Text

Initial Exam 2014-302 Final SRO Written Exam
	ML15009A338
Person / Time
Site:	Oconee
Issue date:	01/09/2015
From:	; NRC/RGN-II
To:	; Duke Energy Carolinas
References
	50-269/OL-14, 50-270/OL-14, 50-287/OL-14
	Download: ML15009A338 (163)
	v • d • e

Oconee Nuclear Station Question:

I 1LT46 ONSSRONRCExamination (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 decreasing o 2B Loop SCM = 0°F stable o 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. is

2. prevent pump damage that occurs from pumping a steam/water mixture B. 1, is

2. ensure RCPs are secured before the RCS can evolve to a void fraction of>

70%

C. 1. is NOT

2. prevent pump damage that occurs from pumping a steam/water mixture D. 1, is NOT

2. ensure RCPs are secured before the RCS can evolve to a void fraction of>

70%

Page 1 of 100

Oconee Nuclear Station Question:

2 1LT46 ONSSRONRCExamination (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 RCPs 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 should be(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).

Which ONE of the following completes the statements above?

A. 1. left running

2. ONLY the associated B. 1. left running

2. BOTH C. 1. secured

2. ONLY the associated D. 1. secured

2. BOTH Page 2 of 100

Oconee Nuclear Station Question: 3 IL T46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

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 Time 0402:30 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 Page 3 of 100

Oconee Nuclear Station Question:

4 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

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.

Which ONE of the following completes the statements above?

A. 1.65

2. 5.4 B. 1.74

2. 5.4 C. 1.65 2, 6.1 D. 1.74

2. 6.1 Page4oflOO

Oconee Nuclear Station Question: 5 1LT46 ONSSRONRCExamination (1 point)

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

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

Which ONE of the following completes the statements above?

A. 1 excessive RCS leakage

2. ANY B. 1. excessive RCS leakage

2. ALL C. 1. RCP shaft binding

2. ANY D. 1. RCP shaft binding

2. ALL Page 5 of 100

Oconee Nuclear Station Question:

6 1LT46 ONSSRONRCExainination (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 Heat Re mova A. 1 a backup to the Switchover mode of LPI

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

2. 2B and 20

0. 1. additional cooling capacity during 2/0 pump ops

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

2. 2B and 20 1age 6 of 100

Oconee Nuclear Station Question:

7 1LT46 ONSSRONRCExamination (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. has

2. does B. 1. has

2. does NOT C. 1. has NOT

2. does D. 1. has NOT

2. does NOT Page 7 of 100

Oconee Nuclear Station Question:

8 1LT46 ONSSRONRCExamination (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.

Which ONE of the following completes the statements above?

A. 1. subcooled

2. is B. 1. subcooled

2. is NOT C. 1. saturated

2. is D. 1. saturated

2. is NOT Page 8 of 100

Oconee Nuclear Station Question:

9 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

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) aligning HPI injection from the BWST.

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

Which ONE of the following completes the statements above?

A. 1. prior to

2. wear B. 1. priorto

2. NOT wear C. 1. after

2. wear D. 1, after

2. NOT wear Page 9 of 100

Oconee Nuclear Station Question:

10 1LT46 ONSSRO NRCExarnination (1 point)

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 feed rate allowed to EACH Steam Generator is limited to _(1 )_ gpm in order to prevent

_(2 )_.

Which ONE of the following completes the statement above?

A. 1. 100

2. damage to the Steam Generators B. 1. 100

2. an RCS overcooling event C 1.50

2. damage to the Steam Generators D. 150

2. an RCS overcooling event Page 10 of 100

Oconee Nuclear Station Question:

11 1LT46 ONSSRONRCExamination (1 point)

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 FAIL 100-8 (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 following the blackout.

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

Page 11 of 100

Oconee Nuclear Station Question:

12 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor trip from 100% power due to a loss of offsite power (Switchyard Isolation)

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 Which ONE of the following completes the statement above?

A. prevent exceeding CT-4 Overload Limits B. prevent exceeding CT-5 Overload Limits C. ensure Si 2 (STBY BUS 2 to MFB2) Breaker is operated within limits D. ensure adequate voltage to ES equipment during a subsequent LOCA Page 12 of 100

Oconee Nuclear Station Question:

13 1LT46 ONSSRONRCExamination (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 for Quadrant Power Tilt indications in accordance with OP/i /A/1105/014 (Control Room Instrumentation Operation And Information) Enclosure 4.13 (Reactor Parameter Information).

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

Which ONE of the following completes the statements above?

A. 1. is

2. 20%

B. 1. is

2. 40%

C. 1. is NOT

2. 20%

D. 1. is NOT

2. 40%

Page 13 of 100

Oconee Nuclear Station Question:

14 1LT46 ONS SRO NRC Examination (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 5 _(1) t rip.

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

Which ONE of the following completes the statements above?

A. 1.will NOT

2. one B. 1.will NOT

2. four C. 1.will

2. one D. 1.will

2. four Page 14 of 100

Oconee Nuclear Station Question:

15 1LT46 ONSSRONRCExamination (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 will INITIALLY be required to throttle 1 HP-31 in the _(2)_ direction.

Which ONE of the following completes the statements above?

A. 1. does

2. closed B. 1. does

2. open C. 1,does NOT

2. closed D. I.does NOT

2. open Page 15 of 100

Oconee Nuclear Station Question:

16 1LT46 ONSSRONRCExamination (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)_.

Which ONE of the following completes the statement above?

A. 1. may NOT

2. RCS pressure is decreasing B. 1. may NOT

2. CETCs are increasing C. 1. may

2. Pzr Level is increasing D. 1. may

2. CETCs are decreasing Page 16 of 100

Oconee Nuclear Station Question:

17 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

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. Operating

2. Can be secured with TDEFWP control switch before AFIS is reset B. 1. Operating

2. Can be secured with TDEFWP control switch ONLY after AFIS is reset C. 1. NOT operating

2. Can be started with TDEFWP control switch before AFIS is reset D. 1. NOT operating

2. Can be started with TDEFWP control switch ONLY after AFIS is reset Page 17 of 100

Oconee Nuclear Station Question:

18 1LT46 ONS SRO NRC Examination (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.

Which ONE of the following completes the statements above?

A. 1. 10

2. 532 B. 1.20

2. 532 C. 1.10

2. 525 D. 1.20

2. 525 Page 18 of 100

Oconee Nuclear Station Question: 19 1LT46 ONSSRONRCExamination (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).

Which ONE of the following completes the statements above?

A. 1.65

2. Local Linear Heat Rate limits are not exceeded B. 1.65

2. adequate margin in preparation for resetting RPS trip set points C. 1.55

2. Local Linear Heat Rate limits are not exceeded D. 1.55

2. adequate margin in preparation for resetting RPS trip set points Page 19 of 100

Oconee Nuclear Station Question:

20 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor in MODE 3 Current conditions:

1 DIB inverter DC Input breaker trips The associated source range power will be restored using the Which ONE of the following completes the statement above?

A. ASCO Switch B. Static Transfer Switch C. Manual Bypass Switch D. Inverter Bypass Switches Page 20 of 100

Oconee Nuclear Station Question: 21 1LT46 ONSSRONRCExamination (1 point>

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

A. 25 B. 24 C. 22 D. 19 Page 21 of 100

Oconee Nuclear Station Question: 22 1LT46 ONSSRONRCExarnination (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)_.

Which ONE of the following completes the statements above?

A. 1. will

2. setpoint is raised to provide for indication of RCS leakage B. 1. will

2. detector is removed from the Reactor Building C. 1. will NOT

2. setpoint is raised to provide for indication of RCS leakage D. 1. will NOT

2. detector is removed from the Reactor Building Page 22 of 100

Oconee Nuclear Station Question:

23 1LT46 ONSSRONRCExamination (1 point)

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 by observing 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.

Which ONE of the following completes the statements above?

A. 1. can

2. is B. 1. can

2. is NOT C. 1. can NOT

2. is D. 1. can NOT

2. is NOT Page 23 of 100

Oconee Nuclear Station Question:

24 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 2 conditions:

Initial conditions:

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 the reason for the action, in accordance with OMP 1-18 (Implementation Standard During Abnormal 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 Page 24 of 100

Oconee Nuclear Station Question: 25 1LT46 ONSSRONRCExarnination (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 Steam Generators in addition to the Main Feedwater pumps.

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

Which ONE of the following completes the statements above?

A. 1. are

2. do B. 1. are

2. do NOT C. 1. are NOT

2. do D. 1. are NOT

2. do NOT Page 25 of 100

Oconee Nuclear Station Question:

26 1LT46 ONSSRONRCExamination (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 Subsequent Actions.

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

Which ONE of the following completes the statements above?

A. 1. Loss of SCM

2. is B. 1. Loss of SCM

2. is NOT C. 1, Excessive Heat Transfer

2. is D. 1. Excessive Heat Transfer

2. is NOT Page 26 of 100

Oconee Nuclear Station Question:

27 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Time = 1200

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.

Which ONE of the following completes the statements above?

A. 1. greaterthan

2. is NOT B. 1. greaterthan

2. is C. 1. approximately

2. is NOT D. 1. approximately

2. is Page 27 of 100

Oconee Nuclear Station Question:

28 1LT46 ONSSRONRCExamination (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 when power stabilizes, 1 A loop Tc will be (2) 1 B loop Tc.

Which ONE of the following completes the statement above?

ASSUME NO OPERATOR ACTIONS A. 1. 20% per minute

2. less than B. 1. 20% per minute

2. approximately the same as C. 1. 25%perminute

2. less than D. 1. 25% per minute

2. approximately the same as Page 28 of 100

Oconee Nuclear Station Question:

29 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

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 RCP starting interlocks.

Which ONE of the following completes the statements above?

A. 1. will

2. will B. 1. will

2. will NOT C. 1. will NOT

2. will D. 1. will NOT

2. will NOT Page 29 of 100

Oconee Nuclear Station Question:

30 1LT46 ONSSRONRCExamination (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 to HAND _(2)_ stop the rod motion.

Which ONE of the following completes the statements above?

A. 1. inserting

2. will B. 1. inserting

2. will NOT C. 1. withdrawing

2. will D. 1. withdrawing

2. will NOT Page 30 of 100

Oconee Nuclear Station Question: 31 1LT46 ONSSRONRCExamination (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 Page 31 of 100

Oconee Nuclear Station Question:

32 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 3 conditions:

Reactor power 100%

3A Core Flood Tank o Pressure = 587 psig stable o Level = 12.87 ft stable

3B Core Flood Tank o Pressure = 629 psig stable o Level = 13.36 ft stable Which ONE of the following describes the potential adverse effect and its cause that could occur during a design basis large break LOCA?

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

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

0. 3B CFT wiN discharge too much inventory during the blow down phase and not cover the hotspot during re-flood due to OFT level.

D. 3B OFT will discharge too much inventory during the blow down phase and not cover the hotspot during re-flood due to OFT pressure.

Page 32 of 100

Oconee Nuclear Station Question:

33 1LT46 ONS SRO NRC Examination (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 the following describes:

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

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

A. 1. 159

2. stop the 1 B LPI pump AND 1 B RBS pump B. 1. 159

2. Maximize total LPI flow < 3100 gpm C. 1. 96

2. stop the 1 B LPI pump AND 1 B RBS pump D. 1. 96

2. Maximize total LPI flow < 3100 gpm Page 33 of 100

Oconee Nuclear Station Question:

34 IL T46 ONS SRO NRC Examination (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 Tank Level shall be maintained at a MAXIMUM of _(1)_ inches.

2) The Component Drain Pump _(2)_ automatically trip once Quench Tank level reaches 80 inches Which ONE of the following completes the statements above?

A. t90

2. will B. 1.90

2. will NOT C. 1. 100

2. will D. 1. 100

2. will NOT Page 34 of 100

Oconee Nuclear Station Question:

35 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

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 s isolated the MAXIMUM letdown flow is (2) gpm.

Which ONE of the following completes the statements above?

A. 1. stay the same 2.88 B. 1. stay the same

2. 125 C. 1. increase 2.88 D. 1. increase

2. 125 Page 35 of 100

Oconee Nuclear Station Question: 36 1LT46 ONS SRO NRC Examination (1 point)

Which ONE of the following sets of components are BOTH cooled by the Component Cooling 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 Page 36 of 100

Oconee Nuclear Station Question:

37 1LT46 ONS SRO NRC Examination (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.

Which ONE of the following completes the statements above?

ASSUME NO OPERATOR ACTIONS A. 1. will

2. has B. 1. will

2. has NOT C. 1. will NOT

2. has D. 1. will NOT

2. has NOT Page 37 of 100

Oconee Nuclear Station Question: 38 1LT46 ONSSRONRCExamination (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 prevent exceeding the Departure from Nucleate Boiling Ratio (DNBR) safety !imit?

A. Flux/Pump B. L0wRCS Pressure C. Flux/Flow/Imbalance D. High RCS Temperature Page 38 of 100

Oconee Nuclear Station Question:

39 1LT46 ONSSRONRCExamination (1 point)

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 two trip condition.

Which ONE of the following completes the statements above?

A. 1. ODD

2. one B. 1. ODD 2, two C. 1. EVEN

2. one D. 1. EVEN

2. two Page 39 of 100

Oconee Nuclear Station Question: 40 1LT46 ONSSRONRCExamination (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 to OPEN.

OPEN CLOSED Which ONE of the following completes the statements above?

1. has NOT

2. has NOT

1. has NOT

2. has ,Wt111 t2. 1. has

2. has NOT

1. has

2. has Page 40 of 100

Oconee Nuclear Station Question:

41 1LT46 ONSSRONRCExamination (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 the Reactor Building Spray pumps is _(1 )_ psig.

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

Which ONE of the following completes the statements above?

A. 1. 4.2

2. does NOT B. 1. 4.2

2. does C. 1. 11.5

2. does NOT D. 1. 11.5

2. does Page-fl of 100

Oconee Nuclear Station Question: 42 IL T46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

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 its safety function.

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

Which ONE of the following completes the statements above?

A. 1. will

2. entrain Iodine thus reducing offsite dose B. 1. will NOT

2. entrain Iodine thus reducing offsite dose C. 1. will

2. minimize hydrogen production D. 1. will NOT

2. minimize hydrogen production Page 42 of 100

Oconee Nuclear Station Question: 43 IL T46 ONS SRO NRC Examination (1 point)

Given the following Unit 3 conditions:

Initial conditions:

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) .

Which ONE of the following completes the statements above?

A. 1 close

2. close B. 1. close

2. remain open C. 1. remain open

2. close D. 1, remain open

2. remain open Page 43 of 100

Oconee Nuclear Station Question:

44 IL T46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions Initial 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. higher

2. OP/i /A11106/23 (High and Low Pressure Extraction)

B. 1. higher

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

C. 1. lower

2. OP/iIAIllO6/23 (High and Low Pressure Extraction)

D. 1. lower

2. OP!i/A/1106/002 (Condensate and FDWsystem)

Page 44 of 100

Oconee Nuclear Station Question:

45 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor power 100%

Current conditions:

Condenser vacuum = 18.5 inches Hg stable

1TA and 1TB de-energized SG levels will be automatically controlled at Which ONE of the following completes the statement above?

A. 25 inches Startup Range B. 30 inches XSUR C. 50% Operating Range D. 240 inchesXSUR Page 45 of 100

Oconee Nuclear Station Question: 46 1LT46 ONS SRO NRC Examination (1 point)

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

A. C LPSW pump B. 1CRBCU C. 1BMDEFWP D. 1BRBS pump Page 46 of 100

Oconee Nuclear Station Question:

47 1LT46 ONSSRONRCExamination (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 AND Standby Bus 2.

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

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

Page 47 of 100

Oconee Nuclear Station Question:

48 IL T46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

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 pump inoperable is (1)

2) Cross connecting (2) buses is required.

Which ONE of the following completes the statements above?

A. 1. immediately

2. IPA and IPB B. 1. immediately

2. 1PA,2PAand3PA C. 1. within one hour

2. 1PA and 1PB D. 1. within one hour

2. 1 PA, 2PA and 3PA Page 48 of 100

Oconee Nuclear Station Question: 49 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Time = 1200

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?

ASSUME NO OPERATOR ACTIONS 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 Page 49 of 100

Oconee Nuclear Station Question: 50 1LT46 ONSSRONRCExamination (1 point)

Which ONE of the following describes the operation of the Unit Vent Radiation Monitors RIA-45 and R46 when the switchover acceptance range setpoint is reached?

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

A. twill

2. only alarm and unit vent radiation level indication B. twill

2. the same interlock functions that R-45 performs C. twill NOT

2. only alarm and unit vent radiation level indication D. 1.willNOT

2. the same interlock functions that RU-45 performs Page 50 of 100

Oconee Nuclear Station Question:

51 1LT46 ONSSRONRCExamination (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 in accordance with 1API2O (Loss of Component Cooling).

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

Which ONE of the following completes the statements above?

A. 1. 140

2. increase B. 1. 140

2. remain unchanged

0. 1. 180

2. increase D. 1. 180

2. remain unchanged Page 51 of 100

Oconee Nuclear Station Question:

52 1LT46 ONSSRONRCExamination (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 Which ONE of the following completes the statement above?

A. Reactor ONLY B. Main Turbine ONLY C. Main Feedwater Pumps ONLY D. Reactor and Main Feedwater Pumps ONLY Page 52 of 100

Oconee Nuclear Station Question:

53 1LT46 ONSSRONRCExamination (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 control RCS 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 throttle TDEFWP speed Page 53 of 100

Oconee Nuclear Station Question: 54 1LT46 ONSSRONRCExamination (1 point>

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 result of the I RL-49 HIGH alarm.

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

Which ONE of the following completes the statements above?

A. 1. will

2. AP/26 (Loss of Decay Heat Removal)

B. 1. will

2. AP/2 (Excessive RCS Leakage)

C. 1. will NOT

2. AP/26 (Loss of Decay Heat Removal)

D. 1. will NOT

2. AP/2 (Excessive RCS Leakage)

Page 54 of 100

Oconee Nuclear Station Question: 55 IL T46 ONS SRO NRC Examination (1 point)

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 AUTOMATICALLY trip OFF?

A. Suction pressure = 5 of water vacuum B. 1 RIA45, 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 light is off on 1VB2 Page 55 of 100

Oconee Nuclear Station Question: 56 1LT46 ONSSRONRCExamination (1 point)

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 the following is the EARLIEST condition during a reactor startup where criticality should be expected?

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 Page 56 of 100

Oconee Nuclear Station Question: 57 1LT46 ONSSRONRCExamination (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 1BSGs 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).

Which ONE of the following completes the statements above?

A. 1. pressure

2. HPI Forced Cooling B. 1. pressure

2. SSFASW C. ttemperature

2. HPI Forced Cooling D. 1.temperature

2. 5SF ASW Page 57 of 100

Oconee Nuclear Station Question: 58 1LT46 ONSSRONRCExamination (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 with OP/i IA/i 105/014 (Control Room Instrumentation).

Which ONE of the following completes the statements above?

A. 1. did

2. is B. 1. did

2. is NOT C. 1. did NOT

2. is D. 1. did NOT

2. is NOT Page 58 of 100

Oconee Nuclear Station Question:

59 IL T46 ONS SRO NRC Examination (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 lOS Hand/Auto stations will _(2).

Which ONE of the following completes the statements above?

ASSUME NO OPERATOR ACTIONS A. 1. will

2. remain in HAND B. 1. will

2. revert to AUTO C. 1. will NOT

2. remain in HAND D. 1. will NOT

2. revert to AUTO Page 59 of 100

Oconee Nuclear Station Question:

60 1LT46 ONSSRONRCExamination (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 Fuel Pool 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. have

2. One B. 1. have

2. Two C. 1. have NOT

2. One D. 1. have NOT

2. Two Page 60 of 100

Oconee Nuclear Station Question:

61 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

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.

Which ONE of the following completes the statements above?

A. 1. closed

2. are B. 1. 50% open

2. are C. 1. closed

2. are NOT D. 1. 50% open

2. are NOT Page 61 of 100

Oconee Nuclear Station Question:

62 1LT46 ONSSRONRCExamination (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.

Which ONE of the following completes the statements above?

A. 1. 0400:00

2. are B. 1. 0400:00

2. are NOT C. 1. 0401:30

2. are D. 1, 0401:30

2. are NOT Page 62 of 100

Oconee Nuclear Station Question:

63 1LT46 ONS SRO NRC Examination (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 prior to re-initiating the release?

A. 1. Closes 1A GWD tank inlet AND outlet valves

2. is B. 1. Closes 1A GWD tank inlet AND outlet valves

2. is NOT C. 1. Closes 1A GWD tank outlet valves but does NOT close the 1A GWD tank inlet valves

2. is D. 1. Closes 1A GWD tank outlet valves but does NOT close the 1A GWD tank inlet valves

2. is NOT Page 63 of 100

Oconee Nuclear Station Question:

64 1LT46 ONSSRONRCExamination (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 Page 64 of 100

Oconee Nuclear Station Question: 65 1LT46 ONS SRO NRC Examination (1 point>

IA Pressure vs. Time 100 LU D

Cl)

LU U

1200 1210 1220 1230 TIME Based on the graph above, which ONE of the following describes the EARLIEST time at which SA-141 (SA to IA Controller) will automatically open?

A. 1207 B. 1210 C. 1212 D. 1215 Page 65 of 100

Oconee Nuclear Station Question: 66 1LT46 ONSSRONRCExamination (1 point>

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.

Which ONE of the following completes the statements above?

A. 1. may

2. is B. 1. may

2. is NOT C. 1. may NOT

2. is D. 1. may NOT

2. is NOT Page 66 of 100

Oconee Nuclear Station Question: 67 1LT46 ONSSRONRCExamination (1 point)

( (., .. *.

C N

,J Note: Drawing not representative of actual plant conditions.

Given the following Unit 1 conditions:

Initial 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 plant conditions.

Which ONE of the following completes the statements above?

A. 1. upper

2. will B. 1. upper

2. will NOT C. 1. lower

2. will D. 1. lower

2. will NOT Page 67 of 100

Oconee Nuclear Station Question: 68 1LT46 ONS SRO NRC Examination (1 point)

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 maintained within the Unit I & 2 Control Room (inside the CAD doors), with the following potential exception:

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

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

Which ONE of the following completes the statements above?

A. 1. three

2. 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. three

2. another qualified licensed operator with no other concurrent duties relieves the BOP/SSF operator and stays within the Unit 1 & 2 Control Room (inside the CAD doors) until the first individual returns (if SSF activation not required)

C, 1. four

2. 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. four

2. another qualified licensed operator with no other concurrent duties relieves the BOP/SSF operator and stays within the Unit I & 2 Control Room (inside the CAD doors) until the first individual returns (if SSF activation not required)

Page 68 of 100

Oconee Nuclear Station Question:

69 1LT46 ONSSRONRCExamination (1 point)

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 the Reactivity Manger PRIOR to Rod withdrawal.

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

Which ONE of the following completes the statements above?

A. 1. ALL

2. is B. 1. ALL

2. is NOT C. 1. ONLY the first

2. is D. 1. ONLYthefirst

2. is NOT Page 69 of 100

Oconee Nuclear Station Question:

70 1LT46 ONSSRONRCExamination (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) require direct observation of the breaker position by opening the breaker cubicle door.

Which ONE of the following completes the statements above?

A. 1.is

2. does B. 1. is

2. does NOT C. 1. is NOT

2. does D. 1. is NOT

2. does NOT Page 70 of 100

Oconee Nuclear Station Question: 71 1LT46 ONSSRONRCExamination (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 Room indication of Pressurizer level reaches _(1).

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

Which ONE of the following completes the statements above?

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 Page 71 of 100

Oconee Nuclear Station Question: 72 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

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. will

2. does B. 1. will

2. does NOT C. 1. will NOT

2. does D. 1. will NOT

2. does NOT Page 72 of 100

Oconee Nuclear Station Question:

73 1LT46 ONSSRONRCExamination (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) the normal 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.

Which ONE of the following completes the statements above?

A. 1. double

2. will B. 1. double

2. will NOT C. 1. half

2. will D. 1. half

2. will NOT Page 73 of 100

Oconee Nuclear Station Question:

74 1LT46 ONSSRONRCExamination (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 Operations Personnel), the j1)_ BOP will be dispatched to perform AP/25 (SSF Activation).

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 abve?

A. 1. Unit 1

2. ALL B. 1. Unit 1

2. all but ONE C. 1. Unit 2

2. ALL D. 1. Unit 2

2. all but ONE Page 74 of 100

Oconee Nuclear Station Question:

75 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

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 in operation?

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. 1.10

2. are B. 1.1A

2. are C. 1.1C

2. are NOT D. 1.1A

2. are NOT Page 75 of 100

Oconee Nuclear Station Question: 76 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

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 as the ROS Makeup pump _(1)_ require the 1HP-120 Travel Stop to be re-adjusted before considering it OPERABLE for LTOP?

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

Which ONE of the following completes the statements above?

A. 1. does

2. is B. 1. does

2. is NOT C. 1. does NOT

2. is D, 1. does NOT

2. is NOT Page 76 of 100

Oconee Nuclear Station Question: 77 1LT46 ONSSRONRCExamination (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 being closed _(2)_ make I RC-66 INOPERABLE.

Which ONE of the following completes the statements above?

A. 1. 2450

2. does B. 1. 2450

2. does NOT C. 1. 2500

2. does D. 1. 2500

2. does NOT Page 77 of 100

Oconee Nuclear Station Question:

78 IL T46 ONS SRO NRC Examination (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 stable o Both loop SCM = 14°F slowly increasing Time 1230

RVLIS indicates:

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

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

2) If EOP Enclosure 5.6 is being used at 1230, pressurizer level must be at least

> _(2)_ inches.

Which ONE of the following completes the statements above?

A. 1. can

2. 100 B. 1. can NOT

2. 100 C. 1. can

2. 200 D. 1,canNOT

2. 200 Page 78 of 100

Oconee Nuclear Station Question:

79 1LT46 ONSSRONRCExainination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

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 KVIC Panelboard 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)_.

Which ONE of the following completes the statements above?

A. 1. OPERABLE

2. OPERABLE B. 1. OPERABLE

2. INOPERABLE C. 1. INOPERABLE

2. OPERABLE D. 1. INOPERABLE

2. INOPERABLE Page 79 of 100

Oconee Nuclear Station Question:

80 IL T46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Reactor power = 100%

SOP and OATC are only ROs 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 and Emergency Events) the Procedure Director can direct that AP122 be performed in parallel with the EOP _(1 )_.

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

Which ONE of the following completes the statements above?

A. 1 immediately after Immediate Manual Actions and Symptoms Check are completed

2. on scale and increasing B. 1. immediately after Immediate Manual Actions and Symptoms Check are completed

2. >lO0inches C. 1. ONLY after RuleS (Main Steam Line Break) and EOP Enclosure 5.1 (ES Actuation) have been completed

2. on scale and increasing D. 1. ONLY after Rule 5 (Main Steam Line Break) and EOP Enclosure 5.1 (ES Actuation) have been completed

2. >100 inches Page 80 of 100

Oconee Nuclear Station Question:

81 1LT46 ONSSRONRCExamination (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 be maintained, following required actions in AP134, the next required procedure transition is to initiate _(2)_.

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A. 1. 725

2. Unit 1 EOP B. 1. 725

2. AP/1 (Unit Runback)

C. 1. 425

2. Unit 1 EOP D. 1. 425

2. AP/1 (Unit Runback)

Page 81 of 100

Oconee Nuclear Station Question:

82 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Time = 1200:

Reactor power = 85% stable

DeftaTcinHAND Time 1210:

ICS runback in progress

Reactor power as indicated below POWER RANGE NIS A A A A

+60 +60 125 126 125 125 100 +40 100 *40 100 .40 100 +40 80 +20 80 +20 80 +20 80 +20 0 60 0 60 0 60 0 60 40 20 40 -20E 40 -20 40 -20k 20-40 20-40 20-40 20-40 0 .60 60 0 60 0 60 V V V V

/ MB / IBM / 1MM / MM

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 limits provided by Tech Spec 3.2.3 (Quadrant Power Tilt> is j2)_?

REFERENCE PROVIDED A. 1. Dropped Control Rod

2. >3.50 B. 1. Dropped Control Rod

2. >7.11 C. 1.RCPtrip

2. >3.50 D. 1.RCPtrip

2. >7.11 Page 82 of 100

Oconee Nuclear Station Question:

83 1LT46 ONSSRONRCExarnination (1 point)

Given the following Unit 1 conditions:

Time = 0400

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 (SG B lowdown).

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

Which ONE of the following completes the statements above?

A. 1. are NOT

2. continue B. 1. are NOT 2, stop C. 1. are

2. continue D. 1. are

2. stop Page 83 of 100

Oconee Nuclear Station Question: 84 1LT46 ONSSRONRCExamination (1 point)

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 above conditions 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 Page 84 of 100

Oconee Nuclear Station Question:

85 1LT46 ONSSRONRCExamination (1 point>

Given the following Unit 1 conditions:

Reactor power = 100%

Breaker Status o ACB 4 Closed o PCB8-Open o 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), Keowee Hydro Unit-i is currently _(2).

Which ONE of the following completes the statements above?

A. 1. can

2. OPERABLE B. 1. can

2. INOPERABLE C. 1. can NOT

2. OPERABLE D. 1. can NOT

2. INOPERABLE Page 85 of 100

Oconee Nuclear Station Question:

86 1LT46 ONSSRONRCExarnination (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 action required?

REFERENCE PROVIDED A. RCS pressure and temperature exceed the limits that ensure brittle fracture prevention 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 fracture prevention 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 with TS 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 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in accordance with TS 3.4.12 Low Temperature Over Pressure Protection.

Page 86 of 100

Oconee Nuclear Station Question:

87 1LT46 ONSSRONRCExaminatjon (1 point)

Given the following Unit 1 conditions:

Time = 0600

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 Which ONE of the following completes the statement above?

REFERENCE PROVIDED A. NOT required to enter a CONDITION of Tech Spec 3.3.1 (RPS Instrumentation>; the reactor has automatically tripped and TS 13.1 no longer applies 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 3.3.1 ONLY D. Required to enter/have entered CONDITIONs A, B, and C of Tech Spec 3.3.1 Page 87 of 100

Oconee Nuclear Station Question: 88 1LT46 ONSSRONRCExamination (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 as follows:

A=353 psig B = 404 psig C 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.

Which ONE of the following completes the statement above?

REFERENCE PROVIDED A. 1. 3.0

2. are B. 1. 3.0

2. are NOT C. 1. 3.5

2. are D. 1. 3,5

2. are NOT Page 88 of 100

Oconee Nuclear Station Question:

89 1LT46 ONSSRONRCExamination (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)_ allowed once ALL additional requirements specified in the associated basis are satisfied.

Which ONE of the following completes the above statement?

A. 1. is

2. is B. 1. is

2. is NOT C. 1. is NOT 2is D. 1. is NOT

2. is NOT Page 89 of 100

Oconee Nuclear Station Question:

90 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit I conditions:

Time 0700

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 gpm o 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).

Which ONE of the following completes the statements above?

A. 1. should

2. OPERABLE B. 1. should

2. INOPERABLE C. 1. should NOT

2. OPERABLE D. 1. should NOT

2. INOPERABLE Page 90 of 100

Oconee Nuclear Station Question:

91 1LT46 ONS SRO NRC Examination (1 point)

Given the following Unit 1 conditions:

Time 1200:

Reactor startup in progress

Reactor power = 6E-3% stable on all WR Nis

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 to greater than 5% power.

Which ONE of the following completes the statements above?

A. 1.B

2. does B. 1.B

2. does NOT C. 1.C

2. does D. 1.C

2. does NOT Page 91 of 100

Oconee Nuclear Station Question:

92 1LT46 ONSSRONRCExamination (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 damage during withdrawal.

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

Which ONE of the following completes the statement above?

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 Page 92 of 100

Oconee Nuclear Station Question: 93 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Time = 1200

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.

Which ONE of the following completes the statements above?

A. 1. is

2. is B. 1. is

2. is NOT C. 1. isNOT

2. is D. 1. is NOT

2. is NOT Page 93 of 100

Oconee Nuclear Station Quest,on: 94 ILT46 ONSSRONRCExamination (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 Task Assignment (WOTA) Ready for Work.

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

Which ONE of the following completes the statements above?

A. 1. is

2. do B. 1.is

2. do NOT C. 1. is NOT

2. do D. 1. is NOT

2. do NOT Page 94 of 100

Oconee Nuclear Station Question:

95 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit I conditions:

SGTR tab in progress

RCS temperature = 530°F stable

1A SG isolated

3 RCPs 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 a Shutdown Margin verification is _(2) °F.

Which ONE of the following completes the statements above?

A. 1.SGTR

2. 240 B. 1.SGTR

2. 450 C. 1.FCD

2. 240 D. 1.FCD

2. 450 Page 95 of 100

Oconee Nuclear Station Question:

96 1LT46 ONSSRONRCExamination (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 Page 96 of 100

Oconee Nuclear Station Question:

97 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

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

Which ONE of the following completes the statement above?

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

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

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

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

Page 97 of 100

Oconee Nuclear Station Question:

98 1LT46 ONS SRO NRC Examination (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 the above release in accordance with OPI1-2/A111041018 (GWD System).

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

Which ONE of the following completes the statements above?

A. 1.is

2. 0.5 Rem in the event of a GWD tank rupture.

B. 1. is

2. 100 mrem during a planned GWD tank release.

C. 1. is NOT

2. 0.5 Rem in the event of a GWD tank rupture.

D. 1. is NOT

2. 100 mrem during a planned GWD tank release.

Page 98 of 100

Oconee Nuclear Station Question: 99 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit 1 conditions:

Initial conditions:

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 to mitigate the RCS leak.

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

Which ONE of the following completes the statements above?

A. 1. will

2. is B. 1. will

2. is NOT C. 1. will NOT

2. is D. 1. will NOT

2. is NOT Page 99 of 100

Oconee Nuclear Station Question: 100 1LT46 ONSSRONRCExamination (1 point)

Given the following Unit I conditions:

Time 1200

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 classification within 15 minutes.

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

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

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A. 1. would

2. ALERT B. 1. would

2. SITE AREA EMERGENCY C. 1. would NOT

2. ALERT D. 1. would NOT

2. SITE AREA EMERGENCY Page 100 of 100

Examination KEYfor: 1LT46 ONS SRO NRC Examin Question Answer Number 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 of 4

Examination KEY for: 1LT46 ONS SRO NRC Examin Question Answer Number 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 V

42 B 43 B V 44 C 45 D V 46 C 47 B V 48 B 49 A 50 B Printed 12/18/2014 10:51:0 7 AM Page 2 of 4

Examination KEYfor: 1LT46 ONS SRO NRC Examin Question Answer Number 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 Printed 12/18/2014 10:51:07 AM Page 3 of4

Examination KEY for: 1LT46 ONS SRO NRC Examin Question Answer Number 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 Printed 12/18/2014 10:51:07 AM Page 4 of 4

Oconee I Cycle 28 ONEI 0400-50 Rev 34 I j Page 25 of 33 105 105 I 00 : 100 Control Rod Position Setpo nts ,

95 11 Inoperable Rods 4 PumD Flow 95 90 I . R stricted 90 Operatior 85 85 80 80 75 75 70 : Unacceptable 70 Operation 65 65 U- i H 60 60 c 55 a

50 Acceptable 50 0 Oneration

- 45 45 40 40 35 1 35 30 30 25 25 I ii : :

20 20 I w

I

[i .I .

15 I 15 10 :__ : :10 Group6 :

5 : :, 5 5 1 - 25 35 45 55 b5 75 85 95 I rII ij HilL I 0 o 0 10 20 30 40 50 60 70 80 90 100 0 10 20 30 40 50 60 70 80 90 100 Group 5 I Group 7 Control Rod Position, % WD

It) 0 C) 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 CO ci)

CD Ic) cD CD 9

w z

0 D

C 0

U) 0

t3 0

0 C

0 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 -°Pi

ONEI-0400-50 Rev 34 Oconee I Cycle 28 Page 27 of 33

1 05 L 105 100

IItt1t 100 Control RodPos tion Setpoints 95 1 Inoperable Rod, 4 Pump Flow 95 90 90 85 85 80 80 75 75 70 70 65 65 0

Unacceptable 60 Operation 60 i55 55 0

0 50 Acceptable 50 0

Operation 45 45 0

40 40 35 35 30 30 25 25 20 20 15 15 10 10 5 Group 6 5 5 15 25 35 45 55 65 75 85 95 0 0 r 102030 40 50 60 70 80 90 100 j I 0 10 20 30 40 50 60 70 80 90 100

- I Group 5 Control Rod Position, % WD I Group 7

ONEI-0400-50 Rev 34 Oconee I Cycle 28 Page 28 of 33 105 105 100 100 95 95 90 90 85 85 80 80 75 75 70 70 65 65 U

60 55 I

50 50 0

C)

Ct 45 a) a::

40 40 35 35 30 30 25 25 20 20 15 15 10 10 5 S 0 0 10 10 20 30 40 5060 70 80 90 100 10 10 20 30 40 50 60 70 80 90 1001 Group 5 Group 7 Control Rod Position, % WD

Regulating Rod Position Limits 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Regulating Rod Position Limits LCO 3.2.1 Regulating rod groups shall be within the physical position, sequence, and overlap limits specified in the COLR.

NOTE Not 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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months sequence or overlap groups to within limits.

requirements not met.

(continued)

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

Regulating Rod Position Limits 3.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Regulating rod groups B.1 -NOTE-positioned in restricted Not applicable to or unacceptable region. regulating rod groups positioned in the restricted region.

Initiate boration to 15 minutes restore SDM to within the limits specified in the COLR.

AND B.2.1 Restore regulating 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months rod groups to within acceptable region.

OR B.2.2 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to less than or equal to THERMAL POWER allowed by regulating rod group position limits.

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

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

Regulating Rod Position Limits 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify regulating rod groups are within the In accordance with the sequence and overlap limits as specified in Surveillance Frequency the COLR. Control Program SR 3.2.1.2 Verify regulating rod groups meet the position In accordance with the limits 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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to in 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 1 Unit 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 the same 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 RCP NPSH 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 NPSH curve. This limits cumulative damage to the single operating pump caused by cavitation due to required 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 RCS Temp Max Heatup Rate {22}

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 1/2 hour period T 270°F <45°F in any 1/2 hour period T < 140°F 45°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period RCS depressurized < 45°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period Note: PT/1/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.

Enclosure 4.31 OP/O/A/I 108/001 Unit 1 RCS Heatup/Cooldown Curves Page 3 of 9 Unit 1 Wide Range Cooldown Curve 1

Tcold REACTOR COOLANT TEMPERATURE (°F) 0 100 200 300 400 500 600 700 2200 2200 2100 i- f 2100 2000 2000 1900 1900 20°F 1800 SUBCOOLD, -

1800 C 1700 C C

1700 C I

1600 cj 1500 -t 4

- (ID

-I (ID 1400 (ID (ID 1300 1300 z

T 1200 z LI I C C C C hop C

1000 Ei C 1000 900 -w ff1- 900 800 800 700 700 600 600 500 500 400 400 300 300 k1t *CPun p NPSHF 200 F 200 3OO°F 100 Lh I

SUBCOOLEII 100

-r 0 -

I-- I r ii n 0 0 100 200 300 400 500 600 700 Tcold REACTOR COOLANT TEMPERATURE (°F) UIWRCI) 54 FFPY, Rev. 0 Note: PT/1/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.

Enclosure 4.31 0PIO/A/1 108/001 Unit 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 RCP NPSH 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 NPSH curve. This limits cumulative damage to operating pump caused by cavitation due to required NPSH 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 Heatup/Cooldown Limits 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 hour0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 months period T> 270°F <45°F in any 1/2 hour period T < 140°F 45°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period RCS depressurized 45°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period Note: PT/1/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.

Enclosure 4.31 OP/O/A/1 108/00 1 Unit 1 RCS Heatup/Cooldown Curves Page 5 of 9 Unit 1 Wide Range Heatup Curve Tcold REACTOR COOLANT TEMPERATURE (°F) 0 100 200 300 400 500 600 700 2200 2200 2100 2100 2000 2000 C

1900 ii hiii:-

1900 C

C 1800 c,D liii ETh1T1 +/-

it 1400 I

z 1300 ++ 1300 <

C C :X C c-) 1200 1200 p

1100

iE:tE:t:1:

II lifi 1100 1000 __1_4_!rf.j__I_I iiiii*

- _1000 z 900 -1 800 700 :3;:ii- 700 600 I

HI :rt 600 500 __

500 h

400 400 300 300

-j- 4RCPump NPS1I 200 *TH IIrJT42 200

/-3O0F LLIf 100 __1iIi:: zzt 1 _LII_I I *II J 100 i

0 I F 0 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, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.

Enclosure 4.31 OP/O/A/1 108/00 1 Unit 1 RCS Heatup/Cooldown Curves Page 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. Minimize operating time below this line with single RCP in a loop operating to limit cumulative damage to operating 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.

Heatup/Cooldown Limits f RCS Temp T> 270°F Max Cooldown Rate

< 45°F in any 1/2 hour period RCS Temp T < 270°F Max Heatup Rate {22}

<25°F in any 1/2 hour period 140°F < T < 270°F < 20°F in any 1/2 hour period T> 270°F <45°F in any 1/2 hour period T < 140°F < 45°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period RCS depressurized < 45°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period Note: PT/1/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.

Enclosure 4.31 OP/O/A/I 108/001 Unit 1 RCS Heatup/Cooldown Curves Page 7 of 9 Unit 1 Low Range Cookiown Curve TCOId Reactor Coolant Temperature, °F 0 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400 600 575 550 1 - 550 Hi 525 H+/- -

525 500 475 tubcoc ad 500 475 450 ZE 450 425 +

425 0) 0)

ci) 400 400 0

0 a) a)

0) 375 375 0)

C C

350 350 325 325 a) itF\ D 300 24 a) 300 a) 275 275 C

ct: C Ca 250 I Subcoole 250 0 C-) tH_._-

LTOP LIMIT HNHF-t Ii . I 0 j r C-)

225 F H- Maintain \f,J__QTrJ. JL_ i!

T 1 FF PZRLev& LT1Pr1T 225 0 iJ <22Oinches 200 in this area r- C.)

.. ii..

H 200

N:

175

. 2z

. +/-: 175 150 -- .

150 125 kf

---rI H -

1-TR-b---

125 100 -

100 75 LTOP LIMIT WE - --

75

._ Maintain --

I.

PZRLeveI

,-1 50

<3lOpnches 50 in this area .

25 25 0 I

.0 0 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400 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, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.

Enclosure 4.31 OP/O/A/l 108/001 Unit 1 RCS Heatup/Cooldown Curves Page 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. Minimize operating time below this line with single RCP in a loop operating to limit cumulative damage to operating 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.

Heatup/Cooldown Limits RCS Temp Max Cooldown Rate {22} RCS Temp Max Fleatup 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 1/2 hour period T270°F <45°F in any 1/2 hour period T< 140°F 45°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period RCS depressurized <45°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period Note: PT/1/A/0600/001 (Periodic Instrument Surveillance) contains Enclosure (RCS Pressure, Temperature, Heatup and Cooldown Surveillance Sheet) for conditions when RCS pressure/temperature are changing.

Enclosure 4.31 OP/O/A/l 108/001 Unit 1 RCS Heatup/Cooldown Curves Page 9 of 9 Unit I Low Range Heatup Curve TCOld Reactor Coolant Temperature, 5 F 0 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400 600 600 575 uucieaf 575 550 r

550 525 .

525 i I -

4 ,. -I-500 - -.

500

..t..i. fjl 475 . -

3 -i Ii_

475 450 450 425

. 250°F 425 C)

(I)

Subcooled C)

C.

400 400 0)

C)

C (3

375 rft-- .

H- i2-375 ci) 350-350 C

-J -- - --

325-325 0)

D : -

4 L -J -

C,)

C,) 300 350F 300

0) Subcooled - - . . . . . . -

ci) 0 rf 275 -

C r - 275 (3 it! --

C

.E (3 0 250 -f 0 250 o C-) C 225 C-)

0 . LTOP Limit . - . - 225 i-0 (3

I 300 F

. Maintain -

lEE C)

0) 200 PZR Level (3

. Subcooled v 220 inches 200 0)

. I . -,

l in this area 175 I- I . -

175 150

+ 150

1 125 ioo 100

] : ,

-. Top Limit - I 75

- Maintain 50 t-- 4-t PZR Level 50

-. <3l0inches

- is this area 25 -

-:.ZL 25 0 E.Z L_ -

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

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

LTOP System 3.4.12 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 lift setpoint of 535 psig; and

b. Administrative controls implemented that assure 10 minutes are available 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 the most limiting LTOP event is not open.

NOTES

1. CFT isolation is only required when CFT pressure is greater than or equal to the maximum RCS pressure for the existing RCS temperature allowed by the pressure and temperature limit curves provided in Specification 3.4.3.

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

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

LTOP System 3.4.12 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. HPI activated. A.1 Initiate action to Immediately deactivate HPI.

B. A CFT not isolated B.1 Isolate affected OFT. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months when OFT pressure is greater than or equal to the maximum ROS pressure for existing temperature allowed by Specification 3.4.3.

C. Required Action and 0.1 Be in MODE 4 with 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion RCS temperature Time of Condition B not > 200°F.

met.

OR 0.2 Depressurize affected 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OFT to < 373 psig.

D. PORV inoperable. D.1 Restore PORV to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OPERABLE status.

E. Required Action and E.1 Be in MODE 3 with 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months associated Completion RCS average Time of Condition D not temperature met. > 325° F.

OR E.2 Depressurize RCS to 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months

< 100 psig.

(continued)

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

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Administrative Controls F.1 Provide compensatory 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months that assure measures to monitor 10 minutes are for initiation of an available to mitigate LTOP event.

consequences of an LTOP event not implemented.

G. Required Action and G.1 Depressurize the RCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion and establish an RCS Time of Condition F not vent path capable of met. mitigating the most limiting LTOP event.

H. Administrative Controls H.1 Restore system to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months that assure OPERABLE status.

10 minutes are available to mitigate the Q!

consequences of an LTOP event not H.2 Depressurize RCS and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months implemented and establish RCS vent PORV inoperable, path capable of mitigating the most OR limiting LTOP event.

LTOP System inoperable for any reason other than Condition A through Condition G.

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

RPS Instrumentation 3.3.1 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 3.3.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required channel A.1 Place channel in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for Unit(s) with inoperable. RPS digital upgrade not complete OR 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for Unit(s) with RPS digital upgrade complete B. Two or more required B.1 Enter the Condition Immediately channels inoperable, referenced in Table 3.3.1-1 for the OR Function.

Required Action and associated Completion Time of Condition A not met.

(continued)

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

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. As required by Ci Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action B.1 and referenced in AND Table 3.3.1-1.

C.2 Open all control rod 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months drive (CRD) trip breakers.

D. As required by D.1 Open all CRD trip 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action B.1 breakers.

and referenced in Table 3.3.1-1.

E. As required by El Reduce THERMAL 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action B.1 POWER < 30% RTP.

and referenced in Table 3.3.1-1.

F. As required by F.1 Reduce THERMAL 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action B.1 POWER < 2% RTP.

and referenced in Table 3.3.1-1.

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

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS NOTE Refer to Table 3.3.1-1 to determine which SRs apply to each RPS Function.

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.2 NOTE Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is 15% RTP.

Compare results of calorimetric heat balance In accordance with the calculation to the power range channel output Surveillance Frequency and adjust power range channel output if Control Program calorimetric exceeds power range channel output by 2% RTP.

SR 3.3.1.3 NOTE Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is 15% RTP.

Compare out of core measured AXIAL In accordance with the POWER IMBALANCE (API ) to incore 0 Surveillance Frequency measured AXIAL POWER IMBALANCE (API )

1 Control Program as follows:

0 (RTP!TP)(API (CS X API

))

1 = imbalance error where CS is CORRELATION SLOPE Adjust power range channel output if the absolute value of imbalance error is 2% RTP.

(continued)

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

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.4 NOTE Not applicable to Unit(s) with RPS digital upgrade complete.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.5 NOTE Only applicable to Unit(s) with RPS digital upgrade complete.

Manually verify the setpoints are correct. In accordance with the Surveillance Frequency Control Program SR 3.3.1.6 NOTE Only applicable to Unit(s) with RPS digital upgrade complete.

Manually actuate the output channel In accordance with the interposing relays. Surveillance Frequency Control Program SR 3.3.1.7 NOTE Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program OCONEE UNITS 1,2, &3 3.3.1-4 Amendment Nos. 372, 374, 373

RPS Instrumentation 3.3.1 Table 331-1 (page 1 of 2)

Reactor Protective System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED 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 psig SR 3.3.1.4 SR 3.3.1.5 SR 3.3.1.6 SR 3.3.1.7 OCONEE UNITS 1,2, & 3 3.3.1-5 Amendment Nos. 366, 368 & 367

RPS Instrumentation 3.31 Table 3.3.1-1 (page 2 of 2)

Reactor Protective System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS ACTION B.1 REQUIREMENTS VALUE (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 rod withdrawal.

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

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

ESPS Input Instrumentation 3.3.5 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 in Table 3.3.5-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5-1.

ACTIONS NOTE Separate Condition entry is allowed for each Parameter.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Place channel in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for Unit(s) with Parameters with one ESPS digital upgrade not channel inoperable, complete OR 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for Unit(s) with ESPS digital upgrade complete B. One or more B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Parameters with two or more channels AND inoperable.

B.2.1 NOTE QE Only required for RCS Pressure Low.

Required Action and associated Completion Time not met. Reduce RCS pressure 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

< 1750 psig.

AND (continued)

OCONEE UNITS 1, 2, & 3 3.3.5-1 Amendment Nos. 366, 368 & 367

ESPS Input Instrumentation 3.3.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2.2 NOTE Only required for RCS Pressure Low Low.

Reduce RCS pressure 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

< 900 psig.

AND B.2.3 NOTE Only required for Reactor Building Pressure High and High High.

Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program (continued)

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

ESPS Input Instrumentation a3.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.5.2 NOTE Only applicable to Unit(s) with ESPS digital upgrade complete.

Manually verify that the setpoints are correct. In accordance with the Surveillance Frequency Control Program SR 3.3.5.3 NOTE Not applicable to Unit(s) with ESPS digital upgrade complete.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.5.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program OCONEE UNITS 1, 2, & 3 3.3.5-3 Amendment Nos. 372, 374, 373 I

ESPS Input Instrumentation I 3.3.5 Table 3.3.5-1 (page 1 of 1)

Engineered Safeguards Protective System Input Instrumentation I APPLICABLE MODES 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 OCONEE UNITS 1, 2, & 3 3.3.5-4 Amendment Nos. 366, 368 & 367

Duke Energy -- - -

- Procedure No. --

Oconee Nuclear Station RP/O/A/1 000/001 Emergency Classification Revision No.

001 Electronic Reference No.

0p009A63 Reference Use PERFORMANCE I

* * * * * * * *

UNCONTROLLED FORPRTNT* * * * * * * * * *

(ISSUED) PDF Format

RP/O/A/1000/001 Page 2 of 6 Emergency Classification NOTE: This procedure is an implementing procedure to the Oconee Nuclear Site Emergency plan and must be forwarded to Emergency 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 an emergency condition.

1.2 This procedure identifies the four emergency classifications and their corresponding Emergency 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 in assessing emergency conditions:

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

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

1.4.3 The BASIS Document (Volume A, Section D of the Emergency Plan) is available 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 the Emergency Notification Form.

A. Information relating to the problem(s) on the other unit(s) will be captured on the Emergency Notification Form as shown in RP/0/A/1000/015A, (Offsite Communications From The Control Room),

RP/0/A/1000/015B, (Offsite Communications From The Technical Support Center) or SR/0/B/2000/004, (Notification to States and Counties from the Emergency Operations Facility).

1.4.5 IF An event occurs, AND A lower or higher plant operating mode is reached before the classification can be made, THEN The classification shall be based on the mode that existed at the time the event occurred.

2

RP/O/A/l000/OOl Page 3 of6 1.4.6 The Fission Product Barrier Matrix is applicable only to those events that occur at Mode 4 (Hot Shutdown) or higher.

A. An event that is recognized at Mode 5 (Cold Shutdown) or lower shall not be classified using the Fission Product Barrier Matrix.

1. Reference should be made to the additional enclosures that provide Emergency 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 concludes that the specified duration is exceeded or will be exceeded, (i.e.;

condition cannot be reasonably corrected before the duration elapses),

THEN Classify the event.

1.5.2 IF A plant condition exceeding EAL criteria is corrected before the specified 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 10CFR5O.72 may be required for the following step. Such a condition could occur, for example, if a follow up evaluation of an abnormal condition uncovers evidence that the condition was more severe than earlier believed.

1.5.3 IF A plant condition exceeding EAL criteria is not recognized at the time of occurrence, but is identified well after the condition has occurred (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/OO1 Page 4 of 6 1.5.4 IF An emergency classification was warranted, but the plant condition has been corrected prior to declaration and notification THEN The Emergency Coordinator must consider the potential that the initiating condition (e.g.; Failure of Reactor Protection System) may have caused plant damage that warrants augmenting the on shift personnel through activation of the Emergency Response Organization.

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 separate termiiation notification.

B. IF An Alert, Site Area Emergency, or General Emergency condition 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/EOF Director assessment determines that the Emergency Action Levels for the Initiating Condition have been exceeded.

4

RP/O/A/l000/OOl Page 5 of 6

2. Immediate Actions 2.1 Assessment, classification and declaration of any applicable emergency condition should be completed within 15 minutes after the availability of indications or information to cognizant 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 any protection 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 the categories 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 classification continues to be applicable.

5

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

3. Subsequent Actions 3.1 Continue to review the emergency conditions to assure the current classification continues 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

Enclosure 4.1 RP/0/A/ 1000/001 Fission Product Barrier Matrix Page 1 of 1 DETERMINE THE APPROPRIATE CLASSIFICATION USING THE TABLE BELOW: ADD POINTS TO CLASSIFY. SEE NOTE BELOW RCS BARRIERS (lID 5-7) FUEL CLAD BARRIERS (lID 8-9) CONTAINMENT BARRIERS (BD 10-13)

Potential Loss (4 Points) Loss (5 Points) Potential Loss (4 Points) Loss (5 Points) Potential Loss (1 Point) Loss (3 Points)

RCS Leakrate? 160 gpm RCS Leak rate that results in a loss Average of the 5 highest Average of the 5 highest CETC CETC 1200° F 15 minutes Rapid unexplained containment of subcooling. CETC 1200° F OR pressure decrease after increase 700° F CETC 700° F 15 minutes with a valid RVLS reading 0 containment pressure or sump level not consistent with LOCA SGTR ? 160 gpm Valid RVLS reading of 0 Coolant activity 300 llCi/ml DEl RB pressure? 59 psig Failure of secondary side of SG OR results in a direct opening to the RB pressure? 10 psig and no environment with SG Tube Leak RBCUorRBS lOgpmintheSAMESG NOTE: RVLS is NOT valid if one or more RCPs are running OR if Entiy into the PTS (Pressurized IRIA 57 or 58 reading? 1.0 RJhr LPI pump(s) are Hours RIA 57 OR RIA 58 Hours RIA 57 OR RIA 58 SG Tube Leak? 10 gpm exists in Thermal Shock) Operation running AND taking Since SD RIhr RJhr Since SD R/hr R/hr one SG.

NOTE: PTS is entered under 2 RIA 57 reading 1.6 Rlhr auction from the LPI drop line. 0- <0.5 ? 300 ? 150 0- <0.5 ? 1800 ? 860 the other SO has secondary side either of the following: 2 RIA 58 reading? 1.0 RJhr failure that results in a direct

. A cooldown below 400°F @ opening to the environment Jj 0.5 - < 2.0 ? 80 ? 40 0.5- < 2.0 ? 400 ? 195

> 100°F/hr. has occurred. 3RIA 57 or 58 reading 1.0 R/hr is being fed from the affected unit

. HPI has operated in the 2.0- 8.0 2.0- 8.0 ? 32 ? 16 ? 280 ? 130 injection mode while NO RCPs were operating.

HPI Forced Cooling RCS pressure spike? 2750 psig Hydrogen concentration ? 9% Containment isolation is incomplete and a release path to the environment exists Emergency CoordinatorfEOF Emergency Coordinator/EOF Emergency Coordinator/EOF Emergency Coordinator/EOF Director Emergency Coordinator/EOF Emergency CoordinatorlEOF Directorjudgment Directorjudgment Directorjudgment judgment Directorjudgment Direetorjudgment UNUSUAL EVENT (1-3 Total Points) ALERT (4-6 Total Points) SITE AREA EMERGENCY (7-10 Total Points) GENERAL EMERGENCY (11-13 Total Points)

OPERATING MODE: 1,2,3,4 OPERATING MODE: 1,2,3,4 OPERATING MODE: 1,2,3,4 OPERATING MODE: 1,2,3,4 4.1 .U. I Any potential loss of Containment 4.1. A. I Any potential loss or loss of the RCS 4 1 S 1 Loss of any two barriers 4.1 .G. I Loss of any Iwo barriers and potential loss of the third barrier 4.1 .U.2 Any loss of containment 4.1 .A.2 Any potential loss or loss of the Fuel 4.1.S.2 Loss of one barrier and potential loss of either Clad RCS or Fuel Clad Barriers 4.1.0.2 Loss of all three barriers 4.1.S.3 Potential loss of both the RCS and Fuel Clad Barriers NOTE:

An event with multiple events could occur which would result in the conclusion that exceeding the loss or potential loss threshold is IMMINENT (i.e., within 1-3 hours). In this IMMINENT LOSS situation, usejudgment and classify as if the thresholds are exceeded.

Referencing this matrix frequently will aid in determining a fission barrier failure or other upgrade criteria.

7

Enclosure 4.2 RP/O/AJ1000/OO1 System Malfunctions Page 1 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY RCSLEAKAGE(BD 15)

OPERATING MODE: 1,2,3,4 A. Unidentified leakage 10 gpm B. Pressure boundary leakage 10 gpm C. Identified leakage 25 gpm Includes SO tube leakage

2. UNPLANNED LOSS OF MOST OR ALL 1. UNPLANNED LOSS OF MOST OR ALL SAFETY SYSTEM ANNUNCIATION! SAFETY SYSTEM ANNUNCIATION! 1. INABILITY TO MONITOR A INDICATION IN CONTROL ROOM INDICATION IN CONTROL ROOM SIGNIFICANT TRANSIENT IN FOR> 15 MINUTES (BD 16)

OPERATING MODE: 1,2, 3,4 OPERATING MODE: 1,2, 3,4 OPERATING MODE: 1,2, 3,4 A. Unplanned loss of> 50% of the following A. Unplanned loss of> 50% of the following A. Unplanned loss of> 50% of the following annunciators on one unit for> 15 minutes: annunciators on one unit for> 15 minutes: annunciators on one unit for> 15 minutes:

Units 1 & 3 Unitsl&3 Unitsl&3 1 SAl, 2,3,4,5,6,7,8,9, 14, 15, 16, & 18 ISA1,2,3,4,5,6,7,8,9,14,15,16,&18 1SA1,2,3,4,5,6,7,8,9,14,15,16,&18 3 SAl, 2,3,4,5,6,7,8,9, 14, 15, 16, & 18 3SA1,2,3,4,5,6,7,8,9, 14,15, 16,& 18 SA1,2,3,4,5,6,7,8,9, 14, 15, 16,& 18 t2 Umt2 Umt2 2 SAl, 2,3,4,5,6,7,8,9, 14, 15, & 16 2 SAl, 2,3,4, 5,6,7, 8,9, 14, 15, & 16 2 SAl, 2,3,4, 5,6,7,8,9, 14, 15, & 16 AND AND Loss of annunciators or indicators requires Loss of annunciators or indicators requires A significant transient is in progress additional personnel (beyond normal shift additional personnel (beyond normal shift complement) to safely operate the unit complement) to safely operate the unit AND Loss of the OAC and ALL PAM indications (CONTINUED)

Significant plant transient in progress OR Inability to directly monitor any one of the following functions:

Loss of the OAC and ALL PAM indications

1. Subcriticality (END) 2. Core Cooling

3. Heat Sink

4. RCS Integrity

5. Containment Integrity

6. RCS Inventoiy

= (END) 8

Enclosure 4.2 RP/0/A/1 000/00 1 System Malfunctions Page 2 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY

3. INABILITY TO REACH REQUIRED SHUTDOWN WITHIN LIMITS (BD 17)

OPERATING MODE: 1,2,3,4 A. Required operating mode not reached within TS LCO action statement time

4. UNPLANNED LOSS OF ALL ONSITE OR OFFSITE COMMUNICATIONS (BD 18)

OPERATING MODE: All A, Loss of all onsite communications capability (Plant phone system, PA system, Pager system, Onsite Radio system) affecting ability to perform Routine operations

13. Loss of all onsite communications capability (Selective Signaling, NRC ETS lines, Offsite Radio System, AT&T line) affecting ability to communicate with offsite authoiities.

5. FUEL CLAD DEGRADATION (BD 19)

OPERATING MODE: All:

A. DEI->5lICi/ml (END) 9

Enclosure 4.3 RP/0/A!1 000/001 Abnormal Rad Levels/Radiological Effluent Page 1 of2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY j

ANY UNPLANNED RELEASE OF 1. ANY UNPLANNED RELEASE OF BOUNDARY DOSE RESULTING FROM 1. BOUNDARY DOSE RESULTING FROM GASEOUS OR LIQUID RADIOACTIVITY GASEOUS OR LIQUID RADIOACTIVITY ACTUAL/IMMINENT RELEASE OF ACtUAL/ IMMINENT RELEASE OF TO THE ENVIRONMENT THAT TO THE ENVIRONMENT THAT GASEOUS ACTIVITY (BD 35) GASEOUS ACTIV1TY (BD 39)

EXCEEDS TWO TIMES THE SEC EXCEEDS 200 TIMES RADIOLOGICAL LIMITS FOR 60 MINUTES OR LONGER TECHNICAL SPECIFICATIONS FOR 15 OPERATING MODE: All OPERATING MODE: All (BD 25) MINUTES OR LONGER (BD 30)

A. Valid reading on RIA 46 of> 2.09E+05 cpm or A. Valid reading on RIA 46 of> 2.09E+06 cpm or OPERATING MODE: All OPERATING MODE: All RIA 56 reading of 175 RIhr or RP sample RIA 56 reading of 17.5 R/hr or RP sample reading of 6.62E+01 uCi/mI Xe 133 eq for> reading of 6.62E+O2uCi/ml Xe 133 eq fork 15 A. Valid indication on radiation monitor RTA 33 A. Valid indication of RIA-46 of> 2.09 E+ 04 15 minutes (See Note 2) minutes (See Note 3) of 4.06E+06 cpm for> 60 minutes cpm or RP sample reading of 6.62 uCi/mi Xe (See Note 1) 133 eq for> 15 minutes. (See Note I) B. Valid reading on RJA 57 or 58 as shown on B. Valid reading on RIA 57 or 58 as shown on Enclosure 4.8 (See Note 2) Enclosure 4.8 (See Note 3)

B. Valid indication on radiation monitor RIA-45 B R1A33 HIGH Alarm of> 9.35E+05 cpm or RP sample reading of C. Dose calculations result in a dose projection at C. Dose calculations result in a dose projection at 6.62E-2uCi/ml Xe 133 eq for> 60 minutes AND the site boundary of:

the Site boundary of:

(See Note I)

Liquid effluent being released exceeds 200 100 mRem TEDE or 500 mRem CDE adult 1000 mRem TEDE C. Liquid effluent being released exceeds two times the level of SLC 16.11.1 for> 15 minutes thyroid times SLC 16.11.1 for> 60 minutes as as determined by Chemistry Procedure OR determined by Chemistry Procedure D. Field survey results indicate site boundary dose 5000 mRem CDE adult thyroid C. Gaseous effluent being released exceeds 200 D. Gaseous effluent being released exceeds two times the level of SLC 16.11.2 for >15 minutes rates exceeding l00 mRad/hr expected to times SLC 16.11.2 for> 60 minutes as as determined by RP Procedure continue for more than one hour D. Field survey results indicate site boundary dose determined by RP Procedure rates exceeding l 000 mRad/hr expected to OR continue for more than one hour Analyses of field survey samples indicate adult (CONTINUED)

OR thyroid dose commitment of 500 mRem CDE (3.84 F 7 pCi/mI) for one hour of Analyses of field survey samples indicate adult inhalation thyroid dose commitment of 5000 mRem CDE for one hour of inhalation NOTE 1: If monitor reading is sustained for the time period indicated in the EAL AND the required assessments (procedure NOTE 2: If actual Dose Assessment cannot calculations) cannot be completed within NOTE 3: If actual Dose Assessment cannot be completed within 15 minutes, then the this period, declaration must be made on the be completed within 15 minutes, then the valid radiation monitor reading should be valid Radiation Monitor reading. valid radiation monitor reading should be used for emergency classification.

used for emergency classification.

(CONTINUED)

(END1 10

Enclosure 4.3 RP/0/A/1 000/001 Abnormal Rad LevelsfRadiological Effluent Page 2 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 2 UNEXPECTED INCREASE IN PLANT 2. RELEASE OF RADIOACTIVE 2. LOSS OF WATER LEVEL IN THE RADIATION OR AIRBORNE MATERIAL OR INCREASES IN REACTOR VESSEL THAT HAS OR CONCENTRATION (BD 27) RADIATION LEVELS THAT IMPEDES WILL UNCOVER FUEL IN THE OPERATION OF SYSTEMS REQUIRED REACTOR VESSEL (BD 38)

OPERATING MODE: All TO MAINTAIN SAFE OPERATION OR TO ESTABLISH OR MAINTAIN COLD OPERATING MODE: 5,6 SHUTDOWN (BD 32)

A. LT 5 reading 14 and decreasing with makeup not keeping up with leakage WITH fuel in the OPERATING MODE: All A. Loss of all decay heat removal as indicated by core the inability to maintain RCS temperature A. Valid radiation reading 15 rnRad/hr in CR, below 200° F CAS, or Radwaste CR B. Valid indication of uncontrolled water decrease in the SFP or fuel transfer canal with all fuel B. Unplanned/unexpected valid area monitor AND assemblies remaining covered by water readings exceed limits stated in Enclosure 4.9 LT 5 indicates 0 inches after initiation of RCS NOTE: These readings may also be indicative of makeup AND Fission Product Barrier concerns which makes a review of the Fission Product Barrier Matrix Unplanned Valid NA 3, 6 or Portable Area necessary. B. Loss of all decay heat removal as indicated by Monitor readings increase. the inability to maintain RCS temperature

3. MAJOR DAMAGE TO IRRADIATED below 200° F C. 1 RIhr radiation reading at one foot away from FUEL OR LOSS OF WATER LEVEL THAT HAS OR WILL RESULT IN THE AND a damaged storage cask located at the ISFSI UNCOVERING OF IRRADIATED FUEL Either train ultrasonic level indication less than D. Valid area monitor readings exceeds limits OUTSIDE THE REACTOR VESSEL 0 inches and decreasing after initiation of RCS stated in Enclosure 4.9. (BD 33) makeup OPERATING MODE: All NOTE: This Initiating Condition is also located NOTE: This Initiating Condition is also in Enclosure 4.4., (Loss of Shutdown Functions). A. Valid NA 3*, 6,41, OR 49* HIGH Alarm located in Enclosure 4.4., (Loss of Shutdown High radiation levels will also be seen with this Functions). High radiation levels will also be

- Applies to Mode 6 and No Mode Only condition. seen with this condition.

B. HIGH Alarm for portable area monitors on the main bndge or SFP bridge C. Report of visual observation of irradiated fuel uncovered (END))

(END) D. Operators determine water level drop in either the SFP or fuel transfer canal will exceed makeup capacity such that irradiated fuel will be uncovered NOTE: This Initiating Condition is also located in Enclosure 4.4., (Loss of Shutdown Functions).

High radiation levels will also be seen with this condition.

(END) 11

Enclosure 4.4 RP/O/A!l000/OOl Loss of Shutdown Functions Page 1 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY I

FAILURE OF RPS TO COMPLETE OR 1. FAILURE OF RPS TO COMPLETE OR 1. FAILURE OF RPS TO COMPLETE INITIATE A Rx SCRAM (BD 44) INITIATE A Rx SCRAM (BD 50)

OPERATING MODE: 1,2 OPERATING MODE 1,2,3 OPERATING MODE: 1,2 (CONTINUE TO NEXT PAGE) A. Valid Rx trip signal received or required A. Valid reactor trip signal received or required A. Valid reactor trip signal received or required WITHOUT automatic scram WITHOUT automatic scram WITHOUT automatic scram AND AND DSS has inserted Control Rods Manual trip from the Control Room was OR DSS has NOT inserted Control Rods QI successful in reducing reactor power to <

Manual trip from the Control Room is 5%

successful and reactor power is less AND and decreasing than 5% and decreasing Manual trip from the Control Room was NOT ANI successful in reducing reactor power to less than 5% and decreasing Average of the 5 highest CETCs 12000 F on ICCM

2. INABILITY TO MAINTAIN PLANT IN 2. COMPLETE LOSS OF FUNCTION (END)

MODES (COLD SHUTDOWN) (BD 46) NEEDED TO ACHIEVE OR MAINTAIN MODE 4 (HOT SHUTDOWN) (BD 51)

OPERATING MODE: 5,6 OPERATING MODE: 1,2,3,4 A. Loss of LPI and/or LPSW A. Average of the 5 highest CETCs l2000 F AND shown on ICCM Inability to maintain RCS temperature B. Unable to maintain reactor subcritical below 2000 F as indicated by either of the following:

C. EOP directs feeding SO from SSF ASWP or station ASWP RCS temperature at the LPI Pump Suction (CONTINUED)

Average of the 5 highest CETCs as indicated by ICCM display OR Visual observation (CONTINUED) 12

Enclosure 4.4 RP/0/A/ 1000/001 Loss of Shutdown Functions Page 2 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY

1. UNEXPECTED INCREASE IN PLANT 3. MAJOR DAMAGE TO IRRADIATED 3. LOSS OF WATER LEVEL IN THE RADIATION OR AIRBORNE FUEL OR LOSS OF WATER LEVEL REACTOR VESSEL THAT HAS OR CONCENTRATION (BD 42) THAT HAS OR WILL RESULT IN THE WILL UNCOVER FUEL IN THE OPERATING MODE: All UNCOVERING OF IRRADIATED FUEL REACTOR VESSEL (BD 52)

OUTSIDE THE REACTOR VESSEL (BD 48) OPERATING MODE: 5,6 A. LT 5 reading 14 and decreasing with makeup not keeping up with leakage 3111i1 fuel in the core OPERATING MODE: All A. Loss of all decay heat removal as indicated by the inability to maintain RCS temperature A. Valid RIA 3*, 6,41, OR 49* HIGH Alarm below 2000 F B. Valid indication of uncono-olled water decrease in the SFP or fuel transfer canal with all fuel

Applies to Mode 6 and No Mode Only AND assemblies remaining covered by water B. HIGH Alarm for portable area monitors on the LT-5 indicates 0 inches after initiation of RCS AND main bridge or SFP bridge Makeup (Inplanned Valid RIA 3, 6or Portable Area B. Loss of all decay heat removal as indicated by Monitor readings increase. C Report of visual observation of irradiated fuel the inability to maintain RCS temperature uncovered below 200° F C. I R/hr radiation reading at one foot away from AND a damaged storage cask located at the ISFSI D. Operators determine water level drop in either the SFP or fuel transfer canal will exceed makeup capacity such that irradiated fuel will Either train ultrasonic level indication less than D. Valid area monitor readings exceeds limits 0 inches and decreasing after initiation of RCS stated in Enclosure 4.9. be uncovered makeup NOTE: This Initiating Condition is also located NOTE: This Initiating Condition is also located in Enclosure 4.3, (Abnormal Rad in Enclosure 4.3., (Abnormal Rad Levels/Radiological Effluent). High radiation NOTE: This Initiating Condition is also located Levels/Radiological Effluent). High radiation levels will also be seen with this condition. in Enclosure 4.3, (Abnormal Rad levels will also be seen with this condition. Levels/Radiological Effluent), High radiation levels will also be seen with this condition.

(END)

(END) 13

Enclosure 4.5 RP/0/Atl 000/001 Loss of Power {4} Page 1 of I UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY

1. LOSS OF ALL OFFSITE POWER TO 1. LOSS OF ALL OFFSITE AC POWER AND LOSS OF ALL OFFSITE AC POWER AND 1. PROLONGED LOSS OF ALL OFFSITE ESSENTIAL BUSSES FOR GREATER LOSS OF ALL ONSITE AC POWER TO LOSS OF ALL ONSITE AC POWER TO POWER AND ONSITE AC POWER THAN 15 MINUTES (BD 55) ESSENTIAL BUSSES (BD 57) ESSENTIAL BUSSES (BD 59) (BD62)

OPERATING MODE: All OPERATING MODE: 5,6 OPERATING MODE: 1,2,3,4 OPERATING MODE: 1,2,3,4 Defueled A. Unit auxiliaries are being supplied from A. MFB I and 2 dc-energized A. IvIFB 1 and 2 dc-energized Keowee or CT5 A. MFB 1 and 2 dc-energized AND AND AND AND Failure to restore power to at least one MFB SSF fails to maintain Mode 3 Failure to restore power to at least one MFB within 15 minutes from the lime of loss of (Hot Standby) within 15 minutes from the lime of loss of both

{I Inability to energize either MFB from an offsite both offsite and onsite AC power source (either switchyard) within 15 minutes. offsite and onsite AC power AND At least one of the following conditiona exist:

2. AC POWER CAPABILITY TO 2. LOSS OF ALL VITAL DC POWER

2. UNPLANVED LOSS OF REQUIRED DC ESSENTIAL BUSSES REDUCED TO A (lID 60) Restoration of power to at least one POWER FOR GREATER THAN 15 SINGLE SOURCE FOR GREATER THAN MFB within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is NOT likely MINUTES (BD 56) 15 MINUTES (BD 58) OPERATING MODE: 1,2,3,4 OR OPERATING MODE: 5,6 OPERATING MODE: 1,2,3,4 A. Unplanned loss of vital DC power to required Indications of continuing DC busses as indicated by bus voltage less than A. Unplanned baa of vital DC power to required degradation of core cooling based A, AC power capability has been degraded to a 110 VDC DC busses as indicated by bus voltage less on Fission Product Barrier single power source for> 15 minutes due to the monitonng than 110 VDC loss of all but one of the following: AND AND (END)

Unit Normal Transformer (backcharged) Failure to restore power to at least one required Unit SU Transformer DC bus within 15 minutes from the time of loss Failure to restore power to at least one required Another Unit SU Transformer (alied)

DC bus within 15 minutes from the time of loss CT4 (END)

CT5 (END)

(END)

Loss of Power Emergency Action Levels (EALs) apply to the ability of electrical energy 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 the motors intended. The result to the plant is the same as if both MFBs were de-energized. {4}

14

Enclosure 4.6 RP/OIAI1000IOOI Fire/Explosions and Security Actions {2} {3} Page 1 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY

[

FIRES/EXPL OSIONS WITHIN THE 1. FIRE/EXPLOSION AFFECTING (CONTINUE TO NEXT PAGE) (CONTINUE TO NEXT PAGE)

PLANT (BD 65) OPERABILITY OF PLANT SAFETY SYSTEMS REQUIRED TO ESTABLISH/MAINTAIN SAFE OPERATING MODE: All SHUTDOWN (BD 70)

NOTE: Within the plant means:

Turbine Building

NOTE: Only one train of a system needs to Auxiliary Building be affected or damaged in order to satisfy this Reactor Building condition.

keowee Hydro Transformer Yard B3T B4T Service Air Diesel Compressors A 1ire/explosioiis Keowee Hydro & associated Transfoi-mers SSF Affected safety-related system parameter indications show degraded petformance OR A. Fire within the plant not extinguished within 15 minutes of Control Room notification or Plant personnel report visible damage to verification of a Control Room alarm permanent structures or equipment required for safe shutdown B. Unanticipated explosion within the plant resulting in visible damage to permanent (Continued) structures/equipment includes steam line break and FDW line break (Continued) 15

Enclosure 4.6 RP/0/A!l 000/001 Fire/Explosions and Security Actions {2} {3} Page 2 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY I

2. CONFIRMED SECURITY CONDITION 2 HOSTILE ACTION WITHIN THE HOSTILE ACTION within the PROTECTED A HOSTILE ACTION RESULTING IN OR THREAT WHICH INDICATES A OWNER CONTROLLED AREA OR AREA (BD 76) LOSS OF PHYSICAL CONTROL OF POTENTIAL DEGRADATION iN THE AIRBORNE ATTACK THREAT. (BD 72) THE FACILITY (BD 79)

LEVEL OF SAFETY OFTHE PLANT (BD 67)

A. A HOSTILE ACTION is occurling or has OPERATING MODE: All OPERATING MODE: All occurred within the OWNER CONTROLLED OPERATING MODE: All AREA as reported by the Secunty Shift A. A HOSTILE ACTION is occurring or has A. A HOSTILE ACTION has occurred such that Supervision. occurred within the PROTECTED AREA as plant personnel are unable to operate A. Security condition that does not involve a reported by the Security Shift Supervision. equipment required to maintain safety HOSTILE ACTION as reported by the B. A validated notification from NRC of an functions Security Shift Supervision. AIRLINER attack threat within 30 minutes of 2. OTHER CONDITIONS EXIST WHICH IN the site. THE JUDGEMENT OF THE EMERGENCY B. A HOSTILE ACTION has caused failure of B. A credible site-specific security threat DIRECTOR WARRANT DECLARATION Spent Fuel Cooling Systems and notification OF A SITE AREA EMERGENCY. (BD 78) IIvIIvIINENT fuel damage is likely for a

3. OTHER CONDITIONS EXIST WHICH IN freshly off-loaded reactor core in pool.

C. A validated notification from NRC providing THE JUDGEMENT OF THE information of an aircraft threat EMERGENCY DIRECTOR WARRANT DECLARATION OF AN ALERT (BD 75) OPERATING MODE: All 2. OTHER CONDITIONS EXIST WHICH IN THE JUDGMENT OF THE

3. OTHER CONDITIONS EXIST WHICH A. Other conditions exist which in the judgment of EMERGENCY DIRECTOR WARRANT IN THE JUDGEMENT OF THE the Emergency Director indicate that events are in DECLARATION OF A GENERAL EMERGENCY DIRECTOR WARRANT progress or have occurred which involve actual or EMERGENCY. (BD 81)

DECLARATION OF A NOUE. (BD 69) OPERATING MODE: All likely major failures of plant functions needed for protection of the public or HOSTILE ACTION A. Other conditions exist which in thejudgment that results in intentional damage or malicious of the Emergency Director indicate that events acts; (1) toward site personnel or equipment that OPERATING MODE: All are in progress or have occurred which involve could lead to the likely failure of or; (2) that OPERATING MODE: All an actual or potential substantial degradation of prevent effective access to equipment needed for A. Other conditions exist which in thejudgment the level of safety of the plant or a secunty the protection of the public. Any releases are not A. Other conditions exist which in the judgment of the Emergency Director indicate that event that involves probable life threatening expected to result in exposure levels which of the Emergency Director indicate that events are in progress or have occurred which risk to site personnel or damage to site exceed EPA Protective Action Guideline events are in progress or have occurred indicate a potential degradation of the level of equipment because of HOSTILE ACTION.

exposure levels beyond the site boundary. which involve actual or IMMINENT safety of the plant or indicate a security threat Any releases are expected to be limited to small substantial core degradation or melting with to facility protection has been initiated. No fractions of the EPA Protective Action potential for loss of containment integrity or releases of radioactive material requiring off- Guideline exposure levels.

HOSTILE ACTION that results in an actual site response or monitoring are expected (END) loss of physical control of the facility.

unless further degradation of safety systems (END) Releases can be reasonably expected to occurs. exceed EPA Protective Action Guideline exposure levels off-site for more than the (END) immediate site area.

(END) 16

Enclosure 4.7 RP/O/A!1000/OO1 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety Page 1 of 3 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY

1. NATURAL AND DESTRUCTIVE 1. NATURAL AND DESTRUCTIVE PHENOMENA AFFECTING THE PHENOMENA AFFECTING THE PLANT (CONTINUE TO NEXT PAGE) (CONTINUE TO NEXT PAGE)

PROTECTED AREA (BD 83) VITAL AREA (BD 89)

OPERATING MODE: All OPERATING MODE: All A. Tremor felt and seismic trigger actuates (O.05g)

A. Tremor felt and valid alarm on the strong motion accelerograph NOTE: Only one train of a safety-related system needs to be affected or damaged in B Tornado stoking within Protected Area Boundaiy order to satisfy these conditions.

C. Vehicle crash into plant structures/systems B. Tomado, high winds, missiles resulting from within the Protected Area Boundaiy turbine failure, vehicle crashes, or other catastrophic event.

D. Turbine failure resulting in casing penetration or damage to turbine or generator seals AND Visible damage to permanent strnctures or equipment required for (CONTINUED) safe shutdown of the unit.

OR Affected safety system parameter indications show degraded performance.

(CONTINUED) 17

Enclosure 4.7 RP/0/A/1 000/00 1 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety Page 2 of 3 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY

2. NATURAL AND DESTRUCTIVE 2. RELEASE OF TOXIC/FLAMMABLE CONTROL ROOM EVACUATION AND PHENOMENA AFFECTING KEOWEE GASES JEOPARDIZING SYSTEMS PLANT CONTROL CANNOT BE HYDRO CONDITION B (lID 85) REQUIRED TO MAINTAIN SAFE ESTABLISHED (lID 96) (CONTINUE TO NEXT PAGE)

OPERATION OR ESTABLISH!

OPERATING MODE: All MAINTAIN MODES (COLD SHUTDOWN) (lID 91)

A. Reservoir elevation 805.0 feet with all OPERATING MODE: All spiliway gates open and the lake elevation OPERATING MODE: All continues to use A. Report/detection of toxic gases in A. Control Room evacuation has been initiated concentrations that will be life-threatening to B. Seepage readings increase or decrease greatly plant personnel AND or seepage water is carrying a significant amount of soil particles B. Report/detection of flammable gases in Control of the plant cannot be established from concentrations that will affect the safe the Aux Shutdown Panel or the SSF within 15 C New area of seepage or wetness, with large operation of the plant:

minutes amounts of seepage water observed on dam,

Reactor Building dam toe, or the abutments

Auxiliary Building

Turbine Building 2. KEOWEE HYDRO DAM FAILURE D. Slide or other movement of the dam or

Control Room (BD 97) abutments which could develop into a failure E. Developing failure involving the powerhouse or 3. TURBINE BUILDING FLOOD (BD 93) OPERATING MODE: All appurtenant structures and the operator believes the safety of the structure is questionable A. Imminent/actual dam failure exists involving OPERATING MODE: All any of the following:

Keowee Hydro Dam

3. NATURAL AND DESTRUCTIVE A. Turbine Building flood requiring use of

Little River Dam PHENOMENA AFFECTING JOCASSEE AP/l,2,3/A/l 700/10, (Turbine Building Flood)

Dikes A, B, C, or D HYDRO CONDITION B (BD 86)

Intake Canal Dike

Jocassee Dam Condition A

4. CONTROL ROOM EVACUATION HAS OPERATING MODE: All BEEN INITIATED (BD 94) (CONTINUED)

A. Condition B has been declared for the Jocassee OPERATING MODE: All Dam A. Evacuation of Control Room (CONTINUED)

AND ONE OF THE FOLLOWING:

AND Plant control IS established from the Aux shutdown Panel or the SSF OR Plant control IS BEING established from the Aux Shutdown Panel or SSF (CONTINUED) 18

Enclosure 4.7 RP/O/AI1000/OO1 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety Page 3 of 3 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4 RELEASE OF TOXIC OR FLAMMABLE j 5. OTHER CONDITIONS WARRANT 3. OTHER CONDITIONS WRRANT

[ 1. OTHER CONDITIONS WARRANT GASES DEEMED DETRIMENTAL TO SAFE CLASSIFICATION OF AN ALERT DECLARATION OF SITE AREA DECLARATION OF GENERAL OPERATJON OF THE PLANT (BD 87) (BD 95) EMERGENCY (BD 98) EMERGENCY (BD 99)

OPERATING MODE: All OPERATING MODE: All OPERATING MODE: All OPERATING MODE: All A. Report/detection of toxic or flammable gases A. Emergency Coordinatorjudgment indicates A. Emergency Coordinator/EOF Director A Emergency Coordinator/EOF Director that could enter within the site area boundaiy in that: judgment indicates:

judgment amounts that can affect normal operation of the plant Plant safety may be degraded Actual/imminent substantial core (END) degradation with potential for loss of B. Report by local, county, state officials for containment potential evacuation of site personnel based on offsite event Increased monitoring of plant functions OR is warranted Potential for uncontrolled (END) radionuclide releases that would

5. OTHER CONDITIONS EXIST WHICH result in a dose projection at the WARRANT DECLARATION OF AN site boundaiy greater than 1000 mRem UNUSUAL EVENT (BD 88) TEDE or 5000 mRem CDE Adult Thyroid OPERATING MODE: All (END)

A. Emergency Coordinator determines potential degradation of level of safety has occurred (END) 19

Enclosure 4.8 RP/O/A/1 000/001 Radiation Monitor Readings for Emergency Classification Page 1 of 1 All RIA values are considered GREATER THAN or EOUAL TO HOURS SINCE RIA 57 R/hr RIA 58 RIhr*

REACTOR TRIPPED Site Area Emergency General Emergency Site Area Emergency General Emergency 0.0 < 0.5 5.9E+003 5.9E+004 2.6E+003 2.6E+004 0.5 < 1.0 2.6E+003 2.6E+004 L1E+003 1.IE+004 1.0- < 1.5 1.9E+003 1.9E+004 8.6E+002 8.6E+003 1.5 -<2.0 1.9E+003 1.9E+004 8.5E+002 8.5E+003 2.0- < 2.5 1.4E+003 1.4E+004 6.3E+002 6.3E+003 2.5 < 3.0 1.2E+003 1.2E+004 5.7E+002 5.7E+003 3.0-<3.5 1.1E+003 1.1E+004 5.2E+002 5.2E+003 3.5 < 4.0 1 .OE+003 I .OE+004 4.8E+002 4.8E+003 4.0 < 8.0 1.OE+003 1.OE+004 4.4E+002 4.4E+003 RIA 58 is partially shielded 20

Enclosure 4.9 RP/0/A/1 000/001 Unexpected/Unplanned Increase In Area Monitor Readings Page 1 of 1 NOTE: This Initiating Condition is not intended to apply to anticipated temporary increases due to planned events (e.g.; incore detector movement, radwaste container movement, depleted resin transfers, etc.).

UNITS 1,2,3 MONITOR NUMBER UNUSUAL EVENT l000x ALERT NORMAL LEVELS mRAD/HR mRAD/HR RIA 7, Hot Machine Shop Elevation 796 150 5000 RIA 8, Hot Chemistry Lab Elevation 796 4200 5000 RIA 10, Primary Sample Hood Elevation 796 830 5000 RIA 11, Change Room Elevation 796 210 5000 RIA 12, Chem Mix Tank Elevation 783 800 5000 RIA 13, Waste Disposal Sink Elevation 771 650 5000 RIA 15, HP! Room Elevation 758 NOTE* 5000 NOTE: RIA 15 normal readings are approximately 9 mRad/hr on a daily basis. Applying l000x normal readings would put this monitor greater than 5000 mRad/hr just for an Unusual Event. For this reason, an Unusual Event will NOT be declared for a reading less than 5000 mRad/hr.

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Enclosure 4.10 RP/O/A/l000/OOl Definitions/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 potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.

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

1.3 COGNIZANT FACILITY STAFF any member of facility staff, who by virtue of training and experience, is qualified to assess the indications or reports for validity and to compare the same to the EALs in the licensee s emergency classification scheme. (Does not include staff t

whose 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 or is about to occur and minutes to days may be allowed to respond dependent upon the proximity to the dam.

1.5 CONDITION B Potentially Hazardous Situation is Developing A situation where failure may 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 or activities at the site.

1.7 EXPLOSION A rapid, violent, unconfined combustion, or catastrophic failure of pressurized/energized equipment that imparts energy of sufficient force to potentially damage permanent 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 drive belts or overheated electrical equipment, do NOT constitutefires. Observation of flames is preferred 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 fuel assemblies from the reactor core and placed in the spent fuel pool. (Typical of a No Mode operation during a refuel outage that allows safety system maintenance to occur and results in maximum decay heat load in the spent fuel pool system).

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Enclosure 4.10 RP/0/A/1000/001 Definitions/Acronyms Page 2 of 5 1.10 GENERAL EMERGENCY Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity 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 exposure levels offsite for more than the immediate area.

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

1.12 HOSTILE ACTION An act toward an NPP or its personnel that includes the use of violent force to destroy equipment, takes HOSTAGES, and/or intimidates the licensee to achieve an end. 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 overall intent may be included. HOSTILE ACTION should not be construed to include acts of civil disobedience 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 between individuals 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 to be successful, and trended information indicates that the event or condition will occur. Where IMMINENT timeframes are specified, they shall apply.

1.15 INTRUSION A person(s) present in a specified area without authorization. Discovery of a BOMB 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 are unavailable 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 electrical energy 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 the motors 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 continued operability, reliability, or personnel safety.

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

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Enclosure 4.10 RP/0/A/1000/001 Definitions/Acronyms Page 3 of 5 1.20 REACTOR COOLANT SYSTEM (RCS) LEAKAGE - RCS Operational Leakage as defined in the Technical Specification Basis B 3.4.13:

RCS leakage includes leakage from connected systems up to and including the second normally closed valve for systems which do not penetrate containment and the outermost isolation valve for systems which penetrate containment.

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

LEAKAGE, such as that from pump seals, gaskets, or valve packing (except RCP seal water injection or leakoff), that is captured and conducted to collection systems or a sump or collecting tank; LEAKAGE through a steam generator (SG) to the Secondary System (primary to secondary LEAKAGE): Primary to secondary LEAKAGE must be included in the total calculated for identified LEAKAGE.

B. Unidentified LEAKAGE All LEAKAGE (except RCP seal water injection or leakoff) that is not identified LEAKAGE.

C. Pressure Boundary LEAKAGE LEAKAGE (except primary to secondary LEAKAGE) through a nonisolable fault in an RCS component body, pipe wall or vessel wall.

1.21 RUPTURED (As relates to Steam Generator) Existence of Primary to Secondary leakage of a 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 with the intent to render the equipment inoperable. Equipment found tampered with or damaged due to malicious mischief may not meet the definition of SABOTAGE until this determination is made by security supervision.

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

1.24 SAFETY-RELATED SYSTEMS AREA Any area within the Protected area which contains equipment, systems, components, or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation.

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Enclosure 4.10 RP/0/A/l000/0O1 Definitions/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 the following:

(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 actual or likely major failures of plant functions needed for the protection of the public, or HOSTILE ACTION that results in intentional damage or malicious act; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevents effective access to equipment needed for the protection of the public. Any releases are NOT expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the Site Boundary.

1.28 SITE BOUNDARY That area, including the Protected Area, in which DPC has the authority 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 of normal operations, testing, or maintenance. Events that result in corrective or mitigative actions being taken in accordance with abnormal or emergency procedures are UNPLANNED.

1.32 UNUSUAL EVENT Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated. No releases of radioactive material requiring offsite response or monitoring 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 is conclusively verified by: (I) an instrument channel check; or, (2) indications on related or redundant instrumentation; or, (3) by direct observation by plant personnel such that doubt related to the instruments operability, the conditions existence, or the reports accuracy is removed. Implicit with this defmition is the need for timely assessment.

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Enclosure 4.10 RP/O/A/l000/OOl Definitions/Acronyms Page 5 of 5 1.34 VIOLENT Force has been used in an attempt to injure site personnel or damage plant property.

1.35 VISIBLE DAMAGE Damage to equipment or structure that is readily observable without measurements, testing, or analyses. Damage is sufficient to cause concern regarding the continued 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 in to gain access to the area that houses equipment important for nuclear safety. The failure or destruction of this equipment could directly or indirectly endanger the public health and safety by exposure to radiation.

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Enclosure 4.11

/O/A/1000/o0I Operating Modes Defined In Improved Page 1 of 1 Technical Specifications MODES REACTIVITY % RATED AVERAGE CONDITION 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/ool Instructions 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 fission product barriers have been affected, refer to Enclosure 4.1, (Fission Product Barrier Matrix) 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 determine if there is a Loss or Potential Loss of that barrier.

NOTE: An event with multiple events could occur which would result in the conclusion that exceeding the loss or potential loss thresholds is imminent (i.e. within 1-3 hours). In this 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 the page to determine appropriate classification.

1.3 The numbers in parentheses out beside the label for each column can be used to assist in determining the classification. If no EAL is met for a given barrier, that barrier 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 barrier to determine a total for all barriers. Compare this total point value with the numbers in parentheses beside each classification to see which one applies.

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

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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 in extremely 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 by loss of subcooling margin.

Barrier EAL Failure Points RCS SGTR> Makeup capacity of one HPT pump in Potential Loss 4 normal makeup mode with letdown isolated Entry into PTS operating range Potential Loss 4 RCS leak rate> available makeup capacity as Loss 5 indicated by a loss of subcooling Fuel Clad No EALs met and no justification for No 0 classification on judgment Challenge Containment Failure of secondary side of SG results in a Loss 3 direct 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 for the RCS barrier, credit is only taken for the worst case (highest point value) EAL, so the points from this barrier equal 5.

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

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

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

E. Look in the box below Site Area Emergency. You have identified a loss of two barriers. This agrees with one of the bullet statements.

The classification is correct.

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

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

ML15009A338

Text

References:

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