Text

Initial Exam 2011-301 Final SRO Written Exam with References
	ML110760682
Person / Time
Site:	Browns Ferry
Issue date:	01/17/2011
From:	; NRC/RGN-III/DRS/OLB
To:	; Tennessee Valley Authority
References
	50-259/11-301, 50-260/11-301, 50-296/11-301
	Download: ML110760682 (60)
	v • d • e

ILT 1102 Written Exam

76. Unit 1 was at 100% Reactor Power when Reactor Recirc Pump lAtripped. Total Core Flow indication lowered to 50%.

Which ONE of the following completes the statements below?

Following the trip, APRM Flow Biased Scram set point will be_(1)_ Simulated Thermal Power.

The APRM Flow Biased Simulated Thermal Power HIGH setpoint is required to be adjusted to Single Loop allowable value within a MAXIMUM of _(2)_ in accordance with T.S. 3.4.1, Recirculation Loops Operating.

A. (1)92%

(2) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B. (1)92%

(2) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C. (1)98%

(2)12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D. (1)98%

(2) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 76

ILT 1102 Written Exam

77. Which ONE of the following completes the statement below?

In accordance with the Unit 1 Bases for Tech Spec 3.3.1.1 RPS Instrumentation, an RPS actuation is required as a result of Turbine Stop Valve Closure above a MINIMUM Reactor Power of _(1 )_ to ensure the _(2)_ Safety Limit is not exceeded.

A. (1)25%

(2) Reactor core MCPR B. (1)25%

(2) Reactor Coolant System RPV Pressure C. (1)30%

(2) Reactor core MCPR D. (1)30%

(2) Reactor Coolant System RPV Pressure 77

ILT 1102 Written Exam

78. Unit 3 was operating at 100% Reactor Power when the following occurred:

Main Control Room evacuation is required due to a fire in the Control Bay

The Backup Control Panel is manned twenty-five (25) minutes after evacuation of the Main Control Room

The Unit Supervisor is informed that ONE SRV is continuously open AND a second SRV is cycling periodically Which ONE of the following completes the statements below?

Based on the SRV status, Reactor Power is currently between _(1)_.

In accordance with EPIP-1, Emergency Plan Implementing Procedure, the HIGHEST emergency action level classification that is required for these conditions is a (an) _(2)_.

A. (1)6%andl4%

(2) Alert B. (1) 15% and 23%

(2) Alert C. (1)6%andl4%

(2) Site Area Emergency D. (1) 15% and 23%

(2) Site Area Emergency 78

ILT 1102 Written Exam

79. Unit 1 RHR 1A is in Shutdown Cooling with Reactor Coolant temperature at 180° F. The Drywell Equipment Hatch is open. A leak on RHR Loop I results in the following:

RHR LOOP I PUMP ROOM FLOOD LEVEL HIGH, (1-9-4C, Window 17), is in alarm

RHR Loop I is secured AND isolated

RHR Loop Ills placed in service

Reactor Coolant Temperature is now 2150 F Which ONE of the following completes the statements below?

Entry into 1-EOl-3, Secondary Containment Control, _(1)_ required.

In accordance with EPIP-1, Emergency Plan Implementing Procedure, _(2)_.

[REFERENCE PROVIDED]

A. (1)is (2) Emergency Action Level for an Alert is met B. (1)is (2) Emergency Action Level for a Site Area Emergency is met C. (1)is NOT (2) Emergency Action Level for an Alert is met D. (1)is NOT (2) Emergency Action Level for a Site Area Emergency is met 79

ILT 1102 Written Exam

80. Unit 3 was operating at 100% Reactor Power, when a leak in the Drywell resulted in the following conditions:

Drywell Pressure is 57 psig and rising

Suppression Chamber Pressure is 56 psig and rising

Suppression Pool Level is 15 feet

Drywell Radiation is 2500 RJHr

Reactor Water Level lowered to (-) 180 inches and is now (-) 170 inches and rising Which ONE of the following identifies the required procedure to vent the Primary Containment AND the release rate requirements during the venting process in accordance with 3-EOI-2, Primary Containment Control?

A. 3-EOI-APPENDIX-1 2, Primary Containment Venting; vent irrespective of offsite release rates B. 3-EOl-APPENDIX-1 2, Primary Containment Venting venting MUST be secured if approaching General Emergency Release Rate Limits C. 3-EOl-APPENDIX-13,Emergency Venting Primary Containment; vent irrespective of offsite release rates D. 3-EOl-APPENDIX-13,Emergency Venting Primary Containment; venting MUST be secured if approaching General Emergency Release Rate Limits 80

ILT 1102 Written Exam

81. Given the following plant conditions on Unit 3:

A steam line break has occurred inside the Drywell

ALL Reactor Water Level (RWL) instruments display erratic indication

Reactor Pressure AND Drywell Temperature are in the Action Required region of RPV Saturation Curve 8 Which ONE of the following completes the statement below?

The Unit Supervisor must select EOI flowchart _(1 )_ for these conditions and raise injection to establish Reactor Pressure to a MINIMUM of _(2)_ above Suppression Chamber Pressure.

A. (1) 3-0-4, RPV Flooding (2) 70 psig B. (1) 3-C-2, Emergency Depressurization (2) 70 psig C. (1) 3-0-4, RPV Flooding (2) 90 psig D. (1) 3-0-2, Emergency Depressurization (2) 90 psig 81

ILT 1102 Written Exam

82. Unit 1 is at 100% Reactor Power:

Main Steam Line radiation levels are greater than three times normal full power background

OG AVG ANNUAL RELEASE RATE EXCEEDED 1-RA-90-157C, (1-9-40, Window

27) is in alarm Which ONE of the following completes the statement below?

The direction AND criteria to CLOSE MSIVs is contained in _(1)_ AND is based upon a determination that (2)_.

A. (1) 0-EOl-4, Radioactivity Release Control (2) releases are still in excess of Offsite Dose Calculation Manual limits B. (1) Alarm Response Procedure 1-9-3A, Window 27 Section for MAIN STEAM LINE RADIATION HIGH-HIGH (2) releases are still in excess of Offsite Dose Calculation Manual limits C. (1) 0-EOI-4, Radioactivity Release Control (2) the reactor will remain subcritical without boron under all conditions D. (1) Alarm Response Procedure 1-9-3A, Window 27 Section for MAIN STEAM LINE RADIATION HIGH-HIGH (2) the reactor will remain subcritical without boron under all conditions 82

ILT 1102 Written Exam

83. UNIT 2 was at 100% Reactor Power when an accident resulted in the following conditions:

Main Steam Tunnel Temperature in the Turbine Building is 298 °F and rising.

Main Steam Tunnel Temperature in the Reactor Building is 190 °F and rising.

Main Steam Line C Inboard AND Outboard MSIVs can NOT be closed.

Gaseous Release Rate Stack Noble Gas (WRGERMS) reading has been 6 x 1010 pCi/sec for 16 minutes.

NO Offsite Emergency Response Facilities are operational.

Which ONE of the following completes the statements below?

In accordance with the EOIs, Emergency Depressurization (1)_ required to be performed for these conditions.

The Shift Manager / Site Emergency Director _(2)_ delegate the determination of Protective Action Recommendation.

[REFERENCE PROVIDED]

A. (1)is (2) can B. (1)is NOT (2) can C. (1)is (2) CANNOT D. (1)isNOT (2) CANNOT 83

ILT 1102 Written Exam

84. A leak into Unit 2 Suppression Pool has resulted in the following indications:

At 0200 Suppression Pool Level is (-) 3 inches and rising at 1 inch per hour Which ONE of the following completes the statements below?

The Tech Spec Limit for 3.6.2.2, Suppression Pool Level, will be reached at (1).

The bases of the Tech Spec Suppression Pool upper level limit is to (2)_ during a DBA LOCA.

A. (1)0315 (2) ensure that peak primary containment pressure does not exceed maximum allowable values B. (1)0315 (2) prevent excessive clearing loads from S/RV discharges and excessive pool swell loads C. (1)0400 (2) ensure that peak primary containment pressure does not exceed maximum allowable values D. (1)0400 (2) prevent excessive clearing loads from S/RV discharges and excessive pool swell loads 84

ILT 1102 Written Exam

85. Unit 3 was operating at 100% Reactor Power. RHR Pump 3B was tagged out for planned maintenance at 0600 on 1/13/11.

At 1000 on 1/14/11, a RCIC steam line leak occurred in the Reactor Building resulting in a trip of Loop I Core Spray Room Cooler.

Based on these conditions, which ONE of the following identifies the LATEST time that Unit 3 must be in Mode 3 in accordance with Tech Spec 3.5.1, ECCS-Operating?

[REFERENCE PROVIDED]

A. 2200on 1/14/11 B. 2300on 1/14/11 C. l800on 1/20/11 D. 2200on 1/21/11 85

ILT 1102 Written Exam

86. Unit 1 has experienced a Loss of Offsite Power concurrent with a LOCA. Multiple equipment failures have resulted in need for RHR Crosstie to be lined up for injection into the reactor.

Which ONE of the following completes the statements below?

Unit I RHR can be crosstied to Unit 2 RHR (1)_.

The Unit 2 RHR Pump Suction Valve interlocks must be defeated in accordance with

_(2).

A. (1)Loopl (2) 2-01-74, Residual Heat Removal System B. (1)Loopl (2) 1-EOl Appendix 7C, Alternate RPV Injection System Lineup RHR Crosstie C. (1)Loopll (2) 2-01-74, Residual Heat Removal System D. (1) Loop II (2) 1-E0I Appendix 7C, Alternate RPV Injection System Lineup RHR Crosstie 86

ILT 1102 Written Exam

87. The following conditions exist on Unit 3:

Reactor Power is 100%

Emergency Diesel Generator 3EA is tagged out of service The following sequence of events occur:

1130 ALL Offsite power is lost and NO Unit 3 EDGs tie to their associated Board

1140 EDG 3EB started and tied to its associated Board

1145 EDG 3EB Output Breaker trips open and cannot be closed

1155 EDG 3EC started and tied to its associated Board

1205 EDG 3EB Output Breaker is repaired and subsequently closed Which ONE of the following identifies the HIGHEST emergency classification required AND who the Site Emergency Director should notify within five minutes of classifying the event?

[REFERENCE PROVIDED]

A. Alert; Operations Duty Specialist B. Alert; State of Alabama C. Site Area Emergency; Operations Duty Specialist D. Site Area Emergency; State of Alabama 87

ILT 1102 Written Exam

88. Unit 3 is at 100% Reactor Power. Standby Gas Treatment System (SGTS) A was tagged out of service on 1/16/11 at 0600. SGTS B has been manually started. At 1000 on 1/16/11, a container is removed from the Unit 3 Spent Fuel Pool (SFP) resulting in the following Refuel Zone Radiation Monitor indications:

3-RM-90-140 Detector A is reading 73 mr/hr

3-RM-90-140 Detector B is reading 72 mr/hr

3-RM-90-141 Detector A is reading 71 mr/hr

3-RM-90-141 Detector B is reading 71 mr/hr SGTS C did NOT start. The container was placed back in the SFP AND Refuel Zone Radiation Monitor indications returned to normal.

Which ONE of the following completes the statements below?

A Tech Spec required shutdown condition must be entered at _(1) in accordance with Tech Spec 3.6.4.3, Standby Gas Treatment System.

A _(2)_ hour report to the NRC is required when the shutdown is commenced.

[REFERENCE PROVIDED]

A. (1)l000onl/16/11 (2) four B. (1) 0600 on 1/23/11 (2)four C. (1) 1000 on 1/16/11 (2) one D. (1)O6000n 1/23/11 (2) one 88

ILT 1102 Written Exam

89. With Unit 1 Operating at 100% Reactor Power, a Loss of Offsite Power occurs.

Which ONE of the following completes the statements below?

In accordance with Tech Spec 3.8.1 Bases, AC Sources Operating, on a Loss of Offsite Power, the MAXIMUM allowed time for Emergency Diesel Generators to energize their associated Shutdown Boards is _(1)_ seconds.

Direction to reset EECW to Control Air Compressors is contained in_(2)_.

A. (1)7 (2) 0-AOl-32-1, Loss of Control and Service Air Compressors B. (1)10 (2) 0-AOl-32-1, Loss of Control and Service Air Compressors C. (1)7 (2) 0-AOl-57-1A, Loss of Offsite Power (161 and 500 KV)/Station Blackout D. (1)10 (2) 0-AOl-57-IA, Loss of Offsite Power (161 and 500 KV)/Station Blackout 89

ILT 1102 Written Exam

90. Unit 3 is at 100% Reactor Power. Plant Control Air has been aligned to Drywell Control Air to allow maintenance on the Nitrogen Storage Tanks.

Which ONE of the following completes the statement below?

Technical Requirements Manual Section 3.6.3, Drywell Control Air System, requires Reactor Thermal Power be reduced to less than or equal to _(1) power within _(2)_ if Plant Control Air is being used to supply the pneumatic control system inside primary containment.

A. (1)15%

(2) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B. (1)15%

(2) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C. (1)25%

(2)12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D. (1)25%

(2) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 90

ILT 1102 Written Exam

91. Which ONE of the following completes the statements below?

Tech Spec 3.3.1.1, Reactor Protection System (RPS) Instrumentation AND its associated Bases for the Reactor Vessel Water Level - Low, Level 3 setpoint is to prevent significant carryunder _(1 )_.

If this function is lost due to TWO inoperable channels in a trip system, then RPS trip capability must be restored (2)_.

A. (1) to ensure the accuracy of core DIP and level instrumentation (2) Immediately B. (1) to ensure the accuracy of core DIP and level instrumentation (2) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months C. (1) to protect available Reactor Recirc Pump Net Positive Suction Head (2) Immediately D. (1) to protect available Reactor Recirc Pump Net Positive Suction Head (2) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 91

ILT 1102 Written Exam

92. The following alarms AND indications exist on Unit 3:

DRYWELL PRESS HIGH, (3-9-3B, Window 23), is in alarm

REACTOR VESSEL WTR LVL CH A LOW-LOW-LOW (3-9-5B, Window 4), is in alarm

REACTOR VESSEL WTR LVL CH B LOW-LOW-LOW (3-9-5B, Window 5), is in alarm

DRYWELL EQPT DR SUMP PUMP EXCESSIVE OPRN, (3-9-4B, Window 11), is in alarm

Drywell Floor Drain Leakage is calculated at 100 gpm

Group 1 PCIS Logic A Success light is NOT illuminated

ALL other PCIS Logic Success lights are illuminated

Dose equivalent lodine-131 sample results indicate 16 pCi/gm Which ONE of the following completes the statement below?

These alarms AND indications establish that A. a loss of the Fuel Clad Barrier ONLY exists B. a loss of the Reactor Coolant System Barrier ONLY exists C. a loss of the Reactor Coolant System Barrier AND Fuel Clad Barrier ONLY exists D. a loss of the Containment Barrier AND Reactor Coolant System Barrier ONLY exists 92

ILT 1102 Written Exam

93. Unit 3 is operating at 100% Reactor Power. Offgas Hydrogen Analyzer 3A was tagged out for planned maintenance at 0600 on 1/13/11.

At 0700 on 1/13/11, the Unit Supervisor discovers an error on Offgas Hydrogen Analyzer 3B Surveillance completed at 0400 on 1/13/11. Based on the corrected calculation, Offgas Hydrogen Analyzer 3B alarm setpoint is set too high to ensure the limit of TRM LCO 3.7.2 is not exceeded.

Which ONE of the following completes the statements below?

In accordance with TR 3.7.2, Airborne Effluents, the concentration of hydrogen in Offgas downstream of the recombiners shall be limited to a MAXIMUM of _(1)_. In accordance with TR 3.3.9, Offgas Hydrogen Analyzer Instrumentation, Condition A must be entered with a start time of (2)_ on 1/13/11.

[REFERENCE PROVIDED]

A. (1)1%

(2) 0600 B. (1)1%

(2) 0700 C. (1)4%

(2) 0600 D. (1)4%

(2) 0700 93

ILT 1102 Written Exam

94. Which ONE of the following completes the statements below for Shift Turnover AND Control Board walk down requirements in accordance with OPDP-1 ,Conduct of Operations?

During shift turnover, the oncoming Shift Manager _(1 )_ required to walk down the Control Boards with an off going RO or SRO.

The Unit Supervisor must walk down Main Control Room panels _(2)_.

A. (1)is (2) once prior to mid shift brief AND once prior to end of shift turnover B. (1)is NOT (2) once prior to mid shift brief AND once prior to end of shift turnover C. (1)is (2) once every hour during power operations with a 25% grace period D. (1)isNOT (2) once every hour during power operations with a 25% grace period 94

ILT 1102 Written Exam

95. In accordance with OPDP-10, License Status Maintenance, Reactivation and Proficiency for Non-Licensed Operators, which ONE of the following completes the statements for License Reactivation requirements?

Licensee requalification training must be verified current _(1) 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions under instruction.

When ALL Reactivation requirements are met, the Licensed individual is authorized to resume licensed activities by the _(2)_.

A. (1) prior to standing (2) Plant Manager B. (1) prior to standing (2) Site Licensing Manager C. (1) after standing (2) Plant Manager D. (1) after standing (2) Site Licensing Manager 95

ILT 1102 Written Exam

96. Which ONE of the following completes the statements below?

If the criteria is met (in accordance with TS Section 1.3, Completion Times) to apply a Completion Time extension, the total Completion Time allowed for completing a Required Action shall be limited to the (1)_ restrictive of either:

The stated Completion Time, as measured from the initial entry into the Condition, plus an additional (2)_ OR the stated Completion Time as measured from discovery of the subsequent inoperability.

A. (1)more (2) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B. (1) less (2) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months C. (1)more (2) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months D. (1) less (2) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 96

ILT 1102 Written Exam

97. A seismic event has resulted in the following Unit 2 plant conditions:

ALL control rods are fully inserted

RPV level is (-)1 50 inches and lowering slowly

RPV pressure is 875 psig with a cooldown in progress at <90 °F/hr

RHR Loop II is lined up for Drywell Spray

ALL other ECCS systems are unavailable

Drywell pressure is 4.8 psig and lowering

ADS has been inhibited in accordance with 2-EOl-1, RPV Control step RCIL-7 Which ONE of the following describes the required actions to mitigate this event?

A. Enter 2-EOl-C1, Alternate Level Control and direct performance of 2-EOl-Appendix 6A, Injection Subsystems Lineup Condensate.

B. Enter 2-EOI-C1, Alternate Level Control and direct performance of 2-EOI-Appendix 5A, Injection System Lineup Condensate/Feedwater.

C. Enter 2-EOl-C2, Emergency Depressurization and direct performance of 2-EOl-Appendix 6A, Injection Subsystems Lineup Condensate.

D. Enter 2-EOI-C2, Emergency Depressurization and direct performance of 2-EOl-Appendix 5A, Injection System Lineup Condensate/Feedwater.

97

ILT 1102 Written Exam

98. Which ONE of the following completes the statements below in accordance with 1-GOl-200-2, Primary Containment Initial Entry and Closeout?

Initial Drywell Entry with the Reactor at Power must be approved by the _(1)_.

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 ONLY (2) Rad Protection B. (1) Shift Manager AND Plant Manager (2) Rad Protection C. (1) Shift Manager ONLY (2) Operations D. (1) Shift Manager AND Plant Manager (2) Operations 98

ILT 1102 Written Exam

99. In accordance with RCDP-3, Administration of Radiation Work Permits, for normal and emergency situations, which ONE of the following completes the statements below?

During NORMAL situations, RADPRO Supervision _(1)_ authorize short term deviation from RWP requirements (for example, verbally requiring additional protective clothing),

without revising the RWP.

If the Shift Manager authorizes IMMEDIATE entry into a High Radiation Area during emergency situations, then RADPRO escort _(2)_.

A. (1)may (2) is still required B. (1)mayNOT (2) is still required C. (1) may NOT (2) is NOT required D. (1)may (2) is NOT required 99

ILT 1102 Written Exam 100. With an ATWS, Emergency Operating Instructions (EOls) require operators to reduce Recirc Pump speeds to minimum prior to tripping them if Reactor Power is above 5%.

Which ONE of the following identifies the (1) bases for this action AND (2) the EOI leg which requires it?

A. (1) To allow time for ARI to actuate thus allowing the Recirc Pumps to stay in operation for coolant circulation.

(2) C-5, Level / Power Control B. (1) To allow time for ARI to actuate thus allowing the Recirc Pumps to stay in operation for coolant circulation.

(2) EOl-l, RPV Control, RC/Q leg C. (1) To prevent tripping the turbine on high water level AND exceeding the capacity of the bypass valves.

(2) C-5, Level / Power Control D. (1) To prevent tripping the turbine on high water level AND exceeding the capacity of the bypass valves.

(2) EOI-I, RPV Control, RC/Q leg 100

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SRO REFERENCES PROVIDED 13 EOI Curve 1 &2Rev.8 14 EOI Caution 1 I Curve 8 28 2-LI-3-52162 Correction Curve 49 DG KWvs. KVAR LOADING 0-01-82 Rev. 112 Illustration I 79 EPIP-I Rev. 46 Matrix Sect. I (Minimum Re-flood Pressures blanked out) 83 EPIP-I Rev. 46 Matrix Sect. 4 85 U3 TS 3.5.1 ECCS 87 EPIP-1 Rev. 46 Matrix Sect. 5 88 U3 TS 3.6.4.3 SGTS 93 U3 TR 3.3.9 Offgas H2 Analyzer

CURVE 1 CS NPSH LIMITS 250 230 1OFSIGSAFEi 210 5PSISAFE*

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90 500 1500 2500 3500 4500 CS PUMP FLOW (GPM) *SUPPR CHMBR PRESS CURVE 2 RHR NPSH LIMITS 245 15 SAFE*

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CAUTIONS CAUTION #1

AJ4 RPV WATER LVL INSTRUMENT MAY BE USED TO DETERMINE OR TREND LVL Lj IT READS ABOVE THEMINIMUM INDICATED LVL ASSOCIATED WTH THE HIGHEST MAX OW OR SC RUN TEMP.

IF DWTEMPS. OR Sc AREATEMPS (IABLE 8),AS APPLICABLE, ARE OUTSIDE THE SAFE REGION OF C1JR[E8, THEASSOCIATED INSTRUMENT MAY BEUNRELIABLE DUE TO BOIUNG IN THE RUN.

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ON SCALE N/A BELOW 150

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08 800 OUTGOING 800 I

400 T :-

2O0 C 200 400 600 800 1000 1200 1400 1100 1800 2000 2200 2400 kVAR (Lagging or Outgoing)

BROWNS FERRY EMERGENCY CLASSIFICATION PROCEDURE I EVENT CLASSIFICATION MATRIX EPIP1 REACTOR 1.0 PAGE 17 OF 206 REVISION 46

BROWNS FERRY EMERGENCY CLASSIFICATION PROC EDU RE EVENT CLASSIFICATION MATRIX NOTES

1. 1-Ui/i 1 -Al Applicable when the Reactor Head is removed and the Reactor Cavity is flooded 1 .1S1 Applicable in Mode 5 when the Reactor Head is installed.

I 1-G2 The reactor will remain subcritical under all conditions without boron when:

Unit 1: All control rods are inserted to or beyond position 02.

Unit 2: Any 19 control rods are inserted to position 02, with all other control rods fully inserted.

Unit 3: Any 19 control rods are inserted to position 02, with all other control rods fully inserted.

All control rods except one are inserted to or beyond position 00.

Determined by Reactor Engineering.

CURVES!TABLES:

TABLE 1.1 G2 MINIMUM ALTERNATE RPV FLOODING PRESS (MARFP)

NUMBER OF OPEN MSRVs MARFP (PSIG)

SorMore 190 5 230 4 290 PAGE 18 OF 206 REVISION 46

RROWNS FERRY I EMERGENCY CLASSIFICATION PROCEDURE EVENT CL.ASSIFICATION MATRIX EPIP1 WATER LEVEL u*scription iOscnption 1.1-UI I INOTEI 1.1-U21 I I Uncontrolled water level decrease in Reactor Uncontrolled water level decrease in Spent Fuel Cavity with irradiated fuel assemblies expected to Pool with irradiated fuel assemblies expected to z remain covered by water, remain covered by water.

C I

m OPERATING CONDITION: OPERATING CONDITION Mode5 ALL 1.1-All INOTEI I.l-A21 I Uncontrolled water level decrease in Reactor Uncontrolled water level decrease in Spent Fuel Cavity expected to result in irradiated fuel Storage Pool expected to result in irradiated fuel assemblies being uncovered, assemblies being uncovered.

OPERATING CONDITION: OPERATING CONDITION:

Mode 5 ALL 1.1-SI I INOTEI 1.1-S21 I I Reactor water level can NOT be maintained Reactor water level can NOT be determined.

above -162 inches (TAF) rn m

C) m OPERATING CONDITION: OPERATING CONDITION:

ALL Modelor2or3 -<

1.1-Gil I.i-G21 INOTEITABLEIUS -

Reactor water level can NOT be restored and Reactoi water level can NOT be detennined maintained above -180 inches. AND Either of the following exists:

. The reactor will remain subcritical without boron under all conditions, and m Less than 4 MSRVs can be opened, or Z Reactor pressure can NOT be restored and m

maintained above SuppressTon Chamber pressure by at least

+ UNIT1 psi rn UNIT 2 psi

+ UNIT3 psi rn

. It has NOT been determined that the reactor will remain subcritical without boron under all conditions and unable to restore and maintain C)

MARFP in Table 1.1-02.

OPERATING CONDITION: OPERATING CONDITION:

Mode 1 or 2 or 3 Mode I or 2 or 3 PAGE 19 OF 206 REVISION 46

0 o z 01 C O 0

< m rn Cl) z a) 1 01 Ill I-m 6 m g

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m Cl, (t

a 0 1111111111 IJ

-n III 111111 I II IIIFi III III g hF Ii It C IF hII m rn rn a) 0 0

z 0)

BROWNS FERRY EMERGENCY CLASSIFICATION PROCEDURE EVENT CLASSIFICATION MATRIX EPIP-1 Reactor coolant activity exceeds 26 j.iCilgm dose equivalent 1-131 (Technical Specification Limits) z as determined by chemistry sample.

C I

F, OPERATING CONDITION Eli ALL z

-l 1.2-A I I NOTE I I 1.3-A I I I I Failure of RPS automatic scram functions to bring Reactor coolant activity exceeds 300 tCiIgm dose the reactor subcritical equivalent Iodine-131 as determined by chemistry AND sample.

I-Manual scram or ARI (automatic or manual) was (fl successful.

OPERATING CONDITION:

OPERATING CONDITION: Mode 1 or 2 or 3 Mode 1 or 2 1.2-S I INOTEI I I I I I Failure of automatic scram, manual scram, and Ci)

AR! to bring the reactor subcritical.

in m

G) in OPERATING CONDITION: z o

Model -<

1.2.0 ICURVEI I US I I I I Failure of automatic scram, manual scram, and ARI. Reactor power is above 3% C)

AND Either of the following conditions exists:

. Suppression Pool temp exceeds HCTL ni Referto Curve 1.2-G.

. Reactor water level can NOT be restored and maintained at or above -180 inches.

ni z

OPERATING CONDITION:

Modelor2 PAGE 21 OF 206 REVISION 46

,1 0

C) z 03 C 0

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FERRY EMERGENCY CLASSIFICATION PROCEDURE I EVENT CLASSIFICATION MATRIX EPIP1]

THIS PAGE INTENTIONALLY BLANK PAGE 24 OF 206 REVISION 46

o 0 z

0 m J r0 b

0>0 (fl-I p

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BROWNS FERRY I EMERGENCY CLASSIFICATION PROCEDURE I EVENTCLASSIFICAT)QNMATRIX EPIP-1 NOTES 4.1-U Pnorlo making this emergency dassif.calicn based upon the WRGE4Siridba1ion. assess the release byelther oithe *owVtg:

1.Acjl field measwemeri exceed the Qmits., t.Xle 4.1-U 10-SI 4.8.8. .3.1 release fraction exceeds 2.0 lfrieithe,-easment can be oonduid -in 60 rrint*es then the dedon mtbe made on Ihev.d WRGERMS ieacfrig.

4.1-A Pflorte making this emerge aWlcaticn based upon the WRGEiIS,ra1ion. assess the release by either ot the *o*lg:

1 Ac5ial field measements exceed the limks m talle 4.1-A l0.S14.8.B..a.l reeasefractionexoeeds2(X) if neither assessment can benducsed eel-in 16 n-mutes then the dedon rnustbe made on the akd WRGERMS reading.

4.1-S Prorto rnaidng this emeigencyass1lca1icn based upon the gaseous release rse indication. assess the release by ether cithe IbMng methods:

1. Actasi field measurements exceed the limes r table 4.1-S.

2 Pnected or dose assessments exceed 100 mrem TEDEor 500 m,emCDE.

If neither assessment can be ocnduid e*i 15 rreiuses then ti dec4araticn must be made based on the vakdiiRGERMS leading.

4.143 Prorte making this emergency dassticalicn based upon the gaseous release rase indication. assess the release byeiherctthe bng methods I .Actial field measurements exceed the ri table 4. I-G.

1 Pmected oractjai dose assessnwits exceed 1000 mrern TED cr5000 mrem CVE If neither assessment can be condued eli 15 rvwiutss then the dedaray must be made based on the vd WRGERMS reading.

rFABLES:

Table 4.1 -U RELEASE LIMITS FOR UNUSUAL EVENT TYPE MONITORING METHOD LIMIT DURATION t3aseous Release Rate Stack Noble Gas (WRGERMS} 2.88 X 10 7uCitsec 1 Hour Gaseous Release Rate 0-SI 4.8.8.1 .a.1 Release Fraction 2.0 1 Hour Site Boundary Radiation Reading Field Assessment Team 0.10 MREMIHR Gamma 1 Hour Table 4.1-A RELEASE LIMITS FOR i LERT TYPE mI.JN, I .JT%HTJ mc i IbJL, LIMIT DURATION Gaseous Release Rate Stack Noble Gas IWRGERMS) 2.88 X iuiisec 15 Minutes Gaseous Release Rate 0-SI 4.8.B. 1.a.1 Release Fraction 200 15 Minutes Site Boundary Radiation Reading Field Assessment Team 10 MREMFHR Gamma 15 Minutes Table 4.1 -S REI EASE LIMITS FOR SITE ARE L EMERGENCY TYPE .IJm .JmI mc i rIJI., LIMIT LUF?i IJl G.aseous Release Rate Stack Noble Gas (WRGERMS) s.o X 10 llCiIsec 15 Minutes Site Boundary Radiation Reading Field Assessment Team 100 MREMIHR Gamma 1 Hour Site Boundary Iodine131 Field Assessment Team 3.OX 10uCl/cm 3 1 Hour Table 4.1.6 RELEASE LIMITS FOR GENERAL EMERGENCY TLPE !tLONIT0RXNGIITHOD LI\fiT DURATION

° Gaseous Release Rate Stack Noble Gas WRGERMSLJ 5.9 X 10 IjCiIsec 15 Minutes Site Boundary Radiation Reading Field Assessment Team 1000 MREMIHR Gamma 1 Hour Site Boundary lodine-13 I Field Assessment Team 3.9 X 10 4 iCl 1 cm 3 1 Hour PAGE 40 OF 206 REVISION 46

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I I OWNS FERRY EMERGENCY CLASSIFICATION PROCEDURE EVENT CLASSIFICATION MATRIX E P I P-I THIS PAGE INTENTIONALLY BLANK PAGE 44 OF 206 REVISION 46

BROWNS FERRY EMERGENCY CLASSIFICATION PROCEDURE EVENT CLASSIFICATION MATRIX EPIP1 LOSS OF POWER 5.0 PAGE 45 OF 206 REVISION 46

BROWNS FERRY EMERGENCY CLASSIFICATION PROCEDURE EVENT CLASSIFICATION MATRIX NOTES 5.1-li Loss of normal and alternate supply voltage implies inability to restore voltage from any qualified source to normal or alternate feeder for at least one of the unit specific boards within 15 minutes. At least two boards must be energized from Diesel power to meet this cJassificafion If only one board can be energized and that board has only one source of power then refer to EAL 5.1-Al or 5. 1-A2.

5.1-At Only one source of power (Diesel or Offsite) is available to any one of the listed unit specific 4KV Shutdown Boards. No power is available to the three remaining boards.

5.1 -A2 Loss of voltage to all unit specific 4KV Shutdown Boards applies to those boards which normally supply emergency AC power to the affected unit only. Determination of the event classification depends on the affected unit operating mode. For units in operation 5.1-S would apply.

5.1-S Loss of voltage to all unit specific 4KV Shutdown Boards applies to those boards which normally supply emergency AC power to the affected unit only. Determination of the event classification depends on the affected unit operating mode. For units in Shutdown or Refuel 5. l-A2 would apply.

5.14 Loss of voltage to all unit specific 4KV Shutdown Boards applies to those boards which normally supply emergency AC power to the affected unit only.

CURVES/TABLES:

h.. Tabt* 5.1 UNIT 4KV SHUTDOWN BOARD APPLICABILITY APPLICABLE UNIT APPLICABLE 4KV SHUTDOWN BOARDS UNIT 1 A, B, C, and D UNIT2 A, B, C,andD UNIT 3 3A, 3B, 3C. and 3D PAGE 46 OF 20 REVISION 46

5ROWNS FERRY EMERGENCY CLASSIFICATION PROCEDURE I

I EVENT CLASSIFICATION MATRIX EPIP1 D.scrlptien Description 5,1-U I INOTEITABLEI US I I I I Loss of normal and alternate supply voltage to ALL unit specific 4KV shutdown boards from Table 5.1 z for greater than 15 minutes AND At least two Diesel Generators supplying power to c

unit specifIc 4KV shutdown boards listing in Table 5.1.

OPERATING CONDITION: m ALL 5.1-Al I I NOTE I TABLE I US 5.1-A2 I I NOTE I TABLE I US -

Loss of voltage to ANY THREE unit specific 4KV Loss of voltage to ALL unit specific 4KV shutdown shutdown boards from Table 5.1 for greater than boards from Table 5.1 for greater than 15 minutes.

15 minutes AND Only ONE source of power available to the 171 remaining board.

OPERATING CONDITION: OPERATING CONDITION:

Mode 1 or 2 013 Mode 4 or 5 or Defueled 5.1-S I INOTEITABLEI US I I I I Loss of voltage to ALL unit specific 4KV shutdown boards from Table 5.1 for greater than 15 minutes.

m m

m z

C, OPERATING CONDITION: -4 Model or2or3 5.1-G I INOTEITABLEI US I I I I Loss of voltage to ALL unit specific 4KV shutdown boards from Table 5.1 Iii AND m Either of the following conditions exists;

. Restoration of at least one 4KV shutdown board is NOT likely within three hours.

. Adequate core cooling can NOT be assured.

m z

OPERATING CONDITION.

Model or2or3 PAGE 47 OF 206 REVISION 46

BROWNS FERRY EMERGENCY CLASSIFICATION PROCEDURE EVENT CLASSIFICATION MATRIX NOTES 52 250V DC power voltage below 248 volts constitutes a loss of DC power to the affected board. The voltage readings may be obtained at the 250V Shutdown Battety Board (or the 250V Plant Battery Board) that is feeding the affected board CURVESITASLES:

Table 5.2-U UNIT 4KV SHUTDOWN BOARD APPLICABILITY APPLICABLE UNIT APPLICABLE 4KV SHUTDOWN BOARDS UNIT1 A,B,C,ANDD UNIT2 A,8,C,ANDD UNIT 3 3A, 38, 3C, AND 3D Tabi. 5.2-S CRITICAL DC POWER AND ESSENTIAL SYSTEMS COMBINATION LOSS OF CRITICAL 250V DC POWER POTENTIALLY RESULTS (Unit Specific Unless Otherwise Noted) IN Control Power for 4KV Unit Boards A, B, and C Loss of Main Condenser AND AND Control Power for 480V Unit Boards A and B Loss of Both EHC Pumps AND AND Power for Panel 9-9 Cabinet 1 Loss of All Reactor Feed Pumps Power for 250V DC RMOV Board A Loss of HPCI III Power for 250V DC RMOV Board C Loss of RCIC IV Power for 250V DC RMOV Boards A, B, and C Less than 4 MSRV5 AND AND Control Power for 4KV Shutdown Boards A, B, C, and D Loss of All RHR Pumps (4KV Shutdown Boards 3A, 38, 3C, arid 3D for Unit 3) And Core Spray Pumps PAGE 48 OF 206 REVISION 46

E BROWNS FERRY I

EMERGENCY CLASSIFICATION PROCEDURE EVENT CLASSIFICATION MATRIX EPIP-1 J LOSS OF 250V DC POWER u*scripuor -- - - -

5.2-U I I NOTE I TABLE I US I I I I Unplanned loss of 250V DC control power to ALL unit specitic 4KV shutdown boards from z Table 5.2-U for greater than 15 minutes OR Unplanned loss of 250V DC control power to unit specific 480V shutdown boards A and B for greater than 15 minutes.

m OPERATING CONDITION: Z Modes4or5 I I I I I I I I I r

m

-I 5.2-S I INOTEITABLEI US I I I I Loss of 250V DC power to ALL combinations (I, II, Ill, and IV) of essential systems from Table 52-S for greater than 15 minutes.

m m

u m

z C)

OPERATING CONDITION Mode 1 or 2013 I I I I I I I I G

m z

m I

I,,

m m

z C)

PAGE 49 OF 206 REVISION 46

8ROWNS FERRY EMERGENCY CLASSIFICATION PROCEDURE EVENT CLASSIFICATION MATRIX EPIP1 THIS PAGE INTENTIONALLY BLANK PAGE 50 OF 206 REVISION 46

ECCS Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS - Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurizatiori System (ADS) function of six safety/relief valves shall be OPERABLE.

APPLICABILITY: MODE 1.

MODES 2 and 3. except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.

ACTIONS LCO 3.0.4.b is not applicable to HPCI.

CONDITION REQU I RED ACTION COMPLETION TIME A. One low pressure ECCS A.1 Restore low pressure 7 days injection/spray subsystem ECCS injection/spray inoperable, subsystem(s) to OPERABLE status.

OR One low pressure coolant injection (LPCI) pump in both LPCI subsystems inoperable.

(continued)

BFN-UNIT 3 3.5-1 Amendment No. 212, 229, 244 December 1, 2003

ECCS Operating 3.5.1 ACTIONS (continuedi CONDITION REQUIRED ACTiON COMPLETION TIME B. Required Action and 8.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not NP met.

B.2 Be In MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

BFN-UNIT 3 3.5-la Amendment No. 244 December 1, 2003

ECCS Operating 3.5.1 ACTIONS (coritinuecfl CONDITION REQUIRED ACTION COMPLETION TIME C. HPCI System inoperable. C.1 Verify by administrative Immediately means RCIC System is OPERABLE.

AND C.2 Restore HPCI System to 14 days OPERABLE status.

D. HPCI System inoperable. D.1 Restore HPCI System to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

AND OR Condition A entered.

D.2 Restore low pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ECCS injection/spray subsystem to OPERABLE status.

E. One ADS valve E.1 Restore ADS valve to 14 days inoperable. OPERABLE status.

F. One ADS valve F.1 Restore ADS valve to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. OPERABLE status.

Condition A entered. F.2 Restore low pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ECCS injection/spray subsystem to OPERABLE status.

(continued)

BFN-UNIT 3 3.5-2 Amendment No. 242T 229 March 12. 2001

ECCS Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Two or more ADS valves G.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable.

AND OR G.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action and dome pressure to associated Completion 150 psig.

Time of Condition C, D.

E. or F not met.

H. Two or more low pressure H.1 Enter LCO 3.0.3. Immediately ECCS injection/spray subsystems inoperable for reasons other than Condition A.

OR HPCI System and one or more ADS valves inoperable.

BFN-UNIT 3 3.5-3 Amendment No. 2-1-27 229 March 12, 2001

SGT System 3.6.4.3 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 Three SGT subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SGT subsystem A.1 Restore SGT subsystem 7 days inoperable, to OPERABLE status.

B. Required Action and 6.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not met in MODE 1. 2. or 3.

6.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued>

BFN-UNIT 3 3.6-51 Amendment No. 24-2, 249 September 27, 2004

SGT System 3.6.4.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Place o OPERABLE Immediately associated Completion SGT subsystems in Time of Condition A not operation.

met during OPDRVs.

OR C.2 Initiate action to suspend Immediately OPDRVs.

D. Two or three SGT D.1 Enter LCO 3.0.3. Immediately subsystems inoperable in MODE 1, 2, or 3.

(continued)

BFN-UNIT 3 3.6-52 Amendment No.232, 249 September 27, 2004

SGT System 36.4.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two or three SGT E.1 Initiate action to suspend Immediately subsystems inoperable OPDRVs.

during OPDRVs.

BFN-UNIT 3 3.6-53 Amendment No. 242 249 September 27, 2004

Offgas Hydrogen Analyzer Instrumentation TR 3.3.9 TR 3.3 INSTRUMENTATION TR 3.3.9 Offgas Hydrogen Analyzer Instrumentation LCD 3.3.9 There shall be at least one OPERABLE Offgas Hydrogen Analyzer instrument with alarm setpoint set to ensure the limit of TRM LCD 3.7.2 is not exceeded.

APPLICABILITY: During main condenser offgas treatment system operation TRM LCD 3.0.3 is not applicable.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No OPERABLE Offgas A.1 Install a temporary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Hydrogen Analyzer monitor instruments.

OR A.2.1 Take grab samples 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of no OPERABLE AND instrument AND Every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter A.2.2 Analyze the sample for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following explosive concentration grab sample of hydrogen.

BFN-UNIT 3 3.3-54 TRM Revision 16 March 31, 2000

ML110760682

Text

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