Text

Initial Exam 2015-301 Draft SRO Written Exam
	ML15126A418
Person / Time
Site:	Sequoyah
Issue date:	05/06/2015
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	Download: ML15126A418 (71)
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QUESTIONS REPORT for 1503 SRO Exam

76. 015 AA2.02 076 Given the following plant conditions:

0800 - With Unit 1 at 100% power, the following annunciator alarms:

- "LS-68-53A/B REAC COOL PMP 3 OIL RESERVOIR LEVEL HI/LO,"

(1-M5B, C5)

- "RC PUMP 3 OIL COOLERS OUTLET FLOW LOW" (M27B-A, 04)

RCP #3 Lower Motor bearing temperature is 185°F and rising.

0805 - While the crew is preparing to perform a reactor shutdown, RCP #3 Lower motor bearing temperature reaches 205°F and rising.

- The reactor will NOT trip from either trip switch.

0810 - Reactor power is 10% and lowering.

RCP #3 Lower Motor bearing is 285°F and rising.

0812 - Reactor power is 4% and lowering.

RCP #3 Lower Motor bearing is 315°F and rising.

Which ONE of the following identifies (1) the earliest time that #3 RCP is to be tripped and (2) the latest time that the event is to reported to the State?

A (1) 0805 (2) 0835 B. (1) 0805 (2) 0842 C'( (1) 0812 (2) 0835 D. (1) 0812 (2) 0842 Thursday, January 15, 2015 10:30:04 AM 76

QUESTIONS REPORT for 1503 SRO Exam DISTRACTOR ANAL YS/S:

A. Incorrect, Plausible since at this time the RCP is above the temperature limit in AOP-R.04 to trip the RCP, however if the candidate does not recall that RCPs are not to be tripped while in FR-S. 1 with reactor power greater than 5% then they would choose this response. Also plausible since the time the report to the State of Tn is a maximum of 30 min from the start of the event.

B. Incorrect, Plausible since at this time the RCP is above the temperature limit in A OP-R. 04 to trip the RCP, however if the candidate does not recall that RCPs are not to be tripped while in FR-S. 1 with reactor power greater than 5% then they would choose this response. Also plausible if the candidate gets the reporting times confused and determines the 30 minutes from the time of Rx power being below the value of FR-S. 1 which is <5%.

C. Correct, In accordance with AOP-R.04, RCP ma/functions and FR-S.1 do not tum off RCPs if reactor power is above 5%. Also in accordance with EPIP-1, the event is to be classified within 15 minutes of idendification of an emergency condition and then the State is to be notified within 15 mins of making the classification. Thus RCP is not to be tripped until 0812 and the latest notification would be 0805 + 15 +

15 = 0835 D. Incorrect, Plausible since the first part is correct. Also plausible if the candidate gets the reporting times confused and determines the 30 minutes from the time of Rx power being below the value of FR-S. 1 which is <5%.

Thursday, January 15, 2015 10:30:04 AM 77

QUESTIONS REPORT for 1503 SRO Exam Question Number: 76 Tier: _1_ Group 1 KIA: 015 RCP Malfunctions AA2.02 Ability to determine and interpret the following as they apply to RCP Malfunctions:

Abnormalities in RCP air vent flow paths and/or oil cooling system.

Importance Rating: 2.8 I 3.0 10 CFR Part 55:

10CFR55.42.b: 5 KIA Match: This question matches the KIA by having the candidate determine when an RCP is required to be tripped based on a failure of the RCP oil cooling system and how that trip is be delayed if the Unit is undergoing an ATWS event.

SRO only because it requires the identification of the correct time to notify an offsite agency during periods of emergency operations.

Technical

Reference:

1-AR-M5-B rev 41 AOP-R.04 rev 27 EPIP-1 rev 51 Proposed references None to be provided:

Learning Objective: OPL271AOP-R.04 OPL271 FR-S.1 OPL271REP Question Source:

New X Modified Bank Bank Question History: New question written for 1503 ILT exam Comments:

Thursday, January 15, 2015 10:30:04 AM 78

QUESTIONS REPORT for 1503 SRO Exam

77. 022AG2.l.7077 Given the following plant conditions:

Unit 1 is at 75% power.

- The 1A-A CCP is OOS for maintenance.

Subsequently the 1B-B CCP trips.

- The following indications are reported:

PZR level is 40% and slowly lowering

- Tave is on program and stable RCP lower bearing and seal water temperatures are 150°F and stable Which ONE of the following completes the statements below?

In accordance with OPDP-8, "Operability Determination Process and Limiting Conditions for Operation Tracking," the Immediate Determination of Operability (IDO) forthe 1B-B CCP, (1) be made by an Off-shift SRO.

In accordance with AOP-M.09, "Loss of Charging," step 22. "Monitor if reactor trip is needed:" the reactor (2) required to be tripped at this time.

A. (1) can NOT (2) is NOT B'!"' (1) can NOT (2) is C. (1) can (2) is NOT D. (1) can (2) is Thursday, January 15, 2015 10:39:23 AM 77

QUESTIONS REPORT for 1503 SRO Exam DISTRACTOR ANALYSIS:,

A. Incorrect, Plausible because the first part is correct. Also plausible if the candidate does not recognize that PZR level is > 10% lower than program which in accordance with AOP-M.09, requires the plant to be manually tripped.

B. Correct, In accordance with OPDP-8, any Immediate Operability Determinations are required to made by an On-shift SRO. Also, in accordance with AOP-M.9, with PZR level> 10% below program (should be 51.2% for this power level), then the plant is required to be tripped.

C. Incorrect, Plausible if the candidate thinks that an Immediate Operability Determination can be performed by any SRO. (This has been done previously).

However in accordance with OPDP-8, this can only be done by an On-shift SRO.

Also plausible if the candidate does not recognize that PZR level is > 10% lower than program which in accordance with AOP-M.09, requires the plant to be manually tripped.

D. Incorrect, Plausible if the candidate thinks that an Immediate Operability Determination can be performed by any SRO. (This has been done previously).

However in accordance with OPDP-8, this can only be done by an On-shift SRO.

Also plausible since the second part is correct.

Thursday, January 15, 2015 10:39:24 AM 78

QUESTIONS REPORT for 1503 SRO Exam Question Number: 77 Tier: _1__ Group 1 KIA: 022 Loss of Reactor Coolant Makeup AG2.1. 7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Importance Rating: 4.4 I 4.7 10 CFR Part 55: 41.5 10CFR55.43.b: 5 KIA Match: This question matches the KIA by having the candidate evaluate plant conditions and make an operational judgement as to whether continued plant operation is allowed.

SRO only because it requires detailed knowledge of the procedure actions which will require a plant trip for the event in progress and because its an SRO only responsibility to make operability determinations during plant operation.

Technical

Reference:

AOP-M.09, Loss of Charging, Rev 5 OPDP-8, Operability Determination Process and Limiting Conditions for Operation Tracking, rev 0017 Proposed references None to be provided:

Learning Objective: OPL271AOP-M.09 Question Source:

New X Modified Bank Bank Question History: New question written for 1503 ILT exam Comments: 2013 SON OE (PER 754965)

Thursday, January 15, 2015 10:43:52 AM 79

QUESTIONS REPORT for 1503 SRO Exam

78. 029 G2.2.38 078 Given the following plant conditions:

Unit 1 is operating at 100% power.

1000 - Both Reactor Trip Breakers are INOPERABLE.

- SSPS remains OPERABLE.

1045 - A valid reactor trip signal is generated and neither of the Reactor Trip Breakers will open from the MCR.

1050 - AUO reports ALL Reactor Trip and Bypass Breakers open and both CROM MG Set output breakers are open.

In accordance with Technical Specifications, which ONE of the following completes the statements below?

The BASES of LCO 3.0.3 allowing up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months "to initiate action to place the unit in MODE 3" is to (1)

After the Unit enters Mode 3, the conditions (2)

REFERENCE PROVIDED A"I (1) prepare for an orderly shutdown before initiating a change in unit operation (2) allow the unit to remain in Mode 3 indefinitely B. (1) prepare for an orderly shutdown before initiating a change in unit operation (2) require the unit to proceed to Mode 4 C. (1) provide a time period to restore required conditions for safe operation (2) allow the unit to remain in Mode 3 indefinitely D. (1) provide a time period to restore required conditions for safe operation (2) require the unit to proceed to Mode 4 Thursday, January 15, 2015 10:46: 10 AM 78

QUESTIONS REPORT for 1503 SRO Exam D/STRACTOR ANAL YS/S:

A. Correct, The Bases for LCO 3.0.3 identifies the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months allowance is for the crew to prepare for an orderly shutdown before initiating a change in unit operation. After the reactor is tripped LCO 3.0.3 no longer applies since the RTBs are opened.

Table 3.3-1 identifies that when the RTBs are open, the LCO 3.3.1.1 action no longer applies via

With RTBs closed and Rod Control System capable of rod withdrawal for Modes 3, 4, 5" at bottom. of the table.

B. Incorrect, Plausible because the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months allowance being for the crew to prepare for an orderly shutdown before initiating a change in unit operation is correct and while LCO 3.0.3 is applicable in Modes 1-4, the condition that caused the entry is only applicable until the RTBs are open.

C. Incorrect, Plausible because it is a common misconception the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is to allow restoration of the required systems/conditions for continued operation and it is also true if the systems/conditions are restored the shutdown is not required. Also plausible because the plant can remain in Mode 3 due to conditions in LCO 3.3.1.1 no longer being applicable.

0. Incorrect, Plausible because it is a common misconception the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is to allow restoration of the required systems/conditions for continued operation and it is also true if the systems/conditions are restored the shutdown is not required. Also plausible because LCO 3.0.3 does contain action to place the plant in Mode 4 within a defined time period if the conditions remained applicable after entering Mode 3.

Thursday, January 15, 2015 10:46: 10 AM 79

QUESTIONS REPORT for 1503 SRO Exam Question Number: 78 Tier: _1_ Group: _1_

KIA: 029 Anticipated Transient Without Scram (ATWS)

EG2.2.38 Knowledge of conditions and limitations in the facility license.

Importance Rating: 3.4 / 4. 7 10 CFR Part 55: 41.10143.2143.5145.3 10CFR55.43.b: 2 KIA Match: KIA is matched because the question requires the application of Tech Spec due to equipment failures that resulted in an ATWS condition.

SRO ONLY: The question meets the requirements for SRO level question due to the application of both LCO 3.3.1.1 and LCO 3.0.3 and specifically knowledge of how 3.0.3 applies in this case.

Technical

Reference:

Unit 1 Technical Specification Proposed references LCO 3.3.1.1, table 3.3-1 with action statements redacted to be provided:

Learning Objective: OPT200.TS-APP Cognitive Level:

Higher X Lower Question Source:

New Modified Bank X Bank Question History: Farley bank question from 2007 exam modified for use on WBN 03/2013 NRC exam.

Comments: Originally 029 G2.2.40 from the 03/2013 WBN exam Thursday, January 15, 2015 10:54:48 AM 80

QUESTIONS REPORT for 1503 SRO Exam

79. 040 AG2.4.30 079 Given the following plant conditions:

Unit 1 is at 100% power, a reactor trip and safety injection occurs.

Prior to the trip, Main Steam Line 1 Rad Monitor, 1-RA-90-421, was in alarm.

- The crew is preparing to transition from E-0, "Reactor Trip or Safety Injection."

- The current conditions exist:

RCS pressure is 1550 psig and lowering slowly.

SG 1 pressure is 300 psig and lowering slowly.

SG 2, 3, and 4 pressures are 650 psig and stable.

Containment Pressure is 2.3 psig and rising slowly.

Which ONE of the following identifies; (1) the procedure transition required from E-0, and (2) based on the conditions given the EPIP event classification?

REFERENCE PROVIDED A"I (1) E-2, "Faulted Steam Generator Isolation."

(2) Alert B. (1) E-2, "Faulted Steam Generator Isolation."

(2) Site Area Emergency C. (1) E-3, "Steam Generator Tube Rupture."

(2) Alert D. (1) E-3, "Steam Generator Tube Rupture."

(2) Site Area Emergency Thursday, January 15, 2015 10:59:30 AM 79

QUESTIONS REPORT for 1503 SRO Exam DIS TRACTOR ANALYSIS:

A. Correct, The crew would transition to E-2 first due to indications of a steam line break. The E-2 transition step is prior to E-3 transition. Also per EPIP-1 the loss of RCS boundary would dictate that an Alert classification is required.

B. Incorrect, Plausible since the first part is correct, a transition to E-2 is required. Also plausible if the candidate thinks there is a faulted - ruptured SG with a release outside CNMT. This would dictate a Site Area Emergency classification. However the fault is not outside CNMT thus an Alert is the correct classification.

C. Incorrect, Plausible since entry into E-3 will be required, however E-3 will be entered after the actions of E-2 are completed. Also plausible since the second part is correct.

0. Incorrect, Plausible since entry into E-3 will be required, however E-3 will be entered after the actions of E-2 are completed.A/so plausible if the candidate thinks there is a faulted - ruptured SG with a release outside CNMT. This would dictate a Site Area Emergency classification. However the fault is not outside CNMT thus an Alert is the correct classification.

Thursday, January 15, 2015 10:59:30 AM 80

QUESTIONS REPORT for 1503 SRO Exam Question Number: 79 Tier: _1__ Group 1 KIA: 040 Steam Line Rupture - Excessive Heat Transfer AG2.4.30 Knowledge of events related to system operations/status that must be reported to internal organizations or outside agencies.

Importance Rating: 2.7 I 4.1 10 CFR Part 55: 41.10 10CFR55.43.b: 5 KIA Match: This question matches the KIA by having the candidate determine the correct procedure transition for an indicated Steam line rupture with complications.

SRO only because the candidate is to assess plant conditions and select the appropriate procedure as well as assess conditions and make the appropriate Emergency Plan declaration.

Technical

Reference:

E-0 rev 36 EPIP-1 rev 51 Proposed references EPIP-1 pg 11 and 12 rev 51 to be provided:

Learning Objective: OPL271.REP Question Source:

New x Modified Bank Bank Question History: New question written for 1503 ILT exam Comments:

Thursday, January 15, 2015 10:59:30 AM 81

QUESTIONS REPORT for 1503 SRO Exam

80. 057 AA2.04 080 Given the following plant conditions:

Unit 1 is at 100% power.

- OATC reports all channel status lights on RX Trip - SI Status panels are dark.

Which ONE of the following identifies ...

(1) the 120V AC Vital Instrument Power Board (VIPB) which has been lost, AND (2) if not repaired, the Unit-1 Tech Spec required time to enter Mode 3 if this board loss occurs concurrently with VIPB 2-111 becoming inoperable?

REFERENCE PROVIDED A-t (1) 1-1 (2) 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months B. (1) 1-1 (2) 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months C. (1) 1-11 (2) 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months D. (1) 1-11 (2) 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Thursday, January 15, 2015 11 :04:49 AM 80

QUESTIONS REPORT for 1503 SRO Exam DISTRACTOR ANALYSIS:

A. Correct, The indications (all status lights not lit) are consistent with a loss of 120V AC Vital Instrument Power Board 1-1. Also LCO 3.8.2.1 Action A provides actions for inoperability of one or more boards and would be the Tech Spec LCO that would be required to be entered. Tech Spec LCO 3.0.3 is not required to be entered. The time required to enter Mode 3 if the Inst Board is not returned to service is 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months (8 hrs + 6 hrs)

B. Incorrect, Plausible since the first part is correct. Also plausible if the candidate does not apply the correct action and detemines that entry into LCO 3.0.3 would be required. Thus 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months would be required to enter Mode 3 (1 hr+ 6 hrs).

C. Incorrect, Plausible if the candidate misdiagnoses the Inst board that is lost and thinks the indications are consistent with a loss of 1-11. Also plausible since the second part is correct.

D. Incorrect, Plausible if the candidate misdiagnoses the Inst board that is lost and thinks the indications are consistent with a loss of 1-11. Also plausible if the candidate does not apply the correct action and detemines that entry into LCO 3.0.3 would be required. Thus 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months would be required to enter Mode 3 (1 hr+ 6 hrs).

Thursday, January 15, 2015 11 :04:49 AM 81

QUESTIONS REPORT for 1503 SRO Exam

81. 077 AA2.01 081 Given the following plant conditions:

Unit 1 is at 45% power.

Electric load is 550 MWe.

- A disturbance on the offsite electrical grid has just occurred.

After attempting to adjust the Unit 1 Voltage Regulator with the exciter base adjust, the following plant conditions are noted:

Unit 1 Generator Hydrogen pressure is 65 psi.

Unit 1 is at 550 MVARs incoming.

SDBD 1A-A and 1B-B are at 6500 V.

USST load tap changers are in AUTO and functioning correctly.

Which ONE of the following completes the statement below?

The Unit 1 main generator (1) operating within the limits of capability curve and the next required action in accordance with AOP-P.07, "Degraded Grid Conditions or Generator Voltage Regulator Malfunctions" is to direct the unit operator to (2)

REFERENCE PROVIDED A. (1) is (2) place affected shutdown boards on DIG using Appendix F of AOP-P.07.

B. (1) is (2) manually transfer the affected 6.9KV Unit Boards to ALTERNATE supply using O-S0-202-3, "6.9KV Unit Station Service Boards."

C':" (1) is NOT (2) place affected shutdown boards on DIG using Appendix F of AOP-P.07.

D. (1) is NOT (2) manually transfer the affected 6.9KV Unit Boards to ALTERNATE supply using O-S0-202-3, "6.9KV Unit Station Service Boards."

Thursday, January 15, 2015 11: 17:48 AM 81

QUESTIONS REPORT for 1503 SRO Exam DIS TRACTOR ANAL YS/S:

A. Incorrect, Plausible if candidate misinterprets the incoming MVAR load and looks at

(+550) point of curve vs (-550) point. The main generator would appear to be within the curve. Also plausible since the second part is correct.

B. Incorrect, Plausible if candidate misinterprets the incoming MVAR load and looks at

(+550) point of curve vs (-550) point. The main generator would appear to be within the curve. Also plausible if the candidate misinterprets the procedure guidance and directs the crew to perform actions for Unit 1 USSTs operating in Auto and the crew is to Evaluate manually transferring to the Alternate supply.

C. Correct, In accordance with AOP-P.07 Appendix C for 550 MVARs incoming (-550) the Mn Gen is not operating within acceptable limits. Also in accordance with AOP-P.07 for the given SD board voltage (6500 V) the operators would be directed to attempt to adjust the tap changer on the USST to raise voltage. If the voltage cannot be adjusted then the operators are to place the SD boards on DIG using Appendix F.

D. Incorrect, Plausible since the first part is correct. Also plausible if the candidate misinterprets the procedure guidance and directs the crew to perform actions for Unit 1 USSTs operating in Auto and the crew is to Evaluate manually transferring to the Alternate supply.

Thursday, January 15, 201511:17:48 AM 82

QUESTIONS REPORT for 1503 SRO Exam Question Number: 81 Tier: _1__ Group 1 KIA: 077 Generator Voltage and Electric Grid Disturbances AA2.01 Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances:

Operating point on the generator capability curve.

Importance Rating: 3.5 I 3.6 10 CFR Part 55: 41.5 10CFR55.42.b: 5 KIA Match: This question matches the KIA by having the candidate determine if the Mn Generator is operating within the safe limits of the capability curve by applying the information given in the stem.

SRO only because it requires a detailed knowledge of the actions within the AOP to allow selection of appropriate attachments or procedures based on plant conditions.

Technical

Reference:

AOP-P.07, Degraded Grid Conditions or Generator Voltage Regulator Malfunctions, rev 5 Proposed references AOP-P.07, Appendix C rev 5 to be provided:

Learning Objective: OPL271AOP-P.07 Question Source:

New Modified Bank Bank x Question History: SQN bank question Comments:

Thursday, January 15, 2015 11 :17:48 AM 83

QUESTIONS REPORT for 1503 SRO Exam

82. 001 AA2.02 082 Given the following plant conditions:

Unit 1 is at 75% power.

- The control rods start continuously stepping out at 8 steps/min.

- Auctioneered High Tave is observed to be 568.5°F.

Subsequently, reactor power is now observed to be 73.5% power.

Which ONE of the following identifies the (1) indications that are consistent for this condition and (2) in accordance with NPG-SPP-10.4, "Reactivity Management Program," this event is considered a Significance Level __ event ?

Note:

FCV-62-138, Emergency Boration Flow Control Valve REFERENCE PROVIDED A. (1) Red light on handswitch for FCV-62-138 LIT; NO flow indicated on emergency borate flow indicator Fl-62-137A.

(2) 2 B~ (1) Red light on handswitch for FCV-62-138 LIT; flow indicated on emergency borate flow indicator Fl-62-137A.

(2) 3 C. (1) Green light on handswitch for FCV-62-138 LIT; flow indicated on emergency borate flow indicator Fl-62-137A.

(2) 2 D. (1) Green light on handswitch for FCV-62-138 LIT; NO flow indicated on emergency borate flow indicator Fl-62-137A.

(2) 3 Thursday, January 15, 2015 11 :25:02 AM 82

QUESTIONS REPORT for 1503 SRO Exam DISTRACTOR ANALYSIS:

A. Incorrect, Plausible since first part is correct a slow boration is taking place, however the procedure guidance should be from AOP-C.02 for uncontrolled RCS boration not AOP-C.01 due to uncontrolled rod withdrawal. Also plausible since in accordance with NPG-SPP-10.2, an event where there is an uncontrolled rod withdrawal is considered a Reactivity Event Level 2.

B. Correct, The indications of the emergency borate valve open (red light) and some flow would indicate that an uncontrolled boration is taking place causing a negative reactivity to be added to the RCS, thus outward rod motion will be required to compensate. The correct procedure for this condition is AOP-C.02. Also in accordance with NPG-SPP-1004, an unplanned reactivity event which results in a

_::: 1% power change is considered an event level 3.

C. Incorrect, Plausible since the Green light would indicate that the emergency boration valve is closed, however with flow indicated they could determine that the valve is leaking by (since the Boric Acid transfer pump is normally running, however in slow speed), the candidate may think that a boration is taking place. Also the correct procedure would be AOP-C.02 not AOP-C.01. Also plausible if the candidate thinks that this is uncontrolled rod withdrawal event and determines that this is a Reactivity Event Level 2.

D. Incorrect, Plausible since the Green light would indicate that the emergency boration valve is closed, and with no flow indicated they could determine that an event is taking place which is causing the control rods to move. Also the correct procedure would be AOP-C.02 not AOP-C.01. Also plausible since the second part is correct this would be considered a level 3 Reactivity Event.

Thursday, January 15, 2015 11 :25:02 AM 83

QUESTIONS REPORT for 1503 SRO Exam Question Number: 82 Tier: _1_ Group _2_

KIA: 001 Continuous Rod Withdrawal AA2.02 Ability to determine and interpret the following as they apply to the Continuous Rod Withdrawal:

Position of the emergency borate valve Importance Rating: 4.2 I 4.2 10 CFR Part 55: n/a 10CFR55.43.b: 5 KIA Match: Question matches the KIA by having the candidate determine the position of the emergency borate valve while the control rods are withdrawing.

SRO only by having the candidate assess plant conditions and select the appropriate Reactivity Event classification for the event in progress. This is an SRO task.

Technical

Reference:

NPG-SPP-10.4 rev 5 AOP-C.02 rev 09 1,2-47W809-2 Proposed references NPG-SPP-10.4, pages 56 & 57 of 70 with definition to be provided: statements redacted.

Learning Objective: OPT200.CVCS Obj 4.h; 8.c Cognitive Level:

Higher X Lower Question Source:

New X Modified Bank Bank Question History: New for 1503 NRC exam.

Comments:

Thursday, January 15, 2015 11 :30:50 AM 84

QUESTIONS REPORT for 1503 SRO Exam

83. 033 AG2. l.20 083 Given the following plant conditions:

Unit 1 is at 30% power.

IR NI N-35 has failed due to a blown fuse.

- The failed channel is being removed from service in accordance with AOP-1.01, "Nuclear Instrument Malfunction."

Which ONE of the following identifies; (1) the condition on the 1-M-13 instrument drawer that would indicate the fuse, that if blown, would prevent bypassing the High Flux reactor trip output signal, and (2) the LCO 3.3.3.7, Accident Monitoring Instrumentation (PAM), bases?

A. (1) CONTROL POWER ON light DARK (2) provides sufficient functional capability for protective and ESF purposes during the mitigation of accident and transient conditions.

B~ (1) CONTROL POWER ON light DARK (2) provides information required by the control room operators to take preplanned manual actions to accomplish safe plant shutdown.

C. (1) INSTRUMENT POWER ON light DARK (2) provides sufficient functional capability for protective and ESF purposes during the mitigation of accident and transient conditions.

D. (1) INSTRUMENT POWER ON light DARK (2) provides information required by the control room operators to take preplanned manual actions to accomplish safe plant shutdown.

Thursday, January 15, 2015 11 :36:20 AM 83

QUESTIONS REPORT for 1503 SRO Exam DISTRACTOR ANAL YS/S:

A. Incorrect, Plausible since the first part is correct. The Control Power On light being dark indicates that the fuse that was blown is in the control power circuit. If the control power circuit does not have power then the manual bypass of the channel directed by the AOP will not disable the high flux trip. Also plausible since this is a Tech Spec basis associated with Ni's however this is a basis for the 3.3.1 & 3.3.2 Protective and ESF Instrumentation, not the 3.3.3. 7 Accident Monitoring Instrumentation.

B. Correct, The Control Power On light being dark indicates that the fuse that was blown is in the control power circuit. If the control power circuit does not have power then the manual bypass of the channel directed by the AOP will not disable the high flux trip. Also this statement is from the 3. 3. 3. 7 Accident Monitoring Instrumentation, bases.

C. Incorrect, Plausilbe since the Instrument Power On light being dark would indicate that a fuse has blown, however this would not prevent the high flux trip from being bypassed by the actions of the AOP. Also plausible ifthe candidate gets the basis for T. S. 3. 3. 1 confused with T. S. 3. 3. 7 D. Incorrect, Plausilbe since the Instrument Power On light being dark would indicate that a fuse has blown, however this would not prevent the high flux trip from being bypassed by the actions of the AOP. Also plausible since the second part is correct.

Thursday, January 15, 2015 11 :36:20 AM 84

QUESTIONS REPORT for 1503 SRO Exam Question Number: 83 Tier: _1_ Group _2_

KIA: 033 Loss of Intermediate Range NI AG 2.1.20 Ability to execute procedure steps.

Importance Rating: 4.6 I 4.6 10 CFR Part 55: 41.10 10CFR55.43.b: 2, 5 KIA Match: This question matches the KIA by having the candidate determine whether the actions of AOP-1.01 would be effective in blocking the high flux trip from the effected channel SRO only because it requires the candidate to recall the bases of Tech Spec for Accident Monitoring Instrumentation Technical

Reference:

AOP-1.01 rev 12 Tech Spec 3.3.1.1 Tech Spec 3.3.3.7 Proposed references None to be provided:

Learning Objective: OPT271AOP-l.01 Question Source:

New X Modified Bank Bank Question History: New question written for 1503 ILT exam Comments:

Thursday, January 15, 2015 11 :36:20 AM 85

QUESTIONS REPORT for 1503 SRO Exam

84. 061AA2.06084 Given the following plant conditions:

Unit 1 is at 100% power.

Unit 2 is in Mode 6.

- O-RM-90-103, "Spent Fuel Pit RadMon," is out of service.

- The High Rad relays have been removed.

- Train B rad monitor block switch is positioned to OFF and pushed-in.

- A source check is being performed on O-RM-90-102, "Spent Fuel Pit RadMon."

- Train A rad monitor block switch is positioned to 0-102 and pulled out.

- When the source check is performed, O-RM-90-102 fails to respond.

Which ONE of the following identifies ...

(1) the status of the following annunciators:

"O-HS-90-136A1 HIGH RAD IN CNMT INPUT TO TR A OF SSPS BLOCKED" "O-HS-90-136A2 HIGH RAD IN CNMT INPUT TO TR B OF SSPS BLOCKED" and (2) the requirements of LCO 3.9.12, ABGTS __ met?

A't (1) ONLY, O-HS-90-136A1 HIGH RAD IN CNMT INPUT TO TR A OF SSPS BLOCKED will be LIT (2) are NOT B. (1) ONLY, O-HS-90-136A1 HIGH RAD IN CNMT INPUT TO TR A OF SSPS BLOCKED will be LIT (2) are C. (1) BOTH of the listed annunciator windows will be LIT.

(2) are NOT D. (1) BOTH of the listed annunciator windows will be LIT.

(2) are Thursday, January 15, 201511:46:17 AM 84

QUESTIONS REPORT for 1503 SRO Exam DISTRACTOR ANALYSIS:

A. Correct, The "A" Train alarm will be lit since handswitch O-HS-90-136A 1 is pulled out for the FT. The Train "B" alarm will not be lit since its associated HS is pushed in. O-RM-90-103 is Inoperable (initial condition) and O-RM-90-102 must be declared Inoperable due to its failure to source check. The SFP area monitors are required attendant equipment for ABGTS Operability for TS 3.9.12, therefore both Units must enter the Tech Spec since there is fuel in the Spent Fuel Pool.

11 11 B. Incorrect. Plausible since the first part is correct, only the A Train alarm will be lit since handswitch O-HS-90-136A 1 is pulled out for the FT. Also plausible if the 11 11 candidate thinks that only 1 train of ABGTS is Inoperable since only the A train alarm is lit. Thus with unit 2 in refueling mode they could consider that only Unit 2 would be required to enter T. S. 3. 9. 12. However since the Spent Fuel Pool is common, and O-RM-90-103 is Inoperable (initial condition) and O-RM-90-102 must be declared Inoperable due to its failure to source check; The SFP area monitors are required attendant equipment for ABGTS Operability for TS 3. 9. 12, therefore both unit must enter TS 3. 9. 12.

C. Incorrect, Plausible because the "B Train alarm would normally be lit with O-RM-90-103's auto function blocked by O-HS-90-136A2, however the handswitch must be pulled out to cause the alarm. Also plausible since the second part is correct.

11 11 D. Incorrect, Plausible because the 8 Train alarm would normally be lit with O-RM-90-103's auto function blocked by O-HS-90-136A2, however the handswitch must be pulled out to cause the alarm. Also plausible because the candidate may fail to recall that the SFP area monitor is required attendant equipment for ABGTS Operability for TS 3. 9. 12.

Thursday, January 15, 201511:46:17 AM 85

QUESTIONS REPORT for 1503 SRO Exam Question Number: 84 Tier: _1_Group _2_

KIA: 061 Area Radiation Monitoring (ARM) System Alarms AA2.01 Ability to determine and interpret the following as they apply to the Area Radiation Monitoring (ARM) System Alarms:

ARM panel displays Importance Rating: 3.5 I 3.7 10 CFR Part 55: n/a 10CFR55.43.b: 2, 5 KIA Match: Question matches the KIA by having the applicant interpret indications associated with area rad monitors and SRO because application of TS Operability is dependent on information in the required surveillance of the specification.

Technical

Reference:

O-AR-M12-D E3 and E4 rev 42 T.S. 3.3.3.1, Radiation Monitoring Instrumentation, Amendment 322 T.S. 3.7.8, Auxiliary Building Gas Treatment System, Amendment 263 Proposed references None to be provided:

Learning Objective: OPT200.RM Obj 6 ; 11 Cognitive Level:

Higher X Lower Question Source:

New Modified Bank X Bank Question History: Modified bank question from 09/2010 ILT exam.

Comments:

Thursday, January 15, 201511:46:17 AM 86

QUESTIONS REPORT for 1503 SRO Exam

85. W/E14 EG2.2.44 085 Given the following plant conditions:

Unit 1 has tripped due to a large break LOCA from 100% power.

RHR pump 1A-A was tagged out ofservice for maintenance.

Containment pressure is 11 psig.

RWST level is 23% and slowly lowering.

When shifting to cold leg recirc using ES-1.3, "Transfer to RHR Containment Sump," 1-FCV-63-73 Train B RHR Cntmt Sump Suction Valve, fails to open.

The crew implements ECA-1.1, "Loss of RHR Sump Recirculation."

Both Containment Spray pumps are aligned to the RWST.

Which ONE of the following completes the statements below?

The procedure that takes priority under these conditions is (1) and, based on current plant conditions, the number of Containment Spray pumps required to be operating for this condition is (2)

Note: FR-Z.1, "High Containment Pressure" A. (1) FR-Z.1 (2) 1 B. (1) FR-Z.1 (2) 2 C"!" (1) ECA-1.1 (2) 1 D. ( 1) ECA-1 .1 (2) 2 Thursday, January 15, 2015 11 :51 :18 AM 85

QUESTIONS REPORT for 1503 SRO Exam DISTRACTOR ANAL YS/S:

A. Incorrect, Plausible since there would be an Orange path on FR-Z (due to Containment pressure greater than 2. 8 psg) an based on normal rules of useage any Red or Orange path FR condition takes priority over other E or EGA series procedures, thus FR-Z. 1 would normally be the controlling procedure. Also since 1-FCV-63-73 will not open, the candidate could think that only 1 Containment Spray pump be allowed by the procedure. The direction to only run 1 Containment Spray pump under this condition is provided in ECA-1.1, but only after the spray pump suction is aligned to the containment sump.

B. Incorrect, Plausible since normal rules of useage would dictate that any FRP that is at an Orange level or above requires the operators to implement the FRP at the earliest time. Also plausible since both Containment Spray pumps would be required to be in operation during implementation of FR-Z. 1 prior to containment sump suction swapover.

C. Correct, In accordance with EPM-3 if ECA-1.1 has been implemented, and conditions exist where an Orange path condition leads to FR-Z. 1 (Containment pressure between 2. 8 psig and 12 psig) then the quidance for Containmnet Spray pump operation associated with ECA-1. 1 has priority. Also with Containment pressure greater than 9. 5 psig but less than 12 psig, the procedure requires that only 1 Containment Spray pump be operated while pump suction is aligned to the RWST.

D. Incorrect, Plausible since the first part is correct. Also plausible since during the use of ECA-1. 1, the candidate could mis-interpret the table that directs the number of spray pumps required and think that both are needed and directed by ECA-1.1.

However since Containment pressure is less than 12 psig only one pump is required.

Thursday, January 15, 201511:51:18 AM 86

QUESTIONS REPORT for 1503 SRO Exam Question Number: 85 Tier: _1__ Group 2 KIA: W/E14 High Containment Pressure (Loss of Containment Integrity)

EG2.2.44 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.

Importance Rating: 4.2 I 4.4 10 CFR Part 55: n/a 10CFR55.43.b: 2, 5 KIA Match: This question matches the KIA by having the candidate determine that containment integrity is beening challenged as indidated by an Orange Path condition of Containment pressure and determine the procedure that has priority for current plant conditions.

SRO only because it requires the candidate to select the appropriate procedure and also requires detailed knowledge of procedure actions to mitigate the accident.

Technical

Reference:

EPM-3 ECA-1.1 FR-Z.1 Proposed references None to be provided:

Learning Objective: OPL271 ECA-1.1 OPL271 FR-Z.1 Question Source:

New x Modified Bank Bank Question History: New question written for 1503 ILT exam Comments:

Thursday, January 15, 2015 11 :55:24 AM 87

QUESTIONS REPORT for 1503 SRO Exam

86. 012 G2.4.49 086 Given the following plant conditions:

Unit 1 is operating at 100% power.

The reactor fails to trip on a valid automatic trip signal.

The reactor cannot be tripped from the control room.

The turbine fails to trip using the turbine trip handswitch on 1-M-2.

Which ONE of the following completes the statements below?

The FIRST required action to be taken due to the failure of the turbine to trip is to (1)

In accordance with EPIP-1, if the reactor is tripped within 5 minutes, the SM is required to (2)

A. (1) close main turbine governor valves using valve position limiter (2) report but not declare the event because the conditions were terminated before the event was declared B~ (1) close main turbine governor valves using valve position limiter (2) declare the event and make the required notifications C. (1) close MSIVs and bypasses (2) declare the event and make the required notifications D. (1) close MS IVs and bypasses (2) report but not declare the event because the conditions were terminated before the event was declared Thursday, January 15, 201512:11:50 PM 86

QUESTIONS REPORT for 1503 SRO Exam DISTRACTOR ANAL YS/S:

A. Incorrect, Plausible since the RNO for the turbine failing to trip during performance of FR-S. 1 is to 'Close main turbine governor valves Using VAL VE POSITION LIMITER," This is accomplished by driving the turbine Valve Position Limiter to 'O'.

Also plausible if the candidate thinks that since the condition was terminated or controlled before the event was declared (declaration done in 15 min) and since there is no event classification for a Rx Trip, they could report the event but not have to declare the event.

B. Correct, The RNO for the turbine failing to trip during the performance of FR-S. 1 is to "Close main turbine governor valves Using VALVE POSITION LIMITER," which is the same as manually running back the turbine. Also in accordance with EPIP-1, 2.3 Failure of Rx Protection Sys., NOTE" Although a mode change will occur, this event will still be classified and declared as an SAE. "

C. Incorrect, Plausible because this is the action directed in FR-S. 1 if the turbine trip is not successful, however it is not the first action directed to be taken, this action is taken if the governor valves would not close. Also plausible since the second part is correct.

D. Incorrect, Plausible because this is the action directed in FR-S. 1 if the turbine trip is not successful, however it is not the first action directed to be taken. Also plausible if the candidate thinks that since the condition was terminated or controlled before the event was declared (declaration done in 15 min) and since there is no event classification for a Rx Trip, they could report the event but not have to declare the event.

Thursday, January 15, 2015 12:11 :50 PM 87

QUESTIONS REPORT for 1503 SRO Exam Question Number: 86 Tier: _2_ Group: _1_ _

KIA: 012 Reactor Protection System (RPS)

G 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

Importance Rating: 4.6 / 4.4 10 CFR Part 55: 41.10 / 43.2 / 45.6 10CFR55.43.b: 5 KIA Match: KIA is matched because the question requires ability to perform required immediate operator actions during an A TWS without reference to the procedure.

SRO only due to having the candidate determine required actions from EPIP-1 (Emergency Response Plan) for reporting conditions that are corrected prior to event declarations being made and reported to offsite agencies.

Technical

Reference:

FR-S.1, Nuclear Power Generation/ATWS, Revision 23 EPIP-1 rev 51 Proposed references None to be provided:

Learning Objective: OPL271 FR-S.1 OPL271REP Cognitive Level:

Higher Lower x Question Source:

New Modified Bank x Bank Question History: Modified bank question from WBN 03/2013 exam (#75)

Comments:

Thursday, January 15, 2015 12: 11 :50 PM 88

QUESTIONS REPORT for 1503 SRO Exam

87. 025 A2.05 087 Given the following plant conditions:

- Unit 1 is operating at 100% power.

- Annunciator, "LIS-61-195B/A GLYCOL EXP TANK LEVEL LOW-LOW LOW" (1-M6-E, D-6) alarms.

- An operator is dispatched to investigate the alarm, but before a report is received the alarm reflashes.

Which ONE of the following completes the statement below?

The Glycol Expansion Tank Isolation Valves (1-FSV-61-109 and 1-FSV-61-118) will be (1) , and in accordance with LCO 3.6.5.1, ICE BED, the Ice Bed is currently (2)

A. (1) open (2) OPERABLE B. (1) open (2) INOPERABLE C'( (1) closed (2) OPERABLE D. (1) closed (2) INOPERABLE Thurnday, Janua'Y 15, 201512017013 P/ 87

QUESTIONS REPORT for 1503 SRO Exam DISTRACTOR ANAL YS/S:

A. Incorrect, 1091118 auto close on lo-lo level (18" decreasing) and will auto open when the lo-lo level clears. The ref/ash indicates that level has reached lo-lo level setpoint. 1911193 will auto close on lo-lo level. Plausible because both valves would be open if lo-lo level not reached. Also Tech Spec 3.6.5.1 Surveillance requires that Ice Bed temperature remain below 27°F for the ice bed to be OPERABLE not the position of the glycol valves and normal temperature of the ice is 18°F to 20°F thus the Ice Bed would remain OPERABLE for some time.

B. Incorrect, 1091118 auto close on lo-lo level (18" decreasing) and will auto open when the lo-lo level clears. The ref/ash indicates that level has reached lo-lo level setpoint. 1911193 will auto close on lo-lo level. Plausible because both valves would be open if lo-lo level not reached. Also plausible since the candidate could assume that the low level in the expansion tank will cause the Ice Bed to become immediately INOPERABLE, however Tech Spec 3.6.5.1 Surveillance requires that Ice Bed temperature remain below 27°F for the ice bed to be operable not the position of the glycol valves.

C. Correct, 1091118 auto close on lo-lo level (18" decreasing) and will auto open when the lo-lo level clears. The ref/ash indicates that expansion tank level has reached lo-lo level setpoint. 1911193 will auto close on lo-lo level. Also Tech Spec 3.6.5.1 Surveillance requires that Ice Bed temperature remain below 27°F for the ice bed to be OPERABLE not the position of the glycol valves and normal temperature of the ice is 18°F to 20°F thus the Ice Bed would remain OPERABLE for some time.

D. Incorrect, Plausible since the first part is correct. Also plausible since the candidate could assume that with the glycol valves closed the Ice Bed is immediately INOPERABLE, however Tech Spec 3.6.5.1 Surveillance requires that Ice Bed temperature remain below 27°F for the ice bed to be operable not the position of the glycol valves.

Thursday, January 15, 2015 12:17:13 PM 88

QUESTIONS REPORT for 1503 SRO Exam Question Number: 87 Tier: _2__ Group 1 KIA: 025 Ice Condenser System A2.05 Ability to (a) predict the impacts of the following malfunctions or operations on the Ice Condenser System and (b) based on those predictions correct, control or mitigate the consequences of those malfunctions or operations:

Abnormal glycol expansion tank level.

Importance Rating: 2.5 I 2.7 10 CFR Part 55: 41.5 10CFR55.42.b: 2, 5 K/A Match: This question matches the KA by having the candidate predict system status following an abnormal glycol expansion tank alarm (Low-Low). And SRO only because it requires the candidate to apply conditions in the surveillance to determine if Ice Condenser remains OPERABLE for the given condition.

Technical

Reference:

Tech Spec 3.6.5.1 ICE BED Amend 279 AR-M6-E window D-6 Rev 29 47W611-61-2 Proposed references None to be provided:

Learning Objective: OPT200.ICE, Obj 10; 12 Question Source:

New Modified Bank x Bank Question History: First part of question is from bank ICE COND-B.O with second part changed to make SRO only.

Comments:

Thursday, January 15, 2015 12:17:13 PM 89

QUESTIONS REPORT for 1503 SRO Exam

88. 039 G2.4.50 088 Given the following plant conditions:

Unit 1 is at 100% power Condenser rad monitors RM-99 and RM-119 are both out of service for repair.

- The following alarm is received:

1-RA-421A MN STM LN HI RAD (M30A-C8)

- The OATC has taken manual control of charging flow control and has stabilized PZR Level at 60%.

Current plant conditions are reported as:

Letdown in service at 75 gpm Charging flow is at 102 gpm Seal return flow at 12 gpm total Which ONE of the following identifies:

(1) the required section of AOP-R.01, "Steam Generator Tube Leak," to mitigate the event and (2) in accordance with NPG-SPP-03.5, "Regulatory Reporting Requirements,"

the latest time that the NRC is to be notified of this event?

REFERENCE PROVIDED A. (1) sect 2.1 "SIG Tube Leak Requiring Rapid Shutdown."

(2) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. (1) sect 2.2 "Steam Generator Leak Monitoring."

(2) 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C'!" (1) sect 2.1 "SIG Tube Leak Requiring Rapid Shutdown."

(2) 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months D. (1) sect 2.2 "Steam Generator Leak Monitoring."

(2) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Thursday, January 15, 2015 12:24:50 PM 88

QUESTIONS REPORT for 1503 SRO Exam DISTRACTOR ANAL YS/S:

A. Incorrect, Plausible since the first part is correct. Also plausible if the candidate thinks that this would be an event which would be declared by any of the plant's Emergency classifications, however with idenified leakage of less than 25 gpm then no EPIP event classification would be required.

B. Incorrect, Plausible since entry into AOP-R.01 would be required, and if the candidate thought that since PZR level was stabilized, then only further monitoring would be required, however PZR was lowering at the start of the event thus not stable. Also the second part is correct.

C. Correct, In accordance with AOP-R.01 with high radiation alarm and PZR level dropping requiring operator action, then entry would be into section 2. 1 which would require a rapid plant shutdown. However SG tube leakage is identified leakage and would have to be 25 gpm to meet the NOUE level, however this leak rate does exceed the tech spec value which would require a plant shutdown thus a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months report is required.

D. Incorrect, Plausible since entry into AOP-R.01 would be required, and if the candidate thought that since PZR level was stabilized, then only further monitoring would be required, however PZR was lowering at the start of the event thus not stable. Also plausible if the candidate thinks that since the leak rate of 15 gpm is greater than the 10 gpm (sect 2.1) that the classification would be an NOUE.

However SG tube leakage is identified leakage and thus would have to be 25 gpm to meet the NOUE level.

Thursday, January 15, 2015 12:24:50 PM 89

QUESTIONS REPORT for 1503 SRO Exam Question Number: 88 Tier: _2_ Group _1_

KIA: 039 Main and Reheat Steam System (MRSS)

G2.4.50 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

Importance Rating: 4.2 I 4.0 10 CFR Part 55:

10CFR55.43.b: 5 KIA Match: This question matches the KIA by having the operators validate the alarm given by changing plant conditions and taking actions identified in the alarm response procedure to mitigate the event.

SRO only because the candidate needs to recognize the changing plant conditions (lowering PZR level which required manual action to stabilize) to go to the correct section of the AOP and also the size of the leak to make the correct decision of the time of report required.

Technical

Reference:

1-AR-M30-A rev 18 AOP-R.01 rev 32 EPIP-1 rev 51 NPG-SPP-03.5, rev 10 Proposed references NPG-SPP-03.5, Regulatory Reporting Requirements, to be provided: Appendix A, rev 0010, pages 20 - 34 (with 1 hr items redacted)

EPIP-1, pg 17 rev 51 Learning Objective: OPL271REP OPL271AOP-R.01 Question Source:

New x Modified Bank Bank Question History: New question written for 1503 ILT exam Comments:

Thursday, January 15, 2015 12:24:50 PM 90

QUESTIONS REPORT for 1503 SRO Exam

89. 063 A2.01 089 Given the following plant conditions:

Unit 1 is at 100% power.

- The following annunciator is received:

125V DC VITAL BAT BD I ABNORMAL (1-M1-C, A-5)

Battery Board I voltage indicates -132V DC and stable.

- Ground indication is +85V DC Which ONE of the following completes the statement below?

High battery board (1) caused the main control room alarm.

AND In accordance with NPG-SPP-07.1.4, "Work Control Prioritization - On Line,"

the SRO will initiate a (2) Work Order to MEG.

REFERENCE PROVIDED A. (1) voltage (2) Priority 2 B. (1) voltage (2) Priority 3 c~ (1) ground (2) Priority 2 D. (1) ground (2) Priority 3 Thursday, January 15, 2015 12:30:27 PM 89

QUESTIONS REPORT for 1503 SRO Exam DISTRACTOR ANALYSIS:

A. Incorrect, Plausible if the candidate thinks that a high system voltage (132Vdc) exists, since the nominal system voltage is 125V DC and determines that a battery charger setpoint may need to be adjusted. However the high voltage alarm setpoint is 143V DC. Also plausible since the second part is correct.

B. Incorrect, Plausible if the candidate thinks that a high system voltage (132Vdc) exists, since the nominal system voltage is 125V DC and determines that a battery charger setpoint may need to be adjusted. However the high voltage alarm setpoint is 143 V DC. Also plausible if the candidate thinks that a Priority 3 Work Order "Schedule within the normal cycle or at next available system week" would be assigned, however in accordance with O-G0-10, the SRO is to assign a Priority 2 Work Order to get the ground indentified and corrected quickly.

C. Correct, In accordance with alarm response procedure, a +85V ground cause the alarm to annunciate. A +85V ground would be of sufficient magnitude to warrant an "Urgent - Schedule at the earliest opportunity within T-3 week schedule, " in accordance with NPG-SPP-07.1.4, "Work Control Prioritization," since the SROs are the only personnel to assign priority levels to WOs. Also, the requirements of O-G0-10, "Electrical Apparatus Operation." Section 5.10 applies which provides the direction to locate grounded circuits on DC Board or panels.

D. Incorrect, Plausible since the first part is correct. Also plausible if the candidate thinks that a Priority 3 Work Order "Schedule within the normal cycle or at next available system week" would be assigned, however in accordance with O-G0-10, the SRO is to assign a Priority 2 Work Order to get the ground indentified and corrected quickly.

Thursday, January 15, 2015 12:30:27 PM 90

QUESTIONS REPORT for 1503 SRO Exam Question Number: 89 Tier: _2__ Group _1_

KIA: 063 DC Electrical Distribution A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on DC Electrical Distribution and (b) based on those predictions use procedures to correct, control or mitigate the consequences of those malfunctions or operations:

Grounds.

Importance Rating: 2.5 I 3.2 10 CFR Part 55: 41.10 10CFR55.43.b: 5 KIA Match: This question matches the KIA by having the candidate assess the alarm provided in the stem and determine what type of failure/malfunction has occurred.

SRO only by having the candidate assess the plant conditions and select the appropriate procedure which will correct the conditions, as well as requiring detailed knowledge of SRO responsibility of setting priorities for Work Orders.

Technical

Reference:

1-AR-M1-C (A-5) rev 0049 O-G0-10 rev 51 O-S0-250-1, 125 Volt DC Vital Power System. rev 54 NPG-SPP-07.1.4 rev 3 Proposed references NPG-SPP-07.1.4 page 36 of 37 to be provided:

Learning Objective: OPL271AOP-P.02 rev 2 Obj. 13 Question Source:

New X Modified Bank Bank Question History: New question written for 1503 ILT Exam Comments:

Thursday, January 15, 2015 12:36:34 PM 91

QUESTIONS REPORT for 1503 SRO Exam

90. 103 A2.03 090 Given the following plant conditions:

- Unit 1 is operating at 100% power.

- Channel #1 containment "HIGH-HIGH PRESS" instrument loop failed 2 weeks ago.

- The channel was removed from service in accordance with LCO 3.3.2 "ESF Actuation System Instrumentation."

- Subsequently Channel #3 containment pressure transmitter fails HIGH.

Which ONE of the following completes the statement below?

Containment Isolation Phase B will (1) and LCO 3.0.3 (2) be required to be entered?

A. (1) actuate (2) will B. (1) actuate (2) will NOT C. (1) NOT actuate (2) will NOT IY. (1) NOT actuate (2) will Thursday, January 15, 2015 12:46:28 PM 90

QUESTIONS REPORT for 1503 SRO Exam DISTRACTOR ANALYSIS:

A. Incorrect, Plausible if the candidate thinks that the first failed channel was tripped when removed from service, however per LCO 3. 3. 2. 1 action #18 the failed channel would be placed in Bypass not tripped, thus the required 214 logic is not made up for phase B actuation. Also plausible if the candidate thinks that one channel can be in Bypass and the other in Tripped and fails to recognize that there are no directed actions for more than 1 failed channel..

B. Incorrect, Plausible if the candidate thinks that the first failed channel was tripped when removed from service, however per LCO 3. 3. 2. 1 action #18 the failed channel would be placed in Bypass not tripped, thus the required 214 logic is not made up for phase B actuation. Also plausible since the second part is correct.

C. Incorrect, Plausible since the first part is correct, no Phase B actuation would occur. Also plausible if the candidate thinks that one channel can be in Bypass and the other in Tripped and fails to recognize that there are no directed actions for more than 1 failed channel.

D. Correct, In accordance with AOP-1.05 and LCO 3.3.2.1 for a failed channel 1 of High-High containment pressure the channel is Bypassed within 6 hrs and power operation may continue. With only the High-High channel removed from service (bypassed) a subsequent failure did not makeup the required 214 logic to actuat.e phase B. However with two channels of High-High containment pressure failed, LCO 3.0.3 would also be entered along with LCO 3.3.1.1 & 3.3.2.1 Thursday, January 15, 2015 12:46:28 PM 91

QUESTIONS REPORT for 1503 SRO Exam Question Number: 90 Tier: _2__ Group 1 KIA: 103 Containment System A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the Containment System and (b) based on those predictions use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Phase A and B isolation Importance Rating: 3.5 I 3.8 10 CFR Part 55: 41.5 10CFR55.43.b: 2, 5 KIA Match: This question matches the KIA by having the candidate analyze the effects of instrument failures on containment phase B actuation and applying the necessary LCO actions.

SRO only because requires the candidate to apply in depth knowledge of the LCO actions when removing a failed CNMT pressure channel from service and knowledge of LCO actions required for multiple failed channels.

Technical

Reference:

LCO 3.0.3 LCO 3.3.1.1 LCO 3.3.2.1 AOP-1.05 rev 4 Proposed references None to be provided:

Learning Objective: OPT200.EAGLE21 obj 5; 9 Question Source:

New x Modified Bank Bank Question History: New question written for 1503 ILT exam Comments:

Thursday, January 15, 2015 1:06:15 PM 92

QUESTIONS REPORT for 1503 SRO Exam

91. 028 G2.l.25 091 Given the following plant conditions:

Unit 1 tripped from 100% due to a small break LOCA.

- While implementing E-1, "Loss of Reactor or Secondary Coolant," the following data is reported by the crew:

RCS pressure 1200 psig slowly lowering.

CETs are 500°F and slowly lowering.

CNMT pressure 2.0 psig.

CNMT hydrogen concentration has just been confirmed at 4.2%.

Hydrogen Recombiner Reference power is 39 KW (data plate)

- The crew is implementing EA-268-1, "Placing Hydrogen Recombiners In Service."

Which ONE of the following identifies:

(1) the 25 minute hydrogen recombiner power setting, and (2) the REP classification that would be required for the conditions described?

REFERENCE PROVIDED A. (1) 51 Kw (2) Alert B~ (1) 51 Kw (2) Site Area Emergency C. (1) 78 Kw (2) Alert D. (1) 78 Kw (2) Site Area Emergency Thursday, January 15, 20151:12:06 PM 91

QUESTIONS REPORT for 1503 SRO Exam DISTRACTOR ANALYSIS:

A. Incorrect, Plausible since the first part is correct. The power setting would be 51 Kw.

Also plausible since an Alert would be correct if candidate only recognizes the RCS barrier potential loss.

B. Correct, In accordance with EA-268-1, given the reference data power of 51 Kw using the Appendix A graph to determine the pressure correction factor- 1.31.

=

Thus the power setting (1.31) x (39) 51Kw Also EPIP-1 requires that a Site Area Emergency be declared for a Loss or Potential loss of any two barriers ( RCS potential loss due to entering E-1 and CNMT potential loss due to hydrogen > 4%.)

C. Incorrect, Plausible if the candidate does not apply the correction factor and multiplies the CNMT pressure with reference power setting. Thus (2 psig) x (39) =

78 Kw. Also plausible since an Alert would be the correct classification if candidate only recognizes the RCS barrier potential loss.

D. Incorrect, Plausible if the candidate does not apply the correction factor and multiplies the CNMT pressure with reference power setting. Thus (2 psig) x (39) =

78 Kw. Also plausible since the second part is correct. EPIP-1 requires that a Site Area Emergency be declared for a Loss or Potential loss of any two barriers ( RCS potential loss due to entering E-1 and CNMT potential loss due to hydrogen> 4%.)

Thursday, January 15, 20151:12:06 PM 92

QUESTIONS REPORT for 1503 SRO Exam Question Number: 91 Tier: _2_ Group _2_ _

KIA: 028 Hydrogen Recombiner and Purge Control A2.01 Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

Importance Rating: 3.9 I 4.2 10 CFR Part 55: 41.10 10CFR55.43.b: 5 KIA Match: Question matches KIA by having the candidate determine the power setting for the Hydrogen recombiners when Containment pressure is above the nominal reference pressure and temperature.

SRO level by having candidate determine which emergency event classification applies to data presented.

Technical

Reference:

EA-268-1 rev 4 EPIP-1 rev 51 Proposed references EPIP-1 pages 11, 12 rev 51 to be provided: EA-268-1 rev 4 Learning Objective: OPT200.CGCS Obj 10; 14 OPL271 REP Obj 3 Cognitive Level:

Higher x Lower Question Source:

New Modified Bank Bank x Question History: SON bank question written for 1009 NRC exam Comments:

Thursday, January 15, 20151:12:06 PM 93

QUESTIONS REPORT for 1503 SRO Exam

92. 071 A2.02 092 Given the following plant conditions:

- A release of Waste Gas Tank Bis in progress.

Power is lost to O-RM-90-118, "Waste Gas Effluent Rad Monitor".

Which ONE of the following identifies:

(1) the effect the loss of power will have on the release and (2) the requirement to allow any additional release of the tank with the radiation monitor out of service?

A~ (1) The release will automatically terminate; (2) A new release package would be required for any additional release of the tank after ODCM actions were met.

B. (1) The release will automatically terminate; (2) The existing release package could be used for any additional release of the tank after ODCM actions were met.

C. (1) A manual termination of the release will be required; (2) A new release package would be required for any additional release of the tank after ODCM actions were met.

D. (1) A manual termination of the release will be required; (2) The existing release package could be used for any additional release of the tank after ODCM actions were met.

Thursday, January 15, 20151:21:21 PM 92

QUESTIONS REPORT for 1503 SRO Exam D/STRACTOR ANALYSIS:

A. Correct, The release would be automatically terminated due to an instrument malfunction and a new package would be required to make any additional releases from the tank.

B. Incorrect, Plausible since the release would be automatically terminated due to an instrument malfunction but the current release package would not be used to make any additional releases from the tank, a new package would be required. Also plausible because releases can be stopped and restarted using the same package under other conditions.

C. Incorrect, Plausible because some release point radiation monitor instrument malfunctions only alarm, however the release would be automatically terminated due to an instrument malfunction. Also plausible since the second part is correct. A new release package would be required.

D. Incorrect, Plausible because some release point radiation monitor instrument malfunctions only alarm, however the release would be automatically terminated due to an instrument ma/function. Also plausible because releases can be stopped and restarted using the same package under other conditions.

Thursday, January 15, 20151:21:21 PM 93

QUESTIONS REPORT for 1503 SRO Exam Question Number: 92 Tier: _2__ Group 2 KIA: 071 Waste Gas Disposal System (WGDS)

A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the Waste Gas Disposal System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Use of waste gas release monitors, radiation, gas flow rate and totalizer.

Importance Rating: 3.3 I 3.6 10 CFR Part 55: 41.5 10CFR55.43.b: 5 KIA Match: This question matches the KIA by having the candidate determine the effect of a power loss to a process rad monitor while a gaseous release is in progress.

SRO only because it requires SRO level knowledge of the administrative requirements for starting and stopping radioactive gaseous releases.

Technical

Reference:

1,2-47W611-77-4Rev10 1,2-45N677-1Rev16 O-AR-M12-B Rev 28 O-S0-77-15 Rev 18 O-Sl-CEM-077-410.4 Rev 23 ODCM Rev 58 Proposed references None to be provided:

Learning Objective: OPT200.GRW obj. 8; 12 Question Source:

New Modified Bank Bank x Question History: SQN bank question Comments:

Thursday, January 15, 2015 1:21 :21 PM 94

QUESTIONS REPORT for 1503 SRO Exam

93. 079 A2.0l 093 Given the following plant conditions:

Unit 1 in Mode 3 with the RCS at normal operating temperature and pressure preparing for reactor startup.

- Alarm "PS-32-104 TRAIN A AUX CONTROL AIR PRESS LOW" (M15-B) is actuated.

Control Air pressure indications are:

Pl-32-200 Control Air Header pressure is 65 psig and lowering.

Pl-32-104 Aux Bldg Control air header A pressure is 65 psig and lowering.

Pl-32-105 Aux Bldg Control air header B pressure is 82 psig and rising.

Which ONE of the following identifies both ...

1) the direction given the AUO and

2) which train(s) of AFW will be INOPERABLE on Unit 1?

Note:

O-FCV-32-82, Aux. Compsr. A-A Aux. Bldg !sol.

O-FCV-32-85, Aux. Compsr. B-B Aux. Bldg /sol.

1-FCV-32-80, Unit 1 Train A Rx Bldg /sol.

1-FCV-32-102, Unit 1 Train B Rx Bldg /sol.

Direction U-1 AFW Trains Inoperable A'! Ensure O-FCV-32-82, Motor Driven Train A only and O-FCV-32-85 are closed.

B. Ensure 1-FCV-32-80 Motor Driven Train A and Turbine Driven Train and 1-FCV-32-102 are closed.

C. Ensure O-FCV-32-82, Motor Driven Train A and Turbine Driven Train and O-FCV-32-85 are closed.

D. Ensure 1-FCV-32-80 Motor Driven Train A only and 1-FCV-32-102 are closed.

Thursday, January 15, 2015 1:31 :37 PM 93

QUESTIONS REPORT for 1503 SRO Exam DISTRACTOR ANAL YS/S:

A. Correct, The isolation valves should automatically close at 69 psig. With the control header pressure and Aux Bldg control header A at the same pressure with Aux Bldg B header rising it would indicate that at least one of the isolation valves did not go closed. AOP-M02 would have the operators ensure that the O-FCV-32-82 & 85 are closed to isolate the leak. The Aux Bldg A header pressure is less than 70 psig according to the notes in alarm response procedure the A header would be considered Inoperable. In accordance with the TIS Bases, the loss of a train of essential air is no more severe than the loss of one of the motor driven trains because the TD Pump can still supply to steam generators.

B. Incorrect, Plausible if the candidate thinks that 1-FCV-32-102 is also isolated by the AOP-M.02 for leak isolation. This valve would automatically isolate at 50 psig. Also Only the Train A is inoperable due to loss of air to the A MO driven LC Vs. Also the candidate may get confused on whether the TD AFW train is also inoperable, however in accordance with the TIS Bases, the loss of a single train of essential air is no more severe than the loss of one of the motor driven trains because the TD Pump can still supply 2 steam generators due to B train of air available.

C. Incorrect, Plausible since the first part of is correct. Also the candidate may get confused on whether the TD AFW train is also inoperable, however in accordance with the TIS Bases, the loss of a single train of essential air is no more severe than the loss of one of the motor driven trains because the TD Pump can still supply 2 steam generators due to B train of air available.

0. Incorrect, Plausible if the candidate thinks that 1-FCV-32-102 is also isolated by the AOP-M.02 for leak isolation. This valve would automatically isolate at 50 psig. Also the second part is correct.

Thursday, January 15, 20151:31:37 PM 94

QUESTIONS REPORT for 1503 SRO Exam Question Number: 93 Tier: _2_ Group 2 KIA: 079 Station Air System (SAS)

A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the SAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Cross-connection with IAS Importance Rating: 2.9 / 3.2 10 CFR Part 55: 41.5 / 43.5 / 45.3 / 45.13 10CFR55.43.b: 2 KIA Match: KA is matched because the question requires the ability to predict the impact a loss of air has on the operability of the AFW system and SRO because it requires using the information in the bases of the Tech Spec in determining the impact of the instrument air lineup.

Technical

Reference:

Technical Specification Bases AOP-M.02, Loss of Control Air, Rev. 23 Proposed references None to be provided:

Learning Objective: OPL271AOP-M.02 obj 7 & 8 Question Source:

New Modified Bank Bank x Question History: SQN bank question Comments:

Thursday, January 15, 20151:31:37 PM 95

QUESTIONS REPORT for 1503 SRO Exam

94. G 2.1.35 094 Given the following plant conditions:

Unit 2 is in Mode 6 with refueling operations in progress.

- The RCCA change fixture is empty.

One fuel assembly is being moved by the manipulator crane.

Subsequently:

- "LS-78-3 SPENT FUEL PIT LEVEL HIGH-LOW," (M6D, D-3) alarm is LIT.

- A reactor cavity seal failure is reported to the control room.

Which ONE of the following completes the statement below?

The fuel handling supervisor will direct the crane operator to place the fuel assembly into (1) , and in accordance with T.S. 3.9.10, "Water Level -

Reactor Vessel," bases, the reason for the minimum water level above the reactor vessel flange is to (2)

A. (1) the RCCA change fixture (2) limit the dose rate at the surface of reactor cavity to 5.0 R/hr B. (1) the RCCA change fixture (2) remove 99% of the iodine gap activity released from a ruptured irradiated fuel assembly C. (1) any available core location (2) limit the dose rate at the surface of reactor cavity to 5.0 R/hr D'!" (1) any available core location (2) remove 99% of the iodine gap activity released from a ruptured irradiated fuel assembly Thursday, January 15, 2015 1:40:28 PM 94

QUESTIONS REPORT for 1503 SRO Exam D/S TRACTOR ANAL YS/S:

A. Incorrect, Plausible since the AOP does have steps which discuss fuel assemblies in the RCCA change fixture, however the guidance is to remove any assemblies not put them into the fixture. Also plausible since a note in AOP-M.04 warns that lowering level above the Refueling cavity could cause radiation levels to rapidly rise, and there is a basis to limit the dose of CR operators to < 5 Rem/hr during a fuel handling accident, however this the basis for CREVS not minimum level above the fuel.

B. Incorrect, Plausible since the AOP does have steps which discuss fuel assemblies in the RCCA change fixture, however the guideance is to remove any assemblies not put them into the fixture. Also plausible since the second part is correct.

C. Incorrect, Plausible since the the first part is correct. Also plausible since a note in AOP-M.04 warns that lowering level above the Refueling cavity could cause radiation levels to rapidly rise, and there is a basis to limit the dose of CR operators to < 5 Rem/hr during a fuel handling accident, however this the basis for CREVS not minimum level above the fuel.

D. Correct, In accordance with AOP-M.04, the refueling SRO would direct the crane operator to place the assembly in any availabe core location to ensure it remains covered even if all water above the flange is lost. Also T. S. 3. 9. 10, 11 bases, the minimum water level above the Reactor vessel flange is to ensure sufficient water level is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly.

Thursday, January 15, 2015 1:40:28 PM 95

QUESTIONS REPORT for 1503 SRO Exam Question Number: 94 Tier: _3_ Group KIA: G 2.1.35 Knowledge of the fuel handling responsibilities of SRO's.

Importance Rating: 3.2 I 4.2 10 CFR Part 55: n/a 10CFR55.43.b: 2 KIA Match: This question matches the KIA by having the candidate identify the Tech Spec bases for fuel pool level.

SRO only by determining the required actions to be taken by the refueling SRO to mitigate a loss of level in the refueling cavity and the basis in Tech Spec for water level above the irradiated fuel.

Technical

Reference:

AOP-M.04, Refueling Malfunctions, rev 13 T.S. 3.9.10 & 11 Water Level - Reactor Vessel and Spent Fuel pool, basis.

Proposed references None to be provided:

Learning Objective: OPL271AOPM04 Question Source:

New X Modified Bank Bank Question History: New question written for 1503 Audit Exam Comments:

Thursday, January 15, 2015 1:40:28 PM 96

QUESTIONS REPORT for 1503 SRO Exam

95. G 2.2.17 095 Given the following plant conditions:

Both Units are operating at 100% power.

Maintenance activities require removing the A-A ERCW traveling screen from service to support diving operations.

Both the J-A and K-A ERCW pumps are removed from service in accordance with O-S0-67-1, "ERCW," and will be tagged as part of the clearance.

Which ONE of the following identifies the MINIMUM required Initial Risk Level classification and operability status of the 'A' Train ERCW Headers in accordance with NPG-SPP-07.3, "Work Activity Risk Management Process," and Tech Specs, respectively?

REFERNCE PROVIDED Minimum Required Risk Level Operability Status A. Low 'A' train ERCW is INOPERABLE B. Low 'A' train ERCW is OPERABLE C. High 'A' train ERCW is INOPERABLE High 'A' train ERCW is OPERABLE Thursday, January 15, 20151:58:11 PM 95

QUESTIONS REPORT for 1503 SRO Exam D/STRACTOR ANALYSIS:

A. Incorrect, Plausible since there are maintenance activities that are considered Low risk activities, however these activiites are single point vulnerability or direct Reactor trip hazard type items. Diving operations are not considered Low Risk activities (they are High Risk activities). Also the Train A ERCW is not inoperable as result of the diving activity even though 2 ERCW pumps are required to be removed from service to support the activity. Plausible because the Train A of ERCW will have 2 of the ERCW pumps removed from service.

B. Incorrect, Plausible since there are maintenance activities that are considered Low risk activities, however these activiites are single point vulnerability or direct Reactor trip hazard type items. Diving operations are not considered Low Risk activities (they are High Risk activities). Also the Train A ERCW does remain operable during the diving activity even though 2 ERCW pumps are required to be removed from service to support the activity. Plausible because there are activities designated as Site High Risk activities and the ERCW Train A remaining operable is correct.

C. Incorrect, Plausible since diving operations are High Risk activities, however the Train A ERCW is not inoperable as a result of the diving activity even though 2 ERCW pumps are required to be removed from service to support the activity.

Plausible because diving operations are considered High Risk activities and conditions on the Train A of ERCW will have 2 of the ERCW pumps removed from service.

D. Correct, In accordance with NPG-SPP-07. 3 all diving operations are considered as High Risk activities and in accordance with T. S. 3. 7. 4, the Train A of the ERCW system remains operable during the activity even though 2 of the ERGS pumps as well as the screen would be removed from service to support the diving activity.

Thursday, January 15, 20151:58:11 PM 96

QUESTIONS REPORT for 1503 SRO Exam Question Number: 95 Tier: _3_ Group n/a KIA: G 2.2.17 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.

Importance Rating: 2.6 I 3.8 10CFRPart55: 41.10/43.5/45.13 10CFRSS.43.b: 5 KIA Match: Question requires knowledge of the responsibilities of SROs during the process by which risk assessments are properly conducted for maintenance activities to be performed with the unit(s) on-line.

Technical

Reference:

NPG-SPP-07.3 Rev 16 Tech Spec 3.7.4 ERCW Proposed references NPG-SPP-07.3, Work Activity Risk Management to be provided: Process, Rev 16 Learning Objective: OPL271WMPI

8. In regards to the Work Management Schedule, be able to PERFORM the following:

e. DESCRIBE the method used for risk analysis.

OPT200.ERCW rev 7 obj. 11 d, f obj. 14 c Question Source:

New Modified Bank Bank x Question History: SON bank question G 2.2.17 with distractors A & B changed from Medium Risk to Site High Risk due to changes to NPG-SPP-07.3 procedure.

Comments:

Thursday, January 15, 2015 1:58:11 PM 97

QUESTIONS REPORT for 1503 SRO Exam

96. G 2.2.21 096 Given the following plant conditions:

Unit 1 is at 100% power.

Loop 4 OTDT circuit has been declared INOPERABLE and removed from service.

All applicable Tech Spec actions have been completed.

In accordance with Tech Spec LCO 3.0.6, which ONE of the following completes the statement below?

The instrument loop can ...

A. be restored to service to perform EITHER troubleshooting activities or post maintenance testing.

B. ONLY be restored to service to perform troubleshooting activities.

C"!' ONLY be restored to service to perform post maintenance testing.

D. NOT be restored to service to perform EITHER troubleshooting activities or post maintenance testing.

DISTRACTOR ANALYSIS:

A. Incorrect, Plausible if the candidate thinks that the instrument loop could be returned to service for either trouble shooting or for testing required to demonstrate operability, however only testing for operability is allowed.

B. Incorrect, Plausible if the candidate gets the direction of the LCO 3.0.6 confused and thinks that return to service under administrative control for trouble shooting would be allowed.

C. Correct, In accordance with LCO 3.0.6 equipment that has been declared inoperable and removed from service may be returned to service solely to perform testing required to demonstrate operability.

0. Incorrect, Plausible if the candidate thinks that the equipment cannot be returned to service for testing or troubleshooting if removed to comply with a Tech Spec LCO.

Thursday, January 15, 2015 2:05:50 PM 96

QUESTIONS REPORT for 1503 SRO Exam Question Number: 96 Tier: _3__ Group KIA: G 2.2.21 Knowledge of pre- and post- maintenance operability requirements.

Importance Rating: 2.9 I 4.1 10 CFR Part 55: 41.2 10CFR55.43.b: 2 KIA Match: This question matches the KIA by having the candidate identify the requirements for post maintenance testing of valves that are required for Tech Specs.

SRO only because it requires knowledge of generic Tech Spec surveillance procedures.

Technical

Reference:

LCO 3.0.6 Proposed references None to be provided:

Learning Objective: OPT200. TS-APP Question Source:

New Modified Bank Bank x Question History: SQN bank question Comments:

Thursday, January 15, 2015 2:05:50 PM 97

QUESTIONS REPORT for 1503 SRO Exam

97. G 2.3.13 097 Given the following plant conditions:

Unit 2 is at 100% power.

An unscheduled entry into the Unit 2 containment is required to inspect inside the Polar Crane wall.

Which ONE of the following identifies both the incore detector placement requirements and the MINIMUM permission required to make the containment entry?

Required lncore Flux Detector Placement Permission Required.

A. Storage position or inserted Rad Protection Manager ONLY to within 10 ft of the core and tagged B'!"' Storage position or inserted Rad Protection Manager and to within 10 ft of the core and tagged Plant Manager C. Storage position ONLY Rad Protection Manager ONLY D. Storage position ONLY Rad Protection Manager and Plant Manager D/S TRACTOR ANALYSIS:

A. Incorrect, Plausible since the first part is correct. Also plausible since if the plant was in Mode 2 the Rad Protection manager is the only authorization needed for entry.

B. Correct, In accordance with O-Pl-OPS-000-011.0, the incore instruments must be either in their storage location or could be within 1O ft of the core and tagged to allow a containment entry. Also for an unplanned entry during Mode 1 both the Plant Manger and the Rad Protection Manager must authorize this entry.

C. Incorrect, Plausible to think that the incore instruments must be within their storage location to allow an entry into containment. Also plausible since if the plant was in Mode 2 the Rad Protection manager is the only autorization needed for entry.

D. Incorrect, Plausible to think that the incore instruments must be within their storage location to allow an entry into containment. Also second part is correct.

Thursday, January 15, 2015 2: 11 :08 PM 97

QUESTIONS REPORT for 1503 SRO Exam Question Number: 97 Tier: _3__ Group KIA: G 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Importance Rating: 3.4 I 3.8 10 CFR Part 55: 41.12 10CFR55.43.b: 4 KIA Match: This question matches the KIA by testing the candidates knowledge of the radiation protection requirements for containment entry during power operation.

SRO only because it requires detailed knowledge of the requirements to allow entry into containment and administrative requirements for containment entry. This is performed by the SROs at SON.

Technical

Reference:

O-Pl-OPS-000-011.0 rev 15 RCl-10 rev 36 Proposed references None to be provided:

Learning Objective: OPL271 C260 Rad Pro Stds rev 9 Question Source:

New Modified Bank Bank x Question History: SON bank question Comments:

Thursday, January 15, 2015 2:11:08 PM 98

QUESTIONS REPORT for 1503 SRO Exam

98. G 2.3.6 098 Given the following plant conditions:

Both units are at 100% power.

Rad Waste water inventory is approaching storage capacity.

- A release of the Monitor Tank is planned.

Non gaseous activity in the tank is higher than the 7.0E-6 uci/ml value listed in O-Sl-CEM-077-400.1, "Liquid Waste Effluent Batch Release," for opening a Batch Release Permit.

O-RM-90-122, Liquid Radwaste Release Monitor, has been declared INOPERABLE.

Which ONE of the following identifies the requirements regarding release of the Monitor Tank?

A. Cannot release due to activity levels.

B. Cannot release due to O-RM-90-122 being INOPERABLE.

C-t Comply with ODCM actions and perform release with Shift Manager approval.

D. Comply with ODCM actions and perform release. Shift Manager approval is NOT required.

Thursday, January 15, 2015 2:16:58 PM 98

QUESTIONS REPORT for 1503 SRO Exam D/S TRACTOR ANALYSIS:

A. Incorrect, RM does not required to be operable as long as 2 Independent samples of tank contents are analyzed, 2 Independent discharge valve alignment, 2 Independent release rate calculations are verified per ODCM 1.1.1. High activity level requires SM approval for release. Plausible if student knows high activity limit but does not know that the SM can authorize the release.

B. Incorrect, 2 Independent samples of tank contents are analyzed, 2 Independent discharge valve alignment, 2 Independent release rate calculations are verified per ODCM 1. 1. 1. High activity level requires SM approval for release. Plausible if student believes that to release a tank with high activity it would require active monitoring during the release.

C. Correct, In accordance with ODCM 1.1.1, 2 Independent samples of tank contents are analyzed, 2 Independent discharge valve alignment, 2 Independent release rate calculations are required to be verified. The high activity level requires SM approval for release.

0. Incorrect, 2 Independent samples of tank contents are analyzed, 2 Independent discharge valve alignment, 2 Independent release rate calculations are verified per ODCM 1. 1. 1. The high activity level requires SM approval for release. Plausible is student does not know requirement to have SM approval for releasing tank with high activity levels. Raising dilution flow adds to the plausibility of being able to release with a higher activity versus getting additional approvals.

Thursday, January 15, 2015 2:16:58 PM 99

QUESTIONS REPORT for 1503 SRO Exam Question Number: 98 Tier: _3__ Group KIA: G 2.3.6 Ability to approve release permits.

Importance Rating: 2.0 I 3.8 10 CFR Part 55: 41.13 10CFR55.43.b: 4 KIA Match: This question matches the KIA by having the candidate recall the requirements for approving a liquid release permit.

SRO only because it requires detailed knowledge of administrative requirements required to approve a release permit and whose authorization is needed if activity is above normal to a radiation monitor is out of service.

Technical

Reference:

O-Sl-CEM-077-400.1 Rev 56 ODCM 1.1.1 and Table 1.1.1.

O-S0-77-1 Rev 53 Proposed references None to be provided:

Learning Objective: OPT200.LRW obj. 13 Question Source:

New Modified Bank Bank x Question History: SQN bank question Comments:

Thursday, January 15, 2015 2:16:58 PM 100

QUESTIONS REPORT for 1503 SRO Exam

99. G 2.4.38 099 Given the following plant conditions:

A General Emergency has been declared.

The TSC and CECC have NOT been activated.

Which of the following identifies the limitations, if any, on the delegation of the Site Emergency Director responsibilities in accordance with the Radiological Emergency Plan Implementing Procedures?

Emergency Classification Determination of Escalation Protective Action Recommendations A'!' Can NOT be delegated Can NOT be delegated B. Can NOT be delegated Can be delegated C. Can be delegated Can NOT be delegated D. Can be delegated Can be delegated DISTRACTOR ANALYSIS:

A. Correct, In accordance with EPIP-1, the classification level cannot be delegated and with the CECC not staffed and active, the PAR could not be delegated by the SEO.

B. Incorrect, Plausible because the classification level not being delegated is correct and the determination of Protective Actions Recommendations (PAR) could be delegated to the CECC director if the CECC were staffed and activated.

C. Incorrect, Plausible because the SEO can delegate other responsibilities (such as filling out forms and contacting agencies EPIP-2) and with the CECC not being staffed, the PAR not being delegated is correct.

0. Incorrect, Plausible because the SEO can delegate other responsibilities (such as filling out forms and contacting agencies EPIP-2) and if the CECC were staffed and activated the PAR could be delegated.

Thursday, January 15, 2015 2:25:30 PM 99

QUESTIONS REPORT for 1503 SRO Exam Question Number: 99 Tier: _3_ Group n/a KIA: G 2.4 Emergency Procedures/Plan 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required.

Importance Rating: 2.4 I 4.4 10 CFR Part 55: 41.10 I 43.5 I 45.11 10CFR55.43.b: 4, 5 KIA Match: KIA is matched and is SRO only because the question requires the ability to take action as the SEO (emergency coordinator) and know the requirements and limitations duties of the position, including the recall of specific facts regarding SEO duties and their execution (what cannot be delegated).

Technical

Reference:

EPIP-1 Revision 51 EPIP-6 Revision 50 Proposed references None to be provided:

Learning Objective: OPL271.REP Cognitive Level:

Higher Lower X Question Source:

New Modified Bank Bank X Question History: WBN bank question G 2.4.38 100 used on the 05/2009 exam Comments:

Thursday, January 15, 2015 2:25:30 PM 100

QUESTIONS REPORT for 1503 SRO Exam 100. G 2.4.5 100 Given the following plant conditions:

- A Station Blackout has occurred.

Unit 1 is performing ECA-0.0, "Loss of All AC Power."

Per ECA-0.0, the SGs have been depressurized to 160 psig.

RCS subcooling based on core exit T/Cs is 10°F.

1A-A EOG is started and is supplying the 1A-A SDBD.

- The crew has reached the last step of ECA-0.0 and is preparing to transition to the appropriate recovery procedure.

- A RED Path exists on the Heat Sink CSF Status Tree.

Which ONE of the following identifies the required recovery strategy?

A. Transition to ECA-0.1, "Loss of All AC Power Recovery Without SI Required",

and enter FR-H.1, "Response to Loss of Secondary Heat Sink" when allowed by ECA-0.1.

B~ Transition to ECA-0.2, Loss of All AC Power Recovery With SI Required",

and enter FR-H.1, "Response to Loss of Secondary Heat Sink" when allowed by ECA-0.2.

C. Transition to FR-H.1, "Response to Loss of Secondary Heat Sink" upon exit from ECA-0.0. Perform ECA-0.1, "Loss of All AC Power Recovery Without SI Required", when FR-H.1 is complete.

D. Transition to FR-H.1, "Response to Loss of Secondary Heat Sink" upon exit from ECA-0.0. Perform ECA-0.2, "Loss of All AC Power Recovery With SI Required", when FR-H.1 is complete.

Thursday, January 15, 2015 2:34:02 PM 100

QUESTIONS REPORT for 1503 SRO Exam D/S TRACTOR ANALYSIS:

A. Incorrect, Plausible because with more subcooling the transition to ECA-0. 1 would be correct, however EGGS flow is required and the transition to ES-0. 2 would be made. Also plausible but not correct because entering FR-H. 1 is not done until identified in procedure would be correct.

B. Correct, EGGS flow is required because subcooling is insufficient, thus ECA-0.2 is the correct transition from ECA-0. 0. Status tree are monitored for information only until power is restored because the FRPs are written assuming a Train of shutdown power is available. The power will be restored in ECA-0. 2 and a step will address the resumption of Status Tree implementation.

C. Incorrect, CSFST are only monitored but not addressed until allowed in appropriate recovery procedure. Performance of ECA-0. 1 is also incorrect due to the lack of subcooling. Plausible because a Status Tree RED path is normally implemented immediately and ECA-0. 1 would be the correct recovery procedure if subcooling had been higher.

D. Incorrect, CSFST are only monitored but not addressed until allowed in appropriate recovery procedure. Performance of ECA-0. 2 is incorrect due to the lack of subcooling but it would be implemented prior to performance FR-H. 1. Plausible because a Status Tree RED path is normally implemented immediately and ECA-0. 2 is the correct recovery procedure.

Thursday, January 15, 2015 2:34:02 PM 101

QUESTIONS REPORT for 1503 SRO Exam Question Number: 100 Tier: _3_ Group: n/a KIA: G 2.4.5 Emergency Procedures I Plan Knoweldge of the organization of the operating procedures network for normal, abnormal, and emergency procedures.

Importance Rating: 3. 7 I 4.3 10 CFR Part 55: 41.10 10CFR55.43.b: 5 KIA Match: This question matches the KIA by having the candidate determine the correct procedures implementation necessary to mitigate the event.

SRO ONLY: SRO only because it requires detailed knowledge of the procedure content to correctly select the appropriate procedures to mitigate the event.

Technical

Reference:

EPM-4, User's Guide ECA-0.0 rev 26 ECA-0.1 rev 10 ECA-0.2 rev 10 Proposed references None to be provided:

Learning Objective: OPL271 EPM-4 OPL271 ECA-0.0 OPL271 ECA-0.2 Cognitive Level:

Higher x Lower x Question Source:

New Modified Bank Bank x Question History: SON bank question used on 09/2009 retake exam Comments:

Thursday, January 15, 2015 2:34:02 PM 102

ML15126A418

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