.10.1 (SSF) - Ensures the RC Makeup pump can maintain all three Oconee Units in MODE 3 for a minimum of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months D. 1. AP/18 (Abnormal Release of Radioactivity)

2. TS 3.7.11 (Spent Fuel Pool Water Level) - Ensures adequate iodine removal during a fuel handling accident Wednesday, April 01, 2015 Page 230 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 94 94 B General Discussion Answer A Discussion 1st part is correct. Entry conditions for AP/35 are met and this will address the lowering fuel pool level.

2nd part is incorect because the bases is to ensure adequate iodine removal. It is plausible because it applies to makeup inventory.

Answer B Discussion 1st part is correct. Entry conditions for AP/35 are met and this will address the lowering fuel pool level.

2nd part is correct. This is the bases for SFP water level during a fuel handling accident.

Answer C Discussion 1st part is incorrect because AP-35 is a higher priority. Plausible because a valid alarm on RIA-32 is an entry condition for AP/18, but AP/35 is a higher priority and the procedure used to mitigate this event.

2nd part is correct for AP/18. It is true for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Answer D Discussion 1st part is incorrect because AP-35 is a higher priority. Plausible because a valid alarm on RIA-32 is an entry condition for AP/18, but AP/35 is a higher priority and the procedure used to mitigate this event.

2nd part is incorrect because it does not apply to AP/18. Plausible because the water does provide shielding and reduces dose rate Basis for meeting the KA The question requires knowledge of administrative (Tech Spec) requirements for fuel handling.

Basis for Hi Cog Basis for SRO only Meets 10CFR55.43(b)(2) Facility operating limitations in the technical specifications and their bases.

Job Level Cognitive Level QuestionType Question Source SRO Memory BANK ILT39 Q94 Development References Student References Provided ILT43 Q92 AP 18 AP 35 TS 3.7.11 B TS 3.10.1 B EAP-APG AP35 GEN2.1 2.1.40 - GENERIC - Conduct of Operations Conduct of Operations Knowledge of refueling administrative requirements. (CFR: 41.10 / 43.5 / 45.13) 401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 231 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 95 GEN2.1 2.1.4 - GENERIC - Conduct of Operations 95 B Conduct of Operations Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc. (CFR: 41.10 / 43.2)

Given the following Unit 1 conditions:

Initial conditions:

All 3 Units reactor power = 100%

1SA-3/B6 (FIRE ALARM) actuated AO's dispatched to the Turbine Building 3rd Floor (1TA and 1TB area)

Current conditions:

AO 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) In accordance with SLC 16.13.1 (Minimum Station Staffing Requirements), an SRO

__ (2) __ required to serve as the fire brigade leader.

Which ONE of the following completes the statements above?

A. 1. can

2. is B. 1. can

2. is NOT C. 1. can NOT

2. is D. 1. can NOT

2. is NOT Wednesday, April 01, 2015 Page 232 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 95 95 B General Discussion Answer A Discussion 1st part is correct. In accordance with the "Fire Plan" a water fog can be used to fight this fire.

2nd part is incorrect because an SRO is NOT required to serve as Fire Brigade Leader. It is plausible since under normal conditions an SRO is the Fire Brigade leader.

Answer B Discussion 1st part is corect. In accordance with the "Fire Plan" a water fog can be used to fight this fire.

2nd part is correct. In accordance with SLC 16.13.1 an SRO or a quilified NEO can be the Fire Brigade Leader.

Answer C Discussion 1st part is incorrect because a fog can be used. It is plausible because a water stream cannot be used on this fire.

2nd part is incorrect because an SRO is NOT required to serve as Fire Brigade Leader. It is plausible since under normal conditions an SRO is the Fire Brigade leader.

Answer D Discussion 1st part is incorrect because a fog can be used. It is plausible because a water stream cannot be used on this fire.

2nd part is correct. In accordance with SLC 16.13.1 an SRO or a quilified NEO can be the Fire Brigade Leader.

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 (when a water fog can be used).

The bases of SLC 16.13.1 regarding who can serve as fire brigade leader.

Job Level Cognitive Level QuestionType Question Source SRO Memory BANK ILT42 (Q99) NRC Exam Development References Student References Provided Fire plan SLC 16.13.1 ILT42 Q99 GEN2.1 2.1.4 - GENERIC - Conduct of Operations Conduct of Operations Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc. (CFR: 41.10 / 43.2) 401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 233 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 96 GEN2.2 2.2.11 - GENERIC - Equipment Control 96 C 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) An on-line temporary design change is required to have a plan that specifies removal of the change within __ (1) __ year(s) from installation.

2) The Operational Control Group (Operations) __ (2) __ responsible for maintaining a log of installed changes.

Which ONE of the following completes the statements above?

A. 1. 3

2. is B. 1. 3

2. is NOT C. 1. 1

2. is D. 1. 1

2. is NOT Wednesday, April 01, 2015 Page 234 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 96 96 C General Discussion Answer A Discussion Incorrect. First part is plausible because 3 years is the time allowed for an equivalent change to expire. Second part is correct.

Answer B Discussion Incorrect. First part is plausible because 3 years is the time allowed for an equivalent change to expireSecond part is plausible the process is "owned" by engineering.

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 the process is "owned" by engineering.

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 This question is SRO only because it requires knowledge of facility licensee procedures required to obtain authority for design and operating changes in the facility.

Job Level Cognitive Level QuestionType Question Source SRO Memory BANK ILT42 (Q95) NRC Exam Development References Student References Provided ADM-SD Pg 17 NSD-301 Pg 17 & 31 ILT42 Q95 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: Remarks/Status Wednesday, April 01, 2015 Page 235 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 97 GEN2.2 2.2.23 - GENERIC - Equipment Control 97 C Equipment Control Ability to track Technical Specification limiting conditions for operations. (CFR: 41.10 / 43.2 / 45.13)

Given the following Unit 3 conditions:

Time = 1100 3KVIA panelboard de-energized Current conditions:

Time = 1200 DC panelboard 3DIB is de-energized

1) Tech Spec 3.8.8 requires that you __(1)__.

2) KVIA AND KVIB have shorter completion times than KVIC and KVID because they

__(2)__.

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A. 1. restore 3KVIA by 1500 and 3KVIB by 1600

2. are the source of power for the ES Digital Channels B. 1. restore 3KVIA by 1500 and 3KVIB by 1600

2. provide power for SK and SL breakers protective relaying C. 1. enter LCO 3.0.3 immediately

2. are the source of power for the ES Digital Channels D. 1. enter LCO 3.0.3 immediately

2. provide power for SK and SL breakers protective relaying Wednesday, April 01, 2015 Page 236 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 97 97 C General Discussion Answer A Discussion Incorrect: First part is plausible since Condition F is entered if either KVIA or KVIB is inoperable and has a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months completion time for either panelboard therefore it would be plausible to determine that 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to restore the panelboards would be allowed.

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 1s 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 3DIB is de-energized then 3KVIB would also de-energize.

With both 3KVIA and 3KVIB 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 deenergized.

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

Basis for meeting the KA 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 Requires applying the generic LCO 3.0.3 rule to a situation where there are insufficient TS Conditions to cover all inoperabilitys that exist. This requirement is unique to the SRO position Job Level Cognitive Level QuestionType Question Source SRO Comprehension BANK 2010A (Q 80) NRC Exam Development References Student References Provided EL VPC Pg 24 TS 3.8.8 TS 3.8.8 TS 3.8.8 B 2010A Q80 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: Remarks/Status Wednesday, April 01, 2015 Page 237 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 97 97 C Wednesday, April 01, 2015 Page 238 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 98 GEN2.3 2.3.14 - GENERIC - Radiation Control 98 A Radiation Control Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12 /

43.4 / 45.10)

Given the following Unit 1 conditions:

Initial conditions:

EOP Enclosure 5.12 (ECCS Suction Swap to RBES) in progress Current conditions:

The step to open 1HP-939 and 1HP-940 has just been completed

1) These valves direct HPI flow to the __ (1) __.

2) In accordance with the bases of SLC 16.6.12 (Additional HPI Requirements) this flow path is established to prevent __ (2) __.

Which ONE of the following completes the statements above?

A. 1. RBES

2. elevated dose rates in the Auxiliary Building B. 1. RBES

2. Boron precipitation in the core C. 1. LDST

2. elevated dose rates in the Auxiliary Building D. 1. LDST

2. HPI pump damage due to flow below minimum Wednesday, April 01, 2015 Page 239 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 98 98 A General Discussion Answer A Discussion Correct. 1HP-939/940 provide a flow path from the LDST outlet to the RBES. These valves are opened to prevent the HPI pump recirc flow during piggyback from causing HPI relief valves from opening. If opened this would cause high dose rates in the AB.

Answer B Discussion Incorrect. First part is correct. Second part is plausible a flow path to the RBES is aligned to provide for post LOCA Boron Dilution. However this is not the correct flow path.

Answer C Discussion Incorrect. Plausible if the candidate has the misconception that the valves are used to ensure an HPI pump recirc flow path back to the LDST.

Second part is correct.

Answer D Discussion Incorrect. Plausible if the candidate has the misconception that the valves are used to ensure an HPI pump recir flow path back to the LDST.

Second part is plausible because the candidate could have the misconception that these valves ensured HPI pump minimum flow was established. Also they do allow the minimum flow path to stay aligned during piggy back operation.

Basis for meeting the KA Question requires knowledge of radation hazards that can occur during a SBLOCA and how it is prevented.

Basis for Hi Cog Basis for SRO only This question requires knowledge from the basis of SLC 16.6.12 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 Memory BANK ILT41 (Q97) NRC Exam Development References Student References Provided PNS-HPI Pg 37, 38 SLC 16.6.12 EOP Encl. 5.12 ILT41 Q97 GEN2.3 2.3.14 - GENERIC - Radiation Control Radiation Control Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12 /

43.4 / 45.10) 401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 240 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 99 GEN2.4 2.4.19 - GENERIC - Emergency Procedures / Plan 99 B Emergency Procedures / Plan Knowledge of EOP layout, symbols, and icons. (CFR: 41.10 / 45.13)

Given the following Unit 1 conditions:

Time = 0400 Reactor has tripped Subsequent Actions tab in progress RCS pressure = 2150 psig stable RCS temperature = 547°F stable Time = 0405 While at step 4.13 of the SA tab (checking for indications of a SGTR) the following occurs:

o 1SA-18/D-6 (RC System Approaching Saturation Conditions) actuates o 1SA-8/B-9 (Process Monitor Radiation High) actuates o Pzr level = 0 inches o RBNS level increases off scale high o RCS pressure 1330 psig slowly decreasing o A loop SCM = 0°F o B loop SCM = 18°F slowly decreasing o Core SCM = 18°F slowly decreasing

1) At 0405, the Procedure Director will GO TO the LOSCM tab based on a Parallel Actions page transfer ___(1)___

2) After the transfer to the LOSCM tab is made, a subsequent ___(2)___ will require a transfer to a different EOP tab.

Which ONE of the following completes the statement above?

A. 1. immediately

2. Turbine Building Flood B. 1. immediately

2. Blackout C. 1. ONLY when Core SCM reaches 0°F

2. Turbine Building Flood D. 1. ONLY when Core SCM reaches 0°F

2. Blackout Wednesday, April 01, 2015 Page 241 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 99 99 B General Discussion Answer A Discussion First part is correct.

Second part is plausible because the candidate could have the misconception that TBF tab is a higher priority because drastic action are taken in TBF tab due to the imminent loss of important plant equipment.

Answer B Discussion Correct. Per EAP-EOP lesson plan:

...anytime plant conditions have changed, the Procedure Director will use the Parallel Actions page to determine where to go within the EOP to address the changes. Parallel actions transfers are made in order of priority of symptoms. TBF is a higher priority than LOSCM.

Answer C Discussion First part is plausible because there is a EOP PA page transfer that is based on Core SCM only. That is the transfer to the ICC tab when core SCM indicates superheated.

Second part is plausible because the candidate could have the misconception that TBF tab is a higher priority because drastic action are taken in TBF tab due to the imminent loss of important plant equipment.

Answer D Discussion First part is plausible because there is a EOP PA page transfer that is based on Core SCM only. That is the transfer to the ICC tab when core SCM indicates superheated.

Second part is correct.

Basis for meeting the KA Requires knowledge of the layout of the EOP. Specifically how the Parllell actions pages are laid out and how they are used.

Basis for Hi Cog Basis for SRO only

1. Per SRO guidance document, Knowledge of dignoastic steps and decision points in the EOP that involve transigtions to event specific sections of the EOP. The concept of the parallel actions transfer page is NOT used in AP's and is therefore SRO only.

2. Knowledge of the transfers using Parallel Actions is an SRO ONLY objective (R31) in the Generic EOP lesson plan.

Job Level Cognitive Level QuestionType Question Source SRO Memory BANK ILT45 Q99 Development References Student References Provided ILT45 Q99 EAP-EOP EOP SA LOSCM PA Page GEN2.4 2.4.19 - GENERIC - Emergency Procedures / Plan Emergency Procedures / Plan Knowledge of EOP layout, symbols, and icons. (CFR: 41.10 / 45.13) 401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 242 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 100 GEN2.4 2.4.43 - GENERIC - Emergency Procedures / Plan 100 B Emergency Procedures / Plan Knowledge of emergency communications systems and techniques. (CFR: 41.10 / 45.13)

Given the following plant conditions:

Time = 1200 Security Supervisor reports intruders have forced their way through the Vehicle Access Point (Security Point 1) near the complex using various weapons and have been seen heading towards the 525kv Switchyard Time = 1205 Security Supervisor reports intruders and their weapons are in the 525kvSwitchyard AND the 230kv Switchyard Without using the Emergency Coordinator Judgment option, which ONE of the following:

1) states the EAL classification required by the conditions at Time = 1205?

2) is the correct notification code to activate the Emergency Response Organization (ERO) per RP/0/A/1000/002 (Control Room Emergency Coordinator Procedure)?

REFERENCE PROVIDED A. 1. Alert

2. E2a B. 1. Alert

2. E2f C. 1. Site Area Emergency

2. E3a D. 1. Site Area Emergency

2. E3f Wednesday, April 01, 2015 Page 243 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 100 100 B General Discussion Answer A Discussion 1st part is correct. This event would be classified as an alert per RP 1000 001 Enclosure 4.6.

2nd part is incorrect because the correct notification code is E2f. It is plausible because for any other event that would require activation of the ERO, it would be correct. In RP 1000 002, step 2.2 it states that IF a security event is in progess, then GO TO step 4. This is correct. IF the applicant performs step 2.3, they will determine E2a as the notification code.

Answer B Discussion 1st part is correct. This event would be classified as an alert per RP 1000 001 Enclosure 4.6.

2nd part is correct per enclosure 4.11.

Answer C Discussion 1st part is incorrect because the event would be classified as an Alert. It is plausible because the 230 kv switchyard does contain Safety Related equipment (the Yellow Bus) it would therefore be reasonable to believe it would be considered inside the protected area (especially since the 230kv SWYD has a fence around it).

2nd part is incorrect because the correct notification code is E2f. It is plausible because for any other SAE that would require activation of the ERO, it would be correct. In RP 1000 002, step 2.2 it states that IF a security event is in progess, then GO TO step 4. This is correct. IF the applicant performs step 2.3, they will determine E3a as the notification code.

Answer D Discussion 1st part is incorrect because the event would be classified as an Alert. It is plausible because the 230 kv switchyard does contain Safety Related equipment (the Yellow Bus) it would therefore be reasonable to believe it would be considered inside the protected area (especially since the 230kv SWYD has a fence around it).

2nd part is incorrect because it should be E2f. It is plausible because if it were a SAE, it would be correct.

Basis for meeting the KA Requires knowledge of and ability to use correct communication techniques (determine notification code).

Basis for Hi Cog Basis for SRO only Requires EAL determinations and ERO notification codes which are activities performed by SROs.

Job Level Cognitive Level QuestionType Question Source SRO Memory MODIFIED ILT40 Q100 Development References Student References Provided ILT40 Q100 RP 1000 001 RP 1000 001 RP 1000 002 RP 1000 002 EAP SEP GEN2.4 2.4.43 - GENERIC - Emergency Procedures / Plan Emergency Procedures / Plan Knowledge of emergency communications systems and techniques. (CFR: 41.10 / 45.13) 401-9 Comments: Remarks/Status Wednesday, April 01, 2015 Page 244 of 245

FOR REVIEW ONLY - DO NOT DISTRIBUTE ILT 47 ONS SRO NRC Examination QUESTION 100 100 B Wednesday, April 01, 2015 Page 245 of 245

ML15247A401

Text

Navigation menu

Search