ML073040388

Ro/Sro Initial Written Examination

ML073040388
Person / Time
Site:	Monticello
Issue date:	10/31/2007
From:	Operations Branch III
To:	Nuclear Management Co
References
50-263/07-302
Download: ML073040388 (20)

Text

U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: October 3, 2007 Facility/Unit: Monticello Plant Region: I II III IV Reactor Type: W CE BW GE Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicant=s Signature Results RO/SRO-Only/Total Examination Values n/a / 25 / 25 Points Applicant=s Scores / / Points Applicant=s Grade / / Percent

SENIOR REACTOR OPERATOR Page 1 of 15 Question 1 Which of the following procedures would require a 10CFR50.59 screening if it were significantly revised?

a. D.2-05.E.1 (RAISING A FUEL ASSEMBLY)

b. 4211-PM (CORE SPRAY PUMP MOTOR 11)

c. A.2-101 (CLASSIFICATION OF EMERGENCIES)

d. C.4-C (SHUTDOWN OUTSIDE CONTROL ROOM)

Question 2 The plant is operating at rated conditions with 11Core Spray pump isolated for maintenance. A Station Blackout occurs concurrent with a LOCA. Plant conditions are as follows:

• RPV pressure is 300 psig and lowering 10 psig/minute

• RPV water level is - 80 inches and lowering 5 inches/minute

• Drywell pressure is 9 psig and rising 0.2 psig/minute

• Drywell temperature is 260ºF and rising 1ºF/minute Ten minutes later 15 Bus is reenergized from #11 EDG. Which of the following should be directed FIRST?

a. C.5-3502, (CONTAINMENT SPRAY).

b. C.4-H, (RESTORATION OF PLANT LOADS)

c. C.5-3503, (DEFEAT DRYWELL COOLER TRIPS).

B.09.07-05.E.7, (TRANSFER OF LPCI SWING BUS FROM ALTERNATE TO NORMAL SOURCE).

SENIOR REACTOR OPERATOR Page 2 of 15 Question 3 The plant was operating at rated conditions when an inadvertent Group I Isolation occurred.

While taking actions for the scram the crew notices all suppression chamber to drywell vacuum breakers are cycling open when a SRV opens. The following conditions are now present:

• Torus spray is OFF

• Torus pressure is 6 psig

• Drywell cooling fans are OFF

• Drywell temperature is 250°F For the given conditions, can you direct the initiation of Drywell Sprays from the temperature leg of C.5-1200? Why or why not?

a. No, torus sprays must be placed in service prior to initiation of drywell sprays

b. No, under current plant conditions drywell pressure is less than torus pressure.

c. No, both recirc pumps are running and must be tripped prior to initiating drywell sprays.

d. Yes, drywell temperature is approaching 281ºF and all conditions are met to initiate sprays.

Question 4 An event has occurred that has resulted in the Reactor Vessel Safety Pressure Limit being exceeded. A Site Area Emergency has been declared. It has been determined that an operator is required to enter the reactor building and manipulate a number of valves to protect valuable property.

As Emergency Director, which of the following is the Emergency Plan exposure limit that you can authorize for this activity?

a. 5 REM

b. 10 REM

c. 15 REM

d. 25 REM

SENIOR REACTOR OPERATOR Page 3 of 15 Question 5 Which of the following conditions would NOT ensure Adequate Core Cooling?

Reactor Blowdown RPV Water RPV Pressure Power in-progress Level

a. 18% NO - 145 820 psig

b. 11% YES - 161 306 psig

c. 2% YES - 155 128 psig

d. 0% YES - 138 70 psig Question 6 The plant was operating at 95% power when a 2R Lockout resulted in an ATWS event. Ten minutes following the event the following conditions exist:

• Bus 15 is locked out, all other buses are energized from 1R

• Reactor power is 15% and slowly lowering

• SBLC is injecting, tank level is 1300 gallons and lowering

• RPV water level is -80 inches and difficult to control

• H SRV remains full open and G SRV is cycling open and closed As the CRS, which of the following must be directed to the Balance of Plant operator?

a. Allow LO-LO SET to remain cycling

b. Stabilize RPV pressure 800-1000 psig using SRVs

c. Open additional SRVs to lower RPV pressure to 930 psig

d. Stabilize RPV pressure below 1056 psig using main turbine bypass valves

SENIOR REACTOR OPERATOR Page 4 of 15 Question 7 The plant was operating at rated conditions when control room receives a report of a fire in the Heating Boiler Room. Given the following timeline:

00:00:00 Fire reported to control room 00:08:00 Fire Brigade began attacking the fire 00:16:00 Control Room notified the fire is extinguished Determine if Emergency Plan classification is required and, if so, who would fulfill the responsibilities of the Shift Emergency Communicator (SEC)?

Emergency Plan classification

a. is NOT required

b. Is required, Shift Security Supervisor

c. Is required, Shift Chemistry Technician

d. Is required, Shift Radiation Protection Technician Question 8 A plant startup is being performed with a rod withdrawal currently in progress. The OATC completes withdrawal of the selected control rod and the following occurs:

00:00:00 IRMs indicate 10 on Range 3 00:00:08 Reactor power has doubled 00:00:10 The OATC inserts the selected control rod 00:00:13 The OATC completes insertion of the selected control rod 00:00:42 Reactor power has doubled again As the CRS, you are required to direct the OATC to insert control rods

a. and establish a 60-100 second period IAW C.1 (Reactor Startup).

b. to bring the reactor subcritical until the Nuclear Engineer completes an evaluation and notify personnel IAW 4AWI-04.08.01 (Event Notifications).

c. to bring the reactor subcritical until the Nuclear Engineer completes an evaluation, then reestablish a 60-100 second period IAW C.1 (Reactor Startup).

d. to bring the reactor subcritical until the Nuclear Engineer completes an evaluation, then with permission from the Operations Manager continue the startup IAW C.1 (Reactor Startup). .

SENIOR REACTOR OPERATOR Page 5 of 15 Question 9 An event has occurred that has resulted in the following conditions:

• General Emergency has been declared

• A Radioactive release is in progress

• The MET tower is out of service

• Field teams report wind directly from the West

• Severe weather is NOT predicted in the forecast For the above conditions, determine wind direction and the initial Protective Action Recommendations?

Wind direction from __(1)___ degrees.

Evacuate __(2)__ sectors out to 2 miles.

Evacuate __(3)__ sectors out to 5 miles Evacuate __(4)__ sectors out to 10 miles.

(1) (2) (3) (4)

Wind From 2 miles 5 miles 10 miles

a. 270 D, E, F 5N, 5E, 5S 10E, 10SE

b. 90 M, N, P 5W 10SW, 10W, 10NW

c. 90 All 5W None

d. 270 All 5N, 5E, 5S None

SENIOR REACTOR OPERATOR Page 6 of 15 Question 10 The plant is operating at rated conditions with a fuel bundle currently being shuffled in the Spent Fuel Pool. While the fuel bundle is being moved radiation levels change and are now as follows:

• Area Radiation Monitor A-1 reads 27 mrem/hr

• Area Radiation Monitor A-2 reads 22 mrem/hr

• Area Radiation Monitor A-3 reads 11 mrem/hr

• RM-17-453A (FUEL POOL MONITOR CHANNEL A) reads 22 mrem/hr

• RM-17-453B (FUEL POOL MONITOR CHANNEL B) reads 28 mrem/hr As the CRS, which of the following meets the requirements for the above conditions?

a. Declare an NUE

b. Evacuate the Reactor Building

c. Verify Standby Gas Treatment System is operating

d. Continue with the fuel shuffle, radiation levels are normal for this evolution Question 11 A reactor startup is in progress when a complete loss of Y-50 (RPS Bus A) occurs. Given the following:

• Reactor power is 4%

• The Mode Switch is in START TO HOT STANDBY

• APRMs 1 & 6 are currently bypassed

• Bypassed LPRMs are circled on the given LPRM assignment matrix (see photo on next page)

What action, if any, is required to be taken prior to placing the Mode Switch in RUN?

a. Bypass APRM #4

b. Bypass APRM #5

c. No action required; APRM #6 is already bypassed

d. No action required; LCO 3.0.4 applies allowing a mode change for this condition

SENIOR REACTOR OPERATOR Page 7 of 15 SENIOR REACTOR OPERATOR Page 8 of 15 Question 12 The plant is in Mode 5 with movement of irradiated fuel in progress. A change to the Refueling procedure (Verification Checklist Data File and Fuel Handling Supervisor Verification Checklist) has been requested. The in-core location of a fuel bundle will be changed to prevent SRM count rate from lowering below 10 CPS.

Which of the following meets the required signatures for this change?

a. Control Room Supervisor AND Shift Manager

b. Fuel Handling Supervisor AND Nuclear Engineer

c. Control Room Supervisor, Shift Manager AND Nuclear Engineer

d. Fuel Handling Supervisor, Control Room Supervisor AND Operations Manager Question 13 The plant is operating at rated conditions. The previous shift performed routine maintenance on HPCI (See photo on next page for HPCI system status). The following event occurs:

• SRV H tailpipe is reading 140°F and rising 1°F/hr

• SRV H Amber light is OFF As the CRS, if these conditions continue, which of the following must be directed if SRV H tailpipe temperature exceeds 210°F?

a. Place DIV I Core Spray in Torus Mixing Mode and restore Core Spray to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

b. Place DIV I Torus Cooling in service and restore RHR/LPCI mode to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

c. Reduce Reactor power IAW C.4-F (Rapid Power Reduction) with Recirc pumps but do not reduce flow < 34 Mlb/hr

d. Place DIV II Core Spray in Torus Mixing Mode, restore Core Spray to operable status within 7 days AND restore SRV H to operable status within 14 days

SENIOR REACTOR OPERATOR Page 9 of 15 SENIOR REACTOR OPERATOR Page 10 of 15 Question 14 The plant is operating at rated conditions. Given the following conditions:

• Outside air temp is 89ºF

• Static Inverter Y-81 tagged out for maintenance.

• Y-81 loads are being powered via MBS Y-83

• Breaker B4482 (Y82 120V INST AC ALT SOURCE XFMR) trips on over current.

For the conditions given above, which procedure must be prioritized FIRST to mitigate this event?

a. C.4-F (Rapid Power Reduction)

b. C.4-K (Immediate Reactor Shutdown)

c. C.4-B.06.03.A (Decreasing Condenser Vacuum)

d. C.4-B.05.07.A (Loss of Reactor Water Level Control)

Question 15 The plant is operating at rated conditions when a LONOP and small break LOCA occurred.

Given the following:

• 15 Bus is LOCKED out

• 12 EDG-ESW pump failed to start

• 11 Service Water pump is running

• Drywell pressure is 2.2 psig and slowly rising

• Drywell temperature is 138°F and slowly rising

• RPV pressure is 820 psig and slowly lowering

• RPV water level is -10 inches and slowly rising using HPCI Which of the following directions should be prioritized FIRST?

a. Place Torus sprays in service

b. Restore cooling to the #12 EDG

c. Start all available Drywell cooling

d. Prevent Core Spray and LPCI injection

SENIOR REACTOR OPERATOR Page 11 of 15 Question 16 The plant has been operating at rated conditions for several months. On August 6th at 1300 it was discovered that SR 3.1.3.3 had not been performed on control rod 26-19 since June 28th at 0800. Given the following:

• Control rod 26-19 is at position 12

• It has been determined that the risk impact can be managed Determine if an extension is allowed, if so, when is the latest the surveillance can be completed and remain in compliance with Technical Specifications?

a. Perform the surveillance prior to August 7th at 0200.

b. Perform the surveillance prior to August 7th at 1300.

c. Perform the surveillance prior to September 6th at 1300.

d. An extension IS NOT allowed, immediately enter the ACTIONS of TS 3.1.3.

Question 17 The plant is operating at 50% power with #12 Circulating Water Pump isolated for required maintenance. The following events occur:

• Lockout on Bus 13

• LC-107 fails to reenergize

• The reactor is scrammed

• Ten control rods are at position 48

• IRMs are reading 75 on range 7 and lowering As the CRS, which of the following actions should be directed?

a. Trip both recirc pumps IAW C.4-A

b. Trip both recirc pumps IAW C.5-2007

c. Defeat low-low RPV water level MSIV isolation IAW C.5-3301

d. Manually open enough SRVs and lower RPV pressure to 930 psig

SENIOR REACTOR OPERATOR Page 12 of 15 Question 18 The plant was operating at 7% with a startup in progress. Predict the impact if there was a loss of controller signal to the in-service Level Control Valve, and what action should be directed to mitigate this abnormal condition.

RPV water level would ___(1)___ and the CRS should direct the crew to ___(2)___.

(1) (2)

a. remain relatively constant adjust RWCU dump flow as required

b. rise raise reactor power

c. lower lower reactor power

d. lower take local manual control of the valve Question 19 The plant is operating at rated conditions. While performing the SBLC operability surveillance Test, the Out-plant Operator inadvertently drained an unknown volume of solution from the storage tank. The following information has been obtained.

• Tank level indication is 1150 gallons.

• Boron enrichment is 58 percent.

• Boron solution concentration is 12.6 percent.

• Pump flow rate is 26 gpm at 1275 psig.

• Boron solution temperature is 70oF.

Is the SBLC system OPERABLE or INOPERABLE and why?

a. The SBLC system is OPERABLE. Existing conditions satisfy Table 3.1.7-1 Equations 1 and 2.

b. The SBLC system is INOPERABLE; a minimum of 50 gallons of demin water must be added to declare the SBLC system operable.

c. The SBLC system is INOPERABLE; boron concentration must be raised a minimum of 0.62 percent to declare the SBLC system operable.

d. The SBLC system is OPERABLE. Tank volume and Boron concentration are within the allowed operation region of Figure 3.1.7-1 of Technical Specifications.

SENIOR REACTOR OPERATOR Page 13 of 15 Question 20 A plant startup is in progress with the reactor critical and a positive period established in the intermediate range. The Duty RO has completed OPERATIONS DAILY LOG - PART J and has given it to you for review.

After reviewing the given completed portions of OPERATIONS DAILY LOG - PART J, which of the following, if any, describes the Technical Specification required action and completion time?

a. None, RCS Operational LEAKAGE is within limits

b. Reduce RCS Total LEAKAGE to within limits in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

c. Reduce RCS Unidentified LEAKAGE to within limits in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

d. Verify RCS Unidentified LEAKAGE increase is not in service sensitive type 304 or type 316 austenitic stainless steel in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Question 21 The plant is operating in single loop with the following conditions:

• Reactor power is 50%

• MCPR is determined to be 1.10 Which of the following, if any, is the required action that must be directed to satisfy Technical Specifications?

a. Insert control rods until RTP< 25%

b. No action required, maintain MCPR 1.10

c. Fully insert all insertable control rods within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

d. Restore MCPR to within COLR limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

SENIOR REACTOR OPERATOR Page 14 of 15 Question 22 Which of the following fleet tagging responsibilities can ONLY be carried out by Operations Shift Supervision or persons designated by Operations Management in the Work Control Center (WCC)?

a. Status a clearance checklist to Distributed

b. Status a clearance order to Working

c. Authorize more than one holder at a time for each operating permit.

d. Direct Primary Authorized Employee(s) to release OR verify released all stored energy prior to start of work.

Question 23 As the CRS, you had been working with the Reactor Building Operator and the ALARA Coordinator to determine the best way to perform an upcoming evolution in the plant. The following facts are known:

• Past task performance has resulted in an average exposure of 550 mrem

• The task historically required 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to complete

• If shielding is hung it would lower the dose rate by 25%

• The total dose to hang and remove the shielding is estimated to be 220 mrem

• A special tool is available to perform the task that would allow the operator to be in a lower exposure area (200 mrem/hr)

• Use of the special tool is estimated to extend the job time by 40%

What direction must the CRS provide to the Reactor Building Operator and the ALARA Coordinator to ensure that the task is performed within the principles of ALARA?

a. Hang the shielding AND use the special tool

b. DO NOT use the shielding, but use the special tool

c. Hang the shielding, but DO NOT use the special tool

d. DO NOT use the shielding AND DO NOT use the special tool

SENIOR REACTOR OPERATOR Page 15 of 15 Question 24 A plant shutdown is in progress with reactor power at 25%. De-inerting preparations are in progress IAW 2140 (DEINERTING PRIMARY CONTAINMENT).

As the CRS, you are required to

a. De-inert by venting primary containment through the Reactor Building plenum.

b. Complete de-inerting within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the time the primary containment purge was initiated.

c. Verify an analysis of primary containment atmosphere has been completed within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d. Stop the primary containment purge once the drywell equipment hatch, drywell personnel hatch, or torus manway are opened.

Question 25 The plant is operating at 60% power when an unisolable reactor coolant leak occurs in the RWCU pump room. Given the following:

• SBGT has automatically initiated

• RWCU Pump Room temperature is 215°F and rising

• 962-foot elevation outside the RWCU Pump Room is 205°F and rising

• 962-foot elevation outside the RWCU Pump Room is 1100 mrem/hr and rising As the CRS, which of the following actions is required to be taken for the above conditions?

a. Open all 3 ADS valves and rapidly depressurize the RPV

b. Stabilize RPV pressure and maintain cooldown rate <100ºF/hr

c. Restart Turbine Building Ventilation to ensure a diluted elevated release

d. Open main turbine bypass valves and exceed a 100°F/hour cooldown rate

SENIOR REACTOR OPERATOR Page 1 of 4 QUESTION 001 Question 006 K/A 95016 2.2.9 K/A 295037EA2.06 REFERENCE AWI-02.02.02 REFERENCE C.5.1-2007 and MEMORY C.5-2007 NEW Reference provided during exam: EOP flowcharts HIGHER QUESTION 002 MODIFIED K/A 295003AA2.04 REFERENCE B.09.07-02 HIGHER Question 7 NEW K/A 600000 2.4.29 REFERENCE 4AWI-08.02.02, A.2-101 QUESTION 3 Reference provided during exam: EAL K/A 295024EA2.04 Matrix REFERENCE C.5-1200, HIGHER B.04.01.01-02 NEW Reference provided during exam: EOP Flow Charts HIGHER QUESTION 008 NEW K/A 295014AA2.02 REFERENCE C.6-005-A-20, C.1 FUNDAMENTAL QUESTION 004 NEW K/A 295025 2.3.4 REFERENCE A.2-401 FUNDAMENTAL QUESTION 009 NEW K/A 295017AA2.05 REFERENCE A.2-204, 5790-102-02 QUESTION 5 Reference provided during exam: 5790-K/A 295031EA2.04 102-02 pg. 2 of 3 REFERENCE C.5.1-1000, C.5- HIGHER 1100, C.5-2002 and C.5-2007 NEW Reference provided during exam: EOP flowcharts HIGHER QUESTION 010 NEW K/A 295034 2.4.11 REFERENCE D.2-05, page 6 paragraph 11)

Reference provided during exam: EOP flowcharts and EAL Matrix FUNDAMENTAL NEW

SENIOR REACTOR OPERATOR Page 2 of 4 QUESTION 011 QUESTION 016 K/A 212000A2.16 K/A 201002 2.2.12 REFERENCE B.05.01.02, TS 3.0, REFERENCE SR 3.0, TS 3.1.3 3.3.1.1 Reference provided during exam: SR Reference provided during exam: TS 3.0, TS 3.1.3, 2007 calendar 3.0, 3.3.1.1 HIGHER HIGHER NEW NEW QUESTION 017 QUESTION 012 K/A 202002A2.02 K/A 215004 2.2.26 REFERENCE C.5.1-1000, C.5.1-REFERENCE D.2-05 2007, C.5-2007, C.4-A, and C.4-FUNDAMENTAL B.09.07.E NEW Reference provided during exam: EOP Flow Charts HIGHER QUESTION 013 NEW K/A 239002A2.02 REFERENCE C.4-B.03.03.B, TS 3.4.3 & 3.5.1 QUESTION 018 Reference provided during exam: TS K/A 259001A2.07 3.4.3 & 3.5.1 REFERENCE B.05.07-01, C.4-HIGHER B.05.07.A NEW HIGHER BANK QUESTION 014 K/A 262002A2.01 QUESTION 019 REFERENCE C.4-B.09.13.E & G K/A 2.1.25 HIGHER REFERENCE TS 3.1.7 NEW Reference provided during exam: TS 3.1.7 and figures HIGHER QUESTION 015 BANK K/A 264000 2.4.22 REFERENCE C.6-008-C-17 QUESTION 020 Reference provided during exam: EOP K/A 2.1.33 Flow Charts REFERENCE B.07.01-05 and TS HIGHER 3.4.4 NEW Reference provided during exam: TS 3.4.4, Completed Pages 11, 12 and 13 of 0000-J HIGHER NEW

SENIOR REACTOR OPERATOR Page 3 of 4 QUESTION 021 K/A 2.2.22 REFERENCE TS 2.1.1.2, 2.2 and 3.2.2 Reference provided during exam:

Technical Specification (Safety Limit Section 2 removed)

HIGHER NEW QUESTION 022 K/A 2.2.13 REFERENCE 4 AWI-04.05.04 and FP-OP-TAG-02 FUNDAMENTAL NEW QUESTION 023 K/A 2.3.2 REFERENCE 4AWI-08.04.01, GET-Radiation Worker HIGHER NEW QUESTION 024 K/A 2.3.9 REFERENCE 2140 MEMORY NEW QUESTION 025 K/A 2.4.6 REFERENCE C.5-1-1000, C.5 1100, and C.5-1100 Reference provided during exam: EOP Flow Charts HIGHER NEW

• • • • • END OF EXAM*****

SENIOR REACTOR OPERATOR Page 1 OF 1 ANSWER KEY MULTIPLE CHOICE 001 d.

002 d.

003 b.

004 b.

005 c.

006 c.

007 b.

008 b.

009 d.

010 b.

011 b.

012 c.

013 a.

014 d.

015 b.

016 c.

017 a.

018 d.

019 a.

020 c.

021 c.

022 a.

0023 d.

024 c.

025 d.