ML23191A042

Final SRO Written Exam - Browns Ferry 2023-301

ML23191A042
Person / Time
Site:	Browns Ferry
Issue date:	07/10/2023
From:	Tennessee Valley Authority
To:	NRC/RGN-II
References
Download: ML23191A042 (1)

Text

Form 4.2-4 Senior Reactor Operator Written Examination Cover Sheet U.S. Nuclear Regulatory Commission Senior Reactor Operator Written Examination Applicant Information Name:

Date:

Facility/Unit: Browns Ferry Region:

I II III IV Reactor Vendor/Type: BWR 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 percent overall, with 70 percent or better on the senior reactor operator (SRO)-only items if given in conjunction with the reactor operator (RO) exam; SRO-only exams given alone require a final grade of 80 percent to pass. You have 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-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-only portion.

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

Applicants Signature Results RO/SRO-Only/Total Examination Points ______ / ______ / ______ Points Applicants Points ______ / ______ / ______ Points Applicants Grade ______ / ______ / ______ Percent ML23191A042

ILT 2304 Written Exam 76

76.

Unit 2 is operating at 100% RTP when the following conditions occur:

x HPCI LOGIC POWER FAILURE (2-9-3F, Window 3) alarms x HPCI 120 VAC POWER FAILURE (2-9-3F, Window 7) alarms x ADS BLOWDOWN POWER FAILURE (2-9-3C, Window 32) alarms Given the conditions above, the 250V DC RMOV Board (1) has been lost.

After manually transferring the affected 250V DC RMOV Board to its alternate power supply, the Board (2) in accordance with Tech Spec 3.8.7 Bases, Distribution Systems - Operating.

A. (1) 2A (2) remains OPERABLE B. (1) 2A (2) is INOPERABLE C. (1) 2B (2) remains OPERABLE D. (1) 2B (2) is INOPERABLE

ILT 2304 Written Exam 77

77.

Control Rod coupling integrity (1) one of the OPERABILITY factors listed in Tech Spec 3.1.3 Bases, Control Rod OPERABILITY.

In accordance with Technical Specification Bases, CRD Temperatures above (2) may result in a measurable delay in SCRAM time response.

A. (1) is (2) 281 °F B. (1) is (2) 350 °F C. (1) is NOT (2) 281 °F D. (1) is NOT (2) 350 °F

ILT 2304 Written Exam 78

78.

Unit 3 is operating at 100% RTP when the following conditions occur:

At 0220:

x PRIMARY CONTAINMENT N2 PRESSURE HIGH (3-9-3B, Window 10) alarms x DRYWELL PRESSURE ABNORMAL (3-9-5B, Window 31) alarms At 0235:

x The NUSO enters 3-AOI-100-2, Control Room Abandonment At 0220, the Unit 3 EDGs (1) automatically start.

Given the conditions above and in accordance with EPIP-1, Emergency Classification Procedure, the EARLIEST time an ALERT condition exists is (2).

Note: SED judgement shall NOT be used as a basis for Classification

[REFERENCE PROVIDED]

A. (1) did (2) 0220 B. (1) did (2) 0235 C. (1) did NOT (2) 0220 D. (1) did NOT (2) 0235

ILT 2304 Written Exam 79

79.

Following a Reactor SCRAM on Unit 2, the following conditions exist:

x DRYWELL CONTROL AIR PRESSURE LOW, (2-9-3E, Window 35), is in alarm x Drywell Control Air Pressure (DWCA) is 45 psig x Reactor Water Level lowered to (-) 10 inches, currently at (+) 30 inches x NO Operator actions have been taken Given the conditions above, which ONE of the following completes the statements below?

The OUTBOARD MSIVs are currently (1).

The Containment Atmosphere Dilution (CAD) System (2) OPERABLE when aligned to DWCA.

A. (1) OPEN (2) remains B. (1) OPEN (2) is NOT C. (1) CLOSED (2) remains D. (1) CLOSED (2) is NOT

ILT 2304 Written Exam 80

80.

In accordance with EOIPM Section 0-X(G), EOI-2 Primary Containment Control Bases, the Suppression Chamber Spray Initiation Pressure is a threshold pressure that signals (1) the Suppression Chamber.

BEFORE this Suppression Chamber Pressure is reached, the NUSO is required to direct the performance of (2).

Note: EOI APPENDIX-17B, RHR System Operation Drywell Sprays EOI APPENDIX-17C, RHR System Operation Suppression Chamber Sprays A. (1) over-pressurization of (2) EOI APPENDIX-17B B. (1) over-pressurization of (2) EOI APPENDIX-17C C. (1) the possibility of chugging in (2) EOI APPENDIX-17B D. (1) the possibility of chugging in (2) EOI APPENDIX-17C

ILT 2304 Written Exam 81

81.

Unit 2 was operating at 100% RTP when the following conditions occurred:

x A PCIS Group 1 Isolation resulted in a SCRAM x Reactor Pressure peaked at 1136 psig, currently at 1090 psig x NO Operator actions have been taken Given the conditions above, which ONE of the following completes the statements below?

(1) Main Steam Relief Valves (MSRVs) are automatically cycling.

The Nuclear Unit Senior Operator (NUSO) (2) required to direct the performance of 2-EOI Appendix-11A, Alternate RPV Pressure Control Systems MSRVs.

A. (1) Four (4)

(2) is NOT B. (1) Four (4)

(2) is C. (1) Five (5)

(2) is NOT D. (1) Five (5)

(2) is

ILT 2304 Written Exam 82

82.

Which ONE of the following completes the statements below in accordance with 0-FSS-001, Fire Safe Shutdown?

The (1), or designee, will be responsible for the implementation and control of FSS procedures and will assign personnel as necessary.

NFPA-805 Code allows plant personnel to use all available equipment until proven unreliable with the exception of (2).

A. (1) Shift Manager (2) annunciators B. (1) Shift Manager (2) the RHR System C. (1) Fire Brigade Leader (2) annunciators D. (1) Fire Brigade Leader (2) the RHR System

ILT 2304 Written Exam 83

83.

Unit 2 is in MODE 4 with the following conditions:

x No forced circulation exists x The crew is implementing 2-AOI-74-1, Loss of Shutdown Cooling x Thermal stratification is NOT indicated, nor suspected In accordance with 2-AOI-74-1, which ONE of the following completes the statements below?

Reactor Water Level (1) required to be raised to between (+) 70 to (+) 90 inches.

2-SR-3.4.9.1(1), Reactor Heatup and Cooldown Rate Monitoring, is (2) to determine the current RPV Heatup Rate.

A. (1) is (2) NOT allowed to be used B. (1) is (2) required to be performed C. (1) is NOT (2) NOT allowed to be used D. (1) is NOT (2) required to be performed

ILT 2304 Written Exam 84

84.

Unit 3 is operating at 100% RTP with the following conditions:

x Reactor Water Level is (+) 33 inches x RFWCS INPUT FAILURE, (3-9-6C, Window 14) alarms x The OATC reports REACTOR WATER LEVEL NARROW RANGE 3-LI-3-60 (LEVEL B) and 3-LI-3-206 (LEVEL C) on Panel 3-9-5 indicate BYPASSED x NO Operator Actions have been taken Given the conditions above, which ONE of the following completes the statements below?

3-LIC-46-5, REACTOR WATER LEVEL MASTER CONTROLLER PANEL DISPLAY STATION (PDS), is in (1) mode.

Emergency Preparedness (EP) (2) required to be notified.

[REFERENCE PROVIDED]

A. (1) MANUAL (2) is NOT B. (1) MANUAL (2) is C. (1) AUTOMATIC (2) is NOT D. (1) AUTOMATIC (2) is 14 RFWCS INPUT FAILURE 3-LA-46-5D

ILT 2304 Written Exam 85

85.

Which ONE of the following completes the statements below?

In accordance with NPG-SPP-10.4, Reactivity Management Program, the MINIMUM planned Reactor Power change that requires a dedicated Reactivity Management SRO to be present is a Power change greater than (1) RTP.

In accordance with OPDP-1, Conduct of Operations, the NUSO is required to notify the duty Reactor Engineer of UNPLANNED reactivity changes greater than (2) RTP.

A. (1) 10%

(2) 1%

B. (1) 10%

(2) 10%

C. (1) 15%

(2) 1%

D. (1) 15%

(2) 10%

ILT 2304 Written Exam 86

86.

Unit 3 is operating at 100% RTP with HPCI operating to support 3-SR-3.5.1.7(COMP),

HPCI Comprehensive Pump Test, when the following occurs:

x 3-LI-3-208A and D, RX WATER LEVEL NARROW RANGE, fail UPSCALE x Indicated Reactor Water Level peaked as shown below Given the conditions above, the Unit 3 HPCI Turbine is CURRENTLY (1).

Unit 3 Tech Spec 3.3.5.1, ECCS Instrumentation, REQUIRED ACTION C.2 (2) required.

[REFERENCE PROVIDED]

A. (1) tripped (2) is NOT B. (1) tripped (2) is C. (1) operating (2) is NOT D. (1) operating (2) is

ILT 2304 Written Exam 87

87.

The following conditions exist on Unit 3:

x 3-HS-99-5A-S1, REACTOR MODE SWITCH, is in START HOT STANDBY x 3-OI-92A, IRMs, Preparing IRMs for Reactor Startup, is in progress x IRM H just failed high and has been bypassed Subsequently, the IRM B IN backlight failed to extinguish when the DRIVE OUT pushbutton was depressed and held, indicating IRM B was stuck.

Given the conditions above, in accordance with Tech Spec 3.3.1.1, RPS Instrumentation, the REQUIRED ACTION that must be performed is based on (1) and is completed using (2).

[REFERENCE PROVIDED]

A. (1) CONDITION A (2) 3-OI-99, Reactor Protection System B. (1) CONDITION A (2) 3-OI-92A, Intermediate Range Monitors C. (1) CONDITION B (2) 3-OI-99, Reactor Protection System D. (1) CONDITION B (2) 3-OI-92A, Intermediate Range Monitors

ILT 2304 Written Exam 88

88.

Unit 2 was operating at 100% RTP when an event occurred, resulting in the following conditions:

x A manual Reactor SCRAM was inserted x Drywell Pressure is 4.0 psig and rising x Primary Containment Hydrogen indicates 2.5% and stable x Offsite Radioactivity Release Rate is expected to remain BELOW ODCM limits Given the conditions above, 2-EOI-2, PRIMARY CONTAINMENT CONTROL, entry is required based on (1) and the NUSO is required to direct the performance of (2).

Note: 2-EOI Appendix-12, Primary Containment Venting 2-EOI Appendix-13, Emergency Venting Primary Containment A. (1) Drywell Pressure ONLY (2) 2-EOI Appendix-12 B. (1) Drywell Pressure ONLY (2) 2-EOI Appendix-13 C. (1) Drywell Pressure AND Hydrogen Concentration (2) 2-EOI Appendix-12 D. (1) Drywell Pressure AND Hydrogen Concentration (2) 2-EOI Appendix-13

ILT 2304 Written Exam 89

89.

Unit 1 is operating at 100% RTP with the following conditions:

At 1200:

x 0-SR-3.8.1.1(A), Diesel Generator A Monthly Operability Test, is in progress x A EDG is loaded with DG A MODE SELECT switch in PARALLEL WITH SYSTEM x Standby Gas Train C is INOPERABLE At 1215:

x DIESEL GEN A OVERLOAD (1/2-9-23A, Window 11) alarms At 1300:

x Maintenance Electrical Group (MEG) determined that the overload alarm was caused by a voltage regulator malfunction Given the conditions above, which ONE of the following completes the statements below?

At 1215, breakers 1614 AND 1716 (1).

The EARLIEST time Unit 1 is required to enter LCO 3.0.3 is (2).

Note: 4KV Shutdown Board A Normal Breaker (1614) 4KV Shutdown Board A Alternate Breaker (1716)

Diesel Generator A Breaker (1818)

[REFERENCE PROVIDED]

A. (1) remain closed and Diesel Generator A Breaker (1818) opens (2) 1215 B. (1) remain closed and Diesel Generator A Breaker (1818) opens (2) 1615 C. (1) automatically open and EDG continues carrying 4KV Shutdown Board A (2) 1215 D. (1) automatically open and EDG continues carrying 4KV Shutdown Board A (2) 1615

ILT 2304 Written Exam 90

90.

Units 1, 2, and 3 are operating at 100% RTP in their normal electrical lineups when:

x 250V DC Battery Board 4 is de-energized x 480V Shutdown Board 2A is de-energized Given the conditions above, which ONE of the following completes the statements below?

Unit 2 Battery Board 2, Panel 11, Unit Preferred, (1).

(2) contains the steps to re-energize Panel 9-9, Cabinet 5, Unit NON-Preferred Note: 2-AOI-57-4, Loss of Unit Preferred 0-AOI-57-6, Loss of Plant Non Preferred A. (1) remains energized (2) 2-AOI-57-4 B. (1) remains energized (2) 0-AOI-57-6 C. (1) is de-energized (2) 2-AOI-57-4 D. (1) is de-energized (2) 0-AOI-57-6

ILT 2304 Written Exam 91

91.

Which ONE of the following completes the statements below?

The full-in (S52) position reed switch which provides full-in green indication on the Full Core Display (1) the reed switch used to satisfy Tech Spec 3-9.4, Control Rod Position Indication, full-in position information to the refueling interlocks.

In accordance with 2-OI-85, Control Rod Drive System, bypassing a failed full-in position reed switch (2) be performed in the Main Control Room.

A. (1) is NOT (2) can NOT B. (1) is NOT (2) can C. (1) is also (2) can NOT D. (1) is also (2) can

ILT 2304 Written Exam 92

92.

Unit 1 is operating at 100% RTP with 0-RM-90-259A, CONTROL ROOM VENTILATION RADIATION MONITOR, indicating DOWNSCALE when the following occurs:

x 0-RM-90-259B, CONTROL ROOM VENTILATION RADIATION MONITOR, indicates 230 counts per minute Given the above conditions, which ONE of the following completes the statements below?

The Control Room Emergency Ventilation System (CREV) (1) receive an automatic initiation signal.

In accordance with Unit 1 Tech Spec Bases, 3.3.7.1, CREV System Instrumentation, if BOTH channels of Control Room Air Supply Duct Radiation - High are INOPERABLE, alternate monitoring capability is provided by (2).

A. (1) will (2) Portable Air Particulate Monitor ONLY B. (1) will (2) Portable Air Particulate Monitor AND Main Control Room Radiation Indicator (RI-90-8)

C. (1) will NOT (2) Portable Air Particulate Monitor ONLY D. (1) will NOT (2) Portable Air Particulate Monitor AND Main Control Room Radiation Indicator (RI-90-8)

ILT 2304 Written Exam 93

93.

Unit 1 was operating at 100% RTP when the following conditions occur:

x 1-DMP-064-0013, REACTOR ZONE SUPPLY OUTBOARD ISOLATION DAMPER, failed CLOSED and declared INOPERABLE x All REQUIRED ACTIONS have been completed in accordance with Tech Spec 3.6.4.2, Secondary Containment Isolation Valves (SCIVs)

As a result of the 1-DMP-064-0013 failure, 1-OI-30B, Reactor Zone Ventilation System, Section 7.1, Shutdown of Reactor Zone Supply and Exhaust Fans, is being implemented.

Given the conditions above, which ONE of the following completes the statements below?

Technical Specification 3.6.4.1, Secondary Containment, REQUIRED ACTION A.1, (1) required to be completed.

In accordance with 1-OI-30B, Reactor Zone Ventilation System, operation of the Steam Vault Exhaust Booster Fan, (2) permitted.

REFERENCE PROVIDED A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT

ILT 2304 Written Exam 94

94.

In accordance with EPIP-1, Emergency Classification Procedure, which ONE of the following completes the statements below?

NOTE: CONSIDER EACH STATEMENT BELOW SEPARATELY In accordance with BFN-ODM-4.20, Strategies for Successful Transient Mitigation, if a crew is unable to validate the indications that an Emergency Classification Action Level (EAL) has been exceeded within 15 minutes of receiving the notification/indications, that EAL Classification (1) required to be declared.

If a higher EAL Classification was met, but resolved PRIOR to declaration, that Classification (2) required be declared.

A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT

ILT 2304 Written Exam 95

95.

Unit 2 is in MODE 5 performing a NON-SPIRAL core reload during a scheduled refueling outage with the following conditions:

x The next fuel bundle is to move from the fuel pool to Reactor Cavity position 26-43 x As the respective fuel bundle is grappled, SRM A and D fail downscale x ALL other SRMs are OPERABLE NOTE: CONSIDER EACH STATEMENT BELOW SEPARATELY Which ONE of the following completes the statements below in accordance with Tech Specs and 0-GOI-100-3C, Fuel Movement Operations During Refueling?

Given the conditions above, the next fuel movement to cavity position 26-43 (1) continue.

Three-direction (X, Y and Z planes) movements are allowed in (2).

[REFERENCE PROVIDED]

A. (1) can (2) Reactor Vessel area ONLY B. (1) can (2) Spent Fuel Pool AND Reactor Vessel area C. (1) can NOT (2) Reactor Vessel area ONLY D. (1) can NOT (2) Spent Fuel Pool AND Reactor Vessel area

ILT 2304 Written Exam 96

96.

In accordance with NPG-SPP-07.3, Work Activity Risk Management Process, Operations (1) REQUIRED to review Attachment 4, BWR Operational Risk Review - RED SHEET for a normally scheduled performance of 0-SR-3.8.1.1(A) - Diesel Generator A Monthly Operability Test.

In accordance with NPG-SPP 6.1, Work Order Process, the (2) has the responsibility of assigning a task as a Priority 1 emergent work order.

A. (1) is NOT (2) Shift Manager B. (1) is NOT (2) Work Week Manager C. (1) is (2) Shift Manager D. (1) is (2) Work Week Manager

ILT 2304 Written Exam 97

97.

In accordance with Tech Spec 3.0, LCO Applicability, which ONE of the following identifies when a Loss of Safety Function evaluation is required to be performed?

A. Entry to Tech Spec LCO 3.0.3.

B. Changing modes where an LCO required action permits operation for an unlimited period of time.

C. When a support systems LCO is not met but the supported system(s) LCO is still considered to be met.

D. When Special Operations LCOs in Section 3.10 are entered.

ILT 2304 Written Exam 98

98.

In accordance with 2-GOI-200-2A, Primary Containment Initial Entry, which ONE of the following completes the statements below?

(1) approval is required for all initial entries.

A member of (2) will remain at the Personnel Airlock in continuous communication with the Control Room AND with the persons in the Drywell.

A. (1) Shift Manager (2) Operations B. (1) Shift Manager (2) Radiation Protection C. (1) Plant Manager (2) Operations D. (1) Plant Manager (2) Radiation Protection

ILT 2304 Written Exam 99

99.

In accordance with Technical Specification 3.3.3.1, PAM Instrumentation, which ONE of the following is a Post-Accident Monitoring (PAM) instrument?

A. Reactor Steam Dome Pressure (PI-3-74A and PI-3-74B)

B. Source Range Monitor (SRM) Instrumentation C. ECCS and RCIC Trip System Bus Power Monitors D. Control Rod Motion - Control Rod Position

ILT 2304 Written Exam 100 100. Unit 1 was operating at 100% RTP when an event occurred, requiring an Emergency Declaration of NOUE.

Given the conditions above, in accordance with the EPIPs, which ONE of the following completes the statements below?

Activation of the Technical Support Center (TSC) (1) required.

<REP 1> on the Emergency Communication and Notification System (ECNS) phone will contact the (2).

A. (1) is (2) State of Alabama ONLY B. (1) is (2) State of Alabama AND ODS C. (1) is NOT (2) State of Alabama ONLY D. (1) is NOT (2) State of Alabama AND ODS

BFN ILT 2304 SRO References 06082023 REFERENCE PROVIDED to candidate

76. HPCI LOGIC POWER FAILURE (2-9-3F, Window 3) - picture only HPCI 120 VAC POWER FAILURE (2-9-3F, Window 7) - picture only ADS BLOWDOWN POWER FAILURE (2-9-3C, Window 32) - picture only

78. EPIP-1, Attachment 1, HOT INITIATING CONDTIONS-MODES 1-2-3 PRIMARY CONTAINMENT N2 PRESSURE HIGH (3-9-3B, Window 10) - picture only DRYWELL PRESSURE ABNORMAL (3-9-5B, Window 31) - picture only

79. DRYWELL CONTROL AIR PRESSURE LOW, (2-9-3E, Window 35) - picture only

84. RFWCS INPUT FAILURE, (3-9-6C, Window 14) - picture only NPG-SPP-18.3.5, Rev. 12 (pages 1-27, 60-62)

86. Unit 3 Tech Spec 3.3.5.1 (pages 36-48) 3-LI-3-208A, B, C, and D, REACTOR WATER LEVEL NARROW RANGE instrument indications-picture only

87. Unit 3 Tech Spec 3.3.1.1 (pages 3.3 3.3-7)

89. Unit 1 Tech Spec 3.8.1 (pages 1-13)

Unit 1 Tech Spec 3.6.4.3 (pages 51-54)

DIESEL GENERATOR A OVERLOAD (1/2-9-23A, Window 11) - picture only

93. Unit 1 Tech Spec 3.6.4.1 (pages 3.6 3.6-46)

Unit 1 Tech Spec 3.6.4.2 (pages 3.6 3.6-50)

95. 0-GOI-100-3C, Attachment 14 (Page 1 of 1) Core Quadrants