Text

2007 Written SRO Initial Exam
	ML072910375
Person / Time
Site:	Palisades
Issue date:	10/22/2007
From:	Hironori Peterson; NRC/RGN-III/DRS/OLB
To:	Schwarz C; Entergy Nuclear Operations
References
	50-255/07-301 50-255/07-301
	Download: ML072910375 (25)
	v • d • e

SRO Question 1 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 1 of 25 Question Number:

1 Source of Question:

NEW K/A:

000015/017 Reactor Coolant Pump (RCP) Malfunctions AA2.09 Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): When to secure RCPs on high stator temperatures.

Tier:

1 Group: 1 SRO Imp:

3.5 Applicable 10CFR55 Section:

43.5 Palisades Learning Objective: PCP_CK13.0

References:

ARP-5, windows 8, 9, rev 72; DBD 2.04, page 81.

Question:

From full power, the following occurs:

A loss of 4160VAC Bus 1A.

A Main Steam Line Break has occurred inside containment.

Containment High Pressure actuates.

What is the expected effect on the stator winding temperatures of the two operating Primary Coolant Pumps (PCP), and what procedural guidance will be used for this condition?

Stator winding temperatures will first begin rising....

a. after Component Cooling Water to containment isolates. The Emergency Operating Procedure requires establishing a temperature trend on the Plant Process Computer (PPC).

b. when the Main Steam Line Break occurs. The Alarm Response Procedure provides guidance to have the System Engineer evaluate the condition if stator temperatures exceed 140° C.

c. when the Main Steam Line Break occurs. The Alarm Response Procedure provides guidance to trip a PCP if stator temperatures exceed 185° F.

d. after Component Cooling Water to containment isolates. ONP-6.2, Loss of CCW, provides guidance to trip a PCP if stator temperatures exceed 140° C.

DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible if the student believes that CCW cools the motor stator. Only air flow through the motor cools that stator.

b.

CORRECT

c.

INCORRECT - Correct occurrence but wrong guidance. Plausible if the student believes that a PCP should be tripped due to high motor winding temperature.

d.

INCORRECT - Plausible if the student believes that CCW can affect motor winding temperature.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 2 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 2 of 25 Question Number:

2 Source of Question:

NEW K/A:

000025 Loss of Residual Heat Removal System (RHRS)

G2.1.2 Knowledge of operator responsibilities during all modes of plant operation.

Tier:

1 Group: 1 SRO Imp:

4.0 Applicable 10CFR55 Section:

43.2 Palisades Learning Objective: SDC_CK22.0

References:

ONP-17, 4.8; LCO-3.9.4.A.4, GOP-14 attachment 10, step 1.0 Question:

At 0948, a Loss of Shutdown Cooling event occurs. The plant is in MODE 6 with Reactor Cavity Water Level at 648 feet. The time for PCS temperature to reach 200°F is 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . Operators are dispatched to close the equipment hatch and to verify containment closure. Which one of the following lists the time by which the containment must be closed?

a. 1048

b. 1148

c. 1248

d. 1348 DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible if the student thinks because the in service SDC train can be secured for 1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period that the equipment hatch must be closed within this time. This is a requirement for MODE 5

b.

INCORRECT - Plausible if the student thinks because both SDC trains can be inoperable for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period that the equipment hatch must be closed within this time. This is a requirement for MODE 5

c.

CORRECT

d.

INCORRECT - Plausible if the student correctly believes that the containment must be closed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per LCO 3.9.4.A.4, however, ONP-17, 4.8 and GOP-14 attachment 10, section 1.0 states that containment closure shall be completed prior to exceeding the time for the PCS to reach 200°F.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 3 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 3 of 25 Question Number:

3 Source of Question:

NEW K/A:

000026 Loss of Component Cooling Water (CCW)

AA2.01 Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: Location of a leak in the CCWS.

Tier:

1 Group: 1 SRO Imp:

3.5 Applicable 10CFR55 Section:

43.5 Palisades Learning Objective: CCW_CK22.0

References:

SOP-16, 4.1.3; T.S. 3.7.7 Basis; LCO 3.0.3 Question:

With the plant in MODE 1, the shell side of E-54A, Component Cooling Water (CCW) Heat Exchanger developed a leak and had to be isolated from the header to stop the leak. How does this affect the CCW System's ability to perform its design function, and which guidance applies?

100% of CCW post accident cooling capability is...

a. still available. SOP-16, Component Cooling Water System, requires starting an additional CCW pump to maintain E-54B CCW Hx differential pressure within required limits.

b. NOT available. ONP-6.2 Attachment 1, CCW Leak Isolation, is performed to restore required post accident cooling capability.

c. still available. Technical Specification 3.7.7, CCW System, requires that E-54A CCW Heat Exchanger be restored to service within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

d. NOT available. Technical Specification 3.0.3 requires initiating actions for plant shutdown within one hour.

DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible if the student applies the requirements associated with securing SW to the tube side of a CCW heat exchanger.

b.

INCORRECT - Plausible if the student believes that ONP-6.2 entry is appropriate for this condition.

c.

INCORRECT - Plausible if the student believes that only condition A is applicable for this condition.

d.

CORRECT - Per LCO 3.7.7 and 3.03 Level of Knowledge:

HIGH Difficulty:

3

SRO Question 4 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 4 of 25 Question Number:

4 Source of Question:

NEW K/A:

000027 Pressurizer Pressure Control System (PZR PCS) Malfunction G2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

Tier:

1 Group: 1 SRO Imp:

3.7 Applicable 10CFR55 Section:

43.2 Palisades Learning Objective: PPCS_CK22.0

References:

Tech. Spec 3.4.9 Basis, page 3.4.9-3 Question:

A Surveillance Requirement in the Technical Specifications requires the alternate power supply for Pressurizer heaters to be capable of powering the affected heaters within five (5) hours. What is the basis for these five (5) hours?

a. Ensures that a 20° F subcooling margin, due to pressure decay, is not exceeded.

b. Allows the operating crew to evaluate stripping unneeded Bus 1C loads to prevent overloading D/G 1-1.

c. Prevents exceeding 375 kW on the remaining heaters which have power from Bus 1D.

d. Ensures full restoration of all Pressurizer Heaters in order to preclude reactor head voiding.

DISTRACTOR ANALYSIS

a.

CORRECT

b.

INCORRECT - Plausible if the student believes that the most limiting equipment in this situation is the D/G 1-1.

c.

INCORRECT - Plausible if the student misapplies tech spec 3.9.4 and believes that each bus is limited to supplying 375 kW.

d.

INCORRECT - Plausible if the student believes the limiting scenario is a bubble moving from the PZR to the Reactor Head.

Level of Knowledge:

LOW Difficulty:

3

SRO Question 5 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 5 of 25 Question Number:

5 Source of Question:

NEW K/A:

000056 Loss of Offsite Power AA2.06 Ability to determine and interpret the following as they apply to the Loss of Offsite Power:

Operational status of CCW pump.

Tier:

1 Group: 1 SRO Imp:

3.6 Applicable 10CFR55 Section:

43.5 Palisades Learning Objective: IOTF_CK03.0

References:

ONP-2.1, Attachment 3, Step 3 Question:

With the plant at full power a loss of all offsite power occurs. D/G 1-1 FAILS to start automatically, or manually. Which one of the following describes an effect on the noted Component Cooling Water Pump, and what procedure will be used to address the concern?

a. P-52B discharge pressure may be less than required. Per SOP-16, Component Cooling Water System, stop P-52B if CCW heat exchanger deltaP limits are exceeded.

b. P-52A discharge pressure may be less than required. Per ONP-6.2, Loss of CCW, start all available CCW pumps.

c. P-52B discharge pressure may be less than required. Per ONP-2.1, Loss of AC Power, isolate selected radwaste loads if needed to restore discharge pressure.

d. P-52C discharge pressure may be less than required. Per SOP-16, Component Cooling Water System, isolate selected radwaste loads to restore discharge pressure.

DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible if the student believes that SOP-16 contains guidance to control CCW HX dP by stopping a CCW pump. Student also fails to recognize that HX dP limits are for optimal operation of the pump and not an immediate operational concern.

b.

INCORRECT - Plausible if the student believes that P-52A will be in service. If D/G 1-1 fails to start, power will not be available to P-52A during a loss of off-site power.

c.

CORRECT

d.

INCORRECT - Plausible if the student believes that P-52C will be in service. If D/G 1-1 fails to start, power will not be available to P-52C during a loss of off-site power Level of Knowledge:

HIGH Difficulty:

3

SRO Question 6 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 6 of 25 Question Number:

6 Source of Question:

BANK - Palisades K/A:

000058 Loss of DC Power G2.4.15 Knowledge of communications procedures associated with EOP implementation.

Tier:

1 Group: 1 SRO Imp:

3.5 Applicable 10CFR55 Section:

43.1 Palisades Learning Objective: PL-N00109, APOR_E01.05

References:

EI-3, 5.2.1.c Question:

A manual reactor trip has occurred due to a loss of DC Bus D21-2. The NRC must be notified...

a. after notifying the county and state but no longer than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from classification per EI-3, Communications and Notifications.

b. after notifying the county and state but no longer than 15 minutes from classification per EI-3, Communications and Notifications.

c. of a non-emergency event within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per ADMIN 4.00, Operations Organization, Responsibilities and Conduct.

d. via the Emergency Response Data System (ERDS) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 10CFR50.72.

DISTRACTOR ANALYSIS

a.

CORRECT -

b.

INCORRECT - Plausible if the student believes that the NRC must be notified in the same time frame as the local and state authorities.

c.

INCORRECT-Plausible if the student believes that this is a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reportability issue.

d.

INCORRECT - Plausible if the student believes that ERDS is an acceptable form of notification.

Level of Knowledge:

HIGH Difficulty:

2 This is HIGH Cog because the candidate needs to recognize that a loss of D21-2 will cause a loss of all annunciators in the control room which is classified as an unusual event (UE) and will require entry into the functional recovery procedure, EOP-9.0.

SRO Question 7 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 7 of 25 Question Number:

7 Source of Question:

MODIFIED BANK - Palisades K/A:

000005 Inoperable / Stuck Control Rod G2.1.10 Knowledge of conditions and limitations in the facility license.

Tier:

1 Group: 2 SRO Imp:

3.9 Applicable 10CFR55 Section:

43.2 Palisades Learning Objective: CRD_CK22.0

References:

Tech. Spec. 3.1.4.E; TS Basis 3.1.4 page 7 Question:

A plant startup is in progress at 13% power. A review of post-maintenance documentation indicates that there is NO reasonable assurance that control rod 17 is trippable. The control room team has determined that the required action is to place the plant in MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

What is the Technical Specification basis for this action?

a. Quadrant Power Tilt (QPT) limit may be exceeded with one stuck rod.

b. ASI limit may be exceeded with one stuck rod.

c. The plant is outside of the safety analysis since one additional rod is assumed to stick on a reactor trip.

d. The plant is outside of the safety analysis since all shutdown rods are assumed to insert on a reactor trip to achieve a 3.5% shutdown margin.

DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible if the student believes that the stuck control rod will have a large effect on QPT. QPT not applicable < 25% power.

b.

INCORRECT - Plausible if the student believes that the stuck control rod will have a large effect on ASI. ASI not applicable < 25% power

c.

CORRECT - The safety analyses assumes one stuck rod (other than 34), this stuck rod would place the plant in a condition outside the analyses.

d.

INCORRECT - The safety analysis assumes an additional stuck rod, it does not specifiy if it is a shutdown or regulating rod Level of Knowledge:

HIGH Difficulty:

3

SRO Question 8 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 8 of 25 Question Number:

8 Source of Question:

NEW K/A:

000033 Loss of Intermediate Range Nuclear Instrumentation AA2.08 Ability to determine and interpret the following as they apply to the Loss of Intermediate Range Nuclear Instrumentation: Intermediate range channel operability.

Tier:

1 Group: 2 SRO Imp:

3.4 Applicable 10CFR55 Section:

43.2, 43.5 Palisades Learning Objective: IOTF2_E04.01

References:

LCO 3.3.9 bases page 2 Question:

With the plant shutdown in MODE 5 alarm EK-0608C NI CHANNEL TROUBLE annunciates. It is determined that the cause of the alarm is Wide Range Nuclear Instrument 4A channel failing low.

Which one of the following accurately describes the operability of the Source Range/Wide Range Neutron Flux Monitoring Channels?

a. Declare one channel inoperable. Enter LCO 3.3.9, Neutron Flux Monitoring Channels.

b. Both channels remain operable if Source Range NI-2A is capable of detecting the existing neutron flux and is in reasonable agreement with Source Range NI-1A.

c. Declare one channel inoperable. No LCO action statement should be entered because only one channel is required to be operable in the current MODE.

d. Both channels remain operable if Wide Range Nuclear Instrument 4A detector voltage remains above 45VDC.

DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible if the student misapplies the tech spec and interprets a neutron flux channel as requiring both a WR and SR NI to be operable.

b.

CORRECT -

c.

INCORRECT - Plausible if the student believes that only one channel of neutron flux instruments is required since the plant is in MODE 5 and not refueling.

d.

INCORRECT - Plausible if the student believes that the detector is still able to detect a flux but is not indicating due to a low power supply voltage.

Level of Knowledge:

HIGH Difficulty:

4

SRO Question 9 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 9 of 25 Question Number:

9 Source of Question:

NEW K/A:

000076 High Reactor Coolant Activity G2.4.36 Knowledge of chemistry / health physics tasks during emergency operations.

Tier:

1 Group: 2 SRO Imp:

2.8 Applicable 10CFR55 Section:

43.5 Palisades Learning Objective: TBCORE_CP06.0

References:

EOP-5.0, step 1.b Question:

The plant is currently in action level 3 for high dose equivalent Iodine-131 due to fuel cladding leaks.

Steam Generator Blowdown Radiation Monitor, RIA-0707, is out of service. A Steam Generator tube rupture event then occurs. Safety Injection Actuation has not occurred. To confirm proper event diagnosis, Chemistry technicians will be directed to sample:

a. Steam Generators for boron and activity.

b. Blowdown Demineralizers effluent for boron and activity.

c. Steam Generators for lithium and activity.

d. Blowdown Demineralizers effluent for lithium and activity.

DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible if the student believes that boron concentration in the S/G is meaningful. Boron is added to the S/Gs under normal operation to prevent S/G tube denting.

b.

INCORRECT - Plausible if the student believes that this would be a good place to sample to ensure dose levels are lower to personnel. However, the demineralizers would remove much of the activity.

c.

CORRECT

d.

INCORRECT - Plausible for the same reason as b.

Level of Knowledge:

LOW Difficulty:

3

SRO Question 10 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 10 of 25 Question Number:

10 Source of Question:

NEW K/A:

CE/A11 RCS Overcooling - PTS AA2.1 Ability to determine and interpret the following as they apply to the (RCS Overcooling)

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

Tier:

1 Group: 2 SRO Imp:

3.3 Applicable 10CFR55 Section:

43.5 Palisades Learning Objective: TBAD_E03.01

References:

EOP-1.0, Event Diagnostic Flow Chart; EOP-6.0 basis step 14 and 16 Question:

Given the following conditions:

Reactor Protective system has initiated a trip from a valid Containment High Pressure (CHP) signal PCS Pressure is 1190 psia PZR Level is 12%

A S/G Pressure is 850 psia, B S/G Pressure is 520 psia TC in both loops are lowering PCS subcooling is 95 °F EOP-1.0 Standard Post Trip Actions has been completed Which one of the following describes (1) the appropriate procedure to enter, (2) the actions that need to be taken, and (3) the reason for the actions?

a. (1) EOP-6.0, Excess Steam Demand Event (2) Isolate the B Steam Generator per EOP supplement 18 AND maintain 'A' S/G pressure within 50 psi of 'B" S/G.

(3) This will isolate the affected S/G and maintain heat removal to avoid a pressurized thermal shock condition.

b. (1) EOP-6.0, Excess Steam Demand Event (2) Isolate the B Steam Generator per EOP supplement 18 AND maintain 'A' S/G pressure within 50 psi of 'B' S/G after 'B' S/G indicates it has boiled dry.

(3) This will prevent overcooling the PCS to avoid a pressurized thermal shock condition.

c. (1) EOP-9.0, Functional Recovery Procedure (2) Isolate the B Steam Generator per EOP supplement 18 when level reaches -84% AND stabilize PCS temperature with A Steam Generator per EOP-6.0 (3) This allows maximum safety injection flow for Pressurizer level recovery

d. (1) EOP-9.0, Functional Recovery Procedure (2) Isolate BOTH Steam Generators per EOP supplement 17 and 18 AND establish once-through cooling per EOP-9.0.

(3) This prevents challenging the Containment design pressure limit of 55 psig.

DISTRACTOR ANALYSIS

a.

CORRECT -

b.

INCORRECT - Plausible if the student believes that A S/G should NOT be steamed until after B S/G is dry to prevent adding to the cooldown.

c.

INCORRECT - Plausible if the student believes that EOP-9.0 is the correct procedure to enter. The student could believe that there is a ESDE in A S/G also since TC in both loops is lowering.

d.

INCORRECT - Plausible if the student believes that there is also an ESDE in A S/G and once-through cooling needs to be established due to isolation of both S/Gs.

Level of Knowledge:

HIGH Difficulty:

2

SRO Question 11 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 11 of 25 Question Number:

11 Source of Question:

NEW K/A:

003 Reactor Coolant Pump System (RCPS)

A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Problems associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems.

Tier:

2 Group: 1 SRO Imp:

3.1 Applicable 10CFR55 Section:

43.5 Palisades Learning Objective: PCP_CK13.0

References:

ARP-5, EK-0937, 0938, 0939, E-186 sheet 1, 4 Question:

WIth the plant operating at 50% power, EK-0937, EK-0938 and EK-0939, "PRI COOLANT PUMP P-50A, P-50B, P-50C BACKSTOP OIL LOW FLOW" annunciate simultaneously and do not clear. Which one of the following describes the correct action to take?

a. Immediately trip the reactor and enter EOP-1.0, "Standard Post Trip Actions." Trip P-50A, P-50B, and P-50C, because backstop oil flow to these pumps is lost.

b. Immediately start the DC backstop oil pump because power has been lost to all AC backstop oil pumps.

c. Dispatch Electrical Maintenance to check amps on supply breakers to backstop oil pumps to verify one backstop oil pump is running for each PCP.

d. Perform a normal plant shutdown per GOP-8, Shutdown to MODE 2 or MODE 3 525 °F, because the backstop device can only operate for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months without oil flow.

DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible if the student believes that this alarm is indicative of no backstop oil flow and damage to the PCP is imminent.

b.

INCORRECT - Plausible if the student confuses the backstop pumps with the lift pumps

c.

CORRECT

d.

INCORRECT - Plausible if the student believes that there is no backstop oil flow and there is no immediate concern for damage to the PCP. This is plausible because P-50D does not have a backstop oil pump.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 12 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 12 of 25 Question Number:

12 Source of Question:

NEW K/A:

005 Residual Heat Removal System (RHRS)

G2.4.3 Ability to identify post-accident instrumentation.

Tier:

2 Group: 1 SRO Imp:

3.8 Applicable 10CFR55 Section:

43.2 Palisades Learning Objective: PCS_CK22.0

References:

Tech. Spec. 3.3.7, Table 3.3.7-1 Question:

Which one of the following instrumentation indications that are used during Shutdown Cooling operations is also identified as post-accident monitoring instrumentation per Technical Specifications?

a. FIC-0306, SDC HX Bypass Flow

b. PIA-0306, LPSI Pump Discharge Pressure

c. TI-0912, SDC HX CCW Outlet Temperature

d. Cold Leg Temperature (wide range)

DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible if the student believes that, since SI flow is through the bypass on SDC HX, this flow indicator would be required during accident conditions.

b.

INCORRECT - Plausible if the student believes that LPSI discharge pressure is important during a large break LOCA.

c.

INCORRECT - Plausible if the student believes that this indication is important when a RAS initiates.

d.

CORRECT Level of Knowledge:

LOW Difficulty:

4

SRO Question 13 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 13 of 25 Question Number:

13 Source of Question:

NEW K/A:

026 Containment Spray System (CSS)

A2.02 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 of operations:

Failure of automatic recirculation transfer.

Tier:

2 Group: 1 SRO Imp:

4.4 Applicable 10CFR55 Section:

43.5 Palisades Learning Objective: TBAG_E01.02

References:

EOP Supplement 42 step 2.0.b.2); P&ID M-204 sheet 1 & 1A Question:

During a LOCA with all Safety Injection pumps and Containment Spray pumps operating, SIRWT level reaches 2% and a RAS initiates. All equipment has been verified aligned per RAS with the exception of CV-3029, East ESG Containment Sump Isolation, which does not open. How does this impact operation of the Containment Spray and Safety Injection systems and what action(s) need(s) to be taken?

a. Left channel Containment Spray and HPSI Pumps have lost suction from containment sump.

Initiate post-RAS injection from Spent Fuel Pool per EOP Supplement 44.

b. Right channel Containment Spray and HPSI Pumps have lost suction from containment sump.

STOP Containment Spray Pump P-54A AND ensure OPEN CV-3071, P-66A subcooling valve per EOP Supplement 42.

c. Left channel Containment Spray and HPSI Pumps have lost suction from containment sump.

Initiate post-RAS refill of SIRW Tank per EOP Supplement 43.

d. Right channel Containment Spray and HPSI Pumps have lost suction from containment sump.

STOP Containment Spray Pump P-54A AND P-66A, HPSI Pump per EOP-4.0 Operator Actions.

DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible is the student believes that CV-3029 is associated with left channel equipment.

b.

CORRECT - EOP-4.0 step 52 directs performance of EOP Supplement 42 when SIRW Tank level reaches 2%. EOP Supplement 42 directs P-54A be secured and CV-3071 verified open if CV-3029 does not open on RAS. CV-3029 supplies all right channel safety injection and containment spray pumps. P-67A trips on RAS, P-54A needs to be tripped for equipment protection, and P-66A will continue to operate as long as CV-3071 is open which is supplied from the containment spray header (P-54B and P-54C)

c.

INCORRECT - Plausible for same reason as a

d.

INCORRECT - Plausible if the student fails to recognize that P-66A still has suction available from the left train CSS pumps via CV-3071.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 14 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 14 of 25 Question Number:

14 Source of Question:

BANK 2001 NRC SRO K/A:

039 Main and Reheat Steam System (MRSS)

G2.3.11 Ability to control radiation releases.

Tier:

2 Group: 1 SRO Imp:

3.2 Applicable 10CFR55 Section:

43.4 Palisades Learning Objective: TBAF_E01.01

References:

EOP-5.0 Basis, page 62 Question:

During a Steam Generator Tube Rupture, why do we use the turbine bypass valve (TBV) instead of the atmospheric dump valves (ADVs)?

a. Minimizes the release of radioactivity.

b. Ensures availability of Steam Driven Aux. Feedwater P-8B.

c. Minimizes PCS shrinkage due to excess cooldown.

d. Ensures finer control over PCS temperature and pressure.

DISTRACTOR ANALYSIS

a.

CORRECT -

b.

INCORRECT - Plausible if the student believes that P-8B exhaust is directed to the Main Condenser. When the TBV is used, condenser vacuum is maintained;

c.

INCORRECT - Plausible due to difference in steam flow (15%) from ADVs associated with one S/G versus steam flow from TBV (4.5%).

d.

INCORRECT - Plausible from same reason as c.

Level of Knowledge:

LOW Difficulty:

2

SRO Question 15 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 15 of 25 Question Number:

15 Source of Question:

MODIFIED - Palisades 2005 NRC K/A:

073 Process Radiation Monitoring (PRM) System A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure.

Tier:

2 Group: 1 SRO Imp:

3.2 Applicable 10CFR55 Section:

43.5 Palisades Learning Objective: CRHV_E01.01

References:

ARP-33, window 39; SOP-24, section 4.3.5 Question:

Given the following conditions:

The plant is at full power.

"A" Train of Control Room HVAC is in service in Normal Mode.

The following alarm annunciates:

o EK-0239, "CRHVAC TRAIN A RIA-1818A HI RAD/FAIL" It is determined that RIA-1818A has failed and is inoperable.

What are the consequences of continuing to operate the A Train Control Room HVAC system and what actions will be taken to mitigate this condition?

a. If radiation entered the Control Room envelope, the A train would not be able to automatically swap to Emergency Mode. The affected CRHVAC Train (A) shall be placed in Emergency Mode within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , OR the opposite CRHVAC train (B) must be started within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , AND the affected train must be Caution Tagged to only run in Purge Mode.

b. If radiation entered the Control Room envelope, the A train would not be able to automatically swap to Emergency Mode. The affected CRHVAC Train (A) shall be placed in Emergency Mode immediately, OR the opposite CRHVAC train (B) must be started immediately, AND the affected train must be Caution Tagged to only run in Emergency Mode.

c. Any radioactive contamination entering the Control Room envelope from the outside will not be detected. The affected CRHVAC Train (A) shall be placed in Emergency Mode immediately, OR the opposite CRHVAC train (B) must be started immediately, AND the affected train must be Caution Tagged to only run in Emergency Mode.

d. Any radioactive contamination entering the Control Room envelope from the outside will not be detected. The affected CRHVAC Train (A) shall be placed in Emergency Mode within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , OR the opposite CRHVAC train (B) must be started within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , AND the affected train must be Caution Tagged to only run in Purge Mode.

DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible if the student believes that RIA-1818A will cause the Control Room HVAC system to automatically swap to emergency; this provides an indication and alarm feature only. Also if the student believes that purge mode will keep radioactivity out of the control room.

b.

INCORRECT - Plausible for same reason as a.

c.

CORRECT.

d.

INCORRECT - Correct consequence, incorrect action. Plausible if the student believes that purge mode will keep radioactivity out of the control room.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 16 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 16 of 25 Question Number:

16 Source of Question:

NEW K/A:

015 Nuclear Instrumentation G2.1.12 Ability to apply technical specifications for a system.

Tier:

2 Group: 2 SRO Imp:

4.0 Applicable 10CFR55 Section:

43.2, 43.5 Palisades Learning Objective: IOTF2_E05.01

References:

LCO 3.3.1.A; SOP-35, 7.2.2.c Question:

Given the following:

The plant is at 100% power.

NI-05, Power Range Nuclear Instrument, experiences a failed power supply.

Which one of the following actions should be taken for this condition?

a. Place Variable High Power Trip (VHPT) for RPS channel 'A' in trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b. Bypass VHPT, TM/LP, Loss of Load, and High Power Rate for RPS channel 'A'.

c. Lower reactor power to 70 % within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

d. Perform a Quadrant Power Tilt calculation per PO-3, "Alternate Incore and Excore Applications" using excore detectors.

DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible because VHPT is bypassed but not tripped

b.

CORRECT

c.

INCORRECT - Plausible because this is the action for 2 PRNIs inoperable

d.

INCORRECT - Plausible because power range channels can be used to monitor LHR, however, the in-core NIs are used to monitor LHR.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 17 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 17 of 25 Question Number:

17 Source of Question:

NEW K/A:

055 Condenser Air Removal G2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Tier:

2 Group: 2 SRO Imp:

4.0 Applicable 10CFR55 Section:

43.5 Palisades Learning Objective: IOTA_T06.0

References:

SOP-13, section 4.1.1 Question:

During a secondary plant startup, the following conditions exist:

Condensate Pump, P-2A, is in service.

Both Cooling Tower Pumps, P-39A/B, are in service.

All of the following are required to be available for the startup except:

a. Hogging jet and/or Condenser Vacuum Pump (P-910)

b. One Primary and one Secondary Air Ejector Jet

c. One Gland Condenser Exhauster (C-1A/B)

d. One Circ Water Priming Pump (C-16A/B)

DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible if the student believes that the steam jet air ejectors can draw a vacuum on the main condenser starting at 0 Hg.

b.

INCORRECT - Plausible if the student believes that the Hogging Jet air ejector or Condenser Vacuum Pump can draw a full vacuum on the main condenser.

c.

INCORRECT - Plausible if the student believes that a gland exhauster is not required to draw a vacuum.

d.

CORRECT Level of Knowledge:

LOW Difficulty:

3

SRO Question 18 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 18 of 25 Question Number:

18 Source of Question:

NEW K/A:

068 Liquid Radwaste System (LRS)

A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of automatic isolation.

Tier:

2 Group: 2 SRO Imp:

3.3 Applicable 10CFR55 Section:

43.5 Palisades Learning Objective: RMS_CK09.0

References:

ARP-8, window 65 and Attachment 3 Question:

A liquid radwaste batch release of Utility Water Storage Tank T-91 is in progress via CV-1049, 3" Discharge Isolation. RIA-1049 reaches its high alarm setpoint and EK-1365, Process Liquid Monitoring Hi Radiation alarms, but CV-1049 does NOT automatically close.

Based on these conditions, you must...

a. have the release terminated by selecting handswitch for CV-1049 to close, and refer to EI-8, Onsite Radiological Monitoring.

b. have the release terminated by closing MV-CRW172, Discharge to Lake, and refer to EI-1, Emergency Classification and Actions.

c. have the release terminated by selecting handswitch for CV-1049 to close, and refer to EI-1, Emergency Classification and Actions.

d. have the release terminated by closing MV-CRW172, Discharge to Lake, and refer to EI-8, Onsite Radiological Monitoring.

DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible if the student believed that the correct action was to close CV-1049, however, the correct action is to close MV-CRW172. Also the student would believe that EI-8 was the correct procedure.

b.

CORRECT

c.

INCORRECT - Plausible if the student believed that the correct action was to close CV-1049.

d.

INCORRECT - Plausible if the student believes that the correct procedure to use is EI-8.

Level of Knowledge:

LOW Difficulty:

4

SRO Question 19 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 19 of 25 Question Number:

19 Source of Question:

BANK 2001 NRC SRO K/A:

G2.1.10 Knowledge of conditions and limitations in the facility license.

Tier:

3 Group:

SRO Imp:

3.9 Applicable 10CFR55 Section:

43.2 Palisades Learning Objective: APTS_E01.11

References:

TS-2.1.2 Question:

What is the Safety Limit for PCS pressure when the plant is in MODE 5?

a. 500 psia

b. 750 psia

c. 2650 psia

d. 2750 psia DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible as this is the setpoint for LTOP setting at 200°F.

b.

INCORRECT - Plausible as this is the setpoint for LTOP setting at 300°F

c.

INCORRECT - Plausible as this is the 3rd PZR Safety Valve setting.

d.

CORRECT Level of Knowledge:

LOW Difficulty:

2

SRO Question 20 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 20 of 25 Question Number:

20 Source of Question:

MODIFIED - BANK 2003 NRC SRO K/A:

G2.1.22 Ability to determine Mode of Operation.

Tier:

3 Group:

SRO Imp:

3.3 Applicable 10CFR55 Section:

43.5 Palisades Learning Objective: APTS_E01.04

References:

Tech. Spec. Table 1.1-1; GOP-4, Att.1, 1.12 Question:

For the following conditions:

A plant startup is in progress Reactor is critical at 3% power TAVE is 532 ºF Which one of the following describes the MODE change, if any, and the minimum required authorization, if any, when power is raised to 7%?

a. No MODE change. No approvals required.

b. MODE 2 to MODE 1 and requires authorization from the Site Vice President.

c. MODE 2 to MODE 1 and requires authorization from the Plant Manager.

d. MODE 2 to MODE 1 and requires authorization from the Operations Manager.

DISTRACTOR ANALYSIS

a.

INCORRECT - Mode change occurs at 5%.

b.

INCORRECT - Correct mode change, incorrect approver

c.

CORRECT -

d.

INCORRECT - Correct mode change, incorrect approver.

Level of Knowledge:

LOW Difficulty:

2

SRO Question 21 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 21 of 25 Question Number:

21 Source of Question:

NEW K/A:

G2.2.14 Knowledge of the process for making configuration changes.

Tier:

3 Group:

SRO Imp:

3.0 Applicable 10CFR55 Section:

43.3 Palisades Learning Objective: APES_E01.07, APES_E01.02

References:

Admin 4.02, 5.8.1.i Question:

To maintain the plant at power operations, a fuse replacement is required for a non-safety related component. A comparable fuse is available; however an identical fuse is NOT available. The design change process has NOT been completed. A Work Order has been created for use of the comparable fuse.

The comparable fuse may...

a. not be used for this application, since the design change process has not been implemented.

b. be used since it will be controlled by the Work Order.

c. be used since it involves maintaining power operations.

d. not be used since the plant is above Mode 5.

DISTRACTOR ANALYSIS

a.

INCORRECT - Incorrect action, incorrect reason

b.

CORRECT

c.

INCORRECT - Correct action, incorrect reason

d.

INCORRECT - Incorrect action, incorrect reason Level of Knowledge:

LOW Difficulty:

3

SRO Question 22 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 22 of 25 Question Number:

22 Source of Question:

BANK - STP 2003 SRO K/A:

G2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

Tier:

3 Group:

SRO Imp:

3.1 Applicable 10CFR55 Section:

43.4 Palisades Learning Objective: APWC_T04.00

References:

EI-2.1, 6.14 Question:

A LOCA inside containment has occurred and a Site Area Emergency has been declared. The Technical Support Center and EOF have been activated. To prevent core damage it is recommended that an entry be made into East Safeguards. The projected dose rate in this room is 124 R/hr.

Duration of the exposure is expected to be 3 minutes. Who must authorize this exposure?

a. Plant Manager

b. Site Vice President

c. Site Emergency Director

d. Health Physics Supervisor DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible because the Plant Manager can authorize exceeding plant administrative levels.

b.

INCORRECT - Plausible for same reason as a.

c.

CORRECT -

d.

INCORRECT - Plausible because a Health Physics technician can authorize exceeding 10CFR20 limits but only in the case of immediate life saving.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 23 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 23 of 25 Question Number:

23 Source of Question:

NEW K/A:

G2.3.6 Knowledge of the requirements for reviewing and approving release permits.

Tier:

3 Group:

SRO Imp:

3.1 Applicable 10CFR55 Section:

43.4 Palisades Learning Objective: RMS_T02.00

References:

HP-6.6 form HP 6.6.-3 Question:

A waste gas release is being planned for Waste Gas Decay Tanks, T-101C and T-68A. Samples have been completed and analyzed per HP-6.5, Sampling Waste Gas Decay Tank, and HP-6.6, Evaluation and Release of Waste Gas Decay Tank." The following information is contained on the batch release forms for T-101C and T-68A: NOTE: Todays date/time is 9/14/2007@1800 T-101C T-68A Sample date/time - 9/11/2007@1400 Sample date/time - 9/13/2007@1500 Isolation pressure - 93 psig Isolation Pressure - 92 psig Current pressure - 89 psig Current Pressure - 99 psig Which one of the following describes which tank(s), if any, should be disapproved for release and why?

a. T-101C and T-68A. Pressure at the start of release cannot be > 3 psig different than isolation pressure.

b. T-101C only. More than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months have passed since the sample analysis.

c. T-68A only. Pressure at the start of the release cannot be > 5 psig different than isolation pressure.

d. Neither tank. There are no requirements for sample time or tank pressure.

DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible if the student believes that a batch must be disapproved if tank pressure has changed by 4 psig from isolation.

b.

INCORRECT - Plausible if the student believes that the tank must be released within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (or less) of tank isolation.

c.

CORRECT

d.

INCORRECT - Plausible if the student believes that there are no requirements for tank pressure or sample time.

Level of Knowledge:

HIGH Difficulty:

4

SRO Question 24 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 24 of 25 Question Number:

24 Source of Question:

NEW K/A:

G2.4.11 Knowledge of abnormal conditions procedures.

Tier:

3 Group:

SRO Imp:

3.6 Applicable 10CFR55 Section:

43.5 Palisades Learning Objective: TBCORE_CK05.0

References:

ONP-12, section 4.12 Question:

With the plant in MODE 1, a tornado warning is issued by the National Weather Service for Van Buren County. What action is required based on this report?

a. Ensure P-8C, AFW Pump, is OFF and selected to MANUAL.

b. Start P-8C, AFW Pump, and place on recirculation.

c. Perform a normal plant shutdown per GOP-8, Power Reduction and Plant Shutdown to MODE 2 or MODE 3 525 °F.

d. Start BOTH Emergency Diesel Generators and parallel to Bus 1C and 1D.

DISTRACTOR ANALYSIS

a.

CORRECT

b.

INCORRECT - Plausible if the student confuses saving P-8C with placing it in service.

c.

INCORRECT - Plausible if the student believes that this is a conservative action.

d.

INCORRECT - Plausible if the student believes that this is a conservative action.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 25 Palisades 2007 NRC Initial License Exam WRITTEN QUESTION DATA SHEET 25 of 25 Question Number:

25 Source of Question:

NEW K/A:

G2.4.38 Ability to take actions called for in the facility emergency plan, including (if required) supporting or acting as emergency coordinator.

Tier:

3 Group:

SRO Imp:

4.0 Applicable 10CFR55 Section:

43.5 Palisades Learning Objective: PL-N00112, PL-N00113

References:

EI-2.1, section 6.0 Question:

If the Shift Manager becomes incapacitated and you assume his/her duties during an emergency, which one of the following responsibilities as the Site Emergency Director can you delegate?

a. Approving Protective Action Recommendations

b. Approving decisions regarding site evacuation.

c. Declaring the appropriate classification for the incident

d. Authorizing Potassium Iodine (KI) distribution DISTRACTOR ANALYSIS

a.

INCORRECT - Plausible if the student believes that this can be delegated

b.

INCORRECT - Plausible if the student believes that this can be delegated

c.

INCORRECT - Plausible if the student believes that this can be delegated

d.

CORRECT - Per EI-2.1, SITE EMERGENCY DIRECTOR, section 6.0 Level of Knowledge:

LOW Difficulty:

3

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