ML061650309

Final SRO Written Exam Outlines

ML061650309
Person / Time
Site:	Vogtle
Issue date:	02/01/2006
From:	NRC/RGN-II
To:
References
50-424/05-302, 50-425/05-302
Download: ML061650309 (52)

Text

Draft Submittal (Pink Paper)

Senior Reactor Operator Written Exam VOGTLE NOVEMBER RETAKE 2005 EXAM 05000424/2005302 AND 05000425/2005302 WRITTEN ONLY ON NOVEMBER 23, 2005 2/1/06

QUESTIONS REPORT for Questions Draft NRC Exam

1. During a Control Bank D group I dropped rod recovery, you directed the BOP to open all lift coil disconnect switches for control bank D except for the affected rod.

As soon as the RO started rod withdrawal with the bank select switch in the Control Bank D position, a Rod Control Urgent Failure alarm illuminates.

You should direct the RO to:

A. Stop rod withdrawal because the pulser / oscillator is inhibited.

B. Continue rod withdrawal, this alarm is expected and is due to a regulation failure in group 2 of Control Bank D.

C. Stop rod withdrawal since holding currents are being simultaneously applied to the stationary and moveable gripper coils in Control Bank D.

D. Continue rod withdrawal, this alarm is expected due to being in the bank select position resulting in a loss of proper bank overlap.

Wednesday, February 01, 2006 1:59:52 PM DRAFT

QUESTIONS REPORT for Questions Draft NRC Exam K/A 001 Control Rod Drive System.

A2.20 Ability to (a) predict the impacts of the following malfunctions or operations on the CRDS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Isolation of lift coil on affected rod to prevent coil burnout.

K/A MATCH ANALYSIS Question gives a plausible scenario with a dropped control rod which is being withdrawn in accordance with the AOP for rod retrieval. During retrieval a Rod Control Urgent Failure annunciator is received. Candidate decide whether to stop or continue rod retrieval and why.

ANSWER / DISTRACTOR ANALYSIS A. Incorrect. Plausible, Pulser Oscillator is normally inhibited on an urgent failure.

B. Correct. Regulation failure is reason per ARP for Urgent Failure.

C. Incorrect. Plausible, this action occurs if urgent failure is due to a logic problem.

D. Incorrect. Plausible, this is expected alarm, but bank overlap does not feed into the urgent failure alarm.

REFERENCES AOP-18003, Rod Control Malfunction, section A for Dropped Rods in Mode 1 ARP-1 7010 window B06 for ROD CONTROL URGENT FAILURE V-LO-LP-60303, page 12 VEGP learning objectives:

V-LO-LP-60303-03, State why an urgent failure alarm will sound during a dropped rod retrieval.

MCS Time: I Points: 1.00 Version: 0 1 2345 6 7 89 Answer: BACBDDAAAA Scramble Range: A - D Wednesday, February 01, 2006 1:59:52 PM 2

QUESTIONS REPORT for Questions Draft NRC Exam

2. The plant has just entered Mode 4 and currently has the following conditions:

• RCS temperature - 340 degrees F

• RCPs # 1 and # 4- running

• All SG levels are approximately 65% on NR.

• SG ARVs have just been shut and placed in auto.

• RHR Train "B" placed in service in the shutdown cooling mode.

• RHR Train "A" is aligned for ECCS injection.

The RO is controlling the RCS cooldown rate to approximately 50 degrees F per hour when RHR pump "B" unexpectedly trips for reasons unknown.

As the SS, which ONE of the following would be the CORRECT actions for you to direct the crew to take and why ?

A. Align RHR Train NA" to the shutdown cooling mode of operation, continue the cooldown. ARVs cannot provide adequate cooldown at lower RCS temperatures.

B. Leave RHR Train "A" aligned for ECCS injection and use the ARVs to continue the cooldown. Aligning RHR "A" to the shutdown cooling mode could lead to steam binding and / or water hammer if RHR "A' realigned back to the injection mode.

C. Align RHR Train "A" to the shutdown cooling mode of operation and continue the cooldown. Tech Specs considers RHR "A", OPERABLE in Mode 4 as long as it can still be manually aligned to the injection mode.

D. Leave RHR Train "A" aligned for ECCS injection. In Modes 1 through 4 one train of RHR must always be aligned for the ECCS injection mode per Tech Specs.

K/A 006 Emergency Core Cooling System (ECCS).

A2.06 Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.

Water Hammer K/A MATCH ANALYSIS Question places candidate in a Loss of RHR scenario just after entering Mode 4 when an RHR pump trips. Has to decide whether to align the standby train of RHR from the ECCS iniection mode to shutdown coolina mode. With other eauinment available, he Wednesday, February 01, 2006 1:59:52 PM 3

QUESTIONS REPORT for Questions Draft NRC Exam should not. Doing so would cause steam binding / water hammer to other ECCS components.

ANSWER / DISTRACTOR ANALYSIS A. Incorrect. RHR Train "A" should NOT be aligned to shutdown cooling mode as long as RCPs, SG levels, ARVs and / or steam dumps available to prevent steam binding / water hammer of ECCS piping. At lower RCS temperatures it is true that you can not achieve a high cooldown rate. No procedural limitations though.

B. Correct. As long as RCS > 250 degrees F, use ARVs / dumps for cooldown to prevent Wolf Creek Event where ECCS can steam binding / water hammer.

C. Incorrect. Should not be aligned to prevent steam binding / water hammer. The Tech Spec part is correct and plausible.

D. Incorrect. Train "A" should be left in the ECCS injection mode alignment.Tech Specs does allow alignment to shutdown cooling if neccessary as long as you can manually align to ECCS phase which makes this answer plausible.

REFERENCES 18019-C, "Loss of Residual Heat Removal", section A.

Technical Specifications 3.5.2, "ECCS - Operating" Technical Specifications 3.5.3, "ECCS - Shutdown" Technical Specification Bases for 3.5.2, "ECCS - Operating" Technical Specification Bases for 3.5.3, "ECCS - Shutdown" VEGP learninq obiectives:

V-LO-LP-60315-04, "Given the entire AOP, describe:

a. Purpose of selected steps.

b. How and why the step is being performed.

c. Expected response to plant/parameter(s) for the step".

MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: BDDAABDACB Scramble Range: A - D Wednesday, February 01, 2006 1:59:52 PM 4

QUESTIONS REPORT for Questions Draft NRC Exam

3. After swapping from 120 gpm letdown to 75 gpm letdown, the RO has adjusted letdown pressure with the letdown pressure controller PIC-0131 and placed in automatic.

Shortly after the evolution, Letdown Hx temperature element TE-0130 begins to oscillate and fails downscale low with TIC-01 30 in automatic.

Which ONE of the following CORRECTLY describes plant response to this malfunction and the first action(s) you should direct the RO to take ?

A. Letdown temperature would increase, the bypass valve around the CVCS demins would automatically open, an inadvertent RCS boration could occur.

Manually control ACCW flow to the Letdown Hx using TIC-0130 to control cooling.

B. Letdown temperature would decrease, the bypass valve around the CVCS demins would remain shut, an inadvertent RCS dilution could occur.

Open bypass valve around CVCS demins, divert to RHUT to minimize the dilution.

C. Letdown temperature would increase, the bypass valve around the CVCS demins would automatically open, an inadvertent RCS dilution could occur.

Manually control ACCW flow to the Letdown Hx using TIC-01 30 to control cooling.

D. Letdown temperature would decrease, the automatic bypass around the CVCS demins would remain shut, an inadvertent RCS boration could occur.

Open bypass valve around CVCS demins, divert to RHUT to minimize the boration.

K/A 008 Component Cooling Water (ACCW cools Letdown Hx at Vogtle)

A2.09 Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.

Results of excessive exit temperatures from the letdown cooler, including the temperature effects on ion-exchange resins.

K/A MATCH ANALYSIS Question gives a plausible failure of ACCW temperature controller to the Letdown Hx.

CVCS demins would bypass on high temperature. Higher temperature at demins would result in a possible boration of the RCS.

ANSWER / DISTRACTOR ANALYSIS Wednesday, February 01, 2006 1:59:52 PM 5

QUESTIONS REPORT for Questions Draft NRC Exam A. Correct. As described above.

B. Incorrect. Ltdn temp would increase. Demin would bypass releasing boron.

C. Incorrect. Ltdn temp would increase. Demin would bypass releasing boron.

D. Incorrect. Ltdn temp would increase. Demin would bypass releasing boron.

REFERENCES ARP-1 7007, ALB07 window D03 for LTDN HX OUT HI TEMP ARP-17007, ALB07 window F04 for LTDN HX HI TEMP DEMIN DIVERT VEGP learning obiectives:

LO-PP-09100-02, "Describe how the following systems interact with the Chemical Volume Control System (CVCS):

c. Aux. Closed Cooling Water System

g. Reactor Coolant System" LO-PP-09100-03, State the purpose and describe the control signals, setpoints, and any interlocks for the following:

e. Letdown heat exchanger temperature divert valve, TV-130.

g. Demineralizer divert valve, TV-129".

LO-PP-09100-05, "State how letdown temperature is controlled, relative to the following:

b. Demineralizer performance".

MCS Time: 1 Points: 1.00 Version: 0 12 3 4 5 6 7 8 9 Answer: ADCCBACAAC Scramble Range: A - D Wednesday, February 01, 2006 1:59:52 PM 6

QUESTIONS REPORT for Questions Draft NRC Exam

4. Given the following conditions:

• A Reactor Trip and Safety Injection have occurred due to a small break LOCA in the pressurizer steam space.

• The crew transitioned to 19011-C, "SI Termination" and is preparing to establish normal letdown flow.

• The Reactor Operator points out SI Reinitiation Criteria has been met on the Foldout Page due to loss of subcooling and inability to maintain pressurizer level.

• RCS pressure is 1700 psig and lowering.

While performing Attachment C for Re-establishing CCP Cold Leg Injection the team inadvertently opens the BIT DISCH ISOLATION valves (HV-8801A and B) and fails to shut the CHARGING TO RCS ISOLATION valves (HV-8105 and HV-8106).

• The Reactor Operator points out that CCP discharge pressure is low and oscillating.

Which ONE of the following actions should be taken by the crew ?

A. Isolate the charging line due to the CCP alternate mini flows are lifting, continue in 19011 -C, "SI Termination".

B. Isolate the charging line due to the CCPs possibly operating at runout conditions, transition to 19010-C, "Loss of Reactor or Secondary Coolant".

C. Isolate the charging line due to the CCP alternate mini flows are lifting, transition to 19010-C, "Loss of Reactor or Secondary Coolant".

D. Isolate the charging line due to the CCPs possibly operating at runout conditions, continue in 19011-C, SI Termination".

K/A 009 Small Break LOCA G2.4.7 Emergency Procedures Plan Knowledge of event based EOP mitigation strategies.

K/A MATCH ANALYSIS Question gives a condition during a small break LOCA and a transition to SI Termination, SS has to determine proper actions taken in response to required Foldout Page actions and a valve misalignment.

ANSWER / DISTRACTOR ANALYSIS Wednesday, February 01, 2006 1:59:52 PM 7

QUESTIONS REPORT for Questions Draft NRC Exam A. Incorrect. Foldout page requires transition to 19010-C, "Loss of Reactor or Secondary Coolant if subcooling or pressurizer level cannot be maintained.

Bases of shutting normal charging valves before opening BIT discharge valves is to prevent possible CCP runout. RCS pressure is also below the setpoint for the CCP miniflows to be open.

B. Correct. Foldout page requires transtion to 19010-C, "Loss or Reactor or Secondary Coolant" if subcooling or pressurizer level cannot be maintained.

Bases of shutting normal charging valves before opening BIT discharge valves is to prevent possible CCP runout. RCS pressure is also below the setpoint for the CCP miniflows to be open.

C. Incorrect. See A and B above.

D. Incorrect. See A and B above.

REFERENCES

1. 19011-C, "SI Termination" foldout page and attachment C for realigning CCP flow to the BIT.

2. 13006-1/2, Limitation 2.2.17 for CCP miniflow operation.

3. HL-AW-37000-00-004, HL-13 Audit bank not previously used.

4. ES-I.1, SI Termination step deviation document.

VEGP learninq objectives:

LO-LP-37022-04, "Using EOP 19011-C, briefly describe how each step is accomplished".

LO-LP-37022-05, "State the ECCS reinitiation criteria. Include how the operator would carry out this directive".

LO-LP-37022-08, "Given a scenario requiring use of the foldout page, state the actions that the operator would be required to take".

MCS Time: I Points: 1.00 Version: 0 12 3 4 5 6 7 8 9 Answer: BDACBCDDDC Scramble Range: A - D Wednesday, February 01, 2006 1:59:52 PM 8

QUESTIONS REPORT for Questions Draft NRC Exam

5. The operating crew has energized 1 set of PRZR backup heaters to equalize PRZR and RCS boron concentrations.

Both pressurizer spray valves show dual indication with approximately 5% demand controlling pressurizer pressure approximately 2260 psig.

The RO notes several alarms and reports:

• PORV PV-455A is fully open.

• Pressurizer sprays are now fully closed.

Identify the problem and it's associated corrective action you should direct the RO to take.

A. The PORV cycled open due to the integrating response of the master controller.

Verify the PORV shuts at 2185 psig.

B. The PORV has failed open, manually shut the PORV and / or it's block valve.

C. The PORV cycled open due to the integrating response of the master controller.

Take the pressurizer master controller to 25% demand and verify the PORV closes.

D. The controlling PRZR pressure channel has failed high, manually close the PORV and / or it's block valve.

Wednesday, February 01, 2006 1:59:52 PM 9

QUESTIONS REPORT for Questions Draft NRC Exam K/A 010 Pressurizer Pressure Control System (PZR PCS).

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

PORV failures.

K/A MATCH ANALYSIS Question gives plant conditions with a stuck open PORV and asks why it is open and actions to take to mitigate event.

ANSWER / DISTRACTOR ANALYSIS A. Incorrect. PORV no longer has integrating function and now open only on a fixed PRZR pressure setpoint.

B. Correct. Response correct per AOP-18000-C, Response to Pressurizer Spray, Safety, or Relief Valve Malfunction.

C. Incorrect. Integrating function has been removed from the PORVs.

D. Incorrect. Closing the PORV is correct, but spray valves closed eliminate the possibility of a failed pressure instrument channel.

REFERENCES AOP-1 8000, "Pressurizer Spray, Safety, or Relief Valve Malfunction" Current Events RQ-LP-63177 and 63180 VEGP learning objectives:

V-LO-PP-16303-02 Describe the response of the pressurizer control system to the following failures:

a. controlling channel fails low

b. controlling channel fails high

c. controller high or low failure V-LO-PP-16303-05 State the setpoint, coincidence, and protective actuations with the low pressurizer PORV interlock.

Wednesday, February 01, 2006 1:59:52 PM 10

QUESTIONS REPORT for Questions Draft NRC Exam MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: BCBDBBADCC Scramble Range: A - D Wednesday, February 01, 2006 1:59:52 PM 11

QUESTIONS REPORT for Questions Draft NRC Exam

6. The following sequence of events has occurred:

• Reactor trip from 100% RTP

• All RCPs lose seal injection and ACCW cooling

• Engineering recommends not re-starting the RCPs

• Natural Circulation cooldown started due to possible damage to RCP seals

• Small break LOCA through RCP seals develops

• Red path on Core Cooling occurs due to CETs > 711 degrees F with RVLIS Full Range level < 39%

• Crew implements 19221-C, FR-C.1, "Response to Inadequate Core Cooling"

• Steam generators have been depressurized, with no ECCS flow established

• CETs currently 879 degrees F and slowly rising Which ONE of the following would be CORRECT regarding starting the RCPs while in 19221-C, "Response to Inadequate Core Cooling" ?

A. Due to the previous loss of ACCW and Seal Injection. RCPs should not be started until evaluated by engineering. The TSC will provide direction to start the RCPs.

B. Initiate starting RCPs one at a time regardless of SG levels until CETs begin to lower. Support conditions are desired but not required to start.

C. Do not start RCPs until CETs > 1200 degrees F. and SG levels are > 10% NR for the loops desired to start. Support conditions are desired but not required to start.

D. Initiate starting RCPs one at a time regardless of SG levels until CETs begin to lower. Support conditions are required to start until CETs exceed 1200 degrees.

Wednesday, February 01, 2006 1:59:52 PM 12

QUESTIONS REPORT for Questions Draft NRC Exam K/A 015 Reactor Coolant Pump (RCP) Malfunctions AA2.11 Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions.

When to jog RCPs during ICC.

K/A MATCH ANALYSIS Question gives a scenario requiring RCPs to be stopped due to loss ACCW and Seal Injection. Engineering recommends not starting. Then a LOCA with ICC conditions follows. Candidate has to determine if RCP start would be allowed or not and why.

ANSWER / DISTRACTOR ANALYSIS A. Incorrect. Engineering evaluation can not over rule the Red Path for ICC.

RCPs should be started if proper conditions met.

B. Incorrect. RCPs not sacrificed until CETs > 1200 degrees F by procedure.

C. Correct. RCPs should be started with CETs > 1200 degrees F and adequate SG NR level (10%) in loop desired to start. 10% NR SG level prevents clad creep failure.

D. Incorrect. RCPs should not be sacrificed until CETs > 1200 degrees F by procedure.

REFERENCES 19002-C, "Natural Circulation Cooldown" note prior to step # 1.

19221-C, "Response to Inadequate Core Cooling" step # 2 VEGP learning obiectives:

LO-LP-37061-02, "Using EOP 19221-C as a guide, briefly describe how each step is accomplished".

MCS Time: I Points: 1.00 Version: 0 12 3 4 5 6 7 8 9 Answer: CCBAAAADAB Scramble Range: A - D Wednesday, February 01, 2006 1:59:52 PM 13

QUESTIONS REPORT for Questions Draft NRC Exam

7. You are the SS. Based on the following scenarios, which ONE of the following would require a Technical Specification LCO entry ?

A. Containment pressure relief scheduled for beginning of shift has been delayed.

Tech Spec rounds finds containment pressure has risen to +1.6 psig.

B. Containment coolers are stopped for slave relay testing when the test is delayed.

Tech Spec rounds finds containment air temperature has risen to 122 degrees F.

C. Containment pressure relief is in progress when the BOP is distracted by other activities. Tech Spec rounds finds containment pressure has fallen to -0.22 psig.

D. Containment coolers are all running during extremely cold outside air conditions.

Tech Spec rounds finds containment air temperature has fallen to 88 degress F.

Wednesday, February 01, 2006 1:59:52 PM 14

QUESTIONS REPORT for Questions Draft NRC Exam K/A 022 Containment Cooling.

G2.1.33 Conduct of Operations.

Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

K/A MATCH ANALYSIS Question gives 4 plausible scenarios for containment parameters and candidate must choose the one that requires entry into Technical Specifications.

ANSWER I DISTRACTOR ANALYSIS A. Incorrect. Containment pressure limit is + 1.8 psig.

B. Correct. Containment air temperature limit is 120 degrees F.

C. Incorrect. Containment pressure limit is - 0.3 psig.

D. Incorrect. Containment does not have a low temperature limit.

REFERENCES Technical Specification 3.6.4 "Containment Pressure" Technical Specification 3.6.5 "Containment Air Temperature" VEGP learning objectives:

LO-LP-39210-01, "For any given item in section 3.6 of Tech Specs, be able to:

a. State the LCO MCS Time: 1 Points: 1.00 Version: 0 12 3 4 5 6 7 8 9 Answer: BCBDCADBCA Scramble Range: A - D Wednesday, February 01, 2006 1:59:52 PM 15

QUESTIONS REPORT for Questions Draft NRC Exam

8. Following an RCS Large Break LOCA, containment Hydrogen concentration has been discovered to be 6.8 %.

Which ONE of the following would be CORRECT regarding the containment Hydrogen concentration and the actions you should direct as SS ?

A. 6.8 % is below the flammable concentration threshold. No actions would be necessary at this concentration but periodic monitoring is required.

B. 6.8 % is above the flammable concentration threshold. It would be preferred to place the Post LOCA Containment Hydrogen Purge system in service.

C. 6.8 % is below the flammable concentration threshold. It would be preferred to place the Post LOCA Hydrogen Recombiners in service.

D. 6.8 % is above the flammable concentration threshold. It would be preferred to Dilute the Containment With Service Air.

Wednesday, February 01, 2006 1:59:52 PM 16

QUESTIONS REPORT for Questions Draft NRC Exam K/A 028 Hydrogen Recombiner and Purge Control System.

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

The hydrogen air concentration in excess of limit flame propagation or detonation with resulting equipment damage in containment.

K/A MATCH ANALYSIS Question gives a Hydrogen concentration in containment following a LOCA. Candidate must discriminate whether this is above or below the flammable limit and actions he would direct as SS.

ANSWER / DISTRACTOR ANALYSIS A. Incorrect. Concentration is in the flammable range. We would continue to monitor.

B. Incorrect. In flammable range. However, Post LOCA Hydrogen Purge is a last resort.

C. Incorrect. Concentration is in the flammable range. Hydrogen Recombiners deleted.

D. Correct. In flammable range. Dilution with service air is the method per procedure.

REFERENCES 13130-1/2, "Post Accident Hydrogen Control".

19010-C, "Response to Loss of Reactor or Secondary Coolant" VEGP learning obiectives:

LO-LP-37111-08, "Using EOP-1 9010-C as a guide, briefly describe how each step is accomplished".

LO-PP-29101-03, "List the systems that are designed to control and mitigate hydrogen gas buildup in containment".

MCS Time: 1 Points: 1.00 Version: 0 12 3 4 5 67 8 9 Answer: DACDBDDBAB Scramble Range: A - D Wednesday, February 01, 2006 1:59:52 PM 17

QUESTIONS REPORT for Questions Draft NRC Exam

9. As Shift Supervisor you must ensure a surveillance is performed on the Par Refueling Machine within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to movement of fuel assemblies, RCCAs, thimble plugs, or control rod drive shafts within the reactor vessel.

The Par Refueling Machine has a specific interlock required by the TRM to prevent damage to fuel assemblies and other core components which if found INOPERABLE would require an Immediate Tech Spec action to stop refueling operations.

This interlock would be ?

A. Slack Cable Interlock.

B. Hoist Overload Interlock.

C. Core Boundary Interlock.

D. Machine Off Index Interlock.

Wednesday, February 01, 2006 1:59:52 PM 18

QUESTIONS REPORT for Questions Draft NRC Exam K/A 034 Fuel Handling Equipment.

K6.01 Knowledge of the effect of a loss or malfunction of the following will have on the Fuel Handling System:

Fuel Handling Equipment.

K/A MATCH ANALYSIS Question gives four Par Console interlocks and candidate must choose which one would have Tech Spec / TRM actions of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or less.

ANSWER I DISTRACTOR ANALYSIS A. Incorrect. Slack Cable interlock not in TRM.

B. Correct. Hoist Overload has TRM actions.

C. Incorrect. Core Boundary interlock not in TRM.

D. Incorrect. Machine Off Index interlock not in TRM.

REFERENCES Technical Requirements Manual 13.9.3 - Refueling Machine HL-AW-25000-00-001 from question bank VEGP learning objectives:

LO-LP-39213-03, "For any given item in section 13.9 of the TRM, be able to:

a. State the TR for operaton

b. State any one hour or less required action".

MCS Time: I Points: 1.00 Version: 0 12 3 4 5 6 7 8 9 Answer: BACACACCDB Scramble Range: A - D Wednesday, February 01, 2006 1:59:53 PM 19

QUESTIONS REPORT for Questions Draft NRC Exam

10. You are the Unit SS when the following has occurred:

PORV 455A has developed excessive seat leakage and the appropriate Tech Spec actions were taken. The PORV is capable of being manually cycled if necessary.

PORV 456A & block valve are in their normal alignments and will function as designed.

Subsequently a SGTR has occurred and 19030-C, Steam Generator Tube Rupture" is in progress. 19030-C has directed you to ensure power to the block valves, check PORVs shut, and at least one block valve open. RCS pressure is currently 1860 psig and slowly rising due to injection flow.

Which ONE of the following would be CORRECT regarding the Tech Spec actions previously taken and directions you should give the crew regarding the train "A" PORV and it's block valve ?

A. The block valve should have been closed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with power maintained.

WHEN PRZR pressure > 2185 psig, THEN open block valve.

B. The block valve should have been closed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with power removed.

Restore power to block valve, WHEN PRZR pressure > 2185 psig, do not open block valve.

C. The block valve should have been closed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with power maintained.

WHEN PRZR pressure > 2185 psig, do not open block valve.

D. The block valve should have been closed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with power removed.

Restore power to block valve, WHEN PRZR pressure > 2185 psig, THEN open block valve.

Wednesday, February 01, 2006 1:59:53 PM 20

QUESTIONS REPORT for Questions Draft NRC Exam K/A 038 Steam Generator Tube Rupture EG2.1.11 Conduct of Operations Knowledge of less than one hour technical specification action statements for systems.

K/A MATCH ANALYSIS Question gives a PORV with excessive seat leakage and requires the candidate to know the correct choice of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or less Tech Spec actions from memory. A SGTR develops and the candidate must choose the correct action from 19030-C.

ANSWER i DISTRACTOR ANALYSIS A. Incorrect. Block valve should remain shut to isolate the PORV seat leakage.

B. Incorrect. The block valve should have remained energized per Tech Specs.

C. Correct. Do not open the block valve since Train B PORV & Block still operable.

D. Incorrect. The block valve should have remained energized per Tech Specs.

REFERENCES 19030-C, "Steam Generator Tube Rupture", step 23.

Tech Spec 3.4.11 for PORVs and Block valves.

Tech Spec Bases 3.4.11 for PORVs and Block valves.

VEGP learning objectives:

LO-LP-37311-07, "Using EOP 19030-C as a guide, briefly describe how each step is accomplished".

LO-LP-39208-01, "For any given item in section 3.4 of Tech Specs, be able to:

a. State the LCO

b. State any one hour or less required actions" MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: CAAADCACBC Scramble Range: A - D Wednesday, February 01, 2006 1:59:53 PM 21

QUESTIONS REPORT for Questions Draft NRC Exam

11. You are the Shift Supervisor when:

• An LOSP occurs when RAT 1A and RAT 1B both trip.

• A Reactor Trip and Safety Injection (SI) occurs.

During the load sequencing for SI / LOSP the following occurs:

• DG1A trips

• DG1 B maintains rated speed and voltage while energizing it's associated 1E bus Which ONE of the following would CORRECTLY describe the status of the control board valve indication for the AFW system ?

A. Train A illuminated, Train B illuminated, Train C illuminated.

B. Train A extinguished, Train B illuminated, Train C extinguished.

C. Train A extinguished, Train B illuminated, Train C illuminated.

D. Train A illuminated, Train B illuminated, Train C extinguished.

Wednesday, February 01, 2006 1:59:53 PM 22

QUESTIONS REPORT for Questions Draft NRC Exam K/A 056 Loss of Off-site Power AA2.69 Ability to determine and interpret the following as they apply to the Loss of Offsite Power.

Valve position.

K/A MATCH ANALYSIS Question poses a scenario where an LOSP occurs to both of the RATs with an SI.

Question asks for AFW valve position for all 3 trains following an LOSP.

ANSWER / DISTRACTOR ANALYSIS A. Incorrect. Train A would be de-energized, Train C maintained by CD1 battery.

B. Incorrect. Train A would be de-energized, Train C maintained by CD1 battery.

C. Correct. Train A would be de-energized, Train C maintained by CD1 battery.

D. Incorrect. Train A would be de-energized, Train C maintained by CD1 battery.

REFERENCES V-LO-TX-20101, Auxiliary Feedwater System page # 25 VEGP learning obiectives:

V-LO-PP-20101-09, Determine the impact to AFW system operation and the overall integrated plant operations to the following types of power supply failures:

a. UN condition on either AA02 or BA03 with the bus being re-energized from the EDG while at 100% power.

b. UN condition on either AA02 or BA03 with the bus remaining de-energized while at 100% power.

MCS Time: 1 Points: 1.00 Version: 0 12 3 4 5 6 7 89 Answer: CADDADAB BD Scramble Range: A - D Wednesday, February 01, 2006 1:59:53 PM 23

QUESTIONS REPORT for Questions Draft NRC Exam

12. Unit 1 is in mode 3 when the following occur:

• Trouble alarms are recieved for 1AY1A/ 1AY2A and lAD1

• Indicating lights for the train A MSIVs and the loop 1 1 E RCP breaker are off Which of the following procedures should the SS enter?

A. 18032-C, for loss of 120 VAC vital bus 1AY1A.

B. 18032-C, for loss of 120 VAC vital bus 1AY2A.

C. 18034-C, for loss of 125 VDC 1 E bus 1AD1.

D. 18031--C, for loss of 4160 VAC 1 E bus 1AA02.

K/A 058 Loss of DC Power AA2.02 Ability to determine and interpret the following as they apply to the Loss of DC Power.

125V dc bus voltage, low/critical low, alarm K/A MATCH ANALYSIS Question tests candidates knowledge of actions to take when a bus problem is indicated with Train A 125V DC bus and 120V AC bus AY1A and AY2A.

ANSWER / DISTRACTOR ANALYSIS A. Incorrect. Annunciators are indicative of loss of lAD1 125V DC 1E bus.

B. Incorrect. Annunciators are indicative of loss of lAD1 125V DC 1E bus.

C. Correct. Symptoms for loss of 125V DC bus lAD1.

D. Incorrect. Annunciators are indicative of loss of lAD1 125V DC bus.

REFERENCES AOP-1 8034, Loss of 1E DC Bus VEGP learning objectives:

V-LO-LP-60329-04 Given conditions and/or indications, determine the required AOP to enter (including subsections, as applicable).

Wednesday, February 01, 2006 1:59:53 PM 24

QUESTIONS REPORT for Questions Draft NRC Exam MCS Time: 1 Points: 1.00 Version: 0 1 23456789 Answer: CACDDACBDD Scramble Range: A - D Wednesday, February 01, 2006 1:59:53 PM 25

QUESTIONS REPORT for Questions Draft NRC Exam

13. You are the Shift Supervisor when:

A trip of a running Train A NSCW pump with failure of the standby pump to auto start has resulted in entrance of 18021-C, "Loss of Nuclear Service Cooling Water".

Attempts to manually start the standby pump were not successful and Train A NSCW was eventually shutdown.

Due to CCP "B" repairs in progress, a Tech Spec shutdown is required within the next 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

You desire "Emergency Maintenance" work authorization to attempt to restore Train A NSCW to operable status.

Which ONE of the following is CORRECT regarding if "Emergency Maintenance" is required and who makes this determination ?

A. Conditions justify Emergency Maintenance. Shift Supervisor determines.

B. Conditions do not justify Emergency Maintenance. Shift Manager determines.

C. Conditions justify Emergency Maintenance. Shift Manager determines.

D. Conditions do not justify Emergency Maintenance. Shift Supervisor determines.

Wednesday, February 01, 2006 1:59:53 PM 26

QUESTIONS REPORT for Questions Draft NRC Exam K/A 062 Loss Nuclear Service Water EG2.2.19 Equipment Control Knowledge of Maintenance work order requirements.

K/A MATCH ANALYSIS Question gives situation where NSCW has placed plant in motherhood and requires shutdown within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. Asks what conditions emergency maintenance could be authorized and who can authorize.

ANSWER / DISTRACTOR ANALYSIS A. Incorrect. Tech Spec shutdown within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> allows, SM authorization required.

B. Incorrect. Tech Spec shutdown within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> allows, SM authorization required.

C. Correct. Tech Spec shutdown within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> allows, SM authorization required.

D. Incorrect. Tech Spec shutdown within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> allows, SM authorization required.

REFERENCES 00350-C, "Maintenance Work Program". Definition 2.8 for "Emergency Maintenance" and step 3.11.1.1 for who determines if work is Emergency Maintenance.

VEGP learning obiectives:

LO-LP-63350-04, "Describe the requirements for emergency maintenance and when emergency maintenance can be performed".

MCS Time: I Points: 1.00 Version: 0 12 3 4 5 6 7 8 9 Answer: CBCDDADCDD Scramble Range: A - D Wednesday, February 01, 2006 1:59:53 PM 27

QUESTIONS REPORT for Questions Draft NRC Exam

14. With the unit at 100% power a loss of 4.16 kV bus 2BA03 occurs. EDG-2B starts and re-energizes 2BA03. Automatic load sequencing is in progress when the following occur:

• ALB38, Window C04 "DG2B HIGH TEMP JACKET WATER OUT" alarms

• The BOP reports only NSCW pump # 6 has auto started Which ONE of the following is a CORRECT action(s) for the SS to direct ?

A. Emergency trip DG2B which should have automatically tripped, enter section A of AOP 18031-C, "Loss of Class 1 E Electrical Systems With DG Failure To Tie".

B. Emergency trip DG2B if a second NSCW pump cannot be started, enter section A of AOP 18031-C, "Loss of Class 1E Electrical Systems With DG Failure To Tie".

C. Enter section B of AOP 18031-C, "Loss of Class 1E Electrical Systems With DG Tying", enter section A of 18031-C if DG2B trips on high jacket water temperature.

D. Enter section B of AOP-18031-C, "Loss of Class 1E Electrical Systems With DG Tying", align NSCW for single pump operation to provide cooling to DG2B.

Wednesday, February 01, 2006 1:59:53 PM 28

QUESTIONS REPORT for Questions Draft NRC Exam K/A 064 Emergency Diesel Generator (ED/G) System.

G2.4.4 Emergency Procedures / Plan Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

K/A MATCH ANALYSIS This question test the knowledge of AOP entry conditions for malfunctions with the emergency diesel generators.

ANSWER / DISTRACTOR ANALYSIS A. Incorrect - Plausible since this is the section of AOP you would enter. However, DG will not auto trip on high JW during Emergency starts.

B. Correct - step B3a RNO of 18031-C, directs the crew to start 2 NSCW pumps on the affected train. If 2 NSCW pumps cannot be started, then emergency trip the DG and go to section A. Step 1 RNO of 18021 "Loss of NSCW also directs to trip DG if 2 NSCW pumps can't be started.

C. Incorrect - Plausible since 18031-C section B would be entered if DG left running, however DG will not auto trip on high JW temperature.

D. Incorrect - Plausible since there is direction for single pump operations for NSCW, but only if both NSCW trains not available or in lower modes of operation.

REFERENCES

1. AOP 18031-C, "Loss of Class 1 E Electrical Systems"

2. AOP 18021-C, "Loss of Nuclear Service Cooling Water" VEGP learning obiectives:

LO-LP-60323-04, "Given conditions and/or indications, determine the required AOP to enter (including subsections, as applicable).

MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: BACADBDCBA Scramble Range: A - D Wednesday, February 01, 2006 1:59:53 PM 29

QUESTIONS REPORT for Questions Draft NRC Exam

15. You are the SS when:

A plant event has resulted in the crew entering 19221-C, FR-C.1 "Response to Inadequate Core Cooling".

CCP "A" was tagged out and CCP "B" unexpectedly tripped during the event. Neither pump will be available in the near future. You are at step 2 of procedure 19221-C and have just checked the CCP flow indicators for BIT flow which shows none.

Which ONE of the following CORRECTLY describes the next sequence of actions you expect to have the crew perform to mitigate the event ?

A. Reset Safety Injection and start the NCP.

Check for SI flow and start SI Pumps and align valves if necessary.

Check for RHR flow and start RHR pumps and align valves if necessary.

B. Rapidly depressurize the Steam Generators to depressurize the RCS.

Check for SI flow and start SI pumps and align valves if necessary.

Check for RHR flow and start RHR pumps and align valves if necessary.

C. Check for SI flow and start SI pumps and align valves if necessary.

Rapidly depressurize the Steam Generators to depressurize the RCS.

Check for RHR flow and start RHR pumps and align valves if necessary.

D. Rapidly depressurize the Steam Generators to depressurize the RCS.

Start all RCPs one at a time and open all RCS vent paths to containment.

Isolate the SI accumulators.

Wednesday, February 01, 2006 1:59:53 PM 30

QUESTIONS REPORT for Questions Draft NRC Exam K/A 074 Inadequate Core Cooling EG2.4.6 Emergency Procedures / Plan Knowledge of symptom based EOP mitigation strategies.

K/A MATCH ANALYSIS Question gives scenario in 19221-C, "FR-C.1 "Response to Inadequate Core Cooling" and candidate must determine proper response with symptoms / conditions given.

ANSWER / DISTRACTOR ANALYSIS A. Correct. Reset SI and start NCP and other ECCS pumps is the first major action of this EOP.

B. Incorrect. Starting ECCS pumps is the first major action and should be performed prior to rapid depressurization.

C. Incorrect. Starting ECCS pumps is the first major action and should be performed prior to rapid depressuriztion.

D. Incorrect. Starting ECCS pumps is the first major action and should be performed ahead of all the actions listed in this choice.

REFERENCES 19221-C, FR-C.1 "Response to Inadequate Core Cooling", step # 2 VEGP learning objectives:

LO-LP-37061-02, "Using EOP 19221-C as a guide, briefly describe how each step is performed".

MCS Time: 1 Points: 1.00 Version: 0 1 234567 89 Answer: ADCBCDBBBC Scramble Range: A - D Wednesday, February 01, 2006 1:59:53 PM 31

QUESTIONS REPORT for Questions Draft NRC Exam

16. Given the following:

A tour group with 9 individuals from Nustart Energy has arrived for a tour of Plant Vogtle. One of the group members is the minor daughter of another utiliities CEO.

Which ONE of the following would be CORRECT regarding Visitor Access to the Protected Area and/or Personnel Escort Duties and Responsibilities ?

A. The Shift Manager or Shift Supervisor would have to authorize visitor access for the minor.

B. Visitor authorization expires at the end of shift or completion of visit, whichever occurs first. No visitor authorization shall exceed a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period.

C. A female tour group member needs to use a restroom which has only one door.

A male escort would need to transfer escort responsibility to a female escort.

D. One escort would be required for this group as long as a vital area is not entered.

To enter a vital area would require an additional escort.

K/A G2.1.13 Knowledge of facility requirements for controlling vital / controlled areas.

K/A MATCH ANALYSIS Question gives scenarios regarding allowing access of visitors inside the protected or vital areas. Candidate must pick out the correct choice that would be allowed.

ANSWER / DISTRACTOR ANALYSIS A. Incorrect. Minors need to be authorized by General Manager or AGMs.

B. Incorrect. Expires at midnight or completion with a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time limit.

C. Incorrect. With only one door change of escort not required.

D. Correct. Would need another escort if entering the vital area since limit is 5 persons.

REFERENCES 00652-C, "Personnel Escort - Duties and Responsibilities" 00653-C, "Protected Area Entry/Exit Control" VEGP learning objectives:

None - GET handbook.

Wednesday, February 01, 2006 1:59:53 PM 32

QUESTIONS REPORT for Questions Draft NRC Exam MCS Time: I Points: 1.00 Version: 0 1 23456789 Answer: DACDBDDBAB Scramble Range: A - D Wednesday, February 01, 2006 1:59:53 PM 33

QUESTIONS REPORT for Questions Draft NRC Exam

17. Given the following plant conditions:

• Unit 2 at 100% power for the past three weeks.

• Chemistry has just provided the following results from RCS chemistry samples that were taken within the last hour.

- RCS Fluroide = 0.15 ppm

- RCS Chloride = 0.15 ppm

- RCS Oxygen = 0.15 ppm Which ONE of the following describes the above conditions and appropriate actions to be taken by the SS ?

A. Chloride concentration is above the TRM limit. Corrective action must be taken to bring Chloride concentration within limits. The plant must be taken to Cold Shutdown if outside of limits after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B. Oxgen concentration is above the TRM limit. Corrective action must be taken immediately to bring the plant to Cold Shutdown conditions.

C. Chloride concentration is above the TRM limit. Corrective action must be taken immediately to bring the plant to Cold Shutdown conditions.

D. Oxygen concentration is above the TRM limit. Corrective action must be taken to bring Oxygen concentration within limits. The plant must be taken to Cold Shutdown if outside of limits after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Wednesday, February 01, 2006 1:59:53 PM 34

QUESTIONS REPORT for Questions Draft NRC Exam K/A G2.1.34 Ability to maintain primary and secondary plant chemistry within allowable limits.

K/A MATCH ANALYSIS Question tests the correct knowledge of TRM actions for RCS chlorides, flourides, and dissolved oxygen being out of limits.

ANSWER I DISTRACTOR ANALYSIS A. Incorrect. RCS Chloride is within limits.

B. Incorrect. Plant does not immediately need to be taken to cold shutdown per TRM.

C. Incorrect. RCS Chloride is within limits.

D. Correct. TRM action is to immediately try to restore and go to cold shutdown if not in limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

REFERENCES

1. Surry 2004 NRC Exam question # 88

2. TRM 13.4.1 for RCS Chemistry VEGP learning objectives:

LO-LP-39208-03, "For any given item in section 13.4 of the TRM:

a. State the TR for operaton"

b. State any one hour or less actions.

LO-LP-39208-01, "Given the TRM, determine for a specific set of plant condition, equipment availability, and operational mode:

a. Whether any TR of section 13.4 has been exceeded.

b. The required actions for all sections of 13.4 TRs.

MCS Time: 1 Points: 1.00 Version: 0 12 3 4 5 6 7 8 9 Answer: DCACCAADBD Scramble Range: A - D Wednesday, February 01, 2006 1:59:53 PM 35

QUESTIONS REPORT for Questions Draft NRC Exam

18. Given the following:

• A TCP has been written for the IST surveillance procedure for CCP "A" to test whether the discharge MOV will stroke against full pump dP and to collect MOV and pump motor data during the surveillance.

• The plant conditions required for the evolution are NOT described in current procedures or the Final Safety Analysis Report.

• The author of the TCP is the responsible system engineer who has brought the TCP to the Shift Manager for review and approval.

the Shift Manager should ........

A. review and approve the TCP for 14 days as long as the engineering manager has reviewed and approved the TCP.

B. disapprove the TCP. A 50.59 screening / evaluation would need to be performed.

A special test procedure approved by the PRB and General Manager is required.

C. review and approve the TCP for 14 days as long as the responsible supevisor has reviewed and approved the TCP.

D. disapprove the TCP. A 50.59 screening / evaluation is not required. A special test procedure approved by the PRB and General Manager is required for this test.

Wednesday, February 01, 2006 1:59:53 PM 36

QUESTIONS REPORT for Questions Draft NRC Exam K/A G2.2.10 Knowledge of the process for determining if the margin of safety, as defined in the basis of any technical specification is reduced by a proposed change, test or experiment.

K/A MATCH ANALYSIS Question gives a condition where system engineer has written a temporary change to a CCP IST procedure to determine if the discharge valve will stroke against full pump dP.

Condition is not described in FSAR or Tech Spec Bases. Candidate must choose whether or not to allow procedure to be performed.

ANSWER / DISTRACTOR ANALYSIS A. Incorrect. A 50.59 evaluation is required and requires higher approval.

B. Correct.

C. Incorrect. A 50.59 evaluation is required and requires higher approval.

D. Incorrect. A 50.59 evaluation is required and requires higher approval.

REFERENCES Prairie Island 2004 NRC Exam SRO Question # 21 00052-C, "Temporary Changes to Procedures" 00056-C, "10CFR50.59 Screening and Evaluations" 00053-C, "Temporary Procedures and Special Tests" VEGP learning objectives:

LO-LP-63052-02, "In application of temporary changes to procedures, describe the following:

a. Review/approval responsiblity

b. Time period a TCP is valid and processing of expired of disapproved TCPs.

c. Interim approval process.

MCS Time: I Points: 1.00 Version: 0 12 3 4 5 6 7 8 9 Answer: BCABDDDCAD Scramble Range: A - D Wednesday, February 01, 2006 1:59:53 PM 37

QUESTIONS REPORT for Questions Draft NRC Exam

19. Given the following conditions to perform work at the Radwaste Processing Facility:

• Radiation level at the work site is 80 mrem/hr.

• Radiation level with shielding would be 20 mrem/hr.

• Time for one worker to install and remove shielding is 30 minutes.

• Time to perform the work with one person is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

• Time to perform the work with two persons is 40 minutes.

Assume the following:

• A dose rate of 80 mrem/hr will be received installing and removing the shielding.

• Shielding is to be installed and removed by one worker only.

Which ONE of the following would result in the lowest whole body dose ?

A. one worker with shielding.

B. one worker without shielding.

C. two workers with shielding.

D. two workers without shielding.

Wednesday, February 01, 2006 1:59:53 PM 38

QUESTIONS REPORT for Questions Draft NRC Exam K/A G2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel radiation exposure.

K/A MATCH ANALYSIS Question gives a plausible scenario where the candidate must evaluate which method would achieve ALARA to perform a job. Has to calculate whether or not installing shielding and whether one worker or two could do the job with the least dose.

ANSWER / DISTRACTOR ANALYSIS A. Incorrect. 40 mr to install + (20 mr X 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> = 40 mr) = 80 mr total B. Incorrect. 0 mr to install + (80 mr X 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> = 160 mr) = 160 mr total C. Correct. 40 mr to install + (13.33 mr each to work = 26.66 mr ) = 66.67 mr total D. Incorrect. 0 mr to install + (53.33 mr each to work - 106.66 mr) = 106.66 mr total REFERENCES Turkey Point December 2003 NRC Exam Question # 83 VEGP learning objectives:

None - ALARA per GET.

MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: CADADDBADC Scramble Range: A-D Wednesday, February 01, 2006 1:59:53 PM 39

QUESTIONS REPORT for Questions Draft NRC Exam

20. Given the following:

• The plant is near full power at EOL preparing for unit shutdown for outage in 1 week.

• A Unit 2 liquid waste permit has been issued for Waste Monitor Tank # 9.

• The source check on Liquid Proceesing System Effluent Monitor 2-RE-001 8 has failed.

• The radiation monitor will not come off of the low end of scale.

• The Shift Supervisor has declared 2-RE-001 8 Inoperable.

Which ONE of the following statements is CORRECT regarding approving the permit for the release of Waste Monitor Tank # 9 ?

A. Approve. As long as independent samples of tank contents are analyzed and the discharge valve alignment and release rate calculations are independently verified.

B. Disapprove. The release CANNOT proceed until 2-RE-001 8 has been returned to Operable status in accordance with ODCM requirements.

C. Approve. As long as 1-RE-0018 remains Operable tank contents shall be routed through the opposite units radiation monitor.

D. Disapprove. The release CANNOT proceed because the discharge flow path cannot be aligned with 2-RE-001 8 failed offscale low.

Wednesday, February 01, 2006 1:59:53 PM 40

QUESTIONS REPORT for Questions Draft NRC Exam K/A G2.3.6 Knowledge of the requirements for reviewing and approving release permits.

K/A MATCH ANALYSIS Question gives conditions for a waste monitor tank release with RE-0018 inoperable and candidate will have to determine correct choices to approve the release.

ANSWER / DISTRACTOR ANALYSIS A. Correct. ODCM action 37 allows with independent samples, discharge path IV, and release rate calculation IV.

B. Incorrect. Release could occure per ODCM Table 1 for Liquid Radwaste.

C. Incorrect. No provisions in SOP for cross unit release operations.

D. Incorrect. Valves could be aligned for Waste Montitor Release since interlock to shut valve is rad monitor failing high.

REFERENCES

1. 13216-1, "Liquid releases"

2. ODCM Section 2.1, Table 2.1 section 1 for LIQUID RADWASTE TREATMENT SYSTEM.

3. Arkansas Nuclear One 2005 NRC Exam question # 98 VEGP learning objectives:

LO-PP-47101-10, "State the ODCM, TR, applicabilities, and any one hour or less actions required for the Liquid Waste Processing System."

MCS Time: I Points: 1.00 Version: 0 12 3 4 5 6 7 8 9 Answer: ABDBADACDD Scramble Range: A - D Wednesday, February 01, 2006 1:59:53 PM 41

QUESTIONS REPORT for Questions Draft NRC Exam

21. Given the following conditions:

The plant is operating at 100% power.

• DG "A" is tagged out for an AOT and will not be returned to service for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• A sudden thunderstorm sweeps through the area causing a Loss of Offsite Power to both RATs.

• The Reactor has tripped, the crew has entered E-0, "Reactor Trip or Safety Injection"

• An SI has actuated due to a stuck open PRZR safety valve.

• After exiting E-0 the crew has transitioned to 19010-C, "Response to Primary or Secondary Loss of Coolant"

• A valid red path CSFST for Heat Sink has been identified and 19231-C is identified as the required procedure per the decision tree.

Subsequently, DG "B" output breaker trips due to a bus fault.

Which ONE of the following actions should you take as the SS ?

A. Transition to 19231-C and remain there until exit criteria are met or a higher priority red path procedure is identified.

B. Transition to 19100-C, Loss of All AC Power and remain there until power restored.

Then immediately transiton to 19231-C.

C. Transition to 19231-C and remain there unless RCS pressure is lower than steam generator pressure which would require a return to 19010-C.

D. Transition to 19100-C, Loss of All AC Power and remain there until power restored.

Transition to 19231-C only when FRP implementation is procedurally directed.

Wednesday, February 01, 2006 1:59:53 PM 42

QUESTIONS REPORT for Questions Draft NRC Exam K/A G2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures..

K/A MATCH ANALYSIS Question gives plant conditions which would result in a Loss of All AC power and candidate has to determine appropriate procedure implementation.

ANSWER / DISTRACTOR ANALYSIS A. Incorrect. Loss of All AC Power procedure would be implemented.

B. Incorrect. Loss of All AC is correct procedure. However, you remain in this series of procedures until directed to implement the FRPs C. Incorrect. Loss of All AC Power procedure would be implemented.

D. Correct. Loss of All AC Power is correct procedure and a transition to FR-H.1 not made until procedures direct FRP implementation again.

REFERENCES 19231-C, FR-H.1 "Loss of Secondary Heat Sink" 19100-C, ECA-0.0, "Loss of All AC Power" 19102-C, ECA-0.2, "Loss of All AC Power SI Recovery Required" Beaver Valley 2004 NRC Exam Question # 100 VEGP learning objectives:

LO-LP-37031-07, "State the bases for "Loss of All AC Power" procedure".

LO-LP-37031-08, "Using EOP 19100-C as a guide, describe how each step is accomplished."

MCS Time: 1 Points: 1.00 Version: 0 12 3 4 5 6 7 8 9 Answer: DACDBDDBAB Scramble Range: A - D Wednesday, February 01, 2006 1:59:54 PM 43

QUESTIONS REPORT for Questions Draft NRC Exam

22. The unit has had a transient compounded by AFW equipment inoperabilties which has led to a red path on the Heat Sink CSFST.

Which one of the following choices correctly describes a loss of heat sink (LOHS) and the recovery strategy used?

A. An LOHS occurs when all SG NR levels are < 10% and total FW flow is < 570 gpm.

The recovery methods are to use a high pressure feed source to a SG if available, if not a SG is depressurized below the discharge pressure of condensate pumps to establish feed flow. RCS bleed and feed is used when the SGs dry out to provide temporary core cooling.

B. An LOHS occurs when AFW flow is < 570 gpm and RCS pressure is > intact SG pressures. RCS bleed and feed is immediately established to provide a long term method of core cooling while the crew attempts to feed a selected SG from any available source of water.

C. An LOHS occurs when all SG NR levels are < 10% and total FW flow is < 570 gpm.

RCS bleed and feed is immediately established to provide a temporary method of core cooling while the crew attempts to feed a selected SG from any available source of water.

D. An LOHS occurs when AFW flow is < 570 gpm and RCS pressure is < intact SG pressures. The recovery methods are to use a high pressure feed source to a SG if available, if not a SG is depressurzed below the discharge pressure of condensate pumps to establish feed flow. RCS bleed and feed is used when the SGs dry out to provide temporary core cooling.

Wednesday, February 01, 2006 1:59:54 PM 44

QUESTIONS REPORT for Questions Draft NRC Exam K/A G2.4.6 Knowledge of symptom based EOP mitigation strategies.

K/A MATCH ANALYSIS Question directly tied to the K/A.

ANSWER / DISTRACTOR ANALYSIS A. Correct.

B. Incorrect. Plausible since RCS pressure check > intact SG pressure is performing in the FRP to see if FRP implementation is required. Also RCS bleed & feed is likely to be estalblished but it is not an immediate action.

C. Incorrect. Plausible since the paramters stated are correct for a loss of heat sink.

RCS bleed & feed is most likely established as a temporary source of core cooling but it is not an immediate action.

D. Incorrect. Plausible the recovery methods listed are correct. The heat sink is correct except for the RCS pressure check which is done in the body of the FRP and is not a part of the heat sink CSFST.

REFERENCES

1. 19200-C, Critical Safety Function Status Trees

2. 19231-C, FR-H.1, Response to Loss of Secondary Heat Sink VEGP learning obiectives:

LO-LP-37051-07, "State the intent of 19231-C, "Response to Loss of Secondary Heat Sink".

MCS Time: 1 Points: 1.00 Version: 0 12 3 4 5 6 7 8 9 Answer: ABDBDDCBBD Scramble Range: A - D Wednesday, February 01, 2006 1:59:54 PM 45

QUESTIONS REPORT for Questions Draft NRC Exam

23. Following a plant event requiring the crew to enter the EOPs. The SS has implemented 19005-C, "Rediagnosis".

Which ONE of the following could operators have been performing that would allow the use of Rediagnosis ?

A. 19010-C, "Response to RCS LOCA" in effect. A Loss of Offsite Power (LOSP) occurs and the Train "A" DG re-energizes AA02.

B. 19000-C, "Reactor Trip or Safety Injection" in effect. The SS has reached the steps for transition diagnostics and is not sure which procedure to implement.

C. 19231-C, "Loss of Secondary Heat Sink" in effect. The OAO operator successfully resets the Trip and Throttle valve re-establishing AFW flow.

D. 19002-C, "Natural Circulation Cooldown" is in effect. An RCP has just been started and the SS is not sure which procedure to implement.

K/A WE01 Rediagnosis EA2.2 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

K/A MATCH ANALYSIS Question gives several different scenarios which do not allow use of Rediagnosis.

Candidate has to pick the condition which would allow use of 19005-C.

ANSWER / DISTRACTOR ANALYSIS A. Correct. Rediagnosis may be entered from 19010-C.

B. Incorrect. E-0 must be completed and a transtition made to allow use of Rediagnosis.

C. Incorrect. Rediagnosis cannot be entered from a Red Path.

D. Incorrect. ECCS must be in service or required to allow use of Rediagnosis.

REFERENCES 19005-C, "Rediagnosis", step # 1.

VEGP learning obiectives:

LO-LP-37002-12, State the intent and entry conditions for EOP 19005-C, Rediagnosis.

Wednesday, February 01, 2006 1:59:54 PM 46

QUESTIONS REPORT for Questions Draft NRC Exam MCS Time: 1 Points: 1.00 Version: 0 123456789 Answer: ABAAADCBAC Scramble Range: A - D Wednesday, February 01, 2006 1:59:54 PM 47

QUESTIONS REPORT for Questions Draft NRC Exam

24. The crew is implementing EOP 19012-C, "ES-1.2 Post-LOCA Cooldown and Depressurization", in response to the following sequence of events:

• Unit at 100% RTP

• RCS cold leg temps 557 degrees F

• Reactor trip and SI due to small break LOCA

• RCS cold leg temperatures stabilize at 511 degrees F.

• Both trains of ECCS are in service

• 15 minutes have elapsed since the reactor trip The crew is cooling down and depressuring the RCS in accordance with 19012-C.

Which of the following describes the proper implementation of RCS cooldown?

A. The instantaneous cooldown rate of the RCS cold legs is limited to 100 deg F / hour to comply with technical specifications requirements.

B. The cooldown of the RCS cold legs is limited to 100 deg F over the next 60 minutes once cooldown is initiated per 19012-C.

C. The cooldown of the RCS cold legs is limited to 54 deg F over the next 45 minutes to comply with technical specification requirements.

D. The cooldown of the RCS cold legs is limited to 100 deg F / hour instantaneous rate or 54 deg F over the next 45 minutes, which ever is more limiting.

Wednesday, February 01, 2006 1:59:54 PM 48

QUESTIONS REPORT for Questions Draft NRC Exam K/A WE03 LOCA Cooldown - Depressurization.

EA2.2 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

K/A MATCH ANALYSIS Question deals with RCS cooldown as directed in the Post LOCA Cooldown EOP ES-1.2. The limit on the cooldown rate is to comply with technical specification requirements.

ANSWER / DISTRACTOR ANALYSIS A. Incorrect. You may exceed the instanteous rate. Many operators use this parameter as the goal of their cooldown but it is not the actual limit.

B. Incorrect. Plausible since the operator may think the cooldown rate limit only applies from the begining of the EOP ES-1.2. This is incorrect in this case because the tech limits always apply.

C. Correct. The operator must account for the previous 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> history of RCS cold leg temperatures to determine the allowable cooldown.

D. Incorrect. Plausible, since many operators conservatively apply the most limiting of these two related parameters.

REFERENCES

1. 19012-C, "ES-1.2 Post-LOCA Cooldown and Depressurization" step 13b, page 8.

2. VEGP LCO 3.4.3, RCS Pressure and Temperature Limits

3. WOG ERG background document, ES-12.doc, page 98

4. Operations Instructor Handbook page 28.

VEGP learning obiectives:

LO-LP-37112-01, "USing EOP 19012-C as a guide, describe how each step is accomplished".

MCS Time: 1 Points: 1.00 Version: 0 12 3 4 5 6 7 8 9 Answer: CBBCBCDDCA Scramble Range: A - D Wednesday, February 01, 2006 1:59:54 PM 49

QUESTIONS REPORT for Questions Draft NRC Exam

25. The crew is responding to a red path on the Integrity CSFST using 19241-C, "Response to Pressurized Thermal Shock". All of the following were performed:

• A temperature soak was required.

• The RCS was not cooled down for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

• RCS pressure was not raised for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Once the temperature soak was completed.

• RCS cooldown rate established in cold legs < 50 degrees F in 60 minutes period.

• RCS pressure is being maintained within the requirements of the POST SOAK COOLDOWN LIMIT CURVE.

The actions taken in 19241-C are based on ..........

A. minimizing tensile stresses in the reactor vessel upper head to reduce the likelihood of plastic deformation.

B. minimizing the compressive stresses in the reactor vessel hot leg nozzles to reduce the likelihood of rapid propagation of an existing flaw.

C. minimizing tensile stresses in the reactor vessel downcomer beltline area to reduce the likelihood of rapid propagation of an existing flaw.

D. minimizing compressive stresses in the reactor vessel cold leg nozzles to reduce the likelihood of plastic deformation.

Wednesday, February 01, 2006 1:59:54 PM 50

QUESTIONS REPORT for Questions Draft NRC Exam K/A WE08 RCS Overcooling - PTS.

EG2.2.25. Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

K/A MATCH ANALYSIS Question tests the knowledges contained in the tech spec bases for LCO on RCS pressure temperature limits applied to use in a PTS condition.

ANSWER / DISTRACTOR ANALYSIS A. Incorrect. Plausible since your are minimize tensile stresses but the upper head is not the most limiting component and you must know the difference between plastic and brittle deformation.

B. Incorrect. Plausible since rapid propagation is correct, you must know that the most limiting stress is tensile versus compressive.

C. Correct.

D. Incorrect. Plausible because you must know the limiting component, type of failure of concern and the type of stresses that are more limiting.

REFERENCES

1. LCO bases 3.4.3 pages 1 & 2.

2. 19241-C, "Response to Pressurized Thermal Shock (PTS), pages 22, 28, and 29.

VEGP learning objectives:

LO-LP-39208-04, "Describe the bases for any given Tech Spec in section 3.4" MCS Time: I Points: 1.00 Version: 0 12 3 4 5 6 7 8 9 Answer: CDAABDABCA Scramble Range: A - D Wednesday, February 01, 2006 1:59:54 PM 51