ML052060210

Draft - Lsro Written Exam (Folder 2)

ML052060210
Person / Time
Site:	Peach Bottom, Limerick
Issue date:	05/01/2005
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: ML052060210 (101)

Text

PROPOSED WRllTEN EXAM REFERENCES Q2 - GP-6.1, Shutdown Operations - Refueling, Core Alteration and Core Off-Loading.

Q4 - P&ID Limerick RHR.

Q22-Simplified Drawing Lube Oil Heat Exchanger

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

L 01 of 50 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.

b.

L-C.

d.

+12.5

-1 61

-214

-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:

Reference(s):

Learning Objective:

K n owl ed g e/A b i I it y :

Question #

01 New Exam Item NLSR00010.5A 2 9 50 3 1 E K3.0 2 I Importance: 4.7 Choice

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 Licensina Examination Question: 02

/

02 of 50 ATTACHMENT Q02 IS PROVIDED LGS Unit 1 plant conditions are as follows:

OPCON 5 Core Shuffle Part II in progress 1A 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:

IC 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 L

b.

497.5 Upset

c.

496.7 Wide Range

d.

496.7 Upset

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LGS/PBAPS 2005 NRC LSRO Licensing Examination u

Answer Key and Question Data Question# 02 Cognitive (H, L)

Unit (0. I.

2. 3)

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 H

PRA (Y/N)

SRO 1

N Y 43.5 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.

Source:

Learning Objective:

Knowledge/Ability:

Reference(s):

GP-6.2 Required Attachments or Reference New Exam Item N LSR00050.3a 295008AA2.01 I Importance: 3.9 GP-6.1 I Source Documentation

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

03 of 50 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 Both spent fuel pools are connected through the cask pit per S53.0.C, Connecting Unit 1 Fuel Pool Cooling is in service with 2 pumps and 1 demineralizer Spray Pump Discharge" with no abnormal results Fuel Storage Pools to Cask Storage Pit Including Cross Connecting Fuel Storage Pools Unit 2 Fuel Pool oling is not in service A crud burst from hydrolyzing p.

ctivatbs has resulted in a North Spent Fuel Pool ARM alarm with an indicated reading of 40 mr/hr.

/ sp a<

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

a.

Place Unit 2 Fuel Pool Cooling demineralizer in service per S53.1.A, Startup and Temperature Control of Fuel Pool Cooling System 1

b.

Secure Core Spray valve LLRT per ST-4-LLR-161-2, "A Core Spray Pump Discharge "

c.

Secure "2B" RHR from Shutdown Cooling mode per S51.8.B, Shutdown Cooling/Reactor Coolant Circulation Operation Start-up and Shutdown

d.

Install Fuel Pool Gates Between Fuel Storage Pool and Cask Storage Pit per M-097-009, Cask Loading Pit Gate Removal, Installation, Maintenance And Movement Of Fuel Pool Gates Between Storage/Repair Locations

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LGS/PBAPS 2005 NRC LSRO Licensinq Examination Answer Key and Question Data Psychometrics Cognitive (H, L)

I H I PRA(Y/N) 1 SRO Choice Source:

Reference(s):

Learning Objective:

Knowledge/Ability:

a.

Direct From Bank NRC-ILT-05-Q89 S53.1.A LLOT0750.7 295033 G2.3.10 I Importance: 3.3

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 - Installing Fuel Pool gates will not lower Refuel Floor radiation levels.

Required Attachments or Reference I Unit (0, 1, 2, 3) 12 I N I Y 43.4 Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensina Examination Question: 04 v

04 of 50 ATTACHMENT Q04 IS PROVIDED LGS Unit 1 plant conditions are as follows:

After full power operation for 640 days, a shutdown is in progress per GP-6.1, "IA" RHR is in Shutdown Cooling with the following information provided Shutdown Operations-Refueling Core alteration and Core Offload Reactor has been shutdown for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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-51-103A, 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?

1 Heat Exchanger Outlet OPCON Tern pe ratu re

a.

b.

C.

d.

Rise 3

Rise 4

Lower 3

Lower 4

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LGS/PBAPS 2005 NRC LSRO Licensina Examination Answer Key and Question Data M-042 Sheet 2 Required Attachments or Reference Question #

04 Source:

Reference(s1:

Choice New Exam Item S51.8.B

a.

Learning 0 bjective:

Knowledge/Ability:

b.

NLRS00372L.3B 205000 A I.08 1 Importance: 2.9 C.

d.

Basis or Justification 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.

Incorrect - See answer C Incorrect - See answer C Incorrect - See answer C Prepared by: CBG

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

L 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 2B 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 48

c.

FPCC Pumps will not automatically trip and must be manually secured when LOW FPCC PUMP SUCTION (206221 A-I) 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 (212 Cleanup J-5) alarm

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LGS/PBAPS 2005 NRC LSRO Licensinq Examination

a.

b.

C.

d.

Answer Key and Question Data 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-I) will occur after the pump trips. This distractor is incorrect because an automatic action will occur (Pump Trip) on Low Skimmer Surge Tank Level 48 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 B4 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 48 or Low Suction pressure 6 psig Question #

05 Cognitive (H, L)

Unit (0, 1,2, 3)

Choice I Basis or Justification L

PRA (Y/N)

SRO 2

N N

Source:

Reference (s):

Learning Objective:

Knowledge/Ability:

Required Attachments or Reference New Exam Item SURGE TANK LO LEVEL NLSR0750.11 233000 K6.10 1 Importance: 3.3 LOW FPCC PUMP SUCTION (20C221 A-I), 20C222 B4 SKIMMER Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 06 06 of 50 4

6 k LGS Unit 1 plant conditions are as follows:

v A Post Maintenance Test (PMT) is being perform on the Rod Drift Circuitry The ROD DRIFT TEST pushbutton is depressehith 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 l l Odd Reed Switch closed

c.

Simulates no signal from the Rod Motion Timer Card

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

LGS/PBAPS

~-

2005 NRC LSRO Licensina Examination

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Required Attachments or Reference Answer Key and Question Data Cognitive (H, L)

Unit (0, 1, 2, 3)

Question#

06 L

PRA (Y/N)

SRO 1

N N

Choice Source:

Reference( s):

Learning Obiective:

a.

~

New Exam Item S73.0.C NLSR00080 (No Objective)

b.

C.

d.

Basis or Justification 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 (Le. 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 Knowledge/Ability: I 201002 A4.03 I Importance: 2.8 (Description of K&A, from catalog)

Ability to manually operate and/or monitor in the control room:

Rod Drift Test Switch Prepared by: CBG

LGS/PBAPS 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?

a.

b.

C.

d.

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

LGS/PBAPS

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2005 NRC LSRO Licensing Examination Required Attachments or Reference Answer Key and Question Data Source:

Reference( s):

Learning 0 bjective:

Knowledge/Ability:

v 1 Question #

07 New Exam Item ON-I 04 NLSRO-0080.2 F 214000 K1.05

[ Importance: 3.3 Choice

a.

b.

C.

d.

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 believes 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 Prepared by: CBG

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LGWPBAPS 2005 NRC LSRO Licensina Examination Question: 08 LGS Unit 1 plant conditions are as follows:

u 08 of 50 Reactor Mode Switch is in Startup RPS Shorting Links are installed All IRMs are on range 4 indicating etween 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.

b.

C.

d.

An IRM Downscale Rod Block will occur due to 1 C IRM indicating 10/125 An IRM Rod Block will occur due to IRM detector withdrawn with mode switch in Startup An IRM Upscale Rod Block and Half Scram will occur due to IRM being inoperable An IRM Upscale Rod Block and Full Scram will occur due to IRM detector withdrawn with Mode Switch in Startup

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

L Unit (0. 1. 2. 3) 2 Answer Key and Question Data PRA (Y/N)

SRO N

N

/Choice Source:

Reference(s):

Learning 0 bject ive:

Knowledge/Ability:

r New Exam Item T-102, Trip Bases NLSR00240.3Cl 21 5003 K5.03 I Importance: 3.1 Basis or Justification Incorrect - Set point for IRM downscale rod block is (5/125).

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

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

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

LGSIPBAPS 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.

v

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, continue transfers, monitor for multiple challenges Suspend transfers and initiate a Condition Report (CR). Obtain NMD Management approval prior to resuming transfers

LGS/PBAPS 2005 NRC LSRO Licensing Examination Answer Key and Question Data Question #

09 Required Attachments or Reference Choice Cognitive (H, L)

Unit (0. 1. 2.3)

a.

L PRA (Y/N)

SRO 0

N Y 43.5

b.

Reference(s):

Learning C.

FH-105 NLSRO-b767.6

d.

0 bjective:

Knowledge/Ability:

Basis or Justification Incorrect - See justification for C.

G2.2.26 I Importance: 3.7 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.

I Psvchometrics 1

Source Documentation Source:

I Modified from Bank NRC 2002 (Q35)

Prepared by: CBG

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

I 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

-AA-203, EXPOSURE CONROL AND AUTHORIZATION?

a.

isor Only b

L

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 Licensing Examination Cognitive (H, L)

Unit (0. 1. 2. 3)

Answer Key and Question Data Question #

10 L

PRA (Y/N)

SRO 0

N Y 43.4 Choice Source:

Reference(s1:

a.

New Exam Item RP-AA-203

b.

Learning 0 bjective:

Knowledge/Ability:

C.

NLSRO1760.4 G2.3.4 I Importance: 3.1

d.

Basis or Justification Incorrect - Radiation Protection Manager 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 Psychometrics I Source Documentation Prepared by: CBG

LGSlPBAPS 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 Licensing Examination Source:

Reference(s):

Learning Answer Key and Question Data Modified from Bank NRC2002 (Q45)

R P-AA-2 03 NLSRO-1760.4 Choice 0 bjective:

Know I ed g e/A b i I i ty :

a.

G 2.3.1 I Importance: 3.0

b.

C.

d.

Basis or Justification Incorrect - See explanation for d 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 Required Attachments or Reference Cognitive (H, L)

L PRA (Y/N)

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

Y 43.4 I Source Documentation Prepared by: CBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 12 12 of 50 WHICH ONE of the following is the least severe Emergency Action Level (EAL) where the refueling crew will be required to evacuate to an offsite assembly area?

b

a. Unusual Event

b. Alert

c.

Site Area Emergency

d.

General Emergency

LGWPBAPS Source:

Learning Reference(s):

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2005 NRC LSRO Licensinq Examination Direct from bank NRC2002 ((244)

LSROl570.2 EP-M-111 Answer Key and Question Data Objective:

Knowledge/Ability:

Question #

12 2.4.29 I Importance: 4.0 Choice

a.

b.

C.

d.

Basis or Justification Incorrect - See Answer C Incorrect - See Answer C Correct - EP-AA-I 12-1 00-F-01, Step 1.3 requires evacuation of site personnel. Less server emergency action levels do not require off site evacuation Incorrect - See Answer C Required Attachments or Reference I Psychometrics Coanitive (H. L)

I L 1 SRO Prepared by: CBG

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

L-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-LOADING, 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 I njection

d.

8000GPM Prevent RHR Pump Runout

LGWPBAPS 2005 NRC LSRO Licensing Examination Choice

a.

Answer Key and Question Data I

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 Question #

13

b.

instruments are subjected to.

Incorrect - Has no effect on in-core visibility. See a justification C.

d.

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 Cognitive (H, L)

Unit (0, 1, 2,3)

L PRA (Y/N)

SRO 2

N Y 43.2 0 b iective:

Knowledge/Ability: 1 G2.1.32 I Importance: 3.8 (Description of K&A, from catalog)

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:

4 OPCON 5 Shift turnover is in progress in the MCR and on the Refuel Floor A refuel crew Pre-Job brief is required for special grapple testing involving fuel A Radiation Protection (RP) Technician is not on the refuel floor, but is on-site and movement in the spent fuel pool only available at all times WHICH ONE of the following HANDLING DIRECTOR O

L individual responsible for conducting the refuel crew per OP-LG-112-101-1011, FUEL Ability to Commence Fuel Movements briefing, and the ability to com Brief Conductor

a.

Shift Manager Fuel moves may commence

b.

Shift Manager Fuel moves may NOT commence

c.

Fuel Handling Director Fuel moves may commence

d.

Fuel Handling Director Fuel moves may NOT commence

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

Unit (0, 1, 2, 3)

Answer Key and Question Data L

PRA (Y/N)

SRO 2

N Y 43.6 Question #

14 Source:

Reference(s):

Learning Choice Modified from Bank NRC 2002 (Q42)

OP-LG-112-101-1011 / HU-AA-1211 N LS RO-0767.8

a.

0 bjective:

Knowledge/Ability:

b.

G2.2.29

[ Importance: 3.8 C.

d.

Basis or Justification Incorrect - See answer D Incorrect - See answer D Incorrect - See answer D Correct Answer - The Fuel Handling director is responsible for conducting the briefing (per HU-AA-1211) and continuous RP coverage is required (per OP-LG-112-101-101 1) on the refuel floor regardless of whether the work is in the spent fuel pool onlv.

Required Attachments or Reference 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 events 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 2200°F

d.

All Vessel Head Closure Bolts Less than fully tensioned

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LGS/PBAPS 2005 NRC LSRO Licensinq Examination

b.

Answer Key and Question Data Incorrect - Mode switch to REFUEL is independent of OPCON.

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 fullv tensioned I Question #

15 1 Choice I Basis or Justification Psychometrics t

Cognitive (HI L) 1/

PRA (Y/N)

SRO b l c,

Unit (0, 1, 2, 3)

N Y 43.5 Incorrect - Average coolant temperature <200°F is the requirement for entry into OPCON 4 I

1 d.

1 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 (Description of K&A, from catalog)

Ability to determine mode of operation Prepared by: CBG

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

L-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 that were received within the last two minutes 20C221 B-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-I Seal #3 Reactor Well (Top Seal)

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

or Well per S53.0.A 2

9 FPCCU pump per S53.8.E O

L

./

c.

Reduce skimmer surge tank level per S53.3.G

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

I Answer Key and Question Data Cognitive (H, L)

Unit (0. 1.2. 3)

Question #

16 H

PRA (Y/N)

SRO 2

N Y 43.5 Choice r--

Source:

Reference( s):

Learning b

New Exam Item S53.0.A NSLRO-1550.1 B Basis or 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 Objective:

KnowledgelAbility:

Action Level Incorrect - The cause of the Fuel Pool Cooling and Cleanup Trouble alarm is due to' 2.4.45 I Importance: 3.6 lowering level due to both Cavity seals being failed. Starting an additiona 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.

Required Attachments or Reference

- I Psvchometrics I Source Documentation 1

Prepared by: CBG

LGSlPBAPS 2005 NRC LSRO Licensina Examination Question: 17 17 of 50 u 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 of 1AY160 (RPS/UPS power) electrical bus.

a.

b. Fuel moves cannot occur in any core quadrants

c.

Fuel moves can continue in A & C core quadrants only

d. Fuel moves can continue in B & D core quadrants only

~~

~

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

H PRA (Y/N)

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

Answer Key and Question Data SRO Y 43.2 Question #

17 Source:

Reference(s):

Obiective:

Learning Choice New Exam Item E-1AY16O / Tech Spec 3.9.2 LLSRO-0655.1 F

a.

b.

C.

d.

Basis or Justification Incorrect - See Answer B Correct Answer - A loss of 1AY160 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 1A or I C SRM to be operable. Fuel moves in the D quadrant would require 1A or 1C SRM to be operable.

Incorrect - See Answer B Incorrect - See Answer B 1

Required Attachments or Reference L

I I

Knowledge/Ability: I 21 5004 K2.01 I Importance: 2.8 (Description of K&A, from catalog)

Knowledge of the electrical power supplies to the following:

SRM Channels/Detectors Prepared by: CBG

LGSlPBAPS 2005 NRC LSRO Licensins Examination Question: 18 18 of 50 LGS Unit 1 plant conditions are as follows:

L 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 D1 I 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

Source:

Reference( s):

Learning Objective:

Knowledge/Ability:

LGS/PBAPS 2005 NRC LSRO Licensing Examination New Exam Item E-I 0 N LS RO-0655.3 264000 K1.01 I Importance: 4.1 Answer Key and Question Data Question #

18 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 Reference Knowledge of the physical connections and /or cause-effect relationships between Emergency Generators and the following:

A.C. Electrical Distribution Prepared by: CBG

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

L OPCON 5 Vessel Disassembly is in progress per GP-6.1 Area Radiation Monitor RIS30-MI-2K600 has been placed to "ZERO" position in preparation for moving the steam dryer to the equipment pit.

WHICH ONE of the following describes the expected indications on the Area Rad Monitor indicating unit in the Aux. Equipment Room?

Meter Indication Low Light

a.

Upscale Lit

b.

Downscale Lit

c.

Upscale Not Lit

d.

Downscale Not Lit

~~

LGS/PBAPS 2005 NRC LSRO Licensina Examination Answer Key and Question Data Psychometrics Cognitive (H, L)

L PRA (Y/N)

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

N Question #

19 Source:

Learning Objective:

Knowledge/Ability:

Reference( s):

Choice Direct From Bank (LSRO-2928)

NSLRO-0710 (No Objective) 272000 A I.01 1 Importance: 3.2 GP-6.1

a.

b.

C.

d.

Basis or Justification Incorrect - See Answer B Correct Answer - When the ARM mode switch is taken to Zero, the meter output goes downscale and the Low white light illuminates Incorrect - See Answer B Incorrect - See Answer B Required Attachments or Reference Prepared by: CBG

LGS/PBAPS 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 Area Refuel Area Radiation Monitors are alarming All four (4) Refuel Floor Exhaust monitors indicate 2.6 mrem/hour and are slowly All automatic actions occur as designed rising 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 Bypass Refuel Floor Isolation per GP-8.4, Isolation Bypasses 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-I20 Fuel ha nd I i ng Pro b I ems Manually Isolate Refuel Floor Per S76.8.8, Initiation of Reactor Enclosure or Refuel Floor Secondary Containment

LGS/PBAPS Choice

a.

b.

~~~

2005 NRC LSRO Licensins Examination Basis or Justification Incorrect - When Refuel Exhaust Rad levels exceed 2.0 mremlhr, 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 GP-8.4.

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

Answer Key and Question Data Reference( s):

Learning ON-1 20 NLSRO-1550.1A C.

Objective:

Knowledge/Ability:

d.

290001 A2.03 I Importance: 3.6 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-I20 directs the Refuel floor to be evacuated and verification of a Refuel Floor isolation Incorrect - See above for justification Required Attachments or Reference Source Documentation Source:

I New Exam Item Prepared by: CBG

LGSPBAPS 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 1A Reactor Water Cleanup (RWCU) is operating in the Alternate Decay Heat Removal mode per S44.7.B, 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. IA RWCU pump trips with no system isolation *

b. IA RWCU pump remains in service with no system isolation

c.

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

I

d.

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

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

Unit (0. 1. 2. 3)

Answer Key and Question Data H

PRA (Y/N)

SRO 1

N N

Question #

21 Source:

Reference( s):

0 biect ive :

Learning Choice New Exam Item MCR ARC - 112 G-2, 1A RWCU Recirc Pump Trip NLSRO-O110.6A

a.

b.

C.

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 Knowledge/Ability: I 204000 A3.04 I Importance: 3.5 (Description of K&A, from catalog)

Ability to monitor automatic operations of the Reactor Water Cleanup System including:

Response to interlocks and trips designed to protect system components Prepared by: CBG

~~

LGS/PBAPS 2005 NRC LSRO Licensina Examination Question: 22 22 of 50 ATTACHEMENT 422 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

Cognitive (H, L)

Unit (0. 1.2.3)

~

~~

LGS/PBAPS 2005 NRC LSRO Licensinq Examination L

1 PRA(Y/N)

SRO 0

I N N

Answer Key and Question Data I Knowledge/Ability: I 291006 K1.08 I Importance: 3.0 Question#

22 Reference( s):

Learning Obiective:

Choice 1 Basis or Justification GF Materials Chapter 3, Heat Exchangers and Condensers Objective 10

a.

I Correct Answer I

b.

C.

d.

Required Attachments or Reference GF Equation Sheet

- I Psychometrics Source Documentation Source :

I Direct From Bank (QID B331)

(Description of K&A, from catalog) 291 006, Relationship between flow rates and temperature 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 fuel bundle is being lowered into the core Bottom of fuel bundle has just cleared the top guide One of the grapple air supply lines has just separated at the end fitting WHICH ONE of the following describes the effect on the grapple and the bundle?

a. Both grapple hooks remain closed and the bundle is not released

b.

Both grapple hooks immediately open and the bundle is released

c.

One grapple hook immediately opens and the bundle is released

d. One grapple hook operis immediately after the bundle is seated

LGWPBAPS 2005 NRC LSRO Licensina Examination Answer Key and Question Data Question#

23 Psychometrics Cognitive (H, L)

L PRA (Y/N)

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

N Choice Reference(s):

Objective:

Knowledge/Ability:

Learning

/d M97.OM NLSRO-0766.13 295023 AA1.03 I Importance: 3.6 L

Basis or Justification Correct - Air pressure is required to release the grapple. Without air pressure the grapple will remain as-is Incorrect - See answer A Incorrect - See answer A Incorrect - See answer A Required Attachments or Reference Source Documentation Source:

I Direct From Bank (LSRO-2723)

Prepared by: CBG

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

L.

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 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 South Stack Monitor

b.

e t

e c -a a < dRL rco All dampers isolate Radiation Monitors All dampers Isolate I

North Stack Monitor

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

Unit (0. 1. 2. 3)

Answer Key and Question DAta H

PRA (Y/N)

SRO 2

N N

Question#

24 Source:

Learning Objective:

Knowledge/Ability:

Reference(s):

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 PBILGS Difference - At LGS a failure of a channel to actuate will result in a damper remairiing in its as found position, division redundant dampers will allow the appropriate flow path to be alignedkecured.

Incorrect - South Stack is the exit path when normal ventilation is in service. When the isolation signal is received the exit path is routed to the North Stack New Exam Item NLSOR0200.2 295034 EK2.01 14.2 GP-8.1 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 Required Attachments or Reference I Psvchometrics Prepared by: CBG

LGSIPBAPS 2005 NRC LSRO Licensina 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 I&C testing resulted in a Reactor Enclosure Isolation Slgna I-A broken instrument air E resulted in HV76-019 Refuel Floor/SBGT Connecting 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 Licensinq Examination Choice

a.

b.

Answer Key and Question Data Basis or Justification Incorrect - Refuel Floor differential Pressure dropped to -0.1 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 Cognitive (H, L)

H 2

Unit (0, 1, 2, 3)

C.

PRA (Y/N)

SRO N

N

d.

Source:

Reference(s):

Learning Objective:

Knowledge/Ability:

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.

New Exam Item GP-8.1 NLSRO-0200.5 261 000 A4.02 I Importance: 3.1 Required Attachments or Reference

LGWPBAPS 2005 NRC LSRO Licensina 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? (Assume continued forced circulation through the core)

a. Moderator temperature coefficient

b. Fuel temperature coefficient

c.

Void coefficient

d.

Pressure coefficient

LGS/PBAPS Choice

a.

_ _ _ ~

2005 NRC LSRO Licensina Examination Basis or Justification Correct Answer Cognitive (H, L)

Unit (0, 1,2,3)

b.

L PRA (Y/N)

SRO 0

N N

C.

I Source:

Reference(s):

Learning 0 biective:

d.

Direct From Bank NRC QID:B52 BWR Fundamentals Chapter 2 BWR Fundamentals Chapter 2 Objective 9 Required Attachments or Reference I

I I

I Knowledge/Ability: I 292004 K1.I4 I Importance: 3.3 (Description of K&A, from catalog)

I Evaluate change in shutdown margin due to changes in plant parameter status Prepared by: CBG

LGSlPBAPS 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 28 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 2B 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.

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

LGS/PBAPS Choice

a.

b.

C.

2005 NRC LSRO Licensing Examination 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 Required Attachments or Reference

d.

Answer Key and Question Data Incorrect - Only directed during a loss of offsite power event (E-10120) S I I

.8.A prerequisite.

- Psychometrics Cognitive (H, L)

H PRA (Y/N)

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

N Source:

Learning Objective:

Knowledge/Ability:

Referen ce(s):

Source Documentation New Exam Item NLSRO-460.2B 29501 8 AKI.01 1 Importance: 3.6 S I 1.8.A, S51.8.G, MCR ARC 112 G-2 Prepared by: CBG

LGS/PBAPS

~

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

L OPCON 5 Reactor cavity water level is 468 inches CRDM replacement is in progress under vessel All Control Rod Blade replacements have been completed IA loop of RHR is operating in Shutdown Cooling 1 B RHR HX is INOPERABLE and not expected to be OPERABLE for 6 days 1 C and 1 D RHR pumps are both inoperable 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 verifieG available withll\\ 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

d.

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

~

~~

~~

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

Unit (0. 1. 2.3)

Answer Key and Question Data H

PRA (Y/N)

SRO 1

N Y 43.2 Question #

28 Source:

Reference(s):

Objective:

Knowledge/Ability:

Learning F-Modified From Bank 202866 Tech Spec 3.9.1 1.1/2 295021 AK1.03 I Importance: 3.9 NLSRO-370.11 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.I Incorrect - If no RHR Shutdown Cooling subsystems are in operation, reactor coolant circulation shall be verified within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and alternate method of decay heat removal must be verified available Tech Specs.

Required Attachments or Reference Prepared by: CBG

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

L New fuel receipt is in progress While lowering a new bundle in a rack location, the HOIST LOADED light extinguishes with the hoist encoder reading +I 73 inches.

WHICH ONE of the following describes the required actions?

a. Stop lowering the hoist, verify grapple engaged, raise the fuel bundle, notify the Fuel Handling Director, suspend fuel handling operations

b. Continue to lower the hoist until the SLACK CABLE light is lit, then verify bundle is properly seated, continue fuel handling operations

c.

Stop lowering the hoist, re-attempt to seat the bundle in the original orientation before attempting a different location, suspend fuel handling operations

d. Raise the bundle, attempt to seat the bundle using a different orientation, document on the CCTAS the new orientation of the bundle, continue fuel handling operations

LGS/PBAPS Choice

a.

b.

C.

d.

~

2005 NRC LSRO Licensina Examination Basis or Justification Correct - Step 3.13.2 of S97.0.M. provides direction on what actions to take if the hoist loaded light extinguishes prematurely (16.0 mrem/hr), SGTS e x h a u w 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 flow path to be aligned/secured.

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 I and Unit 2 HVAC rad monitors will not have flow past them following an isolation and are not valid indications Incorrect - All dampers will isolate, path is to the Main Stack Required Attachments or Reference 1

I I

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

Process Radiation Monitoring System Prepared by: CBG

LGS/PBAPS 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-6.1 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 21 0°F WHICH ONE of the following describes the RWCU valves that will isolate and the reason for the isolation?

Valve(s) that Auto Isolate Reason for Isolation

a.

MO RWCU INBD isolation, MO RWCU OUTBD isolation, MO RWCU Return Minimize loss of RPV inventory

b.

MO RWCU OUTBD isolation only Prevent Resin Damage

c.

MO RWCU INBD isolation, Prevent Resin Damage MO RWCU OUTBD isolation, MO RWCU Return

d.

MO-18 only OUTBD isolation only Minimize loss of RPV inventory

LGS/PBAPS Cognitive (HI L)

Unit (0, 1,2, 3) 2005 NRC LSRO Licensing Examination H

PRA (Y/N)

SRO 2

N N

Answer Key and Question Data Source:

Reference(s):

Learning

- I Question #

32 New Exam Item COL GP-8b NLSRO-0110.4 Choice 0 bjective:

Knowledge/Ability:

e 204000 A3.04 I Importance: 3.4 Basis or Justification Incorrect - Distractor test candidates knowledge RWCU isolation setpoints. RWCU will not isolate until RPV level is + I 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 I

[ Psychometrics I Source Documentation Prepared by: CBG

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

Fuel Bundles:

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

" A WRNM Detector is partially withdrawn with 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 provided that the "A" WRNM indicated count rate remains above 1.I cps

b.

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

c.

must be suspended until "A' WRNM indicates a count rate above 1.2 CPS must be suspended until "C" WRNM is operable

d.

LGS/PBAPS Cognitive (H, L)

Unit (0, 1, 2, 3)

~

2005 NRC LSRO Licensina Examination H

PRA (Y/N)

SRO 2

N Y 43.2 Answer Key and Question Data v

Question #

33 Source:

Reference( s):

Objective:

Knowledge/Ability:

Learning Choice F New Exam Item Tech Spec 3.3.1.2 NLSRO-0240.4E 21 5003 K5.03 I Importance: 3.1 Basis or Justification Incorrect - See answer D Incorrect - Only the A WRNM is required to be operable during spiral offload or reload when the fueled region includes only that WRNM detector Correct Answer-With a signal to noise ration of 6 the minimum count rate to declare the A WRNM operable is > I.2 cps (per figure 3.3.1.2-1 of Tech Spec 3.3.1.2). 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 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:

v 0

Control rod exercising is in progress 0

A control rod is being inserted from position 48 to 00 0

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)

LGWPBAPS 2005 NRC LSRO Licensing Examination Choice

a.

b.

C.

d.

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.

Required Attachments or Reference Psychometrics Cognitive (H, L)

H PRA (Y/N)

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

N None Source:

Learning Objective:

Knowledge/Ability:

Reference( s):

Direct Exam Bank NLSRO-0070 EO 4e 201 003 K6.01 I Importance: 3.3 LOT-5003 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.

Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensina Examination Question: 35

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~~

Page 35 of 50

- PBAPS Unit 3 plant conditions are as follows:

Mode5 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

Answer Key and Question Data Question # 35 Choice Psychometrics Cognitive (H, L)

H PRA (Y/N)

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

N

a.

Reference(s):

Learning

b.

NLSRO-0370 NLSRO-0370 EO 3 C.

d.

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.

None Required Attachments or Reference I

I Obiective:

Knowledge/Ability: I 295021 AK1.03 I Importance: 3.9 (Description of K&A, from catalog)

Knowledge of the operational implications of the following concepts as they apply to LOSS OF SHUTDOWN COOLING: Adequate core cooling.

Prepared by: JBG

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

Mode5 Core Shuffle Part II is in progress 0

Loading the 5h fuel bundle around the E WRNM caused the count rate to rise from 35 CPS to 150 CPS 0

All WRNM count rates have stabilized WHICH ONE of the following identifies the required actions to be taken on the refueling bridge, if any, for this situation?

a.

b.

C.

d.

b No action is required due to the limited extent of the given count rate rise.

If grappled, raise the fuel bundle from the core to above the upper grid.

No action is required for any count rate rise caused by the first five bundles around a WRNM detector.

If grappled, release the grapple and evacuate personnel on the Fuel Floor to Turbine Building elevation 165.

LGS/PBAPS Cognitive (H, L)

H PRA (Y/N)

Unit (0. 1. 2.3) 2 N

2005 NRC LSRO Licensina Examination LSRO N

Answer Key and Question Data v

Question # 36 Source:

Learning Objective:

Knowledge/Ability:

Reference(s):

I New Exam Item NLSRO-1550 1 a 295023 AA1.03

[ Importance: 3.6 ON-124, FH-6C (9.1)

Basis or Justification Incorrect. Action is required when the count rate doubles twice.

Correct. Raising the bundle from the core should terminate the unexpected count rate increase and allow for Reactor Engineering to evaluate the situation incorrect. Action is required if the count rate doubles twice after loading the 4'h bundle around a WRNM detector.

Incorrect. Evacuation of the Fuel Floor is only required if the count rate continues to rise, indicating an inadvertent criticality.

None Required Attachments or Reference I Psvchometrics 1

Source Documentation Prepared by: JBG

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

L 6-ok, 0

ModeP/

0 Core Shuffle Part I has just begun RBCCW is backing up TBCCW 0

The CRD system is in service 0

The RWCU system is in service in a normal lineup dumping 60 GPM to the Main Condenser 0

A fire header break in the RBCCW room has caused both RBCCW pumps to trip

.~

WHICH ONE of the following describes the operational implications of this loss of cooling water?

a. Higher than normal plant dose rates

b. Loss of Instrument Air to the Refueling Bridge

c. Reactor Cavity and Fuel Pool visibility will degrade

d. Reactor Cavity and Fuel Pool water level will begin to lower

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

Unit (0. 1. 2.3)

Answer Key and Question Data I Question # 37 H

PRA (Y/N)

LSRO 2

N N

1 Choice Source:

Reference(s):

Learning Objective:

Knowledge/Ability:

a.

b.

New Exam question NLSRO-0370, M-316, GP-6, FH-6C NLSRO-0370 EO 1L 295018 AKI.01 I Importance: 3.6 C.

d.

Basis or Justification 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 OOF, around 90°F.

Incorrect. The Refueling Bridge at PBAPS has an air compressor mounted on the 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.

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 Required Attachments or Reference I Psvchometrics I

Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 38 Page 38 of 50

- PBAPS Unit 3 plant conditions are as follows:

Mode5 0

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

Failure of the:

b(c, L & u j f -

F

a.

b.

h d

a g

t a

on the m e l i n g Bridge Mast Orientation interlock on the Refueling Bridge

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

L Cognitive (H, L)

Unit (0.

1. 2. 3)

~~

LGS/PBAPS 2005 NRC LSRO Licensinq Examination L

PRA (Y/N)

LSRO 0

N N

Answer Key and Question Data Source:

Reference(s):

Question # 38 New Exam Item FH-6C. SO 18.1.A-3 Choice Learning Objective:

KnowledgelAbility:

a.

NLSRO-0763 E06 234000 K3.03 I Importance: 3.8

b.

C.

d.

Basis or Justification Incorrect. Not required for core alterations.

Incorrect. Optionally used when in full auto. Not needed for core alterations Incorrect. Fuel movement can continue in the manual mode.

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.

Required Attachments or Reference

- I Psvchometrics 1

I Source Documentation Prepared by: JBG

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

Unit 3 is at 100% power Unit 2 is in Mode 5 0

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 0

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

b.

Answer Key and Question Data Question # 39 Choice I Basis or Justification 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

a.

I Incorrect. The EDG will be loaded with both the E-32 and E-33 busses. Both busses I C.

d.

I will initially receive a trip signal and then will reclose automatically. The candidate I

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.

Cognitive (H, L)

Unit (0. 1. 2. 3)

H PRA (Y/N)

LSRO 0

Y N

Required Attachments or Reference Source:

Reference( s):

Learning 0 bjective:

Knowledg e/A bi I ity :

None Modified Bank Item NLSRO-0655, LOT-5054 NLSRO-0655 EO 3 295003 AK2.02 I Importance: 4.2 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF A.C. POWER and the following: Emergency generators.

Prepared by: JBG

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

0 Mode5 0

Core Shuffle Part II is in progress F 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 Annunciator RPS Scram Group Lights

a.

b.

C.

d.

A Lit A

Extinguished B

Lit B

Extinguished

LGS/PBAPS 2005 NRC LSRO Licensing Examination Choice

a.

b.

C.

d.

Answer Key and Question Data Question # 40 Basis or Justification 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.

Cognitive (H, L)

L PRA (Y/N)

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

None Required Attachments or Reference LSRO N

Source:

Reference(s):

Objective:

Learning New Exam Item ARC 21 1 C-1 B Channel Reactor Auto Scram NLSRO-0240.01 b Knowledge/Ability: I 21 2000 A3.04 I Importance: 3.8 (Description of K&A, from catalog)

Ability to monitor automatic operations of the REACTOR PROTECTION SYSTEM including:

System status lights and alarms.

~~~

Prepared by: JBG

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

0 A control rod is moved from position 48 to 24 using the EMERGENCY IN switch on panel 20C005.

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

0 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

LGSlPBAPS I

~

2005 NRC LSRO Licensina Examination Cognitive (H, L)

L PRA (Y/N)

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

Answer Key and Question Data 1-Question # 41 LSRO N

Choice I=

Source :

Learning 0 bjective:

Knowledge/Ability:

Reference( s) :

Direct Exam Bank NLSRO-0080 EO 9e NLSRO-0080 214000 K1.05 I Importance: 3.3

b.

ic

d.

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.

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.

Required Attachments or Reference Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 42 Page 42 of 50

~

PBAPS Unit 2 plant conditions were as follows:

0 Mode5 0

The 2A RHR pump was operating at 6000 GPM in the Fuel Pool to Reactor mode The following transient occurs:

0 The Skimmer Surge Tank Low level alarm is received 0

Skimmer Surge Tank level is 52 as displayed on Ll-2695 located on the 20C075 Panel WHICH ONE of the following describes plant response and required actions for the conditions above?

The plant response The required actions

a.

2A RHR pump is running Shutdown the 2A RHR pump as required by ARC 20C075 B-3, Skimmer Surge Tank Low Level

b.

2A RHR pump is running

+

c.

2A RHR pump is tripped

d.

2A RHR pump is tripped Reduce and maintain 2A RHR pump flow below 4000 GPM using A 0 10.4-2, RHR System -

Fuel Pool to Reactor Mode Verify that the Fuel Pool Cooling Water pumps are also tripped as required by ARC 20C075 B-3, Skimmer Surge Tank LOW Level Restore the 2A RHR pump using A 0 10.4-2, RHR System - Fuel Pool to Reactor Mode

LGS/PBAPS 2005 NRC LSRO Licensing Examination Answer Key and Question Data Question # 42 Psychometrics Cognitive (H, L)

H PRA (Y/N)

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

Y 43.5 Choice

a.

Source:

Reference(s):

Learning Objective:

Knowledge/Ability:

b.

New Exam Item ARC 20C075 8-3, A 0 10.4-2 NLSRO-0750 EO 5,IO 400000 A2.02 I Importance: 3.0 C.

d.

Basis or Justification Correct. ARC 20C075 B-3 requires the RHR pump to be shutdown under these conditions.

Incorrect. Although the procedure discusses reducing flow to maintain Skimmer Surge Tank level, RHR pumps are not to be run at e4000 GPM to prevent pump damage.

Incorrect. The RHR pump does not automatically trip. The Fuel Pool Cooling water pump trips do not occur until 40.

Incorrect. The RHR pump does not automatically trip on low Skimmer Surge Tank level.

None Required Attachments or Reference I

I I

Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensina Examination

~~

~~

~

Question: 43 Page 43 of 50 Peach Bottom Unit 3 conditions are as follows:

0 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

d.

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

LGS/PBAPS 2005 NRC LSRO Licensing Examination Answer Key and Question Data Psychometrics Cognitive (H, L)

H PRA (Y/N)

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

Y 43.1 Question ## 43 Reference( s):

Learning L

NLSR00190 / TS 3.6.4.1 NLSROO190 E02 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.

Objective:

Knowledge/Ability:

Required Attachments or Reference 290001 G2.1.I2 I Importance: 4.0 PBAPS Unit 3 TS sections 3.6.4.1 and 3.6.4.3 I

Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensina Examination

~

Question: 44 Page 44 of 50 PBAPS Unit 2 plant conditions are as follows:

0 Mode4 0

The 2A RHR pump is in Shutdown Cooling 0

A fire in panel 20Y033 has caused a short that deenergized the Inboard PClS logic WHICH ONE of the following describes the status of the listed Shutdown Cooling system components after the PClS power loss?

0 MO-17 RHR Outboard Shutdown Cooling Suction Isolation valve 0

MO-18 RHR Inboard Shutdown Cooling Suction Isolation valve MO-25A RHR LPCl Injection valve RHR Valves 2A RHR Pump

a.

b.

L C.

d.

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

~

~~

2005 NRC LSRO Licensing Examination

\\-

Answer Key and Question Data Question ## 44 Choice I Basis or Justification

a.

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.

b.

C.

- Psychometrics Cognitive (H, L)

I PRA(Y/N)

I LSRO 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.

d.

Prepared by: JBG 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.

Source:

Reference(s):

Learning Objective:

Knowledge/Ability:

New Exam Item N LSRO-0370 EO 9 223002 K3.16 I Importance: 3.3

LGS/PBAPS 2005 NRC LSRO Licensing 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

LGWPBAPS 2005 NRC LSRO Licensing Examination Choice

a.

b.

Answer Key and Question Data Basis or Justification A

loss of Shutdown Cooling will occur at 1. This A and 25B. The 2A RHR pump will trip on loss of a 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 C.

Incorrect - The LPCl system must be manually realigned for injection I

Objective:

Knowledge/Ability:

ss of Shutdown Cooling will occur at 1. This will close the MO-17, and 25B. The 2A RHR pump will trip on a loss of suction path. To RHR Pump; the operator must establish an injection path from the and restart the 2A RHR pump 203000 K5.02 I Importance: 3.7 Required Attachments or Reference 1

Source Documentation Prepared by: JBG

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

L Mode5.

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

Reactor Coolant temperature is 1 10°F.

Reactor coolant temperature needs to be lowered to between 90°F and 100°F using the ILRT HPSW Cooling Bypass Valve (HV-2-32-22228D).

WHICH ONE of the following describes the correct operation the ILRT HPSW Cooling Bypass Valve (HV-2-32-22228D) and the effect on the HPSW Heat Exchanger Outlet Temperature?

ILRT HPSW Cooling HPSW Heat Exchanger Bypass Valve Outlet Temperature

a.

b.

C.

Throttle Open Rise Throttle Open Lower Throttle Close Rise Throttle Close Lower

LGS/PBAPS 2005 NRC LSRO Licensing Examination Source:

Learning 0 bjective:

Knowledge/Ability:

Reference(s):

L New Exam Item EO 5 205000 Al.08 I Importance:

NLSRO-0370 Answer Key and Question Data Question # 46 Choice

a.

b.

C.

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 Reference I Source Documentation Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination

_ _ _ _ _ ~

Question: 47 Page 47 of 50 PBAPS Unit 2 plant conditions are as follows:

v 0

Mode4 0

Both Reactor Recirculation pumps are secured 0

2D RHR has been running in Shutdown Cooling at 5000 GPM for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 0

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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. SDC may be secured for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> out of eveiy 8-hour period

d. Raise RPV level to greater than 50 inches

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

Unit (0. 1. 2. 3)

H PRA (Y/N)

LSRO 2

N N

Answer Key and Question Data Source:

Reference(s):

Learning Objective:

Knowledge/Ability:

Question # 47 New Exam Item ON-I 25, GP-12 NLSRO-0370 EO-1 1 290002 K4.05 I Importance: 3.5 Choice

a.

b.

C.

d.

Basis or Justification Incorrect. Natural circulation does not exist without forced circulation unless RPV Level is >50.

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-125. ON-125 provides the guidance in response d if neither a Recirc pump nor a SDC loop can be started.

Correct. 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.

None Required Attachments or Reference 1

I Psvchometrics Prepared by: JBG

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

Mode4 0

RPV temperature 180°F and lowering 0

3A RHR pump is in Shutdown Cooling (SDC) 0 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 fuel damage.

b. Prevent loss of natural circulation.

c.

Prevent inadvertent entry into Mode 3 due to heatup of the RPV.

d.

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

LGS/PBAPS 2005 NRC LSRO Licensing Examination Source:

Reference(s):

Answer Key and Question Data New Exam Item Peach Bottom PRIMARY CONTAINMENT ISOLATION SYSTEM design Question # 48 Learning Objective:

Knowledge/Ability:

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

a.

b.

C.

d.

Basis or Justification Correct. Automatic closure signals are provided to Group 2B 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. Natural circulation is lost at 6 0 if no forced circulation exists. The low water level isolation does not occur until 1.

Incorrect. Exceeding the heatup rate is not the basis for this isolation.

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 Source Documentation Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination Question: 49 Page 49 of 50 v

PBAPS Unit 2 plant conditions are as follows:

Mode5 0

Core Shuffle Part I is in progress 0

Upon raising a leaking fuel bundle the Refuel Floor ARMS alarm and the Reactor Building and Refuel Floor Ventilation Systems isolate Standby Gas Treatment System initiates 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 Cognitive (H, L)

Unit (0, 1, 2, 3)

__ -~

~~

2005 NRC LSRO Licensina Examination L

PRA (Y/N)

LSRO 2

N N

Answer Key and Question Data Question # 49 Source:

Reference(s):

Choice New Exam Item Design basis document: REACTOR BUILDING HVAC SYSTEM (P-S-

a.

Learning 0 bjective:

Knowledge/Ability:

b.

(P-S-25A). LOT-5040B Rx. Bldg. HVAC, T-104 Radioactive Release.

29501 7 AK3.01 I Importance: 3.9 NLSRO-0200 EO lA, 2c, 4 C.

d.

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

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 Reference I OK), PRIMARY CONTAINMENT PRESSURE SUPPRESSION SYSTEM Prepared by: JBG

LGS/PBAPS 2005 NRC LSRO Licensing Examination WRNM A

Question: 50 Page 50 of 50 COUNT RATE INITIAL COUNT AFTER gTH BUNDLE COUNT RATE RATE LOADED TREND 12 12 Stable PBAPS Unit 3 plant conditions are as follows:

B C

Mode5 Core Shuffle I1 is in progress 0

The sixth fuel bundle was just loaded around the B WRNM 0

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

10 50 Slow rise 14 15 Stable D

12 E

11 F

10 I

30 Slow rise 12 Stable 10 Stable G

H 12 12 Stable 11 11 Stable WHICH ONE of the following describes the cause of the reactivity addition indicated on the B WRNM?

I

a. Prompt criticality

b. Localized criticality

c.

Core wide criticality

d. Subcritical multiplication

LGS/PBAPS 2005 NRC LSRO Licensing Examination Answer Key and Question Data Question # 50 Choice i b

Basis or Justification Incorrect. Prompt criticality would result in a much larger and faster power rise.

Correct. The rising count rate on the B WRNM indicates a critical condition in the localized area of the B (and possibly D) WRNM.

Incorrect. Although criticality exists it has not spread core wide or the other WRNMs would be rising.

Incorrect. The fact that B WRNM count rates have doubled twice and continues to rise indicates a critical condition.

None Required Attachments or Reference Psychometrics Cognitive (H, L) 1 PRA(Y/N)

I LSRO v

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

Prepared by: JBG