Text

Final - Lsro Written Examination with Answer Key (Folder 3)
	ML052060104
Person / Time
Site:	Peach Bottom, Limerick
Issue date:	06/10/2005
From:	Caruso J; Operations Branch I
To:	Conte R; Operations Branch I
	Conte R
References
	50-277/05-302, 50-278/05-302, 50-352/05-302, 50-353/05-302 50-277/05-302, 50-278/05-302, 50-352/05-302, 50-353/05-302
	Download: ML052060104 (99)
	v • d • e

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LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 01 01 of 50 LGS Unit 2 plant conditions are as follows:

OPCON 5 RPV Level is 494 Core Shuffle Part 1 is in progress 2A RHR is in Shutdown Cooling An unisolable leak occurs in the 2A Recirc loop.

No water is injected into the RPV No operator actions are taken WHICH ONE of the following describes the lowest expected RPV level and the reason?

Lowest Expected Level Reason

a.

+12.5

b.

C.

d.

-1 61

-21 4

-31 1

RHR Shutdown Cooling Isolation will terminate leak Water level will stop lowering once level is at the top of the shroud Jet Pump Suction Inlet reached; RPV level will stop lowering With an unisolable leak, RPV level will continue to decrease until the Bottom of Vessel is reached

LGS/PBAPS 2005 NRC LSRO Licensing Examination Source:

Ref e re nce (s) :

Learning Objective:

Knowledge/Ability:

Choice New Exam Item NLSR00010.5A 295031 EK3.02 I Importance: 4.7

a.

b.

C.

~

d.

Basis or Justification Incorrect - leak is from the Recirc Loop and is unisolable. Although Shutdown cooling will isolate at +12.5 this will have no effect on reducing inventory loss Incorrect - a penetration into the shroud exists from the suction of the Jet Pumps.

This penetration will permit RPV Level will continue to lower below -1 61 inches.

Correct Answer - Jet Pump suction inlet is designed to maintain 2/3 core height floodable volume as long as the Jet Pump and Shroud are intact Incorrect - Jet Pump design will maintain core coverage at 2/3 core height Required Attachments or Reference Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 02 02 of 50 ATTACHMENT Q02 IS PROVIDED LGS Unit 1 plant conditions are as follows:

OPCON 5 Core Shuffle Part I I in progress 1 A RHR is in Shutdown Cooling Unit 1 and Unit 2 Spent Fuel Pools are cross-tied Cavity level 494.0 inches and stable I&C Testing results in the following condition:

1C RHR pump started and injected into the RPV at rated flow for exactly 1 minute before it was secured WHICH ONE of the following describes the resulting change in cavity level and the instrument that indicates the level change?

Resulting Level Level Instrument

a.

497.5 Wide Range

b.

497.5 Upset

c.

496.7 Wide Range

d.

496.7 Upset

LGS/PBAPS 2005 NRC LSRO Licensing Examination Source:

Learning Objective:

KnowledgelAbility:

Reference(s):

Question # 02 New Exam Item NLSR00050.3a 295008AA2.01 1 Importance: 3.9 GP-6.1 Choice

a.

b.

C.

d.

Basis or Justification Incorrect - RHR Injecting at rated flow for one minute will add 10,000 gallons of inventory to the Reactor cavity. With both spent fuel pools cross-tied, level will change at a rate of 3640 gallons per inch. If the candidate misreads the GP-6.1 reference and uses the single spent fuel pool number of 2865 gallons per inch and incorrect valve will be obtained 10000 Gallond2865 gallons per inch will result in a change of 3.50 inches. This will result in a final cavity level of 497.5 inches. With the RPV head removed and cavity flooded, only Shutdown (0-500) and Upset (0-500) level indicators will be on scale. The range for Wide Range Level indication is +60 to

-150 inches.

See Answer A See Answer d Correct Answer - RHR Injecting at rated flow for one minute will add 10,000 gallons of inventory to the Reactor cavity. With both spent fuel pools cross-tied, level will change at a rate of 3640 gallons per inch. 10000 Gallons/3640 Gallons per inch will result in a change of 2.74 inches. This will result in a final cavity level of 496.74 inches. With the RPV head removed and cavity flooded, only Shutdown (0-500) and Upset (0-500) level indicators will be on scale. The range for Wide Range Level indication is +60 to -150 inches.

GP-6.2 Required Attachments or Reference Source Documentation %$@&

9.

Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 03 03 of 50 LGS Unit 2 plant conditions are as follows:

OPCON 5 Reactor cavity flooded up to +496 inches 2B RHR is operating in Shutdown Cooling Mode Reactor vessel hydrolazing in progress from the auxiliary platform LLRT in progress for 2A Core Spray system per ST-4-LLR-161-2, A Core Spray Pump Discharge with no abnormal results Both spent fuel pools are connected through the cask pit per S53.0.C, Connecting Fuel Storage Pools to Cask Storage Pit Including Cross Connecting Fuel Storage Pools Unit 1 Fuel Pool Cooling is in service with 2 pumps and 1 demineralizer Unit 2 Fuel Pool Cooling is not in service A crud burst from hydrolazing activities has resulted in a North Spent Fuel Pool ARM alarm with an indicated reading of 40 mr/hr.

WHICH ONE of the following describes an action that will reduce dose rates to Refuel Floor workers?

a.

b.

C.

d.

Place Unit 2 Fuel Pool Cooling demineralizer in service per S53.1.A, Startup and Temperature Control of Fuel Pool Cooling System Secure Core Spray valve LLRT per ST-4-LLR-161-2, A Core Spray Pump Discharge Secure 26 RHR from Shutdown Cooling mode per S51.8.6, Shutdown Cooling/Reactor Coolant Circulation Operation Start-up and Shutdown Place Unit 1 Refuel Floor HVAC in service per S76.1.A, Startup of Refuel Floor HVAC

LGSlPBAPS 2005 NRC LSRO Licensing Examination Choice

a.

b.

C.

d.

Basis or Justification Correct Answer - Placing additional Fuel Pool Cooling in service will help remove the radioactive particles in the water and reduce dose to Refuel Floor workers.

Incorrect - Securing from the Core Spray valve LLRT will prevent further air bubbles from entering the reactor, but will not help to remove radioactivity from the water, and will not reduce Refuel Floor radiation levels.

Incorrect - Securing Shutdown Cooling will not help remove radioactivity from the water, and will not reduce Refuel Floor radiation levels.

Incorrect - Starting Unit 1 HVAC system will have no effect on reducing fuel floor Radiation levels. There are no indications of an airborne release (Le. no refuel floor HVAC exhaust alarms)

I Required Attachments or Reference I

1 1

Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 04 04 of 50 LGS Unit 1 plant conditions are as follows:

After full power operation for 640 days, a shutdown is in progress per GP-6.1,

Shutdown Operations-Refueling Core alteration and Core Off load Reactor has been shutdown for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 1A RHR is in Shutdown Cooling with the following information provided o RPV Temperature is 198°F and lowering o SDC flow rate 9000 GPM o HV-C-51-1 F048A, HEAT EXCH BYPASS is THROTTLED o HV-51-1 F003A, OUTLET is OPEN o HV-C-51-103A1 POS is CLOSED While adjusting cooldown rate, a Reactor Operator fully opens HV-C-51-1 F048, HEAT EXCH BYPASS valve.

No other operator actions are taken.

WHICH ONE of the following describes the expected RHR Heat Exchanger Outlet temperature response and resulting OPCON based on the above actions one hour later?

Heat Exchanger Outlet OPCON Temperature

a.

Rise 3

b.

Rise 4

C.

Lower 3

d.

Lower 4

LGS/PBAPS 2005 NRC LSRO Licensing Examination Source:

Reference(s):

Learning 1 Question #

04 Basis or Justification New Exam Item S51.8.B NLRS00372L.38 Choice L=

Knowledge/Ability:

b.

205000 Al.08 I Importance: 2.9 C.

d.

Correct Answer - S51.8.B describes the methods of establishing and controlling RPV cooldown. Opening the HV-C-1 F048 in this mode will result in bypassing RHR flow around the RHR Heat Exchanger. With RHR flow bypassing around the Heat Exchanger, Heat exchanger outlet temperature will continue to rise. With the loss of cooling temperature will exceed 200°F within a few minutes. Per Tech Spec definition, if RPV temperature exceeds 200°F OPCON 3 should be entered.

LGS / PBAPS difference - PBAPS throttles and maintains temperature by adjusting HPSW flow through the Heat Exchanger, LGS throttles RHR temperature. The orientations are different and there is often confusion over which way to throttle the bypass valves. This question test differences between LGS and PBAPS Incorrect - See answer A Incorrect - See answer A Incorrect - See answer A Required Attachments or Ref e re nce Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 05 05 of 50 LGS Unit 2 plant conditions are as follows:

OPCON 5 Control Rod Blade Exchanges are in progress Unit 2 Fuel Pool Cooling and Cleanup System is in service as follows:

o 2A and 28 Fuel Pool Cooling pumps in service o 2A and 2B Fuel Pool Cooling Heat Exchangers are in service Reactor Cavity Seals #3 and #4 (Reactor Well Top and Bottom) have failed resulting in cavity level lowering.

WHICH ONE of the following describes the effect on the Fuel Pool Cooling System?

a.

FPCC Pumps will automatically trip when pump suction pressure reaches -2 psig

b. FPCC Pumps will automatically trip when Skimmer Surge Tank level drops to 4 8

c.

FPCC Pumps will not automatically trip and must be manually secured when LOW FPCC PUMP SUCTION (20C221 A-1) alarm an nu nciates

d. FPCC Pumps will not automatically trip and must be manually secured when FUEL POOL COOLING AND CLEAN-UP SYSTEM TROUBLE (21 2 Cleanup J-5) alarm

LGS/PBAPS 2005 NRC LSRO Licensing Examination Source:

Reference(s):

Learning Objective:

Knowledge/Ability:

Question #

05 New Exam Item SURGE TANK LO LEVEL NLSR0750.11 233000 K6.10 1 Importance: 3.3 LOW FPCC PUMP SUCTION (2OC221 A-l), 2OC222 94 SKIMMER Choice

a.

b.

C.

d.

Basis or Justification Incorrect - A Loss of Reactor Well Seals 3 and 4 will result in lowering cavity and skimmer surge tank level. An automatic trip signal is generated due to loss of suction pressure at 6 psig. The distractor uses -2 psig which is the setpoint for PBAPS Correct Answer - A Loss of Reactor Well Seals 3 and 4 will result in lowering cavity and skimmer surge tank level. When skimmer surge tank level drops to 48 (normally 8 feet) the FPCC Pumps receive an automatic trip signal Incorrect - Annunciator LOW FPCC PUMP SUCTION (20C221 A-1) will occur after the pump trips. This distractor is incorrect because an automatic action will occur (Pump Trip) on Low Skimmer Surge Tank Level 4 8 or Low Suction pressure 6 psig Incorrect -The FUEL POOL COOLING AND CLEAN-UP SYSTEM TROUBLE (212 Cleanup J-5) alarm generated from local BOP panel 20C222 64 SKIMMER SURGE TANK LO LEVEL which indicated that their may be a problem with the FPCC system.

This distractor is incorrect because an automatic action will occur (Pump Trip) on Low Skimmer Surge Tank Level 4 8 or Low Suction pressure 6 psig Required Attachments or Reference Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination 06 of 50 Question: 06 LGS Unit 1 plant conditions are as follows:

A Post Maintenance Test (PMT) is being performed on the Rod Drift Circuitry The ROD DRIFT TEST pushbutton is depressed with no other operator action WHICH ONE of the following describes the result(s) of the above action?

a. Simulates a continuous insert signal

b. Simulates a 1 Odd Reed Switch closed

c.

Simulates no signal from the Rod Motion Timer Card

d. Simulates 1 Even an 1 Odd Reed Switch closed simultaneously

LGSlPBAPS 2005 NRC LSRO Licensing Examination Cognitive (H, L)

L PRA (Y/N)

SRO LUnit (0, 1, 2, 3) 1 N

N Source:

Reference(s):

Learning Objective:

Knowledge/Ability:

(Choice New Exam Item S73.0.C NLSR00080 (No Objective) 201 002 A4.03 1 Importance: 2.8 Basis or Just if ication Incorrect - See answer B Incorrect - An Odd reed switch only is half of the necessary signal for a rod drift. The activation of an Odd reed switch is accomplished by actual moving a control rod with the Rod Drift Test Pushbutton depressed. The Rod Drift Test Pushbutton only masks the Rod Motion Timer Card.

Correct Answer - A rod drift alarm requires two components, an odd reed switch closed and no signal from the Rod Motion Timer Card (i.e. it moved when not desired) The Rod Drift Test Pushbutton masks the signal from the Rod motion Timer card. In combination with an odd reed switch closed will activate the Rod Drift Circuit.

Incorrect - See answer C Required Attachments or Reference 1 Source Documentation-q#=.+

I Prepared by: CBG

LGWPBAPS 2005 NRC LSRO Licensing Examination Question: 07 07 of 50 LGS Unit 1 plant conditions are as follows:

A rod coupling check was being performed on Control Rod 30-31 When the Withdraw Pushbutton was released at position 48 a directional control valve malfunction resulted in the control rod moving to position 00.

No operator actions have been taken.

WHICH ONE of the following describes the expected indications on the Full Core Display for Control Rod 30-31?

Amber Rod Drift Light Blue Rod Scram Light Green Full In Light

a.

On Off On

b.

Off On Off C.

On On

d.

On Off Off

LGSlPBAPS 2005 NRC LSRO Licensing Examination Source:

Reference(s):

Learning Objective:

Knowledge/Ability:

1 Question #

07 I

Basis or Justification Correct Answer - Candidate must determine that a Control Rod 30-31 has drifted vice scrammed. Failure of Directional control valves can result in a rod drift. The Scram Inlet and Outlet valves never opened (required for Blue Scram Light). The candidate must determine whether any of the three reed switches (00, Full in at 00, overtravel-in) will illuminate the Green Rods Full-in Light on the Full Core Display.

Any one of the three reed switches will illuminate the Rods Full-in on the Full Core Display Incorrect - This distractor is written for the candidate that believes that a control rod scram has occurred. On a control rod scram there is also a misconception that the control rod will overtravel in and not have the Green Rods Full-in Light illuminate.

Incorrect - This distractor is written for the candidate that believes that a control rod scram has occurred. Also this candidate would know that any one of three reed switches on a control rod scram will close during overtravel-in but still have the Green Rods Full-in Light illuminate.

Incorrect - This distractor is written for the candidate that befieves that a control rod drift has occurred. This candidate would believe the control rod has drifted to the Overtravel-in position and not have the Green Rods Full-in Light illuminate New Exam Item ON-1 04 NLSRO-0080.2F 21 4000 K1.05 1 Importance: 3.3 Required Attachments or Ref e re nce Knowledge of the physical connections and/or cause-effect relationships between Rod Position Information System and the following:

Full Core Display Prepared by: CBG

LG S/PBAPS 2005 NRC LSRO Licensing Examination Question: 08 08 of 50 LGS Unit 1 plant conditions are as follows:

Reactor Mode Switch is in Startup RPS Shorting Links are installed All IRMs are on range 4 indicating between 25/125 - 35/125 The 1 C IRM detector is partially withdrawn.

WHICH ONE of the following identifies the plant response and the reason for the response?

a.

An IRM Downscale Rod Block will occur due to 1C IRM indicating 10/125

b.

An IRM Rod Block will occur due to IRM detector withdrawn with mode switch in Startup

c.

An IRM Upscale Rod Block and Half Scram will occur due to IRM being inoperable

d.

An IRM Upscale Rod Block and Full Scram will occur due to IRM detector withdrawn with Mode Switch in Startup

LGS/PBAPS 2005 NRC LSRO Licensing Examination Source:

Reference (s) :

Learning Objective:

Knowledge/Ability:

Question #

08 Choice New Exam Item T-102, Trip Bases NLSR00240.3Cl 21 5003 K5.03 I Importance: 3.1

a.

b.

C.

d.

Basis or Justification I

Incorrect - Set point for IRM downscale rod block is (5/125).

Correct Answer - IRM interlock exists (All IRM must be fully insetted). This interlock is bypassed when the mode switch is taken to run.

Incorrect - The 1 C IRM detector being withdrawn does not result in a half scram signal.

Incorrect - See Answer C Required Attachments or Reference Prepared by: CBG

LG S/PBAPS 2005 NRC LSRO Licensing Examination Question: 09 09 of 50 LGS Unit 2 plant conditions are as follows:

A Double Blade Guide (DBG) has been positioned over the wrong location in the The spotter reports that the RPO is aligned at the correct location The Fuel Handling Director (FHD) recognizes that the DBG is over the wrong rack spent fuel pool on the first component transfer of the shift locations WHICH ONE of the following describes the impact on Concurrent Verification (CV) and the response per FH-105 CORE COMPONENT MOVEMENT - CORE TRANSFERS?

Impact on CV FH-105 Response

a.

b.

C.

d.

Failure of CV Failure of CV Challenge to CV Challenge to CV Correct the position continue transfers, monitor for multiple failures Suspend transfers and initiate a Condition Report (CR). Obtain NMD Management approval prior to resuming transfers Correct the position, re-perform CV, continue transfers, monitor for multiple challenges Suspend transfers and initiate a Condition Report (CR). Obtain Outage Services Management approval prior to resuming transfers

LGS/PBAPS 2005 NRC LSRO Licensing Examination Cognitive (H, L)

Unit (0. 1. 2, 3)

Question #

09 L

PRA (Y/N)

SRO 0

N Y 43.5 Choice Source:

Reference(s):

Learning 0 bject ive:

Knowledge/Ability:

a.

Modified from Bank NRC 2002 (Q35)

FH-105 NLSRO-0767.6 G2.2.26 I Importance: 3.7

b.

C.

d.

Basis or Justification Incorrect - See justification for C.

Incorrect - See justification for C.

Correct Answer - FH-105 treats a mistake that is caught by verification as a Challenge as long as the component is not actually misplaced. This is analogous to testing and interlock. Failure of Concurrent Verification (CV) occurs if both verifiers miss the error, a subsequent of transfers is required. The procedure allows continuation of work after a challenge, but requires a Condition Report (CR) for repeated challenges Incorrect - See justification for C.

Required Attachments or Reference Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 10 10 of 50 Plant conditions are as follows:

Entry to a High Radiation Area is required by a qualified radiation worker Current annual dose to the worker is 1950 mrem General area radiation level in the work area is 500 mrem/hr and the work is expected to take one hour WHICH ONE of the following describes who MUST approve raising the Administrative Dose Control Level to 3000 mrem per RP-AA-203, EXPOSURE CONROL AND AUTHORIZATION?

a.

Radiation Protection Manager Only

b. Work Group Supervisor and Radiation Protection Manager Only

c.

Work Group Supervisor, Radiation Protection Manager and Plant Manager Only

d. Work Group Supervisor, Radiation Protection Manager, Plant Manager and Station Vice President.

LGS/PBAPS 2005 NRC LSRO Licensina Examination Choice p Basis or Justification Incorrect - Work Group Supervisor authorization is also required Correct Answer - Per procedure authorization is required by Work Group Supervisor and Radiation Protection Manager Incorrect - Station Manager approval is not required. This answer would be correct if 4000 ADCL approval is requested Incorrect - Station Manager and Station Vice President approval is not required.

This answer would be correct if >4000 ADCL approval is requested Required Attachments or Reference I Coanitive (H. L)

I L I PRA (Y/N)

I SRO I

I Unit (0, 1, 2, 3) 10 I N I Y43.4 I

Knowledge of radiation exposure limits and contamination controls including permissible levels in excess of those authorized Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 11 11 of50 Plant Conditions are as follows:

Core Shuffle Part 1 is in progress A female Refuel Platform Operator states that she is not feeling well and believes this condition is a result of her being pregnant The RPO was relieved and directed to exit the area WHICH ONE of the following describes the Exelon Nuclear Administrative exposure limits per RP-AA-203, EXPOSURE CONTROL, in effect for the RPO and when the limits are effective?

Exposure Limit In Effect

a.

500 mrem for remaining term Upon verbal declaration

b.

500 mrem for remaining term Upon written declaration

c.

400 mrem for remaining term Upon verbal declaration

d.

400 mrem for remaining term Upon written declaration

~

LGS/PBAPS 2005 NRC LSRO Licensina Examination

b.

C.

d.

Question #

11 Choice I Basis or Justification Incorrect - See explanation for d Incorrect - See explanation for d.

Correct Answer - The Exelon Nuclear administrative control limit is 400 mrem for the entire term, with no planned entry into contamination or airborne areas. This limit is effective only after declaration, and the declaration must be made in writing. 500 mrem is the NRC limit for the term of the pregnancy I

a.

1 Incorrect - See explanation for d Source:

Reference (s) :

Learning 0 bject ive:

Knowledge/Ability:

Modified from BankNRC2002 (Q45)

RP-AA-203 NLSRO-1760.4 G2.3.1

] Importance: 3.0 Required Attachments or Reference Cognitive (H, L)

L PRA (Y/N)

~

SRO

~

Unit (0. 1.2. 31 0

N Y 43.4 Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 13 13 of 50 LGS Unit 2 plant conditions are as follows:

OPCON 5 Preparations for Core Shuffle per GP-6.1 is in progress 1ARHR shutdown cooling is in service at 8500 gpm GP-6.1, SHUTDOWN OPERATIONS - REFUELING, CORE ALTERATION AND CORE OFF-LOAD1 NG, directs RHR Shutdown Cooling Flow be reduced WHICH ONE of the following describes the maximum permissible RHR flow and the reason for the flow reduction?

Maximum Permissible RHR Flow Reason for Flow Reduction

a.

6000GPM Avoid in-core instrumentation vibration

b.

7000GPM Increase in vessel visibility

c.

7500GPM Prevent Condensate Transfer Injection

d.

8000GPM Prevent RHR Pump Runout

LGS/PBAPS 2005 NRC LSRO Licensing Examination Source:

Reference(s):

Objective:

Knowledge/Ability:

Learning Question #

13 New Exam Item GP-6.1 Step 3.9.60 G2.1.32 I Importance: 3.8 NLSRO-1530.2A Choice

a.

b.

C.

d.

Basis or Justification Correct Answer - GP-6.1 directs reduction of flow to prevent vibration of in-core instruments. When refueling activities remove in-core components some instruments are unsupported. Reduction of RHR flow reduces the amount of vibration that these instruments are subjected to.

Incorrect - Has no effect on in-core visibility. See a justification Incorrect - This is a concern for placing RHR in Suppression Pool Cooling because the condensate transfer valves are not isolated. SDC isolates the condensate transfer valves and a reduction of flow would increase condensate transfer if the valves were open Incorrect - This is also a concern for placing RHR in Suppression Pool Cooling. Flow rate is limited to prevent RHR Pump Runout. In this case the RHR pump can operate at 9000 gpm without a runout condition occurring.

Required Attachments or Reference I Ability to explain and apply system limits and precautions Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 14 14 of 50 LGS Unit 2 plant conditions are as follows:

OPCON 5 Core Shuffle Part 1 is in progress While moving a bundle from the core to the spent fuel pool the RPO notes that the bridge trolley motion is not as expected and can not operate at jog speed.

WHICH ONE of the following is the individual responsible for making the decision for continuing fuel handling operations?

a.

Shift Manager (SM)

b.

Reactor Operator (RO)

c.

Fuel Handling Director (FHD)

d.

Outage Services Supervisor (OSS)

LGS/PBAPS 2005 NRC LSRO Licensing Examination Source:

Reference(s):

0 bject ive:

Knowledge/Ability:

Learning

[ Question #

14 New Exam Item S97.0.M NLSRO-0767.8 G2.2.29 I Importance: 3.8

/Choice ia Basis or Justification Correct Answer - The Shift Manager is responsible for determining whether fuel core alterations can continue. The Shift Manager has ultimate responsibility for the overall operation of the plant not limited to fuel handling operations Incorrect Answer - The Reactor Operator has no authority to make continue core alteration decisions. The RO can only make recommendations to halt or continue core alterations.

Incorrect Answer - The Fuel Handling director has the authority to terminate core alterations. The FHD does not have authority to order the commencement of core alterations Incorrect Answer - The RPO cannot authorize the commencement of Core Alterations Required Attachments or Reference 1

I I Unit (0, I, 2,3) 12

( N I Y 43.6

~~~~~

Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 15 15 of 50 LGS Unit 2 plant conditions are as follows:

Reactor shutdown for a refueling outage is in progress WHICH ONE of the following conditions describes the earliest point when OPCON 5 can be entered per Tech Specs?

a.

Mode Switch placed in Refuel

b.

Reactor Pressure Vessel Head Removed C.

Average Reactor Coolant Temperature 1200°F

d.

All Vessel Head Closure Bolts Less than fully tensioned

LGS/PBAPS 2005 NRC LSRO Licensing Examination Cognitive (H, L)

Unit (0, 1, 2, 3)

L PRA (Y/N)

SRO 2

N Y 43.5 F--

Source :

Reference(s):

Learning 0 bjective:

Knowledge/Ability:

Basis or Justification Incorrect - Mode switch to REFUEL is independent of OPCON.

New Exam Item Tech Spec Definition LLOT0080.04 G2.1.22 1 Importance: 3.3 Incorrect - Although the RPV head removed is a condition that places the Unit in OPCON 5, it is not the earliest point where the OPCON is entered. That occurs when the vessel head closure bolts are less than fully tensioned Incorrect - Average coolant temperature ~200°F is the requirement for entry into OPCON 4 Correct Answer - Per Tech Spec definition, OPCON 5 can be entered when the vessel head closure bolts are less than fully tensioned. This event must occur before the RPV head can be removed Required Attachments or Reference Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 16 16 of 50 LGS Unit 2 conditions are as follows:

OPCON 5 Core Shuffle Part I is in progress with a bundle being withdrawn from the core I&C testing has resulted in the inadvertent start of the 2C RHR pump which injected for 10 seconds before it was secured Seal #4 Reactor Well Bottom Seal has failed and is deflated The Fuel Handling Director was notified of the following valid alarms (caused by actual conditions) that were received within the last two minutes 20C221 8-3 Skimmer Surge Tank HI Level 208 Reactor F-3 Rod Out Block 1 12 Cleanup J-5 Fuel Pool Cooling and Clean-up System Trouble 20C222 B-1 Seal #3 Reactor Well (Top Seal)

WHICH ONE of the following actions should be given the highest priority and performed first?

a. Refill the Reactor Well per S53.0.A

b. Start an additional FPCCU pump per S53.8.E

c.

Reduce skimmer surge tank level per S53.3.G

d. Perform S73.0.B to determine the cause of the Rod Block

LGSIPBAPS 2005 NRC LSRO Licensing Examination Cognitive (H, L)

Unit (0, 1, 2, 3)

Question #

16 t

Choice H

PRA (Y/N)

SRO 2

N Y 43.5 Basisor Justification Correct Answer -Loss of Reactor Well and Spent Fuel Pool level would have the highest priority. This condition directly relates to an Emergency Plan Emergency Learning 0 bject ive:

Know I e dg e/A b i I i t y :

Action Level Incorrect - The cause of the Fuel Pool Cooling and Cleanup Trouble alarm is due to lowering level due to both Cavity seals being failed. Starting an additional FPCCU pump will not work. The Pumps will trip on low CST Level and will not start until Level is restored Incorrect Although this is a required action for high Skimmer Surge Tank Level, the loss of both reactor cavity seals will result in lowering level in the Skimmer Surge Tank and Reactor Well. No action will be required to lower level Incorrect - - The MCR Rod Block is an expected condition during Core Shuffle. With the Refueling Mast Loaded and over the core will initiate a Rod Block. No actions are required.

NSLRO-1550.1 B 2.4.4 5 1 Importance: 3.6 Required Attachments or Reference Source:

1 New Exam Item Reference(s\\:

I S53.0.A Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination 17 of 50 Question: 17 LGS Unit 1 plant conditions are as follows:

OPCON 5 Core Shuffle Part 2 is in progress A short to ground electrical fault has resulted in the loss 01 1, bus.

I60 (RPS/UPS power) electrical WHICH ONE of the following describes the effect on the ability to continue fuel moves?

a.

b.

c.

d.

Fuel moves cannot occur in any core quadrants Fuel moves can continue in A & C core quadrants only Fuel moves can continue in B & D core quadrants only Fuel moves can continue in B, C, D core quadrants only

LGS/PBAPS 2005 NRC LSRO Licensing Examination Reference(s):

Learning Question#

17 E-1 AY160 / Tech Spec 3.9.2 LLSRO-0655.1 F Choice

a.

Objective:

Knowledge/Ability:

b.

21 5004 K2.01 I Importance: 2.8 C.

d.

Basis or Justification Correct Answer - A loss of lAYl60 will result in a loss of power to the 1A and 1 C SRMs. Tech Spec 3.9.2 requires that an SRM be operable in the quadrant where the core alteration is being performed and the face adjacent quadrant. Fuel moves in the B quadrant would require 1 A or 1 C SRM to be operable. Fuel moves in the D quadrant would require 1 A or 1 C SRM to be operable.

Incorrect - See Answer A Incorrect - See Answer A Incorrect - See Answer A TS 3.9.2 Required Attachments or Ref e re nce Cogt%ive(H, L j H

PRA (Y/N)

SRO Unit (0, 1, 2, 3) 1 N

Y 43.2 I Source:

I New Exam Item I

(Description of K&A, from catalog)

Knowledge of the electrical power supplies to the following:

SRM Channels/Detectors Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 18 18 of 50 LGS Unit 1 plant conditions are as follows:

OPCON 5 Normal Electrical lineup Core Alterations are in progress An electrical fault results in the loss of the 101 Safeguard bus.

WHICH ONE of the following describes the status of D11 Diesel Generator and the source of power to D11 Safeguard Bus?

D11 Diesel Generator Status D11 Bus Power Source

a.

Running 201 Safeguard Bus

b.

Not Running 201 Safeguard Bus

c.

Running Diesel Generator

d.

Not Running None - De-energized

LGS/PBAPS 2005 NRC LSRO Licensing Examination Source:

Reference (s) :

Learning Objective:

Knowledge/Ability:

Question #

18 New Exam Item E-1 0 NLSRO-0655.3 264000 K1.01 1 Importance: 4.1 Choice

a.

b.

C.

d.

Basis or Justification Correct Answer -.5 seconds after the loss of the 101 Safeguard Bus, D11 diesel generator will start on a dead bus signal. 1 second after the 101 Safeguard Bus loss, the Dl l-201 breaker will close and supply power to the D11 Bus. With the D11 bus re-energized the diesel generator output breaker will not close.

Incorrect - See Answer A Incorrect - See Answer A Incorrect - See Answer A Required Attachments or Ref e re n ce Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 19 19 of 50 LGS Unit 2 plant conditions are as follows:

OPCON 5 Core Shuffle Part 2 is in progress I&C has discovered RIS33-Ml-2K600, Pool Plug Laydown Area ARM setpoint is set to 29mFUhr A failed power supply has resulted in RIS30-Ml-2K600, Steam Separator Area ARM failing.

WHICH ONE of the following describes the impact on Fuel Handling Operations and required action to correct this condition?

Impact on Fuel Handling ODerations Action to correct

a.

Core Alteration can continue

b.

Core Alteration can continue

c.

Suspend Core Alterations

d.

Suspend Core Alterations Remove RIS33-M 1 - K600, Pool Plug Laydown ARM per S27.1.A Direct I&C to adjust setpoint per IC-1 1-00376 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Install a portable continuous monitor with the same alarm setpoint on the Refueling Platform per Tech Spec 3.3.7.1 Restore both ARMS to an operable status per ST-2-026-628-2

LGS/PBAPS 2005 NRC LSRO Licensing Examination Choice

a.

b.

Question #

19 Basis or Justification Incorrect -Removal of a Tech Spec criticality monitor from service with another monitor inop will result in less the minimum to perform core alterations. Tech Specs allows the ARM to be adjusted Correct Answer - Per Tech Spec 3.3.7.1 Core Alterations may continue provided the setpoint can be adjusted within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

d.

C.

failed ARM not the refuel platform.

Incorrect - This distractor assumes that both ARM are required to continue core alterations. Only 2 of 3 monitors are required for core alterations Incorrect - This distractor is the incorrect even if you assume that both monitors are inoperable. Tech Specs require the portable ARM be placed in the vicinity of the Cognitive (H, L)

Unit (0.

1. 2. 3)

H PRA (Y/N)

SRO 2

N Y

I Source:

Reference(s):

0 bject ive:

Knowledge/Ability:

Learning Required Attachments or Reference New Exam Item Tech Spec 3.3.7.1 272000 A2.12 I Importance: 4.0 NSLRO-0710.

I Psychometrics r

Refuel floor handling accidents/operations Prepared by: CBG

LGWPBAPS 2005 NRC LSRO Licensing Examination Question: 20 20 of 50 LGS Unit 1 plant conditions are as follows:

OPCON 5 An irradiated fuel bundle is being transferred from core-to-core Secondary containment integrity is established on the Refuel Floor A catastrophic grapple failure results in the fuel bundle falling on to the top of the core with the following result:

All Refuel Area Radiation Monitors are alarming All four (4) Refuel Floor Exhaust monitors indicate 2.6 mrem/hour and are slowly rising All automatic actions occur as designed WHICH ONE of the following describes the effect on Refuel Floor HVAC and what actions must be directed to mitigate the transient?

Effect Refuel Floor HVAC Actions to be directed

a.

Trips and Isolates

b.

Continues to run

c.

Trips and Isolates

d.

Continues to run Reestablish access to the Refuel Floor by defeating Refuel Floor HVAC Isolation Logic per T-229, Defeating Refuel Floor HVAC Isolation Logic, and restarting Refuel HVAC Manually start SBGT per S76.8.A, Manual Startup and Shutdown of SBGT Ensure Refuel Floor HVAC has isolated and evacuate the Refuel Floor per ON-1 20, Fuel handling Problems Manually Isolate Refuel Floor Per S76.8.B, Initiation of Reactor Enclosure or Refuel Floor Secondary Containment

LGS/PBAPS 2005 NRC LSRO Licensing Examination Reference(s):

Learning Question #

20 ON-1 20 NLSRO-1550.1A Choice Objective:

Knowledge/Ability:

a.

290001 A2.03 I Importance: 3.6

b.

C.

d.

Basis or Justification Incorrect -When Refuel Exhaust Rad levels exceed 2.0 mrem/hr, RF HVAC will automatically isolate and Standby Gas Treatment will start and align to the Refuel Floor. The Refuel Floor Isolation is a valid signal and is not permitted to be bypassed per G P-8.4.

Incorrect - An automatic isolation signal will occur. Manual alignment of SBGT is not required. See justification for c.

Correct Answer - When Refuel Exhaust Rad levels exceed 2.0 mrem/hr, RF HVAC will automatically isolate and Standby Gas Treatment will start and align to the Refuel Floor. ON-1 20 directs the Refuel floor to be evacuated and verification of a Refuel Floor isolation Incorrect - See above for justification Required Attachments or Reference Source:

1 New Exam Item

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 21 21 of 50 LGS Unit 1 plant conditions are as follows OPCON 5 Reactor Cavity Flooded Coolant Temperature 132°F Drywell Chilled Water NOT available 1 A Reactor Water Cleanup (RWCU) is operating in the Alternate Decay Heat Removal mode per S44.7.8, Using RWCU as an Alternate Method of Decay Heat Removal The in-service and standby Reactor Enclosure Cooling Water pumps have both TRIPPED.

WHICH ONE of the following describes the expected automatic response, if any, of the RWCU system?

a. 1A RWCU pump trips with no system isolation

b. 1A RWCU pump remains in service with no system isolation

c.

1A RWCU pump trips and an Inboard Isolation occurs (HV-44-1 F004, OUTBOARD)

d. 1A RWCU pump trips and a complete system isolation occurs (HV-44-1 FOO1, INBOARD and HV-44-1 F004, OUTBOARD)

LGS/PBAPS 2005 NRC LSRO Licensing Examination Cognitive (H, L)

Unit (0. 1. 2. 31 Question #

21 H

PRA (Y/N)

SRO 1

N N

Choice Source:

Reference(s):

Learning

a.

New Exam Item MCR ARC - 112 G-2, 1A RWCU Recirc Pump Trip NLSRO-0110.6A

b.

Objective:

Knowledge/Ability:

C.

204000 A3.04 I Importance: 3.5

d.

Basis or Justification Correct Answer - 1A RWCU pump will trip when RECW pressure is <47 psig for 10 seconds. No RWCU isolations setpoints will be reached so no system isolation will occur Incorrect - See Answer A Incorrect - An outboard isolation would occur if Non-Regenative Heat Exchanger outlet temperature exceeded 140°F. The isolation is designed to protect resin from excessive heat.

Incorrect - See Answers A and C Required Attachments or Reference Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 22 22 of 50 ATTACHEMENT Q22 is provided Increasing the oil flow rate through the heat exchanger will cause the oil outlet temperature to and the cooling water outlet temperature to

a.

Increase, increase

b.

Increase, decrease

c.

Decrease, increase

d.

Decrease, decrease

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question #

22 Choice

a.

b.

C.

d.

Basis or Justification Correct Answer GF Equation Sheet Required Attachments or Reference Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 23 23 of 50 LGS Unit 1 plant conditions are as follows:

OPCON 5 Fuel Shuffle Part 1 is in progress A control rod blade and fuel support combination is being raised on the Monorail Hoist by depressing RAISE and HOIST LIMIT Override WHICH ONE of the following describes the operation of the equipment to prevent inadvertently hoisting the blade and support out of the water with the hoist set up per M-C-741-301, CONTROL ROD BLADE, FSP, AND CONTROL ROD GUIDE TUBE REMOVAL AND INSTALLATION?

a.

The hoist jam block will contact the frame and cause an overload trip of the motor when the blade is 6 feet 7 inches from the surface

b.

The hoist jam block will contact a switch and de-energize the RAISE function when the blade is 6 feet 7 inches from the surface

c.

The hoist jam block will contact the frame and cause an overload trip of the motor when the blade is 5 feet 6 inches from the surface

d.

The hoist jam block will contact a switch and de-energize the RAISE function when the blade is 5 feet 6 inches from the surface

LGS/PBAPS 2005 NRC LSRO Licensing Examination Reference(s):

0 bject ive:

Knowledge/Ability:

Learning Question#

23 M-C-741-301 and Tech Spec -3.9.6 295023 AA1.03 I Importance: 3.6 NLSRO-0766.13 Choice

a.

b.

C.

~

d.

Basis or Justification lnccorect - an overload condition will not occur unless the Raise function fails to de-energize (additional failure)

Correct - Per M-C-741-301, Jam block is set to contact a whisker switch with the CRB no closer than 6 feet to the surface lnccorect - an overload condition will not occur unless the Raise function fails to de-energize (additional failure). The setpoint must be <6 feet below the water level for the hoist jam block lnccorect The hoist Jam block will de-energize the Raise function but the setpoint must be >6 feet below the water level for the hoist jam block Required Attachments or Reference Ability to operate and/or monitor the following as they apply to Refueling Accidents:

Fuel Handlina EauiDment Prepared by: CBG

LGSIPBAPS 2005 NRC LSRO Licensing Examination Question: 24 24 of 50 LGS Unit 2 plant conditions are as follows:

Core Shuffle part 2 is in progress Unit 1 Refuel Floor HVAC is in service A fuel bundle tie plate failure results in a radioactivity release to the refuel floor atmosphere and three Unit 1 Refuel Floor Exhaust Radiation Monitors indicate 2.7 mrem/Hr and stable and the fourth monitor has failed down scale.

WHICH ONE of the following describes the RF HVAC Damper Status and the monitored release point five minutes later?

RF HVAC Damper Status Monitored Release Point

a.

Some dampers Isolate North Stack Monitor

b.

No dampers isolate South Stack Monitor

c.

All dampers isolate Unit 1 Refuel Floor Exhaust Radiation Monitors

d.

All dampers Isolate North Stack Monitor

LGS/PBAPS 2005 NRC LSRO Licensinq Examination Choice

a.

Basis or Justification Correct - Under Isolations conditions (>2.0 mrem), SGTS exhaust to the North Stack.

Common misconception about the swap over of flow paths from normal to isolation condition is tested in this question PB/LGS Difference - At LGS a failure of a channel to actuate will result in a damper remaining in its as found position, division

b.

1 the isolation signal is received the exit path is routed to the North Stack redundant dampers will allow the appropriate flow path to be aligneasecured.

Incorrect - South Stack is the exit path when normal ventilation is in service. When C.

d.

Required Attachments or Ref e rence Incorrect - Unit 1 and Unit 2 HVAC rad monitors will not have flow past them following an isolation and are not valid indications Incorrect - Unit 1 and Unit 2 HVAC rad monitors will not have flow past them following an isolation and are not valid indications Source:

1 New Exam Item Reference(s1:

Learning GP-8.1 NLSOR0200.2 Objective:

Knowledge/Ability:

(Description of K&A, from catalog)

Knowledge of the interrelations between Secondary Containment Ventilation High Radiation and the following:

Process Radiation Monitoring System 295034 EK2.01 14.2 Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 25 25 of 50 LGS Unit 2 plant conditions as follows OPCON 5 Core Alterations are in progress Secondary Containment integrity is not established in the Reactor Enclosure Unit 2 Refuel Floor HVAC is in service The following conditions exist on the refuel floor:

During the Swap from Unit 2 to Unit 1 Refuel Floor HVAC, Refuel Floor differential Hydrolayzing activities in the RPV resulted in Refuel Floor Rad spiking to 1.35 A broken instrument air line resulted in HV76-019 Refuel Floor/SBGT Connecting Pressure dropped to -0.1 WG for 50 seconds then recovered mrem/hr then returned to normal rad levels I&C testing resulted in a Reactor Enclosure Isolation Signal valve indicating open (an Equipment Operator has locally verified that the valve has failed open)

WHICH ONE of the following describes the cause of the Refuel Floor isolation signal and the status of SBGT Fans?

Cause of RF Isolation SBGT Fan Status

a.

Low Refuel Floor AP Not Running

b.

Refuel Floor High Rad Running aligned to RE

c.

Reactor Enclosure isolation Running aligned to RF and RE

d.

Connecting Damper Open Running aligned to RF

LGS/PBAPS 2005 NRC LSRO Licensing Examination Source:

Reference(s):

Learning Objective:

Knowledge/Ability:

1 Question #

25 New Exam Item GP-8.1 NLSRO-0200.5 261 000 A4.02 I Importance: 3.1 Basis or Justification Incorrect - Refuel Floor differential Pressure dropped to -0.1 'I WG for 50 seconds will initiate a RF isolation and SBGT alignment and start until the condition exist for 100 seconds. When the conditions for the interlock occur, SBGT will align to the refuel floor and maintain negative pressure.

Incorrect - Refuel Floor Rad spiking to 1.35 mrem/hr will not initiate a refuel floor isolation (setpoint 2.0 mrem/hr) or SBGT start. SBGT will only align to the refuel floor Incorrect - Since the RF/RE zone are not cross tied, a RE isolation will not result in a RF isolation and SBGT system alignment and start. If the zones were intertied, SBGT would align to both the RF and RE Correct Answer - HV76-019 connecting damper failing open is an automatic refuel floor isolation and standby gas alignment to the refuel floor and automatic fan start.

Required Attachments or Reference Prepared by: CBG

LGWPBAPS 2005 NRC LSRO Licensincl Examination Question: 26 26 of 50 A nuclear reactor has been shutdown for one week from long-term power operation and shutdown cooling is in service. Upon a loss of cooling water to the shutdown cooling heat exchangers, which one of the following coefficients of reactivity will act first to change core reactivity and determine the effect on Shutdown Margin? (Assume continued forced circulation through the core)

Coefficient to Act First Effect on Shutdown Margin

a.

Moderator temperature coefficient Decrease

b.

Fuel temperature coefficient Increase

c.

Fuel temperature coefficient Decrease

d.

Moderator temperature coefficient Increase

LGS/PBAPS 2005 NRC LSRO Licensing Examination

a.

Question #

26 Choice I Basis or Justification Correct Answer Objective:

Knowledge/Ability:

b.

292004 K1.14 I Importance: 3.3 I

_ _ _ _ _ ~ I 4

Required Attachments or Reference Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 27 27 of 50 LGS Unit 2 plant conditions are as follows:

OPCON 5 Core Alterations are in progress The MCR has just announced over the PA system that the 2B RECW pump has tripped WHICH ONE of the following describes the effect on refueling activities if the 2A RECW pump cannot be started?

a.

Water clarity problems may develop due to the loss of Reactor Water Cleanup system

b.

Normal method of Fuel Pool Cooling will be lost and 28 RHR must be used for Fuel Pool Cooling Assist

c.

Heat removal capability will be improved due to Drywell Chilled automatically aligning to supply RECW

d.

6 loop of ESW must be aligned to replace decay heat removal capability normally provided by RECW

Source:

Reference(s):

Learning LGS/PBAPS 2005 NRC LSRO Licensing Examination New Exam Item S11.8.A, S51.8.G, MCR ARC 112 G-2 N LSRO-460.2B Question #

27 Objective:

Knowledge/Ability:

Choice 29501 8 AK1.01 I Importance: 3.6

a.

b.

C.

d.

Basis or Justification Correct Answer - RECW pump trip will result in the loss of RWCU on low RECW pressure. The tripping of the RWCU pump will result in a loss of RWCU flow and degradation of water clarity Incorrect - Fuel Pool Cooling assist can only be aligned to the A Loop on Unit 2.

Incorrect - DWCW must be manually realigned to support RECW operations Incorrect - Only directed during a loss of offsite power event (E-1 0/20)

S11.8.A prerequisite.

~~

Required Attachments or Reference Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 28 28 of 50 LGS Unit 1 plant conditions are as follows:

OPCON 5 Reactor cavity water level is 468 inches CRDM replacement is in progress under vessel All Control Rod Blade replacements have been completed 1A loop of RHR is operating in Shutdown Cooling 1 B and 1 D RHR pumps are both inoperable 1 B RHR HX is INOPERABLE and not expected to be OPERABLE for 6 days 1A RHR Pump has tripped WHICH ONE of the following describes the required actions?

a.

Suspend CRDM replacement undervessel

b.

Reactor coolant temperature must be monitored once per hour

c.

An alternate method of reactor coolant circulation must be verified available within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

d.

An alternate method of reactor decay heat removal must be verified available within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

LGS/PBAPS 2005 NRC LSRO Licensing Examination Tech Specs.

Required Attachments or Reference Question ##

28 Cognitive (H, L)

Unit (0, 1, 2, 3)

Choice H

PRA (Y/N)

SRO 1

N Y 43.2

~

a.

Source:

Reference( s) :

Objective:

Knowledge/Ability:

Learning

b.

Modified From Bank 202866 Tech Spec 3.9.1 1.1/2 295021 AK1.03 I Importance: 3.9 NLSRO-370.11 C.

d.

Basis or Justification Incorrect - OPDVs are not required to be suspended Incorrect - This distractor would be correct if RPV level was than 22 feet above the top of the RPV flange per Tech Spec 3.9.1 1.1 Incorrect - If no RHR Shutdown Cooling subsystems are in operation, reactor coolant circulation shall be verified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of discovery.

Correct -Tech Spec 3.9.1 1.2 Requires that 2 RHR Shutdown Cooling subsystems shall be Operable and 1 RHR Shutdown cooling subsystem shall be in operation when reactor vessel water level is less than 22 feet above the top of the RPV flange.

If this conditions is not met, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and alternate method of decay heat removal must be verified available. 468 is less than 22 feet above the flange (484)

Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 29 29 of 50 LGS Unit 2 plant conditions are as follows:

A double blade guide is suspended from the main hoist The NES combination grapple with a control rod blade (CRB) and Fuel Support Piece (FSP) is suspended from the Monorail Hoist The bridge air system has just depressurized to zero psig due to a broken fitting at the backup hose connection (V-9).

The components are have been seated in a safe location WHICH ONE of the following describes the ability to release the double blade guide and the CRB/FSP combination to the spent fuel pool?

Double Blade Guide CRB/FSP Combo

a. Can be manually released Can be manually released

b. Can be manually released Cannot be released

c. Cannot be released Can be manually released

d. Cannot be released Cannot be released

LGS/PBAPS 2005 NRC LSRO Licensing Examination Cognitive (H, L)

Unit (0.

1. 2.3)

H PRA (Y/N)

SRO 2

N N

Id Basis or Justification Correct - The NES combined grapple has a manual interlock release feature (actuated by reach rods) to address a malfunction of the air actuation system. The main hoist has manual hook eyes on the grapple faces. The location of the air break is chosen to eliminate consideration of using a service air connection from the plant, a feature that is part of the bridge.

Incorrect -

I Incorrect -

Incorrect -

I Required Attachments or Reference (Description of K&A, from catalog)

Knowledge of the effect that a loss or malfunction of the Fuel Handling Equipment will have on the following:

Fuel Handlina oDerations Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensina Examination Question: 30 30 of 50 Unit 2 plant conditions are as follows:

OPCON 5 Core Alterations are in progress 2A RHR Pump is in Alternate Decay Heat Removal Mode The 2A Standby Liquid Control Pump is inadvertently started due to a RRCS Logic Failure WHICH ONE of the following describes the effect on coolant temperature or water clarity if no operator actions are taken?

a.

Coolant temperature will rise due to SBLC fouling the Fuel Pool Cooling and Cleanup Heat Exchangers

b.

Water clarity will degrade due to RWCU Resin Failure due to SBLC intrusion

c.

Coolant temperature will lower due to the effect of SBLC on the RHR Heat Exchanger

d.

Water clarity will degrade due to RWCU isolation

LGSIPBAPS 2005 NRC LSRO Licensing Examination Choice

a.

b.

C.

d.

Question #

30 Basis or Justification Incorrect - SLC will not have any fouling effect on the FPCCU heat exchangers Incorrect - RWCU will isolate and the Resin will not be exposed to SLC Incorrect - SLC will have little effect on the RHR Heat Exchanger, temperature would rise if any effect Correct - RWCU will isolate resulting in a degradation of water quality Source:

Reference(s):

Required Attachments or Reference From Bank Modified OT-1 04 Objective:

Knowledge/Ability: 21 1000 K4.07 I Importance: 3.9 Knowledge of Standby Liquid Control System design Feature(s) and/or interlocks which provide for the following:

RWCU isolation Prepared by: CBG

LGSlPBAPS 2005 NRC LSRO Licensing Examination Question: 31 31 of 50 PBAPS Unit 3 plant conditions are as follows:

Core Shuffle part 2 is in progress Unit 3 Refuel Floor HVAC is in service A fuel bundle tie plate failure results in a radioactivity release to the refuel floor atmosphere and three Unit 3 Refuel Floor Exhaust Radiation Monitors indicate 18.4 mrem/Hr and stable the fourth monitor has failed down scale.

WHICH ONE of the following describes the damper status and monitored release point five minutes later?

Damper Status Monitored Release Point

a.

All dampers isolate Main Stack Monitor

b.

Some dampers Isolate Vent Exhaust Stack Monitor

c.

No dampers isolate Unit 3 Refuel Floor Exhaust Radiation Monitors

d.

Some dampers Isolate Main Stack Monitor

LGS/PBAPS 2005 NRC LSRO Licensing Examination Choice

a.

b.

C.

~~

Question #

31 Basis or Justification Correct - Under Isolations conditions (>16.0 mredhr), SGTS exhausts to the Main Stack. Common misconception about the swap over of flow paths from normal to isolation condition is tested in this question PB/LGS Difference - At LGS a failure of a channel to actuate will result in a damper failing to position, division redundant dampers will allow the appropriate flow path to be alignedkecured.

Incorrect - Exhaust Stack is the exit path when normal ventilation is in service.

When the isolation signal is received the exit path is routed to the Main Stack Incorrect - Unit 1 and Unit 2 HVAC rad monitors will not have flow past them following an isolation and are not valid indications

d.

Incorrect - All dampers will isolate, path is to the Main Stack Required Attachments or Reference Reference(s):

Learning GP-8.1-NLSOR0200.2 Objective:

Knowledge/A bi I ity :

~~

Prepared by: CBG 295034 E K2.0 1 I Importance: 4.2

LGSlPBAPS 2005 NRC LSRO Licensing Examination Question: 32 32 of 50 PBAPS Unit 2 plant conditions are as follows:

OPCON 3 Operations to place the unit into Cold Shutdown for a refueling outage are in progress per GP-6, Refueling Operations The following events occur:

A feedwater malfunction results in RPV level dropping to +10 inches and RBCCW is lost resulting in a NRHX discharge temperature rising to and stabilizing stabilizing at 210°F WHICH ONE of the following describes the RWCU valves that will isolate and the reason for the isolation?

a.

b.

C.

d.

Valve(s) that Auto Isolate Reason for Isolation MO RWCU INBD isolation, MO RWCU OUTBD isolation, MO RWCU Return Minimize loss of RPV inventory MO RWCU OUTBD isolation only Prevent Resin Damage MO RWCU INBD isolation, MO RWCU OUTBD isolation, MO RWCU Return Prevent Resin Damage MO-18 only OUTBD isolation only Minimize loss of RPV inventory

LGS/PBAPS Cognitive (H, L)

Unit (0, 1, 2, 3)

~

2005 NRC LSRO Licensina Examination H

PRA (Y/N)

SRO 2

N N

Question #

32 Source :

Ref e rence( s) :

Learning Choice New Exam Item COL GP-8b NLSRO-0110.4

a.

Objective:

Knowledge/Ability:

b.

204000 A3.04 I Importance: 3.4 C.

d.

Basis or Justification Incorrect - Distractor test candidates knowledge RWCU isolation setpoints. RWCU will not isolate until RPV level is +1 inch. LGS/PB Difference - LGS isolates at -38 Also on see c justification Incorrect - Distractor tests LGS/PB difference. Also see c justification Correct Answer - A complete Group II (RWCU) isolation will occur when NRHX discharge temp >2OO0F. This isolation is designed to prevent resin damage in the filter demins. This is a LGS/PB difference. At LGS Only the outboard isolation valve (HV-44-1 F004) will close.

Incorrect - see c justification Required Attachments or Reference Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 33 33 of 50 PBAPS Unit 3 spiral offload in the "A" Core Quadrant is about to begin with the following conditions:

Fuel Bundles:

Core fully fueled Spiral Off load To unload around "A" WRNM Wide Range Nuclear Monitors: "C" "F" "H" "B" INOP

" A WRNM Detector has the following indications:

0 1.1 cps o Signal to Noise ratio = 6 WHICH ONE of the following describes the ability to commence the spiral offload of the "A" Core Quadrant and the restrictions, if any?

a.

may continue with no other restrictions

b.

must be suspended until "C" WRNM is operable

c.

must be suspended until at least one WRNM is operable in Quadrant It D

d.

must be suspended until " A WRNM indicates a count rate above 1.2 CPS

LGS/PBAPS 2005 NRC LSRO Licensing Examination Source:

Reference(s):

Learning 1 Question #

33 I

New Exam Item Tech Spec 3.3.1.2 NLSRO-0240.4E Choice

a.

b.

C.

d.

Objective:

Knowledge/Ability:

Basis or Justification Correct Answer - Tech Spec 3.3.3.1.2 Bases Note 2 -SR 3.3.1.2.4 WRNM minimum count rate. The requirement does not have to be met during spiral unloading. If the core is being unloaded in this manner, the various core configurations encountered will not be critical Incorrect - Only the A WRNM is required to be operable during spiral offload or reload when the fueled region includes only that WRNM detector Incorrect - Only the A WRNM is required to be operable during spiral offload or reload when the fueled region includes only that WRNM detector Incorrect - Per Tech Specs, Signal to Noise Ratio evaluation is not required for spiral core offload.

21 5003 K5.03 I Importance: 3.1 Tech Spec Required Attachments or Ref e re nce I

I Knowledge of the operational implication of the following concepts as they apply to Intermediate Range Monitor (IRM) System:

Changing Detector Position Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 34 Page 34 of 50 PBAPS Unit 2 is in a refueling outage with the following plant conditions:

Control rod exercising is in progress A control rod is being inserted from position 48 to 00 The insert stabilizing control valve has failed to operate.

WHICH ONE of the following describes the effect on this control rods speed?

Throughout the control rod insertion, rod speed will:

a.

Not be affected

b. Be faster than normal

c.

Be slower than normal

d. Oscillate (faster and slower)

~~

LGS/PBAPS

~

2005 NRC LSRO Licensina Examination Choice

a.

b.

C.

Basis or Justification Incorrect. Rod speed will be slower since less system flow will reduce drive water pressure.

Incorrect. Rod speed will be slower since less system flow will reduce drive water pressure.

Correct. If the stabilizing valve fails to close, the drive water DP will be lower. This will result in a lower rod speed.

Incorrect. Rod speed will be slower since less system flow will reduce drive water pressure. Oscillation should not be any more prevalent due to this failure.

d.

None Required Attachments or Reference Source:

Direct Exam Bank Learning NLSRO-0070 EO 4e Objective:

Knowledge/Ability: 201 003 K6.01

[ Importance: 3.3 (Description of K&A, from catalog)

Knowledge of the effect that a loss or malfunction of the following will have on the CONTROL ROD AND DRIVE MECHANISM: Control rod hydraulic system.

Reference (s) :

LOT-5003 Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 35 Page 35 of 50 PBAPS Unit 3 plant conditions are as follows:

Mode 5 3A Loop of RHR is operating in the shutdown cooling Fuel Pool to Reactor mode A leak through a main steam line plug and an open SRV flange results in a loss of reactor cavity level.

WHICH ONE of the following describes the HIGHEST reactor cavity or vessel level where core cooling by RHR Fuel Pool to Reactor mode circulation will initially be lost?

a. The level of the RPV flange

b. The shutdown cooling PClS setpoint

c.

Below the skimmer surge tank weirs

d. The shutdown cooling vessel return elevation

LGS/PBAPS 2005 NRC LSRO Licensing Examination Reference(s):

Learning I Question # 35 I

NLSRO-0370 NLSRO-0370 EO 3 1 Choice 0 bject ive:

Knowledge/Ability:

Basis or Justification Incorrect. When the water input from the Reactor Cavity and Fuel Pool to the Skimmer Surge Tanks is lost, the RHR pump in Fuel Pool to Reactor mode will loose its suction source. This occurs at the level of the skimmer surge tank weirs.

Incorrect. This set point is 1 which is well below the level that the circulation will be lost.

Correct. In Fuel Pool to Reactor mode, the RHR pumps suction is from the Skimmer Surge Tank. Once the Rx Cavity and Fuel Pool levels drop below the SST weirs the RHR pump will empty the SST and the suction piping, causing a loss of ADHR flow.

Incorrect. The SDC return when in Fuel Pool to Reactor mode is a Recirculation System discharge line, which is well below the bottom of the above-mentioned weirs.

295021 AKl.03 I Importance: 3.9 Required Attachments or Ref e re nce Source:

I Direct Exam Bank Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 36 Page 36 of 50 PBAPS Unit 2 plant conditions are as follows:

Mode 5 Core Shuffle Part II is in progress CRD/CRB replacement is in progress with the refuel platform located over the core The refuel platform operator notices smoke coming from the frame mounted auxiliary hoist safety brake solenoid, and pushes the red backlit STOP pushbutton on the START/STOP control panel.

WHICH ONE of the following describes the effect of this action on CRD replacement?

a.

rod coupling cannot be performed due to rod insert block

b. rod coupling cannot be performed due to rod withdraw block

c.

rod uncoupling cannot be performed due to rod insert block.

d. rod uncoupling cannot be performed due to rod withdraw block

LGWPBAPS 2005 NRC LSRO Licensing Examination Choice

a.

b.

C.

Question # 36 Basis or Justification Incorrect - If a control rod insert block existed it would prevent the coupling of the CRB. With the conditions given a control rod block would be present Incorrect - A control rod withdraw block does not prevent a CRB from being re-coupled Incorrect - A control rod insert block does not prevent a CRB from being uncoupled

d.

Correct Answer - with bridge over the core, and de-energized, the Reactor Manual Control System will enforce a rod withdraw block. The action of uncoupling a control rod requires withdraw motion, and therefore cannot be performed.

None Required Attachments or Reference (Description of K&A, from catalog)

Ability to operate and/or monitor the following as they apply to REFUELING ACCIDENTS:

Fuel handling equipment.

Prepared by: JBG

LGSPBAPS 2005 NRC LSRO Licensing Examination Question: 37 Page 37 of 50 PBAPS Unit 2 plant conditions are as follows:

Mode 5 Core Shuffle Part I has just begun RBCCW is backing up TBCCW The CRD system is in service The RWCU system is in service in a normal lineup dumping 60 GPM to the Main A fire header break in the RBCCW room has caused both RBCCW pumps to trip Condenser WHICH ONE of the following describes the operational implications of this condition?

a. Higher than normal plant dose rates

b. Loss of Instrument Air to the Refueling Bridge

e.

Reactor Cavity and Fuel Pool visibility will degrade

d.

Reactor Cavity and Fuel Pool water level will begin to lower

LGS/PBAPS

b.

2005 NRC LSRO Licensinq Examination around 90°F.

Incorrect. The Refueling Bridge at PBAPS has an air compressor mounted on the Question # 37 Choice I Basis or Justification C.

~

a.

bridge and is therefore independent of station air systems.

Incorrect. RWCU will not isolate on high temperature. The clarity of the Reactor Cavity will not change due to this event.

Incorrect. RWCU will not isolate on high temperature. The isolation temperature is 200°F but the Reactor Cavity temperature will be between 1 10°F and 130°F during refueling operations. Generally, the temperature is maintained well below 1 1 O"F, Source:

Ref e r exce (s ) :

Objective:

Learning Knowledge/Ability:

New Exam question NLSRO-0370, M-316, GP-6, FH-6C NLSRO-0370 EO 1L 29501 8 AK1.01 1 Importance: 3.6

d.

Correct. With RBCCW supplying TBCCW loads, RBCCW is supplying cooling water to the CRD pump lube oil coolers and thrust bearings. The CRD pumps will trip after a loss of RBCCW. The loss of 60 GPM from the CRD system into the Reactor Cavity will cause Reactor Cavity and Fuel Pool levels to slowly lower. RWCU Dump flow is still in service and would lower cavity level at a rate of 60 gpm. This question tests differences between LGS and PBAPS None Required Attachments or Reference Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensina Examination Question: 38 Page 38 of 50 PBAPS Unit 3 plant conditions are as follows:

Mode 5 Core Shuffle Part II is in progress WHICH ONE of the following conditions will require the suspension of core alterations?

Failure of the:

a. Mast Orientation interlock on the Refueling Bridge

b. Loss of one Refuel Floor to MCR communications channel

c. Operator Interface Console screen on the Refueling Bridge

d. White Rod Withdrawal Permissive light (C005) to extinguish with the Bridge loaded over the core

LGS/PBAPS Choice

a.

b.

C.

~~~

~.

-~

2005 NRC LSRO Licensina Examination Basis or Justification Incorrect. Optionally used when in full auto. Not needed for core alterations Incorrect. 2 channels of communications are not required. Tech Spec does not require multiple channels.

Incorrect. Fuel movement can continue in the manual mode.

Question ## 38

d.

Correct. This Rod Withdrawal Permissive light should go out when the Refuel bridge is loaded over the core. FH-6C requires stopping core alterations under this condition.

Cognitive (H, L)

Unit (0, 1, 2, 3)

None Required Attachments or Ref e re nce L

PRA (Y/N)

LSRO 0

N N

Source:

Reference (sl :

I Source D o c u m e n t a & e - ; s

... 7 6.,

-=?

.i New Exam Item FH-6C. SO 18.1.A-3 0 bjective:

Knowledge/Ability: 234000 K3.03 I Importance: 3.8 Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Page 39 of 50 Question: 39 PBAPS plant conditions are as follows:.

Unit 3 is at 100% power Unit 2 is in Mode 5 The E-3 Emergency Diesel Generator (EDG) is loaded and paralleled with the E-32 bus for surveillance testing A total loss of Offsite power occurs Concurrent with the loss of Offsite power Unit 3 Drywell pressure exceeds 3 psig WHICH ONE of the following describes the status of the E-3 EDG FIVE minutes AFTER the loss of Offsite power with no operator action?

E-3 EDG is running:

a.

Unloaded

b. Carrying only the E-32 Bus

c. Carrying only the E-33 Bus

d. Carrying both the E-32 and E-33 Busses

LGS/PBAPS 2005 NRC LSRO Licensing Examination Source:

Reference( s) :

Learning Objective:

Knowledge/Ability:

Question ## 39 Modified Bank Item NLSRO-0655, LOT-5054 NLSRO-0655 EO 3 295003 AK2.02 I Importance: 4.2 Choice

a.

b.

C.

d.

Basis or Justification Incorrect. The EDG will be loaded with both the E-32 and E-33 busses. Both busses will initially receive a trip signal and then will reclose automatically. The candidate may believe that they will trip and lock out.

Incorrect. The candidate may believe that only the E-32 bus will be loaded since this was the condition when the LOOP occurred. -

Incorrect. The candidate may believe that E-32 will lock out after receiving the trip signal and therefore indicate that only the E-33 bus will be energized after the LOOP.

Correct. The EDG will be running with both busses loaded.

Required Attachments or Reference None Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensina Examination Question: 40 Page 40 of 50 PBAPS Unit 2 plant conditions are as follows:

Mode 5 Core Shuffle Part II is in progress IF Wide Range Neutron Monitor (WRNM) fails INOP WHICH ONE of the following describes the Channel Reactor Auto Scram annunciator that will be alarming and the status of the RPS Scram Group Lights?

Channel Reactor Auto Scram RPS Scram Group Lights Annunciator

a.

b.

C.

d.

A Lit A

Extinguished B

Lit B

Extinguished

LGS/PBAPS 2005 NRC LSRO Licensing Examination

a.

b.

C.

d.

Question # 40 Incorrect. The F WRNM inputs to the B RPS System. B RPS Scram Group Lights should be extinguished.

Incorrect. The F WRNM inputs to the B RPS System.

Incorrect. The B RPS Scram Group Lights should be extinguished with a B Channel Auto Scram Signal present.

Correct. The F WRNM inputs to the B RPS System and will result in extinguishing the Scram Group Lights.

Choice I Basis or Justification Source:

Reference(s):

0 bject ive:

Knowledge/Ability:

Learning New Exam Item ARC 21 1 C-1 B Channel Reactor Auto Scram NLSRO-0240.01 b 21 2000 A3.04 I Importance: 3.8 None Required Attachments or Reference Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensina Examination Question: 41 Page 41 of 50 PBAPS Unit 3 plant conditions are as follows:

A control rod is moved from position 48 to 24 using the EMERGENCY IN switch on panel 30C005.

A Rod Drift indication is received on the Full Core Display.

Rod Drift annunciator (21 1 D-4) alarms.

WHICH ONE of the following describes the reason for the Full Core Display indication and annunciator?

a. Absence of the settle function

b. The control rod inserting too fast

c. The bypassing of the Auxiliary Timer

d. A malfunction in the Reactor Manual Control System

LGS/PBAPS 2005 NRC LSRO Licensing Examination Cognitive (H, L)

Unit (0, 1, 2, 3)

L PRA (Y/N)

LSRO 3

N N

Choice

a.

b.

C.

d.

Source:

Learning 0 bjective:

Knowledge/Ability:

Reference(s):

Basis or Justification Correct. A Rod Drift is received when an even numbered reed switch is NOT made up an odd numbered reed switch is made up AND the control rod is NOT selected AND driving. The settle function is bypassed when using the Emergency In switch which causes a drift alarm to be received when an odd reed switch is made up without a driving signal.

This would not cause a Rod Drift but may cause a skipped notch.

Direct Exam Bank NLSRO-0080 EO 9e 21 4000 K1.05 I Importance: 3.3 NLSRO-0080 Only the Settle function is bypassed.

The Drift is not caused by a malfunctioning system when using the Emergency In switch. The system is performing as intended.

None Required Attachments or Reference Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 42 Page 42 of 50 PBAPS Unit 3 plant conditions are as follows:

Mode 5 Core Alterations are in progress A service water pipe has ruptured at the suction of the Service Water Booster pumps The service water has been isolated to the Fuel Pool Cooling Heat exchanger, and service water system pressure has been restored.

WHICH ONE of the following systems is the preferred source of cooling water that will be aligned to the Fuel Pool Cooling Heat Exchangers?

a.

Drywell Chilled Water

b.

Emergency Service Water

c.

Reactor Building Closed Cooling Water

d.

Turbine Building Closed Cooling Water

LGWPBAPS 2005 NRC LSRO Licensing Examination Source:

Reference(s):

Objective:

Knowledge/Ability:

Learning Question # 42 New Exam Item NLSRO-0750.2C 400000 K1.02 I Importance: 3.4 Choice

a.

b.

C.

d.

Basis or Justification Incorrect - RBCCW can be aligned to backup Drywell Chilled water but Drywell Chilled water cannot be aligned to cool the Fuel Pool Heat Exchangers Incorrect - RBCCW backup is prohibited due to flow requirements in ESW system and because the RBCCW Heat Exchangers are Correct Answer: - RBCCW can be aligned via spool pieces and locked closed valves to cool Fuel Pool Heat Exchangers Incorrect - RBCCW can be aligned to back up TBCCW but TBCCW cannot be aligned to cool the Fuel Pool Heat Exchangers None Required Attachments or Reference Loads cooled by CCWS Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 43 Page 43 of 50 Peach Bottom Unit 3 conditions are as follows:

Shutdown with RPV water level at 470 Control Rod Drive Mechanism 30-31 is being replaced.

While reviewing ST-0-009-200-3, Secondary Containment Capability Test, it is noted that Secondary Containment vacuum peaked at 0.22 of vacuum during the test.

WHICH ONE of the following describes the required actions, if any, for this condition?

a. Manually initiate the SBGT system immediately.

b. Initiate actions to stop the CRDM replacement immediately.

c.

Restore Secondary Containment to OPERABLE within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

d.

Restore the SBGT system to OPERABLE within the next 7 days.

~

LGS/PBAPS 2005 NRC LSRO Licensinq Examination Choice

a.

b.

C.

d.

Basis or Justification Incorrect. Based on actions for an inoperable SBGT subsystem with OPDRVs in progress. TS 3.6.4.3.C Correct. TS 3.6.4.1.C requires actions to be initiated to suspend OPDRVs immediately. CRDM replacement constitutes an OPDRV by the TRM definition.

Incorrect. Based on action for an inoperable Secondary Containment in Mode 1,2, or 3 in TS 3.6.4.1.A.

Incorrect. Based on actions for an inoperable SBGT subsystem in TS 3.6.4.3.A.

Required Attachments or Ref e re nce Cognitive (H, L)

Unit (0. 1. 2. 31 PBAPS Unit 3 TS sections 3.6.4.1 and 3.6.4.3 H

PRA (Y/N)

LSRO 3

N Y 43.1 Reference(s):

Learning Source:

NLSROO190 / TS 3.6.4.1 NLSR00190 E02 I New Question Obiective:

I

~~~

I Knowledge/Ability: I 290001 G2.1.I 2 I Importance: 4.0 (Description of K&A, from catalog)

Secondary Containment: Ability to apply TS for a given system.

Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 44 Page 44 of 50 PBAPS Unit 2 plant conditions are as follows:

Mode 4 The 2A RHR pump is in Shutdown Cooling A fire in panel 20Y033 has caused a short that de-energized the Inboard PClS logic WHICH ONE of the following describes the status of the listed Shutdown Cooling system components after the PClS power loss?

a.

b.

C.

d.

MO-17 RHR Outboard Shutdown Cooling Suction Isolation valve MO-18 RHR Inboard Shutdown Cooling Suction Isolation valve MO-25A RHR LPCl Injection valve RHR Valves 2A RHR Pump MO-17 close MO-18 close MO-25A open MO-17 open MO-18 close MO-25A open MO-17 close MO-18 close MO-25A close MO-17 open MO-18 open MO-25A open Trip Running Trip Running

LGS/PBAPS 2005 NRC LSRO Licensing Examination Reference(s):

Learning 0 bject ive:

Knowledge/Ability:

puestion # 44 NLSRO-0370 EO 9 223002 K3.16 I Importance: 3.3 (Choice Basis or Justification Incorrect: MO-25A closes if an isolation signal is received and the MO-18 and MO-17 were open. The RHR pump will trip when either suction valve closes.

Incorrect. MO-25A closes if an isolation signal is received and the MO-18 and MO-17 were open and the RHR pump will trip on loss of suction path.

Correct. Loss of the inboard logic will close the MO-17, 18, & 25A and the RHR pump will trip on loss of suction path.

Incorrect. All indicated valves will close and the pump will trip. The candidate would select this distractor if he incorrectly believes that both logic trains must be tripped to receive the isolation.

None Required Attachments or Reference oanitive IH. L

. r

,.. Z 5 ;

Source Documentat*-

4 Source:

I New Exam Item Prepared by: JBG

LGWPBAPS 2005 NRC LSRO Licensina Examination Question: 45 Page 45 of 50 PBAPS Unit 2 plant conditions are as follows:

Mode 5, 4 head bolts untensioned 2A RHR pump is in Shutdown Cooling A loss of coolant accident (LOCA) caused RPV level to lower rapidly WHICH ONE of the following describes the operational implications of the 2A RHR pump being in Shutdown Cooling when a LOCA occurs resulting in RPV level going below the top of active Fuel?

To align LPCl to injection with ALL RHR pumps, operator must:

a. Manually align RHR for injection and start the 2A RHR pump

b. Manually align RHR for injection. The 2A RHR starts automatically

c.

Manually start the 2A RHR pump. The LPCl loops automatically align for injection

d. Observe the automatic start of all LPCl pumps and the automatic alignment for injection

LG S/PBA PS 2005 NRC LSRO Licensina Examination Source:

Reference(s):

Learning Objective:

Knowledge/Ability:

I Question # 45 I

New Exam Item SO 10.1.A-2 NLSRO-0370 EO-9,10,12 203000 K5.02

[ Importance: 3.7 Choice Basis or Justification Correct - A loss of Shutdown Cooling will occur at 1. This will close the MO-17, 18, and MO-25A and 256. The 2A RHR pump will trip on loss of a suction path. To inject to with the 2A RHR pump, the operator must establish and injection path from the Torus to the RPV and restart the 2A RHR Pump Incorrect - The 2A RHR pump must be manually restarted Incorrect - The LPCl system must be manually realigned for injection Incorrect - A loss of Shutdown Cooling will occur at 1. This will close the MO-17, 18, and Mo-25A and 256. The 2A RHR pump will trip on a loss of suction path. To inject with the 2a RHR Pump; the operator must establish an injection path from the Torus to the RPV and restart the 2A RHR pump Required Attachments or Ref e re nce Cognitive (HI L)

L PRA (Y/N)

LSRO Unit (0, 1, 2,3) 2 Y

N Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 46 Page 46 of 50 PBAPS Unit 2 plant conditions are as follows:

Mode 5.

RHR System is operating in accordance with SO 10.1.C-2, Residual Heat Removal System Precise Reactor Temperature Control.

Reactor Coolant temperature is 110°F.

Reactor coolant temperature needs to be lowered to between 90°F and 100°F using the ILRT HPSW Cooling Bypass Valve (HV-2-32-222280).

WHICH ONE of the following describes the correct operation the ILRT HPSW Cooling Bypass Valve (HV-2-32-222280) and the effect on the HPSW Heat Exchanger Outlet Temperature?

ILRT HPSW Cooling HPSW Heat Exchanger Bypass Valve Outlet Temperature

a.

Throttle Open Rise

b.

Throttle Open Lower C.

Throttle Close Rise

d.

Throttle Close Lower

LGS/PBAPS 2005 NRC LSRO Licensing Examination Cognitive (H, L)

Unit (0, 1, 2, 3)

Choice H

PRA (Y/N)

LSRO 2

Y N

a.

b.

Ref e re nce(s) :

Learning Objective:

Knowledge/Ability:

C.

NLSRO-0370 EO 5 205000 Al.08 I Importance:

d.

Basis or Justification Incorrect. The ILRT HPSW Cooling Bypass Valve bypasses the HX HPSW outlet valve, so it is required to be throttled open to raise the cooling rate. However, throttling open on this valve will cause HX outlet temperatures to lower, not rise.

Correct. The ILRT HPSW Cooling Bypass Valve bypasses the HX outlet valve, so it is required to be throttled open to raise the cooling rate. Throttling open on this valve will cause HX outlet temperatures to lower due to added HPSW flow.

Incorrect. It is a common misconception that the ILRT HPSW Cooling Bypass Valve bypasses the HX rather than the HPSW discharge valve. Believing this, a candidate would expect to throttle closed on this valve forcing more HPSW flow through the HX to lower reactor coolant temps. The candidate may also believe that HPSW temperature would rise as more heat is transferred to it, rather than lowering as it actually does due to increased HPSW flow.

Incorrect. It is a common misconception that the ILRT HPSW Cooling Bypass Valve bypasses the HX rather than the HPSW discharge valve. Believing this, a candidate would expect to throttle closed on this valve forcing more HPSW flow through the HX to lower reactor coolant temps. The candidate may select a lower HPSW outlet temperature due to recognizing that more flow through the HX exists.

None Required Attachments or Ref e re nce I Source Documentation $zs I Source:

I New Exam Item Prepared by: JBG

LGWPBAPS 2005 NRC LSRO Licensing Examination Question: 47 Page 47 of 50 PBAPS Unit 2 plant conditions are as follows:

Mode 4 Both Reactor Recirculation pumps are secured 2D RHR has been running in Shutdown Cooling at 5000 GPM for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Reactor level as read on LI-86 on panel 20C003 is +40 inches.

WHICH ONE of the following describes the required actions, if any, to be taken to promote natural circulation through the Reactor Core if the 2D RHR pump trips?

a.

No action is required, natural circulation exists in the core

b. Secure the Control Rod Drive Hydraulic system and maximize RWCU Bottom Head Drain flow

c. SDC must be restarted in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . SDC may be secured for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months out of every 8-hour period

d.

Raise RPV level to greater than 50 inches

LGWPBAPS 2005 NRC LSRO Licensing Examination Cognitive (H, L)

Unit (0, 1, 2, 3)

Choice L

PRA (Y/N)

LSRO 2

N N

a.

Source:

Refe rence(s) :

Learning 0 bjective:

Knowledge/Ability:

b.

New Exam Item ON-125, GP-12 NLSRO-0370 EO-1 1 290002 K4.05 I Importance: 3.5 C.

d.

Basis or Justification Incorrect. Natural circulation does not exist without forced circulation unless RPV Level is 950".

Incorrect. This action is taken to prevent thermal stratification in the core, not to establish natural circulation.

This guidance is contained in GP-12 for a planned shutdown of a SDC system. The unexpected loss or unavailability of SDC requires entry into ON-1 25. ON-1 25 provides the guidance in response "d" if neither a Recirc pump nor a SDC loop can be stai Correc

ed.

. Natural circulation will exist at an RPV Level of >50" with no forced circulation through the core. This level corresponds to the top of the steam separators.

Required Attachments or Reference None Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 48 Page 48 of 50 PBAPS Unit 3 plant conditions are as follows:

Mode 4 RPV temperature 180°F and lowering 3A RHR pump is in Shutdown Cooling (SDC)

A crack in the SDC suction line causes RPV level to lower to the SDC isolation point WHICH ONE of the following describes the reason for the Shutdown Cooling isolation on low RPV level?

a.

Prevent core from being uncovered

b. Prevent loss of natural circulation.

c.

Prevent loss of net positive suction head for the RHR Pumps

d.

Prevent inadvertent draining of the RHR piping and subsequent water hammer events.

LGS/PBAPS 2005 NRC LSRO Licensing Examination

~

S o u r c e

--New Exam Item Reference( s):

Peach Bottom PRIMARY CONTAINMENT ISOLATION SYSTEM design Choice Learning 0 bject ive:

Knowledge/Ability:

a.

b.

basis document (P-S-26), NLSRO-0370 295031 EK3.02 1 Importance: 4.7 C.

d.

Basis or Justification Correct. Automatic closure signals are provided to Group 29 Isolation Valves because the RHR System piping is part of the RCPB and closure of the isolation valves is intended to ensure against uncovering the core, should a RHR Shutdown Cooling pipe break, or an inadvertent draining of the Reactor vessel occur.

Uncovering the core will result in fuel damage due to overheating.

The NRC issued Branch Technical Position 3-1 that only required moderate energy piping to consider cracks and not breaks. Therefore, the low water level signal indicates just inadvertent draining of the reactor vessel because of valve misalignments.

Incorrect. Not a basis for RHR isolation, RHR pumps are designed to operate with RHR level well below +1 Incorrect. Natural circulation is lost at c50 if no forced circulation exists. The low water level isolation does not occur until 1.

Incorrect. Draining of the RHR piping is a consideration for water hammer events during subsequent restarts of SDC but not a basis for this isolation.

None Required Attachments or Reference I Source Documentation

~ ;#

Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 49 Page 49 of 50 PBAPS Unit 2 plant conditions are as follows:

Mode 5 Core Shuffle Part I is in progress Upon raising a leaking fuel bundle the Refuel Floor ARMS alarm and the Reactor -

Standby Gas Treatment System initiates Building and Refuel Floor Ventilation Systems isolate WHICH ONE of the following describes the basis for the Reactor Building and Refuel Floor Ventilation system isolations?

a.

Prevents all off site radioactive releases

b. Provides a filtered monitored and elevated release

c.

Maintains radiation exposure to station personnel ALARA

d. Prevents ductwork failure by routing the release through hardened ducts

LGS/PBAPS 2005 NRC LSRO Licensing Examination Choice

a.

Basis or Justification Incorrect. This does not prevent a release but lowers the radioactivity of the release and elevates it.

b.

C.

d.

Correct. Aligning the release through the SBGT system provides filtration and elevates the release through the main stack versus the vent stacks.

Incorrect. The specified condition is related to radiation alarms. The radiation dose to station personnel is not changed by the isolation, however, the severity of the release to the public is minimized.

Incorrect. This distractor is based on a procedural caution about how SBGT is aligned, but is not the basis for the isolation.

None Required Attachments or Ref e re nce Reference (s) :

I Learning New Exam Item Design basis document: REACTOR BUILDING HVAC SYSTEM (P-S-08C), PRIMARY CONTAINMENT PRESSURE SUPPRESSION SYSTEM (P-S-25A). LOT-5040B Rx. Bldg. HVAC, T-104 Radioactive Release.

NLSRO-0200 EO l A, 2c, 4 29501 7 AK3.01 I Importance: 3.9 from catalog)

Knowledge of the reasons for the following responses as they apply to HIGH OFF-SITE RELEASE RATE: System isolations.

Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensina Examination WRNM A

Question: 50 Page 50 of 50 Count Rate After Initial Count Rate Above Activities Count Rate Trend 12 12 Stable PBAPS Unit 3 plant conditions are as follows:

B C

Mode 5 Core Shuffle II is in progress 10 50 Slow rise 14 15 Stable The following activities have occurred in the last 5 minutes:

RO lowered Reactor Coolant Temperature by 3 O F Control Rod 18-1 1 was withdrawn to position 02 A control rod blade was removed from a defueled cell 10-41 The sixth fuel bundle was just loaded around the B WRNM D

E The RO reports a significant rise in WRNM count rates as follows:

12 30 Slow rise 11 12 Stable F

10 10 Stable G

H 12 12 Stable 11 11 Stable WHICH ONE of the following describes the most significant contributor to the reactivity change indicated on the WRNMs?

a.

Reactivity added due to the removal of a poison from the control rod blade removal

b. Reactivity added due to lower moderator temperature

c.

Reactivity added due to withdraw of the control rod

d.

Reactivity added due to inserted fuel bundle

LGS/PBAPS 2005 NRC LSRO Licensing Examination Choice

a.

b.

C.

d.

Basis or Justification Incorrect. Control Rod Blade removal form location 10-41 will not effect core reactivity because the location is defueled. Also, Control Rod Blade location is closest to the A and C WRNM which showed no appreciable change Incorrect. A decrease in moderator temperature would effect reactivity in the entire core not just two core locations. WRNM reading did not appreciably change in 6 of 8 locations Incorrect. Withdraw of a control rod would result in reactivity being added however the increase would be indicated on the H WRNM. The amount of reactivity added would be negligible Correct. Inserting the fuel bundle would cause a positive reactivity event in the core.

It this case, unpredicted, unexpected, inadvertent reactivity addition has occurred resulting in inadvertent core criticality. The rising count rate on the B WRNM indicates a critical condition in the localized area of the B (and possibly D) WRNM.

None Required Attachments or Reference 1

I I

I Unit (0, 1, 2, 3) 10 1 Y 43.6 I

Ability to determine and/or interpret the following as they apply to INADVERTENT REACTIVITY ADDITION: Cause of reactivity addition.

Prepared by: JBG

ML052060104

Text

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