ML111890014

Initial Exam 2011-301 Final Simulator Scenarios

ML111890014
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: ML111890014 (91)

Text

Appendix D Scenario Outline Form ES-D-1 LT39 May, 2011 Facility: Oconee Scenario No.: IFS 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 I&E testing

. KHU-i is aligned to the underground path

. Perform 5 Minute Delithiation Using Deborating IX Event Malfunction Event Type* Event No. No. 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-Insert ES Channels 7 and 8 Fail To Actuate Updater 1 N: OATC, SRO 5 Minute Delithiation Using Deborating IX (OP/i i03/04C)

Enclosure 4.4 2 Override C, BOP, SRO 1A HPI Pump trips and standby HPI pump fails to start (TS) 3 MSS45O C: BOP, SRO Seismic Event With iA RBCU Rupture 10-45% (TS) 4 MCSOO4 I: OATC, SRO Controlling Tave Fails HIGH 5 C: BOP, SRO iDi 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 i B MDEFDW Pump Trips (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Page 1 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: I Page 1 of 2 Event

Description:

5 Minute Delith Using Deborating IX (OPII!A111031004 C) (N: OATC, SRO)

Time J Position Crew Response:

Applicants Actions or Behavior SRO Direct OATC 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.

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

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

Appropriate ranged NIs Primary tank levels Neutron error CRD position u IX run-time for proper chemistry control 2.9 Align Unit 1 Deborating IX for service:

2.9.1 Verify closed ICS-32 & 37 (SPARE DEBOR IX INLET & OUTLET)

Ensure closed 1CS-26 (LETDOWN TO RC BHUT) 2.9.3 Open 1CS-27 (DEBOR IX INLET)

Verify 1HP-15 Controller in MANUAL 2.9.5 Ensure open 1HP-16 (LDST MAKEUP ISOLATION) 2.10 Position 1HP-14 (LDST BYPASS) in BLEED to place Unit 1 Deborating IX in service NOTE:

• Chemistry procedures require a minimum of 15 minutes 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 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 2011 Op-Test No.: Scenario No.: I Event No.: I Page 2 of 2 Event

Description:

5 Minute Delith Using Deborating IX (OPIIIA!11031004 C) (N: OATC, SRO)

Crew Response:

SRO/OATC 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 Deborating IX In Service) 2.14 IF AT ANY TIME desired to reduce inventory, reduce RCS inventory (Bleed):

2.14.1 Open ICS-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 Chemist has sampled Unit 1 Deborating IX effluent (R.M.)

2.16 WHEN run time is complete, perform the following:

_2.16.1 Position 1HP-14 (LDST BYPASS) to NORMAL

_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 1HP-15 Controller for Normal Operation 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 This event is complete when the crew reaches Step 2.17, or as directed by the Lead Evaluator.

Page 3 of 35

Appendix D Scenario Outline Form ES-D-1 ILT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 2 Page 1 of 3 Event

Description:

IA HPI Pump trips and the standby HPI pump fails to auto start:

(C; BOP, SRO) TS Time Position Applicants Actions or Behavior Plant response:

Statalarms:

• 1SA-2/B-2 (HP RCP Seal Injection Flow High/Low)

• 1SA-2/C-2 (HP Injection Pump Disch. Header Pressure High/Low)

Board indications:

• RC Makeup Flow 0 gpm

• RCP SI flow = 0 gpm

• 1A HPI Pump amps low = 15 amps PZR level will begin to decrease and LDST level will begin to increase.

BOP/SRO Crew response:

Refer to ARGs: Refer to AP/14 AP/1/A11700/014, Loss of Normal HPI Makeup and/or RCP Seal Injection 3.1 IAAT RCP seal injection flow is lost, AND Component Cooling is lost, THEN perform the following:

A. Trip the Rx.

B. Stop all RCPs.

C. Initiate AP/25 (SSF EOP).

3.2 IAAT loss of suction to operating HPI pumps is indicated:

• Motor amps low or cycling

• Discharge pressure low or cycling

• Abnormal LDST level trend RNO: GO TO Step 4.7 4.7 Announce AP entry using PA System.

4.8 Verify any HPI pump operating. RNO

1. Close 1 HP-5 (Letdown Isolation)

2. Place 1HP-120 in HAND and closed

3. Place 1HP-31 in HAND and closed

4. Attempt to start the Standby HPIP (1 B HPIP starts)

5. IF standby HPI pump started, THEN GO TO Step 4.111.

Page 4 of 35

Appendix D Scenario Outine Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 2 Page 2 of 3 Event

Description:

IA HPI Pump trips and the standby HPI pump fails to auto start:

(C; BOP, SRO) TS Time Position Applicants Actions or Behavior 4.111 Place 1HP-31 in HAND 4.112 Slowly open 1HP-31 in small increments until 8 gpmIRCP is achieved.

4.113 Re-establish normal makeup through 1HP120.

4.115 Reduce 1HP-7 demand to 0%.

4.116 Close 1HP-6 4.117 Open the following:

> 1HP-1 (1A Letdown Cooler Inlet) 1 HP-2 (1 B Letdown Cooler Outlet)

> 1HP-3 (1A Letdown Cooler Inlet)

> 1 HP-4 (1 B Letdown Cooler Outlet Simulator operator: Crew may secure the 1A HPIP and direct NEO to open &

BOP/SRO rack out the 1A HPIP breaker. (Use Quick Strike to open breaker and remove fuses) 4.118 Open 1HP-5 4.119 Throttle open 1 HP-7 for 20 gpm letdown flow.

4.120 Open 1HP-6 4.121 Adjust 1HP-7 for desired letdown flow.

4.122 Open the following: 1 HP-228, 1 HP-226,1 HP-232, 1 HP-230 4.123 Open 1HP-21.

4.124 IAAT SEAL INLET HDR FLOW 32 gpm, THEN place 1 HP-31 in AUTO Refer to Tech Spec 3.5.2 High Pressure Injection

• Condition A

• Required Action: Restore HPI pump to OPERABLE status

• Completion Time: 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Note: Due to sequence of events, SRO may not review the TS during the scenario. Follow-up questions may be required to ensure knowledge of this competency.

Note: Crew may make a batch addition to the LDST. See attached End.

4.4 of 0P111A111031004.

Note: Crew may enter AP/16 (Abnormal RCP Operation) as a result of high seal return temperatures. Steps are on the next page.

Page 5 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 2 Page 3 of 3 Event

Description:

IA HPI Pump trips and the standby HPI pump fails to auto start:

(C; BOP, SRO) TS Time Position Applicants Actions or Behavior APII6 (Abnormal RCP Operation) 4.1 IAAT any RCP meets immediate trip criteria... (does not) GO TO Step 4.12 4.12 IAAT all of the following apply:

• Rx Power> 70%

• Any RCP approaching immediate trip criteria of End 5.1 (RCP Immediate Trip Criteria) or it is desired to secure a RCP THEN perform the following:

• Initiate End 5.2 (Rapid Power Reduction).

• WHEN Rx Power is < 70%,

THEN GO TO Step 4.2.

BOP/SRO 4.13 Announce AP entry using the PA system.

4.14 Notify OSM to request evaluation by RCP Component Engineer.

4.15 AT the failure is identified, THEN GO TO the applicable section per the following table:

4D Loss of Seal Return

1. IAAT any RCP meets immediate trip criteria... (does not) GO TO Step 4.12

12. Monitor RCP parameters for operational abnormalities.

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

14. OpenlHP-228, 1HP-226, IHP-232, and 1HP-230

15. Verify either of the following... (not met) RNO GO TO Step 17.

16. Verify RCP seal return low flow alarms off.

16 RNO Request that RCP Component Engineer provide the following:

• Immediate evaluation

• Additional monitoring requirements Cue: If candidate attempts to monitor the Loose part Monitor, indicate that the noise is normal.

This event is complete when IHP-31 is placed in AUTO, or as directed by the Lead Evaluator.

Page 6 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 3 Page 1 of 2 Event

Description:

Seismic Event With IA RBCU Rupture (C: BOP, SRO) (TS)

Time Position Applicants Actions or Behavior Booth Cue: After IHP-31 is placed in AUTO and at the direction of the Lead Evaluator, call the Control Room (4911) as a security guard and state We have felt a tremor and have observed no plant damage Plant Response:

• 1 SA-9IB-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-91B-9 3.1 Verify alarm is valid by checking RBCU 1A Inlet Flow and RBCU 1A A Flow.

3.2 Verify 1LPSW-18 (RBCU 1A OUTLET) open 3.3 Verify adequate LPSW flow is available; check LPSW pump operation 3.3.1 Verify 1LPSW-16 (1A RBCU INLET PENE) is open 3.3.2 IF 1LPSW-16 (1A RBCU INLET PENE) is NOT open, refer to TS and SLCs 3.4 Monitor RBNS Level for any unexplained increase 3.5 IF RBNS Level is increasing AND ES has actuated, notify Chemistry to sample the RBNS for boron concentration to determine if a cooler rupture has occurred based on sample results.

3.6 IF RBCU 1A Cooler rupture or line break is indicated, then:

3.6.1 Isolate the 1A RBCU Cooler as follows:

A. Close 1LPSW-16 (1A RBCU INLET PENE)

B. Close 1LPSW-18 (1A RBCU OUTLET)

C. Perform TS 3.6.3 Condition C for closed containment system.

D. Enter TS 3.6.5 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 7 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 2011 Op-Test No.: Scenario No.: I Event No.: 3 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 Service Water).

3.6.5 Refer to OP/i/Ni 104/015 (Reactor Building Cooling System).

Refer To APIOIAII700IOO5, 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 RECORDER (Oi D020i) on Unit 1

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

4.4 Notify Keowee operating personnel to initiate AP/0/N2000/OO1 (Natural Disaster).

Booth Cue: Respond as the Keowee Operator and state that AP/OOlwill be initiated.

4.5 Notify Hydro Central.

4.6 Dispatch operators to perform the following enclosures:

• End 5.i (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/i 000/00 i (Emergency Classification)

• OMP i-i4 (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 API5.

This event is complete when IA RBCU has been isolated, or as directed by the Lead Evaluator.

Page 8 of 35

Appendix D Scenario Outline Form ES-D-1 ILT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 4 Page 1 of 3 Event

Description:

Controlling Tave Fails HIGH (I: OATC, SRO)

_Time 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 runback 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 API1!A117001028 (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

• DeltaT O°F+/-2°F 0

4.2 Initiate notification of the following:

• OSM to reference the following:

> OMP 1-14 (Notifications)

> Emergency Plan

• STA Page 9 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 4 Page 2 of 3 Event

Description:

Controlling Tave Fails HIGH (I: OATC, SRO)

_Time_j 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:

• QAC alarm video

• OAC display points

• Control Board indications

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

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

Page 10 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 4 Page 3 of 3 Event

Description:

Controlling Tave Fails HIGH (I: OATC, SRO)

U_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 ICS 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 input to ICS per AM/01B10326/020 (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/Ni 102/004 A End (Placing ICS Stations To AUTO)

Note: The Controlling Tave failure will not be repaired for this scenario.

This event is complete when the SRO reaches the WHEN step (6) in Section 4A, or as directed by the Lead Evaluator.

Page 11 of35

Appendix D Scenario Outline Form ES-D-1 ILT39 May, 2011 Op-Test No.: Scenario No.: I Event No.: 5 Page 1 of 1 Event

Description:

IDI HOP Low Oil Level (C: BOP, SRO)

Time 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 ID1 HDP per OP/i/N1106/002 D.

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

The BOP should secure the 1D1 HDP per OP/i/N1106/002 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 I DI HDP breaker is not required at this time.

Note: The SRO may refer to RPIOIBII 0001017 (Spill Response) andlor 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 101 HDP in a timely manner, it will automatically trip 12 mm after the crew receives the high bearing temperature OAC alarms.

This event is complete when the I DI HDP has been secured, or as directed by the Lead Evaluator.

Page 12 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 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 Applicants Actions or Behavior Plant Response:

Statalarm 1SA2!A1O (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/A/1700/OO1 (Unit Runback)

Entry Conditions:

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

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

Note: The SRO should transfer to Section 4H (Asymmetric Control Rod) of APIIIAII700IOOI Page 13 of 35

Appendix D Scenario Ouliine Form ES-D-1 1LT39 May, 201 1 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/A/1700/001 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/1/A11102/004 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 I %/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 S/D) (page 16)

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:

• Investigate cause of dropped or misaligned control rod.

• Prepare to reduce the following trip setpoints:

• RPS Flux/Flow-Imbalance

• RPS High Flux

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) (may not apply depending on time rod has been dropped)

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

Page 14 of35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 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/11A11700/00i Section 4H

8. Verify> 1% SDM with allowance for the inoperable control rod per PT/i /A/1103/015 (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 jj 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:

q 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 ii. 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 AMIOIA 0301/003 U (Procedure to Reset the Flux/Imbalance/Flow and High Flux Trips for Operation with Excessive Power Tilt, Dropped Control Rod Or Other Conditions)

Page 15 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 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 Applicants Actions or Behavior Crew Response:

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

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

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

3. Start the following pumps:

• lA/lB 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 1 B FDWP to be shut down first.

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

10. GO TO Step 12

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

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

• 1SA-16/A-3 (FWP B FLOW MINIMUM)

• 1SA-16/A-4 (FWP B FLOW BELOW MIN)

THEN trip lB Main FDW Pump This event is complete when the SRO reaches WHEN Step II of APIIIAII700IOOI Section 4H, or as directed by the Lead Evaluator.

Page 16of35

Appendix D Scenario Outline Form ES-D-1 lLT39 May, 2011 Op-Test No.: Scenario No.: I Event No.: 7 Page 1 of 17 Event

Description:

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

Time Position Applicants Actions or Behavior Plant response:

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

• 1SA-21D-3, RC Press High/Low

• Statalarm 1SA-02/A-9 (MS PRESS HIGH/LOW)

Crew response:

• SRO will enter the EOP by directing the OATC to perform Immediate SRO Manual Actions or perform IMAs.

• OATC will perform Immediate Manual Actions OATC Depress REACTOR TRIP pushbutton Verify reactor power < 5% FP and decreasing

> Depress turbine TRIP pushbutton.

> Verify all turbine stop valves closed Verify RCP seal injection available

• BOP 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 decrease

> Steam Generator Tube Rupture o CSAE off-gas alarms, process RIAs (RIA-40, 59, 60), area RIAs (RIA-1 6/17)

Page 17 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 7 Page 2 of 17 Event

Description:

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

_Time_j Position Applicants Actions or Behavior 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 31-32 of this JjVl,. 7 BOP performs Rule #5 (Main Steam Line Break) after receiving concurrence from the SRO (see page 23)

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 28)

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 18 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 7 Page 3 of 17 Event

Description:

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

Time 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 affected SGs:

• 1 FDW-32 and 1 FDW-35

4. Close the following on affected SGs:

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

5. Verify level in both SGs < 96% O.R.

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

7. Throttle HPI per Rule 6 (HPI)

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

9. Verify jjy SG has an intact secondary boundary (intact SG)

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 aB intact SGs

• 1 FDW-382 and 1 FDW-369

11. Start MDEFDWP associated with aH intact SGs

• 1BMDEFDWP RNO: Start TDEFDWP

12. Feed and steam aM intact SGs to stabilize RCS PIT using either of the following: (CT-Il)

• TBVs

• Dispatch two operators to perform End 5.24 (Operation of the ADV5 Page 19 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 2011 Op-Test No.: Scenario No.: I Event No.: 7 Page 4 of 17 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

13. GO TO Step 32

32. Verify y of the following:

HPI has operated in the injection mode while NO RCPs were operating A cooldown below 400° F at> 100°F/hr has occurred RNO: GO TO Step 34

34. Verify 1MS-24 and 1MS-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 aB the following exist:

• ES Bypass Permit satisfied

• All SCMs > 0°F

• RCS pressure controllable THEN bypass ES as necessary

40. Verify any SG is dry Page 20 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 7 Page 5 of 17 Event

Description:

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

U_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)

Note: Target should be 10-20°F SCM.

• 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

• QAC

• EnclS.18

44. Initiate End 5.16 (SG Tube-to-Shell tiT 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 a 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 TcoId approaches 400°F, AND afl RCPs are operating, THEN ensure <four RCPs are operating Page 21 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 7 Page 6 of 17 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:

• jy SG isolated

• y 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:

• TcoId > 280°F: 50°F I Y2 hr

• TcoId 280°F: 25°F I 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 aH 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 This event is complete when the SRO transfers to the Forced Cooldown (FCD) Tab of the EOP, or as directed by the Lead Evaluator.

Page 22 of 35

Appendix D Scenario Outline Form ES-D-1 ILT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 7 Page 7 of 17 Event

Description:

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

Position Applicants Actions or Behavior V_Time Crew Response:

EOP Rule 5

1. Perform the following on affected headers:

• Initiate AFIS 1A SG Digital Channels 1 and 2

• Select OFF for 1A MDEFDW Pump (CT-17)

Note: The critical task is to stop feeding the affected SO.

• 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 lB 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 >0° F, Rx Pwr 1%, and Pzr Level increasing, THEN perform the following to stabilize RCS PIT:

• Throttle HPI

• Reduce 1HP-120 setpointto> 100 (180 ACC)

• Adjust steaming of unaffected SG (1A SG) to maintain CETCs constant Page 23 of 35

Appendix D Scenario Outline Form ES-D-1 ILT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 7 Page 8 of 17 Event

Description:

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

Time Position Applicants Actions or Behavior Crew Response:

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 jy EFDW pump operating. (lB MD is operating to lB SG)

6. GO TO Step 37

37. IAAT an EFDW valve CANNOT control in AUTO OR manual operation if EFDW valve is desired to control flow/level, THEN perform Steps 38-42 RNO: 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 24 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 7 Page 9 of 17 Event

Description:

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

U_Time Position } Crew Response:

Applicants Actions or Behavior 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: GOTO Step 12 Page 25 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 7 Page 10 of 17 Event

Description:

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

[ Timj Position { Crew Response:

Applicants Actions or Behavior 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 IC-b is 10% open.

• If the condensate system is operating, the remaining guidance establishes FDW recirc, monitors and maintains UST, and transfers EFDW suction to the hotwell if required.

12. Notify CR SRO to set priority based on the NOTE above EOP activities Note: The SRO should determine that restoring the secondary side of the plant is not a priority at this time and direct the RO to continue in Rule 3.

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 lB MDEFDW pump will trip. This will require Rule 3 to be reinitiated to start the TO EFDW pump to feed the lB SG.

When the team determines that the lB 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 26 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 7 Page 1 1 of 17 Event

Description:

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

Time Position Applicants Actions or Behavior Crew Response:

EOP Rule 3 (After 1 B 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/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.

6. GO TO Step 37

37. IAAT an EFDW valve CANNOT control in AUTO OR manual operation if EFDW valve is desired to control flow/level, THEN perform Steps 38-42 RNO: 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 27 of 35

Appendix D Scenario Outline Form ES-D-1 ILT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 7 Page 12 of 17 Event

Description:

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

Time j Position Applicants Actions or Behavior 1 Crew Response:

EOP Enclosure 5.1 (ES Actuation)

1. Determine all 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:

q IA Header q lB Header 1HP-410 1HP-409

70. Verify any RCP operating

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

72. IAAT y RCP is operating, AND ES Channels 5 and 6 actuate, THEN perform Steps 73-75 Page 28 of 35

Appendix D Scenario Outline Form ES-D-1 ILT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 7 Page 13 of 17 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 jy LPI pump is operating against shutoff head, THEN at the CR SROs discretion, stop affected LPI pumps (CT)

79. IAAT RCS pressure is < LPI pump shutoff head, THEN perform Steps 80-81 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 ILP-18

87. Start A and B OUTSIDE AIR BOOSTER FANS Page 29 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 7 Page 14 of 17 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 operable 100. Open 1 LPSW-4 and 1 LPSW-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 Hydrogen 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 30 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 7 Page 15 of 17 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 aH the following exist:

y 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 1HP-24 and 1HP-25

7. Start aN 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: 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 Total flow of 950 gpm pumps operating (md. seal injection) with 1 HP-409 open THEN throttle HPI to maximize flow flow limit Page 31 of 35

Scenario Outline Form ES-D-1 Appendix D ILT39 May, 201 1 Scenario No.: I Event No.: 7 Page 16 of 17 Op-Test No.:

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 following

28. Verify 1 SA-21C-8 (AFIS HEADER A INITIATED) lit

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

30. Verify J2Y EFDW pump operating This event continues in conjunction with Event 8 which initiates after Rule 5 is complete, or as directed by the Lead Evaluator.

Page 32 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: I Event No.: 8 Page 17 of 17 Event

Description:

I B MDEFW Pump Trips Time Position Applicants Actions or Behavior Crew Response:

31. Start 1A and 1 B MD EFDW pumps on intact SGs:

RNO: Start 1 TD EFDW PUMP (CT-b)

32. Verify y EFDW pump operating

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

2. GOTO 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 EOP Rule 2

38. Place FDW block valve switches in CLOSE:

1 FDW-33 1 FDW-31 1 FDW-42 1FDW-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°F/Y2 hr when TcoId > 280°F and 25°FP/ 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 This scenario is complete when EFW flow, RCS pressure and temperature are under control, or as directed by the Lead Evaluator.

Page 33 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 CRITICAL TASKS

1. CT-i 7 Isolate Overcooling SG(s)

2. CT-7 Minimize SCM

3. CT-il Control SC Pressure (adjust TBV5/ADVs) to Maintain RC Temperature Constant

4. CT-iO Establish FW Flow and Feed SG(s)

5. CT Secure LPI pumps within 30 minutes of ES actuation and RCS pressure above shut off head of the LPI pumps. (TCA#8)

Page 34 of 35

Appendix D Scenario Outline Form ES-D-l ILT39 May, 201 1 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 EFDW Backup: Yes

. EFDW Backup: Yes (No WCAP action level)

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

Component/Train OOS Restoration TS/SLC #

Date/Time Required DatelTi me 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 I&E testing

. Power was reduced two hours ago per dispatcher. Xenon is building in. Rx ENG is preparing a maneuvering plan.

. The OATC is to perform a 5 minute Delith using Deborating IX per OP/i/Ni 103/004 C Enclosure 4.4 beginning at Step 2.8 Secondary

• 1SSH-i, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, 1SD-355, 1SD-356 and ISD-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 35 of 35

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 2011 Facility: Oconee Scenario No.: 2FS 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 Control Rod movement PT (Group 1 only) per PT/11N06001015 Enclosure 13.2 (Control Rod Movement At Power) beginning at Step 3.3 Event Maif. No. Event Type*

Event No.

Description Oa Pre-Insert AMSAC/DSS Bypassed Ob Pro-Insert SASS in MANUAL Oc Pre-Insert LPSW Pump auto start disabled Od Pre-Insert 1B2 RCP Fails to Trip From Switch Oe Pro-insert 1HP-4 Failed Open 1 N: OATC, SRO Control Rod Movement PT (Group 1 only) 2 Override C: BOP, SRO IHP-31 Fails OPEN in AUTO 3 MPI 281 @ 1 OATC, SRO ATc Controller Fails HIGH (A Loop Hot) 68%

4 Updater & C: BOP, SRO Operating LPSW Pump Trips, Standby LPSW Pump Fails Override (TS) To Auto Start 5 MPS400 C: BOP, SRO, RCS Leak 135 gpm (TS) 6 R: OATC, SRO Manual Power Reduction Due to RCS Leak 7 MPS400 M: All SBLOCA (LOSCM to LOCA CD) 1HP-4 Fails to CLose 8 Override 1FDW-316 Fails Closed (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Page 1 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: 2 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 SRO/OATC NOTE: When operating switches on Diamond, maintain switch depressed 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 Balance Procedure) to be valid.

3.4 IF AT ANY TIME jjy 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:

• 1 SA-2/C-1 0 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-lO CRD Safety Rods Not At Upper Limit will alarm when Group I Control Rods are inserted.

Page 2 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 2011 Op-Test No.: Scenario No.: 2 Event No.: I Page 2 of 3 Event

Description:

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

PT1IIAIO600IOI5 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/i/Ni 102/004 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 f TURBINE MASTER is in manual, perform the following:

Note: Step 2.8.2 is NIA 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. f 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 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 2011 Op-Test No.: Scenario No.: 2 Event No.: I Page 3 of 3 Event

Description:

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

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

SRO/OATC C. IF 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 1AOR lB 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

• 1 B FDW MASTER Measured Variable on the caret D. Perform the following:

• Select IA 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.

This event is complete when ICS has been returned to AUTO, or as directed by the Lead Evaluator.

Page 4 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: 2 Event No.: 2 Page 1 of 1 Event

Description:

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

Time Position Applicants Actions or Behavior Plant response:

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

Crew response:

Refer to ARG 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 I HP-3I and throftie to maintain 32 gpm.

• Refer to API1/A/i7001022 (Loss Of Instrument Air) as required

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

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

Note: The SRO may initially refer to AP/14 (Loss of Normal Makeup and/or Seal Injection) and/or APII6 (Abnormal RCP Operation).

This event is complete when Seal Injection flow is manually reduced to 32 gpm, or as directed by the Lead Evaluator.

Page 5 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 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 to decrease.

• B FDW flow will decrease causing B loop Tc to increase.

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

• 1 SA-02/B-5, RC Cold Leg Duff. Temperature High, will actuate if actual AT0 increases to +/- 5°F

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

Crew Response:

SRO/OATC

• Crew should perform Plant Transient Response (PTR)

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

• 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 (ICS 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 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: 2 Event No.: 3 Page 2 of 2 Event

Description:

ATc Controller Fails HIGH (A Loop Th t) (I: OATC, SRO) 0 Time Position j Applicants Actions or Behavior Crew Response:

4.6 GO TO the applicable section per the following table:

q Section Failure 4F Delta Tc AP/28 Section 4F NOTE

• This section applies to Delta Tc controller failures. T 0 input signal failures are addressed in Section 4A The following may occur when an ICS Delta T 0 controller fails:

• Delta T controller may re-ratio loop FDW flows

• Possible ICS RUNBACK

1. Ensure the following in HAND:

lAand 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 Tc while maintaining total feedwater flow constant

3. Notify SPOC to perform the following:

Investigate and repair the failed Delta T controller Booth Cue: When notified to investigate and repair the failedAT controller, respond as SPOC and state that the AT 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 Stations To Auto)

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

This event is complete when the SRO reaches the WHEN step (4) in Section 4F, or as directed by the Lead Evaluator.

Page 7 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 2011 Op-Test No.: Scenario No.: I Event No.: 4 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/BO P

• Refer to OAC alarm response

1. Refer to AP124 (Loss of LPSW)

2. Notify engineering

3. RefertoTS3.7.7

• Refer to ARG for 1 SA-91A-9 (LPSW Header A/B Press Low) 3.1 Refer to API1/A11700/024 (Loss of LPSW) 3.2 Have Unit 2 refer to AP/21A11700/024 (Loss of LPSW).

Booth Cue: If notified to refer to AP/21A11700/024, inform operator that AP/2!A11700/24 will be referenced immediately.

AP/11A11700/024 (Loss of LPSW)

Entry Conditions:

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

• LPSW header pressure low STATALARM

• LPSW header pressure LO-LO OAC alarm

• Automatic Start of Standby LPSW Pump Page 8 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 2011 Op-Test No.: Scenario No.: I Event No.: 4 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 AP111A117001024 (Loss of LPSW)

NOTE Unit 1 normally handles LPSW System operation unless otherwise directed by the CR SRO 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 aH 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 SRQ 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 actions not required for an operating pump. Would enter and exit on the same Tsail entry.

This event is complete when the SRO has referred to TS, or as directed by the Lead Evaluator.

Page 9 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: 2 Event No.: 5 Page 1 of 4 Event

Description:

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

Time Position Applicants Actions or Behavior Plant Response:

Alarms:

• QAC RB Normal Sump Temp HI HI

• 1SA-91A-6 (RB NORMAL SUMP HIGH/LOW)

• 1SA-81B-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 Leakage) and determine that Condition A, Reduce leakage to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and Condition B, Be in MODE 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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-S prior to the SRO entering APIO2.

Note: APIIIAII700IOI8 entry conditions will also be met due to RB RIA alarms. If the crew asks, Unit 2 will perform AP!18 (Abnormal 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 10 of 28

Appendix D Scenario Outline Form ES-D-1 ILT39 May, 201 1 Op-Test No.: Scenario No.: 2 Event No.: 5 Page 2 of 4 Event

Description:

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

Time Position Applicants Actions or Behavior Crew response:

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

HPI flow is> NORMAL MAKEUP CAPABILITY ( 160 gpm) with letdown isolated 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 13) 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 AP126 4.4 Initiate the following notifications:

OSM to reference the following:

• RP/1 000/001 (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 11 of 28

Appendix D Scenario Outline Form ES-D-1 ILT39 May, 201 1 Op-Test No.: Scenario No.: 2 Event No.: 5 Page 3 of 4 Event

Description:

RCS Leak 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 Areal Symptoms Step Failure Rx Bldg RB RIAs 4.53 1 RBNS rate NO RCP seal failure indications 4.53 IAAT in MODE I AND leak is> LDST makeup capability from 1A BHUT, THEN initiate a shutdown using AP/29 (Rapid Unit Shutdown)

Note: The 135 gpm leak is greater than LOST 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 This event is complete when the SRO has made the decision to shutdown, or as directed by the Lead Evaluator.

Page 12 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: 2 Event No.: 5 Page 4 of 4 Event

Description:

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

Time

[ Position Applicants Actions or Behavior Crew response:

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

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

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

• lAHPlPump

• 1BHPIPump

• 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 secure 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

_NotifySRO

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

6. IAAT 1C HPI PUMP is required, THEN perform Steps 7-9 RNO: GOTOSteplO

10. IAAT LDST level CANNOT be maintained, THEN perform Step 11 RNO: GOTO Step 12

12. IAAT additional makeup flow to LDST is desired, AND 1A BLLED TRANSFER PUMP is operating, THEN dispatch an operator to close 1CS-48 EOP Enclosure 5.5 (Pzr and LDST Level Control) may be run as part of Event 5.

Page 13 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: 2 Event No.: 6 Page 1 of 3 Event

Description:

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

Time Position Applicants Actions or Behavior Crew Response:

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

4.1 Initiate End 5.1 (Support Actions During Rapid Unit Shutdown)

SRO (Details on page 16) 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 OATC 4.8 Verify ICS in AUTO RNO: 1. Initiate manual power reduction to desired power level.

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

NOTE

• 1 B Main FDW Pump is the preferred pump to be shutdown 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 adjusted clockwise.

4.11 Adjust bias for first Main FDW pump desired to be shutdown units suction flow is 1 X I 6 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 14 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: 2 Event No.: 6 Page 2 of 3 Event

Description:

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

Time J Position Crew Response:

Applicants Actions or Behavior 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:

• FWPA FLOW MINIMUM (iSA-i 6/A-i)

• FWPA FLOW BELOW MIN (1SA-16/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 1A through 1 E 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 Page 15 of 28

Appendix D Scenario Outline Form ES-D-1 ILT39 May, 201 1 Op-Test No.: Scenario No.: 2 Event No.: 6 Page 3 of 3 Event

Description:

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

Time Position Applicants Actions or Behavior Crew Response:

BOP Enclosure 5.1 (Support Actions During Rapid Unit Shutdown)

1. Notify WCC SRO to initiate End 5.2 (WOO SRO Support 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 ii. 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 1 MFB1 STARTUP FDR

15. Close El 1 MFB1 NORMAL FDR opens

16. Verify Ni 1 MFB2 STARTUP FDR

17. Close E2 1 MFB2 NORMAL FDR opens

18. Verify N2

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

This event is complete when a unit shutdown of> 10% has occurred AND the transfer of electrical Auxiliaries has not started OR is complete, or as directed by the Lead Evaluator.

Page 16of28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: 2 Event No.: 7 Page 1 of 8 Event

Description:

Small Break LOCA (M: ALL)

Time Position Applicants Actions or Behavior Plant response:

• Statalarms:

1SA-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 < 1600 psig

> ES Channels 3-6 will actuate when RB pressure is > 3 psig Crew response:

The SRO will refer to EOP Subsequent Actions Parallel 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 22)

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 20).

SRO EOP LOSCM Tab

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 GO TO LOCA CD tab Page 17 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 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 a 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 1 MS-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 t\T Control)

98. Verify indications of SGTR exist RNO: GOTO Step 101 101. Verify HPI forced cooling in progress RNO: GOTO Step 103 Page 18 of 28

Appendix D Scenario Outline Form ES-D-1 ILT39 May, 201 1 Op-Test No.: Scenario No.: 2 Event No.: 7 Page 3 of 8 Event

Description:

Small Break LOCA (M: ALL)

Time Position Applicants Actions or Behavior Plant response:

EOP LOSCM Tab SRO 103. Verify CETCs trend decreasing 104. Verify primary to secondary heat transfer is excessive RNO: GO TO 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. GO TO Step 7

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 This portion of the event is complete when the SRO transfers to the LOCA CD Tab, or as directed by the Lead Evaluator.

Page 19 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 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 jy SCM 0°F, Reactor power is 1%, and 2 minutes have elapsed since loss of SCM

2. Stop aM RCPs (within 2 mm of LOSCM) (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 1 TA 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 aM available HPI pumps

8. Open 1 HP-26 and 1 HP-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 digital channels on AFIS HEADER A

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

30. Verify y EFDW pump operating RNO: Place 1FDW-315 and 1FDW-316 in MANUAL and close Page 20 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: 2 Event No.: 7 Page 5 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)

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

32. Verify y EFDW pump operating

33. Verify both SGs intact

34. Establish 300 gpm EFDW flow to 1A and lB 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)

Note: They should feed to the LOSCM Setpoint (290 300 XSUR) and flow may be throttled but level should continue to increase.

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 25 of the scenario)

Booth Cue: After Rule 3 is initiated, or as directed by the Lead Evaluator, FIRE TIMER 8 to fail IFDW-316 closed.

50. WHEN directed by CR SRO, THEN EXIT this rule Page 21 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: 2 Event No.: 7 Page 6 of 8 Event

Description:

Small Break LOCA (M: ALL)

Time Position Applicants Actions or Behavior Crew Response:

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 (CT)

15. IAAT RCS pressure < LPI pump shutoff head, THEN realign LPI RNO: GO TO Step 18

18. IAAT 1A and lB LPI pumps are off/tripped align 1C LPI pump RNO: GO TO Step 21 Page 22 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: 2 Event No.: 7 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 lB LPI pump fails while operating 23 Start A and B OUTSIDE AIR BOOSTER FANS (CT-27 within 30 minutes of ES actuation)

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

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

26. Verify IHP-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-139

33. Fail Open 1LPSW-251/252

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 01 P1600

2. Notify crew of BWST level IAAT step Page 23 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 Op-Test No.: Scenario No.: 2 Event No.: 7 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.

This event is complete after Rule 3 is initiated from Rule 2 (step 49 of Rule 2) is performed, or as directed by the Lead Evaluator.

Page 24 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 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. GOTOStep37

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-31 6 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 25 of 28

Appendix D Scenario Outline Form ES-D-1 ILT39 May, 201 1 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 1 FDW-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 scenario is complete when feedwater flow has been established to the lB SG and the cooldown rate is controllable, or as directed by the Lead Evaluator.

Page 26 of 28

Appendix D Scenario Outline Form ES-D-1 1LT39 May, 201 1 CRITICAL TASKS

1. CT-I Trip All RCPs

2. CT-b Establish FDW Flow And Feed SG(s)

3. CT-27 Implementation Of Control Room Habitability Guidance (Within 30 minutes of ES Actuation)

4. CT Secure LPI pumps within 30 minutes of ES actuation if RCS pressure greater than LPI pump shutoff head. (TCA#8)

Page 27 of 28

Appendix D Scenario Outline Form ES-D-1 ILT39 May, 201 1 SAFETY: Take a Minute UNIT 0 (OSM)

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

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

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

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

ComponentlTrain OOS Restoration TSISLC #

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 I&E testing

. AMSAC/DSS Bypassed for l&E testing

. OATC will perform Control Rod movement PT (Group 1 only) per PT/1/A10600/015 End 13.2 beginning at Step 3.3 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: 93%

Human Performance Emphasis (OSM)

A Procedure Use and Adherence Page 28 of 28

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

BOP Initial Conditions:

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

Turnover:

. SASS in Manual for l&E testing

. AMSAC!DSS Bypassed for I&E testing

. Pressurize the LDST With H 2 Event Maif. No. Event Type* Event No. Description Oa Pre-lnsert SASS in MANUAL Ob Pre-Insert 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 (TS) 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-i 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 28

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 LDST with H 2 (N; BOP, SRO)

N__Time Position Applicants Actions or Behavior Crew response:

SRO!BOP

• Refer to OP/i/Ni 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 1H-1 (LDST SUPPLY) as required to pressurize LDST per LDST Pressure vs Level curve 2.8 WHEN Hydrogen addition complete, ensure closed 1H-1 (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 This event is complete when LDST pressurization is stopped, or as directed by the Lead Evaluator.

Page 2 of 28

Appendix D Scenario Outtine 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:

• 1SA-031A-6 (COND VACUUM LOW)

• OAC alarm, Main Condenser Vacuum LOW Crew response:

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

1. Alarm setpoint

• 25 Hg vacuum decreasing

2. Automatic Action

• None; however, Main Turbine trip setpoint is 21.75 Hg (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 API1IN1700/027 (Loss of Condenser Vacuum)

Refer to AP111A117001027 (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 both of the following apply:

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

Page 3 of 28

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

Description:

Vacuum Leak (C; BOP, SRO)

Time Position

[ Applicants Actions or Behavior Crew response:

AP111N17001027 (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 aW available Main Vacuum Pumps operating (A, B, & C) 4.5 Ensure 1V-186 is closed 4.6 Ensure Stm to Stm Air Eject A, B, C> 255 psig 4.7 Verify Stm Seal Hdr Press> 1.5 psig 4.8 Ensure aH 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.

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

4.9 Verify Condensate flow 2300 gpm 4.10 WHEN condenser vacuum is stable, AND End 5.1 (Main Vacuum Pump Alignment) is complete, THEN EXIT this procedure This event is complete when the SRO reaches Step 4.10 of AP1027, or as directed by the Lead Evaluator.

Page 4 of 28

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-2/D-3 (RC PRESS HIGH/LOW) 3.2 Low Alarm 3.2.1 Refer to AP/1 IA/i 700/044 (Abnormal Pressurizer Pressure Control)

SRO/OATC Refer to API1/AI 1700/044 (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 aM 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 AP/U.

Page 5 of 28

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

Time Position Applicants Actions or Behavior Crew Response:

AP/1 IN1 700/044 (Abnormal Pressurizer Pressure Control) 3.2 IAAT aM the following conditions exist:

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

1RC-1 1 RC-3 Note: If the block valve 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 1RC-1 failed OPEN Page 6 of 28

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) (TS)

_Time Position ] Crew Response:

ApplicanVs Actions or Behavior 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)

(Will be entered if RCS pressure < 2125 psig)

TS 3.4.9 (Pressurizer)

_TS 3.4.12 (LTOP System)

SLC 16.5.1 (RCS Vents) 4.17 WHEN repairs complete, THEN place the following components in desired position for current plant conditions as determined by CR SRO:

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

Page 7 of 28

Appendix D Scenario Outline Form ES-D-1 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:

• QAC (RC PZR level 1&3 mismatch)

• QAC (RC PZR level 2&3 mismatch)

Board indications:

• PZR level 1 and 2 indicates 104 inches

• PZR level 3 indicates 154 inches and slowly increasing Crew Response:

Refer to ARG I SA-021C-3 (RC Pressurizer Level High/Low):

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

2. Automatic Action None OATC

3. Manual Action 3.1 Check alternate PZR level indications..

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

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

Note: If in MANUAL the RO should take IHP-120 back to AUTO.

Page 8 of 28

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/A11700/002 (Excessive RCS Leakage)

• AP/1IA/1700/014 (Loss of Normal HPI M/U and/or RCP SI)

• AP/i/A11700/032 (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 OP/hAll 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.

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

Page 9 of 28

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 Applicants Actions or Behavior Plant Response:

Statalarms:

• iSA-i/C-iC 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/BOP 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 1HP-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 28

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 Position Applicants Actions or Behavior Crew Response:

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

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

1A LPI PUMP

_1 B 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 End. 5.4 (TS/SLC Requirements)

TS 3.3.7 (ES Digital Channels)

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

TS 3.3.6 (ESPS Manual Initiation)

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

TS 3.3.6 (ESPS Manual Instrumentation) due to the manual actuation initiation being blocked if any ES component in MANUAL

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

TS 3.5.4 (BWST) BWST level Entry NOT required This event is complete when ES 3 components are secured, or as directed by the Lead Evaluator.

Page 11 of 28

Appendix D Scenario Outline Form ES-D-1 May, 201 1 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

• Nl-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 in MANUAL to stabilize the plant. (Board operator may also take the FDW Masters to HAND.)

> 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).

This event is complete when the plant is stable or if the Reactor is manually tripped, or as directed by the Lead Evaluator.

Page 12 of 28

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 7 Page 1 of 6 Event

Description:

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

Time Position Applicants Actions or Behavior Plant Response

• 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 all 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-1 6/1 7)

Page 13 of 28

Appendix D Scenario Outline Form ES-D-1 May, 201 1 Op-Test No.: Scenario No.: 3 Event No.: 7 Page 2 of 6 Event

Description:

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

Time Position ApplicanVs Actions or Behavior Crew Response:

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:

IA MD EFDWP

_1 B MD EFDWP

5. Feed and steam available SGs 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 1 TD 1 TE THEN GOTOStep9 RNO: GO TO 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 28

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 7 Page 3 of 6 Event

Description:

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

Time Position Applicants Actions or Behavior Crew Response:

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 jy 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 aH 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 ay 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 28

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 7 Page 4 of 6 Event

Description:

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

Time Position Applicants Actions or Behavior Crew Response:

BOP EOP Enclosure 5.38 (Restoration of Power)

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: GOTO Step 18

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-S 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)

_STANDBY1 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 16of28

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 7 Page 5 of 6 Event

Description:

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

Time Position Applicants Actions or Behavior Crew Response:

BOP 52. Place the following switches in MAN:

CT4 BUS 1 AUTO/MAN CT4 BUS 2 AUTO/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: (CT-8) (*Critical Steps to regain power.

Only one set of breakers is required to regain power)

SL1 CT5 STBY BUS 1 FEEDER*

_SL2CT5STBYBUS2 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 STBYBUS1 TOMFB1*

S2 STBY BUS 2 TO MFB2*

59. Verify jy of the following energized:

1TC, 1TD, 1TE

60. Notify Unit 1 CR SRO of status of 4160V SWGR Note: When power is restored, IAAT Step 8 (BIO Tab) will apply and the SRO will initiate APII I (steps next page) and GO TO the Subsequent Actions Tab.

Page 17of28

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario NoV: 3 Event No.: 7 Page 6 of 6 Event

Description:

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

Time Position Applicants Actions or Behavior Crew Response:

BOP AP/1 1 (Recovery From Loss of Power) 4.1 Announce AP entry using OMP 1-18 placard.

4.2 IAAT Pzr level > 8Q[18Qacc],

AND Pzr heaters are desired, THEN position Pzr heaters to AUTO.

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

iSA-i 5/D-4 (EL LOAD SHED CHNL A LOGIC INITIATE) 1SA-14/D-4 (EL LOAD SHED CHNL B LOGIC INITIATE) 4.10 Verify load shed is complete as indicated by LOAD SHED COMPLETE on any ES Module (Channel 1 or 2).

4.11 Close the following breakers:

1TC INCOMING FDR BUS 1 1TC INCOMING FDR BUS 2 lTD INCOMING FDR BUS 1 lTD INCOMING FDR BUS 2 1TE INCOMING FDR BUS 1 1TE INCOMING FDR BUS 2 4.12 Verify a 230KV Switchyard Isolation has occurred as indicated by either of the following on:

iSA-i 5/E-6 (EL SWYD ISOLATION CONFIRMED CHNL A LOGIC) 1SA-14/E-6 (EL SWYD ISOLATION CONFIRMED CHNL B LOGIC) 4.15 Verify load shed was initiated as indicated by either of the following statalarms on:

iSA-i 5/D-4 (EL LOAD SHED CHNL A LOGIC INITIATE) 1SA-14/D-4 (EL LOAD SHED CHNL B LOGIC INITIATE)

This event is complete when power has been restored and the transfer to Subsequent Actions has occurred, or as directed by the Lead Evaluator.

Page 18 of 28

Appendix D Scenario Outine Form ES-D-1 May, 201 1 Op-Test No.: Scenario No.: 3 Event No.: 8 Page 1 of 8 Event

Description:

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

Time Position Applicants Actions or Behavior Plant Response:

Control Board Indications:

• 1SA-21D-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 SUBCOOLING 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 lB LPI pump will not start)

Crew Response:

SRO

• SRO may direct an RO to perform a Symptoms Check OATC/BOP > Power Range NIs ] <5% and/or QI 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-1 6/1 7)

SRO

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

• Once y Subcooling Margin (SCM) indicates 0°F, the SRO will direct or concur initiation of Rule 2 (Loss of SCM) (see page 25)

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

Page 19 of 28

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

Description:

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

Time Position Applicants Actions or Behavior Crew Response:

SRO LOSCM Tab Parallel Actions

• SRO will direct an RO to initiate End 5.1 (ES Actuation) (see page22)

• 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 EDLs are in affect using PA system

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

2. Verify Station ASW feeding jy SG RNO: GO TO Step 4

4. Verify LOSCM caused by excessive heat transfer RNO: GO TO Step6

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 GOTO LOCACD 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 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 20 of 28

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

Description:

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

Time Position Applicants Actions or Behavior Crew Response:

Note: Once LPI flow is> 2900 gpm, IAAT Step 6 of the LOSCM Tab will 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 aM RBCUs in low speed Open 1 LPSW-1 8 Open 1 LPSW-21 Open 1 LPSW-24

8. Initiate End 5.35 (Containment Isolation)

9. Start all RB Aux fans

10. IAAT either of the following exists:

LPI FLOW TRAIN A 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 all 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 (1 LP-1 04 Bkr)

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

14. Dispatch an operator to perform End 5.28 (Local SG Isolation) to isolate both SGs This event is complete when the SRO has transferred to the LOCA CD Tab, or as directed by the Lead Evaluator.

Page 21 of 28

Appendix D Scenario Outline Form ES-D-1 May, 2011 Op-Test No.: Scenario No.: 3 Event No.: 8 Page 4 of 8 Event

Description:

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

Time_j Position Applicants Actions or Behavior

[

Crew Response:

EOP Enclosure 5.1 (ES Actuation)

OATC/BOP 1. Determine aM ES channels that should have actuated based on RCS pressure and RB pressure:

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

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

3. IAAT additional ES actuation setpoints are exceeded, THEN perform Steps 12

4. Place HPI in manual control

5. Verify Rule 2 in progress or complete

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

8. IAAT y RCP is operating, AND ES Channels 5 and 6 actuate, THEN perform Steps 9 11 RNO: GOTOStep12

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

13. Place the following in manual control:

1A LPI PUMP 1LP-17

_1 B LPI PUMP 1LP-18

14. IAAT jjy LPI pump is operating against shutoff head, THEN at the CR SROs discretion, stop affected LPI pumps Page 22 of 28

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

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

18. IAAT lAand lB LPI PUMPs are off/tripped, AND all the following exist:

RCS pressure < LPI pump shutoff head 1 LP-1 9 closed 1 LP-20 closed THEN perform Steps 1920 RNO: GO TO Step 21

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

22. IAAT lB LPI PUMP fails while operating, AND 1A LPI PUMP is operating, 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 23 of 28

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

Description:

LBLOCA With Failure of lB 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:

1 CF-i 1 CF-2

26. Verify i HP-4i 0 closed

27. Secure makeup to the LDST

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

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

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

29. Verify Unit 2 turbine tripped RNO: GOTO Step 32

32. Close 1 LPSW-1 39

33. Place the following in FAIL OPEN:

_1 LPSW-25i FAIL SWITCH 1 LPSW-252 FAIL SWITCH

34. Start all available LPSW pumps

35. Verify either of the following:

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

36. Open the following:

1LPSW-4 1 LPSW-5

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

Page 24 of 28

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

Description:

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

Time Position Applicants Actions or Behavior Crew Response:

Rule 2 (Loss of SCM)

OATC/BOP 1. IAAT all the following exist:

y SCM 0°F

_Rxpower 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 the following:

1 HP-24 1HP-25

7. Start all available HPI pumps

8. Open the following:

1 HP-26 1 HP-27

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

10. IAAT 2 HPI pumps are operating, AND HPI flow in y 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 pumps operating Total flow of 950 gpm with 1HP-409 open (md. seal injection)

THEN throttle HPI to maximize flow flow limit Page 25 of 28

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

Description:

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

E Time Position Crew Response:

Applicants Actions or Behavior 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 1FDW-315 in MANUAL and close Place 1FDW-316 in MANUAL and close Place 1 FDW-35 in HAND and close Place IFDW-44 in HAND and close

17. Notify crew that performance of Rule 3 is NOT required due to LB LOCA

18. WHEN directed by CR SRO, THEN EXIT this rule This scenario is complete when stable core cooling is established, or as directed by the Lead Evaluator.

Page 26 of 28

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

1. CT-8 Electrical Power Alignment

2. CT-4 Initiate LPI (within 60 minutes of no LPI flow when required)

3. CT-27 Implementation of Control Room Habitability Guidance (Within 30 minutes of ES Actuation)

Page 27 of 28

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

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

Unit I Simulator Other Units Mode: 2 Unit 2 Unit 3 Reactor Power: 3% Mode: 1 Mode: 1 Gross MWE: 0 100% Power 100% Power RCS Leakage: -t025gprn action level) EFDW Backup: Yes EFDW Backup: Yes RBNS Rate: .01 gpm Technical Specifications!SLC Items (CR SRO)

Component/Train OOS Restoration TS/SLC #

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

Primary

. SASS in MANUAL for I&E testing

. AMSAC/DSS Bypassed

. Pressurize the LDST with H2

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

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

Secondary

• 1SSH-1, 1SSH-3, 1SD-2, 1SD-5, ISD-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: 1688 ppmB Gp 6 Rod Position: 49%

Human Performance Emphasis (OSM)

Procedure Use and Adherence Page 28 of 28