ML22161A929

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Bf 2022-301 Exam Report Items, SRO Written Exam
ML22161A929
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 06/10/2022
From:
NRC/RGN-II
To:
Tennessee Valley Authority
References
Download: ML22161A929 (27)
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ILT 2204 Written Exam 76

76.

Following a failure of a Jet Pump, Reactor Pressure will (1).

In accordance with Tech Spec Bases, the OPERABILITY of Jet Pumps is to allow reflooding of the core to (2) Reactor Water Level following a complete break of a Recirculation Pump suction pipe.

A. (1) lower (2) (-) 162 inches B. (1) lower (2) (-) 215 inches C. (1) rise (2) (-) 162 inches D. (1) rise (2) (-) 215 inches ML22161A929

ILT 2204 Written Exam 77

77.

Unit 1 and 2 are in MODE 1, 100% RTP. Unit 3 is in MODE 4, when the following conditions occur on Unit 3:

At 0900:

  • Moderator temperature is 213 °F At 1100:
  • Maintenance reports the fault condition has been repaired and RHR can be placed in service
  • Reactor Water Level maintained in the required band throughout the event Given the conditions above and in accordance with EPIP-1, Emergency Classification Procedure, the HIGHEST required Emergency Classification to report will be a/an (1) and from the time of event declaration, NRC Notification must NOT exceed (2).

Note: Notification of Unusual Event (NOUE)

[REFERENCE PROVIDED]

A. (1) NOUE (2) 15 minutes B. (1) NOUE (2) 60 minutes C. (1) ALERT (2) 15 minutes D. (1) ALERT (2) 60 minutes

ILT 2204 Written Exam 78

78.

Unit 2 was in MODE 5 during a refueling outage, when the following conditions occurred:

At 0905:

  • Operators commence fuel movements
  • The first fuel bundle is dropped due to grapple mechanical failure At 0915:
  • 2-RM-90-1A, Fuel Pool Floor, alarming and indicating 126 mr/hr
  • 2-RM-90-250A, Reactor, Turbine, Refuel Exhaust, alarming and indicating 4.7E+6

µCi/s At 0917:

  • Shift Manager (as the SED), makes an Emergency Plan Event Declaration Given the conditions above and in accordance with EPIP-1, Emergency Classification Procedure, the HIGHEST required Emergency Classification to report is a/an (1) and the State of Alabama is required to be notified NO later than (2).

Note: SED judgement shall NOT be used as a basis for Classification Notification of Unusual Event (NOUE)

[REFERENCE PROVIDED]

A. (1) ALERT (2) 0932 B. (1) ALERT (2) 0945 C. (1) NOUE (2) 0932 D. (1) NOUE (2) 0945

ILT 2204 Written Exam 79

79.

Unit 2 is operating at 8% RTP with the following conditions:

  • Due to a temporary loss of Drywell cooling, Drywell Pressure PEAKED at 2.1 psig
  • HPCI initiated automatically and subsequently was tripped and locked out
  • Subsequently, Drywell cooling was restored with Drywell Pressure stable at 1.4 psig Given the conditions above, the HPCI initiation was (1) and in accordance with Tech Spec Bases, the REACTOR MODE SWITCH (2) be placed in RUN.

A. (1) valid (2) can B. (1) valid (2) can NOT C. (1) invalid (2) can D. (1) invalid (2) can NOT

ILT 2204 Written Exam 80

80.

Unit 2 was in MODE 4 with Reactor Water Level at 120 inches during vessel flood up when the following occurs:

  • Leak in Drywell
  • Drywell Pressure was reported as 15 psig
  • Drywell Temperature reported to be 230 °F
  • 2-LI-3-55, FLOOD UP LEVEL INSTRUMENT, is indicating 46 inches Given the conditions above and in accordance with the EOIs, 2-LI-3-55, FLOOD UP LEVEL INSTRUMENT (1) valid.

The NUSO will direct performance of (2).

Note: 2-EOI-APPENDIX-17B, RHR System Operation Drywell Sprays 2-EOI-APPENDIX-17C, RHR System Operation Suppression Chamber Sprays

[REFERENCE PROVIDED]

A. (1) is (2) 2-EOI-APPENDIX-17C ONLY B. (1) is (2) 2-EOI-APPENDIX-17C AND 2-EOI-APPENDIX-17B C. (1) is NOT (2) 2-EOI-APPENDIX-17C ONLY D. (1) is NOT (2) 2-EOI-APPENDIX-17C AND 2-EOI-APPENDIX-17B

ILT 2204 Written Exam 81

81.

An ATWS has occurred on Unit 3 resulting in the following conditions:

  • Reactor Power is 20%
  • Reactor Water Level is 0 inches 3-EOI-1A, ATWS RPV Control, (1) direct Operators to STOP and PREVENT injection from EHPM and RCIC.

In accordance with the EOI Program Manual Bases, the reason Reactor Water Level is lowered to (-) 50 inches is to uncover the (2) spargers.

A. (1) does (2) Feedwater B. (1) does (2) Core Spray C. (1) does NOT (2) Feedwater D. (1) does NOT (2) Core Spray

ILT 2204 Written Exam 82

82.

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

At 1000

  • A fire is reported in the Unit 3 Main Control Room (MCR)

At 1010

  • The Unit 3 MCR is abandoned At 1025
  • RCIC is controlling Reactor Water Level and MSRVs are controlling Reactor Pressure from 3-Panel-25-32, BACKUP CONTROL PANEL Given the conditions above and in accordance with 3-AOI-100-2, Control Room Abandonment, the responsibility of assessing MCR habitability is performed by the (1).

In accordance with EPIP-1, Emergency Classification Procedure, the HIGHEST required Emergency Classification to report is a/an (2).

[REFERENCE PROVIDED]

A. (1) Shift Manager (2) ALERT B. (1) Shift Manager (2) SITE AREA EMERGENCY C. (1) Incident Commander (2) ALERT D. (1) Incident Commander (2) SITE AREA EMERGENCY

ILT 2204 Written Exam 83

83.

Unit 3 is operating at 100% RTP when a Feedwater Control System malfunction occurs with the following conditions:

  • 3-LI-3-208D, RX WATER LEVEL NARROW RANGE, fails DOWNSCALE
  • Reactor Water Level peaked as indicated

A few minutes later, 3-LI-3-208C, RX WATER LEVEL NARROW RANGE, fails DOWNSCALE in the next minute, LCO 3.3.2.2 entry into Condition B (2) required.

[REFERENCE PROVIDED]

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

ILT 2204 Written Exam 84

84.

Unit 1 is operating in MODE 1 when the following conditions occur:

  • NO high OR low pressure make-up sources are available In accordance with the EOIs, Emergency Depressurization is required BEFORE Reactor Water Level lowers to (1).

In accordance with the EOIPM SECTION 0-V(L), C1, ALTERNATE LEVEL/PRESSURE CONTROL BASES, Minimum Zero Injection RPV Water Level (MZIRWL) lower limit ensures fuel clad temperatures will NOT exceed (2).

A. (1) (-) 235 inches (2) 1500 F B. (1) (-) 235 inches (2) 1800 F C. (1) (-) 162 inches (2) 1500 F D. (1) (-) 162 inches (2) 1800 F

ILT 2204 Written Exam 85

85.

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

  • REACTOR ZONE DIFFERENTIAL PRESSURE LOW (1-9-3D, Window 32) alarms
  • AUO reports REACTOR ZONE DIFFERENTIAL PRESSURE is (+).5 inches of water locally
  • Assume NO Operator action has been taken Given the conditions above, Standby Gas Treatment (1) automatically started.

To mitigate this condition, the NUSO (2) direct entry into 1-AOI-30B-1, Reactor Building Ventilation Failure.

A. (1) has (2) will B. (1) has (2) will NOT C. (1) has NOT (2) will D. (1) has NOT (2) will NOT

ILT 2204 Written Exam 86

86.

Unit 2 Operators have entered 2-EOI-1A, ATWS RPV CONTROL, with the following conditions:

  • Reactor Power indicates 10%
  • ALL SCRAM inlet/outlet blue lights are EXTINGUISHED Given the conditions above and in accordance with 2-EOI-1A, ATWS RPV CONTROL, the Recirc Pumps (1) required to be tripped.

To mitigate this condition, the NUSO will direct (2).

Note: 2-EOI Appendix-1A, Removal and Replacement of RPS SCRAM Solenoid Fuses 2-EOI Appendix-1F, Manual SCRAM A. (1) are (2) 2-EOI Appendix-1A B. (1) are (2) 2-EOI Appendix-1F C. (1) are NOT (2) 2-EOI Appendix-1A D. (1) are NOT (2) 2-EOI Appendix-1F

ILT 2204 Written Exam 87

87.

Unit 2 was operating at 100% RTP while performing the 2-SR-3.5.3.3, RCIC Comprehensive Pump Test surveillance when the following occurred:

  • RCIC exhaust line disc rupture occurs
  • RCIC failed to automatically isolate and attempts to manually isolate RCIC are unsuccessful Steam Leak Detection panel indications (Panel 2-9-21) are as follows:
  • 2-TI-71-41A at 205 F and rising
  • 2-TI-71-41B at 243 F and rising
  • 2-TI-71-41C at 256 F and rising No other temperature indicators are in alarm.

In accordance with EOIs, the NUSO will direct the crew to _________.

[REFERENCE PROVIDED]

A. SHUT DOWN the Reactor using 2-GOI-100-12A B. EMERGENCY DEPRESSURIZE using 6 ADS valves C. DELIBERATELY LOWER Reactor Pressure to 500 - 600 psig D. RAPIDLY DEPRESSURIZE using Main Turbine Bypass Valves

ILT 2204 Written Exam 88

88.

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

  • The next fuel bundle to be moved is currently located in the Spent Fuel Pool and is designated for Reactor Cavity position 10-15
  • As the respective fuel bundle is grappled, SRM C fails downscale and is declared INOPERABLE
  • ALL other SRMs are OPERABLE Given the conditions above, fuel moves in accordance with Tech Specs and 0-GOI-100-3C, Fuel Movement Operations During Refueling.

[REFERENCE PROVIDED]

A. CAN continue since the SRM in the AFFECTED core quadrant is OPERABLE B. CANNOT continue since the SRM in the AFFECTED core quadrant is INOPERABLE C. CANNOT continue since the SRMs in the ADJACENT core quadrants are INOPERABLE D. CAN continue since the SRMs in the AFFECTED AND AN ADJACENT core quadrant are OPERABLE

ILT 2204 Written Exam 89

89.

Unit 3 is operating at 100% RTP when an event occurs with the following conditions:

  • Drywell Pressure PEAKED at 15 psig Given the conditions above, (1) EDGs have started.

Subsequently, the following conditions are observed:

  • 3A EDG is manually tripped due to an oil leak To restore power to 3A 4KV Shutdown Board, the NUSO will direct re-energizing the board by aligning (2).

Note: 0-OI-82, Standby Diesel Generator System 0-AOI-57-1A, Loss of Offsite Power (161 and 500 KV)/Station Blackout A. (1) ALL (2) A EDG in accordance with 0-OI-82 B. (1) ALL (2) 3B EDG in accordance with 0-AOI-57-1A C. (1) ONLY Unit 3 (2) A EDG in accordance with 0-OI-82 D. (1) ONLY Unit 3 (2) 3B EDG in accordance with 0-AOI-57-1A

ILT 2204 Written Exam 90

90.

A leak from the Unit 2 Loop II Core Spray Room Cooler has resulted in the following:

  • CORE SPRAY LOOP II PUMP ROOM FLOOD LEVEL HIGH, (2-9-4C, Window 31), is in alarm

A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT 31 CORE SPRAY LOOP II PUMP ROOM FLOOD LEVEL HIGH 2-LA-77-25B

ILT 2204 Written Exam 91

91.

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

At 0600 on 5/16/22:

  • 3-FCV-69-1, RWCU INBOARD SUCTION ISOLATION VALVE indicates closed
  • 3-FCV-69-2, RWCU OUTBOARD SUCTION ISOLATION VALVE indicates open
  • 3-FCV-69-12, RWCU RETURN ISOLATION VALVE indicates open At 0615 on 5/16/22:

[REFERENCE PROVIDED]

A. (1) A ONLY (2) 1000 B. (1) A ONLY (2) 1015 C. (1) A AND B (2) 1000 D. (1) A AND B (2) 1015

ILT 2204 Written Exam 92

92.

Unit 2 is operating at 50% RTP when the following conditions occur:

  • Reactor Steam Dome Pressure is 850 psig and lowering
  • Prior to Operators performing any manual actions, the Reactor SCRAMs The SCRAM occurred directly from a (1) signal.

A (2) report to the NRC is required in accordance with NPG-SPP-3.5, Regulatory Reporting Requirements.

[REFERENCE PROVIDED]

A. (1) Reactor Pressure (2) 4 Hour B. (1) Reactor Pressure (2) 8 Hour C. (1) MSIV position (2) 4 Hour D. (1) MSIV position (2) 8 Hour

ILT 2204 Written Exam 93

93.

All 3 Units are operating at 100% RTP when the following conditions occur:

At 0845:

  • BFN entered 0-AOI-100-7, Severe Weather
  • Core Spray Pump 1B and 1D are tagged for scheduled maintenance An AUO is dispatched to start (1) EDG Exhaust Fan(s) for each EDG room At 0900:
  • The AUO reports that for the A EDG, neither fan can be placed in service In accordance with Tech Specs, Unit 1 entry in LCO 3.0.3 is required at (2).

[REFERENCE PROVIDED]

A. (1) BOTH (2) 0900 B. (1) BOTH (2) 1300 C. (1) ONLY one (2) 0900 D. (1) ONLY one (2) 1300

ILT 2204 Written Exam 94

94.

Unit 3 is in MODE 1 when the following conditions occur:

At 1000 on 5/01/22:

  • MAIN STEAM LINE CH B FLOW HIGH (3-9-5B, Window 19) alarms due to a failed pressure transmitter The setpoint for the above alarm is (1) of rated steam flow.

In accordance with Tech Spec 3.3.6.1, the REQUIRED ACTION is to enter MODE 3 at 2200 on (2).

[REFERENCE PROVIDED]

A. (1) 135%

(2) 5/01/22 B. (1) 135%

(2) 5/02/22 C. (1) 200%

(2) 5/01/22 D. (1) 200%

(2) 5/02/22 19 MAIN STEAM LINE CH B FLOW HIGH

ILT 2204 Written Exam 95

95.

In accordance with 0-OI-65, Standby Gas Treatment System (SGT), it is PREFERRED to START SGT from the (1) Main Control Room(s).

In accordance with Tech Spec Bases, following a Design Basis Accident, a MINIMUM of (2) SGT train(s) are required to maintain a (-) 0.25 inches water while providing the design flow of 12000 cfm.

A. (1) Unit 3 (2) 1 B. (1) Unit 3 (2) 2 C. (1) Unit 1 AND Unit 2 (2) 1 D. (1) Unit 1 AND Unit 2 (2) 2

ILT 2204 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 2204 Written Exam 97

97.

In accordance with 2-OI-27, Condenser Circulating Water (CCW) System, 2-FCV-77-61, RADWASTE DISCHARGE VALVE to Unit 2 CCW discharge tunnel cannot be opened without a minimum of 2 CCW pumps operating on (1).

In accordance with 0-SI-4.8.A.1-1, Liquid Release Permit, if 0-RM-90-130, RADWASTE EFFLUENT RADIATION MONITOR, is found NONFUNCTIONAL during a release, then the release (2).

A. (1) Unit 2 (2) is no longer valid and a new release permit is required B. (1) Unit 2 (2) may continue if an independent verification of the valve lineup and release calculation is immediately performed C. (1) Any Unit (2) is no longer valid and a new release permit is required D. (1) Any Unit (2) may continue if an independent verification of the valve lineup and release calculation is immediately performed

ILT 2204 Written Exam 98

98.

The MINIMUM required Emergency Classification for entering 0-EOI-4, Radioactivity Release Control, is a/an (1).

During implementation of 0-EOI-4 and in accordance with the EOI Program Manual Bases, operation of Turbine Building Ventilation preserves (2).

Note: Notification of Unusual Event (NOUE)

A. (1) NOUE (2) equipment operability B. (1) NOUE (2) building accessibility C. (1) ALERT (2) equipment operability D. (1) ALERT (2) building accessibility

ILT 2204 Written Exam 99

99.

Site Security personnel are currently engaged with a hostile force in the Turbine Building breezeway and a TVA spokesman has made an official announcement to the public and news agencies regarding the ongoing event.

Given the condition above and in accordance with security procedures, site personnel will be notified to (1).

In accordance with NPG-SPP-03.5, Regulatory Reporting Requirements, the FIRST report is required to be made to the NRC within (2).

[REFERENCE PROVIDED]

A. (1) evacuate (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. (1) evacuate (2) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C. (1) shelter in place (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D. (1) shelter in place (2) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

ILT 2204 Written Exam 100 100. The Shift Manager / Site Emergency Director (SM/SED) has declared a General Emergency.

The Central Emergency Control Center (CECC) is NOT staffed.

Besides classification, which ONE of the following duties can NOT be delegated to another emergency team member by the SM/SED in accordance with Emergency Plan procedures?

A. Notifications to the State.

B. Notifications to Site Personnel.

C. Conducting Site Accountability Actions.

D. Determining Protective Action Recommendations.

BFN ILT 2204 SRO References as of 1/31/2022 Verify ALL (1) hr / immediately are redacted REFERENCE PROVIDED to candidate

77. EPIP-1, Attachment 1, COLD INITIATING CONDTIONS-MODES 4-5-DEFUELED
78. EPIP-1, Attachment 1, COLD INITIATING CONDTIONS-MODES 4-5-DEFUELED
80. 2-EOI-5, CURVES AND CAUTIONS Caution 1 Instrument Level Table, Curve 5, Drywell Spray Initiation Limit
82. EPIP-1, Attachment 1, HOT INITIATING CONDTIONS-MODES 1-2-3
83. Unit 3 Tech Spec 3.3.2.2 (No Bases),

3-LI-3-208A, B, C, D - REACTOR WATER LEVEL NORMAL NARROW RANGE

85. REACTOR BUILDING VENTILATION ABNORMAL (1-9-3D, Window 3),

REACTOR ZONE DIFFERENTIAL PRESSURE LOW (1-9-3D, Window 32)

87. 2-EOI-3, Table SC-1
88. 0-GOI-100-3C, Attachment 14 (Page 1 of 1) Core Quadrants
90. CORE SPRAY LOOP II PUMP ROOM FLOOD LEVEL HIGH, (2-9-4C, Window 31)
91. Unit 3 Tech Spec 3.6.1.3 (No Bases) and Unit 3 TRM 3.4.1 (No Bases)
92. NPG-SPP-3.5 Attachment 1 (Page 1 through 18)
93. Unit 1 Tech Spec 3.8.1 (No Bases) and Unit 1 Tech Spec 3.5.1 (No Bases)
94. Unit 3 Tech Spec 3.3.6.1 (No Bases), MAIN STEAM LINE CH B FLOW HIGH (3-9-5B, Window 19)
99. NPG-SPP-3.5 Attachment 1 (Page 1 through 18), EPIP-1, Attachment 1, HOT INITIATING CONDTIONS-MODES 1-2-3

Signature:

Date:

Name:

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