question: i (1 point) · question: 6 (1 point) given the following unit 2 conditions: rcs cooldown...

Oconee Nuclear Station• 1LT46 ONSSRONRCExaminationQuestion: I

(1 point)

Given the following Unit 2 conditions:Initial conditions:

• Reactor power = 100%• Both MFDW Pumps tripped• 2RC-66 (PORV) has failed OPEN• Subcooling margin monitors indicate as follows:

o 2A Loop SCM = 18°F decreasingo 2B Loop SCM = 0°F stableo BOTH Core SCM = 12°F decreasing

1) Performing Rule 2 (Loss of SCM) _(1) required.

2) A reason RCPs are secured per Rule 2 is to _(2)_.

Which ONE of the following completes the statements above?

A. 1. is2. prevent pump damage that occurs from pumping a steam/water mixture

B. 1, is2. ensure RCP’s are secured before the RCS can evolve to a void fraction of>

70%

C. 1. is NOT2. prevent pump damage that occurs from pumping a steam/water mixture

D. 1, is NOT2. ensure RCP’s are secured before the RCS can evolve to a void fraction of>

70%

of 100

Oconee Nuclear Station• 1LT46 ONSSRONRCExaminationQuestion: 2

(1 point)

Given the following Unit 1 conditions:Time = 1200:00

• Reactor Power = 100%• RCS Pressure = 2100 psig decreasing• RBNS level increasing• Reactor Building RI/Vs are in alarm

Time = 1202:00• Rule 2 directs tripping ALL RCP’s due to SCM indications

Time = 1204:30• IAI RCP remains operating• 1A1 RCP Amps = 520 amps stable

1) In accordance with Rule 2 (Loss of SCM), at Time 1204:30 the 1A1 RCP shouldbe(1).

2) If ANY RCP cannot be secured by the associated RCP Breaker switch on 1 UB2,Rule 2 directs de-energizing _(2) 6900V bus(es).


A. 1. left running2. ONLY the associated

B. 1. left running2. BOTH

C. 1. secured2. ONLY the associated

D. 1. secured2. BOTH

of 100

Oconee Nuclear Station

Question:(1 point)

3IL T46 ONS SRO NRC Examination


• Time = 0400:00• Reactor Power 100%• RCS pressure 2100 psig rapidly decreasing• RB Pressure 0.3 psig rapidly increasing• Multiple RB RIA alarms

Current conditions:• Time = 0402:30• RCS pressure = 104 psig slowly decreasing• RB pressure = 16.2 psig slowly increasing• Operators have NOT adjusted the IA RBCU alignment

Which ONE of the following describes the lights that will be ILLUMINATED at Time0402:30 in the picture below?

..A CU

0

A. Damper RED light and RBCU GREEN light

B. Damper RED light and RBCU AMBER light

C. Damper GREEN light and RBCU GREEN light

D. Damper GREEN light and RBCU RED light

of 100

Oconee Nuclear Station• 1LT46 ONSSRONRCExamination

Question: 4(1 point)


• Reactor power = 80%• 1A Feedwater Flow 4.4 x 106 LB/HR• lB Feedwater Flow = 4.4 x 106 LB/HR

Current conditions:• 1B1 RCP trips

1) Reactor powerwill AUTOMATICALLY be reduced to a MAXIMUM of_ (1) _%

Core Thermal Power.

2) When the MAXIMUM power level is reached, a MFDW flow of approximately(2)_106 LB/HR will be established to the 1A Steam Generator.


A. 1.652. 5.4

B. 1.742. 5.4

C. 1.652, 6.1

D. 1.742. 6.1

Page4oflOO

Oconee Nuclear Station1LT46 ONSSRONRCExaminationQuestion: 5

(1 point)

1) When re-establishing seal injection flow to a RCP, the major concern with thermal shock tothe RCP seals is seal failure resulting in _(1)_.

2) The MINIMUM condition that would require entry into AP/14 (Loss Of Normal HPI Makeupand/or RCP Seal Injection) is loss of seal injection to _(2)_ RCP(s).


A. 1 excessive RCS leakage2. ANY

B. 1. excessive RCS leakage2. ALL

C. 1. RCP shaft binding2. ANY

D. 1. RCP shaft binding2. ALL

of 100

Oconee Nuclear Station• 1LT46 ONSSRONRCExaininationQuestion: 6

(1 point)

Given the following Unit 2 conditions:• RCS cooldown in progress• LPI aligned in the Series Mode

1) The reason Series Mode was developed for Unit 2 was to provide _(1)_.

2) A loss of the _(2)_ LPI Pumps would result in a total loss of Decay HeatRe mova

A. 1 a backup to the Switchover mode of LPI2. 2A and 2C

B. 1. a backup to the Switchover mode of LPI2. 2B and 20

0. 1. additional cooling capacity during 2/0 pump ops2. 2A and 20

D. 1 additional cooling capacity during 2/0 pump ops2. 2B and 20

1age 6 of 100


(1 point)

Given the following plant conditions:Time 1200:00

• Unit 1 100%• Unit2= MODE 5• A and B LPSW Pumps are operating

Time = 1205:00• A LPSW pump trips and will NOT restart• 1SA-91A9 (LPSW HEADER A PRESS LOW) actuates

1) At Time = 1205:05 the C LPSW Pump _(1 )_ received a signal to start.

2) At Time 1206:00 Unit 1 _(2)_ meet the LCO requirements of Tech Spec 3.7.7(LPSW).

Which ONE of the following completes the statement above?

ASSUME NO OPERATOR ACTIONS

A. 1. has2. does

B. 1. has2. does NOT

C. 1. has NOT2. does

D. 1. has NOT2. does NOT

of 100


(1 point)

Given the following Unit 1 conditions:• Reactor power 62% stable• RCS pressure = 2185 psig slowly decreasing• Pressurizer level = 229 inches slowly decreasing• Pressurizer temperature = 648.0°F slowly increasing• Pressurizer Heater Bank 1 switch is ON• Pressurizer Heater Bank 2 (Groups B & D) are in AUTO and OFF• Pressurizer Heater Banks 3 and 4 are in AUTO and OFF

1) The pressurizer is(1).

2) The pressurizer saturation circuit (2) — responding as expected.


A. 1. subcooled2. is

B. 1. subcooled2. is NOT

C. 1. saturated2. is

D. 1. saturated2. is NOT

of 100


(1 point)


• Reactor power = 100%• BOTH MFDW pumps trip

Current conditions:• Reactor power = 57% slowly decreasing

1) In accordance with Rule 1 (ATWS), the CRD breakers are opened _(1) aligningHPI injection from the BWST.

2) The direction given to the operator opening the CRD breaker is to (2) ArcFlash PPE.


A. 1. prior to2. wear

B. 1. priorto2. NOT wear

C. 1. after2. wear

D. 1, after2. NOT wear

of 100

Oconee Nuclear Station• 1LT46 ONSSRO NRCExarnination


Given the following Unit 1 conditions:• Loss of Heat Transfer has occurred• Unit 1 TDEFWP is now available to feed the Steam Generators• 1A SG level = 8” XSUR slowly decreasing• IA SG pressure = 412 psig slowly decreasing• I B SG level = 5” XSUR slowly decreasing• I B SG pressure = 385 psig slowly decreasing

In accordance with Rule 7 (Steam Generator Feed Control), the MAXIMUM initial feedrate allowed to EACH Steam Generator is limited to _(1 )_ gpm in order to prevent_(2)_.


A. 1. 1002. damage to the Steam Generators

B. 1. 1002. an RCS overcooling event

C 1.502. damage to the Steam Generators

D. 1502. an RCS overcooling event

of 100



Oconee plant conditions:• Station blackout has occurred• The EOP Blackout tab has been in progress for three hours• 1CA voltage 104 VDC

Which ONE of the following describes why the Blackout tab directs the crew to FAIL100-8 (CC RETURN PENT (54) OUTSIDE BLOCK) closed?

A. 100-8 will fail open if IA pressure decreases to <35 psig.

B. Prevents auto restart of CC pumps once AC power is restored.

C. CC will not be needed in the Reactor Building during the shutdown followingthe blackout.

D. 1CC-8 will fail open if DC power is lost to the solenoid.

of 100


(1 point)


• Reactor trip from 100% power due to a loss of offsite power (SwitchyardIsolation)

• CT-i lockout

Current conditions:• AP!1 1 (Recovery from Loss of Power) initiated• Si1 (STBY BUS ito MFB1) Breaker will NOT close• LOAD SHED COMPLETE is NOT lit on the ES Component Status Panel

In accordance with AP/1 i, electrical loads are secured to

_______


A. prevent exceeding CT-4 Overload Limits

B. prevent exceeding CT-5 Overload Limits

C. ensure Si2 (STBY BUS 2 to MFB2) Breaker is operated within limits

D. ensure adequate voltage to ES equipment during a subsequent LOCA

of 100


(1 point)

Given the following Unit 1 conditions:Time = 1200

• Reactor Power = 100%• OAC INOPERABLE

Time = 1300• 1 KVIA is de-energized

1) At Time = 1300 Backup Incore Instrumentation (1) preferred to be used forQuadrant Power Tilt indications in accordance with OP/i /A/1105/014 (ControlRoom Instrumentation Operation And Information) Enclosure 4.13 (ReactorParameter Information).

2) The MINIMUM power level at which the Tech Spec Quadrant Power Tilt limits in theCOLR apply is _(2).


A. 1. is2. 20%

B. 1. is2. 40%

C. 1. is NOT2. 20%

D. 1. is NOT2. 40%

of 100

Oconee Nuclear Station• 1LT46 ONS SRO NRC ExaminationQuestion: 14

(1 point)

Given the following plant conditions:• KHU-1 generating to grid• 1 DA input breaker (K1 -DA-1 A, Batt #1 Ckt Bkr) fails OPEN• 2SA-171A3 (Unit 1 Alarm Lockout) actuates

1) KHU#1 _(1)5trip.

2) The reason DC power is used for Keowee control power is that it will be availablefor a MINIMUM of approximately (2) — hour(s) following a loss of ALL ACpower.


A. 1.will NOT2. one

B. 1.will NOT2. four

C. 1.will2. one

D. 1.will2. four

of 100


(1 point)

Given the following Unit I conditions:e Reactor Power 100%• AP/22 (Loss of Instrument Air) in progress

1) Auxiliary Instrument Air (AlA) (1)_ provide a backup source of air to 1 HP-31.

2) With ALL motive force lost, the operator sent to manually operate 1 HP-31 willINITIALLY be required to throttle 1 HP-31 in the _(2)_ direction.


A. 1. does2. closed

B. 1. does2. open

C. 1,does NOT2. closed

D. I.does NOT2. open

of 100


(1 point)

Given the following Unit 1 conditions:• A loss of ALL sources of Steam Generator feed has occurred• HPI Forced Cooling in progress• RCS pressure = 2210 psig slowly decreasing• Pzr Level = 380 inches increasing• Core SCM 56°F increasing

In accordance with Rule 6 (HPI), HPI flow (1 )_ be throttled because _(2)_.


A. 1. may NOT2. RCS pressure is decreasing

B. 1. may NOT2. CETCs are increasing

C. 1. may2. Pzr Level is increasing

D. 1. may2. CETCs are decreasing

of 100


(1 point)


• Reactor power = 100%• 1A Main Steam Line Break occurs

Current conditions:• Reactor has tripped• RCS Tave = 544°F slowly increasing• 1A SG Pressure = 0 psig• 1 B SG Pressure = 990 psig slowly increasing• Turbine bypass valves in Auto• Reactor Building pressure = 0.2 psig stable

Which ONE of the following describes:

1) the status of the TDEFWP?

2) how subsequent operation of the TDEFWP would be performed?

A. 1. Operating2. Can be secured with TDEFWP control switch before AFIS is reset

B. 1. Operating2. Can be secured with TDEFWP control switch ONLY after AFIS is reset

C. 1. NOT operating2. Can be started with TDEFWP control switch before AFIS is reset

D. 1. NOT operating2. Can be started with TDEFWP control switch ONLY after AFIS is reset

of 100


(1 point)

Given the following Unit 1 conditions:• Reactor tripped from 100% power• ALL Control Rods fully inserted• IMS-lO (Main Steam Relief Valve) is stuck open• Main Steam pressure is being reduced in an attempt to reseat 1 MS-i 0

In accordance with Subsequent Actions of the EOP,

1) Main Steam pressure will be reduced in (1) psig increments.

2) the MINIMUM RCS temperature allowed while reseating a MSRV is (2) °F.


A. 1. 102. 532

B. 1.202. 532

C. 1.102. 525

D. 1.202. 525

of 100


(1 point)

Given the following Unit 1 conditions:• Reactor Power = 98% decreasing• Control Rod 4 in Group 6 = 0% withdrawn

1) ICS will automatically reduce Reactor power to _(1)_% Core Thermal Power.

2) The basis for decreasing reactor power to the above level is to ensure _(2).


A. 1.652. Local Linear Heat Rate limits are not exceeded

B. 1.652. adequate margin in preparation for resetting RPS trip set points

C. 1.552. Local Linear Heat Rate limits are not exceeded

D. 1.552. adequate margin in preparation for resetting RPS trip set points

of 100


(1 point)


• Reactor in MODE 3

Current conditions:• 1 DIB inverter DC Input breaker trips

The associated source range power will be restored using the


A. ASCO Switch

B. Static Transfer Switch

C. Manual Bypass Switch

D. Inverter Bypass Switches

of 100


(1 point>

Which ONE of the following is the condenser vacuum (inches Hg) SETPOINT stated inAP/27 (Loss Of Condenser Vacuum) that will require manually tripping the Reactorwhen in MODE 1?

A. 25

B. 24

C. 22

D. 19

of 100

Oconee Nuclear Station1LT46 ONSSRONRCExarninationQuestion: 22

(1 point)

1RIA-3, (Refueling Canal Wall Area Monitor)..

1) HIGH alarm (1)_ cause a Reactor Building Evacuation alarm.

2) is NOT in HIGH alarm during Power Operations because the (2)_.


A. 1. will2. setpoint is raised to provide for indication of RCS leakage

B. 1. will2. detector is removed from the Reactor Building

C. 1. will NOT2. setpoint is raised to provide for indication of RCS leakage

D. 1. will NOT2. detector is removed from the Reactor Building

of 100



Given the following plant conditions:• An Active Fire is taking place in Unit 2 Equipment Room• The SRO dispatches you to the Unit I Equipment Room to determine Control

Room Ventilation and Fire Damper positions

1) Control Room Ventilation system damper positions _(1 )_ be determined byobserving the linkage pointing to either the “OPEN” or “CLOSED” tag.

2) Observing that all damper blades are aligned in either the open or closed position(2)_ the ONLY way to determine Fire Damper positions between Unit 1 and

Unit 2 Equipment Rooms.


A. 1. can2. is

B. 1. can2. is NOT

C. 1. can NOT2. is

D. 1. can NOT2. is NOT

of 100


(1 point)


• Reactor power = 90%• Loop ‘A’ Controlling Thot fails HIGH• 2SA21B4 (RC AVERAGE TEMP HIGH/LOW) actuated

Current conditions:• The Diamond and BOTH FDW Masters taken to HAND

Which ONE of the following describes the INITIAL action taken by an RO, and thereason for the action, in accordance with OMP 1-18 (Implementation Standard DuringAbnormal And Emergency Events)?

A. Decrease Feedwater to stabilize reactor power

B. Decrease Feedwater to stabilize RCS pressure

C. Insert control rods to stabilize RCS pressure

D. Insert control rods to stabilize reactor power

of 100

Oconee Nuclear Station1LT46 ONSSRONRCExarninationQuestion: 25

(1 point)

Given the following Unit 2 conditions:• Reactor power = 100%• 2SA-18/A-11, TURBINE BSMT WATER EMERGENCY HIGH LEVEL, is in

alarm• Turbine Building flooding is confirmed

In accordance with the Turbine Building Flood tab of the EOP...

1) Emergency Feedwater pumps (1) required to be utilized to fill the SteamGenerators in addition to the Main Feedwater pumps.

2) While maximizing feed to the SGs, the MAXIMUM feed rate limits of Rule 7 (SGFeed Control) (2) apply while maintaining Tave> 532 °F.


A. 1. are2. do

B. 1. are2. do NOT

C. 1. are NOT2. do

D. 1. are NOT2. do NOT

of 100


(1 point)

Given the foNowing Unit 1 conditions:Time = 1200

• Reactor trips from 100% power due to a 1A Main Steam Line Break• BOTH 1A and 1 B SG pressures rapidly decreasing• CoreSCM=0°F

Time = 1204• Tcold reaches lowest value of 416°F

Time = 1215• Tcold = 498°F stable• Core SCM = 78°F stable• Rule 2 (Loss of SCM) is complete

1) — (1) — was the EOP tab that was required to be entered first from SubsequentActions.

2) Rule 8 (Pressurized Thermal Shock) — (2) — required to be invoked.


A. 1. Loss of SCM2. is

B. 1. Loss of SCM2. is NOT

C. 1, Excessive Heat Transfer2. is

D. 1. Excessive Heat Transfer2. is NOT

of 100

Oconee Nuclear Station* 1LT46 ONSSRONRCExaminationQuestion: 27

(1 point)


• EOL Unit shutdown in progress• RCS Thot = 439°F stable

Time 1205• Electrical disturbance occurs• The following statalarms actuate

o iSA-i 5/E6 (EL Swyd Isolation Confirmed Chnl A Logic)o ISA-i 4/E6 (EL Swyd Isolation Confirmed Chnl B Logic)o 1 SA-21A3 (RC Loop A Flow Low)o 1 SA-2/A4 (RC Loop B Flow Low)o 1 SA-2/A5 (RC Total Flow Low)

1) Assuming no additional operator actions, at Time = 1230, Thot will be (i)_439°F.

2) Entry into the EOP _(2) required.


A. 1. greaterthan2. is NOT

B. 1. greaterthan2. is

C. 1. approximately2. is NOT

D. 1. approximately2. is

of 100


(1 point)

Given the following Unit 1 conditions:• Reactor power 100% stable• Delta Tc ICS station in HAND• 1A1 RCP shaft shears

When RCP 1A1 shears, the plant will automatically run back at (1) and whenpower stabilizes, 1 A loop Tc will be (2) 1 B loop Tc.



A. 1. 20% per minute2. less than

B. 1. 20% per minute2. approximately the same as

C. 1. 25%perminute2. less than

D. 1. 25% per minute2. approximately the same as

of 100


(1 point)


• 1A1 RCP start in progress• AC oil lift pump is started

Current conditions:• Oil lift pump low discharge pressure does NOT clear

1) The AC oil lift pump (1)_automatically stop after a time delay.

2) The bypass position on the RCP start/stop switch — (2) — bypass ALL RCPstarting interlocks.


A. 1. will2. will

B. 1. will2. will NOT

C. 1. will NOT2. will

D. 1. will NOT2. will NOT

of 100


(1 point)

Given the following Unit 3 conditions:Reactor Power = 100% for previous 7 months

• lOS in automatic• 3A Purification IX was taken out of service 6 months ago• 3A Purification IX was just placed back in service without being saturated to

current RCS boron concentration

1) Group 7 control rods will be _(l)_

2) Assuming no other operator actions, taking the lOS Reactor Bailey station ONLY toHAND _(2)_ stop the rod motion.


A. 1. inserting2. will

B. 1. inserting2. will NOT

C. 1. withdrawing2. will

D. 1. withdrawing2. will NOT

of 100


(1 point)

Whch ONE of the following consists of ONLY components powered from 2TD?

A. 20 LPI pump and 2B HP) pump

B. 20 LPI pump and 2C HP) pump

C. 2B LPI pump and 2B HP) pump

D. 2B LPI pump and 20 HP) pump

of 100


(1 point)

Given the following Unit 3 conditions:• Reactor power 100%• 3A Core Flood Tank

o Pressure = 587 psig stableo Level = 12.87 ft stable

• 3B Core Flood Tanko Pressure = 629 psig stableo Level = 13.36 ft stable

Which ONE of the following describes the potential adverse effect and its cause thatcould occur during a design basis large break LOCA?

A. 3A CFT will discharge an inadequate volume of water into the core due to theCFT level.

B. 3A CFT will discharge an inadequate volume of water into the core due to theCFT pressure.

0. 3B CFT wiN discharge too much inventory during the blow down phase and notcover the hotspot during re-flood due to OFT level.

D. 3B OFT will discharge too much inventory during the blow down phase and notcover the hotspot during re-flood due to OFT pressure.

of 100


(1 point)

Given the following Unit I conditions:• Large Break LOCA has occurred

In accordance with EOP End, 5.12 (ECCS Suction Swap to RBES), which ONE of thefollowing describes:

1) the range of BWST levels (ft) where LPI pump suction would be aligned to both theRB Emergency Sump and the BWST simultaneously?

2) the action(s) that would be required if 1 LP-22 failed to close when isolating theBWST?

A. 1. 15—92. stop the 1 B LPI pump AND 1 B RBS pump

B. 1. 15—92. Maximize total LPI flow < 3100 gpm

C. 1. 9—62. stop the 1 B LPI pump AND 1 B RBS pump

D. 1. 9—62. Maximize total LPI flow < 3100 gpm

of 100

Oconee Nuclear Station• IL T46 ONS SRO NRC ExaminationQuestion: 34

(1 point)

Given the following Unit 1 conditions:• Reactor in MODE 1• Quench Tank is being pumped to 1A BHUT using the Quench Tank Pump AND

the Component Drain Pump

1) In accordance with OP!1IA/1104/017 (Quench Tank Operations), Quench TankLevel shall be maintained at a MAXIMUM of _(1)_ inches.

2) The Component Drain Pump _(2)_ automatically trip once Quench Tank levelreaches 80 inches


A. t902. will

B. 1.902. will NOT

C. 1. 1002. will

D. 1. 1002. will NOT

of 100




• Reactor power= 100%• 1A and lB Letdown Coolers in service• Letdown flow = 78 gpm

Current conditions:• 1A Letdown Cooler is removed from service by the RO in the Control Room

1) CC flow to the 1 B Letdown Cooler will — (1)

2) In accordance with OP/i/All 104/002 (HPI System), once the IA Letdown Cooler sisolated the MAXIMUM letdown flow is (2) gpm.


A. 1. stay the same2.88

B. 1. stay the same2. 125

C. 1. increase2.88

D. 1. increase2. 125

of 100

Oconee Nuclear Station1LT46 ONS SRO NRC ExaminationQuestion: 36

(1 point)

Which ONE of the following sets of components are BOTH cooled by the ComponentCooling system.

A. RCP Seal Return Coolers AND Quench Tank Coolers

B. RCP Seal Return Coolers AND RCP Motor Coolers

C. RCP Seal Coolers AND Quench Tank Coolers

D. RCP Seal Coolers AND RCP Motor Coolers

of 100


(1 point)

Given the following Unit 3 conditions:• Time=1200• Reactor power = 100%• Channel A AND Channel B narrow range RCS pressure fail HIGH

1) At Time = 1200 an AUTOMATIC reactor trip _(1 )_ occur,

2) At Time 1205 a low RCS pressure ES actuation _(2)_ occurred.



A. 1. will2. has

B. 1. will2. has NOT

C. 1. will NOT2. has

D. 1. will NOT2. has NOT

of 100


(1 point)

Given the following Unit 1 conditions:• Reactor power = 100%• I Bi Reactor coolant pump trips

Based on the above conditions, which ONE of the following RPS trips will preventexceeding the Departure from Nucleate Boiling Ratio (DNBR) safety !imit?

A. Flux/Pump

B. L0wRCS Pressure

C. Flux/Flow/Imbalance

D. High RCS Temperature

of 100



Given the following Unit 1 conditions:• Reactor Power = 100%• 1 KVIB panelboard is de-energized

1) The (1)_ Voters will NOT actuate their associated safeguards equipment.

2) Engineered Safeguards System Instrument Channels are in a (2)_ out of twotrip condition.


A. 1. ODD2. one

B. 1. ODD2, two

C. 1. EVEN2. one

D. 1. EVEN2. two

of 100


(1 point)

Given the following Unit 1 conditions:• Reactor power = 100%• 1A Main Steam Line Break inside containment occurs• Reactor Building Pressure peaks at 22.4 psig

1) The pump whose switch is pictured below _(1) received an ES signal to start.

2) The valve whose switch is pictured below _(2)_ received an ES signal toOPEN.

OPEN CLOSED


1. has NOT2. has NOT

1. has NOT2. has ,Wt111

t2. 1. has2. has NOT

1. has2. has

of 100


(1 point)

Given the following Unit 1 conditions:• Reactor in MODE 1

1) The LOWER Reactor Building Pressure that will result in an automatic start of theReactor Building Spray pumps is _(1 )_ psig.

2) The BWST to RBS pump suction valve 1 LP-22 _(2)_ receive a signal to OPENon ECCS actuation.


A. 1. 4.22. does NOT

B. 1. 4.22. does

C. 1. 11.52. does NOT

D. 1. 11.52. does

Page-fl of 100

Oconee Nuclear StationIL T46 ONS SRO NRC ExaminationQuestion: 42

(1 point)


• Reactor power = 100%1 TC locked out

• 1 BS-2 breaker is open and will not close

Current conditions:• ES 1 * 8 actuates due to a Large Break LOCA

1) Based on the above conditions, the RBS system (1) be able to perform itssafety function.

2) When in recirculation mode, one of the RBS system purposes is to (2)


A. 1. will2. entrain Iodine thus reducing offsite dose

B. 1. will NOT2. entrain Iodine thus reducing offsite dose

C. 1. will2. minimize hydrogen production

D. 1. will NOT2. minimize hydrogen production

of 100

Oconee Nuclear StationIL T46 ONS SRO NRC ExaminationQuestion: 43

(1 point)


• Reactor power = 100%• 3MS-112 & 3MS-173 (SSRH 3A13B Controls) are OPEN in MANUAL• 3MS-77, 78, 80, 81 (MS to SSR[fs) control switches in OPEN

Current conditions:• Main Turbine trips

1) 3MS-112&3M5-l73will(1).

2) 3MS-77, 78, 80, 81 will — (2) —.


A. 1 close2. close

B. 1. close2. remain open

C. 1. remain open2. close

D. 1, remain open2. remain open

of 100


(1 point)

Given the following Unit 1 conditionsInitial conditions:

• Reactor power = 70% stable

Current conditions:• 1HPE-6 (Heater 1A1 Bleed Inlet) closed

Which ONE of the following predicts the:

1) impact of the malfunction on Feedwater flow assuming no operator action?

2) procedure which can be used to reopen 1 HPE-6?

A. 1. higher2. OP/i /A11106/23 (High and Low Pressure Extraction)

B. 1. higher2. OP/1/A/1106/002 (Condensate and FDWsystem)

C. 1. lower2. OP/iIAIllO6/23 (High and Low Pressure Extraction)

D. 1. lower2. OP!i/A/1106/002 (Condensate and FDWsystem)

of 100


(1 point)


• Reactor power 100%

Current conditions:• Condenser vacuum = 18.5 inches Hg stable• 1TA and 1TB de-energized

SG levels will be automatically controlled at

_______


A. 25 inches Startup Range

B. 30 inches XSUR

C. 50% Operating Range

D. 240 inchesXSUR

of 100

Oconee Nuclear Station1LT46 ONS SRO NRC ExaminationQuestion: 46

(1 point)

Which ONE of the following utilizes the 1TE ES Power String as its source of electricalpower?

A. C LPSW pump

B. 1CRBCU

C. 1BMDEFWP

D. 1BRBS pump

of 100


(1 point)

Given the following plant conditions:• The Standby Buses are being powered from the 100 kV line• The SL Breakers Auto/Manual Selector switches are in AUTO• The TRIP INTERLOCK DEFEAT SWITCH is in the LEE position

Which ONE of the following conditions will cause the SL Breakers to open?

A. An undervoltage condition occurs on Standby Bus 1 ONLY.

B. An undervoltage condition would have to occur on BOTH Standby Bus 1 ANDStandby Bus 2.

C. The 1st level 100KV Degraded Voltage Relay has been satisfied for 9 secondsAND the 2nd level 100KV Degraded Voltage Relay is now satisfied.

D. The 1st level 100KV Degraded Voltage Relay is satisfied now AND the 2ndlevel 100KV Degraded Voltage Relay has been satisfied for 9 seconds.

of 100


(1 point)


• Reactor power = 100%• 1 PA Battery is inoperable

In accordance with SLC 16.8.3 (Power Battery Parameters):

1) The MAXIMUM Completion time allowed to declare the Unit 1 TDEFDW pumpinoperable is (1)

2) Cross connecting — (2) — buses is required.


A. 1. immediately2. IPA and IPB

B. 1. immediately2. 1PA,2PAand3PA

C. 1. within one hour2. 1PA and 1PB

D. 1. within one hour2. 1 PA, 2PA and 3PA

of 100


(1 point)


• Reactor power = 100%• ACB-4 Closed• Large LOCA occurs coincident with a total loss of offsite power

Time = 1205• Keowee Hydro Unit (KHU)-2 Emergency Lockout occurs

Which ONE of the following describes how ECCS systems are being powered at Time= 1210?


A. KHU-1 through the Overhead power path

B. KHU-1 through the underground power path

C. CT-5 powered from Lee combustion turbine

D. CT-5 powered from Central Switchyard

of 100

Oconee Nuclear Station1LT46 ONSSRONRCExamination


Which ONE of the following describes the operation of the Unit Vent RadiationMonitors RIA-45 and R—46 when the switchover acceptance range setpoint isreached?

RL-45 (1) read ZERO and RIA-46 will provide (2)

A. twill2. only alarm and unit vent radiation level indication

B. twill2. the same interlock functions that R-45 performs

C. twill NOT2. only alarm and unit vent radiation level indication

D. 1.willNOT2. the same interlock functions that RU-45 performs

of 100


(1 point)

Given the following Unit 1 conditions:• Reactor power 100%• A and B LPSW pumps are turned OFF and cannot be restarted• IAP/24 (Loss of LPSW) initiated

1) The LOWEST CRD temperature that will require a Reactor trip is (1)_ °F inaccordance with 1API2O (Loss of Component Cooling).

2) PRIOR to the reactor trip, the ROW heat exchanger outlet temperatures would beexpected to (2).


A. 1. 1402. increase

B. 1. 1402. remain unchanged

0. 1. 1802. increase

D. 1. 1802. remain unchanged

of 100


(1 point)

Given the following Unit I conditions:• Reactor Power = 25% stable• Instrument Air pressure = 63 psig slowly decreasing

AP/22 (Loss of Instrument Air) will direct the operator to trip the


A. Reactor ONLY

B. Main Turbine ONLY

C. Main Feedwater Pumps ONLY

D. Reactor and Main Feedwater Pumps ONLY

of 100


Question: 53(1 point>

Given the following Unit 1 conditions:• Reactor trip from 100% due to loss of all Main Feedwater• 1FDW-316 pneumatic supply line has ruptured and the valve cannot be

operated from Control Room• Enclosure 5.27 (Alternate Methods of Feeding the Steam Generator) in

progress• SRO notified that the startup path to the 1 B SG CANNOT be used

Which ONE of the following is the NEXT method specified in Enclosure 5.27 to controlRCS temperature?

A. Using ONLY the 1A SG

B. Use 1A SG AND feed lB SG with Alternate Units EFDW

C. Use 1A SG AND feed 18 SG by manually throttling 1FDW-316

D. Use 1A SG AND feed 18 SG with TDEFWP using 1MS-94 spindle to throttleTDEFWP speed

of 100



Given the following Unit 1 conditions:Time 1200

• Reactor in MODE 5• RCSLoopsdropped• Pressurizer level = 340” stable• RB Cavity washdown in progress• RB Purge in progress• Reactor Building Sump is being pumped

Time = 1205• Pressurizer level 322” decreasing• 1RIA-49 (Reactor Building High Gas) in HIGH alarm

1) The Containment Evacuation alarm (1) AUTOMATICALLY actuate as a resultof the I RL’-49 HIGH alarm.

2) _(2)_ is the procedure that is required to be entered FIRST.


A. 1. will2. AP/26 (Loss of Decay Heat Removal)

B. 1. will2. AP/2 (Excessive RCS Leakage)

C. 1. will NOT2. AP/26 (Loss of Decay Heat Removal)

D. 1. will NOT2. AP/2 (Excessive RCS Leakage)

of 100

Oconee Nuclear StationIL T46 ONS SRO NRC Examination


Given the following Unit 1 conditions:• Reactor in MODE 5• RB Main Purge in operation

Which ONE of the following will cause the RB Main Purge Fan to AUTOMATICALLYtrip OFF?

A. Suction pressure = 5” of water vacuum

B. 1 RIA—45, UNIT VENT GAS NORM, reaches its ALERT setpoint

C. Statalarm ISA9IB-3, RBV PURGE INLET TEMPERATURE LOW, alarms

D. 1 PR-3 (RB PURGE CONTROL) green CLOSED light is lit and red OPEN lightis off on 1VB2

of 100



Given the following Unit 1 conditions• Reactor startup in progress• ALL Control Rods = 0% withdrawn

In accordance with AD-OP-ALL0203 (Reactivity Management), which ONE of thefollowing is the EARLIEST condition during a reactor startup where criticality should beexpected?

When operators begin withdrawing

________

A. CRD Safety Groups

B. CRD Regulating Groups

C. rods after the -.75% delta K/K ECP position is reached

D. rods after the -1% delta K/K ECP position is reached

of 100


(1 point)

Given the following Unit 1 conditions:Time 1200

• Reactor has tripped from 100%

Time = 1205• ALL Condensate, Feedwater, AND Emergency Feedwater pumps are

unavailable• BOTH lAand 1BSG’s are dry• RCS temperature = 584°F slowly increasing• RCS pressure 2044 psig slowly increasing

1) Assuming NO operator actions, RCS (1)_ will stop increasing FIRST.

2) The NEXT method of decay heat removal required by the EOP will be _(2).


A. 1. pressure2. HPI Forced Cooling

B. 1. pressure2. SSFASW

C. ttemperature2. HPI Forced Cooling

D. 1.temperature2. 5SF ASW

of 100


(1 point>

Given the foNowing Unit I conditions:Initial Conditions:

• Reactor Power 100%• 1 B RPS channel in Manual Bypass due to failed RB pressure transmitter

Current Conditions:• iNl-7 fails HIGH

The 1C RPS channel:

1) _(i )_ AUTOMATICALLY trip.

2) (2) required to be placed in Manual Bypass in accordance withOP/i IA/i 105/014 (Control Room Instrumentation).


A. 1. did2. is

B. 1. did2. is NOT

C. 1. did NOT2. is

D. 1. did NOT2. is NOT

of 100


(1 point)

Given the following Unit 1 conditions:• Reactor power = 90% stable• 1A and 1 B Main FDW Control valves are in HAND• Controlhng Feedwater valve tP fails LOW

1) The initial response to the above failure is that Steam Generator levels _(1)increase

2) IF the conditions above result in a Reactor trip, the FDW Control Valve lOSHand/Auto stations will _(2).



A. 1. will2. remain in HAND

B. 1. will2. revert to AUTO

C. 1. will NOT2. remain in HAND

D. 1. will NOT2. revert to AUTO

of 100


(1 point)

Given the following plant conditions:Time 1200

• Fuel Handling activities in progress in Unit 1&2 Spent Fuel Pool• Fuel Cask is dropped damaging the Spent Fuel Pool liner

Time = 1205• Spent Fuel Pool level = -2.9 feet decreasing• Spent Fuel Pool Ventilation system is in operation

At TIME 1205:

1) The Unit 1 &2 Spent Fuel Cooling Pumps _(1) tripped off on low Spent FuelPool level.

2) Spent Fuel Pool Ventilation system is using the Unit _(2)_ Main Purge Filters.

Which ONE of the following competes the statements above?

A. 1. have2. One

B. 1. have2. Two

C. 1. have NOT2. One

D. 1. have NOT2. Two

of 100




• Reactor power = 100%• Turbine Bypass Valves (TBV5) in HAND

Current Conditions• 1KU is de-energized

1) The TBVs are _(1).

2) The TBVs _(2)_ manually operable from the Control Room.


A. 1. closed2. are

B. 1. 50% open2. are

C. 1. closed2. are NOT

D. 1. 50% open2. are NOT

of 100


(1 point)

Given the fouowing Unit 1 conditions:

0359:45• Reactor power 70% stable• 18 CBP trips

0400:00• Main FDW Pump suction pressure = 235 psig decreasing

0401:00• Main FDW Pump suction pressure = 230 psig decreasing

0401:30• Main FDW Pump suction pressure = 225 psig stable

Based on the above conditions, complete the following statements:

1) Of the times listed above, 1 C-61 (Cond Cooler Bypass Control) will first open at

2) At 0401 :35, the entry conditions for the EOP — (2) — met.


A. 1. 0400:002. are

B. 1. 0400:002. are NOT

C. 1. 0401:302. are

D. 1, 0401:302. are NOT

of 100


(1 point)

Given the following Unit 1 conditions:• 1A GWD tank release in progress• 1 RIA-37 HIGH alarm actuates• 1SA-8/B9 (Process Monitor Radiation High) actuates

1) Which ONE of the following describes the impact on the Gaseous Waste Disposal(GWD) system?

2) AP/1 8 (Abnormal Release of Radioactivity) _(2)_ required to be performed priorto re-initiating the release?

A. 1. Closes 1A GWD tank inlet AND outlet valves2. is

B. 1. Closes 1A GWD tank inlet AND outlet valves2. is NOT

C. 1. Closes 1A GWD tank outlet valves but does NOT close the 1A GWD tankinlet valves

2. is

D. 1. Closes 1A GWD tank outlet valves but does NOT close the 1A GWD tankinlet valves

2. is NOT

of 100


(1 point)

Given the following Unit 1 conditions:• PTIOIAIO23OIOO1, Radiation Monitor Check completed on Unit 1• 1RL’\-57 .75 R/HR

Which ONE of the following is an indication of a satisfactory source check?

A. Alert Alarm Actuation ONLY

B. Alert AND High Alarm Actuation ONLY

C. Area Monitor Fault Alarm Actuation ONLY

D. NO alarms actuate during the source check

of 100

Oconee Nuclear StationQuestion: 65(1 point>

1LT46 ONS SRO NRC Examination

LU

DCl)Cl)LU

U

IA Pressure vs. Time

Based on the graph above, which ONE of the following describes the EARLIEST timeat which SA-141 (SA to IA Controller) will automatically open?

A. 1207

B. 1210

C. 1212

D. 1215

100

TIME

1200 1210 1220 1230

of 100



Given the following Unit 1 plant conditions:• Reactor Power = 100%• An evolution is about to begin in the Control room in which an annunciator alarm has

been deemed “expected”

In accordance with AD-OP-ALL-bOO (Conduct of Operations)..

1) The CR8 _(1)_ suspend the requirement to verbally announce the alarm.

2) Once the annunciator response procedure has been referenced for an Expected alarm, it_(2)_ required to be reviewed for subsequent alarms received during that shift.


A. 1. may2. is

B. 1. may2. is NOT

C. 1. may NOT2. is

D. 1. may NOT2. is NOT

of 100



( (., ‘.. •. C

N,J

Note: Drawing not representative of actual plant conditions.


• Time = 0400• Reactor power = 100% decreasing• Control Rod Group 1 Rod 3 = 0% withdrawn

Current conditions:• Time 0430• Reactor power 68% decreasing• 1B1 RCP trips

1) At 0400, the power to which the ICS is running the plant back is displayed in the— (1) — window. (refer to the drawing above)

2) The unit — (2) — automatically stabilize at the required reactor power for plantconditions.


A. 1. upper2. will

B. 1. upper2. will NOT

C. 1. lower2. will

D. 1. lower2. will NOT

of 100

Oconee Nuclear Station1LT46 ONS SRO NRC Examination


Given the following plant conditions:• Unit I Reactor power = 100%• Unit 2 Reactor in MODE 3• No events in progress that would require activation of the SSF

In accordance with OMP 2-01 Attachment D (SSF Staffing Requirements)...

1) for the given conditions, a minimum of _(1 )_ Reactor Operators is maintainedwithin the Unit I & 2 Control Room (inside the CAD doors), with the followingpotential exception:

2) if one BOP/SSF operator leaves the Unit I & 2 Control Room for a short period oftime, it is required that _(2)_.

NOTE: Consider the two statements separately; i.e., if it is permissible for theBOP/SSF operator to leave the Control Room for a short time, include thatindividual in the minimum number of the first statement.


A. 1. three2. a method of communication is established to ensure the BOP/SSF operator

outside the Control Room can be informed if the SSF needs to be activated

B. 1. three2. another qualified licensed operator with no other concurrent duties relieves

the BOP/SSF operator and stays within the Unit 1 & 2 Control Room (insidethe CAD doors) until the first individual returns (if SSF activation notrequired)

C, 1. four2. a method of communication is established to ensure the BOP/SSF operator

outside the Control Room can be informed if the SSF needs to be activated

D. 1. four2. another qualified licensed operator with no other concurrent duties relieves

the BOP/SSF operator and stays within the Unit I & 2 Control Room (insidethe CAD doors) until the first individual returns (if SSF activation notrequired)

of 100



Given the following Unit 1 conditions:• Startup in progress with extra licensed operators in Control Room• An SRO has been assigned oversight of the startup as the Reactivity Manager• The OATC is training an individual on OJT from License Class

In accordance with AD-OP-ALL-0203 (Reactivity Management)...

1) _(1)_ withdrawal(s) of Safety Rods is/are required to be announced to theReactivity Manger PRIOR to Rod withdrawal.

2) the OATC _(2)_ allowed to peer-check the withdrawal of Safety Rods being doneby the trainee.


A. 1. ALL2. is

B. 1. ALL2. is NOT

C. 1. ONLY the first2. is

D. 1. ONLYthefirst2. is NOT

of 100


(1 point)

Given the following Unit 1 conditions:• Reactor in MODE 5• An electric valve is being tagged closed with its breaker open

In accordance with OMP 1-02 (Rules of Practice)..,

1) When closing the electric valve from the Control Room for the tagout, a peer check_(1) required.

2) Diverse verification of the breaker position in the OPEN position 2) requiredirect observation of the breaker position by opening the breaker cubicle door.


A. 1.is2. does

B. 1. is2. does NOT

C. 1. is NOT2. does

D. 1. is NOT2. does NOT

of 100


(1 point)

Given the following Unit 1 conditions:• Reactor power = 35% stable• RCS Pressure = 2150 psig stable

1) The low Pressurizer level cutoff of Pressurizer heaters occurs when Control Roomindication of Pressurizer level reaches _(1).

2) Based on the above conditions, if Pressurizer level is above the low level cutoffsetpoint and all Pressurizer heaters Manually energized, an RPS trip on high RCSpressure (2) occur.


ASSUME NO ADDITIONAL OPERATOR ACTIONS

A. 1. 80”2. will

B. 1. 85”2. will

C. 1. 80”2. will NOT

D. 1. 85”2. will NOT

of 100


(1 point)


• Reactor in MODE 6• RB Purge in progress

Current conditions:• lRlA-47 (RB Particulate) in HIGH alarm• AP/1 8, Abnormal Release of Radioactivity is initiated

1) RB Purge _(1) automatically terminate.

2) AP/18 (2)_ ensure the evacuation of non-essential personnel from the RB

A. 1. will2. does

B. 1. will2. does NOT

C. 1. will NOT2. does

D. 1. will NOT2. does NOT

of 100


(1 point)

Given the following Unit 3 conditions:• 3A GWD gas tank release in progress• Release is at 2/3 Station Limit

1) 1 REA-45 (Norm Vent Gas) High and Alert setpoints will be set at — (1) — thenormal 1/3 Station Limit as listed in PT/O/A/230/OO1 (Radiation Monitor Check).

2) if 3RIA-45 High alarm setpoint is reached, the 3A GWD gas tank release _(2)_AUTOMATICALLY terminate.


A. 1. double2. will

B. 1. double2. will NOT

C. 1. half2. will

D. 1. half2. will NOT

of 100


(1 point)

Given the following Plant conditions:• UnitllOO%• Unit 2 has an event in progress that requires SSF ASW activation

1) In accordance with OMP 2-1 (Duties and Responsibilities of On-Shift OperationsPersonnel), the j1)_ BOP will be dispatched to perform AP/25 (SSFActivation).

2) Prior to leaving the Control Room for the 8SF, AP/25 directs tripping _(2)_RCP(s),

Which ONE of the following completes the statements abàve?

A. 1. Unit 12. ALL

B. 1. Unit 12. all but ONE

C. 1. Unit 22. ALL

D. 1. Unit 22. all but ONE

of 100


(1 point)


• Reactor in MODE 6• LPI aligned in NORMAL Mode• RCS level = 75” on LT-5 stable• lB LPI Pump tagged out

Current conditions:• RCS level = 72” on LT-5 decreasing

1) In accordance with OP/11A111041004 (LPI System), the _(1)_ LPI pump will be inoperation?

2) In accordance with AP/26 (Loss of Decay Heat Removal), ALL LPI pumps (2)required to be secured in an effort to identify the leak location?

A. 1.102. are

B. 1.1A2. are

C. 1.1C2. are NOT

D. 1.1A2. are NOT

of 100


(1 point)


• RCS cooldown in progress• RCS temperature = 310 °F slowly decreasing

Current conditions:• Both the IA and lB HPI pumps have failed• AP/14 (Loss of HPI Normal Makeup and/or RCP Seal Injection) in progress• IC HPI pump has been aligned to provide RCS makeup

1) In accordance with OP/1/A/1104/002 (HPI System), aligning the 1C HPI pump asthe ROS Makeup pump _(1)_ require the 1HP-120 Travel Stop to be re-adjustedbefore considering it OPERABLE for LTOP?

2) In accordance with the basis of Tech Spec 3.412 (LTOP), opening the breakers for1HP-409 and 1HP-410 _(2)_ required to “deactivate” the 1A HPI train.


A. 1. does2. is

B. 1. does2. is NOT

C. 1. does NOT2. is

D, 1. does NOT2. is NOT

of 100


(1 point)

Given the following Unit 1 conditions:• Reactor Power = 100%• I RC-4 (PORV Block Valve) is Closed due to minor seat leakage past 1 RC-66• Neither 1 RC-4 nor 1 RC-66 have been Red tagged

1) The RCS pressure setpoint atwhich 1RC-66 will Open is_(1)_psig.

2) In accordance with SLC 16.5.1 (Reactor Coolant System Vents), IRC-4 beingclosed _(2)_ make I RC-66 INOPERABLE.


A. 1. 24502. does

B. 1. 24502. does NOT

C. 1. 25002. does

D. 1. 25002. does NOT

of 100


(1 point)

Given the following Unit I conditions:Time 1200

• SGTR tab in progress• Natural Circulation cooldown approved by management and in progress

o Core SCM = 0°F stableo Both loop SCM = 14°F slowly increasing

Time 1230• RVLIS indicates:

o 1A Hot Leg level = 600” stableo 1 B Hot Leg level = 585” stable

1) Based on the conditions at 1200, EOP Enclosure 5.6 (RCP Restart) (1) beutilized to restart a RCP.

2) If EOP Enclosure 5.6 is being used at 1230, pressurizer level must be at least> _(2)_ inches.


A. 1. can2. 100

B. 1. can NOT2. 100

C. 1. can2. 200

D. 1,canNOT2. 200

of 100

Oconee Nuclear Station• 1LT46 ONSSRONRCExaininationQuestion: 79

(1 point)


• Reactor Power = 100%• 1 KVIC power supply is transferred to 1 KRB in support of Maintenance on 1 DIC

inverter

Current conditions:• 1 DIC inverter work is completed and it is ready to be aligned to 1 KVIC, but NO

electrical alignments have been made

1) In accordance with the basis of Tech Spec 3&.6(1rwooro Oporating),- 1 KVICPanelboard is (1) . Vj

.8.2) In accordance with the basis of Tech Spec ,-&.S-(Dist4bution Sys ems-Operating)----- 12/iT?’

the 1 DIC Inverter is _(2)_.


A. 1. OPERABLE2. OPERABLE

B. 1. OPERABLE2. INOPERABLE

C. 1. INOPERABLE2. OPERABLE

D. 1. INOPERABLE2. INOPERABLE

of 100


(1 point)

Given the following Unit 1 conditions:• Reactor power = 100%• SOP and OATC are only RO’s available• Degrading instrument air pressure results in a manual Reactor Trip in

accordance with AP/22 (Loss of Instrument Air)• During the transient, indications of a Main Steam Line Break (MSLB) were

observed• RCS pressure decreased to 1400 psig and then began to increase

1) In accordance with OMP 1-18 (Implementation Standard During Abnormal andEmergency Events) the Procedure Director can direct that AP122 be performed inparallel with the EOP _(1 )_.

2) In accordance with Rule 5 (Main Steam Line Break) HPI can be throttled oncePressurizer level has returned to — (2)


A. 1 immediately after Immediate Manual Actions and Symptoms Check arecompleted

2. on scale and increasing

B. 1. immediately after Immediate Manual Actions and Symptoms Check arecompleted

2. >lO0inches

C. 1. ONLY after RuleS (Main Steam Line Break) and EOP Enclosure 5.1 (ESActuation) have been completed

2. on scale and increasing

D. 1. ONLY after Rule 5 (Main Steam Line Break) and EOP Enclosure 5.1 (ESActuation) have been completed

2. >100 inches

of 100


(1 point)

Given the following Unit I conditions:• Reactor Power 45% stable• AP/34 (Generator Grid Disturbance) in progress• Generator Output = 350 MWe• Hydrogen pressure = 60 psig

In accordance with AP/34,

1) The MAXIMUM limit on MVARs is approximately (1).

2) if operation in the acceptable region of the Generator Capability Curve cannot bemaintained, following required actions in AP134, the next required proceduretransition is to initiate _(2)_.


REFERENCE PROVIDED

A. 1. 7252. Unit 1 EOP

B. 1. 7252. AP/1 (Unit Runback)

C. 1. 4252. Unit 1 EOP

D. 1. 4252. AP/1 (Unit Runback)

of 100



Given the following Unit 1 conditions:Time = 1200:

• Reactor power = 85% stable• DeftaTcinHAND

Time 1210:• ICS runback in progress• Reactor power as indicated below

— .A A A A

125 126+60

125+60

125

100 +40 100 *40 100 .40 100 +40

80 +20 80 +20 80 +20 80 +20

60 0 60 0 60 0 60 0

40 20 40 -20E 40 -20 40 -20k

20-40 20-40 20-40 20-40

0 .60 60 0 60 0 60V V V V

/ MB / IBM / 1MM / MM

POWER RANGE NI’S

1) Which ONE of the following describes the reason for the lOS runback?

2> At Time = 1210 the MINIMUM value of QPT that will result in exceeding the limitsprovided by Tech Spec 3.2.3 (Quadrant Power Tilt> is j2)_?

REFERENCE PROVIDED

A. 1. Dropped Control Rod2. >3.50

B. 1. Dropped Control Rod2. >7.11

C. 1.RCPtrip2. >3.50

D. 1.RCPtrip2. >7.11

of 100

Oconee Nuclear Station• 1LT46 ONSSRONRCExarnination



• Reactor has been tripped due to SGTR in the 1A SG

Time 0430• Feedwater to the 1A SG is isolated• 1A SG level = 273 inches XSUR increasing• 1 B SG level = 30 inches XSUR stable

Time = 0500• 1A SG level = 293 inches XSUR increasing

Time = 0530• IA SG reaches the Water in Steam Line Level

In accordance with the SGTR tab:

1) At 0500, operators (1) required to perform EOP Enclosure 5.22 (SGB lowdown).

2) At 0530, operators are required to _(2) steaming the 1A SG.


A. 1. are NOT2. continue

B. 1. are NOT2, stop

C. 1. are2. continue

D. 1. are2. stop

of 100



Given the following Unit I conditions:Initial conditions:

• Time = 0400• Reactor power = 80% stable• Control Rods Group 7 = 83% withdrawn• Group 7 Rod 3 will not move and is declared INOPERABLE

Current conditions:• Time = 0500• Reactor power = 80% stable• Group 7 Control Rods = 61% withdrawn

In accordance with Tech Spec 3.2.1 (Regulating Rod Position Limits>, if the aboveconditions do not change the reactor is required to be in MODE 3 not later than

___?

REFERENCE PROVIDED

A. 1600

B. 1700

C. 1800

D. 1900

of 100


(1 point>

Given the following Unit 1 conditions:• Reactor power = 100%• Breaker Status

o ACB 4 Closedo PCB8-Openo PCB9-Open

• SA-2, C-i KEOWEE PCB 9 is in alarm• SA-2, B-i DACUS BL. KEOWEE TIE PCB 8 is in alarm

1) Keowee Hydro Unit-2 _(1) be started in AUTOMATIC (NOT Emergency start)from the Control Room.

2) In accordance with the basis of Tech Spec 3.8.1 (AC Systems-Operating), KeoweeHydro Unit-i is currently _(2).


A. 1. can2. OPERABLE

B. 1. can2. INOPERABLE

C. 1. can NOT2. OPERABLE

D. 1. can NOT2. INOPERABLE

of 100

Oconee Nuclear Station• 1LT46 ONSSRONRCExarninationQuestion: 86

(1 point)

Given the following Unit 1 plant conditions:• RCS temperature = 240°F• RCS pressure = 260 psig• No RCS Vent Paths are open• HPI has been deactivated• 1A and 1 B OFT pressure = 500 psig• 1CF-1 and 1CF-2 Closed and Breakers White Tagged Opened• Pressurizer level 235 inches stable• 000ldown to Mode 5 in progress at 20°F/Hr

Which ONE of the following describes the impact of this condition, and the actionrequired?

REFERENCE PROVIDED

A. RCS pressure and temperature exceed the limits that ensure brittle fractureprevention in accordance with TS 3.4.3 RCS Pressure and Temperature (PT)Limits;Establish an RCS Vent Path or dedicated LTOP Operator.

B. RCS pressure and temperature exceed the limits that ensure brittle fractureprevention in accordance with TS 3.4.3 RCS Pressure and Temperature (PT)Limits;Restore RCS Pressure and Temperature to within limits in 30 minutes or less

C. Administrative controls (Train 2) for an LTOP event are lost;Establish an RCS Vent Path or dedicated LTOP Operator in accordance withTS 3.4.12 Low Temperature Over Pressure Protection

D. Administrative controls (Train 2) for an LTOP event are lost;Depressurize CFTs to less than RCS pressure within 1 hour in accordancewith TS 3.4.12 Low Temperature Over Pressure Protection.

of 100

Oconee Nuclear Station* 1LT46 ONSSRONRCExaminatjonQuestion: 87

(1 point)


• Reactor power = 90%• RPS Channel B High RB pressure fails HIGH• RPS Channel B is Placed in Manual Bypass

Time = 0800• RPS Channel C High RB pressure fails LOW

Time = 0815• RPS Channel C placed in TRIP

Time = 0830• RPS Channel A High RB pressure fails LOW

At 0830 the plant operators are


REFERENCE PROVIDED

A. NOT required to enter a CONDITION of Tech Spec 3.3.1 (RPSInstrumentation>; the reactor has automatically tripped and TS 13.1 no longerapplies

B. Required to enter/have entered CONDITION A of Tech Spec 3.3.1 ONLY

C. Required to enter/have entered CONDITIONs B and C of Tech Spec 3.3.1ONLY

D. Required to enter/have entered CONDITIONs A, B, and C of Tech Spec 3.3.1

of 100


(1 point)

Given the following Unit I conditions:• Reactor Power= 100%• While performing SR 3352, Manual ES Setpoint Verification, SPOC

determines that Reactor Building Pressure High “as found” setpoints to be asfollows:A=353 psigB = 404 psigC 409 psig

1) The Actual Setpoint for ES RB Pressure High is (1)_ psig.

2) Operators (2) required to enter Tech Spec 3.3.5 (ESPS Input Instrumentation)CONDON B.


REFERENCE PROVIDED

A. 1. 3.02. are

B. 1. 3.02. are NOT

C. 1. 3.52. are

D. 1. 3,52. are NOT

of 100


(1 point)

Given the following Unit 2 conditions:• Startup in progress• Reactor in MODE 3• 2A RBS pump inoperable

1) Tech Spec 36.5 (Reactor Building Spray and Cooling Systems) LCO (1) met.

2) When Tech Spec 365 LCO is NOT met, Unit 2 entry into MODE 2 _(2)_ allowedonce ALL additional requirements specified in the associated basis are satisfied.

Which ONE of the following completes the above statement?

A. 1. is2. is

B. 1. is2. is NOT

C. 1. is NOT2is

D. 1. is NOT2. is NOT

of 100


(1 point)


• Reactor power = 75% stable• 1A RBCU INOPERABLE

Time = 0800• 1SAI9 A-6 REACTOR BUILDING NORMAL SUMP LEVEL HIGH/LOW in alarm• 10 RBCU flow indications

o A Flow 270 gpmo Inlet Flow = 560 gpm

Time = 0810• 1LPSW-22 (IC RBCU INLET) and 1LPSW-24 (RBCU 10 OUTLET) are closed• RB Sump level has stopped increasing

1) At 0800, 1SAI9 D-9 RBCU C COOLER RUPTURE _(1)_ be in alarm.

2) At 0810, Containment is (2) in accordance with Tech Spec 3.6.1(Containment).


A. 1. should2. OPERABLE

B. 1. should2. INOPERABLE

C. 1. should NOT2. OPERABLE

D. 1. should NOT2. INOPERABLE

of 100


(1 point)

Given the following Unit 1 conditions:Time 1200:

• Reactor startup in progress• Reactor power = 6E-3% stable on all WR Ni’s• 1 Nl1 and 1 NI-3 Source Range Channels are unavailable

Time = 1205:• 1 Nl-2 Source Range power supply fails

1) 1NI-3 is located in RPS channel _(1)_.

2) At Time = 1205, Tech Specs (2) allow the power increase to continue togreater than 5% power.


A. 1.B2. does

B. 1.B2. does NOT

C. 1.C2. does

D. 1.C2. does NOT

of 100


(1 point)

Given the following Unit 3 conditions:• ReactorinMODE6• Core offload in progress• Main Fuel Bridge is withdrawing a fuel assembly

1) A loss of the _(1)_ interlock would increase the risk of fuel assembly damageduring withdrawal.

2) In accordance with MP/01A115001009 (Reactor Bridge Operation), _(2) mustauthorize bypassing the above interlock.


A. 1. Fuel Overload (TS-1)2. BOTH the Fuel Handling Supervisor AND the Refueling SRO

B. 1. Fuel Overload (TS-1)2. EITHER the Fuel Handling Supervisor OR the Refueling SRO

C. 1. Fuel Hoist Up/Down (TS-2)2. BOTH the Fuel Handling Supervisor AND the Refueling SRO

D. 1. Fuel Hoist Up/Down (TS-2)2. EITHER the Fuel Handling Supervisor OR the Refueling SRO

of 100


(1 point)


• ALL Main And Emergency feedwater pumps have been lost• LOHT tab has been initiated

Time = 1205• Condensate Booster Pump Feed is being aligned in accordance with Rule 3• Increasing RCS temperature results in 1A Core SCM = 0°F

At Time = 1205:

1) Performance of Rule 4 _(1)_ required.

2) Transfer to the LOSCM tab (2)_ required.


A. 1. is2. is

B. 1. is2. is NOT

C. 1. isNOT2. is

D. 1. is NOT2. is NOT

of 100

Oconee Nuclear StationILT46 ONSSRONRCExaminationQuest,on: 94

(1 point)

Given the following Unit 1 conditions:• Maintenance is being performed on Unit 1 condensate system• The clearance for the section of piping connected to the component is such that

the piping can be vented but not drained.

In accordance with SOMP 2-1 (Safety Tagging And Configuration Control)...

1) An SRO with an “Inactive” license _(1)_ allowed to sign the Work Order TaskAssignment (WOTA) Ready for Work.

2) Zero Energy Comments (2)_ have to be entered into ST-2 prior to setting theWOTA Ready for Work.


A. 1. is2. do

B. 1.is2. do NOT

C. 1. is NOT2. do

D. 1. is NOT2. do NOT

of 100


(1 point)

Given the following Unit I conditions:• SGTR tab in progress• RCS temperature = 530°F stable• 1A SG isolated• 3 RCP’s operating• HPI pump suction aligned to BWST• Group 3 Rod 2 100% withdrawn

1) _(1) _tab of the EOP will be utilized to cooldown to LPI,

2) The EOP tab above states that the cooldown plateau allowed prior to performing aShutdown Margin verification is _(2) °F.


A. 1.SGTR2. 240

B. 1.SGTR2. 450

C. 1.FCD2. 240

D. 1.FCD2. 450

of 100


(1 point>

Given the following Unit 1 conditions:• Unit is stable in MODE 3 following an unexpected plant trip one hour ago• Operators have just entered a CONDITION of Tech Spec 3.1.1 (Shutdown

Margin (SDM)) that requires boration be initiated in a short time

1) The basis document for Tech Spec 3.1.1 specifies that operators should use the_(1)_ or the Borated Water Storage Tank (BWST) as the source of boration.

2) The Unit 1 COLR states that BWST boron concentration shall be greater than_(2) ppm.

Which ONE of the following completes the above statements?

A. 1. A Bleed Holdup Tank (BHUT)2. 2220

B. 1. ABleedHoldupTank(BHUT)2. 2500

C. 1. Concentrated Boric Acid Storage Tank (CBAST)2. 2220

0. 1. Concentrated Boric Acid Storage Tank (CBAST)2. 2500

of 100


(1 point)


• Defueling in progress• 1 RIA-3 (Fuel Transfer Canal Monitor) = 4 mr/hr stable• Main Fuel Bridge Area Monitor = 6 mr/hr stable

Current conditions:• iRL-3 local reading = 0 mr/hr• 1 RIA-3 View Node indication is magenta

The Refueling SRO will determine that Fuel Handling activities in the Reactor Buildingmay

_______

in accordance with OP/i /AI1 502/007 (Operations Defueli ng/Refueli ngResponsibilities)?


A. NOT continue until a portable area monitor with local alarm capability is inplace.

B. continue because only the Main Fuel Bridge Area Monitor is required.

C. NOT continue until continuous RP coverage is present on the Main FuelBridge.

D. continue provided 1 RLA-49 (RB Normal Gas) is OPERABLE.

of 100


(1 point)

Given the following plant conditions:• Shift is preparing for ONE (1) GWR release of the 1A Gaseous Waste Disposal

(GWD) tank at the 1/3 Station Limit• The release will be through the P/A/C filter• 1A GWD tank holdup time is 41 days

1) The Shift Manager/OSM _(1)_ the MINIMUM level of authority for approval of theabove release in accordance with OPI1-2/A111041018 (GWD System).

2) The SLC basis for limiting the Curie content of the GWD Tanks limits Whole Bodyexposure of an individual at the nearest exclusion boundary to (2).


A. 1.is2. 0.5 Rem in the event of a GWD tank rupture.

B. 1. is2. 100 mrem during a planned GWD tank release.

C. 1. is NOT2. 0.5 Rem in the event of a GWD tank rupture.

D. 1. is NOT2. 100 mrem during a planned GWD tank release.

of 100


(1 point)


• Reactor Power = 100%

Current conditions:• Station Blackout occurs• A large RCS leak that is greater than normal makeup capability has occurred

While waiting on power to be restored to the Unit 1 4160v buses...

1) the actions performed by the operators dispatched to the SSF_(1)_ be able tomitigate the RCS leak.

2) Rule 2 (Loss of SCM) _(2) required to be performed in parallel with theBlackout tab if ALL subcooling margins indicate 0°F.


A. 1. will2. is

B. 1. will2. is NOT

C. 1. will NOT2. is

D. 1. will NOT2. is NOT

of 100


(1 point)


• Unit shutting down due to a 30 gpm tube leak in 1A SG

Time = 1203• Unit trips due to a loss of Main Feedwater• Emergency Feedwater is NOT available

Time 1207• AO reports one Main Steam Relief Valve on the 1 B SG stuck open• Unit 2 TDEFWP aligned and feeding Unit 1 Steam Generators• 1A SG tube leak = 200 gpm stable

1) The conditions present at 1200 (1) require an emergency classificationwithin 15 minutes.

2) At time = 1207 the emergency classification is — (2)

Assume no additional failures occur AND that Emergency CoordinatorJudgment is NOT used as a reason for classification.


REFERENCE PROVIDED

A. 1. would2. ALERT

B. 1. would2. SITE AREA EMERGENCY

C. 1. would NOT2. ALERT

D. 1. would NOT2. SITE AREA EMERGENCY

of 100

Examination KEYfor: 1LT46 ONS SRO NRC Examin

Question AnswerNumber

1 B

2 B

3 C

4 B

5 B

6 C

7 D

8 B

9 D

10 A

11 D

12 A

13 A

14 A

15 A

16 D

17 C

18 A

19 C

20 C

21 C

22 D

23 A

24 A

25 A

Printed 12/18/2014 10:51:07 AM Page 1 of4



26 A

27 B

28 B

29 B

30 D

31 D

32 D

33 C

34 C

35 D

36 C

37 A

38 C V

39 D

40 C

41 C

42 BV

43 BV

44 C

45 DV

46 C

47 B V

48 B

49 A

50 B

Printed 12/18/2014 10:51:0 7 AM Page 2 of 4



51 D

52 D

53 C

54 B

55 D

56 A

57 A

58 D

59 B

60 B

61 A

62 A

63 D

64 D

65 D

66 B

67 D

68 C

69 B

70 D

71 C

72 C

73 D

74 C

75 B




76 B

77 B

78 D

79 B

80 C

81 B

82 A

83 D

84 D

85 C

86 C

87 D

88 A

89 A

90 A

91 A

92 A

93 B

94 A

95 B

96 D

97 A

98 C

99 C

100 A


IO

conee

IC

ycle

28j

Pag

e25

of33

ON

EI

0400

-50

Rev

34

105

______

______

_

:10

5

I00

_______

_____

Con

trol

Rod

Posi

tion

Set

po

nts

,

100

95

__

__

__

11In

oper

able

Rod

s4

Pum

DF

low

95

90

________

:•

80

_________

.R

stri

cted

90

85

_______

I

75

__

__

__

__

_

Op

erat

ior

__________

85

80 75 70

__

__

__

:U

nac

cep

tab

le70

_______

Oper

atio

n65

_______________

65

U-

60i

H’

60

c

____

____

____

____

____

____

55a

__

__

__

__

___________

50

__

__

__

__

_____________

Acc

epta

ble

________

500

__

__

__

__

__

________

Oner

atio

n

________

-45

__

__

__

__

_____________

45

4040

351

35

3030

2525

!

20‘

Iii

w:

:20

II

15[i

.I.

15I

10:_

_:

:10

5G

roup

6:

::,

5I

rII5

1-

2535

4555

b575

8595

ij0

Hil

LI

,

o0

1020

3040

5060

7080

9010

00

1020

3040

5060

7080

9010

0

Gro

up5

IGro

up7

Con

trol

Rod

Posi

tion,

%W

D

CO>ci)

CDIc)

cDCD

9wz0

It) 0C) 0 10 0 10 CD 10 0 Ic) 0 IC) C) Ic) CD 10 CD IC) CD If) 0

(3) 0) CO Co N- N- (0 (0 If) It) ct CO CO (N (N IC)

C,)CO‘4-

0

IL) 0 IC) C) IC) C) IC) CD IC) 0 10 C) If) C) IL) C) If) C) 10 C) IC) C)CD C) 0) 0) CL) Cc) N- N- CL) (0 10 10 - CO C’) (N (N — ‘-‘- -

ad % ‘JOM0 -‘°Pèi

D

C0

U)0

•t30

0

C00

ON

EI-

0400

-50

Rev

34

LO

conee

IC

ycle

28P

age

27of

33•10

5

_____

__

__

__

__

__

_______

::IIt

t1t

____________

105

10

0

__

__

__

_

100

Con

trol

RodP

os

tion

Set

poin

ts

_____

951

Inoper

able

Rod

,4

Pum

pF

low

_____

95

90

______

90

8585

8080

75

______

75

70

__

__

__

70

6565

Un

acce

pta

ble

0

60O

pera

tion

60

i55

5500

50

_____

50A

ccep

table

_____

0

_____

-45

Oper

atio

n

______

45

4040

0

35

__

__

__

35

30

______

30

15

2525

2020

15 1010 5

Gro

up6

__

__

__

__

__

__

55

1525

3545

5565

7585

95

______

0

__

__

__

__

__

_______

0

r1

02030

4050

6070

8090

100

jI0

1020

3040

5060

7080

9010

0

-IG

roup

5C

ontr

olR

odPo

sitio

n,%

WD

IGro

up7

105

100 95 90 85 80 75 70 65

U I 50 0 C)

Ct a) a::

40 35 30 25 20 15 10 5 0

Oco

nee

IC

ycle

28

1010

2030

405

06

070

8090

100

Gro

up5

Con

trol

Rod

Posi

tion,

%W

D

ON

EI-

0400

-50

Rev

34P

age

28of

3310

5

100

95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 S 010

1020

3040

5060

7080

901001

Gro

up7

3.2 POWER DISTRIBUTION LIMITS

3.2.1 Regulating Rod Position Limits

Regulating Rod Position Limits3.2.1

LCO 3.2.1 Regulating rod groups shall be within the physical position, sequence, andoverlap limits specified in the COLR.

NOTENot required for any regulating rod positioned to perform SR 3.1.4.2.

APPLICABILITY: MODES 1 and 2.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. Regulating rod groups A.1 Restore regulating rod 2 hourssequence or overlap groups to within limits.requirements not met.

(continued)

OCONEE UNITS 1, 2, & 3 3.2.1-1 Amendment Nos. 300, 300, & 300


ACTIONS (continued)


B. Regulating rod groups B.1 -NOTE-positioned in restricted Not applicable toor unacceptable region. regulating rod groups

positioned in therestricted region.

Initiate boration to 15 minutesrestore SDM to withinthe limits specified inthe COLR.

AND

B.2.1 Restore regulating 2 hoursrod groups to withinacceptable region.

OR

B.2.2 Reduce THERMAL 2 hoursPOWER to less than orequal to THERMALPOWER allowed byregulating rod groupposition limits.

C. Required Action and C.1 Be in MODE 3. 12 hoursassociated CompletionTime of Condition Aor B not met.

OCONEE UNITS 1, 2, & 3 3.2.1-2 Amendment Nos. 300, 300, & 300


SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.2.1.1 Verify regulating rod groups are within the In accordance with thesequence and overlap limits as specified in Surveillance Frequencythe COLR. Control Program

SR 3.2.1.2 Verify regulating rod groups meet the position In accordance with thelimits as specified in the COLR. Surveillance Frequency

Control Program

SR 3.2.1.3 Verify SDM to be within the limit as specified Within 4 hours prior toin the COLR. achieving criticality

OCONEE UNITS 1, 2, & 3 3.2.1-3 Amendment Nos. 372, 374, 373 I

Enclosure 4.31 oP/O/A/1 108/00 1Unit 1 RCS Heatup/Cooldown Curves Page 1 of 9

NOTE: If changes are required to curves in this enclosure, the OAC curves must be updated at thesame time or the OAC curves must be considered not valid. { I }

Enclosure 4.31 oP/O/A/1 108/00!Unit 1 RCS Heatup/Cooldown Curves Page 2 of 9

Notes For Unit 1 Wide Range Cooldown Curve

1. Maintain RCS PIT below and to the right of the 300°F, 250°F, and 200°F Subcooled curves.

2. Maintain RCS PIT above and to the left of the 20°F Subcooled curve.

3. When any number of RCPs are running, maintain RCS PIT above and to the left of the 4 RCPNPSH curve. (See EOP curves for abnormal containment conditions).

4. When a single RCP in a loop is operating, minimize operating time below the <4 RC Pump NPSHcurve. This limits cumulative damage to the single operating pump caused by cavitation due torequired NPSH at high flows.

5. RCS is considered depressurized when all of the following conditions exist:

• RCS temperature <200°F

• RCS pressure < 50 psig

• All RCPs off

6. Use Low Range Curves when either of the following exist:

• RCS pressure is <550 psig

• RCS temperature is <350°F

Heatup/Cooldown Limits

RCS Temp Max Cooldown Rate

T> 270°F 45°F in any 1/2 hour period

140°F < T < 270°F < 20°F in any 1/2 hour period

T < 140°F 45°F in any 1 hour periodRCS depressurized < 45°F in any 1 hour period

Note: PT/1/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatupand Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.

RCS Temp Max Heatup Rate {22}

T < 270°F <25°F in any 1/2 hour period

T 270°F <45°F in any 1/2 hour period

Enclosure 4.31

Unit 1 RCS Heatup/Cooldown CurvesOP/O/A/I 108/001Page 3 of 9

Unit 1 Wide Range Cooldown Curve

i-f

p NPSHF

1

0 100 200 300 400 500 600 700

Tcold REACTOR COOLANT TEMPERATURE (°F) UIWRCI) 54 FFPY, Rev. 0


Tcold REACTOR COOLANT TEMPERATURE (°F)0 100 200 300 400 500 600 700

2200

2100

2000

1900

1800

1700

1600

1500

1400

1300

1200

2200

2100

2000

190020°FSUBCOOLD, -

-4-t

I

CC

cj

-I

(ID(ID

z

CC

C

LI I

hop

Ei1000

— 1800

• 1700

T 1300

_____

1000

-w

CC-

(ID

(ID

z

CC

C

ff1-900

800

700

600

500

400

300

200k1t •CPun

900

800

700

600

500

400

300

200

100

0

______

F

___

3OO°FLh I • SUBCOOLEII

100

0-r -

I-- I r ii n

Enclosure 4.31 0PIO/A/1 108/001Unit 1 RCS Heatup/Cooldown Curves Page 4 of 9

Notes For Unit 1 Wide Range Heatup Curve

1. Maintain RCS PIT below and to the right of the 300°F, 250°F, and 200°F Subcooled curves.

2. Maintain RCS PIT above and to the left of the 20°F Subcooled curve.

3. When any number of RCPs are running, maintain RCS PIT above and to the left of the 4 RCPNPSH curve. (See EOP curves for abnormal containment conditions).

4. When a single RCP in a loop is operating, minimize operating time below the <4 RC Pump NPSHcurve. This limits cumulative damage to operating pump caused by cavitation due to requiredNPSH needed at high flows.

5. Use Low Range Curves when either of the following exist:

• RCS pressure is < 550 psig

• RCS temperature is <350°F


RCS Temp Max Cooldown Rate {22} RCS Temp Max 1-leatup Rate

T> 270°F <45°F in any 1/2 hour period T < 270°F <25°F in any 1/2 hour period

140°F <T <270°F <20°F in any 112 hour period T> 270°F <45°F in any 1/2 hour period

T < 140°F 45°F in any 1 hour periodRCS depressurized 45°F in any 1 hour period


Enclosure 4.31

Unit 1 RCS Heatup/Cooldown CurvesOP/O/A/1 108/00 1Page 5 of 9

Unit 1 Wide Range Heatup Curve

Tcold REACTOR COOLANT TEMPERATURE (°F)

0 100 200 300 400 500 600 700

Teold REACTOR COOLANT TEMPERATURE (°F)UIWRI-IU 54 EFPV, Rev. 0

Note: PT/1/A/0600/O0l (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatupand Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.

0 100 200 300 400 500 6002200

700

ii hiii:-

2100

2000

1900

1800

1300

1200

1100

CC

c,D

z

CCc-)

p

z

liii ETh1T1 ±

2200

2100

_______

2000

1900C

I1400

++— 1300 <C

______

1200

1100

- _—1000

700

::iE:tE:t:1: I

it

:X

1000 __1_4_!rf.j__I_I iiiii• I

lifi900

800

700

600

500

400

300

200

-1

I—:3;:ii-

-j- 4RCPump NPS1I

•TH IIrJT42

100

0

/-3O0F

HI :rt__

h1 _LII_I’ I •II — —J

i

_____

I

_____

600

500

400

300

200

100

0

__1iIi:: zztLLIf

F

Enclosure 4.31

Unit 1 RCS Heatup/Cooldown CurvesOP/O/A/1 108/00 1Page 6 of 9

[Notes For Unit 1 Low Range Cooldown Curve

1. Curve #1- RCS cooldown limitations.

2. Curve #2- Minimum RCS pressure for RCP operation.

3. Curve #3- Minimum RCS pressure for continuous operation of single RCP in a loop. Minimizeoperating time below this line with single RCP in a loop operating to limit cumulative damage tooperating pump caused by cavitation.

4. Curve #4- Max RCS pressure and temperature for LPI pump initiation.

5. RCS is considered depressurized when all of the following conditions exist:

• RCS temperature <200°F

• RCS pressure < 50 psig

• AIIRCPs off

6. Briefly operating above the LPE pressure curve (#4) or below the RCP NPSH curve (#2) by<40 psig is acceptable while swapping RCPs.


f RCS Temp Max Cooldown Rate

T> 270°F < 45°F in any 1/2 hour period

140°F < T < 270°F < 20°F in any 1/2 hour period

T < 140°F < 45°F in any 1 hour periodRCS depressurized < 45°F in any 1 hour period

RCS Temp Max Heatup Rate {22}


T> 270°F <45°F in any 1/2 hour period


Enclosure 4.31

Unit 1 RCS Heatup/Cooldown CurvesOP/O/A/I 108/001Page 7 of 9

Unit 1 Low Range Cookiown Curve

TCOId Reactor Coolant Temperature, °F

TCOd Reactor Coolant Temperature, °F UII.RCD 54 EFPV, Res’. 0

*PZR level restricted to <380 inches when RCS temperature is < 160°F. AND NO HPIPs operating.

Note: PT/I/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatupand Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.

1

H±-Hi

0 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400

-

—

550

adtubcoc

ZE +

525

500

475

450

425

600

575

550

525

500

475

450

425

0)ci) 4000

a)0) 375C

350

325

300a)

275Cct:

250C-)

2250

200

175

150

125

100

75

50

25

0

0)400

0

a)375 0)

C

350

325 a)D

300a)

275CCa

250 00

C-)225

C.)

200

itF\ 24

I Subcoole - .t—H_._—- -

-

LTOP LIMIT HNHF-t Ii I j rF H- Maintain \f,J__QTrJ. JL_ i!T ‘1 FF PZRLev& LT1Pr1T

iJ’- <22Oinches r—

-

in this area -.. ii..

--— H—’’ —. 2z’ :N:

. ±: . ;..--

.

‘kfH - ‘1-TR-b--’-- ---rI .

-‘:-

-

LTOP LIMIT WE - --

._ Maintain — --

I.PZRLeveI - .

,,., ,-1 . --—. <3lOpnches

.,in this area .

-

175

150

125

100

75

50

I .00 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400

25

Enclosure 4.31

Unit 1 RCS Heatup/Cooldown CurvesOP/O/A/l 108/001Page 8 of 9

Notes For Unit 1 Low Range Heatup Curve

1. Curve #1- RCS heatup limitations.

2. Curve #2- Minimum required RCS pressure for RCP operation.

3. Curve #3- Minimum RCS pressure for continuous operation of single RCP in a loop. Minimizeoperating time below this line with single RCP in a loop operating to limit cumulative damage tooperating pump caused by cavitation.

4. Curve #4- Max RCS pressure and temperature for LPI pump initiation.

5. Briefly operating above the LPI pressure curve (#4) or below the RCP NPSH curve (#2) by<40 psig is acceptable while swapping RCPs.


RCS Temp

T>270°F

140°F<T <270°F

T< 140°FRCS depressurized

Max Cooldown Rate {22}

45°F in any 1/2 hour period

<20°F in any 1/2 hour period

45°F in any 1 hour period<45°F in any 1 hour period

RCS Temp Max Fleatup Rate


T270°F <45°F in any 1/2 hour period


Enclosure 4.31

Unit 1 RCS Heatup/Cooldown CurvesOP/O/A/l 108/001Page 9 of 9

C)(I)C.

0)C)C(‘3

C-J0)

DC,)C,)0)

0

C(‘300

C-)

00(‘30)

Unit I Low Range Heatup Curve

TCOld Reactor Coolant Temperature, 5F

200

175

150

125

100

75

50

25

0

TCOId Reactor Coolant Temperature, °F UILRHU 54 EFPY, Rev. 0

*PZR level restricted to <380 inches when RCS temperature is < 160°F, AND NO HPIPs operating.


600

575

0 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400

__

600

575

550

525

500

475

450

425

C)

400

ci)375

350

325

300ci)

275C(‘3

250 oC

C-)225

C)(‘30)

550r

uucieaf

525 - . - . .. —i I - —

—4,. -I-

500 - —-.

..t..i. fjl475 . - -

.3 -i Ii_

—.- .

.

450 - - , —

425--

. 250°F—

: Subcooled400 — - .

— - —

375 —rft--.

H- i2-

350-‘

-- - --

325-— - - . —

:- L4’ -J -

300 350F — ,.- . -

Subcooled- - . . . . . — . -

275 - rf —

r -

it! -- . .

250 .E -f225 —

. LTOP Limit . - . -

,. i- . —

. Maintain- lEE

200 I 300 F — PZR Level-

. Subcooled v 220 inches -.

. I . -, in this area — — —175I-

lI . -

150 .:

ioo’:1

+

] : -. ‘Top Limit- I

,

- Maintain—

50 t-’- 4-t — - — PZR Level _

. . . --. <3l0inches —

25 - — -

- is this area -

-:.ZL . *- .,. .

0 E.Z L_ --

0 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400

LTOP System3.4.12

3.4 REACTOR COOLANT SYSTEM (RCS)

3.4.12 Low Temperature Overpressure Protection (LTOP) System

LCO 3.4.12 An LTOP System shall be OPERABLE with high pressure injection (HPI)deactivated, and the core flood tanks (CFTs) isolated and:

a. An OPERABLE power operated relief valve (PORV) with a liftsetpoint of 535 psig; and

b. Administrative controls implemented that assure 10 minutes areavailable for operator action to mitigate an LTOP event.

APPLICABILITY: MODE 3 when any RCS cold leg temperature is 325°F,MODES 4, 5, and 6 when an RCS vent path capable of mitigating themost limiting LTOP event is not open.

NOTES1. CFT isolation is only required when CFT pressure is greater than

or equal to the maximum RCS pressure for the existing RCStemperature allowed by the pressure and temperature limit curvesprovided in Specification 3.4.3.

2. The PORV is not required to be OPERABLE when no HPI pumpsare running and RCS pressure < 100 psig.

OCONEE UNITS 1,2, & 3 3.4.12-1 Amendment Nos. 307, 307, & 307

ACTIONS

LTOP System3.4.12

(continued)


A. HPI activated. A.1 Initiate action to Immediatelydeactivate HPI.

B. A CFT not isolated B.1 Isolate affected OFT. 1 hourwhen OFT pressure isgreater than or equal tothe maximum ROSpressure for existingtemperature allowed bySpecification 3.4.3.

C. Required Action and 0.1 Be in MODE 4 with 12 hoursassociated Completion RCS temperatureTime of Condition B not > 200°F.met.

OR

0.2 Depressurize affected 12 hoursOFT to < 373 psig.

D. PORV inoperable. D.1 Restore PORV to 1 hourOPERABLE status.

E. Required Action and E.1 Be in MODE 3 with 23 hoursassociated Completion RCS averageTime of Condition D not temperaturemet. > 325° F.

OR

E.2 Depressurize RCS to 35 hours< 100 psig.

OCONEE UNITS 1, 2, & 3 3.4.12-2 Amendment Nos. 307, 307, & 307 I

LTOP System3.4.12

SURVEILLANCE REQUIREMENTS (continued)


F. Administrative Controls F.1 Provide compensatory 4 hoursthat assure measures to monitor

10 minutes are for initiation of anavailable to mitigate LTOP event.consequences of anLTOP event notimplemented.

G. Required Action and G.1 Depressurize the RCS 12 hoursassociated Completion and establish an RCSTime of Condition F not vent path capable ofmet. mitigating the most

limiting LTOP event.

H. Administrative Controls H.1 Restore system to 1 hourthat assure OPERABLE status.

10 minutes areavailable to mitigate the Q!consequences of anLTOP event not H.2 Depressurize RCS and 12 hoursimplemented and establish RCS ventPORV inoperable, path capable of

mitigating the mostOR limiting LTOP event.

LTOP Systeminoperable for anyreason other thanCondition A throughCondition G.


OCONEE UNITS 1,2, &3 3.4.12-3 Amendment Nos. 372, 374, 373

RPS Instrumentation3.3.1

3.3 INSTRUMENTATION

3.3.1 Reactor Protective System (RPS) Instrumentation

LCO 3.3.1 Three channels of RPS instrumentation for each Function in Table 3.3.1-1shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1-1

ACTIONS


A. One required channel A.1 Place channel in trip. 1 hour for Unit(s) withinoperable. RPS digital upgrade not

complete

OR

4 hours for Unit(s) withRPS digital upgradecomplete

B. Two or more required B.1 Enter the Condition Immediatelychannels inoperable, referenced in

Table 3.3.1-1 for theOR Function.

Required Action andassociated CompletionTime of Condition A notmet.

(continued)

OCONEE UNITS 1, 2, & 3 3.3.1-1 Amendment Nos. 366, 368 & 367


ACTIONS (continued)


C. As required by Ci Be in MODE 3. 12 hoursRequired Action B.1and referenced in ANDTable 3.3.1-1.

C.2 Open all control rod 12 hoursdrive (CRD) tripbreakers.

D. As required by D.1 Open all CRD trip 6 hoursRequired Action B.1 breakers.and referenced inTable 3.3.1-1.

E. As required by El Reduce THERMAL 6 hoursRequired Action B.1 POWER < 30% RTP.and referenced inTable 3.3.1-1.

F. As required by F.1 Reduce THERMAL 12 hoursRequired Action B.1 POWER < 2% RTP.and referenced inTable 3.3.1-1.




NOTERefer to Table 3.3.1-1 to determine which SRs apply to each RPS Function.


SR 3.3.1.1 Perform CHANNEL CHECK. In accordance with theSurveillance FrequencyControl Program

SR 3.3.1.2 NOTENot required to be performed until 24 hoursafter THERMAL POWER is 15% RTP.

Compare results of calorimetric heat balance In accordance with thecalculation to the power range channel output Surveillance Frequencyand adjust power range channel output if Control Programcalorimetric exceeds power range channeloutput by 2% RTP.

SR 3.3.1.3 NOTENot required to be performed until 24 hoursafter THERMAL POWER is 15% RTP.

Compare out of core measured AXIAL In accordance with thePOWER IMBALANCE (API0) to incore Surveillance Frequencymeasured AXIAL POWER IMBALANCE (API1) Control Programas follows:

(RTP!TP)(API0— (CS X API1)) = imbalanceerror

where CS is CORRELATION SLOPE

Adjust power range channel output if theabsolute value of imbalance error is

2% RTP.

(continued)

OCONEE UNITS 1, 2, & 3 3.3.1-3 Amendment Nos. 372, 374, 373




SR 3.3.1.4 NOTENot applicable to Unit(s) with RPS digitalupgrade complete.

Perform CHANNEL FUNCTIONAL TEST. In accordance with theSurveillance FrequencyControl Program

SR 3.3.1.5 NOTEOnly applicable to Unit(s) with RPS digitalupgrade complete.

Manually verify the setpoints are correct. In accordance with theSurveillance FrequencyControl Program

SR 3.3.1.6 NOTEOnly applicable to Unit(s) with RPS digitalupgrade complete.

Manually actuate the output channel In accordance with theinterposing relays. Surveillance Frequency

Control Program

SR 3.3.1.7 NOTENeutron detectors are excluded fromCHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. In accordance with theSurveillance FrequencyControl Program

OCONEE UNITS 1,2, &3 3.3.1-4 Amendment Nos. 372, 374, 373


Table 331-1 (page 1 of 2)Reactor Protective System Instrumentation

APPLICABLE CONDITIONSMODES OR REFERENCED

OTHER FROMSPECIFIED REQUIRED SURVEILLANCE ALLOWABLE

FUNCTION CONDITIONS ACTION B.1 REQUIREMENTS VALUE

6. Reactor Building High Pressure 1,2,3 C SR 3.3.1.1 4 psigSR 3.3.1.4SR 3.3.1.5SR 3.3.1.6SR 3.3.1.7

OCONEE UNITS 1,2, & 3 3.3.1-5 Amendment Nos. 366, 368 & 367

Table 3.3.1-1 (page 2 of 2)Reactor Protective System Instrumentation

APPLICABLE CONDITIONSMODES OR REFERENCED

OTHER FROMSPECIFIED REQUIRED

CONDITIONS ACTION B.1

(a) When not in shutdown bypass operation.

(b) During shutdown bypass operation with any CRD trip breakers in the closed position and the CRD System capable of rodwithdrawal.

(c) With any CRD trip breaker in the closed position and the CRD System capable of rod withdrawal.

FUNCTION

RPS Instrumentation3.31

SURVEILLANCE ALLOWABLEREQUIREMENTS VALUE

OCONEE UNITS 1,2, &3 3.3.1-6 Amendment Nos. 366, 368 & 367

ESPS Input Instrumentation3.3.5

3.3 INSTRUMENTATION

3.3.5 Engineered Safeguards Protective System (ESPS) Input Instrumentation

LCO 3.3.5 Three channels of ESPS input instrumentation for each Parameter inTable 3.3.5-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5-1.

ACTIONS

NOTESeparate Condition entry is allowed for each Parameter.


A. One or more A.1 Place channel in trip. 1 hour for Unit(s) withParameters with one ESPS digital upgrade notchannel inoperable, complete

OR

4 hours for Unit(s) withESPS digital upgradecomplete

B. One or more B.1 Be in MODE 3. 12 hoursParameters with two ormore channels ANDinoperable.

B.2.1 NOTEQE Only required for RCS

Pressure — Low.Required Action andassociated CompletionTime not met. Reduce RCS pressure 36 hours

< 1750 psig.

AND

(continued)


ESPS Input Instrumentation3.3.5


B. (continued) B.2.2 NOTEOnly required for RCSPressure — Low Low.

Reduce RCS pressure 36 hours< 900 psig.

AND

B.2.3 NOTEOnly required forReactor BuildingPressure — High andHigh High.

Be in MODE 5. 36 hours



SR 3.3.5.1 Perform CHANNEL CHECK. In accordance with theSurveillance FrequencyControl Program

(continued)

OCONEE UNITS 1, 2, & 3 3.3.5-2 Amendment Nos. 372, 374, 373

ACTIONS

ESPS Input Instrumentationa3.5



SR 3.3.5.2 NOTEOnly applicable to Unit(s) with ESPS digitalupgrade complete.

Manually verify that the setpoints are correct. In accordance with theSurveillance FrequencyControl Program

SR 3.3.5.3 NOTENot applicable to Unit(s) with ESPS digitalupgrade complete.

Perform CHANNEL FUNCTIONAL TEST. In accordance with theSurveillance FrequencyControl Program

SR 3.3.5.4 Perform CHANNEL CALIBRATION. In accordance with theSurveillance FrequencyControl Program

OCONEE UNITS 1, 2, & 3 3.3.5-3 Amendment Nos. 372, 374, 373 I

ESPS Input Instrumentation I3.3.5

Table 3.3.5-1 (page 1 of 1)Engineered Safeguards Protective System Input Instrumentation I

APPLICABLEMODES OR OTHER SPECIFIED ALLOWABLE

PARAMETER CONDITIONS VALUE

1. Reactor Coolant System Pressure — Low 1750 psig 1590 psig

2. Reactor Coolant System Pressure — Low Low 900 psig 500 psig

3. Reactor Building (RB) Pressure — High 12,3,4 4 psig

4. Reactor Building Pressure — High High 12,3,4 S 15 psig


Duke Energy -- - -

- Procedure No. --

Oconee Nuclear Station RP/O/A/1 000/001

Emergency Classification Revision No.

001

Electronic Reference No.

Reference Use 0p009A63

PERFORMANCE I* * * * * * * * * * UNCONTROLLED FORPRTNT* * * * * * * * * *

(ISSUED) - PDF Format

RP/O/A/1000/001Page 2 of 6

Emergency Classification

NOTE: This procedure is an implementing procedure to the Oconee Nuclear Site Emergency plan and must be forwarded toEmergency Planning within seven (7) working days of approval.

1. Symptoms

1 .1 This procedure describes the immediate actions to be taken to recognize and classify anemergency condition.

1.2 This procedure identifies the four emergency classifications and their correspondingEmergency Action Levels (EAL5).

1.3 This procedure provides reporting requirements for non-emergency abnormal events.

1.4 The following guidance is to be used by the Emergency Coordinator/EOF Director inassessing emergency conditions:

1.4.1 Definitions and Acronyms are italicized throughout procedure for easyrecognition. The definitions are in Enclosure 4.10 (Definitions/Acronyms).

1.4.2 The Emergency Coordinator/EOF Director shall review all applicableinitiating events to ensure proper classification.

1.4.3 The BASIS Document (Volume A, Section D of the Emergency Plan) isavailable for review if any questions arise over proper classification.

1.4.4 IF An event occurs on more than one unit concurrently,

THEN The event with the higher classification will be classified on theEmergency Notification Form.

A. Information relating to the problem(s) on the other unit(s) will becaptured on the Emergency Notification Form as shown inRP/0/A/1000/015A, (Offsite Communications From The Control Room),RP/0/A/1000/015B, (Offsite Communications From The TechnicalSupport Center) or SR/0/B/2000/004, (Notification to States and Countiesfrom the Emergency Operations Facility).

1.4.5 IF An event occurs,

AND A lower or higher plant operating mode is reached before theclassification can be made,

THEN The classification shall be based on the mode that existed at thetime the event occurred.

2

RP/O/A/l000/OOlPage 3 of6

1.4.6 The Fission Product Barrier Matrix is applicable only to those events thatoccur at Mode 4 (Hot Shutdown) or higher.

A. An event that is recognized at Mode 5 (Cold Shutdown) or lower shall notbe classified using the Fission Product Barrier Matrix.

1. Reference should be made to the additional enclosures that provideEmergency Action Levels for specific events (e.g., Severe Weather,Fire, Security).

1.5 IF A transient event should occur,

THEN Review the following guidance:

1.5.1 An Emergency Action Level (EAL) identifies a specific duration

AND The Emergency Coordinator/EOF Director assessment concludesthat the specified duration is exceeded or will be exceeded, (i.e.;condition cannot be reasonably corrected before the durationelapses),

THEN Classify the event.

1.5.2 IF A plant condition exceeding EAL criteria is corrected before thespecified duration time is exceeded,

THEN The event is NOT classified by that EAL.

A. Review lower severity EALs for possible applicability in these cases.

NOTE: Reporting under 1OCFR5O.72 may be required for the following step. Such a conditioncould occur, for example, if a follow up evaluation of an abnormal condition uncoversevidence that the condition was more severe than earlier believed.

1.5.3 IF A plant condition exceeding EAL criteria is not recognized at thetime of occurrence, but is identified well after the condition hasoccurred (e.g.; as a result of routine log or record review)

AND The condition no longer exists,

THEN An emergency shall NOT be declared.

• Refer to NSD 202 for reportability

3

RP/O/A/1000/OO1Page 4 of 6

1.5.4 IF An emergency classification was warranted, but the plant conditionhas been corrected prior to declaration and notification

THEN The Emergency Coordinator must consider the potential that theinitiating condition (e.g.; Failure of Reactor Protection System) mayhave caused plant damage that warrants augmenting the on shiftpersonnel through activation of the Emergency ResponseOrganization.

A. IF An Unusual Event condition exists,

THEN Make the classification as required.

1. The event may be terminated in the same notification or as a separatetermiiation notification.

B. IF An Alert, Site Area Emergency, or General Emergencycondition exists,

THEN Make the classification as required,

AND Activate the Emergency Response Organization.

1.6 Emergency conditions shall be classified as soon as the Emergency Coordinator/EOFDirector assessment determines that the Emergency Action Levels for the InitiatingCondition have been exceeded.

4

RP/O/A/l000/OOlPage 5 of 6

2. Immediate Actions

2.1 Assessment, classification and declaration of any applicable emergency condition shouldbe completed within 15 minutes after the availability of indications or information tocognizant facility staff that an EAL threshold has been exceeded.

2.2 Determine the operating mode that existed at the time the event occurred prior to anyprotection system or operator action initiated in response to the event.

2.3 fl The unit is at Mode 4 (Hot Shutdown) or higher

AND The condition/event affects fission product barriers,

THEN GO TO Enclosure 4.1, (Fission Product Barrier Matrix).

2.3.1 Review the criteria listed in Enclosure 4.1, (Fission Product Barrier Matrix)and make the determination if the event should be classified).

2.4 Review the listing of enclosures to determine if the event is applicable to one of thecategories shown.

2.4.1 IF One or more categories are applicable to the event,

THEN Refer to the associated enclosures.

2.4.2 Review the EALs and determine if the event should be classified.

A. IF An EAL is applicable to the event,

THEN Classify the event as required.

2.5 IF The condition requires an emergency classification,

THEN Initiate the following:• for Control Room - RP/O/B/1000/002, (Control Room

Emergency Coordinator Procedure)• for TSC - RP/O/A/1000/019, (Technical Support Center

Emergency Coordinator Procedure)• for EOF - SR!O/A/2000/003, (Activation of the Emergency

Operations Facility)

2.6 Continue to review the emergency conditions to assure the current classificationcontinues to be applicable.

5

RP/O/A/1000/00 1Page 6 of 6

3. Subsequent Actions

3.1 Continue to review the emergency conditions to assure the current classificationcontinues to be applicable.

4. Enclosures

Enclosures Page Number

4.1 Fission Product Barrier Matrix 7

4.2 System Malfunctions 8

4.3 Abnormal Rad Levels/Radiological Effluents 10

4.4 Loss Of Shutdown Functions 12

4.5 Loss of Power 14

4.6 Fires/Explosions And Security Actions 15

4.7 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety 17

4.8 Radiation Monitor Readings For Emergency Classification 20

4.9 Unexpected/Unplanned Increase In Area Monitor Readings 21

4.10 Definitions 22

4.11 Operating Modes Defmed In Improved Technical Specifications 27

4.12 Instructions For Using Enclosure 4.1 28

4.13 References 30

6

Encl

osu

re4.

1F

issi

onP

rod

uct

Bar

rier

Mat

rix

DE

TE

RM

INE

TH

EA

PP

RO

PR

IAT

EC

LA

SS

IFIC

AT

ION

US

ING

TH

ET

AB

LE

BE

LO

W:

RP

/0/A

/100

0/00

1Pa

ge1

of1

AD

DP

OIN

TS

TO

CL

AS

SIF

Y.

SE

EN

OT

EB

EL

OW

NO

TE

:•

An

even

tw

ithm

ulti

ple

even

tsco

uld

occu

rw

hich

wou

ldre

sult

inth

eco

nclu

sion

that

exce

edin

gth

elo

ssor

pote

ntia

llo

ssth

resh

old

isIM

MIN

EN

T(i

.e.,

with

in1-

3ho

urs)

.In

this

IMM

INE

NT

LO

SSsi

tuat

ion,

usej

udgm

ent

and

clas

sify

asif

the

thre

shol

dsar

eex

ceed

ed.

•R

efer

enci

ngth

ism

atri

xfr

eque

ntly

will

aid

inde

term

inin

ga

fiss

ion

barr

ier

failu

reor

othe

rup

grad

ecr

iteri

a.

RC

SB

AR

RIE

RS

(lID

5-7)

FU

EL

CL

AD

BA

RR

IER

S(l

ID8

-9)

CO

NT

AIN

ME

NT

BA

RR

IER

S(B

D1

0-1

3)

Pot

enti

alL

oss

(4P

oint

s)L

oss

(5P

oint

s)P

oten

tial

Los

s(4

Poi

nts)

Los

s(5

Poi

nts)

Pot

enti

alL

oss

(1P

oint

)L

oss

(3P

oint

s)

RC

SL

eakr

ate?

160

gpm

RC

SL

eak

rate

that

resu

ltsin

alo

ssA

vera

geof

the

5hi

ghes

tA

vera

geof

the

5hi

ghes

tC

ET

CC

ET

C12

00°

F15

min

utes

Rap

idun

expl

aine

dco

ntai

nmen

tof

subc

oolin

g.C

ET

C12

00°

FO

Rpr

essu

rede

crea

seaf

ter

incr

ease

700°

FC

ET

C70

0°F

15m

inut

esw

itha

vali

dR

VL

Sre

adin

g0”

cont

ainm

ent

pres

sure

orsu

mp

leve

lno

tco

nsis

tent

with

LO

CA

SGT

R?

160

gpm

Val

idR

VL

Sre

adin

gof

0”C

oola

ntac

tivi

ty30

0llC

i/ml

DE

lR

Bp

ress

ure

?59

psig

Fai

lure

ofse

cond

ary

side

of

SGO

Rre

sult

sin

adi

rect

open

ing

toth

eR

Bp

ress

ure

?10

psig

and

noen

viro

nmen

tw

ithSG

Tub

eL

eak

RB

CU

orR

BS

lOgpm

inth

eSA

ME

SG

NO

TE

:R

VL

Sis

NO

Tva

lidif

one

orm

ore

RC

Psar

eru

nnin

gO

Rif

Ent

iyin

toth

ePT

S(P

ress

uriz

edIR

IA57

or58

read

ing?

1.0

RJh

rL

PIpu

mp(

s)ar

eH

ours

RIA

57O

RR

IA58

Hou

rsR

IA57

OR

RIA

58SG

Tub

eL

eak?

10gp

mex

ists

inT

herm

alSh

ock)

Ope

ratio

nS

ince

SDR

Ihr

RJh

rS

ince

SDR

/hr

R/h

ron

eSG

.ru

nnin

gA

ND

taki

ng

NO

TE

:PT

Sis

ente

red

unde

r2

RIA

57re

adin

g1.

6R

lhr

auct

ion

from

the

LPI

the

othe

rSO

has

seco

ndar

ysi

deei

ther

ofth

efo

llow

ing:

2R

IA58

read

ing?

1.0

RJh

rdr

oplin

e.0

-<0

.5?

300

?15

00

-<

0.5

?18

00?

860

failu

reth

atre

sults

ina

dire

ct.

Aco

oldo

wn

belo

w40

0°F

@op

enin

gto

the

envi

ronm

entJj

>10

0°F/

hr.

has

occu

rred

.3R

IA57

or58

read

ing

1.0

R/h

r0.

5-

<2.

0?

80?

400.

5-<

2.0

?40

0?

195

isbe

ing

fed

from

the

affe

cted

unit

.H

PIha

sop

erat

edin

the

2.0

-8.

0?

32?

162.

0-8.

0?

280

?13

0in

ject

ion

mod

ew

hile

NO

RC

Ps

wer

eop

erat

ing.

HPI

Forc

edC

ooli

ngR

CS

pres

sure

spik

e?27

50ps

igH

ydro

gen

conc

entr

atio

n?

9%C

onta

inm

ent

isol

atio

nis

inco

mpl

ete

and

are

leas

epa

thto

the

envi

ronm

ent

exis

ts

Em

erge

ncy

Coo

rdin

ator

fEO

FE

mer

genc

yC

oord

inat

or/E

OF

Em

erge

ncy

Coo

rdin

ator

/EO

FE

mer

genc

yC

oord

inat

or/E

OF

Dir

ecto

rE

mer

genc

yC

oord

inat

or/E

OF

Em

erge

ncy

Coo

rdin

ator

lEO

FD

irec

torj

udgm

ent

Dir

ecto

rjud

gmen

tD

irec

torj

udgm

ent

judg

men

tD

irec

torj

udgm

ent

Dir

eeto

rjud

gmen

t

UN

US

UA

LE

VE

NT

(1-3

Tot

alP

oin

ts)

AL

ER

T(4

-6T

otal

Poi

nts)

SIT

EA

RE

AE

ME

RG

EN

CY

(7-1

0T

otal

Poi

nts)

GE

NE

RA

LE

ME

RG

EN

CY

(11

-13

Tot

alP

oint

s)

OP

ER

AT

ING

MO

DE

:1,2

,3,4

OP

ER

AT

ING

MO

DE

:1

,2,3

,4O

PE

RA

TIN

GM

OD

E:

1,2

,3,4

OP

ER

AT

ING

MO

DE

:1

,2,3

,4

4.1

.U.I

Any

pote

ntia

llo

ssof

Con

tain

men

t4.

1.A

.IA

nypo

tent

ial

loss

orlo

ssof

the

RC

S4

1S

1L

oss

ofan

ytw

oba

rrie

rs4.

1.G

.IL

oss

ofan

yIw

oba

rrie

rsan

dpo

tent

ial

loss

of

the

thir

dba

rrie

r4.

1.U

.2A

nylo

ssof

cont

ainm

ent

4.1

.A.2

Any

pote

ntia

llo

ssor

loss

ofth

eFu

el4.

1.S

.2L

oss

ofon

eba

rrie

ran

dpo

tent

ial

loss

ofei

ther

4.1.

0.2

Los

sof

all

thre

eba

rrie

rsC

lad

RC

Sor

Fuel

Cla

dB

arri

ers

4.1.

S.3

Pote

ntia

llo

ssof

both

the

RC

San

dFu

elC

lad

Bar

rier

s

7

Encl

osu

re4.

2R

P/O

/AJ1

000/

OO

1S

yste

mM

alfu

nct

ions

Pag

e1

of

2

UN

US

UA

LE

VE

NT

AL

ER

TS

ITE

AR

EA

EM

ER

GE

NC

YG

EN

ER

AL

EM

ER

GE

NC

Y

RC

SL

EA

KA

GE

(BD

15)

OP

ER

AT

ING

MO

DE

:1,2

,3,4

A.

Uni

dent

ifie

dle

akage

10gp

m

B.

Pre

ssur

ebo

unda

ryle

akag

e10

gpm

C.

Iden

tifi

edle

akag

e25

gpm

Incl

udes

SOtu

bele

akag

e

2.U

NP

LA

NN

ED

LO

SS

OF

MO

ST

OR

AL

L1.

UN

PL

AN

NE

DL

OS

SO

FM

OS

TO

RA

LL

SA

FE

TY

SY

ST

EM

AN

NU

NC

IAT

ION

!S

AF

ET

YS

YS

TE

MA

NN

UN

CIA

TIO

N!

1.IN

AB

ILIT

YT

OM

ON

ITO

RA

IND

ICA

TIO

NIN

CO

NT

RO

LR

OO

MIN

DIC

AT

ION

INC

ON

TR

OL

RO

OM

SIG

NIF

ICA

NT

TR

AN

SIE

NT

IN

FO

R>

15M

INU

TE

S(B

D16

)

OP

ER

AT

ING

MO

DE

:1,

2,3

,4O

PE

RA

TIN

GM

OD

E:

1,2,

3,4

OP

ER

AT

ING

MO

DE

:1,

2,3,4

A.

Unp

lann

edlo

sso

f>50

%of

the

foll

owin

gA

.U

npla

nned

loss

of>

50%

ofth

efo

llow

ing

A.

Unp

lann

edlo

ssof>

50%

ofth

efo

llow

ing

annu

ncia

tors

onon

eun

itfo

r>15

min

utes

:an

nunc

iato

rson

one

unit

for>

15m

inut

es:

annu

ncia

tors

onon

eun

itfo

r>15

min

utes

:

Uni

ts1

&3

_________

Unit

sl&

3U

nit

sl&

31

SA

l,2,3

,4,5

,6,7

,8,9

,14

,15

,16

,&

18IS

A1,2

,3,4

,5,6

,7,8

,9,1

4,1

5,1

6,&

18

1S

A1,2

,3,4

,5,6

,7,8

,9,1

4,1

5,1

6,&

18

3S

Al,

2,3

,4,5

,6,7

,8,9

,14

,15

,16

,&

183S

A1

,2,3

,4,5

,6,7

,8,9

,14

,15,

16,&

18S

A1,2

,3,4

,5,6

,7,8

,9,

14,

15,

16,&

18

t2

Um

t2U

mt2

2S

Al,

2,3

,4,5

,6,7

,8,9

,14

,15

,&

162

SA

l,2,3

,4,

5,6

,7,

8,9

,14

,15

,&

162

SA

l,2,3

,4,

5,6

,7,8

,9,

14,

15,

&16

AN

D

__

AN

D

Los

sof

annu

ncia

tors

orin

dica

tors

requ

ires

Los

sof

annu

ncia

tors

orin

dica

tors

requ

ires

Asi

gnif

ican

ttr

ansi

ent

isin

prog

ress

addi

tion

alpe

rson

nel

(bey

ond

norm

alsh

ift

addi

tion

alpe

rson

nel

(bey

ond

norm

alsh

ift

com

plem

ent)

tosa

fely

oper

ate

the

unit

com

plem

ent)

tosa

fely

oper

ate

the

unit

AN

DL

oss

ofth

eO

AC

and

AL

LPA

Min

dica

tion

s(C

ON

TIN

UE

D)

—

Sig

nifi

cant

pla

nt

tran

sien

tin

prog

ress

OR

Inab

ilit

yto

dire

ctly

mon

itor

any

one

ofth

efo

llow

ing

func

tions

:

Los

sof

the

OA

Can

dA

LL

PAM

indi

cati

ons

1.S

ubcr

itic

alit

y(E

ND

)2.

Cor

eC

ooli

ng3.

Hea

tSi

nk4.

RC

SIn

tegr

ity5.

Con

tain

men

tIn

tegr

ity6.

RC

SIn

vent

oiy

=(E

ND

)

8

Encl

osu

re4.

2R

P/0

/A/1

000/

001

Sys

tem

Mal

funct

ions

Pag

e2

of

2

UN

US

UA

LE

VE

NT

AL

ER

TS

ITE

AR

EA

EM

ER

GE

NC

YG

EN

ER

AL

EM

ER

GE

NC

Y

3.IN

AB

ILIT

YT

OR

EA

CH

RE

QU

IRE

DS

HU

TD

OW

NW

ITH

INL

IMIT

S(B

D17

)

OP

ER

AT

ING

MO

DE

:1,2

,3,4

A.

Req

uire

dop

erat

ing

mod

eno

tre

ache

dw

ithin

TS

LC

Oac

tion

stat

emen

ttim

e

4.U

NP

LA

NN

ED

LO

SS

OF

AL

LO

NS

ITE

OR

OF

FS

ITE

CO

MM

UN

ICA

TIO

NS

(BD

18)

OP

ER

AT

ING

MO

DE

:A

ll

A,

Los

sof

all

onsi

teco

mm

unic

atio

nsca

pabi

lity

(Pla

ntph

one

syst

em,

PAsy

stem

,P

ager

syst

em,

Ons

ite

Rad

iosy

stem

)af

fect

ing

abili

tyto

perf

orm

Rou

tine

oper

atio

ns

13.

Los

sof

all

onsi

teco

mm

unic

atio

nsca

pabi

lity

(Sel

ecti

veSi

gnal

ing,

NR

CE

TS

lines

,O

ffsi

teR

adio

Syst

em,

AT

&T

line)

affe

ctin

gab

ility

toco

mm

unic

ate

with

offs

iteau

thoi

itie

s.

5.F

UE

LC

LA

DD

EG

RA

DA

TIO

N(B

D19

)

OP

ER

AT

ING

MO

DE

:A

ll:

A.

DE

I->

5lIC

i/m

l

(EN

D)

9

Encl

osu

re4.

3R

P/0

/A!1

000/

001

AN

YU

NP

LA

NN

ED

RE

LE

AS

EO

FG

AS

EO

US

OR

LIQ

UID

RA

DIO

AC

TIV

ITY

TO

TH

EE

NV

IRO

NM

EN

TT

HA

TE

XC

EE

DS

TW

OT

IME

ST

HE

SE

CL

IMIT

SF

OR

60M

INU

TE

SO

RL

ON

GE

R(B

D25

)

OP

ER

AT

ING

MO

DE

:A

ll

A.

Val

idin

dica

tion

onra

diat

ion

mon

itor

RTA

33of

4.06

E+

06cp

mfo

r>60

min

utes

(See

Not

e1)

B.

Val

idin

dica

tion

onra

diat

ion

mon

itor

RIA

-45

of>

9.35

E+

05cp

mor

RP

sam

ple

read

ingo

f6.

62E

-2uC

i/m

lX

e13

3eq

for>

60m

inut

es(S

eeN

ote

I)

C.

Liq

uid

effl

uent

bein

gre

leas

edex

ceed

stw

otim

esSL

C16

.11.

1fo

r>60

min

utes

asde

term

ined

byC

hem

istr

yP

roce

dure

D.

Gas

eous

effl

uent

bein

gre

leas

edex

ceed

stw

otim

esSL

C16

.11.

2fo

r>60

min

utes

asde

term

ined

byR

PP

roce

dure

1.A

NY

UN

PL

AN

NE

DR

EL

EA

SE

OF

GA

SE

OU

SO

RL

IQU

IDR

AD

IOA

CT

IVIT

YT

OT

HE

EN

VIR

ON

ME

NT

TH

AT

EX

CE

ED

S20

0T

IME

SR

AD

IOL

OG

ICA

LT

EC

HN

ICA

LS

PE

CIF

ICA

TIO

NS

FO

R15

MIN

UT

ES

OR

LO

NG

ER

(BD

30)

OP

ER

AT

ING

MO

DE

:A

ll

A.

Val

idin

dica

tion

ofR

IA-4

6of>

2.09

E+

04cp

mor

RP

sam

ple

read

ingof

6.62

uCi/m

iX

e13

3eq

for>

15m

inut

es.

(See

Not

eI)

BR

1A33

HIG

HA

larm

AN

D

Liq

uid

effl

uent

bein

gre

leas

edex

ceed

s20

0tim

esth

ele

vel

ofSL

C16

.11.

1fo

r>15

min

utes

asde

term

ined

byC

hem

istr

yPr

oced

ure

C.

Gas

eous

effl

uent

bein

gre

leas

edex

ceed

s20

0tim

esth

ele

vel

ofSL

C16

.11.

2fo

r>1

5m

inut

esas

dete

rmin

edby

RP

Pro

cedu

re

BO

UN

DA

RY

DO

SE

RE

SU

LT

ING

FR

OM

AC

TU

AL

/IM

MIN

EN

TR

EL

EA

SE

OF

GA

SE

OU

SA

CT

IVIT

Y(B

D35

)

OP

ER

AT

ING

MO

DE

:A

ll

Val

idre

adin

gon

RIA

46of>

2.09

E+

05cp

mor

RIA

56re

adin

gof

17.5

R/h

ror

RP

sam

ple

read

ing

of6.

62E

+01

uCi/m

IX

e13

3eq

for>

15m

inut

es(S

eeN

ote

2)

B.

Val

idre

adin

gon

RJA

57or

58as

show

non

Enc

losu

re4.

8(S

eeN

ote

2)

C.

Dos

eca

lcul

atio

nsre

sult

ina

dose

proj

ecti

onat

the

Sit

ebo

unda

ryof

:

100

mR

emT

ED

Eor

500

mR

emC

DE

adul

tth

yroi

d

D.

Fiel

dsu

rvey

resu

ltsin

dica

tesi

tebo

unda

rydo

sera

tes

exce

edin

gl0

0m

Rad

/hr

expe

cted

toco

ntin

uefo

rm

ore

than

one

hour

OR

Ana

lyse

sof

fiel

dsu

rvey

sam

ples

indi

cate

adul

tth

yroi

ddo

seco

mm

itm

ent

of50

0m

Rem

CD

E(3

.84F7

pCi/m

I)fo

ron

eho

urof

inha

lati

on

NO

TE

2:If

actu

alD

ose

Ass

essm

ent

cann

otbe

com

plet

edw

ithin

15m

inut

es,

then

the

vali

dra

diat

ion

mon

itor

read

ing

shou

ldbe

used

for

emer

genc

ycl

assi

fica

tion

.

(CO

NT

INU

ED

)

1.B

OU

ND

AR

YD

OS

ER

ES

UL

TIN

GF

RO

MA

CtU

AL

/IM

MIN

EN

TR

EL

EA

SE

OF

GA

SE

OU

SA

CT

IV1T

Y(B

D39

)

OP

ER

AT

ING

MO

DE

:A

ll

A.

Val

idre

adin

gon

RIA

46of>

2.09

E+

06cp

mor

RIA

56re

adin

gof

175

RIh

ror

RP

sam

ple

read

ing

of6.

62E

+O

2uC

i/ml

Xe

133

eqfo

rk15

min

utes

(See

Not

e3)

B.

Val

idre

adin

gon

RIA

57or

58as

show

non

Enc

losu

re4.

8(S

eeN

ote

3)

C.

Dos

eca

lcul

atio

nsre

sult

ina

dose

proj

ecti

onat

the

site

boun

dary

of:

1000

mR

emT

ED

E

OR 50

00m

Rem

CD

Ead

ult

thyr

oid

D.

Fiel

dsu

rvey

resu

ltsin

dica

tesi

tebo

unda

rydo

sera

tes

exce

edin

gl

000

mR

ad/h

rex

pect

edto

cont

inue

for

mor

eth

anon

eho

ur

OR

Ana

lyse

sof

fiel

dsu

rvey

sam

ples

indi

cate

adul

tth

yroi

ddo

seco

mm

itm

ento

f50

00m

Rem

CD

Efo

ron

eho

urof

inha

lati

on

NO

TE

3:If

actu

alD

ose

Ass

essm

ent

cann

otbe

com

plet

edw

ithin

15m

inut

es,t

hen

the

vali

dra

diat

ion

mon

itor

read

ing

shou

ldbe

used

for

emer

genc

ycl

assi

fica

tion

.

Ab

no

rmal

Rad

Lev

els/

Rad

iolo

gica

lE

fflu

ent

UN

US

UA

LE

VE

NT

AL

ER

Tj

SIT

EA

RE

AE

ME

RG

EN

CY

GE

NE

RA

LE

ME

RG

EN

CY

Pag

e1

of2

A.

(CO

NT

INU

ED

)

NO

TE

1:If

mon

itor

read

ing

issu

stai

ned

for

the

time

peri

odin

dica

ted

inth

eE

AL

AN

Dth

ere

quir

edas

sess

men

ts(p

roce

dure

calc

ulat

ions

)ca

nnot

beco

mpl

eted

with

inth

ispe

riod

,de

clar

atio

nm

ust

bem

ade

onth

eva

lid

Rad

iati

onM

onit

orre

adin

g.

(CO

NT

INU

ED

)

(EN

D1

10

Encl

osu

re4.

3A

bn

orm

alR

adL

evel

sfR

adio

logi

cal

Eff

luen

tR

P/0/

A/1

000/

001

Pag

e2

of

2

2U

NE

XP

EC

TE

DIN

CR

EA

SE

INP

LA

NT

RA

DIA

TIO

NO

RA

IRB

OR

NE

CO

NC

EN

TR

AT

ION

(BD

27)

OP

ER

AT

ING

MO

DE

:A

ll

A.

LT

5re

adin

g14

”an

dde

crea

sing

with

mak

eup

not

keep

ing

upw

ithle

akag

eW

ITH

fuel

inth

eco

re

B.

Val

idin

dica

tion

ofun

cont

roll

edw

ater

decr

ease

inth

eSF

Por

fuel

tran

sfer

cana

lw

ithal

lfu

elas

sem

blie

sre

mai

ning

cove

red

byw

ater

AN

D

Unp

lann

edV

alid

NA

3,6

orP

orta

ble

Are

aM

onit

orre

adin

gsin

crea

se.

C.

1R

Ihr

radi

atio

nre

adin

gat

one

foot

away

from

ada

mag

edst

orag

eca

sklo

cate

dat

the

ISFS

I

D.

Val

idar

eam

onit

orre

adin

gsex

ceed

sli

mit

sst

ated

inE

nclo

sure

4.9.

NO

TE

:T

his

Init

iati

ngC

ondi

tion

isal

solo

cate

din

Enc

losu

re4.

4.,

(Los

sof

Shut

dow

nFu

nctio

ns).

Hig

hra

diat

ion

leve

lsw

illal

sobe

seen

with

this

cond

ition

.

2.R

EL

EA

SE

OF

RA

DIO

AC

TIV

EM

AT

ER

IAL

OR

INC

RE

AS

ES

INR

AD

IAT

ION

LE

VE

LS

TH

AT

IMP

ED

ES

OP

ER

AT

ION

OF

SY

ST

EM

SR

EQ

UIR

ED

TO

MA

INT

AIN

SA

FE

OP

ER

AT

ION

OR

TO

ES

TA

BL

ISH

OR

MA

INT

AIN

CO

LD

SH

UT

DO

WN

(BD

32)

OP

ER

AT

ING

MO

DE

:A

ll

A.

Val

idra

diat

ion

read

ing

15rn

Rad

/hr

inC

R,

CA

S,or

Rad

was

teC

R

B.

Unp

lann

ed/u

nexp

ecte

dva

lid

area

mon

itor

read

ings

exce

edlim

itsst

ated

inE

nclo

sure

4.9

NO

TE

:T

hese

read

ings

may

also

bein

dica

tive

ofFi

ssio

nP

rodu

ctB

arri

erco

ncer

nsw

hich

mak

esa

revi

ewof

the

Fiss

ion

Pro

duct

Bar

rier

Mat

rix

nece

ssar

y. MA

JOR

DA

MA

GE

TO

IRR

AD

IAT

ED

FU

EL

OR

LO

SS

OF

WA

TE

RL

EV

EL

TH

AT

HA

SO

RW

ILL

RE

SU

LT

INT

HE

UN

CO

VE

RIN

GO

FIR

RA

DIA

TE

DF

UE

LO

UT

SID

ET

HE

RE

AC

TO

RV

ES

SE

L(B

D33

)

OP

ER

AT

ING

MO

DE

:A

ll

A.

Val

idN

A3*

,6

,41

,O

R49

*H

IGH

Ala

rm

*-

App

lies

toM

ode

6an

dN

oM

ode

Onl

y

B.

HIG

HA

larm

for

port

able

area

mon

itors

onth

em

ain

bndg

eor

SFP

brid

ge

C.

Rep

ort

ofvi

sual

obse

rvat

ion

ofir

radi

ated

fuel

unco

vere

d

D.

Ope

rato

rsde

term

ine

wat

erle

vel

drop

inei

ther

the

SFP

orfu

eltr

ansf

erca

nal

will

exce

edm

akeu

pca

paci

tysu

chth

atir

radi

ated

fuel

will

beun

cove

red

NO

TE

:T

his

Init

iati

ngC

ondi

tion

isal

solo

cate

din

Enc

losu

re4.

4.,

(Los

so

fSh

utdo

wn

Fun

ctio

ns).

Hig

hra

diat

ion

leve

lsw

illal

sobe

seen

with

this

cond

itio

n.

(EN

D)

2.L

OS

SO

FW

AT

ER

LE

VE

LIN

TH

ER

EA

CT

OR

VE

SS

EL

TH

AT

HA

SO

RW

ILL

UN

CO

VE

RF

UE

LIN

TH

ER

EA

CT

OR

VE

SS

EL

(BD

38)

OP

ER

AT

ING

MO

DE

:5

,6

A.

Los

so

fal

lde

cay

heat

rem

oval

asin

dica

ted

byth

ein

abil

ity

tom

aint

ain

RC

Ste

mpe

ratu

rebe

low

200°

F

AN

D

LT

5in

dica

tes

0in

ches

afte

rin

itia

tion

ofR

CS

mak

eup

B.

Los

sof

all

deca

yhe

atre

mov

alas

indi

cate

dby

the

inab

ilit

yto

mai

ntai

nR

CS

tem

pera

ture

belo

w20

0°F

AN

D

Eit

her

trai

nul

tras

onic

leve

lin

dica

tion

less

than

0in

ches

and

decr

easi

ngaf

ter

init

iati

ono

fR

CS

mak

eup

NO

TE

:T

his

Init

iati

ngC

ondi

tion

isal

solo

cate

din

Enc

losu

re4.

4.,

(Los

sof

Shu

tdow

nF

unct

ions

).H

igh

radi

atio

nle

vels

will

also

bese

enw

ithth

isco

nditi

on.

UN

US

UA

LE

VE

NT

AL

ER

TS

ITE

AR

EA

EM

ER

GE

NC

YG

EN

ER

AL

EM

ER

GE

NC

Y

3.

(EN

D)

(EN

D))

11

Encl

osu

re4.

4R

P/O

/A!l

000/

OO

lL

oss

ofS

hutd

ow

nF

unct

ions

Pag

e1

of

2

UN

US

UA

LE

VE

NT

IA

LE

RT

SIT

EA

RE

AE

ME

RG

EN

CY

GE

NE

RA

LE

ME

RG

EN

CY

FA

ILU

RE

OF

RP

ST

OC

OM

PL

ET

EO

R1.

FA

ILU

RE

OF

RP

ST

OC

OM

PL

ET

EO

R1.

FA

ILU

RE

OF

RP

ST

OC

OM

PL

ET

EIN

ITIA

TE

AR

xS

CR

AM

(BD

44)

INIT

IAT

EA

Rx

SC

RA

M(B

D50

)

OP

ER

AT

ING

MO

DE

:1,

2O

PE

RA

TIN

GM

OD

E1,2

,3O

PE

RA

TIN

GM

OD

E:

1,2

(CO

NT

INU

ET

ON

EX

TP

AG

E)

A.

Val

idR

xtr

ipsi

gnal

rece

ived

orre

quir

edA

.V

alid

reac

tor

trip

sign

alre

ceiv

edor

requ

ired

A.

Val

idre

acto

rtr

ipsi

gnal

rece

ived

orre

quir

edW

ITH

OU

Tau

tom

atic

scra

mW

ITH

OU

Tau

tom

atic

scra

mW

ITH

OU

Tau

tom

atic

scra

m

AN

D—

AN

DD

SSha

sin

sert

edC

ontr

olR

ods

Man

ual

trip

from

the

Con

trol

Roo

mw

as

OR

DSS

has

NO

Tin

sert

edC

ontr

olR

ods

QI

—su

cces

sful

inre

duci

ngre

acto

rpo

wer

to<

Man

ual

trip

from

the

Con

trol

Roo

mis

5%su

cces

sful

and

reac

tor

pow

eris

less

AN

Dan

dde

crea

sing

than

5%an

dde

crea

sing

Man

ual

trip

from

the

Con

trol

Roo

mw

asN

OT

AN

Isu

cces

sful

inre

duci

ngre

acto

rpo

wer

tole

ssth

an5%

and

decr

easi

ngA

vera

geo

fth

e5

high

est

CE

TC

s1

20

00

Fon

ICC

M

2.IN

AB

ILIT

YT

OM

AIN

TA

INP

LA

NT

IN2.

CO

MP

LE

TE

LO

SS

OF

FU

NC

TIO

N(E

ND

)M

OD

ES

(CO

LD

SH

UT

DO

WN

)(B

D46

)N

EE

DE

DT

OA

CH

IEV

EO

RM

AIN

TA

INM

OD

E4

(HO

TS

HU

TD

OW

N)

(BD

51)

OP

ER

AT

ING

MO

DE

:5

,6O

PE

RA

TIN

GM

OD

E:

1,2

,3,4

A.

Los

sof

LPI

and/

orL

PSW

AN

DA

.A

vera

geo

fth

e5

high

est

CE

TC

sl2

000

F—

show

non

ICC

M

Inab

ility

tom

aint

ain

RC

Ste

mpe

ratu

reB

.U

nabl

eto

mai

ntai

nre

acto

rsu

bcri

tica

lbe

low

2000

Fas

indi

cate

dby

eith

ero

fthe

follo

win

g:C

.E

OP

dire

cts

feed

ing

SOfr

omSS

FA

SWP

orst

atio

nA

SWP

RC

Ste

mpe

ratu

reat

the

LPI

Pum

pS

ucti

on

(CO

NT

INU

ED

)

Ave

rage

ofth

e5

high

est

CE

TC

sas

indi

cate

dby

ICC

Mdi

spla

y

OR

Vis

ual

obse

rvat

ion

(CO

NT

INU

ED

)

_____________________________

12

Encl

osu

re4.

4L

oss

of

Sh

utd

ow

nF

unct

ions

RP

/0/A

/100

0/00

1P

age

2o

f2

1.U

NE

XP

EC

TE

DIN

CR

EA

SE

INP

LA

NT

RA

DIA

TIO

NO

RA

IRB

OR

NE

CO

NC

EN

TR

AT

ION

(BD

42)

OP

ER

AT

ING

MO

DE

:A

ll

A.

LT

5re

adin

g14

”an

dde

crea

sing

with

mak

eup

not

keep

ing

upw

ithle

akag

e31

11i1

fuel

inth

eco

re

B.

Val

idin

dica

tion

ofun

cono

-oll

edw

ater

decr

ease

inth

eSF

Por

fuel

tran

sfer

cana

lw

ithal

lfu

elas

sem

blie

sre

mai

ning

cove

red

byw

ater

AN

D

(Inp

lann

edV

alid

RIA

3,6or

Port

able

Are

aM

onit

orre

adin

gsin

crea

se.

C.

IR

/hr

radi

atio

nre

adin

gat

one

foot

away

from

ada

mag

edst

orag

eca

sklo

cate

dat

the

ISFS

I

D.

Val

idar

eam

onito

rre

adin

gsex

ceed

slim

itsst

ated

inE

nclo

sure

4.9.

NO

TE

:T

his

Init

iati

ngC

ondi

tion

isal

solo

cate

din

Enc

losu

re4.

3.,

(Abn

orm

alR

adL

evel

s/R

adio

logi

cal

Eff

luen

t).

Hig

hra

diat

ion

leve

lsw

illal

sobe

seen

with

this

cond

ition

.

MA

JOR

DA

MA

GE

TO

IRR

AD

IAT

ED

FU

EL

OR

LO

SS

OF

WA

TE

RL

EV

EL

TH

AT

HA

SO

RW

ILL

RE

SU

LT

INT

HE

UN

CO

VE

RIN

GO

FIR

RA

DIA

TE

DF

UE

LO

UT

SID

ET

HE

RE

AC

TO

RV

ES

SE

L(B

D48

)

OP

ER

AT

ING

MO

DE

:A

ll

A.V

alid

RIA

3*,

6,4

1,

OR

49*

HIG

HA

larm

*App

lies

toM

ode

6an

dN

oM

ode

Onl

y

B.

HIG

HA

larm

for

port

able

area

mon

itors

onth

em

ain

brid

geor

SFP

brid

ge

CR

epor

tof

visu

alob

serv

atio

nof

irra

diat

edfu

elun

cove

red

D.

Ope

rato

rsde

term

ine

wat

erle

vel

drop

inei

ther

the

SFP

orfu

eltr

ansf

erca

nal

will

exce

edm

akeu

pca

paci

tysu

chth

atir

radi

ated

fuel

will

beun

cove

red

NO

TE

:T

his

Init

iati

ngC

ondi

tion

isal

solo

cate

din

Enc

losu

re4.

3,(A

bnor

mal

Rad

Lev

els/

Rad

iolo

gica

lE

fflu

ent)

.H

igh

radi

atio

nle

vels

will

also

bese

enw

ithth

isco

nditi

on.

3.L

OS

SO

FW

AT

ER

LE

VE

LIN

TH

ER

EA

CT

OR

VE

SS

EL

TH

AT

HA

SO

RW

ILL

UN

CO

VE

RF

UE

LIN

TH

ER

EA

CT

OR

VE

SS

EL

(BD

52)

OP

ER

AT

ING

MO

DE

:5

,6

A.

Los

so

fal

lde

cay

heat

rem

oval

asin

dica

ted

byth

ein

abili

tyto

mai

ntai

nR

CS

tem

pera

ture

belo

w20

00F

AN

D

LT

-5in

dica

tes

0in

ches

afte

rin

itia

tion

ofR

CS

Mak

eup

B.

Los

sof

all

deca

yhe

atre

mov

alas

indi

cate

dby

the

inab

ilit

yto

mai

ntai

nR

CS

tem

pera

ture

belo

w20

0°F

AN

D

Eit

her

trai

nul

tras

onic

leve

lin

dica

tion

less

than

0in

ches

and

decr

easi

ngaf

ter

init

iati

onof

RC

Sm

akeu

p

NO

TE

:T

his

Init

iati

ngC

ondi

tion

isal

solo

cate

din

Enc

losu

re4.

3,(A

bnor

mal

Rad

Lev

els/

Rad

iolo

gica

lE

fflu

ent)

,H

igh

radi

atio

nle

vels

will

also

bese

enw

ithth

isco

nditi

on.

3.

UN

US

UA

LE

VE

NT

AL

ER

TS

ITE

AR

EA

EM

ER

GE

NC

YG

EN

ER

AL

EM

ER

GE

NC

Y

(EN

D)

(EN

D)

(EN

D)

13

Encl

osu

re4.

5L

oss

of

Po

wer

{4}

RP

/0/A

tl00

0/00

1Pa

ge1

of

I

UN

US

UA

LE

VE

NT

AL

ER

TS

ITE

AR

EA

EM

ER

GE

NC

YG

EN

ER

AL

EM

ER

GE

NC

Y

1.L

OS

SO

FA

LL

OF

FS

ITE

PO

WE

RT

OE

SS

EN

TIA

LB

US

SE

SF

OR

GR

EA

TE

RT

HA

N15

MIN

UT

ES

(BD

55)

OP

ER

AT

ING

MO

DE

:A

ll

A.

Uni

tau

xili

arie

sar

ebe

ing

supp

lied

from

Keo

wee

orC

T5

AN

D

Inab

ility

toen

ergi

zeei

ther

MFB

from

anof

fsite

sour

ce(e

ithe

rsw

itch

yard

)w

ithin

15m

inut

es.

1.L

OS

SO

FA

LL

OF

FS

ITE

AC

PO

WE

RA

ND

LO

SS

OF

AL

LO

NS

ITE

AC

PO

WE

RT

OE

SS

EN

TIA

LB

US

SE

S(B

D57

)

OP

ER

AT

ING

MO

DE

:5,6

Def

uele

d

A.

MFB

1an

d2

dc-e

nerg

ized

AN

D

Fai

lure

tore

stor

epo

wer

toat

leas

ton

eM

FBw

ithin

15m

inut

esfr

omth

elim

eo

flo

ssof

both

offs

itean

don

site

AC

pow

er

LO

SS

OF

AL

LO

FF

SIT

EA

CP

OW

ER

AN

DL

OS

SO

FA

LL

ON

SIT

EA

CP

OW

ER

TO

ES

SE

NT

IAL

BU

SS

ES

(BD

59)

OP

ER

AT

ING

MO

DE

:1

,2,3

,4

Failu

reto

rest

ore

pow

erto

atle

ast

one

MFB

with

in15

min

utes

from

the

lime

oflo

ssof

both

offs

itean

don

site

AC

pow

er

1.P

RO

LO

NG

ED

LO

SS

OF

AL

LO

FF

SIT

EP

OW

ER

AN

DO

NS

ITE

AC

PO

WE

R(B

D62

)

OP

ER

AT

ING

MO

DE

:1

,2,3

,4

A.

IvIF

B1

and

2dc

-ene

rgiz

ed

AN

D

SSF

fails

tom

aint

ain

Mod

e3

(Hot

Stan

dby)

{I

2.U

NP

LA

NV

ED

LO

SS

OF

RE

QU

IRE

DD

CP

OW

ER

FO

RG

RE

AT

ER

TH

AN

15M

INU

TE

S(B

D56

)

OP

ER

AT

ING

MO

DE

:5,6

A.

Unp

lann

edba

aof

vita

lD

Cpo

wer

tore

quir

edD

Cbu

sses

asin

dica

ted

bybu

svo

ltage

less

than

110

VD

C

AN

D

Failu

reto

rest

ore

pow

erto

atle

ast

one

requ

ired

DC

bus

wit

hin

15m

inut

esfr

omth

etim

eof

loss

(EN

D)

2.A

CP

OW

ER

CA

PA

BIL

ITY

TO

ES

SE

NT

IAL

BU

SS

ES

RE

DU

CE

DT

OA

SIN

GL

ES

OU

RC

EF

OR

GR

EA

TE

RT

HA

N15

MIN

UT

ES

(BD

58)

OP

ER

AT

ING

MO

DE

:1,2

,3,4

A,

AC

pow

erca

pabi

lity

has

been

degr

aded

toa

sing

lepo

wer

sour

cefo

r>15

min

utes

due

toth

elo

ssof

all

but

one

ofth

efo

llow

ing:

Uni

tN

orm

alT

rans

form

er(b

ackc

harg

ed)

Uni

tSU

Tra

nsfo

rmer

Ano

ther

Uni

tSU

Tra

nsfo

rmer

(ali

ed)

CT

4C

T5

(EN

D)

2.L

OS

SO

FA

LL

VIT

AL

DC

PO

WE

R(l

ID60

)

OP

ER

AT

ING

MO

DE

:1

,2,3

,4

A.

Unp

lann

edlo

ssof

vita

lD

Cpo

wer

tore

quir

edD

Cbu

sses

asin

dica

ted

bybu

svo

ltage

less

than

110

VD

C

AN

D

Failu

reto

rest

ore

pow

erto

atle

ast

one

requ

ired

DC

bus

with

in15

min

utes

from

the

time

oflo

ss

(EN

D)

At

leas

t one

ofth

efo

llow

ing

cond

ition

aex

ist:

Res

tora

tion

ofpo

wer

toat

leas

ton

eM

FBw

ithin

4ho

urs

isN

OT

likel

y

Indi

cati

ons

ofco

ntin

uing

degr

adat

ion

ofco

reco

olin

gba

sed

onF

issi

onP

rodu

ctB

arri

erm

onit

onng

(EN

D)

A.

MFB

Ian

d2

dc-e

nerg

ized

AN

D

AN

D

OR

Los

sof

Pow

er-

Em

erge

ncy

Act

ion

Lev

els

(EA

Ls)

appl

yto

the

abili

tyof

elec

tric

alen

ergy

tope

rfor

mits

inte

nded

func

tion,

reac

hits

inte

nded

equi

pmen

t.ex

.-

Ifbo

thM

FBs,

are

ener

gize

dbu

tal

l41

60V

swit

chge

aris

not

avai

labl

e,th

eel

ectr

ical

ener

gyca

nno

tre

ach

the

mot

ors

inte

nded

.T

here

sult

toth

epl

ant

isth

esa

me

asif

both

MF

Bs

wer

ede

-ene

rgiz

ed.

__________

____

__

__

______

{4}

14

Encl

osu

re4.

6R

P/O

IAI1

000I

OO

IF

ire/

Ex

plo

sio

ns

and

Sec

uri

tyA

ctio

ns{2

}{3

}Pa

ge1

of

2

UN

US

UA

LE

VE

NT

AL

ER

T[

SIT

EA

RE

AE

ME

RG

EN

CY

GE

NE

RA

LE

ME

RG

EN

CY

FIR

ES

/EX

PL

OS

ION

SW

ITH

INT

HE

1.F

IRE

/EX

PL

OS

ION

AF

FE

CT

ING

(CO

NT

INU

ET

ON

EX

TP

AG

E)

(CO

NT

INU

ET

ON

EX

TP

AG

E)

PL

AN

T(B

D65

)O

PE

RA

BIL

ITY

OF

PL

AN

TS

AF

ET

Y

____________

__________________

SY

ST

EM

SR

EQ

UIR

ED

TO

ES

TA

BL

ISH

/MA

INT

AIN

SA

FE

OP

ER

AT

ING

MO

DE

:A

llS

HU

TD

OW

N(B

D70

)

NO

TE

:W

ithin

the

plan

tm

eans

:

____

____

____

____

____

____

____

____

____

___

Tur

bine

Bui

ldin

g•

NO

TE

:O

nly

one

trai

nof

asy

stem

need

sto

Aux

iliar

yB

uild

ing

beaf

fect

edor

dam

aged

inor

der

tosa

tisf

yth

isR

eact

orB

uild

ing

cond

itio

n.ke

owee

Hyd

roT

rans

form

erY

ard

B3T

B4T

Serv

ice

Air

Die

sel

Com

pres

sors

A1i

re/e

xplo

sioi

isK

eow

eeH

ydro

&as

soci

ated

Tra

nsfo

i-m

ers

SSF

Aff

ecte

dsa

fety

-rel

ated

syst

empa

ram

eter

indi

cati

ons

show

degr

aded

petf

orm

ance

OR

A.

Fire

wit

hin

the

plan

tno

tex

ting

uish

edw

ithin

15m

inut

esof

Con

trol

Roo

mno

tifi

cati

onor

Pla

ntpe

rson

nel

repo

rtvi

sibl

eda

mag

eto

veri

fica

tion

ofa

Con

trol

Roo

mal

arm

perm

anen

tst

ruct

ures

oreq

uipm

ent

requ

ired

for

safe

shut

dow

nB

.U

nant

icip

ated

expl

osio

nw

ithin

the

plan

tre

sult

ing

invi

sibl

eda

mag

eto

perm

anen

t(C

onti

nued

)st

ruct

ures

/equ

ipm

ent

incl

udes

stea

mlin

ebr

eak

and

FDW

line

brea

k

(Con

tinu

ed)

15

Encl

osu

re4.

6F

ire/

Ex

plo

sio

ns

and

Sec

uri

tyA

ctio

ns{2

}{3

}

RP

/0/A

!l00

0/00

1P

age

2o

f2

UN

US

UA

LE

VE

NT

AL

ER

TS

ITE

AR

EA

EM

ER

GE

NC

YI

GE

NE

RA

LE

ME

RG

EN

CY

2.C

ON

FIR

ME

DS

EC

UR

ITY

CO

ND

ITIO

NO

RT

HR

EA

TW

HIC

HIN

DIC

AT

ES

AP

OT

EN

TIA

LD

EG

RA

DA

TIO

NiN

TH

EL

EV

EL

OF

SA

FE

TY

OF

TH

EP

LA

NT

(BD

67)

OP

ER

AT

ING

MO

DE

:A

ll

A.

Secu

rity

cond

itio

nth

atdo

esno

tin

volv

ea

HO

STIL

EA

CT

ION

asre

port

edby

the

Secu

rity

Shif

tSu

perv

isio

n.

B.

Acr

edib

lesi

te-s

peci

fic

secu

rity

thre

atno

tifi

cati

on

C.

Ava

lida

ted

noti

fica

tion

from

NR

Cpr

ovid

ing

info

rmat

ion

ofan

airc

raft

thre

at

3.O

TH

ER

CO

ND

ITIO

NS

EX

IST

WH

ICH

INT

HE

JUD

GE

ME

NT

OF

TH

EE

ME

RG

EN

CY

DIR

EC

TO

RW

AR

RA

NT

DE

CL

AR

AT

ION

OF

AN

OU

E.

(BD

69)

OP

ER

AT

ING

MO

DE

:A

ll

A.

Oth

erco

ndit

ions

exis

tw

hich

inth

ejud

gmen

tof

the

Em

erge

ncy

Dir

ecto

rin

dica

teth

atev

ents

are

inpr

ogre

ssor

have

occu

rred

whi

chin

dica

tea

pote

ntia

lde

grad

atio

nof

the

leve

lof

safe

tyof

the

plan

tor

indi

cate

ase

curi

tyth

reat

tofa

cili

typr

otec

tion

has

been

initi

ated

.N

ore

leas

esof

radi

oact

ive

mat

eria

lre

quir

ing

off-

site

resp

onse

orm

onit

orin

gar

eex

pect

edun

less

furt

her

degr

adat

ion

ofsa

fety

syst

ems

occu

rs.

(EN

D)

2H

OS

TIL

EA

CT

ION

WIT

HIN

TH

EO

WN

ER

CO

NT

RO

LL

ED

AR

EA

OR

AIR

BO

RN

EA

TT

AC

KT

HR

EA

T.

(BD

72)

A.

AH

OST

ILE

AC

TIO

Nis

occu

rlin

gor

has

occu

rred

with

inth

eO

WN

ER

CO

NT

RO

LL

ED

AR

EA

asre

port

edby

the

Sec

unty

Shif

tSu

perv

isio

n.

B.

Ava

lida

ted

noti

fica

tion

from

NR

Co

fan

AIR

LIN

ER

atta

ckth

reat

with

in30

min

utes

ofth

esi

te.

3.O

TH

ER

CO

ND

ITIO

NS

EX

IST

WH

ICH

INT

HE

JUD

GE

ME

NT

OF

TH

EE

ME

RG

EN

CY

DIR

EC

TO

RW

AR

RA

NT

DE

CL

AR

AT

ION

OF

AN

AL

ER

T(B

D75

)

OP

ER

AT

ING

MO

DE

:A

ll

A.

Oth

erco

ndit

ions

exis

tw

hich

inth

ejud

gmen

tof

the

Em

erge

ncy

Dir

ecto

rin

dica

teth

atev

ents

are

inpr

ogre

ssor

have

occu

rred

whi

chin

volv

ean

actu

alor

pote

ntia

lsu

bsta

ntia

lde

grad

atio

nof

the

leve

lof

safe

tyof

the

plan

tor

ase

cunt

yev

ent

that

invo

lves

prob

able

life

thre

aten

ing

risk

tosi

tepe

rson

nel

orda

mag

eto

site

equi

pmen

tbe

caus

eof

HO

STIL

EA

CT

ION

.A

nyre

leas

esar

eex

pect

edto

beli

mit

edto

smal

lfr

acti

ons

of

the

EPA

Pro

tect

ive

Act

ion

Gui

deli

neex

posu

rele

vels

.

(EN

D)

HO

ST

ILE

AC

TIO

Nw

ithi

nth

eP

RO

TE

CT

ED

AR

EA

(BD

76)

OP

ER

AT

ING

MO

DE

:A

ll

A.

AH

OST

ILE

AC

TIO

Nis

occu

rrin

gor

has

occu

rred

with

inth

eP

RO

TE

CT

ED

AR

EA

asre

port

edby

the

Secu

rity

Shif

tSu

perv

isio

n.

2.O

TH

ER

CO

ND

ITIO

NS

EX

IST

WH

ICH

INT

HE

JUD

GE

ME

NT

OF

TH

EE

ME

RG

EN

CY

DIR

EC

TO

RW

AR

RA

NT

DE

CL

AR

AT

ION

OF

AS

ITE

AR

EA

EM

ER

GE

NC

Y.

(BD

78)

OP

ER

AT

ING

MO

DE

:A

ll

A.

Oth

erco

ndit

ions

exis

tw

hich

inth

eju

dgm

ent

ofth

eE

mer

genc

yD

irec

tor

indi

cate

that

even

tsar

ein

prog

ress

orha

veoc

curr

edw

hich

invo

lve

actu

alor

likel

ym

ajor

failu

res

ofpl

ant

func

tion

sne

eded

for

prot

ecti

onof

the

publ

icor

HO

STIL

EA

CT

ION

that

resu

ltsin

inte

ntio

nal

dam

age

orm

alic

ious

acts

;(1

)to

war

dsi

tepe

rson

nel

oreq

uipm

ent

that

coul

dle

adto

the

likel

yfa

ilur

eof

or;

(2)

that

prev

ent

effe

ctiv

eac

cess

toeq

uipm

ent

need

edfo

rth

epr

otec

tion

ofth

epu

blic

.A

nyre

leas

esar

eno

tex

pect

edto

resu

ltin

expo

sure

leve

lsw

hich

exce

edE

PAP

rote

ctiv

eA

ctio

nG

uide

line

expo

sure

leve

lsbe

yond

the

site

boun

dary

.

(EN

D)

AH

OS

TIL

EA

CT

ION

RE

SU

LT

ING

INL

OS

SO

FP

HY

SIC

AL

CO

NT

RO

LO

FT

HE

FA

CIL

ITY

(BD

79)

OP

ER

AT

ING

MO

DE

:A

ll

A.

AH

OST

ILE

AC

TIO

Nha

soc

curr

edsu

chth

atpl

ant

pers

onne

lar

eun

able

toop

erat

eeq

uipm

ent

requ

ired

tom

aint

ain

safe

tyfu

ncti

ons

B.

AH

OST

ILE

AC

TIO

Nha

sca

used

failu

reof

Spe

ntFu

elC

ooli

ngSy

stem

san

dII

vIIv

IIN

ENT

fuel

dam

age

islik

ely

for

afr

eshl

yof

f-lo

aded

reac

tor

core

inpo

ol.

2.O

TH

ER

CO

ND

ITIO

NS

EX

IST

WH

ICH

INT

HE

JUD

GM

EN

TO

FT

HE

EM

ER

GE

NC

YD

IRE

CT

OR

WA

RR

AN

TD

EC

LA

RA

TIO

NO

FA

GE

NE

RA

LE

ME

RG

EN

CY

.(B

D81

)

OP

ER

AT

ING

MO

DE

:A

ll

A.

Oth

erco

ndit

ions

exis

tw

hich

inth

eju

dgm

ent

ofth

eE

mer

genc

yD

irec

tor

indi

cate

that

even

tsar

ein

prog

ress

orha

veoc

curr

edw

hich

invo

lve

actu

alor

IMM

INE

NT

subs

tant

ial

core

degr

adat

ion

orm

elti

ngw

ithpo

tent

ial

for

loss

ofco

ntai

nmen

tin

tegr

ityor

HO

STIL

EA

CT

ION

that

resu

ltsin

anac

tual

loss

of

phys

ical

cont

rol

of

the

faci

lity.

Rel

ease

sca

nbe

reas

onab

lyex

pect

edto

exce

edE

PA

Pro

tect

ive

Act

ion

Gui

deli

neex

posu

rele

vels

off-

site

for

mor

eth

anth

eim

med

iate

site

area

.

(EN

D)

16

1.N

AT

UR

AL

AN

DD

ES

TR

UC

TIV

EP

HE

NO

ME

NA

AF

FE

CT

ING

TH

EP

RO

TE

CT

ED

AR

EA

(BD

83)

OP

ER

AT

ING

MO

DE

:A

ll

A.

Tre

mor

felt

and

vali

dal

arm

onth

est

rong

mot

ion

acce

lero

grap

h

BT

orna

dost

okin

gw

ithin

Pro

tect

edA

rea

Bou

ndai

y

C.

Veh

icle

cras

hin

topl

ant

stru

ctur

es/s

yste

ms

wit

hin

the

Pro

tect

edA

rea

Bou

ndai

y

D.

Tur

bine

failu

rere

sult

ing

inca

sing

pene

trat

ion

orda

mag

eto

turb

ine

orge

nera

tor

seal

s

1.N

AT

UR

AL

AN

DD

ES

TR

UC

TIV

EP

HE

NO

ME

NA

AF

FE

CT

ING

TH

EP

LA

NT

VIT

AL

AR

EA

(BD

89)

OP

ER

AT

ING

MO

DE

:A

llA

.T

rem

orfe

ltan

dse

ism

ictr

igger

actu

ate

s(O

.05g

)

NO

TE

:O

nly

one

trai

nof

asa

fety

-rel

ated

syst

emne

eds

tobe

affe

cted

orda

mag

edin

orde

rto

satis

fyth

ese

cond

ition

s.

B.

Tom

ado,

high

win

ds,

mis

sile

sre

sult

ing

from

turb

ine

failu

re,

vehi

cle

cras

hes,

orot

her

cata

stro

phic

even

t.

Vis

ible

dam

age

tope

rman

ent

strn

ctur

esor

equi

pmen

tre

quir

edfo

rsa

fesh

utdo

wn

ofth

eun

it.

OR

Aff

ecte

dsa

fety

syst

empa

ram

eter

indi

cati

ons

show

degr

aded

perf

orm

ance

.

(CO

NT

INU

ED

)

Encl

osu

re4.

7R

P/O

/A!1

000/

OO

1N

atura

lD

isas

ters

,H

azar

ds

and

Oth

erC

ondit

ions

Aff

ecti

ngP

lan

tS

afet

yP

age

1o

f3

UN

US

UA

LE

VE

NT

AL

ER

TS

ITE

AR

EA

EM

ER

GE

NC

YG

EN

ER

AL

EM

ER

GE

NC

Y

(CO

NT

INU

ET

ON

EX

TP

AG

E)

(CO

NT

INU

ET

ON

EX

TP

AG

E)

(CO

NT

INU

ED

)

AN

D

17

Enc

losu

re4.

7N

atura

lD

isas

ters

,H

azar

ds

and

Oth

erC

ondi

tion

sA

ffec

ting

Pla

nt

Saf

ety

RP

/0/A

/100

0/00

1P

age

2o

f3

2.N

AT

UR

AL

AN

DD

ES

TR

UC

TIV

EP

HE

NO

ME

NA

AF

FE

CT

ING

KE

OW

EE

HY

DR

OC

ON

DIT

ION

B(l

ID85

)

OP

ER

AT

ING

MO

DE

:A

ll

A.

Res

ervo

irel

evat

ion

805.

0fe

etw

ithal

lsp

iliw

ayga

tes

open

and

the

lake

elev

atio

nco

ntin

ues

tous

e

B.

Seep

age

read

ings

incr

ease

orde

crea

segr

eatly

orse

epag

ew

ater

isca

rryi

nga

sign

ific

ant

amou

ntof

soil

part

icle

s

CN

ewar

eaof

seep

age

orw

etne

ss,

with

larg

eam

ount

sof

seep

age

wat

erob

serv

edon

dam

,da

mto

e,or

the

abut

men

ts

D.

Slid

eor

othe

rm

ovem

ent

ofth

eda

mor

abut

men

tsw

hich

coul

dde

velo

pin

toa

fail

ure

E.D

evel

opin

gfa

ilure

invo

lvin

gth

epo

wer

hous

eor

appu

rten

ant

stru

ctur

esan

dth

eop

erat

orbe

lieve

sth

esa

fety

ofth

est

ruct

ure

isqu

esti

onab

le

3.N

AT

UR

AL

AN

DD

ES

TR

UC

TIV

EP

HE

NO

ME

NA

AF

FE

CT

ING

JOC

AS

SE

EH

YD

RO

CO

ND

ITIO

NB

(BD

86)

OP

ER

AT

ING

MO

DE

:A

ll

A.

Con

diti

onB

has

been

decl

ared

for

the

Joca

ssee

Dam

RE

LE

AS

EO

FT

OX

IC/F

LA

MM

AB

LE

GA

SE

SJE

OP

AR

DIZ

ING

SY

ST

EM

SR

EQ

UIR

ED

TO

MA

INT

AIN

SA

FE

OP

ER

AT

ION

OR

ES

TA

BL

ISH

!M

AIN

TA

INM

OD

ES

(CO

LD

SH

UT

DO

WN

)(l

ID91

)

OP

ER

AT

ING

MO

DE

:A

llA

.R

epor

t/de

tect

ion

of

toxi

cga

ses

inco

ncen

trat

ions

that

will

beli

fe-t

hrea

teni

ngto

plan

tpe

rson

nel

B.

Rep

ort/

dete

ctio

nof

flam

mab

lega

ses

inco

ncen

trat

ions

that

will

affe

ctth

esa

feop

erat

ion

ofth

epl

ant:

•R

eact

orB

uild

ing

•A

uxili

ary

Bui

ldin

g•

Tur

bine

Bui

ldin

g•

Con

trol

Roo

m

OP

ER

AT

ING

MO

DE

:A

ll

A.

Tur

bine

Bui

ldin

gfl

ood

requ

irin

gus

eo

fA

P/l

,2,3

/A/l

700/

10,

(Tur

bine

Bui

ldin

gFl

ood)

4.C

ON

TR

OL

RO

OM

EV

AC

UA

TIO

NH

AS

BE

EN

INIT

IAT

ED

(BD

94)

CO

NT

RO

LR

OO

ME

VA

CU

AT

ION

AN

DP

LA

NT

CO

NT

RO

LC

AN

NO

TB

EE

ST

AB

LIS

HE

D(l

ID96

)

Con

trol

ofth

epl

ant

cann

otbe

esta

blis

hed

from

the

Aux

Shu

tdow

nPa

nel

orth

eSS

Fw

ithin

15m

inut

es

2.K

EO

WE

EH

YD

RO

DA

MF

AIL

UR

E(B

D97

)

OP

ER

AT

ING

MO

DE

:A

ll

Imm

inen

t/ac

tual

dam

failu

reex

ists

invo

lvin

gan

yof

the

follo

win

g:•

Keo

wee

Hyd

roD

am•

Litt

leR

iver

Dam

•D

ikes

A,

B,

C,

orD

•In

take

Can

alD

ike

•Jo

cass

eeD

am-

Con

diti

onA

(CO

NT

INU

ED

)

A.

Eva

cuat

ion

ofC

ontr

olR

oom

(CO

NT

INU

ED

)

AN

D

AN

DO

NE

OF

TH

EF

OL

LO

WIN

G:

Pla

ntco

ntro

lIS

esta

blis

hed

from

the

Aux

shut

dow

nPa

nel

orth

eSS

FO

R

Pla

ntco

ntro

lIS

BE

ING

esta

blis

hed

from

the

Aux

Shut

dow

nPa

nel

orSS

F(C

ON

TIN

UE

D)

2.

UN

US

UA

LE

VE

NT

AL

ER

TS

ITE

AR

EA

EM

ER

GE

NC

YG

EN

ER

AL

EM

ER

GE

NC

Y

(CO

NT

INU

ET

ON

EX

TP

AG

E)

OP

ER

AT

ING

MO

DE

:A

ll

A.

Con

trol

Roo

mev

acua

tion

has

been

init

iate

d

AN

D

3.T

UR

BIN

EB

UIL

DIN

GF

LO

OD

(BD

93)

A.

OP

ER

AT

ING

MO

DE

:A

ll

18

Encl

osu

re4.

7R

P/O

/AI1

000/

OO

1N

atura

lD

isas

ters

,H

azar

ds

and

Oth

erC

ondit

ions

Aff

ecti

ngP

lant

Saf

ety

Pag

e3

of

3

UN

US

UA

LE

VE

NT

jA

LE

RT

SIT

EA

RE

AE

ME

RG

EN

CY

[G

EN

ER

AL

EM

ER

GE

NC

Y

4R

EL

EA

SE

OF

TO

XIC

OR

FL

AM

MA

BL

E5.

OT

HE

RC

ON

DIT

ION

SW

AR

RA

NT

3.O

TH

ER

CO

ND

ITIO

NS

WR

RA

NT

1.O

TH

ER

CO

ND

ITIO

NS

WA

RR

AN

TG

AS

ES

DE

EM

ED

DE

TR

IME

NT

AL

TO

SA

FE

CL

AS

SIF

ICA

TIO

NO

FA

NA

LE

RT

DE

CL

AR

AT

ION

OF

SIT

EA

RE

AD

EC

LA

RA

TIO

NO

FG

EN

ER

AL

OP

ER

AT

JON

OF

TH

EP

LA

NT

(BD

87)

(BD

95)

EM

ER

GE

NC

Y(B

D98

)E

ME

RG

EN

CY

(BD

99)

OP

ER

AT

ING

MO

DE

:A

llO

PE

RA

TIN

GM

OD

E:

All

OP

ER

AT

ING

MO

DE

:A

llO

PE

RA

TIN

GM

OD

E:

All

A.

Rep

ort/

dete

ctio

noft

oxic

orfl

amm

able

gase

sA

.E

mer

genc

yC

oord

inat

orju

dgm

ent

indi

cate

sA

Em

erge

ncy

Coo

rdin

ator

/EO

FD

irec

tor

A.

Em

erge

ncy

Coo

rdin

ator

/EO

FD

irec

tor

that

coul

den

ter

with

inth

esi

tear

eabo

unda

iyin

that

:ju

dgm

ent

judg

men

tin

dica

tes:

amou

nts

that

can

affe

ctno

rmal

oper

atio

nof

the

plan

tP

lant

safe

tym

aybe

degr

aded

Act

ual/

imm

inen

tsu

bsta

ntia

lco

re

(EN

D)

degr

adat

ion

with

pote

ntia

lfo

rlo

ssof

B.

Rep

ort

bylo

cal,

coun

ty,

stat

eof

fici

als

for

cont

ainm

ent

pote

ntia

lev

acua

tion

ofsi

tepe

rson

nel

base

don

offs

ite

even

tIn

crea

sed

mon

itor

ing

ofpl

ant

func

tion

sO

Ris

war

rant

ed

Pote

ntia

lfo

run

cont

roll

ed(E

ND

)ra

dion

ucli

dere

leas

esth

atw

ould

5.O

TH

ER

CO

ND

ITIO

NS

EX

IST

WH

ICH

resu

ltin

ado

sepr

ojec

tion

atth

e

WA

RR

AN

TD

EC

LA

RA

TIO

NO

FA

Nsi

tebo

unda

iygr

eate

rth

an10

00m

Rem

UN

USU

AL

EV

EN

T(B

D88

)T

ED

Eor

5000

mR

emC

DE

Adu

ltT

hyro

id

OP

ER

AT

ING

MO

DE

:A

ll(E

ND

)

A.

Em

erge

ncy

Coo

rdin

ator

dete

rmin

espo

tent

ial

degr

adat

ion

ofle

vel

ofsa

fety

has

occu

rred

(EN

D)

19

Encl

osu

re4.

8R

adia

tion

Mo

nit

or

Rea

din

gs

for

Em

erg

ency

Cla

ssif

icat

ion

RP/

O/A

/100

0/00

1Pa

ge1

of

1

All

RIA

valu

esar

eco

nsi

der

edG

RE

AT

ER

TH

AN

or

EO

UA

LT

O

HO

UR

SS

INC

ER

IA57

R/h

rR

IA58

RIh

r*

RE

AC

TO

RT

RIP

PE

DS

ite

Are

aE

mer

gen

cyG

ener

alE

mer

gen

cyS

ite

Are

aE

mer

gen

cyG

ener

alE

mer

gen

cy

0.0

-<

0.5

5.9E

+00

35.

9E+

004

2.6E

+00

32.

6E+

004

0.5

-<

1.0

2.6E

+00

32.

6E+

004

L1E

+00

31.

IE+

004

1.0-

<1.

51.

9E+0

031.

9E+

004

8.6E

+00

28.

6E+

003

1.5

-<2

.01.

9E+0

031.

9E+

004

8.5E

+00

28.

5E+

003

2.0

-<

2.5

1.4E

+003

1.4E

+00

46.

3E+

002

6.3E

+00

32.

5-

<3.

01.

2E+0

031.

2E+

004

5.7E

+00

25.

7E+

003

3.0

-<3.5

1.1E

+003

1.1E

+00

45.

2E+

002

5.2E

+00

33.

5-

<4.

01 .

OE

+003

I.O

E+0

044.

8E+

002

4.8E

+00

34.

0-

<8.

01.

OE

+003

1.O

E+0

044.

4E+

002

4.4E

+00

3

*R

IA58

isp

arti

ally

shie

lded

20

Encl

osu

re4.

9R

P/0/

A/1

000/

001

Unex

pec

ted/U

npla

nned

Incr

ease

InA

rea

Mo

nit

or

Rea

din

gs

Page

1o

f1

NO

TE

:T

his

Init

iati

ngC

ondi

tion

isno

tin

tend

edto

appl

yto

anti

cipa

ted

tem

pora

ryin

crea

ses

due

topl

anne

dev

ents

(e.g

.;in

core

dete

ctor

mov

emen

t,ra

dwas

teco

ntai

ner

mov

emen

t,de

plet

edre

sin

tran

sfer

s,et

c.).

UN

ITS

1,2

,3

MO

NIT

OR

NU

MB

ER

UN

US

UA

LE

VE

NT

l000x

AL

ER

T

NO

RM

AL

LE

VE

LS

mR

AD

/HR

mR

AD

/HR

RIA

7,H

otM

achi

neSh

opE

leva

tion

796

150

5000

RIA

8,H

otC

hem

istr

yL

abE

leva

tion

796

4200

5000

RIA

10,P

rim

ary

Sam

ple

Hoo

dE

leva

tion

796

830

5000

RIA

11,

Cha

nge

Roo

mE

leva

tion

796

210

5000

RIA

12,

Che

mM

ixT

ank

Ele

vati

on78

380

050

00R

IA13

,W

aste

Dis

posa

lSi

nkE

leva

tion

771

650

5000

RIA

15,H

P!R

oom

Ele

vati

on75

8N

OT

E*

5000

NO

TE

:R

IA15

norm

alre

adin

gsar

eap

prox

imat

ely

9m

Rad

/hr

ona

daily

basi

s.A

pply

ing

l000

xno

rmal

read

ings

wou

ldpu

tthi

sm

onit

orgr

eate

rth

an50

00m

Rad

/hr j

ust

for

anU

nusu

alE

vent

.F

orth

isre

ason

,an

Unu

sual

Eve

ntw

illN

OT

bede

clar

edfo

ra

read

ing

less

than

5000

mR

ad/h

r.

21

Enclosure 4.10 RP/O/A/l000/OOlDefinitions/Acronyms Page 1 of 5

1. List of Definitions and Acronyms

NOTE: Definitions are italicized throughout procedure for easy recognition.

1.1 ALERT - Events are in process or have occurred which involve an actual or potentialsubstantial degradation of the level of safety of the plant or a security event that involvesprobable life threatening risk to site personnel or damage to site equipment because ofHOSTILE ACTION. Any releases are expected to be limited to small fractions of the EPAProtective Action Guideline exposure levels.

1.2 BOMB — Refers to an explosive device suspected of having sufficient force to damage plantsystems or structures.

1.3 COGNIZANT FACILITY STAFF - any member of facility staff, who by virtue of trainingand experience, is qualified to assess the indications or reports for validity and to compare thesame to the EALs in the licenseetsemergency classification scheme. (Does not include staffwhose positions require they report, rather than assess, abnormal conditions to the facility.)

1.4 CONDITION A - Failure is Imminent or Has Occurred - A failure at the dam has occurred oris about to occur and minutes to days may be allowed to respond dependent upon theproximity to the dam.

1.5 CONDITION B - Potentially Hazardous Situation is Developing - A situation where failuremay develop, but preplanned actions taken during certain events (such as major floods,earthquakes, evidence of piping) may prevent or mitigate failure.

1.6 CIVIL DISTURBANCE - A group of persons violently protesting station operations oractivities at the site.

1.7 EXPLOSION - A rapid, violent, unconfined combustion, or catastrophic failure ofpressurized/energized equipment that imparts energy of sufficient force to potentially damagepermanent structures, systems, or components.

1.7 EXTORTION - An attempt to cause an action at the station by threat of force.

1.8 FIRE - Combustion characterized by heat and light. Sources of smoke, such as slipping drivebelts or overheated electrical equipment, do NOT constitutefires. Observation of flames ispreferred but is NOT required if large quantities of smoke and heat are observed.

1.9 FRESHLY OFF-LOADED CORE - The complete removal and relocation of all fuelassemblies from the reactor core and placed in the spent fuel pool. (Typical of a ‘No Modeoperation during a refuel outage that allows safety system maintenance to occur and results inmaximum decay heat load in the spent fuel pool system).

22

Enclosure 4.10 RP/0/A/1000/001Definitions/Acronyms Page 2 of 5

1.10 GENERAL EMERGENCY - Events are in process or have occurred which involve actual orimminent substantial core degradation or melting with potential for loss of containmentintegrity or HOSTILE ACTION that results in an actual loss of physical control of the facility.Releases can be reasonably expected to exceed EPA Protective Action Guidelines exposurelevels offsite for more than the immediate area.

.11 HOSTAGE - A person(s) held as leverage against the station to ensure demands will be metby the station.

1.12 HOSTILE ACTION - An act toward an NPP or its personnel that includes the use of violentforce to destroy equipment, takes HOSTAGES, and/or intimidates the licensee to achieve anend. This includes attack by air, land, or water using guns, explosives, PROJECTILES,vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overallintent may be included. HOSTILE ACTION should not be construed to include acts of civildisobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities, (e.g., violent acts betweenindividuals in the owner controlled area.)

1.13 HOSTILE FORCE - One or more individuals who are engaged in a determined assault,overtly or by stealth and deception, equipped with suitable weapons capable of killing,maiming, or causing destruction.

1.14 IMMINENT - Mitigation actions have been ineffective, additional actions are not expected tobe successful, and trended information indicates that the event or condition will occur. WhereIMMINENT timeframes are specified, they shall apply.

1.15 INTRUSION — A person(s) present in a specified area without authorization. Discovery of aBOMB in a specified area is indication of INTRUSION into that area by a HOSTILE FORCE.

1.16 INABILITY TO DIRECTLY MONITOR - Operational Aid Computer data points areunavailable or gauges/panel indications are NOT readily available to the operator.

1.17 LOSS OF POWER — Emergency Action Levels (EAL5) apply to the ability of electricalenergy to perform its intended function, reach its intended equipment. Ex. — If both MFBs,are energized but all 4160v switchgear is not available, the electrical energy can not reach themotors intended. The result to the plant is the same as if both MFBs were de-energized.

1.18 PROJECTILE — An object directed toward a NPP that could cause concern for its continuedoperability, reliability, or personnel safety.

1.19 PROTECTED AREA — Typically the site specific area which normally encompasses allcontrolled areas within the security PROTECTED AREA fence.

23

Enclosure 4.10 RP/0/A/1000/001Definitions/Acronyms Page 3 of 5

1.20 REACTOR COOLANT SYSTEM (RCS) LEAKAGE - RCS Operational Leakage asdefined in the Technical Specification Basis B 3.4.13:

RCS leakage includes leakage from connected systems up to and including the secondnormally closed valve for systems which do not penetrate containment and the outermostisolation valve for systems which penetrate containment.

A. Identified LEAKAGE

LEAKAGE to the containment from specifically known and located sources, but does notinclude pressure boundary LEAKAGE or controlled reactor coolant pump (RCP) sealleakoff (a normal function not considered LEAKAGE).

LEAKAGE, such as that from pump seals, gaskets, or valve packing (except RCP sealwater injection or leakoff), that is captured and conducted to collection systems or a sumpor collecting tank;

LEAKAGE through a steam generator (SG) to the Secondary System (primary tosecondary LEAKAGE): Primary to secondary LEAKAGE must be included in the totalcalculated for identified LEAKAGE.

B. Unidentified LEAKAGE

All LEAKAGE (except RCP seal water injection or leakoff) that is not identifiedLEAKAGE.

C. Pressure Boundary LEAKAGE

LEAKAGE (except primary to secondary LEAKAGE) through a nonisolable fault in anRCS component body, pipe wall or vessel wall.

1.21 RUPTURED (As relates to Steam Generator) - Existence of Primary to Secondary leakage ofa magnitude sufficient to require or cause a reactor trip and safety injection.

1.22 SABOTAGE - Deliberate damage, mis-alignment, or mis-operation of plant equipment withthe intent to render the equipment inoperable. Equipment found tampered with or damageddue to malicious mischief may not meet the definition of SABOTAGE until thisdetermination is made by security supervision.

1.23 SECURITY CONDITION — Any Security Event as listed in the approved securitycontingency plan that constitutes a threat/compromise to site security, threat/risk to sitepersonnel, or a potential degradation to the level of safety of the plant. A SECURITYCONDITION does not involve a HOSTILE ACTION.

1.24 SAFETY-RELATED SYSTEMS AREA - Any area within the Protected area whichcontains equipment, systems, components, or material, the failure, destruction, or release ofwhich could directly or indirectly endanger the public health and safety by exposure toradiation.

24

Enclosure 4.10 RP/0/A/l000/0O1Definitions/Acronyms Page 4 of 5

1.25 SELECTED LICENSEE COMMITMENT (SLC) -Chapter 16 of the FSAR

1.26 SIGNIFICANT PLANT TRANSIENT - An unplanned event involving one or more of thefollowing:

(1) Automatic turbine runback>25% thermal reactor power(2) Electrical load rejection >25% full electrical load(3) Reactor Trip(4) Safety Injection System Activation

1.27 SITE AREA EMERGENCY - Events are in process or have occurred which involve actualor likely major failures of plant functions needed for the protection of the public, orHOSTILE ACTION that results in intentional damage or malicious act; (1) toward sitepersonnel or equipment that could lead to the likely failure of or; (2) that prevents effectiveaccess to equipment needed for the protection of the public. Any releases are NOT expectedto result in exposure levels which exceed EPA Protective Action Guideline exposure levelsbeyond the Site Boundary.

1.28 SITE BOUNDARY - That area, including the ProtectedArea, in which DPC has theauthority to control all activities including exclusion or removal of personnel and property(1 mile radius from the center of Unit 2).\

1.29 TOXIC GAS - A gas that is dangerous to life or health by reason of inhalation or skin contact(e.g.; Chlorine).

1.30 UNCONTROLLED - Event is not the result of planned actions by the plant staff.

1.31 UNPLANNED - An event or action is UNPLANNED if it is not the expected result ofnormal operations, testing, or maintenance. Events that result in corrective or mitigativeactions being taken in accordance with abnormal or emergency procedures areUNPLANNED.

1.32 UNUSUAL EVENT - Events are in process or have occurred which indicate a potentialdegradation of the level of safety of the plant or indicate a security threat to facility protectionhas been initiated. No releases of radioactive material requiring offsite response ormonitoring are expected unless further degradation of safety systems occurs.

1.33 VALID - An indication or report or condition is considered to be VALID when it isconclusively verified by: (I) an instrument channel check; or, (2) indications on related orredundant instrumentation; or, (3) by direct observation by plant personnel such that doubtrelated to the instrument’s operability, the condition’s existence, or the report’s accuracy isremoved. Implicit with this defmition is the need for timely assessment.

25

Enclosure 4.10 RP/O/A/l000/OOlDefinitions/Acronyms Page 5 of 5

1.34 VIOLENT - Force has been used in an attempt to injure site personnel or damage plantproperty.

1.35 VISIBLE DAMAGE - Damage to equipment or structure that is readily observable withoutmeasurements, testing, or analyses. Damage is sufficient to cause concern regarding thecontinued operability or reliability of affected safety structure, system, or component.Example damage: deformation due to heat or impact, denting, penetration, rupture.

I .36 VITAL AREA - An area within the protected area where an individual is required to badge into gain access to the area that houses equipment important for nuclear safety. The failureor destruction of this equipment could directly or indirectly endanger the public health andsafety by exposure to radiation.

26

Enclosure 4.11 /O/A/1000/o0IOperating Modes Defined In Improved Page 1 of 1

Technical Specifications

MODES

REACTIVITY % RATED AVERAGECONDITION THERMAL REACTOR COOLANT

MODE TITLE POWER (a) TEMPERATURE(Keff) (°F)

1 Power Operation >0.99 > 5 NA

2 Startup 0.99 <5 NA

3 Hot Standby <0.99 NA 250

4 Hot Shutdown (b) < 0.99 NA 250 > T> 200

5 Cold Shutdown (b) < 0.99 NA < 200

6 Refueling (c) NA NA NA

(a) Excluding decay heat.

(b) All reactor vessel head closure bolts fully tensioned.

(c) One or more reactor vessel head closure bolts less than fully tensioned

27

Enclosure 4.12 /O/A/1ooo/oolInstructions For Using Enclosure 4.1 Page 1 of 2

1. Instructions For Using Enclosure 4.1 — Fission Product Barrier Matrix

1.1 If the unit was at Hot S/D or above, (Modes 1, 2, 3, or 4) and one or more fissionproduct barriers have been affected, refer to Enclosure 4.1, (Fission Product BarrierMatrix) and review the criteria listed to determine if the event should be classified.

1.1.1 For each Fission Product Barrier, review the associated EALs to determineif there is a Loss or Potential Loss of that barrier.

NOTE: An event with multiple events could occur which would result in the conclusion thatexceeding the loss or potential loss thresholds is imminent (i.e. within 1-3 hours). Inthis situation, use judgement and classif, as if the thresholds are exceeded.

1.2 Three possible outcomes exist for each barrier. No challenge, potential loss, or loss.Use the worst case for each barrier and the classification table at the bottom of thepage to determine appropriate classification.

1.3 The numbers in parentheses out beside the label for each column can be used toassist in determining the classification. If no EAL is met for a given barrier, thatbarrier will have 0 points. The points for the columns are as follows:

Barrier Failure Points

RCS Potential Loss 4

Loss 5

Fuel Clad Potential Loss 4

Loss 5

Containment Potential Loss 1

Loss 3

1.3.1 To determine the classification, add the highest point value for each barrierto determine a total for all barriers. Compare this total point value withthe numbers in parentheses beside each classification to see which oneapplies.

1.3.2 Finally as a verification of your decision, look below the EmergencyClassification you selected. The loss and/or potential loss EALs selectedfor each barrier should be described by one of the bullet statements.

28

Enclosure 4.12

Instructions For Using Enclosure 4.1 Page 2 of 2

EXAMPLE: Failure to properly isolate a ‘B’ MS Line Rupture outside containment, results inextremely severe overcooling.

PTS entry conditions were satisfied.

Stresses on the ‘B’ S/G resulted in failure of multiple S/G tubes.

RCS leakage through the S/G exceeds available makeup capacity as indicated byloss of subcooling margin.

Barrier EAL Failure Points

RCS SGTR> Makeup capacity of one HPT pump in Potential Loss 4normal makeup mode with letdown isolated

Entry into PTS operating range Potential Loss 4

RCS leak rate> available makeup capacity as Loss 5indicated by a loss of subcooling

Fuel Clad No EALs met and no justification for No 0classification on judgment

Challenge

Containment Failure of secondary side of SG results in a Loss 3direct opening to the environment

RCS 5 + Fuel 0 + Containment 3 = Total 8

A. Even though two Potential Loss EALs and one Loss EAL are met forthe RCS barrier, credit is only taken for the worst case (highest pointvalue) EAL, so the points from this barrier equal 5.

B. No EAL is satisfied for the Fuel Clad Barrier so the points for thisbarrier equal 0.

C. One Loss EAL is met for the Containment Barrier so the points forthis barrier equal 3.

D. When the total points are calculated the result is 8, therefore theclassification would be a Site Area Emergency.

E. Look in the box below “Site Area Emergency”. You have identified aloss of two barriers. This agrees with one of the bullet statements.The classification is correct.

29

References:

1. PIP 0-05-02980

2. PIP 0-05-4697

3. PIP 0-06-0404

4. PIP 0-06-03347

5. PIP 0-09-00234

6. PIP 0-10-1055

7. PIP 0-10-01750

8. PIPO-11-02811

9. PIP 0-12-1590

10. PIP 0-10-7809

11. PIPO-12-9201

12. PIP 0-12-9198

13. PIP 0-12-11227

Enclosure 4.13 RP!O/A/l000/oolReferences Page 1 of I

question: i (1 point) · question: 6 (1 point) given the following unit 2 conditions: rcs cooldown...

Documents