Text

Initial Exam 2011-302 Final Simulator Scenarios
	ML113390441
Person / Time
Site:	Oconee
Issue date:	12/01/2011
From:	; NRC/RGN-II
To:	;
References
	Download: ML113390441 (122)
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Appendix D Scenario Outline Form ES-D-1 ILT4O Oct, 201 1 Facility: Oconee Scenario No.: Ifs Op-Test No.: I Examiners: Operators:

Initial Conditions:

. Reactor Power = 100% Unit 2: 100% Unit 3: 100%

Turnover:

. SASS in Manual for l&E testing

. AMSAC/DSS bypassed for I&E testing

. 1 B FDWPT on Handjack for MGU repair, work is completed; NEC on station at 1 B FDWPT

. GWD Tank B release in progress

. ACB-3 closed Event Malfunction Event Event Type

Description No. No.

Oa Pre-Insert SASS in Manual Ob Pre-Insert AMSAC/DSS bypassed for l&E testing Oc Pre-Insert 1 B CC pump fails to auto start Od Pre-Insert Block ALL Turbine trip except MANUAL 1 N: BOP, SRO Restore lB MFWP from Hand Jack 2 C: BOP, SRO 1A CC pump trips and 1 B CC pump fails to auto start 3 MPS1 10 C: BOP, SRO (TS) Restore Letdown (1 HP-5 fails CLOSED) (TS) 4 MCSOO8 I: OATC, SRO Selected Tcold Fails HIGH (622°F) 5 MCRO21 R: OATC, SRO (TS) Dropped Control rod (TS), Manual power reduction 6 MEL17O SRO (TS) CT-i Transformer Lockout (TS) trip (Lockout EHC Pumps) 7 MPI29O C: OATC, SRO MELO9O Switchyard Isolate (RX trip) 8 MCRO24 M: ALL Stuck Control rod MELO2O KHU-2 lock out Blackout due to Loss of second Keowee Unit (KHU-1) 9 MEL1 80 M: ALL Recover power from CT-5 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-2 0p-TetNi Scoto.: I Ever1tN I Pe1Of2 Event

Description:

Restore lB FDWPT from Hand Jack (N: BOP, SRO)

Time Position Applicants Actions or Behavior Crew Response:

SRO Direct BOP to perform OP/i/Ni 106/002 B (FDWPT Operation), End. 4.13, Taking the lB FDWPT Off Handjack beginning at Step 2.1 BOP Use the above procedure End. 4.13, and remove the 1 B FDWPT from Handjack and restore speed control to the 1 B MGU (motor gear unit)

2. Procedure 2.1 IF in Mode I OR Mode 2, WHILE enclosure is in progress monitor the following indications: {20}

Appropriate ranged Nis

Neutron error

RCS Loop LiT (curve for Loop LiT Vs Reactor Power is in PT/1/N0600/001)

FDW Flow (curve for Expected Feedwater Flow Per Header Vs Reactor Power is in OP/0/N1 108/001) 2.2 Remove T/O SHEET CR tag from I B MAIN FDW PUMP (ICS) station.

2.3 Run lB MAIN FDW PUMP (ICS) station to HSS (high speed stop).

2.4 Perform the following:

2.4.1 Establish communication with Operator at lB FDWPT.

Booth Cue: NEO will report Standing by the lB FDWPT Motor Gear Unit 2.4.2 Run 1 B MAIN FDW PUMP (ICS) to low speed stop.

2.4.3 Run 1 B MAIN FDW PUMP (ICS) to high speed stop.

( 1/8 from hard stop) 2.4.4 Verify Motor Gear Unit operated smoothly through entire operation.

Booth Cue: NEO will report Motor Gear Unit operated smoothly 2.5 Turn FWT lB HANDJACK switch to OFF.

2.6 IF Unit 1 is in Mode 1 or 2 AND both FDWPT ICS stations are in HAND: (does not apply) 2.7 Decrease lB MAIN FDW PUMP (ICS) until lB FDWPT controlled by lB MAIN FDW PUMP (ICS) station.

2.8 Increase lB FDWPT Motor Speed Changer.

2.9 Verify 1 B FDWPT speed does NOT increase.

Page2of3O

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: I Event No.: I Page 2 of 2 Event

Description:

Restore lB FDWPT from Hand Jack (N: BOP, SRO)

Time Position Applicants Actions or Behavior Crew Response:

2.10 Position 1 B FWPT MOTOR SPEED CHANGER to FR under RAISE until 1 B FDWPT MOTOR SPEED CHANGER is at HSS.

2.11 After lB FDWPT MOTOR SPEED CHANGER reaches HSS, hold lB FDWPT MOTOR SPEED CHANGER switch in FR for 3 to 5 seconds to make all contacts.

Note: Steps 2.12 2.14 do not apply.

2.12 IF Unit 1 is in Mode 3:

2.13 IF Unit 1 is in Mode 1 or 2 with 1A FDWPT shutdown:

2.14 IF Unit 1 is in Mode 1 or 2 with 1A FDWPT operating but NOT in auto:

2.15 IF Unit 1 is in Mode I or 2 with IA FDWPT in auto:

2.15.1 Verify 1A MAIN FDW PUMP (ICS) in AUTO.

2.15.2 Place lB MAIN FDW PUMP (ICS) in AUTO.

2.15.3 Verify ICS adjusts 1 B FDWPT speed to balance suction flow.

2.16 IF required, remove Turnover Sheet note for control of lB FDWPT with Motor Speed Changer.

This event is complete when the I B MFDWPT is placed in AUTO, or as directed by the Lead Examiner.

Page3of3O

Appendix D Scenario Outline Form ES-D-2 Op-Tesf No.: j_ Scenario No: j_ Event No.: 2 - Page 1 of 1 Event

Description:

IA CC pump trips and lB CC pump fails to auto start (C: BOP, SRO)

Time Position

[ ApplicanVs Actions or Behavior Plant response:

1 SA-91B-1 CC CRD RETURN FLOW LOW

1SA-9/C-1, CC COMP COOLING RETURN FLOW LOW

ISA-21C-1, LETDOWN TEMPERATURE HIGH

1 HP-5 (Letdown Isolation) will close due to high letdown temperature

CC Total Flow Low

Component Cooling Pressure Low

Pzr level will begin to increase once 1 HP-5 closes BOP Crew Response:

Refer to ARG 1 SA-91B-1 OR 1 SA-9/C-1

Determine low flow is due to CC Pump failure AND Standby CC Pump did

?PI start and perform the following:

Verify CC Surge Tank level> 12

Start Standby CC Pump Note: The SRO will not be required to initiate API2O if the Standby Pump is started per the ARG.

SRO Initiate AP/20 (Loss of Component Cooling) 3.1 IAAT both of the following are lost:

CC to RCPs and RCP seal injection THEN Trip the Rx, stop all RCPs and initiate AP/25 3.2 IAAT two CRD stator temperatures 180°F, THEN trip Rx 4.1 Verify at least one CC pump operating RNO: GO TO Step 4.3 4.3 Open 1 CC-7 and 1 CC-8 4.4 Verify one CC pump operating RNO: 1. IF CC Surge Tank level 12 THEN attempt to start a CC Pump

2. IF unable to start any CC pump.. .(does not apply) 4.5 Verify CC TOTAL FLOW> 575 gpm 4.6 Verify Letdown in service and LETDOWN TEMP 130°F RNO: 1. IF LETDOWN TEMP> 130°F, THEN close 1HP-5

2. Initiate AP/32 or EOP End 5.5 to restore letdown Note: If the SRO initiates EOP End 5.5 to restore Letdown, these actions are listed beginning on page 26.

This event is complete when the standby CC pump is started, or as directed by the Lead Examiner.

Page 4 of 30

Appendix D Scenario Outline Form ES-D-2 Optest No.: 1 Scenario fo.: 1 vent No.: - page 1 of Event

Description:

Restore Letdown (IHP-5 fails CLOSED) (C: BOP, SRO) (TS)

Time Position Applicants Actions or Behavior Crew Response:

SRO SRO should enter AP/IIA/1700/032 (Loss of Letdown) 4.1 Place 1HP-120 in HAND and reduce demand to zero.

BOP 4.2 Initiate makeup to LDST as required (Encl.5.5 or OP/I/All 103/004).

4.3 Initiate notification of the following:

OSM to reference the following:

OMP 1-14 (Notifications)

Emergency Plan STA 4.4 Notify Chemistry of the following:

Current RCS boron sample is needed for possible unit shutdown.

Normal letdown line is isolated.

4.5 IAAT either of the following exists:

Pzr level 260, AND letdown CANNOT be established Plant conditions exist such that letdown will NOT be restored THEN initiate unit shutdown at 20%/mm per AP/29 (Rapid Unit Shutdown).

4.6 IAAT Pzr level 375, THEN trip Rx.

4.7 Position the standby HPI pump switch to OFF.

4.8 Throttle 1HP-31 to establish 12- 15 gpm SEAL INLET HDR FLOW.

Note: Statalarm ISA-2!B-2 (RCP SEAL INLET HEADER FLOW HIGHILOW) will actuate once seal inlet header flow is decreased to < 22 gpm) 4.9 Verify HPI pump flow 65 gpm. (30 gpm Recirc + SI + MU)

RNO: Log beginning time for HPI pump flow below minimum 4.10 Determine the cause of loss of letdown and GO TO Step 4.29 for actual letdown temperature high.

4.29 Notify SPOC to initiate repairs on failed equipment.

4.30 IAAT letdown can be re-established, THEN perform Steps 4.31 4.46.

4.31 Place CC system in operation 4.32 Close 1HP-6.

4.33 Close 1 HP-7.

4.34 Open the following:

1HP-l

1HP-2

1HP-3

1HP-4 Page5of3O

Appendix D Scenario Outline Form ES-D-2 Op-Test No.:1 ScenarioNo.: 1 Event No.: 3 - Page 2 f 3 Event

Description:

Restore Letdown (IHP-5 fails CLOSED) (C: BOP, SRO) (TS)

Time Position Applicants Actions or Behavior Crew Response:

SROI BOP AP111A117001032 (Loss of Letdown) 4.35 Verify letdown temperature < 135°F (it is not)

RNO: 1. Open 1HP-13.

2. Close the following:

1HP-8

1HP-9&11

3. IF any deborating IX in service.. (no deborating IX is in service)

4. Select LETDOWN HI TEMP INTLK BYP switch to BYPASS Note: Statalarm ISA-21E-4 (HP LETDOWN FLOW INTERLOCK BYPASSED) will actuate once the LETDOWN HI TEMP INTLK BYP switch is placed in BYPASS.

4.36 Open 1HP-5.(wiII not OPEN)

RNO: GOTOStep4.11 4.11 Close IHP-6 4.12 Close IHP-7 4.13 Open 1HP-5 (will NOT open)

RNO: 1. Dispatch an operator in continuous communication with Control Room to manually open 1 HP-5 (LETDOWN ISOLATION)\

Booth cue: When called, use TIME COMPRESSION and FIRE TIMER 14 to manually open IHP-5.

2. IF 1 HP-5 is manually open, THEN enter TS 3.6.3.

3. IF I HP-5 CANNOT be manually opened, THEN GO TO Step 4.29.

4.14 WHEN IHP-5 is open, THEN continue.

4.15 Place the CC system in service.

4.16 Verify letdown temperature is < 135°F (it is not)

RNO: 1. Open 1HP-13.

2. Close the following:

1HP-8

1HP-9&11

3. IF any deborating IX in service.. .(no deborating IX is in service)

4. Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.

Page6of3O

Appendix D Scenario Outline Form ES-D-2 0r5-Test NO. i Seriaric NO. I EVent NO.: a P 3 Of3 Event

Description:

Restore Letdown (1 HP-5 fails CLOSED) (C: BOP, SRO) (TS)

Time Position Applicants Actions or Behavior Crew Response:

SROI BOP 4.17 Throttle open 1HP-7 to establish 20 gpm.

4.18 WHEN letdown temperature < 130°F, THEN place LETDOWN HI TEMP INTLK BYP switch in NORMAL 4.19 Open 1HP-6 4.20 Adjust 1 HP-7 to control desired letdown flow ( 75 gpm) 4.21 Re-establish normal makeup through 1HP-120.

4.22 Verify y purification IX in service RNO: IF purification IX operation is desired, THEN initiate OP/1/A/1103/004 B (Purification lXs) to establish desired IX operation 4.23 Notify SPOC to initiate repairs on 1 HP-5 4.24 Verify seal injection flow reduced in Step 4.8 4.25 Re-establish normal RCP seal injection flow ( 32 gpm) 4.26 Position the standby HPI pump switch to AUTO 4.27 WHEN repairs complete on I HP-5, THEN perform the following:

A. Locally turn 1 HP-5 handwheel fully clockwise B. EXITTS3.6.3 4.28 EXIT this procedure Note: I HP-5 will not be repaired for this scenario.

Note: If pressurizer level exceeds 260 inches, TS 3.4.9 Condition A should be entered requiring level be restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Note: The crew may request an R&R to place the IA CC pump switch to OFF.

The SRO enters TS 3.6.3 Condition A due to one or more penetration flow SRO paths with one containment isolation valve inoperable Required Action is to isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, one closed and de-activated non-automatic power operated valve, closed manual valve, blind flange, or check valve with flow through the valve secured within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND verify the affected penetration flow path is isolated once per 31 days for isolation devices outside containment.

This event is complete when the Standby HPI pump is placed in AUTO, or as directed by the Lead Examiner.

Page7of3O

Appendix D Scenario Outline Form ES-D-2 Op-Test No: J_* Scenár[o Nb.: 1 Event No.: 4 Page lof 2 Event

Description:

Selected Tcold Fails HIGH (622°F) (I: OATC, SRO)

Time Position Applicants Actions or Behavior Plant Response:

Loop B Tc Dixson meter pegs high (620°F)

Loop B T Dixson meter reads 0°F

tTc meter reads pegged low (-10°F; B loop Hot)

Controlling NR Tave digital display reads 595.5°F

Controlling Tave Chessell dislplay reads 595°F

1 SA-2/B4 (RC Average Temperature High/Low)

ISA2/B-5, RC COLD LEG DIFF TEMP HIGH Crew Response:

OATC

When the Statalarms are received, the candidates should utilize the Plant Transient Response process to stabilize the plant.

Verbalize to the SRO reactor power level and direction of movement.

Place the Diamond and both FDW Masters in manual and position as necessary to stabilize the plant.

The SRO should:

> Refer to AP/28, lOS Instrument Failures

> Contact SPOC to repair the failed instrument.

SRO AP/28, ICS Instrument Failures 4.1 Provide control bands as required.

4.2 Initiate notification of the following:

OSM to reference the following:

OMP 1-14 (Notifications)

Emergency Plan STA 4.3 Verify a power transient 5% has occurred.

RNO: GO TO Step 4.5.

4.4 Notify Rx Engineering and discuss the need for a maneuvering plan 4.5 Use the following, as necessary, to determine the applicable section from table in Step 4.6:

OAC alarm video

OAC display points

Control Board indications

SPOC assistance, as needed 4.6 GO TO Section 4A, RCS Temperature Page8of3o

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: j_ Scenario No.: I Event No.: 4 Page 2 of 2 Event

Description:

Selected Tcold Fails HIGH (622°F) (I: OATC, SRO)

Time Position Applicants Actions or Behavior Crew Response:

AP111A117001028 Section 4A RCS Temperature Failure

1. Ensure the following in HAND:

SRO/OATC 1A FDW MASTER lB FDW MASTER

2. Ensure DIAMOND in MANUAL.

3. Notify SPOC to perform the following:

Select a valid RCS Tave and Delta Tc input to ICS per AM/01B10326/020 (Control of Star Module Signal Selection Function).

Investigate and repair the failed RCS temperature instrumention.

4. PERFORM an instrumentation surveillance using applicable table in End 5.2 (ICS Instrument Surveillances) for the failed instrument.

5. Verify instrumentation surveillance in End 5.2 (ICS Instrument Surveillances) was performed satisfactorily as written.

6. WHEN notified by SPOC that a valid RCS Tave and Delta Tc input have been restored to ICS, THEN GO TO OP/i/A/l 102/004 A End (Placing ICS Stations To Auto).

Note: The ICS will remain in manual for the remainder of the scenario.

Note: The crew may initiate EOP End 5.5 for inventory control. These steps are included beginning on page 26 if necessary.

This event is complete when Section 4A Step 6 is reached, or as directed by the Lead Examiner.

Page9of3O

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: I Event No.: 5 Page 1 of 4 Event

Description:

Dropped Control Rod, Manual Power Reduction (C: OATC, SRO) (TS)

Time__[ Position Applicants Actions or Behavior Plant Response:

Group 2 Rod 6 drops into the core Statalarm 1SA-2/A-1O (CRD GLOBAL TROUBLE)

Statalarm ISA-2/B-1O (CRD ASYMMETRIC ROD POSITION ERROR)

Statalarm I SA-2/D-9 (CRD OUT INHIBIT)

Statalarm ISA-4/C-1 (QUADRANT POWER TILT) (alarms in 2 minutes)

Statalarm 1SA-51A-5 (1A RPS TROUBLE)

Statalarm I SA-5/B-5 (1 B RPS TROUBLE)

Statalarm 1SA-51D-5 (1D RPS TROUBLE)

Crew Response:

BOP/OATC Crew should perform Plant Transient Response (PTR)

OATC reports to the SRO reactor power level and direction of movement.

The BOP reports no valid runback (due to ICS in MAN) and monitors RCS pressure and inventory and inserts Control Rods as needed.

The OATC will adjust FDW and/or control rods as necessary to restore reactor power to the desired control band.

SRO SRO should enter AP/1/A/1700/OO1 (Unit Runback)

Entry Conditions:

Any control rod dropped or misaligned > 6.5% (9) from the group average 4.1 GO TO the most limiting section per the following table:

I Section Runback 4H Asymetric Control Rod (1%/mm to 55% power)

Note: The SRO should transfer to Section 4H (Asymmetric Control Rod) of AP/IIAII 7001001 Page 10 of 30

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: I Event No.: Page 2 of 4 Event

Description:

Dropped Control Rod, Manual Power Reduction (C: OATC, SRO) (TS)

[_Time Position Applicants Actions or Behavior Crew Response:

SRO/OATC API1/A117001001 Section 4H

1. IAAT more than one control rod is dropped misaligned 6.5%

(9) from the group average, THEN trip the Rx

2. Verify Rx is critical

3. Verify power> 55% when the rod was dropped or misaligned.

4. Verify Rx runback to 55% core thermal power in progress RNO: 1. Initiate power reduction to 55% core thermal power at 1 %/min

2. IF control rods will not insert manually, THEN perform the following:

A. Trip reactor B. GO TO Unit I EOP

5. Initiate End 5.1 (Control of Plant Equipment During S/D) (page 13)

NOTE The following actions should be performed as quickly as possible due to the complexity of resetting RPS trip setpoints and Tech Spec time limits.

6. Notify SPOC to perform the following:

Investigate cause of dropped or misaligned control rod.

Prepare to reduce the following trip setpoints:

RPS Flux/Flow-Imbalance

RPS High Flux

7. Notify the OSM to ensure the requirements of the following Tech Specs are met:

TS 3.1.4 (Control Rod Group Alignment Limits)

TS 3.1.5 (Safety Rod Position Limits)

TS 3.2.3 (Quadrant Power Tilt) (may not apply depending on time rod has been dropped)

8. Notify OSM to make notifications as required per OMP 1-14 (Notifications)

Booth cue: If asked, the OSM will NOT refer to Tech Specs.

SRO The SRO should enter TS 3.1.5 Condition A for one safety control rod not fully withdrawn.

The Required Action is to withdraw the control rod or verify SDM is within the limit specified in the COLR or initiate boration to restore SDM to within limit and declare the rod inoperable.

Completion Time is within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Page II of3O

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: I Event No.: 5 Page 3 of 4 Event

Description:

Dropped Control Rod, Manual Power Reduction (C: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior Crew Response:

AP/l/A/1700/00l Section 4H

9. Verify> 1% SDM with allowance for the inoperable control rod per PT/1/A/1103/015 (Reactivity Balance Calculation) within one hour

10. Reduce core thermal power the following limits, based on the number of RCPs operating, within two hours:

q RCPs Allowable Thermal Power (% FP) 3 45 4 60 NOTE The following ensures adequate margin in preparation for resetting RPS trip setpoints.

11. IAAT the power decrease is complete, AND y NI is > the following:

RCPs Maximum NI Power

(%_FP) 3 40 4 55 THEN reduce power until ll NIs are the Maximum NI Power limit for the operating RCP combination per End 5.4 (Power Reduction)

12. WHEN all Nls are the Maximum NI Power limit for the operating RCP combination, THEN notify SPOC to reduce RPS trip setpoints based on RPS system installed:

New RPS System

AM/1/A0315/017 (TXS RPS Channel A, B, C, And D Parameter Changes For Abnormal/Normal Operating Conditions.)

Page 12 of 30

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: j_ Scenario No.: I Event No.: 5 Page 4 of 4 Event

Description:

Dropped Control Rod, Manual Power Reduction (C: OATC, SRO) (TS)

Time__j Position Applicants Actions or Behavior Crew Response:

BOP API1/A11700/00l End 5.1 (Control of Plant Equipment During Shutdown)

1. IAAT SRO determines all appropriate actions have been taken, AND the runback is complete, THEN EXIT this Enclosure

2. Notify the WCC SRO to initiate Enclosure 5.2 (WCC SRO Support During Unit Runback).

3. Start the following pumps:

IA/lB FDWP SEAL INJECTION PUMP

lA/lB FDWP AUXILIARY OIL PUMP

4. WHEN CTP 80%,

THEN stop IE1/1E2 HTR DRN PUMP

5. WHEN CTP 65%,

THEN continue this Enclosure.

6. Place 1 FDW-53 and 1 FDW-65 in MANUAL and close NOTE I B FDWP is the preferred pump to shut down first.

7. Verify both Main FDWPs operating.

8. Verify 1 B FDWP to be shut down first.

9. Adjust the FWP bias counter-clockwise to lower 1 B FWP suction flow 1 x 106 lb/hr < 1A FWP suction flow.

10. GOTOStepl2

12. IAAT both Main FDW pumps running, AND of the following exist:

1 B Main FDW pump is first pump to be shut down y of the following alarms occur:

1SA-16/A-3 (FWP B FLOW MINIMUM)

1SA-16/A-4 (FWP B FLOW BELOW MIN)

THEN trip lB Main FDW Pump This event is complete when the SRO reaches WHEN Step 12 of APIOI, or as directed by the Lead Examiner.

Page 13 of 30

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: I Event No.: 6 Page 1 of 1 Event

Description:

CT-I Transformer Lockout (PCB 17 and 18 open) (SRO) (TS)

Time__[ Position Applicants Actions or Behavior Plant Response:

CT-i transformer will be de-energized ISA-i 51C-2 EL SU SOURCE VOLT MONIT LOGIC UNDERVOLTAGE PCB-17 and PCB-18 will open BOP Crew Response:

Refer to ARG 1 SA-i 51C-2

2. Automatic Action 2.1 Loss of startup source from the Yellow Bus.

3 Manual Action SRO Refer to Technical Specification 3.8.1, AC Sources Operating Condition A: Both required offsite sources and the overhead emergency power path inoperable due to inoperable unit startup transformer.

Required Action:

A.1 Perform SR 3.8.13. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if not performed in previous 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

AND A.2 Align the emergency startup bus to share another units startup transformer. Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND A.3.1 Restore unit startup transformer to OPERABLE status and normal startup bus alignment. Within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR A.3.2 Designate one unit, sharing the startup transformer, to be shutdown.

Within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Note: If asked Unit 2 will perform SR 3.8.1.3.

Note: An RO may dispatch a NEO to Emergency Power Switching Logic Panel #1 to determine status.

This event is complete when the SRO has referred to Technical Specifications, or as directed by the Lead Examiner.

PageI4of3O

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: j_ Scenario No.: I Event No.: 7 Page 1 of 1 Event

Description:

Main Turbine Fails to trip (C: OATC, SRO)

Runs concurrent with Event 8 Time__[ Position Applicants Actions or Behavior Plant Response:

The reactor will trip on high RCS pressure due to the Switchyard Isolation.

Crew response:

OATC The SRO will direct the OATC to perform Immediate Manual Actions (IMAs) 3.1 Depress REACTOR TRIP pushbutton.

3.2 Verify reactor power < 5% FP and decreasing.

3.3 Depress turbine TRIP pushbutton.

3.4 Verify all turbine stop valves closed. (They will be open)

RNO: Place both EHC pumps in PULL TO LOCK.

3.5 Verify RCP seal injection available.

RNO: IF CC is unavailable, THEN immediately perform the following:

Stop all RCPs.

Notify CR SRO to initiate AP/25 (Standby Shutdown Facility Emergency Operating Procedure).

Note: Power will be restored in about 15 seconds.

This event is complete when the EHC pumps have been locked out, or as directed by the Lead ExaminerS Page I5of 30

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: I Event No.: 8 Page 1 of 5 Event

Description:

Switchyard Isolation (RX trip) (M: ALL)

Stuck Control Rod KHU-I lock out Time Position Applicants Actions or Behavior Plant Response:

The plant will attempt to runback but will trip on HIGH RCS pressure KHU-1 will lock out KHU-2 will supply power to the MFBs via CT-4 and the Standby Bus in about 30 seconds.

Crew response:

OATC Perform Immediate Manual Actions (lMAs)

Depress REACTOR TRIP pushbutton.

Verify reactor power < 5% FP and decreasing.

Depress turbine TRIP pushbutton.

Verify all turbine stop valves closed.

Verify RCP seal injection available.

IF CC is unavailable, THEN immediately perform the following:

Stop all RCPs.

Notify CR SRO to initiate AP125 (Standby Shutdown Facility Emergency Operating Procedure).

AP125 (May not be implement since power will return in 30 seconds) 4.1 Verify y of the following required due to loss of function:

SSF RCMU feed

SSFASWfeedtoSGs 4.2 Stop aB RCPs 4.3 Verify a Licensed Operator staged in SSF and available to perform AP101A117001025 (Standby Shutdown Facility Emergency Operating Procedure). (no operator is staged at the SSF)

RNO: 1. Obtain the following items:

Vital area access key ring

Flashlight

Respirator (if Security Event)

2. ProceedtotheSSF.

Note: If needed, the RO performing AP125 actions will be stopped before leaving the control room and informed that a Unit 2 RO will perform SSF actions.

Page I6of 30

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: I Event No.: 8 Page 2 of 5 Event

Description:

Switchyard Isolation (RX trip) (M: ALL)

Stuck Control Rod KHU-1 lock out Time Position

[ ApplicanVs Actions or Behavior Crew response:

BOP Perform Symptoms Check

Power Range NIs <5%

Power Range Nis decreasing

Any SCM <0°F

Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW)

Uncontrolled Main Steam line(s) pressure decrease

Indications of SGTR:

The SRO will direct an RO to initiate Rule 3 due to a loss of Main FDW (see page 19)

When power is restored, the SRO should initiate AP/1 1 from Parallel Actions Page of Subsequent Actions tab (see page 25)

SRO The SRO will refer to EOP Subsequent Actions 4.1 Verify all control rods in Groups 1 7 fully inserted. (one control rod will NOT be fully inserted)

RNO: 1. Open 1HP-24 and 1HP-25

2. Secure makeup to the LDST

3. If CRDs are energized... (they are NOT) 4.2 Verify Main FDW in operation RNO: 1. Ensure Rule 3 is in progress or complete

2. GOTOStep4.5 4.5 IAAT Main FDW is operating, AND level in jjy SG is > 96% on the Operating Range, THEN perform Steps 4.6 4.8 -

RNO: GO TO Step 4.9 4.9 IAAT TBVs CANNOT control SG pressure at desired setpoint, THEN manually control pressure in affected SGs 4.10 Verify IRIA-40 operable with CSAE OFF-GAS BLOWER operating 4.11 GOTOStep4.14 4.14 Dispatch an operator with End 5.29 (MSRV Locations) to verify all MSRVs have reseated 4.15 Verify ES is required.

RNO: 1. Initiate End 5.5 (Pzr and LDST Level Control) (see page 26)

2. GO TO Step 4.17 Page 17 of 30

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: I Event No.: 8 Page 3 of 5 Event

Description:

Switchyard Isolation (RX trip) (M, ALL)

Stuck Control Rod KHU-I lock out Time Position ApplicanVs Actions or Behavior Crew Response:

SRO EOP Subsequent Actions 4.17 Open PCB-20 and PCB-21 4.18 Verify Generator Field Breaker open.

4.19 Verify EXCITATION is OFF.

4.20 Verify Aux Bldg and Turbine Bldg Instrument Air pressure 90 psig.

4.21 Verify ICS/NNI power available.

4.22 Verify all 4160V switchgear (ITC, lTD & 1TE) energized.

4.23 Verify both SGs > 550 psig.

4.24 Verify Main FDW operating.

RNO: 1. Ensure Rule 3 (Loss of Main or Emergency FDW) in progress or complete.

2. Ensure SG levels approaching proper setpoint. (Rule 7)

3. GO TO Step 4.28.

4.28 Verify all SCMs> 0°F.

4.29 Verify both SGs intentionally isolated to stop excessive heat transfer.

RNO: GO TO Step 4.31.

4.31 Verify heat transfer exists.

4.32 Verify primary to secondary heat transfer has been excessive.

RNO: GO TO Step 4.34.

4.34 Verify indications of SGTR 25 gpm.

RNO: GO TO Step 4.36.

4.36 Verify required RCS makeup flow within normal makeup capability.

4.37 Verify two Main FDW pumps operating.

RNO: GO TO Step 4.39.

4.39 Verify y CBP operating.

RNO: GO TO Step 4.44.

4.44 Verify any HWP operating.

RNO: GO TO Step 4.48.

4.48 Close 1SSH-9, 1MS-76, and 1MS-79 Page 18 of 30

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: I Event No.: 8 Page 4 of 5 Event

Description:

Switchyard Isolation (RX trip) (M, ALL)

Stuck Control Rod KHU-1 lock out Time Position [ Applicants Actions or Behavior Crew response:

SRO EOP Subsequent Actions 4.49 Perform the following:

Stop all Htr Drain pumps.

Stop both MSRH Drain pumps.

4.50 Place IHD-37 and 1HD-52 in DUMP:

4.51 Verify 1 MS-24 and 1 MS-33 are closed:

4.52 Verify afl MSRVs reseated.

4.53 Verify Pzr level <375 4.54 Verify y RCP operating.

RNO: GO TO Step 4.56.

4.56 IAAT aB the following exist:

< one RCPIloop operating RCP available for restart in idle loop

_RCS PIT stable 4.57 Maintain RCS P/T stable.

4.58 IAAT Station Management desires a Natural Circ cooldown, THEN GO TO FCD tab.

4.59 WHEN the OSM approves, THEN GO TO OP/1/A/1102/010 (Controlling Procedure For Unit Shutdown) End (SID To Mode 3 Following Rx Trip Or Rapid SID).

BOP Rule 3 (Loss of Main or Emergency Feedwater)

1. Verify loss of Main FDW.EFDW is due to Turbine Building Flooding.

RNO: GOTOStep3

3. IAAT NO SGs can be fed with FDW (Main/CBPlEmergency), AND any of the following exist:

RCS pressure reaches 2300 psig OR NDT limit

Pzr level reaches 375 [340 acc]

THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).

4. Start operable EFDW pumps to feed aN intact SGs.

5. Verify any EFDW pump operating.

6. GOTOStep37.

37. IAAT an EFDW valve CANNOT control in AUTO...

RNO: GO TO Step 43 This event is complete when RCS temperature and pressure are stable, or as directed by the Lead Examiner.

Page 19 of 30

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: I Event No.: 8 Page 5 of 5 Event

Description:

Switchyard Isolation (RX trip) (M: ALL)

Stuck Control Rod KHU-I lock out Time Position ApplicanVs Actions or Behavior Crew response:

BOP Rule 3 (Loss of Main or Emergency Feedwater)

43. Verify y SCM 0°F.

RNO: IF overcooling, OR exceeding limits in Rule 7, THEN throttle EFDW as necessary

44. IAAT Unit 1 EFDW is in operation, THEN initiate End 5.9 (Extended EFDW Operation).

45. WHEN directed by CR SRO, THEN EXIT this rule.

EOP Enclosure 5.9 (Extended EFDW Operation)

BOP

1. Monitor EFDW parameters on EFW graphic display

2. IAAT UST level is <4, THEN GO TO Step 117

3. IAAT feeding both SGs with one MD EFDWP is desired, THEN perform Steps 4-7 RNO: GO TO Step 8

8. Perform the following as required to maintain UST level > 7.5:

Makeup with demin water Place CST pumps in AUTO

9. IAAT a the following exist:

Rapid cooldown NOT in progress MD EFDWP operating for each available SG EFDW flow in each header < 600 gpm THEN place 1 TD EFDW PUMP switch in PULL TO LOCK

10. Verify 1 TD EFDW PUMP operating RNO: GOTOStepl2

12. Notify CR SRO to set priority based on the NOTE above and EOP activities This event is complete when RCS temperature and pressure are stable, or as directed by the Lead Examiner.

Page 20 of 30

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: I Event No.: 9 Page 1 of 5 Event

Description:

Blackout Loss of second Keowee Unit Recover Power using CT-5 II__Time Position

[ Applicants Actions or Behavior Plant response:

KHU #2 Emergency Lockout MFBs will de-energize Crew response:

The SRO may direct an RO to perform a Symptoms Check SRO The SRO will direct an RO to re-initiate Rule 3 (see page 24)

SRO will transfer to the BLACKOUT tab

The SRO will direct an RO to initiate AP/25

Direct and RO to announce plant conditions using the plant page and notify the OSM to reference EP and NSD 202 (reportability).

Note: The RO performing AP125 actions should be stopped before SRO leaving the control room and informed that a Unit 2 RO will perform SSF actions.

EOP Blackout tab

1. Verify two ROs available to perform Control Room actions.

2. Notify one RO to perform End 5.38 (Restoration of Power).

Note: Enclosure 5.38 steps begin on the next page.

3. VerifyySG is being fed.

4. Verify jy MD EFDWP operating RNO: Position the following to OFF:

IA MD EFDWP lB MD EFDWP

5. Feed and steam available SGs as necessary to stabilize RCS P/T.

NOTE Feeding SGs with EFDW is desired above HPI Forced Cooling. Step 6 should be performed prior to re-performing Rule 3.

6. IAAT NO SGs are being fed, AND any source of EFDW (Unit 1 or another unit) becomes available,

7. IAAT EFDW from any source is insufficient to maintain stable RCS P/T, THEN notify SSF operator that feeding SGs with SSF ASW is required.

8. IAAT power is restored to 1TC, 1TD, ITE, THEN GO TO Step 9 RNO: GOTOStep11

9. Initiate AP/1 1 (Recovery From Loss of Power)

Page 21 of 30

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: I Event No.: 9 Page 2 of 5 Event

Description:

Blackout Loss of second Keowee Unit Recover Power using CT-5 Time__[ Position Applicants Actions or Behavior

10. GO TO Subsequent Actions tab

11. Verify End 5.38 (Restoration of Power) in progress or complete.

SRO 12. IAAT a 4160V SWGR (1TC, 1TD, ITE) are de-energized, AND Standby Bus #lis energized, THEN GO TO Step 13.

RNO: GO TO Step 78 Note: Power may not be restored at this point. In which case the crew will route to Step 78.

78. IAATaII416OV SWGR (1TC, 1TD, 1TE) are de-energized for 1Y2 hours, THEN dispatch an operator to perform End 5.17 (Generator Emergency Hydrogen Purge). {20}

79. Verify blackout exists on all three units.

RNO: GO TO Step 81.

OATC/BOP

81. Verify MFB I and MFB 2 de-energized

82. WHEN End 5.38 (Restoration of Power) is complete, THEN continue this procedure.

EOP Enclosure 5.38 (Restoration of Power) (CT-8)

Note: The CT is not met if End 5.38 is completed with power NOT restored.

1. Verify power has been restored.

RNO: GO TO Step 3

3. Place 1HP-31 in HAND and reduce demand toO.

4. Close IHP-21.

5. Verify MFB1/2 is energized RNO: GOTOStep8

8. Verify CT-i indicates 4160 volts.

RNO: GOTOStepl8

18. Verify both Standby Bus #1 and Standby Bus #2 are de-energized.

19. Verify both Keowee units operating RNO: I. Emergency start Keowee units:

KEOWEE EMER START CHANNEL A KEOWEE EMER START CHANNEL B (not modeled)

2. IF NO Keowee units are operating, THEN GO TO Step 36.

36. IAAT CT-S indicates 4160 volts, THEN GO TO Step 50.

50. Place the following switches in MAN:

MFB1 / MFB2 AUTO/MAN STANDBY 1 / STANDBY 2 AUTO/MAN Page 22 of 30

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: I Event No.: 9 Page 3 of 5 Event

Description:

Blackout Loss of second Keowee Unit Recover Power using CT-5 Time Position Applicants Actions or Behavior Crew response:

OATC/BOP EOP Enclosure 5.38

51. Open the following breakers:

1 MFB1 NORMAL FDR Ni 1 MFB2 NORMAL FDR N2 1 MFB1 STARTUP FDR

_E1 1 MFB2 STARTUP FDR E2

52. Place the following switches in MAN:

CT4 BUS 1 AUTO/MAN CT4 BUS 2 AUTO/MAN CT5 BUS 1 AUTO/MAN CT5 BUS 2 AUTO/MAN

53. Open the following breakers:

_SK1 CT4STBYBUS1 FEEDER

_SK2CT4STDYBUS2 FEEDER

54. Close the following breakers: (CT-8)

_SL1 CT5STBYBUS1 FEEDER

_SL2CT5STBYBUS2FEEDER

55. Place the following switches in AUTO:

CT5 BUS 1 AUTO/MAN CT5 BUS 2 AUTO/MAN

56. Verify Standby Bus #1 energized.

57. Notify CR SRO in each unit where a blackout exists that Standby Bus #1 is energized.

58. Close the following breakers:

1 STBY BUS 1 TOMFB1

_S1 1 STBYBUS2TO MFB2

_S2

59. Verify y of the following energized:

1TC 1 TD 1 TE

60. Notify Unit I CR SRO of status of 41 60V SWGR.

61. Verify Jocassee Hydro is being aligned to ONS.

RNO: GO TO Step 63.

63. EXIT this enclosure.

Page 23 of 30

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: I Event No.: 9 Page 4 of 5 Event

Description:

Blackout Loss of second Keowee Unit Recover Power using CT-5 Position Applicants Actions or Behavior

__Time Crew response:

OATC/BOP EOP Rule 3

1. Verify loss of Main FDW/EFDW is due to Turbine Building Flooding RNO: GO TO Step 3

3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency), AND jy of the following exist:

RCS pressure reaches 2300 psig OR NDT limit Pzr level reaches 375 [340 acc}

THEN PERFORM Rule 4

4. Start operable EFDW pumps, as required, to feed aM intact SGs

5. Verify y EFDW pump operating

6. GO TO Step 37

37. IAAT an EFDW valve CANNOT control in AUTO...

RNO: GO TO Step 43

43. Verify .j2y SCM 0°F.

RNO: IF overcooling, OR exceeding limits in Rule 7, THEN throttle EFDW as necessary

44. IAAT Unit 1 EFDW is in operation, THEN initiate End 5.9 (Extended EFDW Operation).

45. WHEN directed by CR SRO, THEN EXIT this rule.

Page 24 of 30

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: I Event No.: 9 Page 5 of 5 Event

Description:

Blackout Loss of second Keowee Unit Recover Power using CT-5 Time Position Applicants Actions or Behavior Crew response:

OATC/BOP APII/N1700101 1 Recovery From Loss of Power 4.1 Announce AP entry using OMP 1-18 placard 4.2 IAAT Pzr level > 80 [180 acc], AND Pzr heaters are desired, THEN position Pzr heaters to AUTO 4.3 Verify load shed of inverters was performed per Unit 1 EOP End (Load Shed of Inverters During SBO)

RNO: GO TO Step 4.9 4.9 Verify load shed of inverters has initiated as indicated by either of the following statalarms on:

1 SA-1 5/D-4 1 SA- 1 4/D-4 RNO: GOTOStep4.11 4.11 Close the following breakers:

1TC INCOMING FDR BUS 1 1TC INCOMING FDR BUS 2 lTD INCOMING FDR BUS 1 lTD INCOMING FDR BUS 2 1TE INCOMING FDR BUS I 1TE INCOMING FDR BUS 2 4.12 Verify ISA-i 5/E-6 (EL SWYD ISOLATION CONFIRMED CHNL A LOGIC) is OFF RNO: GOTOStep4.15 4.15 Verify y Oconee unit receiving power from its normal source 4.16 Place transfer switches in MAN for aN Oconee units receiving power from the normal source (IT, 2T, 3T)

MFB1 AUTO/MAN

MFB2 AUTO/MAN

TA AUTO/MAN

TB AUTO/MAN 4.17 Verify load shed was initiated as indicated by either of the following statalarms on:

iSA-i 5/D-4 1 SA-1 4/D-.4 This event is complete when power is restored, or as directed by the Lead Examiner.

Page 25 of 30

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: I Event No.: Page 1 of 3 Event

Description:

EOP End 5.5 actions if needed Time Position Applicants Actions or Behavior Crew response:

OATC/BOP EOP Enclosure 5.5 (Pzr and LDST Level Control)

1. Utilize the following as necessary to maintain desired Pzr level:

1AHPIPump

1BHPIPump

1HP-26

1HP-7

1 HP-I 20 setpoint or valve demand

1HP-5

2. IAAT makeup to the LDST is desired, THEN makeup from 1A BHUT

3. IAAT it is desired to secure makeup to LDST, THEN secure makeup from 1A BHUT

4. IAAT it is desired to bleed letdown flow to 1A BHUT, THEN perform the following:

A. Open 1CS-26 and 1CS-41 B. Position 1HP-14 to BLEED C. Notify SRO

5. IAAT letdown bleed is NO longer desired, THEN position 1 HP-14 to NORMAL

6. IAAT 1C HPI PUMP is required, THEN perform Steps 7-9 RNO: GO TO Step 10

7. Open 1HP-24 and 1HP-25

8. Start 1C HPI PUMP

9. Throttle 1 HP-26 and 1 HP-27 as required to maintain desired Pzr level

10. IAAT LDST vel CANNOT be maintained, THEN perform Step 11 RNO: GOTOStep12

11. Perform the following:

Open 1HP-24 and 1HP-25

Close 1HP-16

12. IAAT additional makeup flow to LDST is desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close 1 CS-48

13. IAAT two Letdown Filters are desired, THEN open 1HP-17 and 1 HP-i 8 Page26of3O

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: j_ Scenario No.: I Event No.: Page 2 of 3 Event

Description:

EOP End 5.5 actions if needed Time__[ Position Applicants Actions or Behavior Crew response:

OATC/BOP EOP Enclosure 5.5 (Pzr and LDST Level Control) continued

14. IAAT all of the following exist:

Letdown isolated LPSW available Letdown restoration desired THEN perform Steps 15-33 RNO: GOTOStep34

15. Open 1CC-7 and ICC-8

16. Ensure only one CC pump running

17. Place non-running CC pump in AUTO

18. Verify 1HP-1 and 1HP-2 are open

19. GOTOStep22

22. Monitor for unexpected conditions while restoring letdown

23. Verify both letdown coolers to be placed in service

24. Open 1HP-1, 1HP-2, 1HP-3, and 1HP-4

25. Verify at least one letdown cooler is aligned

26. Close 1 HP-6

27. Close 1 HP-7

28. Verify Letdown temperature < 135°F RNO: 1. Open 1HP-13

2. Close 1HP-8 and 1HP-9&11

3. IF y deborating IX is in service, THEN perform the following:

A. Select I HP-14 to NORMAL B. Close 1HP-16

4. Select LETDOWN HI TEMP INTLK BYP switch to BYPASS

29. Open 1HP-5

30. Adjust 1 HP-7 for 20 gpm letdown

31. WHEN letdown temperature is < 130°F, THEN place LETDOWN HI TEMP INTLK BYP switch to NORMAL

32. Open 1 HP-6

33. Adjust 1 HP-7 to control desired letdown flow

34. IAAT it is determined that letdown is unavailable due to equipment failures or letdown system leakage, THEN notify SRO to initiate AP/32 Page 27 of 30

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: I Event No.: Page 3 of 3 Event

Description:

EOP End 5.5 actions if needed Time__[ Position ApplicanVs Actions or Behavior Crew response:

OATC/BOP EOP Enclosure 5.5 (Pzr and LDST Level Control) continued

35. IAAT> 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:

A. Obtain SRO concurrence to reduce running HPI pumps B. Secure the desired HPI pumps C. Place secured HPI pump switch in AUTO, if desired

36. IAAT a the following conditions exist:

Makeup from BWST NOT required LDST level > 55 All control rods inserted Cooldown Plateau NOT being used THEN close 1 HP-24 and 1 HP-25

37. Verify 1 CS-48 has been closed to provide additional makeup flow to LDST RNO: GOTOStep39

38. WHEN 1 CS-48 is NO longer needed to provide additional makeup flow to LDST, THEN perform the following:

A. Stop 1A BLEED TRANSFER PUMP B. Locally position 1 CS-48 one turn open C. Close 1 CS-46 D. Start 1A BLEED TRANSFER PUMP E. Locally throttle 1 CS-48 to obtain 90-110 psig discharge pressure F. Stop 1A BLEED TRANSFER PUMP

39. Verify two Letdown Filters in service, AND only one Letdown filter is desired RNO: GO TO Step 41

41. WHEN directed by CR SRO, THEN EXIT this enclosure These actions are complete when directed by the CR SRO.

Page 28 of 30

Appendix D Scenario Outline Form ES-D-2 CRITICAL TASKS CT-8 Electrical Power Alignment Recover Power using CT-5 (CT): Recovering electrical power during a Station Blackout event is necessary for the operation of normal and emergency plant equipment.

Page 29 of 30

Appendix D Scenario Outline Form ES-D-2 SAFETY: TakaMinuft UNIT 0 (OSM)

SSF Operable: Yes KHUs Operable: Ui - UG, U2 OH I LOTs Operable: 2 Fuel Handling: No UNIT STATUS (CR SRO)

Unit I Simulator Other Units Mode: I Unit 2 Unit 3 Reactor Power: 100% Mode: 1 Mode: I Gross MWE: 900 100% Power 100% Power RCS Leakage: +.025 gpm EFDW Backup: Yes EFDW Backup: Yes (No WCAP action level)

RBNS Rate: .01 gpm Technical SpecificationslSLC Items (CR SRO)

ComponentlTrain OOS Restoration TSISLC #

DatelTime Required DatelTime SLC 16.7.2 AMSAC/DSS Bypassed Today / 06:30 7 Days Condition_A_&_B Shift Turnover Items (CR SRO)

Primary

. SASS in MANUAL for l&E testing

. AMSAC/DSS Bypassed for l&E testing Secondary

1SSH-1, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, ISD-355, 1SD-356 and ISD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event.

Control 1 B FDWPT with Motor Speed Changer

TIC SHEET CR tag on 1 B MAIN FDW PUMP (ICS) station.

The BOP is to remove lB MFDWP from the Hand Jack per OP/i/All 106/002 B beginning at Step 2.1. NEC is stationed at the I B MFDWP.

GWD Tank B release in progress Reactivity Management (CR SRO)

RCS Boron: 30 ppmB Gp 7 Rod Position: 90%

Human Performance Emphasis (OSM)

Procedure Use and Adherence

Appendix D Scenario Outline Form ES-D-1 ILT4O Oct, 201 1 Facility: Oconee Scenario No.: 2fs Op-Test No.: I Examiners: Operators:

Initial Conditions:

. Unit 1: Reactor Power = 87% Unit 2: 100% Unit 3: 100%

Turnover:

. SASS in Manual

. AMSAC/DSS bypassed for I&E testing

. GWD Tank B release in progress

. PT/i /A/0290/003, Turbine Valve Movement, in progress. Continue and test CV1.

Event No.

Malfunction No. Event T ype

1 Event Description Oa Pre-Insert SASS in MANUAL Ob Pre-Insert AMSAC/DSS bypassed Oc Pre-Insert Block all reactor trips but manual 1 PT/1/A10290/003, Turbine Valve Movement, in N BOP SRO progress, testing CV1 2 Override SRO (TS) 1A HPI pump trips (TS) 3 MPS244 C: BOP, SRO 1A2 RCP lower seal failure (requires pump shutdown) 4 MPI28I, 68 I: OATC, SRO Controller fails when 1A2 RCP is secured

. C BOP SRO HPSW Jockey Pump trips 5 Override (TS)

A HPSW pump auto initiation logic inoperable (TS) 6 Override C: OATC, SRO PZR spray valve (1 RC-i) fails OPEN Override Loss of power to 1TB (Loss of 1B2 RCP) 7 C OATC SRO MPI300 ATWS with 1C HPI pump failure SBLOCA with LOSCM (ES actuation) (Trip RCPs) 8 MPS400 (.23) M: All Rapid RCS cooldown (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: I Page 1 of 2 Event

Description:

PT111A102901003, Turbine Valve Movement in progress, testing CVI (N: BOP, SRO)

Time Position Applicants Actions or Behavior Crew response:

BOP The BOP should use the in progress procedure PT/i 1A10290/003 (Turbine Valve Movement) Enclosure 13.2, Control Valve Movement At Power, at Step 2.1 to test CV1:

2.1 Ensure Standby EHC pump in operation Note: ISA-4/C-7 (MT TURBINE PANEL TROUBLE) will actuate when the lB EHC pump is started.

Booth Cue: If contacted to respond to invest!gate the Turbine Panel alarm, state that ISA-O/B-5 (STANDBY HYDRAULIC FLUID PUMP RUNNING) is actuated.

2.2 Perform the following:

Verify Standby EHC Pump Amp> 0 amps

Verify Standby EHC Pump running smoothly

Verify Standby EHC Pump Discharge Pressure> 1500 psig 2.3 Verify CV4 closed 2.4 IF CV3 and CV4 test required:

(test not required, pages 2-4 of the procedure are NIA) 2.5 IF CV2 test required:

(test not required, pages 5 & 6 of the procedure are NIA) 2.6 IF CV1 test required:

2.6.1 IF required, select Control Valve 1 & 2 Test.

2.6.2 Verify Test Permissive is ON.

2.6.3 Record CV1 pretest position: 94 % Open.

2.6.4 Select Initiate Test for Control Valve I Test.

2.6.5 IF any of the following conditions occur, select Abort CV1 Test:

NI POWER changes > 2%. (R.M.)

ICS Turbine Master trips to HAND. (R.M.)

Turbine vibration> 10 mils for> 5 seconds.

2.6.6 IF Test Failed is ON AND CV1 is NOT fully closed, select Abort CVI Test.

2.6.7 IF Test Failed is ON AND CVI remains closed perform the following:

A. Do NOT select Abort CV1 Test. (R.M.)

B. Notify WCC & Engineering that the (FASV) for the Control Valve under test is stuck in the energized state.

C. Monitor Turbine Vibrations closely if in this abnormal state.

Page 2 of 29

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: I Page 2 of 2 Event

Description:

PT111A102901003, Turbine Valve Movement in progress, testing CVI (N: BOP, SRO)

Time Position Applicants Actions or Behavior Crew response:

BOP PT111A102901003 (Turbine Valve Movement) Enclosure 13.2, Control Valve Movement At Power, to test CV1:

2.6.8 Perform EITHER for CV1:

A. Verify Test Successful indicated for CVI.

B. if Test Successful QI indicated for CV1, verify CVI moved towards closed position.

2.6.9 Verify CV1 test indicator reset.

2.6.10 Verify CV1 within +/- 5.0% of pretest position.

2.6.11 Perform the following:

Verify acceptance criteria met. (acceptance is met)

I.E acceptance criteria NOT met, notify SRO.

2.7 IF desired:

2.7.1 Stop Standby EHC pump.

2.7.2 Place Standby EHC pump control switch to AUTO.

This event is complete when test of CVI is complete and the standby EHC pump is placed in AUTO, or as directed by the Lead Examiner.

Page 3 of 29

Appendix D Scenario Outline Form ES-D-2 OpTest No.: I Scenarib No. 2 Event No: 2 Page i of 1 Event

Description:

IA HPI pump trips (SRO) (TS)

Time Position Applicants Actions or Behavior Plant response:

Standby HPI Pump starts on low Seal Inlet Header Flow (< 22 gpm) 1SA-02/B-2, HP RCP SEAL INLET HEADER FLOW HIGH/LOW, actuates.

Crew response:

The crew may perform Plant Transient Response Refer to ARG 1 SA-021B-2 BOP Low Alarm 3.2.1 Verify low seal flow condition with individual RCP seal flow indications 3.2.2 IF Low Seal Flow condition is due to an HPI System failure, refer to AP/i/A/1700/014 (Loss of Normal HPI Makeup and/or RCP Seal Injection) 3.2.3 IF Low Seal Flow condition is NOT due to an HPI System failure, adjust 1HP-31 (RCP Seal Flow Control) per OP/i/A11104/002(HPI System) 3.2.4 Monitor for low LDST level:

A. Makeup as required per OP/i/A/l 103/004 (Soluble Poison Concentrate Control)

B. Verify LDST levels as read on OAC:

O1AI 042 HP LDST LVL 1

O1A1 043 HP LDST LVL 2 C. IF an accurate LDST level CANNOT be maintained or verified, align suction for HPI Pumps from BWST per AP/1/A/l 700/014 (Loss of Normal HPI Makeup and/or Seal Injection)

Note: The crew may request an R&R to place the IA HPI pump switch in the OFF position.

Booth cue: If asked the WCC will evaluate placing the IC HPI pump in service.

SRO SRO refers to TS 3.5.2 and enters Condition A for one inoperable HPI pump.

APPLICABILITY: MODES 1 and 2, MODE 3 with RCS temperature > 350°F CONDITION A: One HPI pump inoperable REQUIRED ACTION: Restore HPI pump to OPERABLE status COMPLETION TIME: 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months This event is complete when TS 3.5.2 is addressed, or as directed by the Lead Examiner.

Page4of29

Appendix D Scenario Outline Form ES-D-2 0p-TestNo.: ¶ - ScenariO No.: 2 Event Nb.: 3 Page 1 of 3 Event

Description:

1A2 RCP lower seal failure (requires pump shutdown) (C: BOP, SRO)

Time Position j Applicants Actions or Behavior Plant response:

1SA-06/B-5, RC PUMP 1A2 SEAL CAVITY PRESS HI/LOW

OAC Alarm RCP 1A2 LOWER SEAL CAVITY PRESSURE HI HI

OAC Alarm RCP 1A2 UPPER SEAL CAVITY PRESSURE HI HI Crew response:

BOP Refer to the ARGs 3.1 Upper/Lower Seal Cavity Pressure High 3.1.1 Go To AP/1/A/1700/016, Abnormal RCP Operation, for limits and required action 3.2 Upper/Lower Seal Cavity Pressure Low 3.2.1 IF in Mode I or 2, Go To AP/1/A/1 700/01 6, Abnormal RCP Operation, for limits and required action SRO Refer to AP/1/A/1700/016 (Abnormal RCP Operation) 4.1 IAAT jjy RCP meets immediate trip criteria of End 5.1 (RCP Immediate Trip Criteria), THEN perform Steps 4.2-4.11.

RNO: GO TO Step 4.12.

4.12 IAAT either of the following apply:

y RCP approaching immediate trip criteria of End 5.1 (RCP Immediate Trip Criteria)

It is desired to secure a RCP THEN perform Steps 4.13-4.15.

RNO: GOTOStep4.16 Note: It is acceptable for the SRO to take either procedure path to secure the 1A2 RCP. Step 4.16 is on the next page.

4.13 Verify Rx Power> 70%

4.14 Initiate End 5.2 (Rapid Power Reduction) (see page 7) 4.15 WHEN Rx Power is 70%, THEN GO TO Step 4.2 4.2 Verify MODE 1 or2 4.3 Verify Rx power is 70% as indicated on all NIs 4.4 Verify three RCPs will remain operating after affected RCP is tripped 4.5 Verify y SG on Low Level Limits RNO: GO TO Step 4.8 4.8 Verify FDW masters in Auto 4.9 Stop affected RCP 4.10 Verify ICS re-ratios feed water to establish desired ATc Note: When the 1A2 RCP is secured, ICS will not re-ratio FDW as expected and initiate the next event (see page 8).

Page 5of29

Appendix D Scenario Outline Form ES-D-2 0p-Test No.: I Scenario No.: 2 EventNo.: 3 Page2 of 3 Event

Description:

1A2 RCP lower seal failure (requires pump shutdown) (C: BOP, SRO)

Time Position Applicants Actions or Behavior Crew response:

API1IAJ1700IO16 (Abnormal RCP Operation)

SRO 4.16 Announce AP entry using the PA system 4.17 Notify OSM to request evaluation by RCP Component Engineer 4.18 IAAT the failure is identified, THEN GO TO the applicable section per the following table:

Section Failure 4A Seal Failure 4B Abnormal Vibration 4C High or Low Oil Pot Level 4D Loss of Seal Return 4E Abnormal RCP TemperLitures SRO API1/A117001016 Section 4A, RCP Seal Failure

1. IAAT jy RCP meets immediate trip criteria of End 5.1, THEN perform Steps 2-11 RNO: GOTOStepl2

12. IAAT y of the following indicate external RCP seal leakage:

RB RIAs increasing in alarm

RCS Tave constant with LDST level decreasing more than normal

Quench Tank level rate increasing

RB Normal Sump rate increasing

Visual confirmation THEN initiate AP/02 (Excessive RCS Leakage)

13. Verify the following are open:

1HP-20

1HP-21

14. Verify the following is open for the affected RCP:

1HP-226(1A2RCP)

15. IAAT either of the following conditions apply to an operating RCP:

q RCS Pressure APacrossyseal

> 1000 psig 100 psid 1000 psig 35 psid THEN GO TO Step 16 to shut down the affected RCP since shut down of the RCP is desired due to a seal failure.

Page 6of29

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 ScenarFo No.: 2 Event N6.: 3 Page 3of 3 Event

Description:

1A2 RCP lower seal failure (requires pump shutdown) (C: BOP, SRO)

Time Position Applicants Actions or Behavior Crew response:

SRO API1IAJ1700IOI6 Section 4A, RCP Seal Failure 16 IAAT shut down of an RCP is desired, THEN perform Steps 17-27

17. VerifyMODElor2

18. Verify three RCPs will remain operating after affected RCP is tripped

19. Verify Rx power is 70% as indicated on aM NIs RNO: 1. Direct an RO to initiate End 5.2 (Rapid Power Reduction)

2. WHEN Rx power is 70% on aM NIs, THEN continue this procedure

20. Verify y SG on Low Level Limits RNO: GO TO Step 23

23. Verify FDW masters in Auto

24. Stop affected RCP

25. Verify ICS re-ratios feedwater to establish desired AT Note: When the 1A2 RCP is secured, the Delta Tc controller will fail and Feedwater will not properly re-ratio as expected and initiate the next event.

OATC APII6 Enclosure 5.2, Rapid Power Reduction

1. Verify ICS in AUTO

2. Initiate MAXIMUM RUNBACK to 70% as indicated by aM NIs

3. WHEN Rx Power is 70% as indicated by aM Nls, THEN press MAXIMUM RUNBACK to stop runback

4. Notify CR SRO that Rx Power is 70%

5. Adjust CTPD SET to match CTP DEMAND

6. Stop the following pumps:

_1E1 HTRDRN PUMP 1E2 HTR DRN PUMP

7. Verify Rx Power was reduced 15% within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period

8. Notify Primary Chemistry to perform Tech Spec SR 3.4.11.2 as required

9. EXIT this enclosure This event is complete when Rx power is reduced to 70% and the 1A2 RCP is secured, or as directed by the Lead Examiner.

Page 7of29

Appendix D Scenario Outline Form ES-D-2 O-Tt NO.: I ScéhriONo.: 2 - EventNo.: 4 - Page 1 of 2 Event

Description:

ATc Controller fails when 1A2 RCP is secured (I: OATC, SRO)

Time Position Applicants Actions or Behavior Crew Response:

The crew will be required to diagnose that Feedwater failed to ratio properly and mitigate the failure per API16 AP/11A117001016 Abnormal RCP Operation OATC 25. Verify ICS re-ratios feedwater to establish desired ATc RNO: 1. Place DELTA Tc station in HAND

2. Manually adjust DELTA Tc station to achieve desired z\Tc Note: The approximate value for total FDW flow at 65% power is 7.1 E6 lbmlhr. The IA SIG FDW flow should be 2.4 E6 Ibmlhr and the lB SIG FDW flow should be 4.7 E6 lbmlhr to achieve the desired ATc of zero.

3. IF DELTA Tc station does NOT control, THEN perform the following: (does not apply)

4. Initiate AP/28 (ICS Instrument Failures)

26. Initiate End 4.3 (Special Instructions for <4 RCP Operation) of OP/i/Ni 102/004 (Operation at Power)

27. Initiate the following notifications:

Notify OSM to make required notifications of OMP 1-14 (Notifications)

Notify Rx Engineering and request a power maneuver plan, if needed

Notify SOC if load reduction was required

Notify Chemistry to take RCS boron samples on a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months frequency SRO Refer to AP/1/N1700/028, ICS Instrument Failures 4.1 Provide control bands as required 4.2 Initiate notification of the following:

OSM to reference OMP 1-14 and Emergency Plan

STA 4.3 Verify a power transient 5% has occurred 4.4 Notify Rx Engineering and discuss the need for a maneuvering plan 4.5 Use the following, as necessary, to determine the applicable section from table in Step 4.6

OAC alarm video

OAC display points

Control Board indications

SPOC assistance, as needed This event is complete when the crew initiates AP128, or as directed by the Lead Examiner.

Page8of29

Appendix D Scenario Outline Form ES-D-2 Op-Test no.: 1 Scenario No.: 7 Event No.: 4 Page 2 of 2 Event

Description:

AT Controller fails when 1A2 RCP is secured (I: OATC, SRO)

Time Position Applicants Actions or Behavior Crew Response:

SRO API1 IA/i 700/028, ICS Instrument Failures 4.1 Provide control bands as required 4.2 Initiate notification of the following:

. OSM to reference OMP 1-14 and Emergency Plan

. STA 4.3 Verify a power transient 5% has occurred 4.4 Notify Rx Engineering and discuss the need for a maneuvering plan 4.5 Use the following, as necessary, to determine the applicable section from table in Step 4.6

. OAC alarm video

. OAC display points

. Control Board indications

. SPOC assistance, as needed 4.6 GO TO the applicable section per the following table:

q Section Failure 4F Delta T SRO AP/i/A/1700/028 Section 4F

1. Ensure the following in HAND:

1A FDW MASTER lB FDW MASTER 0

_DELTAT

2. Re-ratio feed water flow, as required, to establish DELTA T while maintaining total feed water flow constant

3. Notify SPOC to perform the following:

Investigate and repair the failed Delta T controller

4. WHEN notified by SPOC that Delta T controller has been repaired, THEN GO TO OP/i/A/I 102/004 A End (Placing ICS Stations To Auto)

Note: The Delta T controller will not be repaired for this scenario.

This event is complete when the crew initiates AP!28, or as directed by the Lead Examiner.

Page 9 of 29

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 - Event No.: 5 Page lof I Event

Description:

HPSW Jockey Pump trips with HPSW auto initiation logic inoperable (C: BOP, SRO) (TS)

Time Position Applicants Actions or Behavior Plant Response:

I SA-9/A-8 HPSW Header A/B PRESS LOW

1SA-91D-8 HPSW JOCKEY PUMP OFF

HPSW header pressure decreases due to Jockey Pump trip.

Crew Response:

BOP Refer to ARG 1 SA-9/D-8 3.1 Verify automatic actions until jockey pump is restarted 3.2 IF there is NO evidence of breaker and/or pump motor problem, attempt to restart jockey pump one time. If restart is unsuccessful, notify Maintenance Department.

The crew may refer to ARG 1 SA-9/A-8 3.1 Verify proper jockey pump operation 3.2 Refer to SLC 16.9.8a 3.3 Verify HPSW pumps start (start manually if NOT already in operation per OP/0/AI1 104/011) when preset levels in EWST are reached 3.4 IF HPSW Header Pressure continues to decrease AND EWST level is NOT dropping, manually start a HPSW Pump 3.5 Refer to API1 -2/A/l 700/030 (Aux Building Flood) 3.6 Investigate and correct reason for excessive HPSW usage 3.7 Verify BASE and STANDBY HPSW Pumps stop at 80,000 gals 3.8 IF manually started, return HPSW Pumps when NO longer needed Booth Cue: After the crew manually starts the HPSW Jockey Pump, call the Control Room as SPOC and report During investigation of the Jockey Pump failure, it has been determined that the A HPSW Pump auto initiation logic circuit is OOS (or not functioning properly)

Booth Cue: If the crew dispatches a NEO to determine if a problem exists with HPSW Jockey Pump motor/breaker, use TIME COMPRESSION and inform the RO that no problem was found with the Jockey Pump motor or breaker SRO SRO refers to SLC 16.9.1 and enters Condition A for HPSW pump A and B auto initiation logic inoperable.

APPLICABILITY: At all times CONDITION A: Equipment inoperable in the Oconee Fire Suppression Water Supply System REQUIRED ACTION: Restore inoperable equipment to OPERABLE status COMPLETION TIME: 7 days This event is complete when the Jockey Pump has been restarted and the SRO refers to SLC 16.9.1, or as directed by the Lead Examiner.

Page 10 of 29

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 6 Page lof 2 Event

Description:

PZR spray valve (I RC-I) fails OPEN (C: OATC, SRO)

Time__j Position Applicants Actions or Behavior Plant Response:

RCS pressure will decrease

1SA-2/D-3 (RC PRESS HIGH/LOW)

Crew Response:

Note: The crew may perform Plant Transient Response (PTR)

BOP Refer to Alarm Response Guide I SA-2/D-3 (RC PRESS HIGH/LOW) 3.2 Low Alarm 3.2.1 Refer to AP/11N17001044 (Abnormal Pressurizer Pressure Control)

SRO Refer to AP/1/N1 700/044 (Abnormal Pressurizer Pressure Control)

1. Entry Conditions 1.1 Inability to maintain control of RC pressure due to failure of the PORV, 1 RC-1, or PZR heaters as indicated by jy of the following:

High or Low RC pressure alarms

RC pressure outside of control band

Pressurizer Relief Valve Flow Statalarm

3. Immediate Manual Actions 3.1 IAAT aH of the following conditions exist:

PORV open RC pressure < 2300 psig (HIGH) or 480 psig (LOW)

PZR level 375 THEN close I RC-4 Note: The crew may perform Immediate Manual Action Step 3.2 from memory prior to the SRO entering AP144.

3.2 IAAT aM the following conditions exist:

RC pressure < 2155 psig RC pressure decreasing without a corresponding decrease in PZR level PZR heaters unable to maintain RCS pressure THEN close the following:

1RC-1 1 RC-3 Note: If the block valve (I RC-3) is not closed, the Reactor will trip on variable low pressure and ES actuation will occur.

Page II of29

Appendix D Scenario Outline Form ES-D-2 bp-Test No.: I Scenario No.: 2 Event No.: 6 Page 2 of 2 Event

Description:

PZR spray valve (IRC-I) fails OPEN (C: OATC, SRO)

Time Position

[ Applicants Actions or Behavior Crew Response:

Note: The PZR spray valve (IRC-1) will remain failed for the remainder of the scenario and the operator will be required to maintain RCS pressure manually, as required, using IRC-3.

Note: IRC-1 normally maintains RCS pressure 2155-2205 psig.

SRO AP/1 IA/i 700/044 (Abnormal Pressurizer Pressure Control) 4.1 Announce AP entry using the PA system 4.2 GO TO the applicable per the following table:

-J Failure Caused Step RCS Pressure Decrease 4.3 Increase 4.19 4.3 Verify the following:

1 RC-4 failed to close PORV open RNO: GO TO Step 4.5 4.5 Verify 1RC-1 failed OPEN 4.6 Position the following to maintain RC pressure within desired band, as required:

IRC-1 I RC-3 4.7 Verify RC pressure decreasing uncontrollably RNO: GO TO Step 4.14 4.14 Verify PZR heaters maintaining RCS pressure within desired band 4.15 Notify SPOC to repair malfunctioning component 4.16 Ensure requirements of following are met: (no TS should not apply)

TS 3.4.1 (RCS Pressure, Temperature, and Flow DNB Limits)

TS 3.4.9 (Pressurizer)

_TS 3.4.12 (LTOP System)

SLC 16.5.1 (RCS Vents) 4.17 WHEN repairs complete, THEN place the following components in desired position for current plant conditions as determined by CR SRO This event is complete when the RCS pressure decrease has been stopped and PZR level is stable, or as directed by the Lead Examiner.

Page 12 of 29

Appendix D Scenario Outline Form ES-D-2 Op-Test No. 1 Scenario No.: 2 Event No.: 7 Page 1 of 3 Event

Description:

Loss of power to ITB (C: OATC, SRO)

ATWS (Rule 1) with IC HPI pump failure Time Position j Applicants Actions or Behavior Plant Response:

An automatic RX trip should have occurred due to the loss of 2 RCPs.

Crew Response:

The SRO will direct the OATC to perform EOP Immediate Manual Actions The SRO will direct the BOP to perform a Symptoms Check OATC EOP Immediate Manual Actions:

3.1 Depress REACTOR TRIP pushbutton.

3.2 Verify reactor power < 5% FP and decreasing.

RNO: GO TO Rule 1 (ATWS/Unanticipated Nuclear Power Production)

OATC EOP Rule I (CT-24)

1. Verify any Power Range NI 5% FP

2. Initiate manual control rod insertion to the IN LIMIT

3. Notify CR SRO to GO TO UNPP tab (see next page)

4. Open 1HP-24 and IHP-25

5. Ensure only one of the following operating:

1AHPIPUMP

1BHPIPUMP

6. Start 1C HPI PUMP Note: The IC HPI pump will not start and only the lB HPI pump (the standby HPI pump) will be operating.

RNO: 1. Start the standby HPI pump

2. IF at least two HPI pumps are operating, THEN open I HP-409

7. Open 1HP-26 and IHP-27

8. Dispatch one operator without wearing Arc Flash PPE to open 600V CRD breakers on the following:

1X9-5C (Unit 1 CRD Norm Fdr Bkr)

2X1-5B (Unit 1 CRD Alternate Fdr Bkr)

Booth Cue: Trip CRD breakers 4 minutes after the CR request.

9. Verify only two HPI pumps operating RNO: IF afl HPI pumps operating, THEN perform the following:

(does not apply)

10. EXIT this rule Page 13 of 29

Appendix D Scenario Outline Form ES-D-2 p-Tht N.: I enar1o No.: 2 Event No.: 7 Page 2 of 3 Event

Description:

Loss of power to ITB (C: OATC, SRO)

ATWS (Rule 1) with IC HPI pump failure Time Position Applicants Actions or Behavior Crew Response:

SRO EOPUNPPtab:

1. Ensure Rule 1 is in progress or complete

2. Verify Main FDW is operating and in AUTO

3. IAAT Main FDW is NOT operating, THEN perform the following:

A. Trip the turbine-generator B. Start available EFDW pumps

4. IAAT all power range NIs are < 5% FP, THEN perform Steps 5-6 RNO: GOTOStep7

5. Depress turbine TRIP pushbutton

6. Verify aM turbine stop valves closed

7. Verify y wide range NI>1% FP RNO: GOTOStepl5

8. Open IRC-4 and 1HP-5

9. Maximize letdown

10. Verify Main FDW available

11. Adjust Main FDW flow as necessary to control RCS temperature

12. Verify overcooling in progress RNO: GOTOStepl5

15. Secure makeup to LDST

16. WHEN aM Wide Range NIs are 1% FP, AND decreasing, THEN continue

17. Control RCS temperature using the following methods:

Tave 555°F Adjust SG pressure as necessary to stabilize RCS temperature using either of the following:

TBVs

Dispatch two operators to perform End 5.24 (Operation of the ADVs)

Tave > 555°F Utilize Rule 7 (SG Feed Control) to control SG feed rate as necessary to maintain cooldown rate within Tech Spec limits during the approach to the SG Level Control Point

18. Throttle HPI per Rule 6 (HPI)

19. WHEN RCS pressure <2300 psig, THEN continue

20. Verify PORV closed

21. Adjust letdown flow as desired

22. Verify RCP seal injection available

23. GO TO Subsequent Actions tab Page 14 of 29

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 7 Page 3 of 3 Event

Description:

Loss of power to ITB (C: OATC, SRO)

ATWS (Rule I) with IC HPI pump failure Time__[ Position Applicants Actions or Behavior Crew Response:

SRO EOP Subsequent Actions tab:

4.1 Verify a control rods in Groups 1-7 fully inserted 4.2 Verify Main FDW in operation 4.3 Verify either of the following:

Main FDW overfeeding causing excessive temperature decrease Main FDW underfeeding causing SG level decrease below setpoint RNO: GO TO Step 4.5 4.5 IAAT Main FDW is operating, AND level in y SG is> 96% on the Operating Range, THEN perform Steps 4.6 4.8 RNO: GO TO Step 4.9 4.9 IAAT TBVs CANNOT control SG pressure at desired setpoint, THEN manually control pressure in affected SG using either of the following:

TBVs Dispatch two operators to perform End 5.24 (Operation of the ADV5) (PS) 4.10 Verify 1RIA-40 operable with CSAE OFF-GAS BLOWER operating 4.11 GOTOStep4.14 4.14 Dispatch operator with End 5.29 (MSRV Locations) to verify aM MSRVs have reseated 4.15 Verify ES is required RNO: 1. Initiate End 5.5 (Pzr and LDST Level Control)

2. GOTOStep4.17 This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.

Page 15 of 29

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: f enario No.: 2 Event No.: 8 Page 1 of 10 Event

Description:

SBLOCA with LOSCM (ES actuation) (M: ALL)

Rapid RCS cooldown Time Position Applicants Actions or Behavior Plant Response:

RCS pressure will begin to decrease 1SA-08/A-9 RM Area Monitor Radiation High 1SA-08/B-9 Process Monitor Radiation High 1SA-08/E-9 Reactor Building Normal Sump Isolate ES Channels 1 and 2 will actuate on low RCS pressure (< 1600 psig)

ES Channels 3 6 will actuate on High RB pressure (> 3 psig) in 6 mm Crew Response:

When y SCM indicates 0°F, the SRO will direct an operator to perform Rule 2. (details on page 21)

The SRO will transfer to the LOSCM tab of the EOP from Subsequent Actions Parallel Actions page.

SRO The SRO will direct an operator to initiate EOP End 5.1, ES Actuation, per LOSCM Parallel Actions Page. (details begin on page 22)

If the crew asks, Unit 2 will perform AP/1/A11700/018 (Abnormal Release of Radioactivity) actions.

Note: The crew may transfer to the ICC tab if it is noticed that Rx Vessel head level briefly indicates 0 (see page 20)

SRO EOP LOSCM tab

1. Ensure Rule 2 (Loss of SCM) is in progress or complete

2. Verify Station ASW feeding y SG RNO: GOTOStep4

4. Verify LOSCM caused by excessive heat transfer RNO: GOTOStep6

6. IAAT either of the following exists:

LPI FLOW TRAIN A LPI FLOW TRAIN B 3400 gpm

Only one LPI header in operation with header flow 2900 gpm THEN GO TO LOCA CD tab

7. Verify SSF activated per AP/25 with of the following systems required:

SSF RC Makeup

SSF Aux Service Water RNO: GOTOStep9 Page 16of29

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 8 Page 2 of 10 Event

Description:

SBLOCA with LOSCM (ES actuation) (M: ALL)

Rapid RCS cooldown Time Position Applicants Actions or Behavior Crew Response:

SRO EOP LOSCM tab

9. Verify all of the following exist:

NO RCPs operating

HPI flow in both HPI headers

Adequate total HPI flow per Figure 1 (Total Required HPI Flow)

RNO: GOTOStepil Note: Since only one HPI pump will be operating, HPI flow will not exist in both HPI headers

11. IAAT all SCMs are> 0°F, OR all the following exists:

NO RCPs operating

HPI flow in both HPI headers

Adequate total HPI flow per Figure 1 THEN GO TO Step 89

12. Start both MDEFDW pumps

1AMDEFDW Pump

1BMDEFDWPump

13. Start the TDEFDWP

14. Establish 300 gpm EFDW flow to each of the following:

1ASG

1BSG

15. Verify both MDEFDW pumps are operating

16. Initiate full depressurization of both SGs utilizing either of the following:

TBVs

ADVs

17. Initiate EFDW flow to all available SGs to LOSCM setpoint at maximum allowable rate (per Table 3 of Rule 7)

Note: The maximum flow for IA and lB MD EFDW pumps are 600 gpm per pump with suction from the UST. The TO EFDW pump maximum flow is 950 gpm. The maximum EFDW flow per header is 1000 gpm.

18. Trip both Main FDW Pumps

19. Place FDW block valve switches in close:

1FDW-33

1FDW-31

1FDW-42

1FDW-40 Page 17of29

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 8 Page 3 of 10 Event

Description:

SBLOCA with LOSCM (ES actuation) (M: ALL)

Rapid RCS cooldown Time__[ Position Applicants Actions or Behavior Crew Response:

SRO EOP LOSCM tab

20. Open 1AS-40 while closing 1MS-47

21. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete

22. GOTO Step 34

34. IAAT RCS pressure reaches 2450 psig, THEN perform Steps 35 and 36 RNO: 1. IF HPI forced cooling is in progress, THEN GO TO Step 37

2. Close 1 RC-4

3. GOTOStep37

37. Close:

1GWD-17

1HP-1

1HP-2

1RC-3

38. Verify either of the following:

Core superheated

Rx vessel head level at 0 RNO: GO TO Step 40

40. IAAT BWST level is 19, THEN initiate End 5.12 (ECCS Suction Swap to RB ES)

41. WHEN aH SCMs are > 0°F, OR aN the following exist:

NO RCPs operating

HPI flow in both HPI headers

Adequate total HPI flow per Figure 1 THEN maintain SG pressure < RCS pressure utilizing either of the following:

TBVs

ADVs

42. Verify primary to secondary heat transfer exists

43. Perform the following:

Control steaming and feed rates on intact SGs to maintain cooldown rate within Tech Spec limits:

TId> 280°F: 50°F I Y hr

TId 280°F: 25°F I ,4 hr Utilize either of the following:

TBVs

ADVs

44. Initiate End 5.16 (SG Tube-to-Shell AT Control)

Page 18 of 29

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 8 Page 4of 10 Event

Description:

SBLOCA with LOSCM (ES actuation) (M: ALL)

Rapid RCS cooldown Time Position Crew Response:

Applicants Actions or Behavior 1

SRO EOPLOSCMtab

45. IAAT an SGTR has occurred, AND y affected SG approaches overfill:

46. Verify HPI forced cooling in progress RNO: GO TO Step 48

48. Verify CETCs trend decreasing

49. Verify primary to secondary heat transfer is excessive RNO: GO TO Step 51

51. Verify indications of SGTR 25 gpm RNO: GO TO Step 53

53. Verify required RCS makeup flow within normal makeup capability RNO: GO TO LOCA CD tab SRO EOP LOCACD tab

1. IAAT BWST level is 19, THEN initiate End 5.12 (ECCS Suction Swap to RBES)

2. Verify ES actuated

3. GOTOStep7

7. Perform the following:

Ensure all RBCUs in low speed Open I LPSW-1 8 Open 1 LPSW-21 Open 1 LPSW-24

8. Initiate End 5.35 (Containment Isolation)

9. Start all RB Aux Fans

10. IAAT either of the following exists:

LPI FLOW TRAIN A LPI FLOW TRAIN B 3400 gpm Only one LPI header in operation with header flow 2900 gpm THEN GOTO Step 11

11. StopallRCPs

12. Dispatch an operator to perform the following (Unit 1 Equip Rm):

Remove white tag and close 1XO-F5C (1A CFT Outlet)

Remove white tag and close 1XP-F5C (1 B CFT Outlet)

_Close 1XS2-F3D (1LP-104 Post LOCA Boron Dilute)

This event is complete when the SRO transfers to the LOCA CD tab, or as directed by the Lead Examiner.

Page 19 of 29

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 8 Page 5 of 10 Event

Description:

SBLOCA with LOSCM (ES actuation) (M: ALL)

Rapid RCS cooldown Time Position Applicants Actions or Behavior Crew Response:

SRO EOP ICC tab (if required)

1. IAAT CETCs> 1200°F, AND TSC is ready to provide guidance, THEN perform the following:

A. Notify TSC to enter the OSAG B. EXIT this procedure

2. Ensure full HPI and control per Rule 6 (H P1)

3. IAAT RCS pressure is 550 psig, OR RB pressure is 3 psig, THEN perform Steps 4-8

4. Open 1LP-21 and 1LP-17

5. Start IA LPI Pump

6. Open 1LP-22 and 1LP-18

7. Start lB LPI Pump

8. Verify two LPI pumps operating

9. IAAT aH the following exists:

1C LPI Pump off 1C LPI Pump available LPI required ECCS pump suction aligned to BWST 1A LPI Pump unavailable lB LPI Pump unavailable THEN perform Steps 10-13 RNO: GOTO Step 14

14. Open 1CF-1 and 1CF-2

15. IAAT core SCM is 0°F, THEN GO TO LOCA CD tab (page 19)

This event is complete when the SRO transfers to the LOCA CD tab, or as directed by the Lead Examiner.

Page 20 of 29

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 8 - Page6of 10 Event

Description:

SBLOCA with LOSCM (ES actuation) (M: ALL)

Rapid RCS cooldown Time Position Applicants Actions or Behavior Crew Response:

Initiate Rule 2 when jy SCM indicates 0°F OATC/BOP EOP Rule 2, Loss of SCM

1. IAAT aB exist:

jySCM0°F

Rxpower1%

2 minutes elapsed since loss of SCM THEN perform Steps 2 and 3

2. Stop all RCPs (CT-I) (Within 2 minutes of LOSCM)

3. Notify CR SRO of RCP status

4. Verify Blackout exists RNO: GOTOStep6

6. Open 1HP-24 and 1HP-25

7. Start aM available HPI pumps

8. GOTOStepl3

13. Open 1HP-26 and 1HP-27

14. Verify at least two HPI pumps are operating using two diverse indications RNO: GOTOStep27

27. Verify at least two HPI pumps are operating RNO: Maximize HPI flow 475 gpm (including seal injection for A hdr only)

28. Verify RCS pressure > 550 psig

29. IAAT either exists:

LPI FLOW TRAIN A LPI FLOW TRAIN B 3400 gpm

Only one LPI header in operation with header flow 2900 gpm THEN GO TO Step 34

30. Dispatch two operators to perform End 5.24 (Operation of the ADV5) 31.. Verify ISA-2/C-8 (AFIS HEADER A INITIATED) lit RNO: Select OFF for both digital channels on AFIS HEADER A

32. Verify 1SA-2/D-8 (AFIS HEADER B INITIATED) lit RNO: Select OFF for both digital channels on AFIS HEADER B

33. Notify CR SRO:

Suspend Rule 3 until directed by LOSCM tab

Degraded HPI exists

34. EXIT this rule These actions are complete when Rule 2, Loss of Subcooling Margin is exited.

Page 21 of 29

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 8 - Page 7 of 10 Event

Description:

SBLOCA with LOSCM (ES actuation) (M: ALL)

Rapid RCS cooldown Time Position Applicants Actions or Behavior Crew Response:

Note: Initially, ES Channels I and 2 will actuate when RCS pressure decreases below 1600 psig. When Reactor Building pressure increases to > 3 psig, ES Channels 3-6 will actuate. If the RO reaches Step 15 prior to ES 3&4 actuation, the procedure directs going to Step 51. When ES Channel 3&4 actuate, the RO should return to IAAT Steps 3, 9, 10, and 15 and perform any required actions OATC/BOP EOP Enclosure 5.1, ES Actuation

1. Determine all ES channel that should have actuated based on RCS pressure and RB pressure:

q Actuation Setpoint Associated ES (psig) Channel 1600 (RCS) 1 &2 550 (RCS) 3&4 3 (RB) 1,2,3,4,5,&6 10 (RB) 7&8

2. Verify aM ES channels associated with actuation setpoints have actuated

3. IAAT additional ES actuation setpoints are exceeded, THEN perform Steps I 2

4. Place Diverse HPI in BYPASS

5. Perform both:

Place ES CH 1 in MANUAL

Place ES CH 2 in MANUAL

6. Verify Rule 2 in progress complete

7. Verify J2Y RCP operating RNO: GO TO Step 9

8. Open I HP-20 and 1 HP-21

9. IAAT aM exist:

Voter associated with ES channel is in OVERRIDE

An ES channel is manually actuated

Components on that channel require manipulation THEN depress RESET on the required channel

10. IAAT jjy RCP is operating, AND ES Channels 5 an 6 actuate, THEN perform Steps 11-14 RNO: GOTOStepl5

15. IAAT ES Channels 3 & 4 are actuated, THEN GO TO Step 16 RNO: GO TO Step 51 (see page 24 if required)

16. Place Diverse LPI in BYPASS Page 22 of 29

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: 8 Page 8 of 10 Event

Description:

SBLOCA with LOSCM (ES actuation) (M: ALL)

Rapid RCS cooldown Time Position Applicants Actions or Behavior Crew Response:

EOP Enclosure 5.1, ES Actuation

17. Perform both:

Place ES CH 3 in MANUAL

Place ES CH 4 in MANUAL

18. IAAT jy LPI pump is operating against a shutoff head, THEN at the CR SROs discretion, stop affected LPI pumps

19. IAAT RCS pressure is < LPI pump shutoff head, THEN perform Steps 20 21 -

RNO: GOTOStep22

22. IAAT 1A and 1 B LPI PUMPs are off! tripped, AND aB of the following exist:

RCS pressure < LPI pump shutoff head

1 LP-1 9 closed

1 LP-20 closed THEN perform Steps 23 24 -

RNO: GO TO Step 25

25. IAAT IA LPI PUMP fails while operating, AND lB LPI PUMP is operating, THEN close 1LP-17

26. IAAT 1 B LPI PUMP fails while operating, AND 1A LPI PUMP is operating, THEN close 1LP-18

27. Start A and B OUTSIDE AIR BOOSTER FANs (CT-27) (Must be started within 30 minutes of LOCA)

28. Notify Unit 3 to start 3A and 3B OUTSIDE AIR BOOSTER FANs

29. Verify ICF-1 and 1CF-2 are open

30. Verify 1HP-410 closed

31. Secure makeup to the LDST

32. Verify a ES channel I 4 components are in the ES position RNO: 1. IF I HP-3 fails to close, THEN close 1 HP-i

2. IF 1 HP-4 fails to close, THEN close 1 HP-2

3. Notify SRO to evaluate components NOT is ES position and initiate action to place in ES position if desired Note: The IA & IC HPI pumps and IA & lB LPI pumps will not be in the ES position.

33. Verify Unit 2 turbine tripped RNO: GOTOStep36

36. Close 1 LPSW-l 39

37. Place in FAIL OPEN:

1LPSW-251 FAIL SWITCH 1LPSW-252 FAIL SWITCH

38. Start all available LPSW pumps Page 23 of 29

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I - Scenario No.: 2 Event No.: 8 Page 9 of 10 Event

Description:

SBLOCA with LOSCM (ES actuation) (M: ALL)

Rapid RCS cooldown Time__[ Position Applicants Actions or Behavior Crew Response:

EOP Enclosure 5.1, ES Actuation

39. Verify either:

Three LPSW pumps operating Two LPSW pumps operating when Tech Specs only requires two operable

40. Open 1 LPSW-4 and 1 LPSW-5

41. IAAT BWST level 19, THEN initiate End 5.12 (ECCS Suction Swap to RBES)

42. Dispatch an operator to perform End 5.2 (Placing RB Hydrogen Analyzers In Service) (PS)

43. Select DECAY HEAT LOW FLOW ALARM SELECT switch to ON

44. IAAT ES channels 5 & 6 have actuated THEN perform Step 45

45. Verify aH ES channel 5 & 6 components are in the ES position

46. IAAT ES channels 7 & 8 have actuated, THEN perform Step 47 RNO: GO TO Step 48

48. Notify U2 CR SRO that SSF is inoperable due to OTS1-1 open

49. IAAT conditions causing ES actuation have cleared, THEN initiate End 5.41 (ES Recovery)

50. WHEN CR SRO approves, THEN EXIT this enclosure Note: The following steps may be required depending on how quick the RO gets to Step 15 of End 5.1. If the RO reaches Step 15 prior to ES 3&4 actuation, the procedure directs going to Step

51. When ES Channel 3&4 actuate, the RO should return to IAAT Steps 3, 9, 10, and 15 and perform any required actions (see page 21).

51. Start A and B OUTSIDE AIR BOOSTER FANS

52. Notify Unit 3 to start 3A and 3B OUTSIDE AIR BOOSTER FANS

53. Verify 1 CF-i and 1 CF-2 are open

54. Verify i HP-41 0 closed

55. Secure makeup to the LDST

56. Verify all ES channel 1&2 components are in the ES position RNO: 1. IF 1 HP-3 fails to close, THEN close 1 HP-i

2. IF 1 HP-4 fails to close, THEN close 1 HP-2

3. Notify SRO to evaluate components NOT is ES position and initiate action to place in ES position if desired Note: The IC HPI pump will not be in the ES position

57. Verify Unit 2 turbine tripped RNO: GOTOStep6O

60. Close 1 LPSW-1 39 Page 24 of 29

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Eveflt No.: 8 P?gQtQQf 10 Event

Description:

SBLOCA with LOSCM (ES actuation) (M: ALL)

Rapid RCS cooldown Time Position Applicants Actions or Behavior Crew Response:

EOP Enclosure 5.1, ES Actuation

61. Place in FAIL OPEN:

_1 LPSW-251 FAIL SWITCH 1LPSW-252 FAIL SWITCH

62. Start all available LPSW pumps.

63. Verify either:

Three LPSW pumps operating Two LPSW pumps operating when Tech Specs only requires two operable

64. Open:

1LPSW-4 1LPSW-5

65. IAAT BWST level 19, THEN initiate End 5.12 (ECCS Suction Swap to RBES).

66. Dispatch an operator to perform End 5.2 (Placing RB Hydrogen Analyzers In Service). (PS)

67. Notify U2 CR SRO that SSF is inoperable due to OTSI-1 open.

68. IAAT conditions causing ES actuation have cleared, THEN initiate End 5.41 (ES Recovery).

69. WHEN CR SRO approves, THEN EXIT this enclosure.

Page 25 of 29

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: Page I of 2 Event

Description:

EOP Enclosure 5.5 (if required)

Time Position Applicants Actions or Behavior Crew Response:

OATC/BOP EOP Enclosure 5.5, Pzr and LDST Level Control (if needed)

1. Utilize the following as necessary to maintain desired Pzr level:

IAHPIPump

IBHPIPump

1HP-26

1HP-7

1 HP-I 20 setpoint or valve demand

1HP-5

2. IAAT makeup to the LDST is desired, THEN makeup from 1A BHUT.

3. IAAT it is desired to secure makeup to LDST, THEN secure makeup from 1A BHUT.

4. IAAT it is desired to bleed letdown flow to IA BHUT, THEN perform the following:

A. Open:

ICS-26

1CS-41 B. Position 1 HP-14 to BLEED.

C. Notify SRO.

5. IAAT letdown bleed is NO longer desired, THEN position 1HP-14 to NORMAL.

6. IAAT 1C HPI PUMP is required, THEN perform Steps 79.

RNO: GO TO Step 10.

7. Open 1HP-24 and 1HP-25

8. Start 1C HPI PUMP

9. Throttle the following as required to maintain desired Pzr level:

1HP-26

1HP-27

10. IAAT LDST level CANNOT be maintained, THEN perform Step 11.

RNO: GOTOStepl2.

11. Perform the following:

Open 1HP-24

Open IHP-25

Close 1HP-16 Page 26 of 29

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 2 Event No.: Page 2 of 2 Event

Description:

EOP Enclosure 5.5 (if required)

Time Position Applicants Actions or Behavior Crew Response:

OATC/BOP

12. IAAT additional makeup flow to LDST is desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close 1CS-48 (1A BHUT Recirc) (A-i-i 07, Unit 1 RC Bleed Transfer Pump Rm.).

13. IAAT two Letdown Filters are desired, THEN perform the following:

Open 1HP-i7.

Open 1HP-18

14. IAAT aM of the following exist:

Letdown isolated

LPSW available

Letdown restoration desired THEN perform Steps 15 33 -

RNO: GO TO Step 34.

34. IAAT it is determined that letdown is unavailable due to equipment failures or letdown system leakage, THEN notify CR SRO to initiate AP/32 (Loss of Letdown).

35. IAAT> 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:

A. Obtain SRO concurrence to reduce running HPI pumps.

B. Secure the desired HPI pumps.

C. Place secured HPI pump switch in AUTO, if desired.

36. IAAT the following conditions exist:

Makeup from BWST NOT required

LDST level > 55

AM control rods inserted

Cooldown Plateau NOT being used THEN close:

1HP-24

1HP-25

37. Verify 1CS-48 (1A BHUT Recirc) has been closed to provide additional makeup flow to LDST.

RNO: GO TO Step 39.

39. Verify two Letdown Filters in service, AND only one Letdown filter is desired.

RNO: GOTOStep4l.

41. WHEN directed by CR SRO, THEN EXIT this enclosure.

These actions are complete when EOP Enclosure 5.5 (Pzr and LDST Level Control) is exited.

Page 27 of 29

Appendix D Scenario Outline Form ES-D-2 CRITICAL TASKS CT-24 Shutdown ReactorATWS In the event the reactor fails to trip in response to automatic and manual demands, then de-energize CRDMs, begin maximum boric acid addition to RCS, and maintain adequate primary to secondary heat transfer.

CT-I Trip All RCPs Tripping all RCPs of a within 2 minutes of a LOSCM ensures fuel will remain adequately covered and avoid possible fuel damage.

CT-27 Implementation of Control Room Habitability Guidance within 30 minutes of LOCA Page 28 of 29

Appendix D Scenario Outline Form ES-D-2 SAFETY Take a Min-ute UNIT 0 (OSM)

SSF Operable: Yes KHUs Operable: UI - OH, U2 - UG H LCTs Operable: 2 Fuel Handling: No UNIT STATUS (CR SRO)

Unit I Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 87% Mode: I Mode: I Gross MWE: 804 100% Power 100% Power RCS Leakage: +.025 gpm

. EFDW Backup: Yes EFDW Backup: Yes (No WCAP action level)

RBNS Rate: .01 gpm Technical SpecificationslSLC Items (CR SRO)

ComponentlTrain OOS Restoration TSISLC #

DatelTime Required DatelTime AMSAC/DSS Bypassed Today I 06:30 7 Days B

Shift Turnover Items (CR SRO)

Primary

. SASS in MANUAL for l&E testing

. AMSAC/DSS Bypassed for I&E testing

. Reactor power reduced for Turbine Valve Testing.

. GWD Tank B release in progress Secondary

1SSH-1, 1SSH-3, 1SD-2, ISD-5, 1SD-140, 1SD-303, ISD-355, 1SD-356 and 1SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event.

Complete PT111A102901003 Turbine Valve Movement test for CVI. Begin at step 2.1 of End.

13.2 (Control Valve Movement At Power)

Reactivity Management (CR SRO)

R2 Reactivity management controls RCS Boron: 30 ppmB Gp 7 Rod Position: 80% established in the Control Room per SOMP 01-02 Human Performance Emphasis (OSM)

Procedure Use and Adherence

Appendix D Scenario Outline Form ES-D-1 ILT4O Oct, 201 1 Facility: Oconee Scenario No.: 3fs Op-Test No.: I Examiners: Operators:

Initial Conditions:

. Reactor Power = 87% Unit 2: 100% Unit 3: 100%

Turnover:

. Turbine Valve Movement PT has just been completed and awaiting maneuvering plan to return to full power

. SASS in Manual

. AMSAC/DSS bypassed for I&E testing Event Malfunction Event No. No. Event Type* Description

[

Oa Pre-Insert SASS in MANUAL Ob Pre-Insert AMSAC/DSS bypassed Oc Pre-Insert A AFIS Circuit Disabled B AFIS Circuit Disabled Od Pre-Insert 1 C HPI pump will not start 1 MPI15O I: OATC, SRO (TS) PZR RTD A Fails LOW (TS) 2 MSS200 C: BOP, SRO Condenser Vacuum Leak 1 B Main FDW Pump Active Thrust Bearing 3 Override C: BOP, SRO Temperature HIGH Requiring Manual Trip C: OATC, BOP, 4 Override Inadvertent ES Channel I actuation (TS)

SRO(TS) 5 MCSOO5 I: OATC, SRO Controlling Tave Fails HIGH 6 MSS36O,30 M: ALL IA MSLB in the reactor building MSS33O Loss of all SG feed 7 MSS26O M: ALL HPI F/C MSS27O (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: I Page 1 of 2 Event

Description:

PZR RTD A Fails LOW (I: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior Booth Cue: Call as a WCC SRO (Tony Green) and inform the BOP that you are performing a key locker audit. Request that he go to the RPS cabinets and report if any shutdown bypass keys are still inside.

(This will help to ensure the OATC will take actions for the PZR RTD failure)

ARG 1 SA-06/D-9 FW TREATED WATER PANEL TROUBLE

3. Manual Action 3.1 Contact Water Treatment Room and/or inform secondary Chemist Note: Once the BOP has taken action to respond to the alarm, the PZR RTD failure will begin.

Plant Response:

Statalarms:

OAC (RC PZR level 1 &3 mismatch)

OAC (RC PZR level 2&3 mismatch)

Board indications:

PZR level 1 and 2 indicates 150 inches

PZR level 3 indicates 220 inches and slowly increasing Crew Response:

Refer to ARG 1 SA-02/C-3 (RC Pressurizer Level High/Low):

1. Alarm Setpoint 1.1 High 260 water 1.2 Low 200 water

2. Automatic Action None

3. Manual Action 3.1 Check alternate PZR level indications.

3.2 Check for proper Makeup/Letdown flows and adjust to restore proper level.

RO may take 1 HP-i 20 to manual to control PZR level.

Note: If taken to MANUAL to control PZR level, the RO should place IHP-120 back to AUTO.

3.3 Refer to the following procedures as required:

AP/1/A1i700/002 (Excessive RCS Leakage)

AP/1/A1i700/0i4 (Loss of Normal HPI M/U and/or RCP SI)

AP/1/A/1700/032 (Loss of Letdown)

Page2of33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: I Page 2 of 2 Event

Description:

PZR RTD A Fails LOW (I: OATC, SRO) (TS)

Time Position ApplicanVs Actions or Behavior Crew Response:

Refer to ARG I SA-02/C-3 (RC Pressurizer Level High/Low):

3.4 Refer to Technical Specification 3.4.9, Pressurizer 3.5 Refer to Technical Specification 3.3.8, PAM Instrumentation.

Condition A applies 3.6 Refer to OP/i/Ni 105/014 (Control Room Instrumentation Operation And Information)

OP/i/NI 105/014 Enclosure 4.11 (SASS Information) 3.2 SASS (Smart Automatic Signal Selector) Manual Operation 3.2.1 IF MISMATCH light is on and TRIP A or TRIP B light is on, a SASS trip has occurred.

A. Controlling signal will be selected from CR keyswitch (for parameters in ICS Cabinet #8).

B. Select valid signal as controlling signal by positioning CR keyswitch or pushbutton for Pzr level to valid signal (for parameters in ICS Cabinet #8).

3.2.2 IF MISMATCH light is on, a mismatch has occurred A. Controlling signal will be signal selected from CR keyswitch (for parameters in ICS Cabinet #8).

B. Select valid signal as controlling signal by positioning CR keyswitch or pushbutton for Pzr level to valid signal (Select Pzr Level #3) 3.2.3 Initiate a Work Request to repair faulty signal Note: The SRO may direct an RO to select Pzr Level #3 prior to referencing OPII tAll 1051014 Note: If the SRO has not addressed the TS for this event, continue to next event and ask the TS as a follow up question.

SRO The SRO should enter TS 3.3.8 Condition A for one or more Functions with one required channel inoperable (two channels of PZR level are required)

The Required Action is to restore the required channel to operable status within 30 days If the level in the Pzr reaches 260 inches, the SRO should enter TS 3.4.9 Condition A. Restore level to within limit within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

This event is complete when PZR level 3 is selected, or as directed by the Lead Examiner.

Page3of33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 2 Page 1 of 2 Event

Description:

Condenser Vacuum Leak (C: BOP, SRO)

Time Position

[ Applicants Actions or Behavior Plant Response:

1SA-03/A-6 (COND VACUUM LOW)

OAC alarm, Main Condenser Vacuum LOW Crew response:

BOP Refer to Alarm Response Guide 1 SA-031A-6

1. Alarm setpoint

25 Hg vacuum decreasing

2. Automatic Action

None; however, Main Turbine trip setpoint is 21.75 Hg and FDWPT trip setpoint is 19 Hg

3. Manual Action

Refer to API1IAJ1700IO27 (Loss of Condenser Vacuum)

Note: For this scenario, condenser vacuum will not be allowed to decrease below 22 Hg. Once ISA-031A-6 alarms, the condenser vacuum leak rate will be decreased to ensure the turbine will not trip.

Booth Cue: When the low vacuum statalarm actuates, FIRE TIMER 14 to reduce the leak size.

Booth Cue: When directed to isolate the vacuum leak, FIRE TIMER 15 to remove the vacuum leak.

Refer to AP111N17001027 (Loss of Condenser Vacuum)

SRO 1. Entry Conditions

Decreasing condenser vacuum as indicated by low condenser vacuum alarms 4.1 Announce AP entry using the PA system 4.2 1AAT both of the following apply:

Condenser vacuum 22 Hg MODE 1 or2 THENtriptheRx.

Page4of33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 2 Page 2 of 2 Event

Description:

Condenser Vacuum Leak (C: BOP, SRO)

Time Position Applicants Actions or Behavior Crew response:

SRO AP111A117001027 (Loss of Condenser Vacuum) 4.3 Dispatch operators to perform the following:

Perform End 5.1 (Main Vacuum Pump Alignment) (PS)

Look for vacuum leaks Booth Cue: Using TIME COMPRESSION, call the Control Room to notit the operator that the Main Vacuum Pumps are aligned and Enclosure 5.1 is complete.

4.4 Ensure aW available Main Vacuum Pumps operating (A, B, & C) 4.5 Ensure 1V-186 is closed 4.6 Ensure Stm to Stm Air Eject A, B, C> 255 psig 4.7 Verify Stm Seal Hdr Press> 1.5 psig 4.8 Ensure all available CCW pumps operating Booth Cue: Call Control Room as the NEO sent out to look for vacuum leaks and report that a leak was found on a Hotwell sight glass.

The leak will be removed after the control room directs the NEO to isolate the sight glass.

4.9 Verify Condensate flow 2300 gpm 4.10 WHEN condenser vacuum is stable, AND End 5.1 (Main Vacuum Pump Alignment) is complete, THEN EXIT this procedure Note: The crew may request an R&R for configuration control of the valves manipulated to stop the vacuum leak.

This event is complete when the SRO reaches Step 4.10 of APl27, or as directed by the Lead Examiner.

Page5of33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 3 Page 1 of 3 Event

Description:

lB Main FDW Pump Active Thrust Bearing Temperature HIGH Requiring Manual Trip (C: BOP, SRO)

Time Position Applicants Actions or Behavior Plant response:

OAC Alarm 01A0928 FWPT lB ACTIVE THRUST BEARING TEMP Crew Response:

Refer to OAC Alarm Response for 01A0928 for HI-HI temperature> 200°F HI-HI: 1) If temperature cannot be maintained below HI-HI setpoint, refer to OP/i IA/i 106/002 B (FDWPT Operation) to remove FDWP from service

2) Refer to OP/i/Ni 102/004 (Operation at Power)

3) Notify Component Engineer Booth cue: If contacted, respond as the Component Engineer and recommend that the lB FDWPT be removed from service as soon as possible.

Booth cue: If contacted, respond as the OSM and recommend that the lB FDWPT be removed from service as soon as possible Booth cue: If a NEO is dispatched, he should report that the lB FDWP SRO smells hot and the bearing housing is hot to the touch.

The BOP should refer to OPI1/N1106/002 B (FDWPT Operation)

The SRO will refer to AP/iIAIi700I029 (Rapid Unit Shutdown) (see next page)

BOP OP/i/Ni 106/002 B (FDWPT Operation) Enclosure 4.9 Initial Conditions 1.1 CTP DEMAND <65% power 1.2 Review Limits and Precautions Procedure 2.1 IF this is first FDWPT to be shutdown:

2.i.1 Verify 1SA-5/E-i (FWPT/RX TRIP ALERT) NOT in alarm 2.i.2 Position the following:

A. Ensure 1 FDW-53 (iA FDWP RECIRC CONTROL) in MAN B. Ensure Closed iFDW-53 (iA FDWP RECIRC CONTROL)

C. Ensure 1FDW-65 (lB FDWP RECIRC CONTROL) in MAN D. Ensure Closed iFDW-65 (lB FDWP RECIRC CONTROL) 2.2 IF in FDW Heatup, perform the following: (does not apply) 2.3 Ensure running 1 B FDWP AUX OIL PUMP 2.4 IF iA FDWP is NOT isolated for maintenance, start 1A FDWP AUX OIL PUMP 2.5 Place lB MAIN FDW PUMP (ICS) in HAND 2.6 Slowly run i B MAIN FDW PUMP demand signal to minimum Page 6of33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 3 Page 2 of 3 Event

Description:

lB Main FDW Pump Active Thrust Bearing Temperature HIGH Requiring Manual Trip (C: BOP, SRO)

Time Position Applicants Actions or Behavior Crew Response:

BOP OP/I/NI 106/002 B (FDWPT Operation) continued 2.7 IF required, verify 1A FDWPT picks up load by observing FDWPT suction flow instruments 2.8 Immediately trip 18 FDWPT from FW TURB 1 B TRIP/RESET switch

Verify closed I B FDWPT HP stop valve

Verify closed 1 B FDWPT LP stop valve 2.9 WHEN 1 B FDWPT reaches 0 speed:

Ensure lB FDWP TURNING GEAR MOTOR starts

Ensure 1 B FDWP TURNING GEAR engages 2.10 Open the following:

1SD-125 (18 FDWPT LPSV BS Stm Trap Byp) (T-l-C25)

1SD-I26 (lB FDWPT HPSV BS Stm Trap Byp) (T-1-D25) 2.11 Place I B FDWP Runback Bypass switch to BYPASS (T-I Located on SG FDW Panel 1 SGFP)

Booth Cue: When contacted, respond as a NEO and state that ISD-125 and ISD-126 are OPEN.

Booth Cue: When contacted, respond as a NEO and state that the lB FDWP Runback Bypass switch is in BYPASS.

2.12 IF both FDWPTs are tripped, close 1AS-97 (does not apply)

SRO AP/1/N1700/029 (Rapid Unit Shutdown) 4.1 Initiate End 5.1 (Support Actions During Rapid Unit Shutdown)

(see next page) 4.2 Announce AP entry using the PA system 4.3 IAAT both of the following apply:

It is desired to stop power decrease CTP> 18%

THEN perform Steps 4.4 4.7 RNO: GO TO Step 4.8 Note: Steps 4.4-4.7 will apply once Rx power has been reduced to < 65%

4.4 Verify ICS in AUTO 4.5 Deselect MAXIMUM RUNBACK 4.6 Initiate OP/i/NI 102/004 (Operation at Power) power reduction End 4.7 WHEN conditions permit, THEN perform one of the following:

Depress MAXIMUM RUNBACK to resume power reduction GO TO appropriate operating procedure for continued operation Page 7 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 3 Page 3 of 3 Event

Description:

lB Main FDW Pump Active Thrust Bearing Temperature HIGH Requiring Manual Trip (C: BOP, SRO)

Time Position Applicants Actions or Behavior Crew Response:

SRO AP/I/A11700/029 (Rapid Unit Shutdown) 4.8 Verify lOS in AUTO 4.9 Depress MAXIMUM RUNBACK 4.10 Verify both Main FDW pumps running 4.11 Adjust bias for first Main FDW pump desired to be shutdown until suction flow is 1 x 106 Ibm/hr less than remaining Main FDW pump suction flow 4.12 WHEN core thermal power is <65%, THEN continue BOP AP/1/AJ1700/029 Enclosure 5.1 (Support Actions During Rapid Unit Shutdown)

I. Notify WCC SRO to initiate End 5.2 (WCC SRO Support During Rapid Unit Shutdown)

2. Start the following pumps:

IA FDWP SEAL INJECTION PUMP 1A FDWP AUXILIARY OIL PUMP lB FDWP AUXILIARY OIL PUMP lB FDWP SEAL INJECTION PUMP

3. WHEN CTP is 80%, THEN continue

4. Stop 1E1 HTR DRN PUMP

5. Place 1HD-254 switch to OPEN

6. Stop 1E2 HTR DRN PUMP

7. Place 1HD-276 switch to OPEN

8. Verify Turbine-Generator shutdown is required RNO: GO TO Step 20

20. IAAT 1SSH-9 is NOT closed, AND CTP is 75%, THEN throttle 1SSH-9 to maintain Steam Seal Header pressure 2.5 4.5 psig

21. WHEN CTP 65%, THEN place the following in MANUAL and close:

1FDW-53 and IFDW-65

22. IAAT load is 550 MWe, THEN perform Steps 23 24 RNO: GO TO Step 25

23. Ensure 1A and lB MSRH DRN PUMPs are stopped

24. Place I HD-37 and 1 HD-52 in DUMP

25. WHEN CTP is 60%, THEN ensure 1SSH-9 is closed This event is complete when I B Main FDW Pump has been secured, or as directed by the Lead Examiner.

Page8of33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 4 Page 1 of 5 Event

Description:

Inadvertent ES Channel I Actuation (C: OATC, BOP, SRO) (TS)

Time Position ApplicanVs Actions or Behavior Plant response:

iSA-i/A-b ES 1 Trip 1SA-16/B-1 EL CT-4 SB Bus 1 Breaker Closed 2SA-17/A-5 KEOWEE STATALARM PANEL ALARM 2SA-17/C-1 KHU 1 EMERGENCY START INITIATED 2SA-18/C-1 KHU 2 EMERGENCY START INITIATED I SA-6/A-5, B-5, C-5, D-5, RC Pump Seal Cavity Press Hi/Low ( I mm later) 1SA-6/D-7, E-5, E-6, E-7 RC Pump Seal Return Temp High Both Keowee Hydro Units Emergency Start Over time, Reactor power will begin to slowly decrease due to BWST water injecting into the core. This affect will vary depending on crew response (how quickly 1HP-24 is closed).

The SRO may enter TS 3.4.9 if PZR level increases to > 260 Crew Response:

SRO The 5RO will initiate AP/l/AJ1700/042 Inadvertent ES Actuation 4.1 Verify jy of the following have inadvertently actuated:

Diverse HPI (not actuated)

ES Channel 1 ES Channel 2 (not actuated) 4.2 Perform the following on a inadvertently actuated system(s):

Ensure DIVERSE HPI BYPASS is in BYPASS (does not apply)

Ensure ES CH-1 is in MANUAL Ensure ES CH-2 is in MANUAL (does not apply) 4.3 Throttle HPI, as required, to maintain desired Pzr level 4.4 Verify y of the following have inadvertently actuated:

ES Channel 5 (not actuated)

ES Channel 6 (not actuated)

RNO: I. IF ES Channel 1, ES Channel 2, or Diverse HPI have inadvertently actuated, AND it is desired to restore letdown, THEN initiate AP/42 End 5.2 (Letdown Restoration) (see page 12)

2. GOTOStep4.b0 4.10 Close 1HP-24 and 1HP-25 4.11 Ensure AP/42 End 5.1 (Required Operator Actions) is in progress (see page 11)

Page9of33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Page 2 of 5 Event

Description:

Inadvertent ES Channel I Actuation (C: OATC, BOP, SRO) (TS)

Time Position

[ Applicants Actions or Behavior Crew Response:

AP111A117001042 Inadvertent ES Actuation 4.12 Verify y of the following have inadvertently actuated:

Diverse LPI ES Channel 3 ES Channel 4 RNO: GOTOStep4.17 4.17 Verify the Rx is critical 4.18 Verify ICS in Auto 4.19 Verify control rods are outside the desired control band RNO: GO TO Step 4.21 4.21 Verify jy of the following have inadvertently actuated:

ES Channel 1 Diverse HPI 4.22 Perform the following on all inadvertently actuated system(s):

Ensure DIVERSE HPI BYPASS is in BYPASSED (does not apply)

Ensure ES ELECTRICAL 1 is in MANUAL 4.23 Dispatch an operator to perform End 5.3 (SSF Restoration) 4.24 Notify SPOC to investigate and repair the cause of the inadvertent ES actuation, as necessary 4.25 Initiate logging TS/SLC Entry/Exit, as applicable, in accordance with End 5.4 (TS/SLC Requirements) (See page 12 for detailed information) 4.26 WHEN all of the following exist:

Reason for inadvertent ES Channel or Diverse HPI/LPI actuation has need resolved ES Channel or Diverse HPI/LPI reset is desired OSM concurs THEN continue The SRO refers to TS 3.3.7 and enters Condition A for one inoperable digital automatic actuation logic channel inoperable APPLICABILITY: MODES I and 2 CONDITION A: One or more digital automatic actuation logic channel inoperable REQUIRED ACTION: Place associated component(s) in ES configuration OR Declare the associated component(s) inoperable COMPLETION TIME: 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Page 10 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 4 Page 3 of 5 Event

Description:

Inadvertent ES Channel I Actuation (C: OATC, BOP, SRO) (TS)

Time Position ApplicanVs Actions or Behavior Crew Response:

OATC/BOP AP111A117001042 Enclosure 5.1 Required Operator Actions I Initiate announcement of AP entry using the PA system 2 Verify y of the following have inadvertently actuated:

Diverse HPI ES Channel 1 ES Channel 2 3 Open the following:

1 HP-20 1 HP-21 4 Open the following for operating RCPs:

1HP-228 (IA1) 1HP-226 (1A2) 1HP-232 (IBI) 1HP-230 (1B2) 5 Verify y of the following have inadvertently actuated:

ES Channel 7 ES Channel 8 RNO: GOTOStep9 9 Perform the following:

A. Open the following to restore RB RIAs:

1PR-7 1PR-8 1PR-9 1PR-10 B. From the ENABLE CONTROLS screen on the RIA View Node, perform the following:

1. Select OFF for RB RIA sample pump

2. Start the RB RIA sample pump

10. Verify y of the following have inadvertently actuated:

Diverse HPI ES Channel 1

11. Notify the following that the SSF is inoperable due to the SSF power loss

. Unit 2, Unit3, and Security

12. EXIT this enclosure Page 11 of33

Appendix D Scenario Outline Form ES-D-2 Op-TestNo.: I Scenar[o No.: 3 Event No: 4 Rage 4 &f5 Event

Description:

Inadvertent ES Channel I Actuation (C: OATC, BOP, SRO) (TS)

Time Position Applicants Actions or Behavior Crew Response:

SRO AP/1 INI 700/042 Enclosure 5.4 (TS/SLC Requirements)

Any ES Channel

TS 3.3.7 (Engineered Safeguards Protective System (ESPS) Digital Automatic Actuation Logic Channels) due to the automatic actuation logic being blocked if any ES channel is in MANUAL or ES Voters in OVERRIDE (DOES APPLY) Condition A. I hour completion time.

TS 3.3.5 (Engineered Safeguards Protective System (ESPS) Analog Instrumentation) due to inoperable ES instrumentation (DOES NOT APPLY)

TS 3.5.4 (Borated Water Storage Tank (BWST)) BWST level (DOES NOT APPLY)

ES Channel I or 2

TS 3.4.15 (RCS Leakage Detection Instrumentation) due to Rx Bldg RIAs being out of service (Applies until RIAs are returned to service.)

TS 3.10.1 (Standby Shutdown Facility(SSF)) for SSF inoperability due to the SSF power loss (ES Channel I only) (APPLIES)

TS 3.4.9 (Pressurizer) if PZR level is > 260 (Applies if Pzr exceeds 260.)

ES Channel 3 or 4

TS 3.7.7 (Low Pressure Service Water (LPSW) System) if LPSW leakage accumulator level is outside allowable band. Evaluate OAC point 01E0507 (LPSW LEAKAGE ACCUMULATOR LEVEL). Notify Unit 2 to evaluate OAC point 02E0507 (LPSW LEAKAGE ACCUMULATOR LEVEL). (DOES NOT APPLY)

Any Diverse Actuation System

SLC 16.7.6 (Diverse Actuation Systems) due to the automatic actuation logic being blocked if any Diverse Actuation system in OVERRIDE or BYPASS.

(DOES NOT APPLY)

Page 12 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 4 Page 5 of 5 Event

Description:

Inadvertent ES Channel I Actuation (C: OATC, BOP, SRO) (TS)

Time Position Applicants Actions or Behavior Crew Response:

OATC/BOP AP111A117001042 Enclosure 5.2 Letdown Restoration 1 Verify a CC pump operating 2 Verify letdown is isolated 3 Close I HP-5

4. Verify it is desired to place both letdown coolers in service

5. Open the following:

1HP-1 1 HP-2 1 HP-3 1 HP-4

6. Close 1HP-6

7. Close 1HP-7

8. Verify letdown temperature < 135°F

9. Open 1 HP-S

10. Adjust 1HP-7 for 20 gpm letdown

11. WHEN letdown temperature <130°F, THEN place LETDOWN HI TEMP INTLK BYP switch in NORMAL

12. Open 1HP-6

13. Adjust 1 HP-7 to control desired letdown flow

14. IAAT it is desired to bleed letdown flow to 1A BHUT, THEN perform the following:

A. Open the following:

1 CS-26 1CS-41 B. Position 1HP-14 to BLEED C. Notify SRO

15. IAAT letdown bleed is NO longer desired, THEN position 1HP-14 to NORMAL

16. WHEN SRO approves, THEN EXIT this enclosure This event is complete when the SRO reaches WHEN step 4.26 and has referred to TS, or as directed by the Lead Examiner.

Page 13 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: Event No.: 5 Page 1 of 2 Event

Description:

Controlling Tave Fails HIGH (I: OATC, SRO)

Time Position Applicants Actions or Behavior Plant Response:

1 SA-021A-1 2 (ICS Tracking) will actuate due to neutron and feedwater cross-limits.

Controlling Tave will indicate 596.2°F.

Actual Loop A & B Tave will decrease until operator stops transient.

RCS pressure and temperature will decrease.

Rx power will initially increase and an ICS FDWPT Runback may occur due to RCS temperature decrease Crew Response:

When the Statalarms are received, the candidates should utilize the Plant Transient Response (PTR) process to stabilize the plant.

OATC reports to the SRO reactor power level and direction of movement.

Place the Diamond and both FDW Masters in manual and position as necessary to stabilize the plant.

The SRO should:

> Refer to AP/28 (ICS Instrument Failures)

If the crew initiates EOP enclosure 5.5 for inventory control, the actions are listed beginning on page 28 Note: The ICS will remain in manual for the remainder of the scenario.

Note: The crew may manually trip the Reactor if the failure is not immediately recognized due to the power increase. If the crew trips the Reactor, continue with the next event.

SRO Refer to AP/11A117001028 (lCS Instrument Failures) 4.1 Provide control bands as required (per OMP 1-18 Attachment I)

NI Power +/- 1% not to exceed the pre-transient or allowable power

Current Tave +/- 2°F

Current SG Outlet Pressure +/- 10 PSIG

Delta T 0°F +/- 2°F 4.2 Initiate notification of the following:

OSM to reference the following:

OMP 1-14 (Notifications)

Emergency Plan STA Page 14 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 5 Page 2 of 2 Event

Description:

Controlling Tave Fails HIGH (I: OATC, SRO)

Time Position Applicants Actions or Behavior Crew Response:

SRO AP/11A117001028 (ICS Instrument Failures) 4.3 Verify a power transient 5% has occurred.

RNO: GO TO Step 4.5 Note: Step 4.3 will be performed based on whether a power transient 5% has or has not occurred.

4.4 Notify Rx Engineering and discuss the need for a maneuvering plan.

4.5 Use the following, as necessary, to determine the applicable section from table in Step 4.6:

OAC alarm video

OAC display points

Control Board indications

SPOC assistance, as needed 4.6 GO TO the applicable section per the following table:

Section Failure 4A RCS Temperature SRO API1/A117001028 Section 4A (RCS Temperature Failure)

1. Ensure the following in HAND:

1A FDW MASTER lB FDW MASTER

2. Ensure DIAMOND in MANUAL.

3. Notify SPOC to perform the following:

Select a valid RCS Tave and Delta T 0 input to ICS per AM/0/B/0326/020 (Control of Star Module Signal Selection Function)

Investigate and repair the failed RCS temperature instrumentation

4. PERFORM an instrumentation surveillance using applicable table in End 5.2 (ICS Instrument Surveillances) for the failed instrument

5. Verify instrumentation surveillance in End 5.2 (ICS Instrument Surveillances) was performed satisfactorily as written

6. WHEN notified by SPOC that a valid RCS Tave and Delta Tc input have been restored to ICS, THEN GO TO OP/I/All 102/004 A End (Placing ICS Stations To AUTO)

Note: The Controlling Tave failure will not be repaired for this scenario.

This event is complete when the SRO reaches the WHEN step (6) in Section 4A, or as directed by the Lead Examiner.

Page 15 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 6 Page 1 of 9 Event

Description:

IA Main Steam Line Break in RB (M: ALL)

HPI Pump Fails to start on ES Time_[ Position Applicants Actions or Behavior Plant response:

iSA-i/A-i, B-i, C-i, D-1, RP Channel Trip

1 SA-2/D-3, RC Press High/Low

Statalarm 1SA-02/A-9 (MS PRESS HIGH/LOW)

The iC HPI pump will fail to start on ES Channel 2 actuation

ES Channels 1-8 will actuate Crew response:

SRO SRO will enter the EOP by directing the OATC to perform Immediate Manual Actions (or IMAs).

OATC OATC will perform Immediate Manual Actions

> Depress REACTOR TRIP pushbutton

> Verify reactor power < 5% FP and decreasing

> Depress turbine TRIP pushbutton.

> Verify all turbine stop valves closed

> Verify RCP seal injection available BOP BOP will perform a Symptoms Check (per OMP 1-18 Attachment C)

Reactivity Control o Power Range NIs <5% and decreasing

ICC/Loss of Subcooling Margin (SCM) o If any SCM 0°F, perform Rule 2

Loss of Heat Transfer (LOHT) o Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW)

Excessive Heat Transfer (EHT) o Uncontrolled Main Steam Line(s) pressure decrease

Steam Generator Tube Rupture o CSAE off-gas alarms, process RIAs (RIA-40, 59, 60), area RIAs (RIA 16/17)

BOP performs Rule #5 (Main Steam Line Break) after receiving concurrence from the SRO (detail begin on page 18)

SRO refers to Parallel Actions page of the Subsequent Actions Tab and transfers to the Excessive Heat Transfer Tab SRO will initiate EOP Enclosure 5.1 (ES Actuation) (details begin on page 21>

The SRO will direct Excessive Heat Transfer Tab actions (see next page)

The SRO will direct an RO to make a PA announcement and notify the OSM to reference the Emergency Plan and NSD-202 Page 16of33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 6 Page 2 of 9 Event

Description:

IA Main Steam Line Break in RB (M: ALL)

IC HPI Pump Fails to start on ES Time__j Position Applicants Actions or Behavior Crew Response:

SRO EOP Excessive Heat Transfer Tab (EHT)

1. Verify jjy SG pressure < 550 psig

2. Ensure Rule 5 (Main Steam Line Break) in progress or complete

3. Place the following in HAND and decrease demand to zero on all affected SGs:

1 FDW-32 and 1 FDW-35 (for 1A SG)

4. Close the following on ll affected SGs:

1FDW-372, 1MS-17, 1MS-79, 1MS-35, 1MS-82, 1MS-368

5. Verify level in both SGs <96% O.R.

6. IAAT core SCM is> 0°F, THEN perform Steps 7 and 8

7. Throttle HPI per Rule 6 (HPI) (CT-5)

Note: HPI flow must be throttled and RCS temperature controlled to prevent a solid Pzr and subsequent operation of the PORV.

8. Verify letdown in service RNO: IF desired to restore letdown, THEN initiate End 5.5 (Pzr and LDST Level Control) (see page 29)

9. Verify jy SG has an intact secondary boundary (intact SG)

10. Open the following on all intact SGs

1 FDW-382, 1 FDW-369, and 1 MS-26

11. Start MDEFDWP associated with aH intact SGs

IBMDEFDWP

12. Feed and steam all intact SGs to stabilize RCS P/T using either of the following:

Note: RCS temperature must be controlled, HPI throttled, and letdow

TBVs

Dispatch two operators to perform End 5.24 (Operation of the ADVs

13. GOTOStep32

32. Verify y of the following:

HPI has operated in the injection mode while NO RCPs were operating A cooldown below 400°F at> 100°F/hr has occurred RNO: GO TO Step 34

34. Verify 1 MS-24 and 1 MS-33 are closed

35. Open 1AS-8

36. Close ISSH-9 Page 17of33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 6 Page 3 of 9 Event

Description:

IA Main Steam Line Break in RB (M: ALL)

IC HPI Pump Fails to start on ES Time Position Applicants Actions or Behavior Crew Response:

SRO EOP Excessive Heat Transfer Tab

37. Perform the following notifications:

Notify Chemistry to determine RCS boron concentration

Notify Secondary Chemistry to check for indications of SGTR

Notify RP to check for indications of a SGTR

38. IAAT RCS boron is determined to be insufficient for adequate SDM, THEN initiate End 5.11 (RCS Boration)

39. IAAT a the following exist:

ES Bypass Permit satisfied

AHSCMs>O°F

RCS pressure controllable THEN bypass ES as necessary RNO: GO TO Step 41

41. VerifyySGisdry

42. Minimize SCM using the following methods as necessary:

De-energize all Pzr heaters Use Pzr spray

_Throttle HPI to maintain Pzr level> 100 [180 acc]

Use PORV Page 18 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 6 Page 4 of 9 Event

Description:

IA Main Steam Line Break in RB (M: ALL)

IC HPI Pump Fails to start on ES Time Position

[ Applicants Actions or Behavior Crew Response:

EOP Rule 5

1. Perform the following on affected headers:

Initiate AFIS 1A SG Digital Channels 1 and 2

Select OFF for 1A MDEFDW Pump (CT-17)

Note: Overcooling must be stopped prior to violating NDT limits.

Note: The critical task is to stop feeding the affected SG.

Trip both Main FDW pumps

Close 1FDW-315, 1FDW-33, and 1FDW-31

2. Verify 1 TD EFDW PUMP operating.

RNO: IF MD EFDWP for the intact SG is operating, THEN GO TO Step 5.

5. Verify 1 B SG is an affected SG.

RNO: GO TO Step 7

7. WHEN overcooling is stopped, THEN adjust steaming of unaffected SG to maintain CETCs constant using either of the following:

TBVs

Dispatch two operators to perform End 5.24 (Operation of ADVs)

8. WHEN afl of the following exist:

Core SCM >00 F

_RxPwr1%

Pzr Level increasing, THEN continue

9. Verify ES HPI actuated

10. Place Diverse HPI in BYPASS

11. Place ES CH 1 and ES CH 2 in MANUAL

12. Perform the following to stabilize RCS PIT:

Throttle HPI

Reduce 1 HP-i 20 setpoint to> 100 (180 ACC)

Adjust steaming of unaffected SG (1 B SG) to maintain CETCs constant

13. WHEN CETCs have stabilized, THEN resume use of T for RCS temperature control

14. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete (see next page)

15. Ensure Rule 8 (Pressurized Thermal Shock (PTS)) is in progress or complete

16. WHEN directed by CR SRO, THEN EXIT this rule Page 19 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 6 Page 5 of 9 Event

Description:

IA Main Steam Line Break in RB (M: ALL)

IC HPI Pump Fails to start on ES Time Position Applicants Actions or Behavior Crew Response:

EOP Rule 3

1. Verify loss of Main FDW/EFDW is due to Turbine Building Flooding RNO: GO TO Step 3

3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency),

AND y of the following exist:

RCS pressure reaches 2300 psig OR NDT limit

Pzr level reaches 375 [340 acc]

THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling)

4. Start operable EFDW pumps, as required, to feed all intact SGs

5. Verify y EFDW pump operating. (lB MD is operating to lB SG)

6. GO TO Step 37

37. IAAT an EFDW valve CANNOT control in AUTO OR manual operation if EFDW valve is desired to control flow/level, THEN perform Steps 38-42 RNO: GOTOstep43

43. Verify jy SCM 0°F RNO: IF overcooling or exceeding limits in Rule 7, THEN throttle EFDW as necessary.

44. IAAT Unit 1 EFDW is in operation, THEN initiate End 5.9 (Extended EFDW Operation) (see next page)

45. WHEN directed by CR SRO, THEN EXIT this rule Page 20 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 6 Page 6 of 9 Event

Description:

IA Main Steam Line Break in RB (M: ALL)

IC HPI Pump Fails to start on ES Time Position Applicants Actions or Behavior Crew Response:

EOP Enclosure 5.9 (Extended EFDW Operation)

1. Monitor EFDW parameters on EFW graphic display

2. IAAT UST level is <4, THEN GO TO Step 117

3. IAAT feeding both SGs with one MD EFDWP is desired, THEN perform Steps 4-7 RNO: GO TO Step 8

8. Perform the following as required to maintain UST level > 7.5 Makeup with demin water Place CST pumps in AUTO

9. IAAT Ji the following exist:

Rapid cooldown NOT in progress MD EFDWP operating for each available SG EFDW flow in each header < 600 gpm THEN place 1 TD EFDW PUMP switch in PULL TO LOCK 10 Verify 1 TD EFDW PUMP operating RNO: GOTOStep12 NOTE

Loss of the condensate system for 25 minutes results in cooling down to LPI using the ADVs. If NO HWPs are operating, continuing this enclosure to restore the condensate system is a priority unless the CR SRO deems EOP activities higher priority. The 25 minute criterion is satisfied when a HWP is started and iC-b is 10% open.

If the condensate system is operating, the remaining guidance establishes FDW recirc, monitors and maintains UST, and transfers EFDW suction to the hotwell if required.

12. Notify CR SRO to set priority based on the NOTE above EOP activities Note: The SRO should determine that restoring the secondary side of the plant is not a priority at this time and direct the RO to continue in Rule 3.

Page 21 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 6 Page 7 of 9 Event

Description:

IA Main Steam Line Break in RB (M: ALL)

IC HPI Pump Fails to start on ES

[__Time Position Applicants Actions or Behavior Crew Response:

OATC/BOP EOP Enclosure 5.1 (ES Actuation)

1. Determine aM ES channels that should have actuated based on RCS pressure and RB pressure.

RB 3 psig: Channels 1, 2, 3, 4, 5 & 6

RB 10 psig: Channels 7 & 8

2. Verify all ES digital channels associated with actuation setpoints have actuated.

RNO: Depress TRIP on affected ES logic channels that have NOT previously been actuated Note: The SRO may direct an RO to manually actuate ES Channel I which was previously placed in manual (place in AUTO)

3. IAAT additional ES actuation setpoints are exceeded, THEN perform Steps 1-2.

4. Place Diverse HPI in BYPASS

5. Place ES OH 1 and ES CH 2 in MANUAL

6. Verify Rule 2 in progress or complete.

RNO: GO TO Step 70

70. Open 1 HP-24 and 1 HP-25

71. Ensure at least two HPI pumps are operating

72. Verify 1 HP-26 and I HP-27 are open

73. IAAT at least two HPI pumps are operating, AND HPI flow in jy header that has NOT been intentionally throttled is in the Unacceptable Region of Figure 1, THEN open the following in the affected header:

J IA Header q lB Header 1HPLI41O 1HP-409 Note: IHP-409 may be opened to allow HPI flow in both headers due to the failure of the IC HPI pump. This will occur if Rule 5 has not intentionally throttled HPI when the RO reaches this step.

74. Verify y RCP operating

75. Open 1HP-20 and 1HP-21

76. IAAT aM exist:

Voter associated with ES channel is in OVERRIDE An ES channel is manually actuated Components on that channel required manipulation THEN depress RESET on the required channel Page 22 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: j_ Scenario No.: 3 Event No.: 6 Page 8 of 9 Event

Description:

IA Main Steam Line Break in RB (M: ALL)

IC HPI Pump Fails to start on ES Time Position Applicants Actions or Behavior Crew Response:

OATC/BOP EOP Enclosure 5.1 (ES Actuation)

77. IAAT y RCP is operating, AND ES Channels 5 and 6 actuate, THEN perform Steps 78-8 1

78. Place ES CH 5 and ES CH 6 in MANUAL

79. Open:

1CC-7 1CC-8 1LPSW-15 I LPSW-6

80. Ensure only one CC pump operating

81. Ensure Standby CC pump in AUTO

82. IAAT ES Channels 3 & 4 are actuated, THEN GO TO Step 83

83. Place Diverse LPI in BYPASS

84. Place ES CH 3 and ES CH 4 in MANUAL CAUTION LPI pump damage may occur if operated in excess of 30 minutes against shutoff head

85. IAAT y LPI pump is operating against shutoff head, THEN at the CR SROs discretion, stop affected LPI pumps

86. IAAT RCS pressure is < LPI pump shutoff head, THEN perform Steps 87-88 RNO: GO TO Step 89

89. IAAT IA and 1 B LPI PUMPs are off/tripped, AND all of the following exists RNO: GOTOStep92

92. IAAT 1A LPI PUMP fails while operating, AND lB LPI PUMP is operating, THEN close 1LP-17

93. IAAT lB LPI PUMP fails while operating, AND 1A LPI PUMP is operating, THEN close I LP-1 8

94. Start A and B OUTSIDE AIR BOOSTER FANS

95. Notify Unit 3 to start 3A and 3B OUTSIDE AIR BOOSTER FANS

96. Verify 1CF-1 and 1CF-2 are open

97. Verify 1HP-410 closed

98. Secure makeup to the LDST Page 23 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 6 Page 9 of 9 Event

Description:

IA Main Steam Line Break in RB (M: ALL)

IC HPI Pump Fails to start on ES Time__[ Position Applicants Actions or Behavior 1

Crew Response:

OATC/BOP EOP Enclosure 5.1 (ES Actuation)

99. Verify all ES channel 1-4 components are in the ES position RNO: 1. IF 1 HP-3 fails to close, THEN close 1 HP-i

2. IF 1HP-4 fails to close, THEN close 1HP-2

3. Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired Note: The IC HPI pump, IA& lB LPI pumps, IHP-26, IHP-20, and IHP 21 will not be in its ES position.

100. Verify Unit 2 turbine tripped RNO: GOTOStep 103 103. Close 1LPSW-139 104. Place 1LPSW-251 and 1LPSW-252 FAIL SWITCH in FAIL OPEN 105. Start all available LPSW pumps 106. Verify either:

Three LPSW pumps operating Two LPSW pumps operating when TS only requires two operable 107. Open I LPSW-4 and I LPSW-5 108. IAAT BWST level 19, THEN initiate End 5.12 (ECCS Suction Swap to RBES) 109. Dispatch an operator to perform End 5.2 (Placing RB Hydrogen Analyzers In Service) (PS) 110. Select DECAY HEAT LOW FLOW ALARM SELECT switch to ON ill. IAAT ES channels 5 & 6 have actuated, THEN perform Step 112 112. Verify all ES channel 5 & 6 components in the ES position RNO: Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired Note: I CC-7, I CC-8, I LPSW-6, and I LPSW-1 5 will not be in the ES position.

113. IAAT ES channels 7 & 8 have actuated, THEN perform Step 114 114. Verify all ES channel 7 & 8 components are in the ES position 115. Notify U2 CR SRO that SSF is inoperable due to OTS1-1 open 116. IAAT conditions causing ES actuation have cleared, THEN initiate End 5.41 (ES Recovery) 117. WHEN CR SRO approves, THEN EXIT this enclosure This event is complete when the SRO reaches Step 32 of the Excessive Heat Transfer tab of the EOP, or as directed by the Lead Examiner.

Page 24 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 7 Page 1 of 4 Event

Description:

Loss of all SG feed requiring HPI FIC (M: ALL)

Time Position Applicants Actions or Behavior Plant Response:

EFDW flow goes to zero and level in the 1 B SG begins to decrease RCS pressure and temperature will begin to increase Crew Response:

The SRO may direct an RO to perform a Symptoms Check An RO may attempt to start the TD EFDW pump during a Symptoms Check The SRO will direct an RO to re-perform Rule 3 (see page 27)

The SRO will transfer to the Loss of Heat Transfer tab from the Excessive Heat Transfer tab Parallel Actions Page When RCS pressure increases to> 2300 psig, the SRO will direct an RO to perform Rule 4 (HPI Forced Cooling) (see page 26)

The SRO will declare Emergency Dose Limits once HPI Forced Cooling is initiated SRO EQP Loss of Heat Transfer tab

1. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete

2. IAAT the RCS heats to the point where core SCM = 0°F, THEN GO TO Step 4

3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency),

AND jy of the following exists:

RCS pressure reaches 2300 psig OR NDT limit Pzr level reaches 375 [340 acc]

THEN GO TO Step 4 RNO 1. Reduce RCPs to one pump/loop

2. When any of the following exits:

EFDW flow has been re-established by existing Rules/Enclosures

EFDW aligned from another unit

Operator performing Rule 3 or End 5.27 reports EFDW available THEN GO TO Step 48

4. PERFORM Rule 4 (Initiation of HPI Forced Cooling)

5. Verify the following:

At least two HPI pumps operating Acceptable HPI flow exists in both HPI headers per Rule 4 PORV open 1RC-4 open

6. GO TO HPI CD tab This event is complete when the SRO transfers to the HPI CD tab of the EOP, or as directed by the Lead Examiner.

Page 25 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 7 Page 2 of 4 Event

Description:

Loss of all SG feed requiring HPI F/C (M: ALL)

Time Position [ Applicants Actions or Behavior Crew Response:

SRO EOPHPICDtab

1. IAAT BWST level is 19, THEN initiate End 5.12 (ECCS Suction Swap to RBES)

2. IAAT either of the following exists:

LPI FLOW TRAIN A pj LPI FLOW TRAIN B 3400 gpm Only one LPI header in operation with header flow 2900 gpm THEN GO TO LOCA CD tab

3. Verify all of the following exists:

_PORV open 1 RC-4 open Two HPI trains injecting CETCs 640° F

4. Perform the following:

Ensure all RBCUs in low speed Open 1 LPSW-1 8

_Open 1LPSW-21 Open 1 LPSW-24

5. Initiate End 5.35 (Containment Isolation)

6. IAAT aB the following exist:

y RBS pump operating RB pressure <3 psig

<24 hours into event Reactor Engineering confirms Condition Zero Condition One per RP/0/B/1000/018 (Core Damage Assessment)

THEN stop aM RBS pumps

7. Start A and B Outside Air Booster Fans

8. Notify Unit 3 to start 3A and 3B Outside Air Booster Fans

9. Verify 1 SA-2/C-8 (AFIS HEADER A INITIATED) lit

10. Verify 1SA-2/D-8 (AFIS HEADER B INITIATED) lit RNO: Select OFF for both digital channels on AFIS HEADER B

11. Verify indications of SGTR 25 gpm RNO: GOTOStepl7 Page 26 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 7 Page 3 of 4 Event

Description:

Loss of all SG feed requiring HPI FIC (M: ALL)

Time Position Applicants Actions or Behavior Crew Response:

EOP Rule 4 (Initiation of HPI Forced Cooling)

1. Verify jy HPI pump can be operated

2. Open 1 HP-24 and 1 HP-25

3. Start aM available HPI pumps

4. Open 1HP-26 and 1HP-27

5. Open IRC-4

6. Verify flow exists in y HPI header

7. Perform the following:

Place 1RC-66 SETPOINT SELECTOR to OPEN Depress 1 RC-66 OPEN PERMIT pushbutton

8. Verify at least two HPI pumps operating

9. Verify flow in both HPI headers is in the acceptable region of Figure 1 RNO: 1. IF 1A HPI header flow is unacceptable, THEN open 1HP-410

2. IF 1 B HPI header flow is unacceptable, THEN open 1 HP-409 Note: IHP-409 may have been previously opened per EOP End 5.1 due to the failure of the IC HPI pump.

10. Verify flow exists in jy HPI header

11. Perform the following:

Place I RC-66 SETPOINT SELECTOR to OPEN Depress 1 RC-66 OPEN PERMIT pushbutton

12. Verify> one RCP operating

13. Stop all but one RCP

14. IAAT the following limits are exceeded, Pump Operation Limit 1 HPI pump/hdr 475 gpm (md. seal injection for A hdr) 1A & 1 B HPI Total flow of 950 gpm pumps operating (md. seal injection) with 1 HP-409 open THEN throttle HPI to maximize flow flow limit

15. De-energize fl Pzr heaters

16. Close 1 HP-5

17. Close TBVs, 1 FDW-35, and 1 FDW-44 This event is complete when the SRO transfers to the HPI CD tab of the EOP, or as directed by the Lead Examiner.

Page 27 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 7 Page 4 of 4 Event

Description:

Loss of all SG feed requiring HPI FIC (M: ALL)

Time Position [ Applicants Actions or Behavior Crew Response:

EOP Rule 3 (Loss of Main or Emergency FDW)

1. Verify loss of Main FDW/EFDW is due to Turbine Building Flooding RNO: GOTOStep3

3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency),

AND jjy of the following exist:

RCS pressure reaches 2300 psig OR NDT limit

Pzr level reaches 375 [340 acc]

THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling)

4. Start operable EFDW pumps, as required, to feed all intact SGs

5. Verify jy EFDW pump operating. (18 MD is operating to 18 SG)

RNO: GO TO Step 7

7. Place the following in MANUAL and close:

1FDW-315 and 1FDW-316

8. Verify th of the following:

y CBP operating TBVs available on an intact SG RNO: GOTOStepl6

16. Verify 1 TD EFDW PUMP is operable and available for manual start

17. Dispatch an operator to perform End 5.26 (MAN Start of TDEFDWP)

18. Verify cross-tie with Unit 2 is desired RNO: 1. Dispatch an operator to open 1FDW-313 and 1FDW-314

2. GOTOStep2O

19. Dispatch an operator to open 2FDW-313 and 2FDW-314

20. Dispatch an operator to 1 FDW-31 3 and have them notify the CR when in position

21. Notify alternate unit to perform the following:

Place both EFDW control valves in manual and closed Start their TD EFDW PUMP

22. WHEN either of the follow exists:

Operator is in position at I FDW-31 3 Unit 1 TD EFDW PUMP has been manually started THEN continue Note: RCS pressure will increase to > 2300 psig and Rule 3 will be suspended while HPI Forced Cooling is aligned.

This event is complete when the SRO transfers to the HPI CD tab of the EOP, or as directed by the Lead Examiner.

Page 28 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 6 Page 1 of 3 Event

Description:

EOP Enclosure 5.5 (Pzr and LDST Level Control) if needed Time Position Applicants Actions or Behavior Crew Response:

OATC/BOP EOP Enclosure 5.5, Pzr and LDST Level Control

1. Utilize the following as necessary to maintain desired Pzr level:

lAHPlPump

lBHPlPump

1HP-26

1HP-7

1 HP-120 setpoint or valve demand

1HP-5

2. IAAT makeup to the LDST is desired, THEN makeup from 1A BHUT.

3. IAAT it is desired to secure makeup to LDST, THEN secure makeup from 1A BHUT.

4. IAAT it is desired to bleed letdown flow to 1A BHUT, THEN perform the following:

A. Open:

1CS-26

1CS-41 B. Position 1HP-14 to BLEED.

C. Notify SRO.

5. IAAT letdown bleed is NO longer desired, THEN position 1HP-14 to NORMAL.

6. IAAT IC HPI PUMP is required, THEN perform Steps 7 9.

RNO: GOTOStepI0.

10. IAAT LDST vel CANNOT be maintained, THEN perform Step 11.

RNO: GOTOStepl2.

11. Perform the following:

Open 1HP-24

Open 1HP-25

Close 1HP-16

12. IAAT additional makeup flow to LDST is desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close 1CS-48 (1A BHUT Recirc) (A-I -1 07, Unit 1 RC Bleed Transfer Pump Rm.).

13. IAAT two Letdown Filters are desired, THEN perform the following:

Open 1HP-17.

Open IHP-18 Page 29 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 6 Page 2 of 3 Event

Description:

EOP Enclosure 5.5 (Pzr and LDST Level Control) if needed Time Position

[ Applicants Actions or Behavior Crew Response:

OATC/BOP EOP Enclosure 5.5, Pzr and LDST Level Control

14. IAAT of the following exist:

Letdown isolated

LPSW available

Letdown restoration desired THEN perform Steps 15 33 -

RNO: GO TO Step 34

15. Open 1CC-7 and 1CC-8

16. Ensure only one CC pump running

17. Place the non-running CC pump in AUTO

18. Verify IHP-1 and 1HP-2 are open

19. GOTOStep22

22. Monitor for unexpected conditions while restoring letdown

23. Verify both letdown coolers to be placed in service

24. Open 1HP-1, 1HP-2, 1HP-3, and 1HP-4

25. Verify at least one letdown cooler is aligned

26. Close 1 HP-6

27. Close 1 HP-7

28. Verify letdown temperature < 135°F RNO: 1. Open 1HP-13

2. Close 1 HP-8 and 1 HP-9&1 1

3. IF y deborating IX is in service, THEN perform the following:

Select 1 HP-14 to NORMAL

_Close 1HP-16

4. Select LETDOWN HI TEMP INTLK BYP switch to BYPASS

29. Open 1HP-5

30. Adjust 1 HP-7 for 20 gpm letdown

31. WHEN letdown temperature is < 130°F, THEN place LETDOWN HI TEMP INTLK BYP switch to NORMAL

32. Open 1HP-6

33. Adjust 1 HP-7 to control desired letdown flow

34. IAAT it is determined that letdown is unavailable due to equipment failures or letdown system leakage, THEN notify CR SRO to initiate AP/32 (Loss of Letdown).

Page 30 of 33

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 3 Event No.: 6 Page 3 of 3 Event

Description:

EOP Enclosure 5.5 (Pzr and LDST Level Control) if needed Time Position j Applicants Actions or Behavior Crew Response:

OATC/BOP EOP Enclosure 5.5, Pzr and LDST Level Control

35. IAAT> 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:

A. Obtain SRO concurrence to reduce running HPI pumps.

B. Secure the desired HPI pumps.

C. Place secured HPI pump switch in AUTO, if desired.

36. IAAT fl the following conditions exist:

Makeup from BWST NOT required

LDST level > 55

AU control rods inserted

Cooldown Plateau NOT being used THEN close:

1HP-24

1HP-25

37. Verify 1CS-48 (1A BHUT Recirc) has been closed to provide additional makeup flow to LDST.

RNO: GOTOStep39

38. WHEN ICS-48 is NO longer needed to provide additional makeup flow to LDST, THEN perform the following:

A. Stop IA BLEED TRANSFER PUMP B. Locally position 1 CS-48 one turn open C. Close 1 CS-46 D. Start IA BLEED TRANSFER PUMP E. Locally throttle 1 CS-48 to obtain 90-1 10 psig discharge pressure F. Stop 1A BLEED TRANSFER PUMP

39. Verify two Letdown Filters in service, AND only one Letdown filter is desired RNO: GO TO Step 41

41. WHEN directed by CR SRO, THEN EXIT this enclosure These steps will be completed as directed by the SRO for RCS inventory control.

Page 31 of 33

CRITICAL TASKS CT-17, Isolate overcooling SG CT-5, Control HPI Page 32 of 33

Appendix D Scenario Outline Form ES-D-2 SAFETY: Take a Minute UNIT 0 (OSM)

SSF Operable: Yes N KHUs Operable: Ui - OH, U2 - UG i LCTs Operable: 2 1 Fuel Handlinc: No UNIT STATUS (CR SRO)

Unit I Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 87% Mode: 1 Mode: 1 Gross MWE: 802 100% Power 100% Power RCS Leakage: +.025 gpm

. EFDW Backup: Yes EFDW Backup: Yes (No WCAP action level)

RBNS Rate: .01 gpm Technical SpecificationslSLC Items (CR SRO)

ComponentlTrain OOS Restoration TS!SLC #

DatelTime Required DatelTime AMSAC/DSS Bypassed Today / 06:30 7 Days CondftionA& B Shift Turnover Items (CR SRO)

Primary

. SASS in MANUAL for I&E testing

. AMSAC/DSS Bypassed for l&E testing Secondary

1SSH-1, ISSH-3, 1SD-2, ISD-5, 1SD-140, 1SD-303, 1SD-355, ISD-356 and 1SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event.

Turbine Valve Movement PT has just been completed and awaiting maneuvering plan to return to full power Reactivity Management (CR SRO)

R2 Reactivity management controls RCS Boron: 30 ppmB Gp 7 Rod Position: 80% established in the Control Room per SOMP 01-02 Human Performance Emphasis (OSM)

Procedure Use and Adherence

Appendix D Scenario Outline Form ES-D-1 1LT40 Oct, 201 1 Facility: Oconee Scenario No.: 4fs (6a .J01 (&0) Op-Test No.: I Examiners: Operators:

Initial Conditions:

. Unit 1: Reactor Power = 3% Unit 2: 100% Unit 3: 100%

Turnover:

. SASS in Manual

. AMSACIDSS bypassed for l&E testing

. GWD Tank B release in progress

. 1C RPS Channel Thot failed to 620°F; this input is bypassed Event Malfunction Event No. No. E vent T ype

Description Oa Pre-Insert SASS in MANUAL Ob Pre-Insert AMSACIDSS bypassed Ob Pre-Insert 1 B RBCU fails to receive an ES signal 1 OP/i/All 103/004, End 4.6 RCS Makeup from 1A and N OATC SRO 1BBHUT 2 Override I: BOP, SRO (TS) 1RIA-37 and 38 fails to terminate GWR (SLC) (TS) 3 C: BOP, SRO (TS) Seismic Event With IA RBCU Rupture (TS) 4 MPSO9O C: OATC SRO 1HP-120 (RC Volume Control) Fails CLOSED 5 Updater I: BOP, SRO (TS) 1A RPS Channel RC pressure fails HIGH (TS) 6 MCRO7O C: OATC, SRO Drop Group 5 Control Rods 7 MPSO2O M: ALL 1 B S/G Tube Rupture 8 MPS400 M: ALL LBLOCA (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-2 Op-rest No: I Scerir1o No. 4 Eveht NO.: 1 Pi Of 3 Event

Description:

OP!11A111031004, End 4.6 RCS Makeup from IA and lB BHUT (N: OATC, SRO)

Time Position Applicants Actions or Behavior Crew response:

OATC The OATC should use the in progress procedure OP/i/NI 103/004 (Soluble Poison Control) Enclosure 4.6 (RCS Makeup From 1A and lB BHUT) beginning at Step 2.1 to makeup to the RCS from 1A and lB BHUT.

2.1 Perform appropriate section(s) to achieve desired results:

Perform Section 3 (Makeup From 1A and 1 B BHUT) for RCS Makeup 3.1 Determine required RCS Makeup volume by performing the following:

3.1.1 IF desired, utilize Enclosure 4.1 (RCS Boron Change Calculation) 3.1.2 IF two Letdown Filters are available, perform the following:

A. Review Component Boron Log for out-of-service Letdown Filter boron B. Make appropriate adjustments to Makeup volumes for placing second Letdown Filter in service 3.1.3 Perform the following:

A. Review Component Boron Log for IA RC Bleed Storage Header boron. {1 8}

B. Make appropriate adjustments to Makeup volumes based on 1A RC Bleed Storage Header boron {18}

3.1.4 Record required Makeup volume: 100 gallons

( 62 gals IA BHUT and 38 gals DW) 3.2 Ensure required RCS Makeup volume and source acceptable. (R.M.)

3.3 IF two Letdown Filters are available, perform the following:

Open 1HP-17 (1A LETDOWN FILTER INLET)

Open IHP-18 (lB LETDOWN FILTER INLET) 3.4 Ensure open IHP-16 (LDST MAKEUP ISOLATION).

Note: The crew may chose to perform the makeup with IHP-15 in AUTO or MANUAL.

3.5 IF Makeup with 1HP-15 in AUTO desired, perform the following:

3.5.1 Select 5 on 1HP-15 Controller.

3.5.2 Enter batch size on 1HP-15 Controller. (R.M.)

3.5.3 Place 1 HP-i 5 Controller in AUTO.

3.5.4 Ensure P on 1HP-15 Controller.

3.6 WHILE making up to Unit I LDST from lA and lB BHUT, monitor the following indications: (R.M.)

Appropriate ranged NIs

Primary tank levels

Neutron error (if applicable)

CRD position (if applicable)

Page 2 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: I Page2 of 3 Event

Description:

OPII/A111031004, End 4.6 RCS Makeup from IA BHUT (N: OATC, SRO)

Time Position Applicants Actions or Behavior Crew response:

OATC 3.7 IF AT ANY TIME abnormal condition(s) require stopping RCS Makeup, perform the following: (RM) 3.7.1 Stop 1A BLEED TRANSFER PUMP.

3.7.2 IF RCS Makeup stopped due to alarm(s) abnormal indication(s), notify CRSRO.

3.7.3 WHEN conditions allow RCS Makeup to continue, perform one of the following:

Start 1A BLEED TRANSFER PUMP.

Go To Step 3.12 to terminate the addition.

3.8 Start 1A BLEED TRANSFER PUMP.

3.9 Open ICS-46 (1A RC BLEED XFER PUMP DISCH).

3.10 IF increased Makeup flow required, perform the following: (AB-1, Unit 1-BTP Room).

Throttle 1 CS-48 (1A BHUT Recirc) to establish desired flow.

Ensure 90 125 psig on 1CS-PG-0084.

3.11 WHEN required volume is added, ensure stopped 1A BLEED TRANSFER PUMP.

3.12 Close 1CS-46 (1A RC BLEED XFER PUMP DISCH). (R.M.)

3.13 Perform one of the following: (R.M.)

Verify correct volume added

Notify CRSRO of incorrect volume added.

3.14 Reset 1HP-15 Controller for Normal Operation.

3.15 Record 1A BHUT boron in Component Boron Log for 1A RC Bleed Storage Header Note: The crew may chose to perform the makeup with IHP-15 in AUTO or MANUAL.

3.16 IF Makeup with 1HP-15 in AUTO desired, perform the following:

3.16.1 Select 5 on 1HP-15 Controller.

3.16.2 Enter batch size on IHP-15 Controller. (R.M.)

3.16.3 Place 1HP-15 Controller in AUTO.

3.16.4 Ensure P on 1HP-15 Controller.

3.17 IF AT ANY TIME abnormal condition(s) require stopping RCS Makeup, perform the following: (RM) 3.7.1 Stop lB BLEED TRANSFER PUMP.

3.7.2 IF RCS Makeup stopped due to alarm(s) OR abnormal indication(s), notify CRSRO.

3.7.3 WHEN conditions allow RCS Makeup to continue, perform of the following:

Start lB BLEED TRANSFER PUMP.

Go To Step 3.22 to terminate the addition.

Page3of27

Appendix D Scenario Outline Form ES-D-2 O5-TefNO.T t - SnnO NO.: 4 Event No.: I Page 3 of 3 Event

Description:

0P111A111031004, End 4.6 RCS Makeup from IA BHUT (N: OATC, SRO)

Time Position Applicants Actions or Behavior Crew response:

OATC 3.18 Start lB BLEED TRANSFER PUMP.

3.19 Open 1CS-56 (lB RC BLEED XFER PUMP DISCH).

3.20 IF increased Makeup flow required, perform the following: (AB-1, Unit 1-BTP Room).

Throttle 1CS-58 (1A BHUT Recirc) to establish desired flow.

Ensure 90 125 psig on ICS-PG-0085.

3.21 WHEN required volume is added, stop lB BLEED TRANSFER PUMP.

3.22 Close 1CS-56 (lB RC BLEED XFER PUMP DISCH). (R.M.)

3.23 Perform one of the following: (R.M.)

Verify correct volume added

Notify CRSRO of incorrect volume added.

3.24 Reset 1 HP-i 5 Controller for Normal Operation.

3.25 Close 1HP-16 (LDST MAKEUP ISOLATION).

3.26 Record RCS batch volume in AutoLog.

3.27 IF desired to remove one Letdown Filter from service, perform the following: (Continue) 3.27.1 Verify> 10 minutes since LDST Makeup was secured. {8} (R.M.)

3.27.2 Position one of the following:

Close 1HP-17 (1A LETDOWN FILTER INLET)

Close 1HP-18 (lB LETDOWN FILTER INLET) 3.27.3 Record RCS boron for out-of-service Letdown Filter in Component Boron Log 3.28 IF RCS sample for boron required, notify Chemistry to sample 3.29 IF increased Makeup flow from IA BHUT was required, perform the following:

3.29.1 Start 1A BLEED TRANSFER PUMP 3.29.2 discharge pressure is NOT 90-i 10 psig, throttle 1 CS-48 to obtain 90 110 psig on 1 CS-PG-0084 3.29.3 Stop 1A BLEED TRANSFER PUMP 3.30 IF increased Makeup flow from 1 B BHUT was required, perform the following:

3.30.1 Start I B BLEED TRANSFER PUMP 3.30.2 IF discharge pressure is NOT 90-i 10 psig, throttle 1 CS-58 to obtain 90 110 psig on I CS-PG-0085 3.30.3 Stop lB BLEED TRANSFER PUMP This event is complete when Step 3.24 is complete to reset I HP-15, or as directed by the Lead Examiner.

Page4of27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 2 Rage 1 óf3 Event

Description:

I RIA-37 and 38 fails to terminate GWR (I: BOP, SRO) (TS)

Time Position Applicants Actions or Behavior Plant response:

1SA-9/A-4, (GWD DISCH RADIATION INHIBIT)

1 SA-81B-9, (RM PROCESS MONITOR HIGH)

Note: SRO may invoke OMPI-18 to close IGWD-5 SOP Crew response:

Statalarm ISA-91A-4, (GWD DISCH RADIATION INHIBIT)

2. Automatic Action 2.1 IF high alarm is received, 1RIA-37 and/or 1RIA-38 will close valves 1 GWD-4, 5, 6, and 7 and GWD-206, 207 and stop the WG Exhauster.

3. Manual Action 3.1 Ensure automatic action has taken place. (they have not) 3.2 Refer to OP/i -2/All 104/18 (Gaseous Waste Disposal System) for direction on continuing or terminating release Crew response:

BOP Statalarm 1SA-81B-9, (RM PROCESS MONITOR HIGH)

2. Automatic Action 2.1 1RIA-37 AND/OR RIA-38 will close valves IGWD-4, 5, 6, 7, GWD-206, 207 and stop the WG exhauster if high setpoint is received.

2.2 AP/l/A/1700/018 (Abnormal Release of Radioactivity) will provide additional Automatic Actions if this ARG directs entry into the AP.

(This ARG does not direct use of AP/18)

3. Manual Action 3.1 Determine radiation monitors in alarm 3.10 IF IRIA-37 or 1RIA-38 alarms during GWD tank release, GO TO OP/i -2/All 104/018 (GWD System) for applicable guidance.

Crew response:

SOP OP/i -2/All 104/018 (GWD Tank Release)

Complete End. 4.9 of OP/i -2/All 104/018 (GWD Tank Release) 3.30 IF 1RIA-37 or 38 High Alarm is received, perform the following:

3.30.1 Close GWR DISCHARGE FLOW CONTROL (GWD-5) 3.30.2 Record maximum cpm of 1 RIA-37 and 1 RIA-38 Note: IRIA-37 maximum value is 7.2E5 cpm and IRIA-38 maximum value is I.IIEI cpm.

3.30.3 IF desired to continue release, Go To Enclosure 4.15 3.30.4 IF desired to terminate release. Go To Section 4 (GWR Termination).

Page 5 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario N6.: Event No.: 2 Page 2 of 3 Event

Description:

IRIA-37 and 38 fails to terminate GWR (I: BOP, SRO) (SLC)

Time Position j Applicants Actions or Behavior Crew Response:

Section 4. GWR Termination:

BOP 4.1 Record Stop GWR # Auto Log 4.2 Complete Enclosure 4.10 (GWD Tank Sample Request) and route to RP 4.3 IF GWD Tank A released, perform the following: (does not apply) 4.4 IF GWD Tank B released, perform the following:

4.4.1 Isolate GWD Tank B as follows:

Close GWD-99 (Tank 1 B Discharge Block)

Close GWD-1 00 (Decay Tanks Discharge Header Block)

Place GWD-5 (B GWD Tank Discharge) switch in CLOSED 4.4.2 Check GWD Tank B for accumulation of water as follows:

Throttle open LWD-241

Throttle open LWD-355

Throttle open LWD-353

Throttle open LWD-354 4.4.3 WHEN no water passes through sight-glass, position the following:

Close LWD-241

Close LWD-355

Close LWD-353

Close LWD-354 4.5 IF GWD Tank C released, perform the following: (does not apply) 4.6 IF GWD Tank D released, perform the following: (does not apply) 4.7 Drain GWD Filters as follows:

Throttle LWD-242 (Waste Gas Absolute Filter Drain)

Throttle LWD-243 (Waste Gas Charcoal Filter Drain) 4.8 After one minute, perform the following:

Close LWD-242 (Waste Gas Absolute Filter Drain)

Close LWD-243 (Waste Gas Charcoal Filter Drain)

Purge 1RIA-37, 38 This event is complete when GWD Tank B is isolated (GWD-5 closed) in Step 4.4, or as directed by the Lead Examiner.

Page 6 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 2 Page 3 of 3 Event

Description:

I RIA-37 and 38 fails to terminate GWR (I: BOP, SRO) (SLC)

Time Position Applicants Actions or Behavior SRO SRO refers to SLC 16.1 1.3 and enters Condition C and Condition I APPLICABILITY: At all times CONDITION C: One or more required gaseous effluent monitoring instrument channels inoperable.

REQUIRED ACTION: Enter the Condition referenced in Table 16.11.3-2 for the function (Immediately)

Restore the instrument(s) to OPERABLE status (30 days)

CONDITION I: As required by Required Action C.1 in Table 16.11.3-2 REQUIRED ACTION: Suspend release of radioactive effluents (Immediately)

This event is complete when GWD Tank B is isolated (GWD-5 closed) in Step 44, or as directed by the Lead Examiner.

Page 7 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 3 Page 1 of 2 Event

Description:

Seismic Event With IA RBCU Rupture (C: BOP, SRO) (TS)

Time Position Applicants Actions or Behavior Plant response:

1 SA-9/B-9 (LPSW RBCU A Cooler Rupture)

Reactor Building Normal Sump level will increase Crew response:

BOP The BOP should refer to ARG for ISA-91B-9 3.1 Verify alarm condition is valid by checking RBCU 1A Inlet Flow and RBCU IA ti Flow.

3.2 Verify 1LPSW-18 (RBCU 1A OUTLET) open 3.3 Verify adequate LPSW flow is available; check LPSW pump operation 3.3.1 Verify 1LPSW-16 (1A RBCU INLET PENE) is open 3.3.2 IF 1 LPSW-16 (1A RBCU INLET PENE) is NOT open, refer to TS and SLCs Booth Cue: Once the BOP begins to perform ARG actions, call the Control Room (4911) as a security guard and state We have felt a tremor and have observed no plant damage If asked, state that the tremor was felt in the Turbine Building.

3.4 Monitor RBNS Level for any unexplained increase 3.5 IF RBNS Level is increasing AND ES has actuated, notify Chemistry to sample the RBNS for boron concentration to determine if a cooler rupture has occurred based on sample results.

3.6 IF RBCU 1A Cooler rupture or line break is indicated, then:

3.6.1 Isolate the 1A RBCU Cooler as follows:

A. Close 1LPSW-16 (1A RBCU INLET PENE)

B. Close 1LPSW-18 (1A RBCU OUTLET)

C. Perform TS 3.6.3 Condition C for closed containment system.

D. Enter TS 3.6.5 Condition B for RBCU inoperable.

E. Continue to monitor RBNS level for increase.

F. IF RBNS level is still increasing, notify TSC to evaluate further isolation of 1A RBCU.

3.6.2 Refer to Technical Specifications.

3.6.3 Refer to SLC 16.9.12 (Additional LPSW and Siphon Seal Water System Operability Requirements) (Does not apply) 3.6.4 Refer to OP/i/All 104/010 (Low Pressure Service Water).

3.6.5 Refer to OP/1!A11104/015 (Reactor Building Cooling System).

Page 8 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 3 Page 2 of 2 Event

Description:

Seismic Event With IA RBCU Rupture (C: BOP, SRO) (TS)

Time Position Applicants Actions or Behavior Crew Response:

SRO Refer To APIOIAII 7001005, EARTHQUAKE:

4.1 Announce AP entry using the PA system 4.2. IAAT jy of the following occur:

Re-flash of SEISMIC TRIGGER (1SA-9, E-1) and/or (3SA-9, E-1)

Re-flash of computer alarm: SEISMIC RECORDER (01 D0201) on Unit 1

Aftershocks felt at ONS or Keowee Hydro Station THEN GO TO Step 4.3 4.3 IAAT major visible damage is observed, THEN evaluate Rx trip on aU affected units.

4.4 Notify Keowee operating personnel to initiate AP/0/A/2000/001 (Natural Disaster).

Booth Cue: Respond as the Keowee Operator and state that AP/OOlwill be initiated.

4.5 Notify Hydro Central.

4.6 Dispatch operators to perform the following enclosures:

End 5.1 (Outside Inspections)

End 5.2 (AB Inspections)

End 5.3 (LPSW Inspections) 4.7 IAAT y Oconee unit is shutdown, THEN dispatch an operator to perform End 5.4 (RB Inspections).

4.8 Notify the OSM to reference the following:

RP/0/B/1 000/001 (Emergency Classification)

OMP 1-14 (Notifications)

Contingency Plan Information supplied from EP for seismic instruments that are out of service, as applicable Booth Cue: If asked, Unit 2 will continue AP/5 actions.

4.9 Initiate the following to monitor SF Pool temperature level:

Unit 1-2 AP/35 (Loss of SFP Cooling and/or Level) End 5.14 (SEP Temperature and Level Monitoring)

Unit 3 AP/35 (Loss of SFP Cooling and/or Level) End 5.14 (SEP Temperature and Level Monitoring) 4.10 Monitor Keowee lake level for indications of dam/dike leakage This event is complete when IA RBCU has been isolated, or as directed by the Lead Examiner.

Page 9 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 4 Page 1 of 2 Event

Description:

IHP-120 (RC Volume Control) Fails CLOSED (C: OATC, SRO)

Note: Activate this event during event 3.

Time Position Applicants Actions or Behavior Plant Response:

RCS makeup flow goes to 10 gpm (HPI Warming Flow)

PZR level begins to decrease

LDST level begins to increase

Valve position demand for 1HP-120 begins to increase to the 100%

demand value and valve position indication will indicate closed (green light)

1SA-02/ B-i, HP LETDOWN TANK LEVEL HIGH/LOW, will illuminate after several minute time delay Crew Response:

BOP The crew may refer to ARG 1 SA-02/B-1, HP LETDOWN TANK LEVEL HIGH/LOW and perform the required actions.

3.1 Instrument Failed:

3.1.1 Compare alternate channels to verify alarm validity:

O1A1 042 LDST LEVEL i

OIAI 043 LDST LEVEL 2 3.2 Verify LDST pressure does not exceed LDST level/pressure operability requirement per OP/i/Ni i04/002, (HPI System).

3.3 IF High Level alarm is received:

3.3.1 Bleed as required by OP/1/N1i03/004 (Soluble Poison Concentration Control).

BOP OP/i/Ni 103/004, Soluble Poison Concentration Control Refer to Enclosure 4.8 Reducing RCS Inventory:

1.1 Verify HPI System operating 1.2 Ensure open 1CS-26 (LETDOWN TO RC BHUT).

1.3 Ensure open 1CS-41 (1A RC BHUT INLET).

1.4 Position 1 HP-14 (LDST BYPASS) to BLEED.

i .5 WHEN desired LDST level achieved, position 1 HP-14 (LDST BYPASS) to NORMAL.

SRO Refer to AP/i/Ni700/0i4, Loss of Normal Makeup and/or RCP Seal Injection 3.1 IAAT RCP seal injection flow is lost, AND Component Cooling is lost, THEN perform the following:

A. Trip the Rx B. Stop all RCPs C. Initiate AP/25 (SSF EOP)

Note: The crew may initiate EOP End 5.5 for RCS inventory control due LDST level increase (see page 22)

Page 10 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 4 Page 2 of 2 Event

Description:

IHP-120 (RC Volume Control) Fails CLOSED (C: OATC, SRO)

Time Position Applicants Actions or Behavior Crew Response:

SRO AP/lIAIi700/014, Loss of Normal Makeup and/or RCP Seal Injection 3.2 IAAT loss of suction to operating HPI pumps is indicated:

Motor amps low or cycling

Discharge pressure low or cycling

Abnormal LDST level trend THEN GO TO Step 3.3 RNO: GO TO Step 4.7 4.7 Announce AP entry using PA System 4.8 Verify jy HPI pump operating 4.9 Verify RCP seal injection or HPI makeup line leak indicated by jy of the following:

Report of line leak

Abnormal LDST level decrease

1 RIA-32 (AUX BLDG GAS)

1 RIA-45 (NORM VENT GAS)

RB RIAs in alarm

Abnormal RBNS level increase

Abnormal LAWT or HAWT level increase RNO: GOTOStep4.11 4.11 Verify RCP seal injection flow exists to y RCP 4.12 Verify 1HP-120 operable in AUTO RNO: 1. Attempt to operate I HP-i 20 in HAND

2. IF 1HP-120 fails to operate, THEN GO TO Step 4.176 4.176 Perform the following as necessary to maintain Pzr level > 200

Close 1 HP-6

Throttle 1 HP-7

Throttle 1 HP-26 4.177 Place 1HP-120 in HAND and close 4.178 Notify SPOC to investigate and repair 1HP-i20 4.179 WHEN 1HP-120 is repaired, THEN slowly re-establish flow through 1HP-120 Note: I HP-I 20 will remain failed for the remainder of the scenario.

This event is complete when Pzr level is returned to normal band (200-230), or as directed by the Lead Examiner.

Page II of27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 5 Page 1 of 2 Event

Description:

IA RPS Channel RC pressure fails HIGH (I: BOP, SRO) (TS)

Time Position Applicants Actions or Behavior Plant Response:

1SA-i/A6(1AHI PRESSTRIP

1SA-5/A5 (IA RPS TROUBLE) actuates

OAC alarm for 1A RPS RC PRESS DEV actuates Crew Response:

BOP Refer to ARG for 1SA-5/A5 (1A RPS TROUBLE) 3.1 IF Reactor trips, GoTo EP/1/A/1800/00i (Emergency Operating Procedure).

3.2 Refer to OP/1/A11105/014 (Control Room Instrumentation Operation and Information).

3.3 Initiate Work Request for I&E to investigate cause.

Refer to ARG for 1SA-i/A-6 (1A HI PRESS TRIP 3.1 Check instrumentation to verify high pressure 3.2 Refer to OP/i/Ni 105/014 (Control Room Instrumentation Operation and Information)

Refer to OP/1/A/1105/014 (Control Room Instrumentation Operation and Information) Enclosure 4.7 (Removal and Restoration of RPS Channels)

2. Initial Conditions 2.1 Verify one of the following:

2.1.1 A procedure requires RPS Channel to be placed in Trip or Bypass.

2.1.2 Equipment failure requires RPS Channel to be placed in Trip or Bypass.

2.2 Identify affected RPS Channel IA (IA, 1B, 10, 1D)

3. Procedure 3.1 IF affected RPS channel is NOT required per TS 3.3.1, perform one of the following: (step not applicable it is required) 3.2 IF affected RPS channel is required per TS 3.3.1, perform the following:

3.2.1 Verify one of the following for the remaining unaffected RPS channels:

A. Verify no RPS channels tripped AND no RPS functions are tripped.

B. Perform the following:

IF any RPS channel is tripped, verify RPS channel is bypassed

I.E any RPS function is tripped, verify RPS functions are bypassed OR verify RPS channel is bypassed 3.2.2 Declare affected RPS Channel inoperable.

Page 12 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 5 - Page 2 of 2 Event

Description:

IA RPS Channel RC pressure fails HIGH (I: BOP, SRO) (TS)

Time Position Applicants Actions or Behavior Crew Response:

BOP NOTE: For determining appropriate TS condition a tripped channel is considered inoperable.

3.2.3 Refer to TS 3.3.1 and enter appropriate TS Condition.

3.2.4 Trip affected RPS channel using MANUAL TRIP Key as follows:

A. Obtain Key #312.

B. Place MANUAL TRIP Keyswitch in TRIP. (Cab. 2, 4, 6, or 8) 3.3 IF RPS Channel removed from service due to equipment failure, perform the following:

Initiate Work Request

IF required per OMP 1-14 (notifications), perform appropriate notifications 3.4 WHEN notified by I&E, restore RPS channels as follows:

Note: The IA RPS channel will remain tripped for the remainder of the scenario.

SRO The SRO should enter TS 3.3.1 Condition A for one required channel inoperable.

The Required Action is to place the channel in trip within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for Unit(s) with RPS digital upgrade complete This event is complete when the IA RPS channel is placed in trip, or as directed by the Lead Examiner.

Page 13 of 27

Appendix D Scenario Outline Form ES-D-2 Pp-Test No.: I Scenario No.: 4 Event No.: 6 Page 1 of 2 Event

Description:

Drop Group 5 Control Rods (C: OATC, SRO)

Time Position Applicants Actions or Behavior Plant Response:

Group 6 control rods will drop into the core which will cause Reactor power to decrease Crew Response:

The OATC should manually trip the reactor Booth Cue: FIRE TIMER 7 to initiate a SGTL in the lB SG when the Reactor is manually tripped.

OATC The SRQ will direct the OATC to perform Immediate Manual Actions:

Depress REACTOR TRIP pushbutton

Verify reactor power < 5% FP and decreasing

Depress turbine TRIP pushbutton.

Verify all turbine stop valves closed

Verify RCP seal injection available BOP The SRO will direct the BOP to perform a Symptoms Check

Reactivity Control

> Power Range NIs <5% and decreasing

ICC/Loss of Subcooling Margin (SCM)

> If any SCM 0°F, perform Rule 2

Loss of Heat Transfer (LOHT)

Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW)

Excessive Heat Transfer (EHT)

Uncontrolled Main Steam Line(s) pressure decrease

Steam Generator Tube Rupture

> CSAE off-gas alarms, process RIAs (RIA-40, 59, 60), area RIAs (RIA-16/17)

Note: The BOP will report indications of a SGTL in the I B SG which will initiate the next event.

This event is complete when the reactor is tripped, or as directed by the Lead Examiner.

PageI4of27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event Np.: 6 Pge 2 of 2 Event

Description:

Drop Group 5 Control Rods (C: OATC, SRO)

Time Position Applicants Actions or Behavior SRO Verify Immediate Manual Actions with the OATC Transfer to Subsequent Actions 4.1 Verify all control rods in Groups I 7 fully inserted.

4.2 Verify Main FDW in operation.

4.3 Verify either of the following:

Main FDW overfeeding causing excessive temperature decrease.

Main FDW underfeeding causing SG level decrease below setpoint.

RNO GO TO Step 4.5.

4.5 IAAT Main FDW is operating, AND level in any SG is > 96% on the Operating Range, THEN perform Steps 4.6 4.8. -

RNO GO TO Step 4.9.

4.9 IAAT TBVs CANNOT control SG pressure at desired setpoint, THEN manually control pressure in affected SGs using either of the following:

TBVs Dispatch two operators to perform End 5.24 4.10 Verify IRIA-40 operable with CSAE OFF-GAS BLOWER operating.

Once the BOP reports the Steam Generator Tube leak rate is greater than 25 gpm, review Parallel Actions page and transfer to the SGTR tab This event is complete when the reactor is tripped, or as directed by the Lead Examiner.

Page 15 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 7 Page 1 of 2 Event

Description:

lB SIG Tube Rupture (M: ALL)

Time Position [ Applicants Actions or Behavior Plant Response:

1SA-08/E-10 (N-16 RM PRIMARY TO SECONDARY TUBE LEAK) 1SA-081D-10 (RM CSAE EXHAUST RADIATION HIGH)

Crew Response:

The SRO will transfer to the SGTR tab from Subsequent Actions Parallel Actions Page The SRO will declare Emergency Dose Limits in effect.

SRO EOPSGTRtab

1. Verify Rx tripped

2. Maintain Pzr level 140 180 [175 215 acc] by initiating End 5.5

3. Start A and B OUTSIDE AIR BOOSTER FANS (CT-27)

(Note: Fans must be started prior to completing End 5.1)

4. Notify Unit 3 to start 3A and 3B OUTSIDE AIR BOOSTER FANS

5. Perform the following:

Monitor RIAs 16 and 17 to identify all SGs with a tube rupture Inform SRO of results

6. Dispatch an operator to open A and B Turbine Bldg Sump pump BKRs

7. Notify RP to survey both MS lines for radiation

8. GO TO Step 27

27. Secure y unnecessary offsite release paths (Main Vacuum Pumps, TDEFDW, Emergency Steam Air Ejector, etc.)

28. Verify Main FDW or EFDW controlling properly

29. Open 1 HP-24 and I HP-25

30. Secure makeup to LDST

31. Maintain both SG pressures <950 psig using TBVs

32. IAAT all the following exists:

All SCMs > 0°F ES Bypass Permit satisfied RCS pressure controllable THEN perform Step 33 RNO: GO TO Step 34

33. Bypass HPI and LPI as applicable

34. Verify y RCP operating

35. Maintain RCP NPSH during the reduction of SCM Page 16 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 7 Page 2 of 2 Event

Description:

SIG Tube Rupture (M: ALL)

Time Position Applicants Actions or Behavior Crew Response:

36. Reduce and maintain SCM at minimum using any/all of the following methods: (CT-7)

Note: To satisfy this CT, SCM must be being reduced to 1020 degrees subcooling in a controlled evolution.

De-energize aM Pzr heaters Use Pzr spray Maintain Pzr level 140 180 [175215 acc]

37. IAAT RCS de-pressurization methods are inadequate in minimizing core SCM, THEN perform Steps 38-40 RNO: GO TO Step 41

38. Verify Pzr spray nozzle t\T 41 0°F

39. Close 1LWD-1 and 1LWD-2

40. Cycle PORV as necessary

41. Verify 1 SA-2/C-8 (AFIS HEADER A INITIATED) lit RNO: Select OFF for digital channels on AFIS HEADER A

42. Verify 1SA-2/D-8 (AFIS HEADER B INITIATED) lit RNO: Select OFF for both digital channels on AFIS HEADER B

43. Verify RCS temperature > 532° F

44. Initiate a cooldown as follows:

Decrease SG pressure to 835 845 psig using any of the following:

TBV setpoint adjusted to 710 720 psig

TBVs in manual

ADVs Maximize cooldown rate limited only by the ability to maintain Pzr level> 100 [180 acc]

This event is complete when the crew begins to action to reduce SCM at Step 36 of the SGTR tab, or as directed by the Lead Examiner.

Page 17 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 8 Page 1 of 6 Event

Description:

LBLOCA (M: ALL)

[_Time Position Applicants Actions or Behavior Plant Response:

ES Channels 1 8 actuate RCS pressure begins to rapidly decrease which will quickly reduce SCM to 0°F 1 B RBCU fails to receive an ES signal Crew Response:

The SRO may direct an RO to perform a Symptoms Check The SRO will direct an RO to perform Rule 2 (Loss of SCM) once any SCM = 0°F (see page 18)

The SRO will transfer to the LOSCM tab from the SGTR Parallel Actions Page The SRO may transfer to the ICC tab from the LOSCM tab Parallel Actions Page if Reactor Vessel head level indicates 0 (see next page)

The SRO will direct an RO to perform EOP End 5.1 (ES Actuation)

(see page 19)

SRO EOPLOSCMtab

1. Ensure Rule 2 (Loss of SCM) is in progress or complete

2. Verify Station ASW feeding y SG RNO: GO TO Step 4

4. Verify LOSCM caused by excessive heat transfer RNO: GOTOStep6

6. IAAT either of the following exists:

LPI FLOW TRAIN A LPI FLOW TRAIN B 3400 gpm Only one LPI HEADER in operation with header flow 2900 gpm THEN GO TO LOCA CD tab SRO EOP LOCACD tab

1. IAAT BWST level is 19, THEN initiate End 5.12 (ECCS Suction Swap to RBES)

2. Verify ES actuated

3. GO TO Step 7

7. Perform the following:

Ensure all RBCUs in low speed

_Open 1LPSW-18, 1LPSW-21, and ILPSW-24

8. Initiate End 5.35 (Containment Isolation)

9. Start all RB Aux fans This event is complete when End 5.1 actions are complete and the SRO transfers to the LOCA CD tab, or as directed by the Lead Examiner.

Page 18 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 8 Page 2 of 6 Event

Description:

LBLOCA (M: ALL)

Time Position Applicants Actions or Behavior Crew response:

SRO EOPICCtab

1. IAAT CETCs> 1200°F, AND TSC is ready to provide mitigation guidance, THEN perform the following:

A. Notify TSC to enter the OSAG B. EXIT this procedure

2. Ensure full HPI and control per Rule 6 (HPI)

3. IAAT RCS pressure is 550 psig, OR RB pressure is 3 psig, THEN perform Steps 4-8

4. Open 1LP-21 and 1LP-17

5. Start 1A LPI Pump

6. Open 1LP-22 and 1LP-18

7. Start lB LPI Pump

8. Verify two LPI pumps operating

9. IAAT all the following exist:

1C LPI Pump off IC LPI Pump available LPI required ECCS pump suction aligned to BWST 1A LPI Pump unavailable lB LPI Pump unavailable THEN perform Steps 10-13 RNO: GOTOStepl4

14. Open ICF-1 and 1CF-2

15. IAAT core SCM is 0°F, THEN GO TO LOCA CD tab Page 19 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 8 Page 3 of 6 Event

Description:

LBLOCA (M: ALL)

Time Position Applicants Actions or Behavior Crew response:

OATC/BOP EOP Rule 2 (Loss of SCM)

1. IAAT aH exist:

Any SCM 0°F

_Rxpower 1%

2 minutes elapsed since loss of SCM THEN perform Steps 2 and 3

2. Stop a RCPs

3. Notify CR SRO of RCP status

4. Verify Blackout exists RNO: GOTOStep6

6. Open 1HP-24 and 1HP-25

7. Start a available HPI pumps

8. GOTOStepl3

13. Open 1HP-26 and 1HP-27

14. Verify at least two HPI pumps are operating using two diverse indications

15. IAAT 2 HPI pumps operating, AND HPI flow in y header is in the Unacceptable Region of Figure 1, THEN perform Step 16-21 RNO: GOTOStepl7

17. IAAT flow limits are exceeded, Pump Operation Limit 1 HPI pump/hdr 475 gpm (md, seal injection for A hdr) 1A & 1 B HPi Total flow of 950 gpm pumps operating (md. seal injection) with I HP-409 open THEN perform Steps 18-20 RNO: GO TO Step 21

18. Place Diverse HPI in BYPASS

19. Place ES CH I and ES CH 2 in MANUAL

20. Throttle HPI to maximize flow flow limit

21. Notify SRO of HPI status

22. Verify RCS pressure > 550 psig RNO: Ensure ES Channels 3 and 4 actuated Page 20 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 8 Page 4 of 6 Event

Description:

LBLOCA (M: ALL)

Time Position [ Applicants Actions or Behavior Crew response:

OATC/BOP EOP Rule 2 (Loss of SCM)

23. IAAT either exists:

LPI FLOW TRAIN A plus LPI FLOW TRAIN B 3400 gpm Only one LPI header in operation with header flow 2900 gpm THEN GO TO Step 24

24. Perform the following:

Place IFDW-315 in MANUAL and close Place 1FDW-316 in MANUAL and close Place 1 FDW-35 in HAND and close Place 1 FDW-44 in HAND and close

25. Notify crew that performance of Rule 3 is NOT required due to LB LOCA

26. WHEN directed by CR SRO, THEN EXIT this rule OATC/BOP EOP Enclosure 5.1 (ES Actuation)

1. Determine aW ES channels that should have actuated based on RCS pressure and RB pressure.

RB 3 psig: Channels 1,2,3,4,5 & 6

RB 10 psig: Channels 7 & 8

2. Verify aB ES digital channels associated with actuation setpoints have actuated.

3. IAAT additional ES actuation setpoints are exceeded, THEN perform Steps 1-2.

4. Place Diverse HPI in BYPASS

5. Place ES CH 1 and ES CH 2 in MANUAL

6. Verify Rule 2 in progress or complete.

7. Verify RCP operating RNO: GO TO Step 9

9. IAAT aM exist:

Voter associated with ES channel is in OVERRIDE An ES channel is manually actuated Components on that channel require manipulation THEN depress RESET on the required channel

10. IAATy RCP is operating, AND ES Channels 5 an 6 actuate, THEN perform Steps 11-14 RNO: GOTOStep15

15. IAAT ES Channels 3 & 4 are actuated, THEN GO TO Step 16 Page 21 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 8 Page 5 of 6 Event

Description:

LBLOCA (M: ALL)

Time Position ApplicanVs Actions or Behavior Crew response:

OATC/BOP EOP Enclosure 5.1 (ES Actuation)

16. Place Diverse LPI in BYPASS

17. Perform both:

Place ES CH 3 in MANUAL

Place ES OH 4 in MANUAL

18. IAAT y LPI pump is operating against a shutoff head, THEN at the CR SROs discretion, stop affected LPI pumps

19. IAAT RCS pressure is < LPI pump shutoff head, THEN perform Steps2021

20. Open 1LP-17 and Start 1A LPI PUMP

21. Open 1LP-18 and Start lB LPI PUMP

22. IAAT lAand lB LPI PUMPs are off/tripped, AND aH of the following exist:

RCS pressure < LPI pump shutoff head 1LP-19 closed 1 LP-20 closed THEN perform Steps 23 24 -

RNO: GO TO Step 25

25. IAAT IA LPI PUMP fails while operating, AND 1 B LPI PUMP is operating, THEN close ILP-17

26. IAAT lB LPI PUMP fails while operating, AND 1A LPI PUMP is operating, THEN close I LP-1 8

27. Start A and B OUTSIDE AIR BOOSTER FANs

28. Notify Unit 3 to start 3A and 3B OUTSIDE AIR BOOSTER FANs

29. Verify 1CF-1 and 1CF-2 are open

30. Verify 1HP-410 closed

31. Secure makeup to the LDST

32. Verify a ES channel 1 4 components are in the ES position

33. Verify Unit 2 turbine tripped RNO: GO TO Step 36

36. Close 1LPSW-139

37. Place in FAIL OPEN:

1LPSW-251 FAIL SWITCH

_1 LPSW-252 FAIL SWITCH

38. Start all available LPSW pumps Page 22 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 8 Page 6 of 6 Event

Description:

LBLOCA (M: ALL)

Time Position Applicants Actions or Behavior Crew response:

OATC/BOP EOP Enclosure 5.1 (ES Actuation)

39. Verify either:

Three LPSW pumps operating Two LPSW pumps operating when Tech Specs only requires two operable

40. Open 1 LPSW-4 and 1 LPSW-5

41. IAAT BWST level 19, THEN initiate End 5.12 (ECCS Suction Swap to RBES)

42. Dispatch an operator to perform End 5.2 (Placing RB Hydrogen Analyzers In Service) (PS)

43. Select DECAY HEAT LOW FLOW ALARM SELECT switch to ON

44. IAAT ES channels 5 & 6 have actuated THEN perform Step 45

45. Verify all ES channel 5 & 6 components are in the ES position RNO: Notify SRO to evaluate components NOT in ES position g initiate action to place in ES position if desired Note: The lB RBCU fails to receive an ES signal and will not be in the ES position unless it has been started lAW guidance in the LOCA CD tab.

If the I B RBCU has not been started per the LOCA CD tab, the SRO should direct starting the I B RBCU in LOW speed.

46. IAAT ES channels 7 & 8 have actuated, THEN perform Step 47

47. Verify all ES 7 & 8 components are in the ES position

48. Notify U2 CR SRO that SSF is inoperable due to OTS1-1 open

49. IAAT conditions causing ES actuation have cleared, THEN initiate End 5.41 (ES Recovery)

50. WHEN CR SRO approves, THEN EXIT this enclosure This event is complete when End 5.1 actions are complete, the I B RBCU has been started in LOW speed and the SRO transfers to the LOCA CD tab, or as directed by the Lead Examiner.

Page 23 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 8 Page 1 of 2 Event

Description:

EOP Enclosure 5.5 (if required)

Time_j Position Applicants Actions or Behavior Crew response:

OATC/BOP EOP Enclosure 5.5 (Pzr and LDST Level Control) (if needed)

1. Utilize the following as necessary to maintain desired Pzr level:

1AHPIPump

lBHPlPump

1HP-26

1HP-7

1 HP-1 20 setpoint or valve demand

1HP-5

2. IAAT makeup to the LDST is desired, THEN makeup from IA BHUT.

3. IAAT it is desired to secure makeup to LDST, THEN secure makeup from IA BHUT.

4. IAAT it is desired to bleed letdown flow to 1A BHUT, THEN perform the following:

A. Open:

1CS-26

1CS-41 B. Position IHP-14 to BLEED.

C. Notify SRO.

5. IAAT letdown bleed is NO longer desired, THEN position 1 HP-I 4 to NORMAL.

6. IAAT 1 C HPI PUMP is required, THEN perform Steps 79.

RNO: GO TO Step 10.

7. Open 1 HP-24 and 1 HP-25

8. Start 1C HPI PUMP

9. Throttle the following as required to maintain desired Pzr level:

1HP-26

1HP-27

10. IAAT LDST vel CANNOT be maintained, THEN perform Step 11.

RNO: GO TO Step 12.

11. Perform the following:

Open 1HP-24

Open IHP-25

Close 1HP-16 Page 24 of 27

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: I Scenario No.: 4 Event No.: 8 Page 2 of 2 Event

Description:

EOP Enclosure 5.5 (if required)

Time__[ Position Applicants Actions or Behavior Crew response:

OATC/BOP EOP Enclosure 5.5 (Pzr and LDST Level Control) (if needed)

12. IAAT additional makeup flow to LDST is desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close 1CS-48 (1A BHUT Recirc) (A-i-i 07, Unit 1 RC Bleed Transfer Pump Rm.).

13. IAAT two Letdown Filters are desired, THEN perform the following:

Open 1HP-17.

Open 1HP-18

14. IAAT a of the following exist:

Letdown isolated

LPSW available

Letdown restoration desired THEN perform Steps 15 33 -

RNO: GO TO Step 34.

34. IAAT it is determined that letdown is unavailable due to equipment failures or letdown system leakage, THEN notify CR SRO to initiate AP/32 (Loss of Letdown).

35. IAAT> I HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:

A. Obtain SRO concurrence to reduce running HPI pumps.

B. Secure the desired HPI pumps.

C. Place secured HPI pump switch in AUTO, if desired.

36. IAAT all the following conditions exist:

Makeup from BWST NOT required

LDST level > 55

All control rods inserted

Cooldown Plateau NOT being used THEN close:

1HP-24

1HP-25

37. Verify ICS-48 (1A BHUT Recirc) has been closed to provide additional makeup flow to LDST.

RNO: GO TO Step 39.

39. Verify two Letdown Filters in service, AND only one Letdown filter is desired.

RNO: GOTOStep41.

41. WHEN directed by CR SRO, THEN EXIT this enclosure.

These actions are complete when EOP Enclosure 5.5 (Pzr and LDST Level Control) is exited.

Page 25 of 27

Appendix D Scenario Outline Form ES-D-2 CRITICAL TASKS CT-27 Implementation of Control Room Habitability Guidance CT-7 Minimize SCM to reduce the leak flowrate from the RCS to the secondary side of a SG Page 26 of 27

Appendix D Scenario Outline Form ES-D-2 SAFETY: Take a Minute - - - -

UNIT 0 (OSM)

SSF Operable: Yes fl KHUs Operable: Ui - OH, U2 UG

- LCTs Operable: 2 fl Fuel Handling: No UNIT STATUS (CR SRO)

Unit I Simulator Other Units Mode: 2 Unit 2 Unit 3 Reactor Power: 3% Mode: 1 Mode: 1 Gross MWE: 0 100% Power 100% Power RCS Leakage: +.025 gpm EFDW Backup: Yes EFDW Backup: Yes (No WCAP action level)

RBNS Rate: .01 gpm Technical SpecificationslSLC Items (CR SRO)

ComponentlTrain OOS Restoration TSISLC #

DatelTime Required DatelTime AMSAC/DSS Bypassed Today / 06:30 7 Days CondftionA& B Shift Turnover Items (CR SRO)

Primary

. SASS in MANUAL for l&E testing

. AMSAC/DSS Bypassed for I&E testing

. 1 C RPS Channel Thot is failed to 620°F input bypassed

. OATC is to use the in progress procedure to perform a 100 gallon batch addition to the LDST from IA and lB BHUT (OP/1/A11103/004 End 4.6 beginning at Step 2.1)

. OP/i/Ni 102/002, End 4.7 in progress and complete up to step 3.39

. GWD Tank B release in progress Secondary

1SSH-1, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, 1SD-355, 1SD-356 and 1SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event.

OP/i/N1102/001 End 4.7 is in progress and complete up to Step 3.39. Holding current power level while Rx Engineering is taking data.

Reactivity Management (CR SRO)

R2 Reactivity Management controls RCS Boron: 1756 ppmB Gp 7 Rod Position: 6% established in the Control Room per SOMP 01-02 Human Performance Emphasis (OSM)

Procedure Use and Adherence

ML113390441

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