Text

Initial Exam 2011-301 Draft Simulator Scenarios
	ML111881113
Person / Time
Site:	Oconee
Issue date:	07/06/2011
From:	; NRC/RGN-II
To:	; Duke Energy Corp
References
	50-269/11-301, 50-270/11-301, 50-287/11-301
	Download: ML111881113 (33)
	v • d • e

Appendix D Scenario Outline May, 2011 Form ES-D-1 j:

Facility: Oconee Scenario No.: I Op-Test No.: I Examiners: Operators:

Initial Conditions:

. Reactor Power = 75%, Unit 2: 100%, Unit 3: 100%

Turnover:

. AMSAC/DSS bypassed for l&E testing

. SASS in Manual for l&E testing

. KHU-1 is aligned to the underground path

. Perform Control Rod movement PT (Group 1 only) per PT/i /A/0600/015 (Control Rod Movement At Power) beginning at Step 3.3 Enclosure 13.2 Event No.

Malfunction No.

J Event Type* Event j_______________ Description Oa Pre-Insert AMSAC!DSS Bypassed Ob Pre-Insert SASS in Manual Oc Pre-Insert A AFIS Circuit Disabled Updater B AFIS Circuit Disabled Od Pre-lnsert ES Channels 7 and 8 Fail To Actuate Updater 1 N; OATC, SRO Control Rod Movement PT (Group 1 only) 2 MPS36O C; BOP, SRO 1 HP-31 Fails OPEN in AUTO 3 Updater C; BOP, SRO Operating LPSW Pump Trips, Standby LPSW Pump Fails (TS) To Auto Start 4 MCSOO4 I; OATC, SRO Controlling Tave Fails HIGH 5 C; BOP, SRO 1D1 HDP Low Oil Level 6 MCRO22 C; OATC, SRO Dropped Control Rod, Manual Power Reduction (TS) 7 MSS36O M; ALL 1A MSLB In Containment Override 8 MSS27O lB MDEFDW Pump Trips (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-i Op-Test No.: Scenario No.: I Event No.: I Page 1 of 3 Event

Description:

Control Rod Movement PT (Group I only) (N; OATC, SRO)

Time Position Applicants Actions or Behavior SRO Direct the OATC to perform Control Rod movement PT (Group 1 only)

PT/1/A10600/015 Enclosure 13.2 (Control Rod Movement At Power

) beginning at step 3.3 PTIIIAIO600IOI5 Enclosure 13.2 at Step 3.3 SRO!OATC NOTE: When operating switches on Diamond, maintain switch depres sed until light indication changes state.

3.3 Perform the following: (R.M.)

. Ensure SEQ OR is ON.

. Ensure SAFETY RODS OUT BYPASS is ON.

. Ensure RUN is ON.

. Ensure SINGLE SELECT SWITCH selected to ALL.

NOTE: CRD Groups 1-6 are required to be 95% withdrawn for Shutdown Margin Calculation at Power enclosure of PT/i/Ni 103/015 (Reactivity Balanc e

Procedure) to be valid.

3.4 IF AT ANY TIME y CRD Group 1-6 reaches 95% during insertion, stop inserting associated group. (R.M.)

3.5 Perform the following to test CRD Group 1: (R.M.)

3.5.1 Ensure GROUP SELECT SWITCH to 1 3.5.2 Ensure Group 1 CONTROL ON lights are ON. (P1 panel)

NOTE:

1SA-21C-10 CRD Safety Rods Not At Upper Limit will alarm when Safety Groups are inserted.

Control rods should NOT be left inserted. Rod withdrawal should commence immediately after insertion is complete.

3.5.3 Perform the following:

A. Insert CRD Group 1 B. WHEN all 100% lights OFF, stop insertion C. Begin Group 1 withdraw to 100%

Note: ISA2IC-1O CRD Safety Rods Not At Upper Limit will alarm when Group I Control Rods are inserted.

Page 2 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No. Scenario No.: I Event No.: I Page 2 of 3 Event

Description:

Control Rod Movement PT (Group I only) (N; OATC, SRO)

PTIIIAIO600IOI5 Enclosure 13.2 SRO!OATC NOTE: In RUN speed, all rod motion is inhibited 12 seconds after first rod reaches OUT LIMIT.

D. WHEN OUT LIMIT is ON, maintain WITHDRAW until CRD TRAVEL Out light OFF 3.5.4 Verify all 100% lights are ON for Group 1 (P1 Panel) 3.5.5 Verify unit is stable Note: Steps 3.6 through 3.12.5 are NAd 3.13 Perform the following: (R.M.)

Ensure SEQ is ON

Ensure GROUP SELECT SWITCH to OFF

Ensure SAFETY RODS OUT BYPASS is OFF 3.14 Return Rx Diamond and FDW Masters To Automatic per OP/i/Ni 102/004 A (ICS Operation)

OP/1/N1102/004 A End 4.1 (Placing Rx Diamond/FDW Masters To Hand) 2.8 WHEN required, place ICS back in auto as follows:

2.8.1 Ensure RATE SET thumbwheels at 0.0 2.8.2 IF TURBINE MASTER is in manual, perform the following:

Note: Step 2.8.2 is N/A 2.8.3 IF DIAMOND is in manual, perform the following:

A. Verify REACTOR MASTER in AUTO B. IF both SGs are off of Level Control, perform the following:

1. IF selected Tave (01 E2086) is different from Tave setpoint (01E2087) by more than +/- 0.15°F, on REACTOR MASTER adjust Tave setpoint (01 E2087) toward selected Tave (01 E2086)

2. Verify selected Tave is within +/- 0.15°F of Tave setpoint Page 3 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-l Op-Test No.: Scenario No.: I Event No.: I Page 3 of 3 Event

Description:

Control Rod Movement PT (Group I only) (N; OATC, SRO)

OP/i/Ni 102/004 A End 4.1 (Placing Rx Diamond/FDW Masters To Hand)

SRO/OATC C. f either SG is on Level Control, adjust Tave setpoint (01 E2087) to 579°F D. Place DIAMOND in AUTO 2.8.4 Ensure STM GENERATOR MASTER in AUTO 2.8.5 IF either 1A OR 1 B FDW Master is in HAND, perform the following:

A. Perform the following:

Select 1A FDW MASTER to MEAS VAR

Select 1 B FDW MASTER to MEAS VAR B. IF either 1A OR 1 B FDW Master Measured Variable is NOT on the caret, notify SPOC to investigate and repair the problem C. Verify the following:

1A FDW MASTER Measured Variable on the caret

lB FDW MASTER Measured Variable on the caret D. Perform the following:

Select 1A FDW MASTER to POS

Select 1 B FDW MASTER to POS E. Simultaneously perform the following:

Select 1A FDW MASTER to AUTO

Select 1 B FDW MASTER to AUTO 2.9 IF required slowly adjust Tave setpoint to 579°F (01 E2087) 2.10 IF desired adjust CTP as follows:

Note: Step 2.10 is not required for this scenario.

When ICS has been returned to AUTO, or when directed by the Lead Examiner, this event is complete.

Page 4 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: I Event No.: 2 Page 1 of 1 Event

Description:

IHP-31 Fails OPEN (C; BOP, SRO)

Time__[ Position Applicants Actions or Behavior Plant response:

1 SA2/B-2 (HP RCP Seal Inlet Header Flow High/Low) (42 gpm)

Crew response:

Refer to ARC for ISA-21B-2:

SRO/BOP 3.1 High Alarm 3.1.1 Verify high seal flow conditions with individual RCP seal indications 3.1.2 1HP-31 may have failed open/mid-position. Take manual control of IHP-31 and throttle to maintain 32 gpm.

Refer to AP/1/A/1700/022 (Loss Of Instrument Air) as required

Refer to AP/1/N1700/023 (Loss Of lOS Power) as required.

3.1.3 IF flow CANNOT be reduced in above manner, adjust 1HP-31 (RCP Seal Flow Control) per OP/i/A/i 104/002 (HPI system)

Note: The SRO may initially refer to APII4 (Loss of Normal Makeup and/or Seal Injection) and/or APII6 (Abnormal RCP Operation).

When Seal Injection flow is manually reduced to 32 gpm, or when directed by the Lead Examiner, this event is complete.

Page 5 of 33

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: I Event No.: 3 Page 1 of 2 Event

Description:

Operating LPSW Pump Trips, Standby LPSW Pump Fails to Auto Start (C; BOP, SRO) (TS)

_Time Position Applicants Actions or Behavior Plant response:

Statalarms:

1 SA-9/A-9 (LPSW Header A Press Low)

OAC Alarm:

LPSW HDR Pressure LO LO

LO LO RCP MTR Cooler Inlet HDR LPSW Control board indications:

LPSW Header A/B Pressure Low Crew response:

SRO/BOP

Refer to OAC alarm response

1. If Standby LPSW doesnt start automatically, then start manually.

2. Refer to AP/24 (Loss of LPSW)

3. Notify engineering

4. RefertoTS3.7.7

Refer to ARG for 1 SA-9/A-9 (LPSW Header A/B Press Low) 3.1 Refer to AP/1/A/1700/024 (Loss of LPSW) 3.2 Have Unit 2 refer to AP/2/AI1 700/024 (Loss of LPSW).

Booth Cue: If notified to refer to AP/2/A/1700/024, in form operator that AP/2/A/1700/24 will be referenced immediately.

AP/1/A/1700/024 (Loss of LPSW)

Entry Conditions:

Loss of or degraded LPSW operation as indicated by jy of the following:

LPSW header pressure low STATALARM

LPSW header pressure LO-LO OAC alarm

Automatic Start of Standby LPSW Pump Page 6 of 33

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: I Event No.: 3 Page 2 of 2 Event

Description:

Operating LPSW Pump Trips, Standby LPSW Pump Fails to Auto Start (C; BOP, SRO) (TS)

Time Position Applicants Actions or Behavior Crew Response:

SRO!BOP AP/1 IA/i 700/024 (Loss of LPSW)

NOTE Unit 1 normally handles LPSW System operation unless otherwise directed by the CR SRD 4.1 Verify Unit 1 is going to handle LPSW system operations.

4.2 IAAT any LPSW pump is cavitating, THEN perform Steps 4.3 4.4 RNO: GO TO Step 4.5 4.5 Start available (NOT previously cavitating) LPSW pumps, as necessary, to raise LPSW header pressure.

4.6 IAAT LPSW to all RBCUs has been isolated, AND LPSW header pressure is > 25 psig, THEN perform Step 4.7 RNO: GO TO Step 4.8 4.8 Verify normal LPSW System operation is restored.

4.9 Verify that RB Auxiliary Coolers have isolated:

RNO: GOTOStep4.11 4.11 EXIT this procedure The SRO should refer to TS:

TS 3.7.7 (Low Pressure Service Water System) Condition A applies.

Restore required LPSW pump to operable status. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months completion time.

TS 3.3.28 (LPSW pump Auto-Start Circuitry) Condition A. Restore Auto-Start Circuitry to operable. 7 day completion time.

Note: TS 3.3.28 entry not required for an operating pump.

Event is complete when the SRO has referred to TS or when directed by the Lead Examiner.

Page 7 of 33

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: I Event No.: 4 Page 1 of 3 Event

Description:

Controlling Tave Failed HIGH (I; OATC, SRO)

_Time_j Position Applicants Actions or Behavior Plant Response:

1SA-02/A-12 (ICS Tracking) will actuate due to neutron and feedwater cross-limits.

Controlling Tave will indicate 596.4°F.

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

RCS pressure and temperature will decrease.

SRO/OATC Crew Response:

When the Statalarms are received, the candidates should utilize the Plant Transient Response 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 BOP reports no valid run back and monitors RCS pressure and inventory and inserts Control Rods as needed.

The SRO should:

> Refer to AP!28 (ICS Instrument Failures)

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

Refer to AP/1 IA/i 700/028 (ICS 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. If at the pre-transient or allowable level, band is NI Power 1%.

Current Tave +/- 2°F

Current SG Outlet Pressure +/- 10 PSIG

DeltaT0°F+/-2°F 4.2 Initiate notification of the following:

OSM to reference the following:

> OMP 1-14 (Notifications)

Emergency Plan

STA Page 8 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: I Event No.: 4 Page 2 of 3 Event

Description:

Controlling Tave Failed HIGH (I; OATC, SRO)

Time Position Applicants Actions or Behavior Crew Response:

SRO/OATC 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

QAC display points

Control Board indications

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

J Section Failure 4A RCS Temperature Section 4A (RCS Temperature Failure) is continued on the next page.

Page 9 of 33

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: I Event No.: 4 Page 3 of 3 Event

Description:

Controlling Tave Failed HIGH (I; OATC, SRO)

Time Position Applicants Actions or Behavior Crew Response:

SRO/OATC NOTE

If Tave instrument circuit failed high, the following may have occurred depending on initial lOS station status:

Unit to TRACK due to Rx Cross Limits

Control Rod insertion

Feedwater flow increase

If Tave instrument circuit failed low, the following may have occurred depending on initial ICS station status:

Unit to TRACK due to Rx Cross Limits

Control Rod withdrawal

Feedwater flow decrease

Feedwater re-ratio

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.

When the SRO reaches the WHEN step (6) in Section 4A, or when directed by the Lead Examiner, this event is complete.

Page 10 of 33

Appendix D Scenario Outflne Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: I Event No.: 5 Page 1 of 1 Event

Description:

IDI HDP Low Oil Level (C; BOP, SRO)

E Time_T__Position Applicants Actions or Behavior Plant Response:

OAC Alarms:

HDP 1D1 MTR Lower Bearing Temp Hi-Hi

HDP 1D1 Thrust Bearing Temp Hi Crew Response:

SRO!BOP Refer to the OAC Alarm Response:

Remove the pump from service per OP/i/Ni 106/002 D (HDP Operation)

Booth Cue: If an NEO is sent to look at the HDP, use time compression and report as an NEO, that the lower oil sight glass of the IDI HDP is empty. The oil has been contained in the HDP sump and cleanup is in progress.

SRO should direct BOP to secure the 1D1 HDP per OP/1/N1106/002 D.

SPOC should be notified to investigate and repair the oil leak.

The BOP should secure the 1D1 HDP per OP/1/A11106/002 D Enclosure 4.4 (Shutdown of 1D1 HDP).

2.1 Verify CTP DEMAND 87%

3.1 Stop 1D1 HTR DRN PUMP 3.2 Verify 1HD-190 (1D1 Flash Tank Emer Level Control) opens by observing computer indication (01 D2092) 3.3 Verify 1HD-208 (1D1 HDP RECIRC) switch in AUTO 3.4 IF 1D1 HD pump breaker is no longer required, rack out 1TE-7 (1D1 Heater Drain Tank Pump Mtr)

Note: The SRO may determine that tagging the 101 HDP breaker is not required at this time.

Note: The SRO may refer to RPIOIBII 0001017 (Spill Response) and/or request the TBS breakers to be opened due to the HOP oil leak.

Booth Cue: If asked, Unit 2 will implement RP/O/B/1000/017 (Spill Response).

Note: If the crew fails to secure the I DI HDP in a timely manner, it will automatically trip 12 mm after the crew receives the high bearing temperature OAC alarms.

When the 101 HOP has been secured, or when directed by the Lead Examiner, this event is complete.

Page 11 of 33

Appendix D Scenario Outine Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: I Event No.: 6 Page 1 of 4 Event

Description:

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

_Time Position

] Plant Response:

ApplicanVs Actions or Behavior Statalarm 1SA2/A10 (CRD GLOBAL TROUBLE)

Statalarm 1SA2/B1O (CRD ASYMMETRIC ROD POSITION ERROR)

Statalarm 1SA2/D9 (CRD OUT INHIBIT)

Statalarm 1 SA4/C1 (QUADRANT POWER TILT) (alarms in 2 minutes)

Crew Response:

SRO/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.

SRO should enter AP/1/A11700/001 (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:

q 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 700/001 Page 12 of33

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: I Event No.: 6 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 AP/1 IA/i 700/001 Section 4H

1. IAAT more than one control rod is dropped or misaligned 6.5% (9) from the group average, THEN trip the Rx NOTE NIs should NOT be calibrated per guidelines contained in OP/i/A/I 102/004 due to actual power re-distributed within the core as a result of a dropped/misaligned rod.

2. Verify Rx is critical

3. 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 1 EOP

4. Initiate End 5.1 (Control of Plant Equipment During Shutdown) (page 4)

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.

5. Notify SPOC to perform the following:

6. 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)

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

Page 13 of 33

Appendix D Scenario Outline Form ES-D-l May, 2011 Op-Test No.: Scenario No.: I Event No.: 6 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/1/A11700/001 Section 4H

8. Verify> 1% SDM with allowance for the inoperable control rod per PT/1/A11103/015 (Reactivity Balance Calculation) within one hour

9. 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.

10. IAAT the power decrease is complete, AND any NI is > the following:

J RCPs Maximum NI Power

(%FP) 3 40 4 55 THEN reduce power until all Nis are the Maximum NI Power limit for the operating RCP combination

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

Old RPS System AM/0/A 030 1/003 U (Procedure to Reset the Flux/Imbalance/Flow and High Flux Trips for Operation with Excessive Power Tilt, Dropped Control Rod Or Other Conditions)

When the SRO reaches WHEN Step II, or when directed by the Lead Examiner, this event is complete.

Page 14 of 33

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: I Event No.: 6 Page 4 of 4 Event

Description:

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

_Time Position

] Crew Response:

Applicants Actions or Behavior AP/1/A/1700/001 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:

1N1B FDWP SEAL INJECTION PUMP

lA/lB FDWP AUXILIARY OIL PUMP

4. WHEN CTP 80%,

THEN stop 1E1/1E2 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 1 B FDWP is the preferred pump to shut down first.

7. Verify both Main FDWPs operating.

8. Verify lB FDWP to be shut down first.

9. Adjust the FWP bias counter-clockwise to lower 1 B FWP suction flow 1 x E6 lb/hr < 1A FWP suction flow.

10. GO TO Step 12

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

lB Main FDW pump is first pump to be shut down 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 Page 15 of 33

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: I Event No.: 7 Page 1 of 16 Event

Description:

IA Main Steam Line Break in RB (M; ALL)

Time Position Applicants Actions or Behavior Plant response:

Statalarm 1SA-021A-9 (MS PRESS HIGH/LOW)

A and B Main Steam (MS) Line pressure decreases until the turbine stop valves are closed Reactor trips:

A MS line pressure continues to decrease

B MS line pressure stops decreasing Crew response:

SRO Refer to EOP The SRO will direct the OATC will 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 3.5 Verify RCP seal injection available The OATC and SRO verify IMAs The SRO directs the BOP to perform a Symptoms Check Note: If Subcooling Margin is lost during this event, Rule 2 will be performed. As a contingency, Rule 2 actions are listed on pages 14-16.

BOP performs Rule #5 (Main Steam Line Break) after receiving concurrence from the SRO (see page 6)

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) (see page II)

The SRO will direct EHT Tab actions (see next page)

Note: ES Channels 7 & 8 will not automatically actuate when RB pressure increases above 10 psig. The SRO may direct an RO to manually actuate ES Channels 7 & 8 or allow the operator to actuate the channels per EOP Enclosure 5.1 (ES Actuation)

Page 16 of 33

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: I Event No.: 7 Page 2 of 16 Event

Description:

IA Main Steam Line Break in RB (M; ALL)

[Timf Position Applicants Actions or Behavior Crew Response:

EOP Excessive Heat Transfer Tab (EHT)

SRO 1. Verify any 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 fl affected SGs:

1 FDW-32 and 1 FDW-35

4. Close the following on fl affected SGs:

1FDW-372, IMS-17, 1MS-79, 1MS-35, 1MS-82, 1MS-368

5. Verify level in SOs <96% OR.

6. IAAT core SCM is > 0°F, THEN perform Steps 7 and 8

7. Throttle HPI per Rule 6 (HPI)

8. Verify letdown in service RNO: IF desired to restore letdown, THEN initiate End 5.5 (Pzr and LDST Level Control)

9. Verify y SO has an intact secondary boundary (intact SO)

NOTE If only one SG is intact and has been isolated for SGTR, the following step will unisolate and use it for heat removal.

10. Open the following on aH intact SGs

1 FDW-382 and 1 FDW-369

11. Start MDEFDWP associated with aM intact SGs

1BMDEFDWP RNO: Start TDEFDWP

12. Feed and steam aM intact SGs to stabilize RCS P/T using either of the following: (CT-li)

TBVs

Dispatch two operators to perform End 5.24 (Operation of the ADVs Page 17 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: I Event No.: 7 Page 3 of 16 Event

Description:

IA Main Steam Line Break in RB (M; ALL)

I Time_j Position

[ Crew Response:

Applicants Actions or Behavior SRO EOP Excessive Heat Transfer Tab

13. GO TO Step 32

32. Verify jy 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 1SSH-9

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 the following exist:

ES Bypass Permit satisfied

AIISCMs>0°F

RCS pressure controllable THEN bypass ES as necessary

40. Verify any SG is dry Page 18 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: I Event No.: 7 Page 4 of 16 Event

Description:

IA Main Steam Line Break in RB (M; ALL)

Time Position Applicants Actions or Behavior Crew Response:

SRO EOP Excessive Heat Transfer Tab

41. Minimize SCM using the following methods as necessary: (CT-7)

De-energize all Pzr heaters

Use Pzr Spray

Throttle HPI to maintain Pzr level> 100 [180 acc}

PORV

42. Verify any RCP operating

43. Maintain RCP NPSH

OAC

Encl5.18

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

NOTE RCP 1A1 provides the best Pzr spray

45. IAAT all the following exist:

<one RCP operating in any loop

All SCMs > 0°F

RCP available in an idle loop THEN initiate End 5.6 (RCP Restart) to start one RCP in each idle loop

46. IAAT the following exist:

RBS actuated

RB pressure < 10 psig

1 RIA-57 NOT in alarm

1 RIA-58 NOT in alarm THEN stop both RBS pumps

47. IAAT ToId approaches 400°F, AND aH RCPs are operating, THEN ensure <four RCPs are operating Page 19 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: I Event No.: 7 Page 5 of 16 Event

Description:

IA Main Steam Line Break in RB (M; ALL)

_Time Position Applicants Actions or Behavior Crew Response:

SRO EOP Excessive Heat Transfer Tab

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

49. Verify all SCMs> 0°F.

50. Verify indications of SGTR 25 gpm RNO: GO TO Step 52

52. Verify required RCS makeup flow within normal makeup capability.

53. Verify either of the following:

y SG isolated

jy SG has an unisolable steam leak

54. GO TO FCD tab EOP Forced Cooldown Tab (FCD)

1. IAAT cooldown rate CANNOT be controlled within Tech Spec limits:

To)d> 280° F: 50°F / 1/2 hr

TcoId 280°F: 25°F / Y2 hr THEN GO TO EHT tab

2. Verify letdown in service

3. Establish and maintain appropriate level per Rule 7 (SG Feed Control) and pressure in available intact SGs

4. IAAT TcoId approaches 400°F, AND all RCPs are operating, THEN ensure <four RCPs are operating

5. IAAT all the following exist:

ES Bypass Permit satisfied

_All SCMs >0°F RCS pressure controllable THEN bypass ES When the SRO transfers to the Forced Cooldown (FCD) Tab of the EOP, or when directed by the Lead Examiner, this event is complete.

Page 20 of 33

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: I Event No.: 7 Page 6 of 16 Event

Description:

IA Main Steam Line Break in RB (M; ALL)

_Time_j Position J Crew Response:

Applicants Actions or Behavior 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)

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: (CT-Il)

TBVs

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

CAUTION Thermal shock conditions may develop if HPI is NOT throttled and RCS pressure NOT controlled.

8. WHEN all of the following exist: Core SCM >00 F, Rx Pwr 1%, and Pzr Level increasing, THEN perform the following to stabilize RCS PIT:

Throttle HPI

Reduce 1 HP-i 20 setpoint to> 100 (180 ACC)

Adjust steaming of unaffected SG (1A SG) to maintain CETCs constant (CT-Il)

Page 21 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: I Event No.: 7 Page 7 of 16 Event

Description:

IA Main Steam Line Break in RB (M; ALL)

_Time_1 Position 1 Crew Response:

Applicants Actions or Behavior EOP Rule 5

9. WHEN CETCs have stabilized, THEN resume use of T for RCS temperature control

10. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete 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 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, 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 operati on if EFDW valve is desired to control flow/level, THEN perform Steps 38-42 RNO: GO TO step 43

43. Verify any SCM 0°F RNO: IF overcooling or exceeding limits in Rule 7, THEN throttle EFDW as necessary.

Page 22 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: I Event No.: 7 Page 8 of 16 Event

Description:

IA Main Steam Line Break in RB (M; ALL)

A_Time Position Applicants Actions or Behavior Crew Response:

EOP Rule 3

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

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 aH 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: GO TO Step 12 Page 23 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-l Op-Test No.: Scenario No.: I Event No.: 7 Page 9 of 16 Event

Description:

IA Main Steam Line Break in RB (M; ALL)

Time Position Applicants Actions or Behavior Crew Response:

EOP Enclosure 5.9 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 1C-lO 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 and 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.

EOP Rule 3 Continued

45. WHEN directed by CR SRO, THEN EXIT this rule EOP Rule 5 Continued

11. Ensure Rule 8 (Pressurized Thermal Shock (PTS)) is on progress or complete

12. WHEN directed by CR SRO, THEN EXIT this rule Note: When Rule 5 is complete, the I B MDEFDW pump will trip. This will require Rule 3 to be reinitiated to start the TD EFDW pump to feed the lB SO.

When the team determines that the I B MDEFDW pump has tripped the SRO should direct that Rule 3 be re-performed. The SRO could also direct the performance of a Symptoms Check in which case the TO EFWP could be started per the Symptoms Check. Rule 3 should still be performed.

Page 24 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: I Event No.: 7 Page 10 of 16 Event

Description:

IA Main Steam Line Break in RB (M; ALL)

_Time_J Position Applicants Actions or Behavior Crew Response:

EOP Rule 3 (After lB MD EFDWP trips)

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/GB P/Emergency),

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, as required, to feed all intact SGs.

5. Verify y EFDW pump operating.

6. GO TO Step 37

37. IAAT an EFDW valve CANNOT control in AUTO OR manual operati on if EFDW valve is desired to control flow/level, THEN perform Steps 38-42 RNO: GO TO step 43.

43. Verify any 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 25 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: I Event No.: 7 Page 11 of 16 Event

Description:

IA Main Steam Line Break in RB (M; ALL)

__Time Position

[ Crew Response:

Applicants Actions or Behavior EOP Enclosure 5.1 (ES Actuation)

1. Determine aH 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: Actuate affected ES digital channels.

Note: The RO actuates ES Channels 7 & 8

3. IAAT additional ES actuation setpoints are exceeded, THEN perform Steps 1-2.

4. Place HPI in manual control.

5. Verify Rule 2 in progress or complete.

RNO: GO TO Step 66.

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

67. Ensure at least two HPI pumps are operating

68. Verify 1HP-26 and 1HP-27 are open

69. IAAT at least two HPI pumps are operating, AND HPI flow in y header that has NOT been intentionally throttled is in the Unacceptable Region of Figure 1, THEN open the following in the affected header:

I lAHeader q lB Header 1HP-410 1HP-409

70. Verify any RCP operating

71. Open 1HP-20 and 1HP-21

72. IAAT gy RCP is operating, AND ES Channels 5 and 6 actuate, THEN perform Steps 73-75 Page 26 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: I Event No.: 7 Page 12 of 16 Event

Description:

IA Main Steam Line Break in RB (M; ALL)

_Time Position Applicants Actions or Behavior Crew Response:

EOP Enclosure 5.1 (ES Actuation)

73. Open the following:

1CC-7 1CC-8 1LPSW-15 1 LPSW-6

74. Ensure only one CC pump operating

75. Ensure Standby CC pump in AUTO

76. IAAT ES Channels 3 & 4 are actuated, THEN GO TO Step 77

77. Place the following in manual control CAUTION LPI pump damage may occur if operated in excess of 30 minutes against shutoff head

78. IAAT jj LPI pump is operating against shutoff head, THEN at the CR SROs discretion, stop affected LPI pumps

79. IAAT RCS pressure is < LPI pump shutoff head, THEN perform Steps 80-8 1 RNO: GO TO Step 82

82. IAAT 1A and 1 B LPI PUMPs are off/tripped, AND all of the following exists RNO: GO TO Step 85

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

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

87. Start A and B OUTSIDE AIR BOOSTER FANS Page 27 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.; Scenario No.; I Event No.; 7 Page 13 of 16 Event Description; IA Main Steam Line Break in RB (M; ALL)

__Time Position Applicants Actions or Behavior Crew Response:

EOP Enclosure 5.1 (ES Actuation)

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

89. Verify 1CF-1 and 1CF-2 are open

90. Verify 1HP-410 closed

91. Secure makeup to the LDST

92. Verify all ES channel 1-4 components are in the ES position

93. Verify Unit 2 turbine tripped RNO: GO TO Step 96

96. Close 1LPSW-139

97. Place 1LPSW-251 and 1LPSW-252 in FAIL OPEN

98. Start all available LPSW pumps

99. Verify either of the following; Three LPSW pumps operating Two LPSW pumps operating when TS only requires two operab le 100. Open 1LPSW-4 and 1LPSW-5 101. IAAT BWST level 19, THEN initiate End 5.12 (ECCS Suction Swap to RBES) 102. Dispatch an operator to perform End 5.2 (Placing RB Hydro gen Analyzers In Service) (PS) 103. Select DECAY HEAT LOW FLOW ALARM SELECT switch to ON 104. IAAT ES channels 5 & 6 have actuated, THEN perform Step 105 105. Verify aM ES channel 5 & 6 components in the ES position 106. IAAT ES channels 7 & 8 have actuated, THEN perform Step 107 107. Verify aM ES channel 7 & 8 components in the ES position 108. Notify U2 CR SRO that SSF is inoperable due to OTS1-1 open Page 28 of 33

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: I Event No.: 7 Page 14 of 16 Event

Description:

IA Main Steam Line Break in RB (M; ALL)

Time Position Applicants Actions or Behavior Crew Response:

EOP Rule 2 (if required)

1. IAAT all the following exist:

Any SCM 0°F Rx power 1%

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

2. Stop all RCPs

3. Notify CR SRO of RCP status

4. Verify Blackout exists RNO: GO TO Step 6

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

7. Start all available HPI pumps

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

9. Verify at least two HPI pumps operating, AND HPI flow in any header is in the Unacceptable Region of Figure 1 THEN perform Steps 11-13 RNO: GO TO Step 12

12. 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 1HP-409 open THEN throttle HPI to maximize flow flow limit Page 29 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: I Event No.: 7 Page 15 of 16 Event

Description:

IA Main Steam Line Break in RB (M; ALL)

Time Position Applicants Actions or Behavior Crew Response:

EOP Rule 2

13. Notify CR SRO of HPI status

14. Verify RCS pressure> 550 psig

15. IAAT either of the following 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 16 RNO: GO TO Step 27

27. IAAT TBVs are unavailable, THEN perform the follow ing:

28. Verify 1SA-2/C-8 (AFIS HEADER A INITIATED) lit

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

30. Verify y EFDW pump operating

31. Start MD EFDW pumps on aH intact SGs:

RNO: Start 1 TD EFDW PUMP

32. Verify jy EFDW pump operating

33. Verify both SGs intact RNO: 1. Establish 450 gpm EFDW flow to the intact SG

2. GO TO Step 35

35. Verify both MD EFDWPs operating RNO: 1. IF 1 TD EFDW PUMP is operating, OR NO Main FDW pumps operating, THEN GO TO Step 37

2. GOTO Step 39

37. Trip both Main FDW pumps Page 30 of 33

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: I Event No.: 7 Page 16 of 16 Event

Description:

IA Main Steam Line Break in RB (M; ALL)

_Time_j Position

] Crew Response:

Applicants Actions or Behavior EOP Rule 2

38. Place FDW block valve switches in CLOSE:

1 FDW-33 1 FDW-31 1 FDW-42 1 FDW-40 NOTE

SG levels must continue to increase until the SG Level Control Point is reached

If Main FDW is feeding any SG, Rule 7 provides a different SG Level Control Point

TS cooldown rates are 50°FP/2 hr when Tcojd > 280° F and 25°FIY2 hr when TcoId 280°F

39. Utilize Rule 7 (SG Feed Control) to feed all intact SGs to the appropriate SG Level Control Point using available feed sources

40. Notify CR SRO of SG feed status Page 31 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-1 CRITICAL TASKS

1. CT-7 Minimize SCM

2. CT-17 Isolate Overcooling SG(s)

3. CT-i 1 Control SG Pressure (adjust TBVs/ADVs) to Maintain RC Temperature Constant Page 32 of 33

Appendix D Scenario Outline May, 2011 Form ES-D-1 i SAFETY: Take a Minute UNIT 0 (OSM)

SSF Operable: Yes KHUs Operable: Ui UG, U2 OH

- - LCTs Operable: 2 Fuel Handling: No UNIT STATUS (CR SRO)

Unit I Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 75% Mode: 1 Mode: 1 Gross MWE: 681 100% Power 100% Power RCS Leakage: +.025 gpm (No WCAP action level) EFDW Backup: Yes EFDW Backup: Yes RBNS Rate: .01 gpm Technical Specifications/SLC Items (CR SRO)

Component/Train OOS Restoration TSISLC #

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

Shift Turnover Items (CR SRO)

Primary

. SASS in MANUAL for l&E testing

. AMSAC/DSS Bypassed for l&E Testing

. Power was reduced two hours ago per dispatche

r. Xenon is building in. Rx ENG is preparing a maneuvering plan.

. Perform Control Rod Movement PT (group 1 only) per PT/1/A10600/015 End 13.2 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.

Reactivity Management (CR SRO)

RCS Boron: 30 ppmB Gp 7 Rod Position: 80%

Human Performance Emphasis (OSM)

Procedure Use and Adherence Page 33 of 33

Appendix D Scenario Outline Form ES-D-l May, 2011 Facility: Oconee Scenario No.: 2 Op-Test No.: I Examiners: Operators: SRO OATC BOP Initial Conditions:

. Reactor power= 100%, Unit 2: 100%, Unit 3: 100%

Turnover:

. AMSAC!DSS Bypassed For I&E Testing

. SASS in Manual For I&E Testing

. Perform 5 Minute Delithiation Using Deborating IX Event Maif. No. Event Type* Event No. Description Oa Pre-Insert AMSAC/DSS Bypassed Ob Pre-Insert SASS in MANUAL Oc Pre-Insert All Turbine Trips Bypassed Od P re-Insert 182 RCP Fails to Trip From Switch 1 N; BOP, SRO 5 Minute Delithiation Using Deborating IX (OP/1103!04C)

Enclosure 4.4 2 Override C; BOP, SRO Seismic Event With 1A RBCU Rupture (TS) 3 MPI 281 © I; OATC, SRO zTc Controller Fails HIGH (A Loop Hot) 68%

4 MPS400 C; BOP, SRO, RCS Leak 135 gpm (TS) 5 R; OATC, SRO Manual Power Reduction Due to RCS Leak 6 C; OATC, SRO Turbine Fails to Trip Requiring EHC Pumps Lockout 7 MPS400 M; All SBLOCA (LOSCM to LOCA CD) 8 Override 1FDW-316 Fails Closed (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: 2 Event No.: I Page 1 of 2 Event

Description:

5 Minute Delith Using Deborating IX (0P111A111031004 C) (N; BOP, SRO)

Time Position Applicants Actions or Behavior Crew Response:

SRO Direct BOP to perform OP/I/All 103/004 C Enclosure 4.4 to place Unit 1 Deborating IX in service for a 5 minute Delith beginning at Step 2.8.

BOP BOP, uses the above procedure Enclosure 4.4 to place Unit 1 Deborating IX in service for a 5 minute Delith.

Procedure 2.8 While placing Unit 1 Deborating IX in service, monitor the following:

o Appropriate ranged Nis Primary tank levels Neutron error o CRD position IX run-time for proper chemistry control 2.9 Align Unit I Deborating IX for service:

2.9.1 Verify closed 1CS-32 & 37 (SPARE DEBOR IX INLET

& OUTLET) 2.9.2 Ensure closed 1 CS-26 (LETDOWN TO RC BHUT) 2.9.3 Open 1CS-27 (DEBOR IX INLET) 2.9.4 Verify 1 HP-iS Controller in MANUAL Ensure open 1HP-16 (LDST MAKEUP ISOLATION) 2.10 Position 1HP-i4 (LDST BYPASS) in BLEED to place Unit I Deborating IX in service NOTE:

Chemistry procedures require a minimum of 15 minute s flush for Deborating IXs (R.M.)

. Steps 2.11, 2.12, 2.13, and 2.14 nay be performed in any order 2.11 IF sample is desired AND Unit 1 Deborating IX will be in service for> 20 minutes, notify Chemist to begin flush for sample of Unit 1 Deborating IX effluent. (R.M.)

Page 2 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: 2 Event No.: I Page 2 of 2 Event

Description:

5 Minute Delith Using Deborating IX (0P111A111031004 C) (N; BOP, SRO)

Crew Response:

SRO!BOP 2.12 IF unexpected changes are noted, perform the following: (R.M.)

Continue enclosure to remove Unit 1 Deborating IX from service

Notify CR SRO for evaluation 2.13 IF AT ANY TIME RCS makeup is required for RCS volume control, perform Section 3 (RCS Makeup With Unit 1 Debo rating IX In Service) 2.14 IF AT ANY TIME desired to reduce inventory, reduce RCS inventory (Bleed):

2.14.1 Open 1CS-26 (LETDOWN TO RC BHUT) 2.14.2 WHEN complete, close 1CS-26 (LETDOWN TO RC BHUT) 2.15 IF sample is desired AND Unit 1 Deborating IX has been in service for>

20 minutes, prior to completing run time ensure Chem ist has sampled Unit 1 Deborating IX effluent (R.M.)

2.16 WHEN run time is complete, perform the follow ing:

2.16.1 Position 1HP-14 (LDST BYPASS) to NOR MAL

_2.16.2 Ensure closed 1HP-16 (LDST MAKEUP ISOLATION) 2.16.3 Perform one of the following: (R.M.)

Verify correct IX run time per Step 2.7

Notify Chemistry for evaluation 2.16.4 Reset 1 HP-I 5 Controller for Normal Oper ation 2.16.5 Close 1CS-27 (DEBOR IX INLET) 2.16.6 Open 1CS-26 (LETDOWN TO RC BHUT) 2.17 Record IX use in Auto Log When the crew reaches Step 2.17, or when directed by the Lead Examiner, this event is complete.

Page 3 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: 2 Event No.: 2 Page 1 of 2 Event

Description:

Seismic Event and IA RBCU Rupture (C; BOP

, SRO) (TS)

Time Position Applicants Actions or Behavior Booth Cue: After Delith is complete and at the direction of the Lead Evaluator, call the Control Room (4911) as a secu rity guard and state We have felt a tremor and have obse rved no plant damage.

Plant Response:

1 SA-9/B-9 (LPSW RBCU A Cooler Rupture)

Reactor Building Normal Sump level will increase Crew Response:

BOP

3. The BOP should refer to ARG for ISA-9/B-9 3.1 Verify alarm is valid by checking RBCU 1A Inlet Flow and RBCU IA i Flow.

3.2 Verify 1LPSW-18 (RBCU 1A OUTLET) open 3.3 Verify adequate LPSW flow is available; chec k 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 3.4 Monitor RBNS Level for any unexplained incre ase 3.5 IF RBNS Level is increasing AND ES has actua ted, notify Chemistry to sample the RBNS for boron concentra tion to determine if a cooler rupture has occurred based on sample results.

3.6 IF RBCU 1A Cooler rupture or line break is indic ated, 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 containm ent system.

D. Enter TS 3.6.5 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.

Page 4 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: 2 Event No.: 2 Page 2 of 2 Event

Description:

Seismic Event and IA RBCU Rupture (C; BOP

, SRO) (TS)

Time Position 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/Ni 104/010 (Low Pressure Serv ice Water).

3.6.5 Refer to OP/1/N1104/015 (Reactor Building Cooling System).

Refer To AP!OIA!1700/005, EARTHQUAKE:

SRO 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-i) and/

or (3SA-9, E-1)

Re-flash of computer alarm: SEISMIC RECORD ER (01 D0201) on Unit 1

Aftershocks felt at ONS or Keowee Hydro Stati on THEN GO TO Step 4.3 4.3 IAAT major visible damage is observed, THEN evaluate Rx trip on aH affected units.

4.4 Notify Keowee operating personnel to initia te AP/0/N2000/001 (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 enclo sures:

End 5.1 (Outside Inspections)

End 5.2 (AB Inspections)

End 5.3 (LPSW Inspections) 4.7 IAAT any 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 take over the completion of AP/5.

When the RBCU has been isolated, or at the direction of the Lead Examiner, this event is complete.

Page 5 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: 2 Event No.: 3 Page 1 of 2 Event

Description:

AT Controller Fails HIGH (A Loop Thot) (I; OATC, SRO)

[ Time

] Position Applicants Actions or Behavior Plant Response:

FDW flow will ratio incorrectly based on the failure

A FDW flow will increase causing A loop T 0 to decrease.

B FDW flow will decrease causing B loop T 0 to increase.

This will cause actual AT0 to increase (become more negative). Failure adjust FDW flow will result in QPT. to

1 SA-02/B-5, RC Cold Leg Duff. Temperature High, will actuate if actual AT 0

increases to +/- 5°F

1SA-02/B-9 MS STM GEN A LEVEL High/Low will actuate when SC Operating Level is 86%

Crew Response:

S RO/OATC

Crew should perform Plant Transient Response (PTR)

Diagnose the AT0 failure by observing the AT 0 meter on 1 UB1. It should return to zero but is staying at + 3.5 degr ees.

Take the Diamond and Feedwater Masters to MANUAL and re-ratio feedwater using the Loop T 0 meters and/or OAC (RCSO1) to return actual AT 0 to near zero.

SRO should direct the BOP to reference Statalarm 1 SA-02/B-5

SRO will refer to AP/28 (lOS Instrument Failures) 4.1 Provide control bands as required (per OMP 1-18 Attach I) 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 Page 6 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: 2 Event No.: 3 Page 2 of 2 Event

Description:

Controller Fails HIGH (A Loop Thot) (I; OATC, SRO)

Time 1 Position

] Applicants Actions or Behavior Crew Response:

4.6 GO TO the applicable section per the following table:

q Section Failure 4F Delta T AP!28 Section 4F NOTE

This section applies to Delta Tc controller failures.

Tc input signal failures are addressed in Section 4A The following may occur when an ICS Delta T controller fails:

Delta T controller may re-ratio loop FDW flows

Possible ICS RUNBACK

1. Ensure the following in HAND:

1A and lB FDW MASTERS DELTATC CAUTION Total feedwater flow should be maintained constant to prevent changes in core reactivity

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

3. Notify SPOC to perform the following:

Investigate and repair the failed Delta T 0 controller Booth Cue: When notified to investigate and repair the failed ZT controller, respond as SPOC and state that the zi T controller will be repaired as soon as possible.

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

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

When the SRO reaches the WHEN step (4) in Sect ion 4F, or when directed by the Lead Examiner, this event is complete.

Page 7 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: 2 Event No.: 4 Page 1 of 4 Event

Description:

RCS Leak 135 gpm: (C; BOP, SRO) (TS)

Time

[ Position Applicants Actions or Behavior Plant Response:

Alarms:

OAC RB Normal Sump Temp HI HI

1SA-9/A-6 (RB NORMAL SUMP HIGH/LOW)

1SA-8!B-9 (RM Process Monitor Radiation HIGH)

Control Board Indications

PZR and LDST level deceasing

RC makeup flow increasing

RB normal sump level increasing Crew Response:

SRO The SRO may refer to TS 3.4.13 (RCS Operational Leakag e) and determine that Condition A, Reduce leakage to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and Condition B, Be in MODE 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months are in effect. This is for an unidentified leak> 1 gpm.

Note: SRO may not refer to TS during the scenario due to other events occurring.

Note: The crew may determine that Immediate Manual Action Step 3.2 of AP/02 applies and close I HP-5 prior to the SRO enterin g APIO2.

Note: APIIIAII700IOI8 entry conditions will also be met due to RB RIA alarms. If the crew asks, Unit 2 will perform AP!18 (Abno rmal Release of Radioactivity) actions.

SRO enters AP/2 (Excessive RCS Leakage)

SRO!BOP AP!02 Immediate Manual Actions 3.1 Verify HPI operating 3.2 IAAT RC makeup flow is> 100 gpm, AND Pzr level is decreasing, THEN close 1 HP-5 Page 8 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: 2 Event No.: 4 Page 2 of 4 Event

Description:

RCS Leak 135 gpm: (C; BOP, SRO) (TS)

Time Position Applicants Actions or Behavior Crew response:

SROIBOP AP/2 (Excessive RCS Leakage) 3.3 IAAT all the following exist: (should not apply)

HPI flow is> NORMAL MAKEUP CAPABILITY letdown isolated

( 160 gpm) with Pzr level decreasing SG Tube Leakage NOT indicated LPI DHR NOT in service THEN perform the following:

A. Ensure Rx is tripped B. Initiate Unit 1 EOP AP/02 Subsequent Actions 4.1 Initiate Pzr and LDST level makeup using Unit 1 EOP End 5.5, as necessary (see page 4) 4.2 Announce AP entry using the PA system 4.3 IAAT LPI DHR in service, AND RCS leakage> LDST makeup capability ( 50 gpm) THEN GO TO AP/26 4.4 Initiate the following notifications:

OSM to reference the following:

RP/1000/O01 (Emergency Classification)

OMP 1-14 (Notifications)

End 5.9 (Oversight Guidelines)

_STA and RP 4.5 Monitor the following trends to determine leak area (AB or RB) and trend for degradation:

T6 APO2 T6 WASTE RIAs Page 9 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: 2 Event No.: 4 Page 3 of 4 Event

Description:

RCS Leak z 135 gpm: (C; BOP, SRO) (TS)

Time Position Applicants Actions or Behavior Crew response:

SRO!BOP 4.6 Verify specific leak location is identified Note: Crew should determine that the leak is in the Reactor Building due to RB RIAs increasing, RBNS rate increasing, and NO RCP seal failure indications and proceed to Step 4.53 4.7 Initiate End 5.1 (Leak Rate Determination)

Calculation of RCS Volume Loss from Enclosure 5.1:

LeakRate= + - -

MU SI LD TSR 4.8 WHEN leak area/failure is identified, THEN GO TO applicable step that best fits leak area/failure iJ Area! Symptoms Step Failure Rx Bldg t RB RIAs 4.53 RBNS rate NO RCP seal failure indications 4.53 IAAT in MODE 1 AND leak is> LDST mak eup capability from 1A BHUT, THEN initiate a shutdown using AP129 (Rapid Unit Shutdown)

Note: The 135 gpm leak is greater than LDST makeup capability from IA BHUT and the SRO should use AP129 to initiate a unit shutdown.

4.54 IAAT leak rate is 10 gpm, THEN discontinue pumping RBNS When the SRO has made the decision to shut down, or when directed by the Lead Examiner this event is complete.

Page 10 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: 2 Event No.: 4 Page 4 of 4 Event

Description:

RCS Leak 135 gpm: (C; BOP, SRO) (TS)

Time Position Applicants Actions or Behavior Crew response:

EOP Enclosure 5.5 (Pzr and LDST Level Control)

NOTE Maintaining Pzr level> 100 [180 acc] will ensure Pzr heate r bundles remain covered

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

1AHPIPump

lBHPlPump

1HP-26

1HP-27

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 secu re makeup from 1A BHUT

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

Open 1 CS-26 and 1 CS-41 Position 1HP-14 to BLEED Notify SRO

5. IAAT letdown bleed is NO longer desired, THEN positio n I HP-14 to NORMAL

6. IAAT iC HPI PUMP is required, THEN perform Step s 7-9 RNO: GO TO Step 10

10. IAAT LDST level CANNOT be maintained, THEN perform Step 11 RNO: GOTOStepl2

12. IAAT additional makeup flow to LDST is desired, AND IA BLLED TRANSFER PUMP is operating, THEN dispatch an operato r to close 1CS-48 Page 11 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: 2 Event No.: 5 Page 1 of 3 Event

Description:

Manual Power Reduction Due To RCS Leakage: (R; OATC, SRO)

Time Position ApplicanUs Actions or Behavior Crew Response:

SRO directs Unit shutdown per AP/29 (Rapid Unit Shutdow n):

4.1 Initiate End 5.1 (Support Actions During Rapid Unit Shut down)

(Details on page 3) 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 4.8 Verify ICS in AUTO RNO: 1. Initiate manual power reduction to desired pow er level.

2. GOTOStep4.10 4.10 Verify both Main FDW pumps running.

NOTE

1 B Main FDW Pump is the preferred pump to be shut down first.

To lower 1 B Main FDW Pump suction flow, bias is adjusted counter-clockwise.

To lower 1A Main FDW Pump suction flow, bias is adju sted clockwise.

4.11 Adjust bias for first Main FDW pump desired to be shutdown units suction flow is 1 X 106 Ibm/hr less than remaining Main FDW pump suction flow.

4.12 WHEN core thermal power is < 65% FP, THEN continue.

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

lB Main FDW Pump is first pump to be shut down.

jy of the following alarms occur:

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

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

THEN trip lB Main FDW Pump.

Page 12 of27

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: 2 Event No.: 5 Page 2 of 3 Event

Description:

Manual Power Reduction Due To RCS Leakage: (R; OATC

, SRO)

Time Position Applicants Actions or Behavior Crew Response:

4.14 IAAT both Main FDW pumps running, AND both of the following exists:

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

FWP A FLOW MINIMUM (1SA-16!A-1)

FWP A FLOW BELOW MIN (1 SA-1 6!A-2)

THEN trip 1A Main FDW Pump 4.15 Verify Turbine-Generator shutdown is required 4.16 Start the TURBINE TURNING GEAR OIL PUMP 4.17 Start lAthrough 1E TURBINE BRNG OIL LIFT PUMPS 4.18 Start the TURBINE MOTOR SUCTION PUMP 4.19 IAAT both of the following apply:

ICS in automatic

_NI power 18%

THEN deselect MAXIMUM RUNBACK 4.20 Verify Turbine-Generator shutdown is required 4.21 WHEN NI power 18%, THEN depress turbine TRIP pushbutton When a unit shutdown of> 10% has occurred and electrical Auxili aries have been transferred, and directed by the Lead Examiner this event is complete.

Page 13 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: 2 Event No.: 5 Page 3 of 3 Event

Description:

Manual Power Reduction Due To RCS Leakage: (R; OATC, SRO)

Time L Position

[ Applicants Actions or Behavior Crew Response:

BOP End 5.1 (Support Actions During Rapid Unit Shutdow n)

1. Notify WCC SRO to initiate End 5.2 (WCC SRO Suppo rt During Rapid Unit Shutdown)

2. Start the following pumps:

1A & lB FDWP Seal Injection Pumps 1A & 1 B FDWP Aux Oil Pumps

3. WHEN CTP <80%, THEN continue

4. Stop 1E1 HTR DRN PUMP

5. Place 1 HD-254 switch to OPEN

6. Stop 1E2 HTR DRN PUMP

7. Place 1 HD-276 switch to OPEN

8. Verify Turbine-Generator shutdown is required

9. Place 1TA & 1TB AUTO/MAN transfer switch in MAN

10. Close 1TA SU 6.9 KV FDR

11. Verify 1TA NORMAL 6.9 KV FDR opens

12. Close 1TB SU 6.9 KV FDR

13. Verify 1TB NORMAL 6.9 KV FDR opens

14. Place MFB1 and MFB2 AUTO/MAN transfer switches in MAN

15. Close El 1 MFB1 STARTUP FDR

16. Verify Ni1 MFB1 NORMAL FDR opens

17. Close 1 E2 MFB2 STARTUP FDR

18. Verify N21 MFB2 NORMAL FDR opens

19. Notify CR SRO that Unit auxiliaries have been transferred Note: Once electrical auxiliaries have been trans ferred, the scenario may continue.

Page 14 of27

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: 2 Event No.: 6 Page 1 of 1 Event

Description:

Turbine Fails To Trip Requiring EHC Pump Lockout: (C; OATC, SRO)

Note: Reactor will trip as a result of the SBLOCA in event 7.

Time

[ Position Applicants Actions or Behavior Plant response:

iSA-i/A-i, B-i, C-i, D-i, RP Channel Trip

iSA-2/D-3, RC Press High/Low

A SBLOCA will result in a reactor trip.

The Main Turbine should trip but does not. This will result in a reduction of steam pressure in both SGs until actions are taken to trip the turbine. This will result in RCS overcooling until the turbine is tripped Crew response:

SRO/OATC

SRO will enter the EOP by directing the OATC to perform Immediate Manual Actions or perform 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 Note: The OATC should diagnose that the turbine did not trip and then perform the RNO step which will stop and lock out both EHC pumps. This will cause the turbine to trip. (CT-18)

> Verify RCP seal injection available BOP

BOP will perform a symptom check (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 decr ease

> Steam Generator Tube Rupture o CSAE offgas alarms, process RIAs (RIA-40, 59, 60), area RIAs (RIA 16/17)

This event is complete when the Turbine has been manually tripped.

Page 15 of 27

Appendix D Scenario Outline May, 201 1 Form ES-D-l Op-Test No.: Scenario No.: 2 Event No.: 7 Page 1 of 8 Event

Description:

Small Break LOCA: (M; ALL)

Time Position

[ Plant response:

Applicants Actions or Behavior

Statalarms:

> 1 SA-8/B-9, Process Radiation Monitor High

Control board indications:

> PZR level will decrease due to the leak

> RCS pressure will decrease

> ES Channels 1&2 will actuate when RCS pressure is SRO < 1600 psig ES Channels 3-6 will actuate when RB pressure is

> 3 psig Crew response:

The SRO will refer to EOP Subsequent Actions Paralle l Actions page.

The SRO will receive Symptoms Check/Report from one of the ROs.

The SRO will transfer to the LOSCM Tab of the EOP.

(details on next page)

The SRO will determine that EDLs are in effect The SRO will direct one of the ROs to perform EOP End. 5.1 (ES Actuation)

(details on page 6)

Note: The RCS will eventually saturate with all HPI injecting.

The SRO will provide concurrence to the other RO to perform Rule 2 (Loss of Subcooling Margin) (details on page 4).

SRO EOPLOSCMTab

1. Ensure Rule 2 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: GO TO Step 6

6. IAAT either of the following exists:

LPI FLOW TRAIN A LPI FLOW TRAIN B 3400 gpm one LPI header in operation with header flow 2900 gpm THEN GOTO LOCA CD tab Page 16 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: 2 Event No.: 7 Page 2 of 8 Event

Description:

Small Break LOCA: (M; ALL)

Time

[ Position Applicants Actions or Behavior Plant response:

EOP LOSCM Tab SRO 7. Verify SSF activated per AP/25 RNO: GO TO Step 9

9. Verify aU of the following exist:

NO RCPs operating HPI flow in both HPI headers Adequate total HPI flow per Figure 1 (Total Required HPI Flow)

10. GO TO Step 89

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

90. Verify HPI forced cooling in progress

91. Close 1GWD-17, 1HP-1, 1HP-2, and 1RC-3

92. Verify either of the following:

Core superheated Rx Vessel head level at 0 RNO: GO TO Step 94

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

95. Maintain SG pressure < RCS pressure utilizing either of the following:

TBVs ADVs

96. Verify any SG available for feeding/steaming

97. Initiate End 5.16 (SG Tube-to-Shell L\T Control)

98. Verify indications of SGTR exist RNO: GO TO Step 101 101. Verify HPI forced cooling in progress RNO: GO TO Step 103 Page 17 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-l Op-Test No.: Scenario No.: 2 Event No.: 7 Page 3 of 8 Event

Description:

Small Break LOCA: (M; ALL)

Time j Position Applicants Actions or Behavior Plant response:

EOP LOSCM Tab SRO 103. Verify CETC5 trend decreasing 104. Verify primary to secondary heat transfer is exce ssive RNO: GOTO Step 106 106. Verify indications of SGTR 25 gpm RNO: GO TO Step 108 108. Verify required RCS makeup flow within normal makeup capability RNO: GO TO LOCA CD tab EOP LOCA CD Tab

1. IAAT BWST level is 19, THEN initiate End 5.12

2. Verify ES actuated

3. GOTOStep7

7. Place all RBCUs in low speed and open 1LPSW

-18, 21, and 24

8. Initiate End 5.35 (Containment Isolation)

9. Start all RB Aux fans

10. IAAT LPI flow is > 2900 gpm, THEN GO TO Step 11 RNO: GO TO Step 42

42. Initiate End 5.36 (Equipment Alignment For Plant Shutdown)

43. IAAT all the following exist:

_All SCMs >0°F RCS pressure> LPI shutoff head Required HPI within normal makeup capability THEN GO TO Step 44 RNO: GO TO Step 47 When the SRO transfers to the LOCA CD Tab, or when directed by the Lead Examiner, this event is complete.

Page 18 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: 2 Event No.: 7 Page 4 of 8 Event

Description:

Small Break LOCA: (M; ALL)

Time

[ Position Applicants Actions or Behavior Plant Response:

BOP Rule 2, Loss of Subcooling Margin (SCM)

1. Verify y SCM 0°F, Reactor power is 1%, and 2 minutes have elapsed since loss of SCM

2. Stop all RCPs (within 2 mEn of [05CM) (CT-I)

Note: 1B2 RCP will not trip from the switch. RNO will be performed to de-energize ITA and ITB (6.9KV switchgear).

Step 2 RNO

1. Place 1TA AUTO/MAN switch in MAN

2. Place 1TB AUTO/MAN switch in MAN

3. Open 1TA SU 6.9 KV FDR

4. Open 1TB SU 6.9 KV FDR

3. Notify CR SRO of RCP status

4. Verify a Blackout does not exist and GO TO Step 6

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

7. Start all available HPI pumps

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

9. Verify at least two HPI pumps are operating using two diverse indications

10. Verify HPI flow is acceptable and GO TO Step 12

12. Verify HPI pump flow limits are not being exceeded

13. Notify CR SRO of HPI status

14. Verify RCS pressure> 550 psig

15. Verify that LPI flow in both headers is <2900 gpm and GO TO Step 27

27. Verify TBVs are available

28. Verify 1 SA-2/C-8 is not lit and Select OFF for both digital channels on AFIS HEADER A

29. Verify 1 SA-2!D-8 is not lit and Select OFF for both digital channels on AFIS HEADER B

30. Verify y EFDW pump operating RNO: Place 1FDW-315 and 1FDW-316 in MANUAL and close Page 19 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-1 Op-Test No.: Scenario No.: 2 Event No.: 7 Page 5 of 8 Event

Description:

Small Break LOCA: (M; ALL)

Time Position

[ Plant response:

Applicants Actions or Behavior BOP Rule 2, Loss of Subcooling Margin (SCM)

31. Start lAand lB MD EFDW pumps on all intact SGs

32. Verify gy EFDW pump operating

33. Verify both SGs intact

34. Establish 300 gpm EFDW flow to 1A and 1 B SGs

35. Verify both MD EFDWPs operating

36. PLace 1 TD EFDW PUMP in PULL TO LOCK

37. Trip both Main FDW pumps

38. Place FDW block valve switches in CLOSE (1FDW-33, 1FDW-31, 1FDW-42, 1FDW-40)

39. Utilize Rule 7 (SG Feed Control) to feed all intact SGs to the appropriate SG Level Control Point using available feed sources (Main & EFDW) (CT-b)

40. Notify CR SRO of SG feed status

41. IAAT SG pressure is> RCS pressure, THEN reduce SG pressure < RCS pressure using TBVs

42. Verify no Main FDW pumps are operating and GO TO Step 49

49. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete (details on page 24 of the scenario)

Booth Cue: After Rule 3 is initiated, or when directed by the Lead Exami ner, FIRE TIMER 8 to fall IFDW-316 closed.

50. WHEN directed by CR SRO, THEN EXIT this rule Page 20 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 2 Event No.: 6 Page 6 of 8 Event

Description:

Small Break LOCA: (M; ALL)

Time

} Position f Crew Response:

Applicants Actions or Behavior When ES Channels 1 and 2 actuate, an operator should inform the SRO that ES Channels 1 and 2 have actuated.

The SRO should direct initiation of EOP End. 5.1, ES Actuation per the Parallel Actions page of Subsequent Actions or the LOSCM Tab.

OATC EOP Enclosure 5.1(ES Actuation)

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

2. Verify all ES digital channels associated with actuation setpoints have actuated

3. IAAT additional ES actuation setpoints are exceeded, THEN perform Steps 1 -2

4. Place HPI in Manual (RZ Modules).

5. Verify Rule 2 in progress or complete.

6. Determine NO RCPs operating and GO TO Step 8.

Note: ES Channels 1-thru-6 may actuate due to High Reactor Building Pressure; therefore, the ES Actuation Checklist may be performed in a staggered fashion as the various ES Channels are actuated.

8. Determine NO RCPs operating and GO TO Step 12

12. IAAT ES channels 3&4 are actuated, THEN GO TO Step 13

13. PlacelA and lB LPI pumps and 1LP-17/18 in manual control.

CAUTION LPI pump damage may occur if operated in excess of 30 minutes against a shutoff head.

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

15. IAAT RCS pressure < LPI pump shutoff head, THEN realign [P1 RNO: GOTO Step 18

18. IAAT 1A and lB LPI pumps are off/tripped align 1C LPI pump RNO: GO TO Step 21 Page 21 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 2 Event No.: 6 Page 7 of 8 Event

Description:

Small Break LOCA: (M; ALL)

Time Position Applicants Actions or Behavior Crew Response:

OATC EOP Enclosure 5.1 (ES Actuation)

21. IAAT 1A LPI pump fails while operating

22. IAAT 1 B LPI pump fails while operating

23. Start A and B OUTSIDE AIR BOOSTER FANS (C127)

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

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

26. Verify 1HP-410 closed

27. Secure makeup to the LDST

28. 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 1 HP-4 fails to close, THEN close 1 HP-2

3. Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired Note: I HP-4 is failed open and will not close. The operator should diagnose this and perform the RNO and close I HP-2 located on I UBI

29. Verify Unit 2 turbine tripped (Unit 2 turbine is online)

RNO: GO TO Step 32

32. Close 1LPSW-i39

33. Fail Open 1LPSW-25i/252

34. Start all available LPSW pumps

35. Verify three LPSW pumps operating

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

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

RNO: 1. Display BWST level using OAC Turn-on Code SHOWDIG O1P1600

2. Notify crew of BWST level IAAT step Page 22 of 27

Appendix D Scenario Outilne Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 2 Event No.: 6 Page 8 of 8 Event

Description:

Small Break LOCA: (M; ALL)

Time Position Applicants Actions or Behavior Crew Response:

EOP Enclosure 5.1 (ES Actuation)

OATC

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

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

40. IAAT ES channels 5 & 6 have actuated, THEN perform Step 41

41. Verify all ES channel 5 & 6 components are in the ES position

42. IAAT ES channels 7 & 8 have actuated, THEN perform Step 43 RNO: GO TO Step 44

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

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

46. WHEN CR SRO approves, THEN EXIT this enclosure Note: The operator must get SRO approval to exit this enclosure.

Page 23 of 27

Appendix D Scenario Outline Form ES-D-l May, 2011 Op-Test No.: Scenario No.: 2 Event No.: 8 Page 1 of 2 Event

Description:

IFDW-316 Fails Closed Time Position Applicants Actions or Behavior Crew response:

BOP Rule 3, Loss of Main or Emergency FDW:

1. Verify loss of Main FDW/EFDW is not due to Turbine Building Flood and GO TO Step 3

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

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 aM intact SGs

5. Verify y EFDW pump operating

6. GO TO Step 37

37. IAAT an EFDW valve CANNOT control in AUTO, OR manual operation of EFDW valve is desired to control flow/level, THEN perform Steps 38 42

38. Place EFDW valve in MANUAL

39. Control EFDW flow with EFDW valve in MANUAL Note: IFDW-316 is failed in the closed position and will not operate in AUTO or Manual. Candidate should then GO TO Step 41

41. Notify CR SRO that End 5.27 (Alternate methods for Controlling EFDW Flow) is being initiated.

42. Initiate End 5.27 Enclosure 5.27 (Alternate Methods for Controlling EFDW Flow)

1. Identify the failure as 1 FDW-316 failed closed and GO TO Step 39

39. Verify 1 B MD EFDWP operating

40. Stop lB MD EFDWP

41. Verify 1A MD EFDWP is operating

42. Place 1 TD EFDW PUMP in PULL TO LOCK Page 24 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 2 Event No.: 8 Page 2 of 2 Event

Description:

IFDW-316 Fails Closed Time Position Applicants Actions or Behavior Crew response:

Enclosure 5.27 (Alternate Methods for Controlling EFDW Flow)

43. Place 1 FDW-44 in HAND and set demand to 0%

44. Close 1 FDW-42

45. Verify 1 B MD EFDWP will be used

46. Open 1FDW-384

47. Verify 1 FDW-45 closed and 1 FDW-47 open

48. Start lB MD EFDWP NOTE

Flow from the TD EFDWP through a S/U control valve should be read on the FDW SU FLOW gauge

Flow from a MD EFDWP through a S/U control valve should be read on the MDEFWP DISCH FLOW gauge

49. Verify either of the following:

HPI Forced Cooling is maintaining core cooling

CBP feed providing SG feed RNO: 1. IF any SG is being fed, THEN perform the following:

A. Throttle 1 FDW-44 to establish 100 gpm B. Throttle 1 FDW-44 to obtain desired level per Rule 7 (SG Feed Control)

4. Notify CR SRO of SG feed status

5. GO TO Step 51

51. IAAT proper SG level is reached per Rule 7 (SG Feed Control), AND SG level permits auto level control, THEN place 1 FDW-44 in AUTO

52. WHEN directed by the CR SRO, THEN EXIT this enclosure This event is complete when feedwater flow has been established to the I B SG and the cooldown rate is controllable.

Page 25 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-1 CRITICAL TASKS

1. CT-18 TurbineTrip

2. CT-i Trip All RCPs

3. CT-i 0 Establish FDW Flow And Feed SC(s)

4. CT-27 Implementation Of Control Room Habitability Guidance Page 26 of 27

Appendix D Scenario Outline May, 2011 Form ES-D-l SAFETY: Take a Minute UNIT 0 (OSM)

SSF Operable: Yes KHUs Operable: Ui OH, U2 UG

- LOTs Operable: 2 Fuel Handling: No UNIT STATUS (CR SRO)

Unit I Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 100% Mode: 1 Mode: 1 Gross MWE: 902 100% Power 100% Power RCS Leakage: +.025 gpm (No WCAP action level) EFDW Backup: Yes EFDW Backup: Yes RBNS Rate: .01 gpm Technical SpecificationslSLC Items (CR SRO)

Component/Train OOS Restoration TS!SLC #

DatelTime Required DatelTime AMSAC!DSS Bypassed Today I 06:30 SLC 16.7.2 7 Days Conditions A & B Shift Turnover Items (CR SRO)

Primary

SASS in MANUAL for l&E testing

. AMSACIDSS Bypassed for l&E Testing

. Perform 5 minute Delithiation using the Deboratin g IX Secondary

1SSH-1, 1SSH-3, ISD-2, ISD-5, 1SD-140, 1SD-303

, 1SD-355, 1SD-356 and 1SD-358 are closed with power supply breakers open per the Start up Procedure for SSF Overcooling Event.

Reactivity Management (CR SRO)

RCS Boron: 30 ppmB Gp 7 Rod Position: 93%

Human Performance Emphasis (OSM)

Procedure Use and Adherence Page 27 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 Facility: Oconee Scenario No.: 3 Op-Test No.: I Examiners: Operators:

OATC BOP Initial Conditions:

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

Turnover:

. SASS in Manual For I&E Testing

. Pressurize the LDST With H 2 Event Maif. No. Event Type* Event No. Description Oa Pre-Insert SASS in MANUAL Ob Pre-lnsert AMSAC!DSS Bypassed 1 N; BOP, SRO Pressurize LDST With H 2 2 MSS200 C; BOP, SRO Vacuum Leak 3 Override C; OATC, SRO PZR Spray Valve (1 RC-1) Fails OPEN 4 MPI15O I; OATC, SRO PZR A RTD Fails LOW (TS) 5 C; BOP, SRO Spurious ES-3 Actuation (TS) 6 MCRO61 C; OATC, SRO Continuous Control Rod Withdrawal 7 M; ALL Blackout Requiring Manual Alignment From CT-5 CT-i Lockout KHU-1 Emergency Lockout KHU-2 Emergency Lockout 8 MPS400 M; ALL LBLOCA With Failure of 1 B LPI Pump (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Page 1 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: I Page 1 of 1 Event

Description:

Pressurize LOST with 2 H (N; BOP, SRO)

Time Position Applicants Actions or Behavior Crew response:

SRO/BOP

Refer to OP/i/All 106/017, Enclosure 4.5 (Unit 1 LDST H 2 Addition) to adjust LDST pressure beginning at Step 2.2.

2.2 Immediately prior to pressurization determine lowest reading of diverse LDST level indications: inches 2.3 For existing LDST level determine LDST Pressure allowable per LDST Pressure vs Level curve: psig 2.4 Notify Operator at H 2 Cage to pressurize primary hydrogen Booth Cue: Using TIME COMPRESSION, notify the operator that primary H 2 is aligned at the H2 cage.

NOTE: Operator should be in constant communication with CR to close I H-26 if I H-I fails open.

2.5 Direct Operator to open 1 H-26 (LDST Block) 2.6 Direct Operator to use explosive detector to monitor the following:

Pressurized, non-welded H 2 piping and fittings within local area of addition

Loop seal (A-2-N of LDST Rm)

Booth Cue: Using TIME COMPRESSION, notify the operator that IH-26 is open and H 2 monitoring is complete.

2.7 Cycle i H-i (LDST SUPPLY) as required to pressurize LDST per LDST Pressure vs Level curve 2.8 WHEN Hydrogen addition complete, ensure closed 1H-i (LDST SUPPLY) 2.9 Direct Operator to close 1 H-26 (LDST Block) 2.10 Ensure LDST pressure within LDST Pressure vs Level curve 2.11 Notify Operator at H 2 Cage to isolate primary hydrogen 2.12 Log LDST Hydrogen addition in Auto Log When LDST pressurization is stopped, or when directed by the Lead Examiner, this event is complete.

Page 2 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 2 Page 1 of 2 Event

Description:

Vacuum Leak (C; BOP, SRO)

Time Position Applicants Actions or Behavior Plant Response:

1 SA-031A-6 (COND VACUUM LOW)

QAC alarm, Main Condenser Vacuum LOW Crew response:

BOP Refer to Alarm Response Guide 1SA-03/A-6

1. Alarm setpoint

25 Hg vacuum decreasing

2. Automatic Action

None; however, Main Turbine trip setpoint is 21.75 Hg (not online for this scenario) and FWPT trip setpoint is 19 Hg 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 operating FDW pump will not trip.

3. Manual Action

Refer to AP/1/Al 700/027 (Loss of Condenser Vacuum)

Refer to AP/1/A/1 700/027 (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 IAAT of the following apply:

Condenser vacuum 22 Hg MODE 1 or2 THEN trip the Rx.

Page 3 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 rj Op-Test No.:

Event

Description:

Scenario No.: 3 Vacuum Leak (C; BOP, SRO)

Event No.: 2 Page 2 of 2 Time Position Applicants Actions or Behavior Crew response:

AP!1!N1700/027 (Loss of Condenser Vacuum) 4.3 Dispatch operators to perform the following:

Perform End 5.1 (Main Vacuum Pump Alignment)

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

4.4 Ensure afl 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 aR 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 the lB Main FDW Pump pumping trap sight glass and the leak has been isolated.

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 When the SRO reaches Step 4.10 of AP1027, or at the direction of the Lead Evaluator, this event is complete.

Page 4 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 3 Page 1 of 3 Event

Description:

PZR Spray Valve (IRC-1) Fails OPEN (C; OATC, SRO)

Time_] 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 1SA-21D-3 (RC PRESS HIGH/LOW) 3.2 Low Alarm 3.2.1 Refer to AP/1/A11700/044 (Abnormal Pressurizer Pressure Control)

SRO/OATC Refer to AP/1IAl 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 any 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 aN of the following conditions exist:

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

PZR level 375 THEN close 1 RC-4 Note: The crew may perform Immediate Manual Action Step 3.2 (next page) from memory prior to the SRO entering AP144.

Page 5 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 3 Page 2 of 3 Event

Description:

PZR Spray Valve (1RC-1) Fails OPEN (C; OATC, SRO)

Time Position Applicants Actions or Behavior Crew Response:

AP!1!A!17001044 (Abnormal Pressurizer Pressure Control) 3.2 IAAT aH 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 is not closed, the Reactor will trip on variable low pressure and ES actuation will occur.

Note: The PZR spray valve (1 RC-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.

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 1 RC-1 failed OPEN Page 6 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 3 Page 3 of 3 Event

Description:

PZR Spray Valve (IRC-1) Fails OPEN (C; OATC, SRO)

Time_J Position Applicants Actions or Behavior Crew Response:

4.6 Position the following to maintain RC pressure within desired band, as required:

1RC-1 1 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:

_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 foHowing components in desired position for current plant conditions as determined by CR SRO:

1RC-1 1RC-3 1 RC-4 PZR heater bank #1 PZR heater bank #2 PZR heater bank #3 PZR heater bank #4 When the RCS pressure decrease has been stopped and PZR level is stable, or when directed by the Lead Examiner, this event is complete.

Page 7 of 27

Appendix D Scenario Outline Form ES-D-l May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 4 Page 1 of 2 Event

Description:

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

Time Position Applicants Actions or Behavior Booth Cue: Call the BOP to request the following: This is the Secondary Chemist requesting the value of steam flow to the EHeaters (This will help to ensure the OATC will take actions for the PZR RTD failure)

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 133 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 1HP-l2Oto manual to control PZR level.

Page 8 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 4 Page 2 of 2 Event

Description:

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

Time Position Applicants Actions or Behavior Crew Response:

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

3.3 Refer to the following procedures as required:

AP!i/A/1700!002 (Excessive RCS Leakage)

AP/i/A/1700/014 (Loss of Normal HPI M/U and/or RCP SI)

AP/1/A/1700/032 (Loss of Letdown) 3.4 Refer to Technical Specification 3.4.9, Pressurizer 3.5 Refer to Technical Specification 3.3.8, PAM Instrumentation.

OATC/BOP

Condition A applies 3.6 Refer to OP/i/Ni 105/014 Enclosure 4.9, Control Room BOP Instrumentation Operation And Information, SASS Information.

OP/i/Ni 105/014 Enclosure 4.9 (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/AI1 105/014 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.

When PZR level 3 has been selected, or when directed by the Lead Examiner, this event is complete.

Page 9 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 5 Page 1 of 2 Event

Description:

Spurious ES Channel 3 Actuation (C; BOP, SRO) (TS)

Time Position

] Plant Response:

Applicants Actions or Behavior Statalarms:

iSA-i/C-b ES Channel 3 Trip Control Board Indications:

ES Channel 3 actuates on RZ Modules

1A LPI pump starts

1A LPI train aligns

A and C LPSW pumps start Crew Response:

1. Determine ES actuation not valid and inform the SRO

2. Crew may perform Plant Transient Response (PTR)

3. SRO enter AP/42 (Inadvertent ES Actuation)

SRO/BQP AP111A117001042 (Inadvertent ES Actuation) actions:

1. Entry Conditions Engineered Safeguards actuation occurred due to invalid reason while in MODE 1-4 4.1 Verify ES Channel 1 or 2 has actuated RNO: GO TO Step 4.4 4.4 Verify ES Channel 5 or 6 has actuated RNO: GO TO Step 4.7 4.7 Close the following:

1 HP-24 1 HP-25 4.8 Ensure AP/42 End 5.1 (Side Board Actions) is in progress Note: End 5.1 of AP142 contains no verifiable actions for the BOP to mitigate a spurious ES-3 actuation 4.9 Initiate announcement of AP Entry using the PA system Page 10 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 5 Page 2 of 2 Event

Description:

Spurious ES Channel 3 Actuation (C; BOP, SRO) (TS)

Time_j Position

[ Crew Response:

Applicants Actions or Behavior 4.10 Verify ES Channel 1 or 2 has actuated RNO: 1. IF ES Channel 5 or 6 has actuated, THEN initiate AP/42 End 5.2 (Letdown Restoration)

2. GOTOStep4.20 4.20 Verify ES Channel 3 or 4 has actuated 4.21 Place the affected components in MANUAL: (RZ Module)

ES Channel 3 LPI-P1A 1LP-17 4.22 Verify P1 was aligned in decay heat removal mode prior to ES actuation RNO: 1. Stop the following:

1A LPI PUMP lB LPI PUMP

2. Close the following:

1LP-17 1LP-18 4.23 Notify SPOC to investigate and repair the cause of the inadvertent ES actuation, as necessary Note: ES-3 components will remain in Manual for the rest of the scenario and will require the crew to manually reinitiate them when conditions require the channel to actuate.

SRO refers to TS 3.3.7 (ES Digital Channels)

Condition A applies (Declare associated components inoperable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months )

SRO refers to TS 3.3.6 (ESPS Manual Initiation)

Condition A applies (Restore to Operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months )

When ES 3 components are secured, or when directed by the Lead Examiner, this event is complete.

Page 11 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 6 Page 1 of 1 Event

Description:

Continuous Rod Withdrawal Requiring Manual Reactor Trip (C; OATC, SRO)

Time Position Applicants Actions or Behavior Plant Response:

Control Rods withdrawing without operator action

NI-5 thru Nl-9 indicate increasing reactor power

SURs on Wide Range Nis increasing Crew Response:

SRO/OATC

The candidates should utilize the Plant Transient Response (PTR) process to stabilize the plant and recognize that control rods are withdrawing without a valid signal.

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

Place the Diamond and both FDW Masters in MANUAL to stabilize the plant.

> The crew should insert control rods and monitor reactor power and wide range startup rate to stabilize the plant BOP

Report no valid (ICS) Runback and monitor RCS pressure and inventory Note: IRC-3 (previously closed due to IRC-1 failing open) may be required to be manually operated to control RCS pressure.

Normally, IRC-1 will open at 2205 psig increasing and close at 2155 psig decreasing. Since IRC-1 is failed open, the operator will be required to control RCS pressure manually with IRC-3.

Note: The SRO/OATC may elect to trip the Reactor during this transient per SOMP 1-02 and OMP 1-18 Attachment J (Plant Transient Response).

During abnormal operating conditions a manual reactor trip shall be initiated if any of the following conditions occur:

Reactor power level approaches any operating limit

Reactor power level exceeds the pre-transient power level by greater than 5% AND the cause of the power change is NOT understood, OR is NOT controllable

Any time plant conditions are considered uncontrollable or unsafe Note: If the Reactor is tripped, then GO TO event 7 (next page).

When the plant is stable or if the Reactor is manually tripped, or when directed by the Lead Examiner, this event is completed.

Page 12 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 7 Page 1 of 5 Event

Description:

Blackout Requiring Manual Alignment From CT-5 (M; ALL)

Time Position

[ Plant Response Applicants Actions or Behavior

Reactor will trip (if not already tripped)

MFBs will de-energize

CT-i Lockout

KHU-1 Emergency Lockout

KHU-2 Emergency Lockout Crew Response:

SRO SRO directs OATC to perform Immediate Manual Actions (IMAs):

OATC

Depress REACTOR TRIP pushbutton

Verify Reactor Power < 5% FP and decreasing

Depress turbine TRIP pushbutton

Verify aM turbine stop valves closed

Verify RCP seal injection available Note: The OATC should determine that RCP Seal Injection and CC are not available and inform the SRO to initiate AP125. The SRO will then direct an RO to initiate AP125. When the RO attempts to leave the Control Room, inform himlher that a Unit 2 RO will perform AP125 actions at the SSF.

SRO directs BOP to perform Symptoms Check:

SRO

Power Range NIs NOT < 5% and/or NOT decreasing

Any SCM 0°F

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

Uncontrolled Main Steam Line(s) pressure decrease

Steam Generator Tube Rupture

> CSAE Offgas alarms

> Process Monitor alarms (RIA-40)

> Area monitor alarms (RIA-i61i7)

Page 13 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 7 Page 2 of 5 Event

Description:

Blackout Requiring Manual Alignment From CT-5 (M; ALL)

__Time Position

[ Crew Response:

Applicants Actions or Behavior SRO will transfer to Subsequent Actions Tab of the EOP after documenting IMAs and will refer to the Parallel Actions Page which will require a transfer to the Blackout Tab due to ALL 4160V switchgear being de-energized.

Perform Rule 3 when the Main FDW Pumps trip (see next page)

SRO Blackout Tab

Direct an RO to announce plant conditions using PA system

Direct an RO to notify OSM to reference the Emergency Plan and NSD 202 (Reportability)

1. Verify two ROs available to perform Control Room actions

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

(see page 4)

3. Verify any SG is being fed

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

1A MD EFDWP lB MD EFDWP

5. Feed and steam available SG5 as necessary to stabilize RCS PIT

6. IAAT NO SGs are being fed, AND y source of EFDW (Unit 1 or another unit) becomes available, THEN perform the following

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

8. IAAT power is restored to y of the following:

1TC lTD 1 TE THEN GO TO Step 9 RNO: GOTO Step 11

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

10. GO TO Subsequent Actions Tab

11. Verify End 5.38 (Restoration of Power) in progress or complete Page 14 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 7 Page 3 of 5 Event

Description:

Blackout Requiring Manual Alignment From CT-5 (M; ALL) r Time Position Crew Response:

Applicants Actions or Behavior OATC 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 py 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 aN intact SGs

5. Verify y EFDW pump operating

6. GOTO Step 37

37. IAAT an EFDW valve CANNOT control in AUTO, OR manual operation of EFDW valve is desired to control flow/level, THEN perform Steps 38-42 RNO: GO TO Step 43

43. Verify any SCM 0°F RNO: IF overcooling, OR exceeding limits in Rule 7 (SG Geed Control),

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)

1. Monitor EFDW parameters on EFD graphic display

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

3. IAAT feeding both SGs with one MD EFDWP is desired 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 Page 15 of 27

Appendix D Scenario Outline Form ES-D-l May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 7 Page 4 of 5 Event

Description:

Blackout Requiring Manual Alignment From CT-5 (M; ALL)

Position Applicants Actions or Behavior

[_Time Crew Response:

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

1. Verify power has been restored RNO: GO TO Step 3

3. Place 1 HP-31 in HAND and reduce demand to 0

4. Close 1HP-21

5. Verify any of the following energized:

MFB1 MFB2 RNO: GO TO Step 8

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: 1. Emergency Start Keowee units:

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

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

36. IAAT CT-5 indicates 4160 volts, THEN GO TO Step 50

50. Place the following switches in MAN:

MFB1 AUTO/MAN (already in manual)

MFB2 AUTO/MAN (already in manual)

STANDBY 1 AUTO MAN STANDBY 2 AUTO MAN

51. Open the following breakers:

1 MFB1 NORMAL FDR (already open)

Ni 1 MFB2 NORMAL FDR (already open)

N2 1 MFB1 STARTUP FDR (already open)

El 1 MFB2 STARTUP FDR (already open)

E2 Page 16 of 27

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 7 Page 5 of 5 Event

Description:

Blackout Requiring Manual Alignment From CT-5 (M; ALL)

Time Position

] Crew Response:

ApplicanVs Actions or Behavior BOP 52. Place the following switches in MAN:

_CT4 BUS 1 AUTO/MAN

_CT4BUS2AUTO/MAN CT5 BUS 1 AUTO/MAN (already in manual)

CT5 BUS 2 AUTO/MAN (already in manual)

53. Open the following breakers:

Ski CT4 STBY BUS 1 FEEDER (already open)

SK2 CT4 STBY BUS 2 FEEDER (already open)

54. Close the following breakers:

_SLi CT5STBYBUS1 FEEDER SL2 CT5 STBY BUS 2 FEEDER

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 Note: The Blackout exists on Unit I only.

58. Close the following breakers:

_S1 STBY BUS 1 TOMFB1

_S2 STBYBUS2TOMFB2

59. Verify jy of the following energized:

1TC 1 TD 1 TE

60. Notify Unit i CR SRO of status of 4160V SWGR Note: When power is restored, IAAT Step 8 (BlO Tab) will apply and the SRO will initiate APIII and GO TO the Subsequent Actions Tab.

When power has been restored and the transfer to Subsequent Actions has occurred, or when directed by the Lead Examiner, this event is complete.

Page 17 of 27

Appendix D Scenario Outline Form ES-D-l May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 8 Page 1 of 9 Event

Description:

LBLOCA With Failure of I B LPI Pump (M; ALL)

Time Position Applicants Actions or Behavior Plant Response:

Control Board Indications:

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

RCS Pressure and PZR level decreasing

ES 1-6 actuate (except ES Channel 3 which is in MANUAL)

RCS subcooling margin will indicate 0°F

The LOOP A and LOOP B SUB000LING MARGINs will indicate Superheat due to no LPI pumps operating (1A LPI pump is in Manual and OFF due to previous ES-3 actuation and the 1 B LPI pump will not start)

Crew Response:

SRO

SRO may direct an RO to perform a Symptoms Check OATC/BOP > Power Range NIs NOT < 5% and/or NOT decreasing

> Any SCM 0°F

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

> Uncontrolled Main Steam Line(s) pressure decrease

> Steam Generator Tube Rupture o CSAE Offgas alarms o Process Monitor alarms (RIA-40) o Area monitor alarms (RIA-16/17)

SRO

SRO may direct an RO to actuate ES Channel 3 components previously placed in manual

Once jy Subcooling Margin (SCM) indicates 0°F, the SRO will direct or concur initiation of Rule 2 (Loss of SCM) (see page 7)

SRO will transfer to the LOSCM Tab (see next page)

Page 18 of 27

Scenario Outline Form ES-D-1 Appendix D May, 2011 Scenario No.: 3 Event No.: 8 Page 2 of 9 Op-Test No.:

Event

Description:

LBLOCA With Failure of I B LPI Pump (M;ALL)

[ Time Position ] Crew Response:

Applicants Actions or Behavior SRO LOSCM Tab Parallel Actions

SRO will direct an RO to initiate End 5.1 (ES Actuation) (see page 4)

SRO will direct an available RO to make notifications

> Announce plant conditions using PA system

> Notify OSM to reference Emergency Plan and NSD 202 (Reportability)

> Notify plant staff that EDL5 are in affect using PA system

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: GO TO Step 6

6. IAAT either of the following exist:

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 Note: When the IA LPI Pump is manually started and aligned per Enclosure 5.1, this step will apply and the SRO should transfer to the LOCA CD tab. (CT-4)

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

SSF RC Makeup SSF Aux Service Water RNO: GO TO Step 9

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)

10. GO TO Step 89

89. Open 1AS-40 while closing 1MS-47 Page 19of27

Scenario Outilne Form ES-D-l Appendix D May, 2011 Event No.: 8 Page 3 of 9 Op-Test No.: Scenario No.: 3 Event

Description:

LBLOCA With Failure of I B LPI Pump (M; ALL)

Te_j Position__J Applicants Actions or Behavior Crew Response:

M Tab will Note: Once LPI flow is> 2900 gpm, IAAT Step 6 of the LOSC apply and the SRO will transfer to the LOCA CD Tab.

LOCA CD Tab SRO

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 aH RBCUs in low speed Open 1 LPSW-1 8 Open 1 LPSW-21

_Open 1LPSW-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 plus LPI FLOW TRAIN B 3400 gpm Only one LPI header in operation with header flow 2900 gpm THEN GO TO Step 11

11. Stop aM RCPs

12. Dispatch an operator to perform the following:

Remove white tag and close 1XO-F5C (1CF-1 Bkr)

Remove white tag and close 1XP-F5C (1CF-2 Bkr)

Close 1XS2-F3D (1LP-104 Bkr) and

13. IAAT breakers for 1CF-1 AND 1CF-2 are closed, THEN close 1CF-1 1CF-2 to isolate

14. Dispatch an operator to perform End 5.28 (Local SG Isolation) both SGs direction Once the SRO has transferred to the LOCA CD Tab, or at the of the Lead Evaluator, this event is comple te.

Page 20 of 27

Scenario Outline Form ES-D-l Appendix D May, 2011 Event No.: 8 Page 4 of 9 Op-Test No.: Scenario No.: 3 Event

Description:

LBLOCA With Failure of I B LPI Pump (M; ALL)

Time Position ] Crew Response:

Applicants Actions or Behavior EOP Enclosure 5.1 (ES Actuation) d based on RCS OATC/BOP 1. Determine all ES channels that should have actuate pressure and RB pressure:

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

2. Verify all ES digital channel associated with actuati actuated ed, THEN perform

3. IAAT additional ES actuation setpoints are exceed Steps 1 2

4. Place HPI in manual control

5. Verify Rule 2 in progress or complete

6. Verify y RCP operating RNO: GO TO Step 8 6 actuate, THEN

8. IAAT y RCP is operating, AND ES Channels 5 and perform Steps 911 RNO: GO TO Step 12 Step 13

12. IAAT ES Channels 3 & 4 are actuated, THEN GO TO

13. Place the following in manual control:

1A LPI PUMP 1LP-17

_1 B LPI PUMP 1LP-18 at the CR

14. IAAT y LPI pump is operating against shutoff head, THEN SROs discretion, stop affected LPI pumps Page 21 of 27

Scenario Outline Form ES-D-1 Appendix D May, 2011 Event No.: 8 Page 5 of 9 Op-Test No.: Scenario No.: 3 Event

Description:

LBLOCA With Failure of I B LPI Pump (M; ALL)

Applicants Actions or Behavior 1_Time Position Crew Response:

OATC/BOP EOP Enclosure 5.1 (ES Actuation) perform

15. IAAT RCS pressure is < LPI pump shutoff head, THEN Steps 1617

16. Perform the following:

_Open 1LP-17 Start 1A LPI PUMP

17. Perform the following:

Open 1LP-18 Start lB LPI PUMP RNO: 1. Stop lB LPI PUMP

2. Close 1LP-18 the following exist:

18. IAAT lAand lB LPI PUMPs are off/tripped, AND aB RCS pressure < LPI pump shutoff head 1LP-19 closed 1 LP-20 closed THEN perform Steps 19 20 RNO: GO TO Step 21 PUMP is operating,

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

22. IAAT lB LPI PUMP fails while operating, AND 1A LPI THEN close 1LP-18

23. Start the following: (CT-27)

A OUTSIDE AIR BOOSTER FAN B OUTSIDE AIR BOOSTER FAN

24. Notify Unit 3 to start the following:

3A OUTSIDE AIR BOOSTER FAN 3B OUTSIDE AIR BOOSTER FAN Page 22 of 27

Scenario Outline Form ES-D.-1 Appendix D May, 2011 Event No.: 8 Page 6 of 9 Op-Test No.: Scenario No.: 3 Event

Description:

LBLOCA With Failure of I B LPI Pump (M; ALL)

Time Position Applicants Actions or Behavior Crew Response:

OATC!BOP EOP Enclosure 5.1 (ES Actuation)

25. Verify the following are open:

1CF-1 1CF-2

26. Verify 1HP-410 closed

27. Secure makeup to the LDST position

28. Verify all ES channel 1 4 components are in the ES 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 n and initiate

3. Notify SRO to evaluate components NOT in ES positio action to place in ES position if desired Note: The lB LPI pump is failed.

29. Verify Unit 2 turbine tripped RNO: GO TO Step 32

32. Close 1LPSW-139

33. Place the following in FAIL OPEN:

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

34. Start all available LPSW pumps

35. Verify either of the following:

Three LPSW pumps operating ires two Two LPSW pumps operating when Tech Specs only requ operable

36. Open the following:

1 LPSW-4 1LPSW-5

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

Page 23 of 27

Scenario Outline Form ES-D-1 Appendix D May, 2011 Event No.: 8 Page 7 of 9 Op-Test No.: Scenario No.: 3 Event

Description:

LBLOCA With Failure of lB LPI Pump (M; ALL)

Time Position [ Crew Response:

AppHcants Actions or Behavior Rule 2 (Loss of SCM)

OATC/BOP 1. IAAT all the following exist:

y SCM 0°F Rx power 1%

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

2. StopaHRCPs

3. Notify CR SRO of RCP status

4. Verify Blackout exists RNO: GO TO Step 6

6. Open the following:

1 HP-24 1HP-25

7. Start a available HPI pumps

8. Open the following:

1 HP-26 1HP-27 diverse indications

9. Verify at least two HPI pumps are operating using two header is in the

10. IAAT 2 HPI pumps are operating, AND HPI flow in jy 13 Unacceptable Region of Figure 1, THEN perform Steps 11 RNO: GOTO Step 12

12. IAAT the following limits are exceeded, Pump Operation Limit 1 HPI pump!hdr 475 gpm (md. seal injection for A hdr) 1A & lB HPI pumps operating Total flow of 950 gpm with 1HP-409 open (mc!. seal injection)

THEN throttle HPI to maximize flow flow limit Page 24 of 27

Scenario Outline Form ES-D-1 Appendix D May, 2011 Event No.: 8 Page 8 of 8 Op-Test No.: Scenario No.: 3 Event

Description:

LBLOCA With Failure of lB LPI Pump (M; ALL)

Time Position Applicants Actions or Behavior Crew Response:

Rule 2 (Loss of SCM)

OATC!BOP 13. Notify CR SRO of HPI status

14. Verify RCS pressure > 550 psig RNO: Ensure ES Digital Channels 3 and 4 actuated

15. 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 Step 16

16. Perform the following:

Place 1 FDW-31 5 in MANUAL and close

_Place 1FDW-316 in MANUAL and close Place 1 FDW-35 in HAND and close Place 1FDW-44 in HAND and close due to LB LOCA

17. Notify crew that performance of Rule 3 is NOT required

18. WHEN directed by CR SRO, THEN EXIT this rule Page 25 of 27

Scenario Outline Form ES-D-1 Appendix D May, 2011 CRITICAL TASKS

1. CT-8 Electrical Power Alignment

2. CT-4 Initiate LPI ity Guidance

3. CT- 27 Implementation of Control Room Habitabil Page 26 of 27

Scenario Outline Form ES-D-1 Appendix D May, 2011 SAFETY: Take a Minute UNIT 0 (OSM)

KHUs Operable: Ui OH, U2 UG LCTs Operable: 2 Fuel Handling: No SSF Operable: Yes -

UNIT STATUS (CR SRO)

Unit I Simulator Other Units Unit 2 Unit 3 Mode: 2 Mode: 1 Mode: 1 Reactor Power: 3%

100% Power 100% Power Gross MWE: 0 RCS Leakage: +.025 gpm EFDW Backup: Yes EFDW Backup: Yes (No WCAP action level)

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

OOS Restoration TS/SLC #

ComponentlTrain Date/Time Required DatelTime SLC 16.7.2 Today/06:30 7 Days AMSAC!DSS Conditions A & B Shift Turnover Items (CR SRO)

Primary

. SASS in MANUAL for l&E testing

. AMSAC/DSS Bypassed

. Pressurize the LDST with H 2

. Hold power increase for about 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months so Rx Engineering can collect data.

EFDW to minimize

. When in MODE 2, evaluate or restrict evolutions involving MS, FDW, and changes to RCS temperature and reactor power.

Secondary 1SD-358 are

1SSH-1, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, 1SD-355, 1SD-356 and Proced ure for SSF Overco oling closed with power supply breakers open per the Startup Event.

Reactivity Management (CR SRO)

RCS Boron: 1688 ppmB Gp 6 Rod Position: 49%

Human Performance Emphasis (OSM)

Procedure Use and Adherence Page 27 of 27

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