ML12270A417

Initial Exam 2012-301 Final Simulator Scenarios

ML12270A417
Person / Time
Site:	Oconee
Issue date:	09/24/2012
From:	NRC/RGN-II
To:	Duke Energy Carolinas
References
Download: ML12270A417 (120)

Text

iAL Facility: Oconee Scenario No.: I ri Op-Test No.: 1 Examiners: Operators:, SRO OATC BOP Initial Conditions:

. Reactor Power 85% Unit 2: 100%, Unit 3: 100%

Turnover:

• Holding power at 85% while monitoring 1A FDWP due to issues with oil coolers. Have the OSM notify component engineer immediately if any unusual alarms/indications occur.

• TDEFWP MS supplies OOS. TDEFWP supply from AS only.

• SASS in Manual for I&E

• 1 MS-82 and I MS-84 closed in support of maintenance. TDEFWP operable on AS only.

• Maintain Letdown Flow 71 gpm for Letdown Cooler performance evaluation

• Perform Control Rod movement PT (Group I only) per PT/1/A/0600/015 Enclosure 13.2 (Control Rod Movement At Power) beginning at Step 3.3 (Rx Diamond and FDW Masters in Hand)

Event Malfunction Event No. No. Event Type* Description Oa Override SASS in Manual Ob MS5330 Disable TDEFWP start Oc Override Disable Standby LPSWP Auto start 1 N: OATC, SRO Control Rod Movement PT (Group 1 only) 2 Override C: BOP, SRO (TS) Operating LPSW Pump Trips, Standby LPSW Pump Fails To Auto Start (TS) 3 MCSOO8 C, BOP, SRO (TS) Failure of AS Controller (TS):

4 C, BOP, SRO 1A Letdown Cooler Leak 5 MCSOO4 I: OATC, SRO Tave Fails HIGH 6 Override R: OATC, SRO 1A MFWP Oil Cooler Outlet Temperature High requiring a manual power reduction to secure pump.

MSS010 M55020 Loss of Main and Emergency Feedwater M55260 M:ALL LOHT Tab M55270 CBP feed CBPs trip requiring HPI Forced cooling 8 Override ALL 1 HP-24 will not open Transfer to HPI CD Tab (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 ILT41 Juneil, 2012 Op-Test No.: ILT4I Scenario No.: I Event No.: 1 Page 1 of 4 Event

Description:

Control Rod Movement PT (Group 1 only)

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 NOTE: When operating switches on Diamond, maintain switch depressed SRO/OATC 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/1/A11103/015 (Reactivity Balance Procedure) to be valid.

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

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

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

NOTE:

• 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 I B. WHEN all 100% lights OFF, stop insertion C. Begin Group I withdraw to 100%. (1SA-2/C-10 clears)

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

Page2of36

Appendix D Scenario Outline Form ES-D-1 ILT41 June11, 2012 Op-Test No.: ILT4I Scenario No.: I Event No.: I Page 2 of 4 Event

Description:

Control Rod Movement PT (Group I only)

Time Position Applicants Actions or Behavior PTIIIAIO600IOI5 Enclosure 13.2 NOTE: In RUN speed, all rod motion is inhibited 12 seconds after first rod SRO/OATC 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/A/I 102/004 A (ICS Operation)

OP/1/A11102/004 A End 4.1 (Placing Rx Diamond/FDW Masters To Hand) 2.9 WHEN required, place ICS back in auto as follows:

2.9.1 Ensure RATE SET thumbwheels at 0.0 Note: Step 2.9.2 and 2.9.3 are NIA 2.9.2 IF TURBINE MASTER is in manual, perform the following:

2.9.3 IF Rx Master is in HAND, perform the following:

2.9.4 IF DIAMOND is in manual, perform the following:

A. Verify REACTOR MASTER in AUTO This event is complete when ICS has been returned to AUTO, or as directed by the Lead Examiner.

Page3of36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: I Event No.: I Page 3 of 4 Event

Description:

Control Rod Movement PT (Group I only)

Time

[ Position Applicants Actions or Behavior B. IF both SGs are off of Level Control, perform the following:

SRO/OATC Examiner Note: It is not expected that Tave & setpoint will be different by more than +/-0.15°F so B.1 will likely NOT be performed.

1. IF selected Tave (01 E2086) is different from Tave setpoint (01E2087) by more than 0.15°F, perform the following:

a. Simultaneously perform the following:

• Ensure 1A FDW MASTER in HAND

• Ensure lB FDW MASTER in HAND NOTE: Cycling the setpoint selector may result in a Star Module failure. This is expected for this condition and entry into APII/A117001028 (ICS Instrument Failures) is NOT required. The Star Module failure shall be cleared before the ICS is returned to Auto.

b. On REACTOR MASTER, cycle Tave setpoint selector between 565°F and 585°F five times.

c. IF Star Module failed, perform the following:

1) Initiate Work Request to repair Star Module.

2) WHEN Star Module repaired, continue procedure.

d. 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 C. IF either SG is on Level Control, adjust Tave setpoint (01 E2087) to 579°F D. Place DIAMOND in AUTO 2.9.5 Ensure STM GENERATOR MASTER in AUTO 2.9.6 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 I B FDW Master Measured Variable is NOT on the caret, notify SPOC to investigate and repair the problem C. Verify the following:

• 1A FDW MASTER Measured Variable on the caret

• lB FDW MASTER Measured Variable on the caret This event is complete when ICS has been returned to AUTO, or as directed by the Lead Examiner.

Page4of36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: j_ Event No.: _j._ Page 4 of 4 Event

Description:

Control Rod Movement PT (Group I only)

Time Position Applicants Actions or Behavior SRO/OATC D. Perform the following:

• Select 1A FDW MASTER to POS

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

• Select 1A FDW MASTER to AUTO

• Select I B FDW MASTER to AUTO Examiner Note: Setpoint adjustments should not be required in step 2.10 and therefore N/A per note below CAUTION:

Adjusting THP, Tave or Delta Tc setpoint too fast can cause plant instability.

NOTE:

If other approved procedures require THP, Tave or Delta Tc to be different than normal setpoint or setpoint adjustment is NOT required then applicable step will be NA.

2.10 Perform the following 2.10.1 If required, slowly adjust THP Setpoint (01E2089) to 885 psig.

2.10.2 If required, slowly adjust Tave setpoint to 579°F.

2.10.3 If required, adjust Delta Tc Setpoint (01 E2091) to 0.0°F.

2.11 IF desired adjust CTP as follows:

Note: Step 2.11 is not required for this scenario.

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

Page 5of36

Appendix D Scenario Outline Form ES-D-1 ILT41 June11, 2012 Op-Test No.: ILT4I Scenario No.: I Event No.: 2 Page 1 of 2 Event

Description:

Operating LPSW Pump Trips, Standby LPSW Pump Fails To Auto Start (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

• LPSW leakage accumulator level

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

• LPSW Header NB Pressure Low SRO/BOP Crew response:

• Refer to QAC alarm response

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

2. Notify engineering

3. RefertoTS3.7.7

• Refer to ARG for 1 SA-91A-9 (LPSW Header NB Press Low) 3.1 Refer to AP/1/N1700/024 (Loss of LPSW) 3.2 Have Unit 2 refer to AP/2/N1 700/024 (Loss of LPSW).

Booth Cue: If notified to refer to AP/2/A11700/024, inform operator that AP/2JA!1700/24 will be referenced.

AP/1/N1700/024 (Loss of LPSW) steps begin on next page.

Page 6 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: I Event No.: 2 Page 2 of 2 Event

Description:

Operating LPSW Pump Trips, Standby LPSW Pump Fails To Auto Start (TS)

Time Position

[ Applicants Actions or Behavior SRO/BOP AP111A117001024 (Loss of LPSW) 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 aM 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 SRO The SRO should refer to TS:

• TS 3.7.7 (Low Pressure Service Water System) o 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.

o Condition B applies due to LPSW Leakage Accumulator Level Alarm (exit this TS Condition when alarm clears).

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

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

Page7of36

Appendix D Scenario Outline Form ES-D-1 ILT4I June 11,2012 Op-Test No.: ILT4I Scenario No.: I Event No.: 3 Page 1 of 2 Event

Description:

Failure of AS Controller (TS):

Time Position Applicants Actions or Behavior Plant response:

• 1SAO6IC-10, AS HDR PRESS LOW will actuate

• 1MS-126 & 1MS-129 MAIN STM TO SU STM PRESS controller will indicate AS pressure < 300 psig and decreasing.

Crew response:

ISAO6IC-IO ARG SRO/BOP Booth Cue: While the crew is referring to the ARG, call Unit I control room to notify them (using time compression) that Unit 2 AS Controller has failed and Unit 3 cannot take control. The OSM is directing you as Unit I to take control of AS system pressure.

3.1 IF excessive steam flow exists, reduce AS load or locate and isolate leak.

3.2 Verify proper operation of MS/AS controller on Unit supplying Auxiliary Steam Header (U2).

3.3 IF necessary, transfer AS Header to another Unit per OP/1/A11106/22 (Auxiliary Steam System).

0P111A11106122 (Auxiliary Steam System) End 4.2 2.1 Notify Unit 2 to reduce setpoint on AS controller. (no actions required since pressure is below setpoint due to the failure).

2.2 Ensure 1MS-126 & 1MS-129 (MAIN STM TO SU STM PRESS) controller in MANUAL.

2.3 Ensure closed 1MS-126 & IMS-129 (MAIN STM TO SU STM PRESS).

2.4 Verify Unit 2 has reduced setpoint on AS controller. (no actions required since pressure is below setpoint due to the failure) 2.5 Perform one of the following: Open 1 MS-24 (or Open 1 MS-33) 2.6 Manually throttle open 1MS-126 & 1MS-129 (MAIN STM TO SU STM PRESS) to increase Aux Steam Header pressure.

2.7 Continue to throttle 1MS-126 & 1MS-129 (MAIN STM TO SU STM PRESS) to increase Aux Steam Header pressure to 300 psig.

2.8 WHEN Aux Steam Header is 300 psig:

2.8.2 Adjust 1MS-126 & 1MS-129 (MAIN STM TO SU STM PRESS) controller setpoint to match Aux Steam Header pressure.

Place 1MS-126 & 1MS-129 (MAIN STM TO SU STM PRESS) controller to AUTO.

2.9 Notify Unit 2 to secure AS supply.

This event is complete when the Unit I AS controller is in AUTO and Tech Spec determination has been made or when directed by the lead examiner.

Page8of36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: I Event No.: 3 Page 2 of 2 Event

Description:

Failure of AS Controller (TS):

Time Position Applicants Actions or Behavior SRO NOTE to Examiner: Since AS pressure is set to go to < 250 psig, the belowTS 1 applies.

The SRO should refer to TS:

TS 3.7.5 (Emergency Feedwater (EFW) System) o Condition B applies. Restore turbine driven EFW pump and EFW flow path to Operable status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND 10 days from discovery of failure to meet LCO.

This event is complete when the Unit I AS controller is in AUTO and Tech Spec determination has been made or when directed by the lead examiner.

Page 9 of 36

Appendix D Scenario Outline Form ES-V-i JLT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: I Event No.: 4 Page 1 of 4 Event

Description:

IA Letdown Cooler Leak Time Position Applicants Actions or Behavior Plant Response:

Statalarms:

1SA-08/B-9 (PROCESS MONITOR RADIATION HIGH)

Crew Response:

SRO/ BOP ISA-08/B-9 3.1 Determine radiation monitors in alarm.

3.1.1 IF VIEW node OR either SCADA node is NOT in service, refer to OP/I/NI 103/026, (Loss of Sorrento Radiation Monitor).

NOTE TO EXAMINER: Steps 3.2 through 3.10 are IF statements for which RIA is in alarm. In this case, the crew determines the radiation monitor alarming is 1 RIA-50, so step 3.9 applies.

3.9 IF any of the following RIAs have valid alarms, GO TO AP/1 8 (Abnormal Release of Radioactivity).

RU RLk-3 1 IRIA-32 tRIA35 RIA-39 IRIA-41 IRIA-42 1IA-454 48 4P, 4c?k I RIA-50 I RIA-54 SRO/BOP APII8 (Can be performed by Unit 2 if API2 has been entered) 4.1 Perform the following:

At the discretion of the CR SRO, make a PA announcement of the event including any necessary precautions to be observed.

Notify OSM to reference the following:

• RP/0/B/1000/00I (Emergency Classification).

. NSD-202 (Reportability) a OMP 1-14 (Notifications)

This event is complete when IA Letdown cooler has been isolated and the crew has determined the leakage has stopped OR as directed by the lead examiner.

Page 10 of 36

Appendix D Scenario Outline Form ES-D-1 ILT4I June 11,2012 Op-Test No.: ILT4I Scenario No.: I Event No.: 4 Page 2 of 4 Event

Description:

IA Letdown Cooler Leak Time_j Position Applicants Actions or Behavior SRO /BOP APII8 (cont) 4.2 GO TO appropriate sections for any monitors in High or Alert alarm:

NOTE TO EXAMINER: Crew should go to Section 41 for 1 RIA-50.

[ 41 1RLA5O Section 41 1 Verify either of the following:

• CC SURGE TANK increasing 5/hour

• CC SURGE TANK off-scale high

2. Initiate AP/2 (Excessive RCS Leakage).

SRO/BOP API2 Immediate Actions 3.1 Verify HPI operating.

3.2 IAAT RC makeup flow is> 100 gpm, AND Pzr level is decreasing, THEN close 1HP-5.

3.3 IAAT all the following exist:

• HPI flow is> NORMAL MAKEUP CAPABILITY (160 gpm) with letdown isolated

• Pzr level decreasing

• SG Tube Leakage NOT indicated

• LPI DHR NOT providing core cooling THEN perform the following:

A. Ensure Rx is tripped.

B. Initiate Unit 1 EOP.

Subsequent Actions 4.1 Initiate Pzr and LDST level makeup using Unit 1 EOP End 5.5 (Pzr and LDST Level Control), as necessary.

4.2 Announce AP entry using the PA system.

4.3 IAAT LPI DHR in service, AND RCS leakage > LDST makeup capability (50 gpm),

THEN GO TO AP/26 (Loss of Decay Heat Removal).

This event is complete when IA Letdown cooler has been isolated and the crew has determined the leakage has stopped OR as directed by the lead examiner.

Page II of36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: I Event No.: Page 3 of 4 Event

Description:

IA Letdown Cooler Leak Time Position

[ Applicants Actions or Behavior SRO /BOP AP/2 (Cont) 4.4 Initiate the following notifications:

OSM to reference the following:

• RP/OIB/1 000/001 (Emergency Classification)

• OMP 1-14 (Notifications)

• End 5.9 (Oversight Guidelines)

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

• T6 APO2

• T6 WASTE

• RIAs 4.6 Verify specific leak location is identified.

4.7 Initiate End 5.1 (Leak Rate Determination). (This will calculate RCS leakage based on CC surge tank level increase and is a very gross calculation since there is no OAC point for CC surge tank level and therefore control room gage must be used.)

4.8 WHEN leak area/failure is identified, THEN GO TO applicable step that best fits leak area/failure:

1 CC 1P1A-5O 4J6 Syteiu CC Swg Taik LevI 4.16 Verify all of the following:

• CC Surge Tank level increasing at 5/ hour (0.65 gpm) or level is off-scale high

• 1 RIA-50 in alarm or increasing 4.17 IAAT CC Surge Tank level is off-scale high, THEN notify Radwaste that the CC Surge Tank has overflowed to the LAWT.

4.18 IAAT RCS leakage is flashing the CC system, OR threatens to overflow the LAWT, THEN perform the following: NIA at this time 4.19 Verify leakage indicated by change in RCP cooler outlet temperatures (Turn-on code GD APO2): (No leakage indicated)

RNO GO TO Step 4.24 This event is complete when IA Letdown cooler has been isolated and the crew has determined the leakage has stopped OR as directed by the lead examiner.

Page 12 of 36

Appendix D Scenario Outline Form ES-D-1 ILT4I June 11,2012 Op-Test No.: ILT4I Scenario No.: j_ Event No.: 4 Page 4 of 4 Event

Description:

IA Letdown Cooler Leak Time Position Applicants Actions or Behavior j

SRO /BOP API2 (cont)

NOTE RCS leakage to CC in the letdown coolers may be indicated by a cooler outlet temperature increasing more than the other cooler. Due to CC system setup, letdown cooler CC outlet temperatures may be different. A historical OAC temperature trend may be required to determine if leakage exists and if actions taken are successful in leak isolation. If leaking cooler CANNOT be identified, the coolers will be isolated one at a time starting with the 1A Letdown Cooler.

4.24 Monitor letdown cooler outlet temperatures to determine which cooler is leaking (Turn-on code GD APO2):

• 01A0065 (LETDOWN COOLER 1A CC OUTLET TEMP)

• O1A0066 (LETDOWN COOLER 1 B CC OUTLET TEMP) 4.25 GO TO the appropriate step to isolate affected cooler:

NOTE TO EXAMINER: According to the Note above and the table below, the crew ends up in the same place whether they have diagnosed which cooler is leaking or not. Either path is acceptable and ends up with the 1A cooler isolated.

Letdown Cooler GO TO Step to b Iolted IA 426 lB 433 Unlznown 426 4.26 Verify 1 B Letdown Cooler is isolated.

RNO: I Isolate the 1A Letdown Cooler by performing the following:

A. Close 1CC-i/l HP-I.

B. Close 1HP-3.

2. GOTO Step 4.31.

4.31 Verify the leak isolation was successful:

• CC Surge Tank level stable if 1 CC-7 and 1 CC-8 open

• Decrease in RCS leakage This event is complete when IA Letdown cooler has been isolated and the crew has determined the leakage has stopped OR as directed by the lead examiner.

Page 13 of 36

Appendix D Scenario Outline Form ES-D-1 ILT4I June 11,2012 Op-Test No.: ILT4I Scenario No.: I Event No.: 5 Page 1 of 2 Event

Description:

Tave Fails HIGH 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.

Crew response:

• When the Statalarms are received, the candidates should announce the SRO/OATC initial alarm and utilize the Plant Transient Response process to stabilize the plant.

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

• Place the Diamond and both FDW Masters in manual and reduce feedwater as necessary to stabilize the plant.

• The SRO should:

• Refer to AP/28, ICS Instrument Failures SRO

• Contact SPOC to repair controlling Tave.

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

Booth and Examiner Cue: If during plant stabilization the reactor trips or is tripped, fire TIMER 6 and go to Event 6 AP/28 4.1 Provide control bands as required 4.2 Initiate notification of the following:

OSM to reference the following:

• OMP 1-14 (Notifications)

• Emergency Plan STA 4.3 Verify a power transient 5% has occurred. RNO: GO TO Step 4.5 4.4 Notify Rx Engineering and discuss the need for a maneuvering plan.

4.5 Determine the applicable section from table in Step 4.6 4.6 GO TO Section 4A, RCS Temperature This event is complete when the SRO reaches the WHEN step (6) in Section 4A or when directed by the lead examiner this event is completed.

Pagel4of36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11, 2012 Op-Test No.: ILT4I Scenario No.: I Event No.: 5 Page 2 of 2 Event

Description:

Tave Fails HIGH Time Position Applicants Actions or Behavior Section 4A 1 Ensure the following in HAND:

SRO/OATC 1A FDW MASTER lB FDW MASTER 2 Ensure DIAMOND in MANUAL SRO/BOP 3 Notify SPOC to perform the following:

Select a valid RCS Tave and Delta Tc input to ICS per AM/i /A/0326/020 (Control of Unit I Star Module Signal Selection Function).

Investigate and repair the failed RCS temperature instrumentation.

Examiner Note: The applicable table in End. 5.2 is Table 1 which requires the operator to verify RCS loop average temperature is within limits specified in the COLR. The surveillance is only applicable if the reactor is at Steady State therefore if power has changed by more than 4% the surveillance is not required to be met.

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

SRO/BOP 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).

This event is complete when the SRO reaches the WHEN step (6) in Section 4A or when directed by the lead examiner this event is completed.

Page 15 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: I Event No.: Page 1 of 4 Event

Description:

IA MFWP Oil Cooler Outlet Temperature High requiring a manual power reduction to secure pump.

Time__[ Position [ Applicants Actions or Behavior Plant Response:

OAC Alarms:

• HI alarm at 135°F

• HI-HI alarm at 160° F STAT Alarms:

Hi alarm:

• ARG I SA-08/E-4, FWPT A Oil cooler Discharge Temperature High Hi Hi alarm:

• ARG I SA-081E-3, FWPT A HP/LP Bearing Drain Temperature High SRO/BOP Crew Response:

Refer to the OAC Alarm Response:

EXAMINERIBOOTH NOTE: Based on turnover and OAC alarm response, the SRO will direct an operator to notify the OSM to contact the component engineer regarding the temperature alarms. The Booth will use time compression and inform the operator that the OSM and component engineer recommend reducing power and tripping the 1A Main Feedwater Pump as quickly as can be done safely. The target power level will be either below 65%

or >10% below the current power level (whichever is lower).

1. Refer to ARG 1 SA-081E-4, FWPT A Oil cooler Discharge Temperature High 3.1 Verify 1 RCW-52 (FWPT Oil Cooler 1A Temperature Control) is open.

3.2 IF 1RCW-52 (FWPT Oil Cooler lATemperature Control) is NOT controlling temperature, open 1RCW-54 (FWPT Oil Cooler 1A Temperature Control Bypass) to bypass flow around 1 RCW-52.

3.3 IF alarm does NOT clear, place alternate cooler in service.

2. Notify System Engineer The SRO should initiate AP129 (Rapid Unit Shutdown) to direct power reduction SRO/BOP in support of securing the 1A MFWP AP129 4.1 Initiate End 5.1 (Support Actions During Rapid Unit Shutdown)

BOP (Details on page 19) 4.2 Announce AP entry using the PA system.

This event is complete when the IA MFW Pump has been tripped or as directed by the lead examiner.

Page 16 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: I Event No.: 6 Page 2 of 4 Event

Description:

IA MFWP Oil Cooler Outlet Temperature High requiring a manual power reduction to secure pump.

Time Position Applicants Actions or Behavior OATC 4.3 IAAT both of the following apply:

It is desired to stop power decrease.

_CTP> 18%

THEN perform Steps 4.4 4.7 (Does NOT apply now)

RNO: GO TO Step 4.8 4.8 Verify lOS in AUTO (It is NOT in Auto)

SRO/OATC RNO: 1. Initiate manual power reduction to desired power level.

Examiner Note: OATC reduces power by first reducing feedwater and then inserting control rods as necessary.

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.

BOP

• 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 until its suction flow is 1 X 106 Ibm/hr less than remaining Main FDW pump suction flow.

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

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

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

jy of the following alarms occur:

• FWP B FLOW MINIMUM (ISA-16/A-3)

OATC/BOP

• FWP B FLOW BELOW MIN (ISA-16/A-4)

THEN trip I B Main FDW Pump. (Does Not Apply) 4.14 IAAT both Main FDW pumps running, AND both of the following exists:

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

• FWPA FLOW MINIMUM (1SA-16/A-1)

• FWP A FLOW BELOW MIN (1SA-16/A-2)

THEN trip 1A Main FDW Pump This event is complete when a 10% power change has occurred or as directed by lead examiner.

Page 17 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: I Event No.: 6 Page 3 of 4 Event

Description:

IA MFWP Oil Cooler Outlet Temperature High requiring a manual power reduction to secure pump.

Time Position ApplicanVs Actions or Behavior OATC/BOP EXAMINER NOTE: If crew takes an inordinate amount of time deciding to trip the 1A MFWP, have the booth operator fire the timer to trip the pump.

4.15 Verify Turbine-Generator shutdown is required.

4.16 Start the TURBINE TURNING GEAR OIL PUMP.

4.17 Start 1A through 1E TURBINE BRNG OIL LIFT PUMPS.

4.18 Start the TURBINE MOTOR SUCTION PUMP.

4.19 IAAT both of the following apply:

ICS in automatic NI power is 18%

THEN deselect MAXIMUM RUNBACK.

4.20 Verify Turbine-Generator shutdown is required.

RNO:

NOTE:

Due to the power decrease initiated in this AP, the current plant configuration must be compared to the normal plant configuration in OP/i/NI 102/004 (Operation at Power) power reduction enclosure. Equivalent steps performed by this AP should be signed off as intent met. Any steps NOT performed by this AP must be evaluated in preparation for power increase or continued shutdown.

1. Initiate OP/1/N1102/004 (Operation at Power) power reduction enclosure.

2. WHEN conditions permit, THEN GO TO appropriate operating procedure for continued operation.

This event is complete when a 10% power change has occurred or as directed by lead examiner.

Page 18 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: I Event No.: 6 Page 4 of 4 Event

Description:

IA MFWP Oil Cooler Outlet Temperature High requiring a manual power reduction to secure pump.

Time Position j Applicants Actions or Behavior AP/29 End. 5.1 BOP 1. Notify WCC SRO to initiate End 5.2 (WCC SRO Support During Rapid Unit Shutdown).

2. Start the following pumps:

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

3. WHEN CTP is 80%, THEN continue.

4. Stop 1E1 HTR DRN PUMP.

5. Place 1HD-254 switch to OPEN.

6. Stop 1 E2 HTR DRN PUMP.

7. Place 1HD-276 switch to OPEN.

8. Verify Turbine-Generator shutdown is required. (It is NOT required)

RNO: GO TO Step 20.

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

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

1 FDW-53 1 FDW-65

22. IAAT load is 550 MWe, THEN perform Steps 23 24. -

RNO: GO TO Step 25.

25. WHEN CTP is 60%, THEN ensure 1SSH-9 closed.

This event is complete when a 10% power change has occurred or as directed by the lead examiner.

Page 19 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: I Event No.: 7 Page 1 of 4 Event

Description:

Loss of Main and Emergency Feedwater LOHT Tab CBP feed Time Position Applicants Actions or Behavior Plant Response:

When directed by the Lead Examiner, a Loss of Main and Emergency Feedwater will occur.

SRO/OATC Crew Response:

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.

BOP will perform a Symptom Check and initiate Rule 3 (Loss of Main and I or Emergency Feedwater)

SRO will transfer to the Loss Of Heat Transfer Tab based on Parallel Actions page.

Page 20 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: I Event No.: 7 Page 2 of 4 Event

Description:

Loss of Main and Emergency Feedwater LOHT Tab CBP feed A__Time_J Position

[ Rule 3 Applicants Actions or Behavior BOP/OATC

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).

Start EFDW pumps to feed all intact SGs.

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

5. Verify any EFDW pump operating.

RNO: GO TO Step 7.

7. Place the following in MANUAL and close:

• 1FDW-315

• 1FDW-316

8. Verify both of the following:

• Any CBP operating

• TBVs available on an intact SG

9. Select OFF for both digital channels on AFIS HEADER A.

10. Select OFF for both digital channels on AFIS HEADER B.

11. Place 1 FDW-33 and 1 FDW-42 control switches in OPEN

12. Simultaneously position Startup Control valves (1 FDW-35 1 FDW-44) 10 - 20% open on intact SGs

13. Perform the following:

• Place 1FDW-31 switch in CLOSE.

• Place 1 FDW-40 switch in CLOSE.

• Close 1 FDW-32.

• Close 1 FDW-41.

Page 21 of 36

Appendix D Scenario Outline Form ES-D-1 ILT4I June11, 2012 Op-Test No.: ILT4I Scenario No.: I Event No.: j.. Page 3 of 4 Event

Description:

Loss of Main and Emergency Feedwater LOHT Tab CBP feed Time Position Applicants Actions or Behavior Rule 3 (Continued)

BOP/OATC

14. Verify Rule 4 (Initiation of HPI Forced Cooling) in progress.

RNO: (CT-Il, Control SG Pressure to Maintain RC Temperature Constant)

1. Lower SG pressure in available SGs to 500 psig.

2. Control FDW flow to stabilize RCS P/T by throttling the Startup Control valves and TBVs as necessary:

3. Notify CR SRO that CBP feed is in progress

4. Place 1 FDW-38 and 1 FDW-47 switches to OPEN

5. Place 1 FDW-36 and I FDW-45 switches to CLOSE

6. GOTOstepl6

16. Verify 1 TD EFDW PUMP is operable and available for manual start.

17. Dispatch an operator to perform End 5.26 (Manual Start of TDEFDWP).

18. Verify cross-tie with Unit 2 is desired.

19. Dispatch an operator to open 2FDW-313 and 2FDW-314

20. Dispatch an operator to 1 FDW-31 3 and have them notify the CR when in position.

21. Notify Unit 2 to:

• Manually Close 2FDW-315 & 316.

• Start their U2 TDEFWP

22. WHEN, either of the following exists: 1 FDW-31 3 Operator in position OR Unit 1 TDEFWP has been manually started; THEN continue.

Page 22 of 36

Appendix D Scenario Outline Form ES-D-1 ILT4I June 11,2012 Op-Test No.: ILT4I Scenario No.: Event No.: Page 4 of 4 Event

Description:

Loss of Main and Emergency Feedwater LOHT Tab CBP feed Time Position Applicants Actions or Behavior Loss Of Heat Transfer Tab

1. Ensure Rule 3 in progress or complete.

NOTE: Transfer to LOSCM tab is NOT required if RCS heats to the point SRO/BOP/

where core SCM = 0°F.

OATC

2. IAAT the RCS heats to the point where core SCM = 0°F, THEN GO TO Step 4.

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

• RCS pressure reaches 2300 psig OR NDT limit

• Pzr level reaches 375 [340 acc]

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

RNO:

NOTE: 1A1 RCP provides the best Pzr spray.

1. Reduce operating RCPs to one pump/loop.

2. WHEN y of the following exists:

• EFDW flow has been re-established by existing Rules/Enclosures

• EFDW aligned from another unit

• Operator performing Rule 3 (Loss of Main or Emergency FDW) or End 5.27 (Alternate Methods for Controlling EFDW Flow) reports EFDW available THEN GO TO Step 48 Examiner Note: The SRO will wait at the WHEN step until one of the bullets are met or until an outstanding IAAT is met. The crew may initiate EOP End 5.5 for inventory control. These steps are included beginning on page 27. To initiate Event 8, IAAT step 3 will be met by tripping the CBPs.

The EOP path for Event 8 continues on Page 24.

This event is complete when RCS temperature is stabilized on Condensate Booster Pump feed or as directed by the lead Examiner.

Page 23 of 36

Appendix D Scenario Outline Form ES-D-1 TLT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: I Event No.: 8 Page 1 of 3 Event

Description:

CBPs trip requiring HPI Forced cooling, I HP-24 will not open, Transfer to HP CD Tab Time Position Applicants Actions or Behavior Loss of CBPs Plant Response:

CBPs trip

• Feedwater flow decreases

• RCS temperature increases Crew Response:

SRO SRO may direct RO to re-perform Rule 3 however there are no EFDWPs available and all required actions will already have been performed during the initial performance of Rule 3.

At 2300 psig RCS pressure, direct performance of Rule 4 (HPI Forced Cooling).

Rule 4 (CT-14 Initiate HPI Forced Cooling Within 5 minutes of BOP/OATC meeting criteria)

1. Verify any HPI pump can be operated.

2. Open IHP-24 and IHP-25.

Examiner Note: IHP-24 will NOT open requiring the RNO actions.

RNO: IF only one BWST suction valve (1 HP-24 or 1 HP-25) is open, THEN perform the following:

A. IF three HPI pumps are operating, THEN secure 1 B HPI PUMP.

B. IF < 2 HPI pumps operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers.

C. GOTOStep4.

Examiner Note: When 1 HP-26 is opened, the standby HPI pump may start due to low seal injection flow. If so, the student should stop one of the HPI pumps because only I BWST suction valve is open (1 HP-24 would not open). The guidance to do this is contained in Rule 6.

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

5. Open 1RC-4.

6. Verify flow exists in y HPI header.

7. Open PORV. (Switch to OPEN, depress OPEN permit)

8. Verify at least two HPI pumps operating.

This event is complete when the SRO transfers to the HPI CD tab or as directed by the lead Examiner.

Page 24 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: I Event No.: 8 Page 2 of 3 Event

Description:

CBPs trip requiring HPI Forced cooling, I HP-24 will not open, Transfer to HP CD Tab Time [ Position Applicants Actions or Behavior Rule 4 (Cont.)

BOP/OATC 9. Verify flow in both HPI headers is in the acceptable region of Figure

10. Verify flow exists in any HPI header

11. Open PORV. (PORV will already be opened from performing step 7)

12. Verify > one RCP operating.

13. Stop all but one RCP. (note: prefer leaving 1A1 RCP running)

14. IAAT the following limits are exceeded,

• 1 HPIP 475 gpm (md. SI)

• IA & lB HPIP with 1HP-409 open -950 gpm (md. SI)

THEN throttle HPI to maximize flow flow limit.

15. De-energize all Pzr heaters.

16. Close 1HP-5.

17. Close TBVs, 1 FDW-35 and 1 FDW-44.

18. IAAT all HPI is lost, stop all RCPs and close the PORV

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

Booth Cue: If the crew requests that Unit 2 handle APII8 due to RIA alarms, reply that Unit 2 WILL handle APII 8.

This event is complete when the SRO transfers to the HPI CD tab or as directed by the lead Examiner.

Page 25 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: I Event No.: 8 Page 3 of 3 Event

Description:

CBPs trip requiring HPI Forced cooling, IHP-24 will not open, Transfer to HPI CD Tab Time Position Applicants Actions or Behavior LOHT tab SROIOATCI BOP Determine that IAAT step 3 is met:

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

5. Verify aM the following:

• At least two HPI pumps operating

• Acceptable HPI flow exists in both HPI headers per Rule 4

• PORV open

• IRC-4 open

6. GO TO HPI CD tab.

HPI CD tab SRO/OATC/ 1. IAAT BWST level is 19, THEN initiate End 5.12 (ECCS Suction BOP SwaptoRBES).

2. 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 LOCA CD tab.

3. Verify aM of the following exist:

• PORV open

• 1RC-4 open

• Two HPI trains injecting

• CETCs640°F

4. Perform the following:

• Ensure all RBCUs in low speed.

• Open 1LPSW-18, 1LPSW-21 and 1LPSW-24.

5. Initiate End 5.35 (Containment Isolation)

This event is complete when the SRO transfers to the HPI CD tab or as directed by the lead Examiner.

Page 26 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Page 1 of 8 NOTE At any time during this scenario the operator may choose to use Enclosure 5.5 to maintain RCS inventory control. See below.

ENCLOSURE 5.5 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Maintaining Pzr level >100 [180 accj will ensure Pzr heater bundles remain covered.

1. Utilize the following as necessary to IF I HP-26 will NOT open, maintain desired Pzr level: THEN throttle 1 HP-41 0 to maintain

. 1A HPI Pump desired Pzr level.

. IBHPI Pump

. 1HP-26

. 1HP-7

. 1HP-120 setpoint or valve demand

. 1HP.-5

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

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

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

A. Open:

1CS-26 1CS-41 B. Position 1HP-l4to BLEED.

C. Notify SRO.

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

Page 27 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Page 2of8 ENCLOSURE 5.5 (cont.)

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

6. IAAT IC HPI PUMP is required, GO TO Step 10.

THEN perform Steps 7-9.

7. Open: l._ IF both BWST suction valves

• 1HP-24 (1HP-24 and 1HP-25) are closed, THEN perform the following:

• 1HP-25 A. Start IA LPI PUMP.

B. Start 1 B LPI PUMP.

C. Open:

ILP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D. IF two LPI Pumps are running Qjjjy to provide HPI pump suction, THEN secure one LPI pump.

E. Dispatch an operator to open 1 HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, UI LPI Hatch Rm, N end).

F. GO TO Step 8.

2._ IF only one BWST suction valve (1HP-24 or 1HP-25) is open, THEN perform the following:

A. IF three HPI pumps are operating, THEN secure lB HPI PUMP.

B. IF <2 HPI pumps are operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers.

C._ GO TO Step 9.

Page 28 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June11, 2012 Page3of8 ENCLOSURE 5.5 (cont.)

ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

8. Start IC HPI PUMP. IF at least two HPI pumps are operating, THEN throttle 1 HP-409 to maintain desired Pzr level.

9. Throttle the following as required to maintain I ._ IF at least two HPI pumps are operating, desired Pzr level: AND 1HP-26 will NOT open, THEN throttle 1 HP-41 0 to maintain I HP-26 desired Pzr level.

1 HP-27 2.IF1AHPIPLIMPandIBHPIPIJMPare operating, AND 1 HP-27 will NOT open, THEN throttle 1 HP-409 to maintain desired Pzr level.

Page 29 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11, 2012 Page4of8 ENCLOSURE 5.5 (cont.)

ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

10. IAAT LDST level CANNOT be GO TO Step 12.

maintained, THEN perform Step 11.

11. Perform the following: 1 . IF both BWST suction valves

. Open 1 HP-24.

(1 HP-24 and 1 HP-25) are closed, THEN perform the following:

. Open 1HP-25.

A. Start 1A LPI PUMP.

• Close 1HP-16.

B. Start lB LPI PUMP.

C. Open:

1LP-15 1LP-16 1LP-9 ILP-10 1LP-6 1LP-7 D. IF two LPI Pumps are running jy to provide HPI pump suction, THEN secure one LPI pump.

E. Dispatch an operator to open 1 HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, Ui LPI Hatch Rm, N end).

F. GO TO Step 12.

2._ IF only one BWST suction valve (1 HP-24 or 1 HP-25) is open, AND three HPI pumps are operating, THEN secure lB HPI PUMP.

Page 30 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Page 5of8 ENCLOSURE 5.5 (cont.)

ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

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

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

Open 1HP-17.

Open IHP-l8 ...,

14. IAAT of the following exist: GO TO Step 34.

Letdown isolated LPSW available Letdown restoration desired THEN perform Steps 15- 33. 41}

15. Open: 1 . Notify CR SRO that letdown CANNOT be i CC-7 restored due to inability to restart the CC 1 CC-8 system.

2._ GO TO Step 34.

16. Ensure only one CC pump running.

17. Place the non-running CC pump in AUTO.

18. Verifybothareopen: 1._ IF 1HP-1 is closed due to 1HP-3 failing to 1HP-i close, 1HP-2 THEN GOTO Step 20.

2._ IF i HP-2 is closed due to 1 HP-4 failing to close, THEN GOTO Step 20.

19. GO TO Step 22.

NOTE Verification of leakage requires visual observation of East Penetration Room.

20. Verify letdown line leak in East GO TO Step 22.

Penetration Room has occurred.

21. GO TO Step 34.

Page 31 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June11, 2012 Page 6 of 8 ENCLOSURE 5.5 (cont.)

ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

22. Monitor for unexpected conditions while restoring letdown.

23. Verify both letdown coolers to be placed 1._ IF 1A letdown cooler is to be placed in in service, service, THEN open:

I HP-i 1 HP-3 2._ IF lB letdown cooler is to be placed in service, THEN open:

1 HP-2 I HP-4 3._ GOTO Step 25.

24. Open:

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

25. Verify at least one letdown cooler is Perform the following:

aligned. A. Notify CR SRO of problem.

B. Step 34.

26. Close 1HP-6.

27. Close 1HP-7.

28. Verify letdown temperature < 125°F. 1._ Open 1HP-13.

2. Close:

IHP-8 1HP-9&11

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

A. 1HP-14 to NORMAL.

B. 1HP-16.

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

Page 32 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June11, 2012 Page 7of8 ENCLOSURE 5.5 (cont.)

ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED I

29. Open 1HP-5.

30. Adjust 1 HP-7 for 20 gpm letdown.

31. WHEN letdown temperature is

<125°F, THEN place LETDOWN HI TEMP INTLK BYP switch to NORMAL.

32. _Open 1HP-6.

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

NOTE AP/32 (Loss of Letdown) provides direction to cool down the RCS to offset increasing pressurizer level.

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

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

A. Obtain SRO concurrence to reduce running HPI pumps.

B. Secure the desired HPI pumps.

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

36. IAAT the following conditions exist:

Makeup from BWST NOT required LDST level > 55 A control rods inserted Cooldown Plateau NOT being used THEN close:

1 HP-24 1HP-25 Page 33 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June11, 2012 Page 8of8 ENCLOSURE 5.5 (cont.)

ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

37. Verify 1CS-48 (1A BHUT Recirc) has GO TO Step 39.

been closed to provide additional makeup flow to LDST.

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

A. 1A BLEED TRANSFER PUMP.

B. Locally position ICS-48 (IA BHUT Recirc) one turn open (A-i-107, Unit 1 RC Bleed Transfer Pump Rm.).

C. Close 1 CS-46.

D. Start 1A BLEED TRANSFER PUMP.

E. throttle 1CS-48 (1A BHUT Recirc) to obtain 90 110 psig discharge pressure.

F. iA BLEED TRANSFER PUMP.

39. Verify two Letdown Filters in service, GO TO Step 41.

AND only one Letdown filter is desired.

40. Perform of the following:

Place IHP-17 switch to CLOSE.

Place 1 HP-i 8 switch to CLOSE.

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

. .. END.

Page 34 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 CRITICAL TASKS

1. CT-i 1, Control SG Pressure to Maintain RC Temperature Constant (Page 22)

2. CT-14, Initiate HPI Cooling (Page 24)

Page 35 of 36

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 SAFETY: Take a Minute UNIT 0 (OSM)

SSF Operable: Yes - -

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

Unit I Simulator Other Units Mode: I Unit 2 Unit 3 Reactor Power: 85% Mode: 1 Mode: I Gross MWE: 778 100% Power 100% Power RCS Leakage: 0.024 gpm EFDW Backup: Yes EFDW Backup: Yes RBNS Rate: 0.01 gpm Technical Specifications/SLC Items (CR SRO)

ComponentlTrain OOS Restoration Required TSISLC #

DatelTime DateiTime Shift Turnover Items (CR SRO)

Primary

. Perform Control Rod movement PT (Group 1 only) per PT/1/A/0600/015 Enclosure 13.2 (Control Rod Movement At Power) beginning at Step 3.3

. SASS in Manual for I&E

. Maintain Letdown Flow 71 gpm for Letdown Cooler performance evaluation Secondary

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

. Holding power at 85% while monitoring IA FDWP due to issues with oil coolers. Have the OSM notify component engineer immediately if any unusual alarms/indications occur.

. 1 MS-82 and 1 MS-84 closed in support of maintenance. TDEFWP operable on AS only.

Reactivity Management (CR SRO)

R2 Reactivity management controls RCS Boron: 6 ppmB Gp 7 Rod Position: 78% established in the Control Room per SOMP 01 -02 Human Performance Emphasis (OSM)

Procedure Use and Adherence Page 36 of 36

JL Facility: Oconee Scenario No.: 2 rl Op-Test No.: 1 Examiners: Operators:

Initial Conditions:

• Reactor Power = 85% Unit 2: 100%, Unit 3: 100%

Turnover:

• Holding power at 85% while monitoring 1A FDWP due to issues with oil coolers. Have the OSM notify component engineer immediately if any unusual alarms/indications occur.

• TDEFWPOOS

• SASS in manual for l&E

• Maintain Letdown Flow 71 gpm for Letdown Cooler performance evaluation Event 1 Malfunction Event No.__[ No. Event Type* Description Oa Override SASS in Manual Ob MSS22O Disable TDEFWP start Oc Override Disable 1AI RCP Switch Od Override Disable Main Turbine Trip Pushbutton Oe MP1290 Block all Turbine Trips except Manual 1 C: OATC, BOP, Override Inadvertent ES Channel I actuation (TS)

SRO(TS) 2 MPS25O C: BOP, SRO 1A2 RCP High Vibration 3 Override I: NONE Turbine inadvertently trips to HAND requiring FDW and Rx to be placed in HAND MPS400, .009% C: BOP, SRO RCS Leak 80 gpm requiring manual power reduction 4 (TS) (TS) 5 R: OATC, SRO Manual Power Reduction 6 Override C: OATC, SRO Turbine fails to trip when performing IMAs requiring EHC pumps lockout SBLOCA MPS400, 0.30%

M: ALL Switch will not stop 1A1 RCP when securing RCPs per Rule 2 8 MPS400, 70% ALL LBLOCA (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 ILT41 June11, 2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: I Page 1 of 5 Event

Description:

Inadvertent ES Channel I Actuation (TS)

Time Position ApplicanVs Actions or Behavior Plant response:

1SA-i/A-i0 ES 1 Trip 1 SA-i 6/B-I EL CT-4 SB Bus 1 Breaker Closed 2SA-17/A-5 KEOWEE STATALARM PANEL ALARM 2SA-i 7/C-i KHU 1 EMERGENCY START INITIATED 2SA-i 8/C-i KHU 2 EMERGENCY START INITIATED 1SA-6/A-5, B-5, C-5, D-5, RC Pump Seal Cavity Press Hi/Low ( I mm later)

ISA-6/D-7, E-5, E-6, E-7 RC Pump Seal Return Temp High Both Keowee Hydro Units Emergency Start Examiner Note: Over time, Reactor power will begin to slowly decrease due to BWST water injecting into the core. This affect will vary depending on crew response, primarily how quickly 1 HP-24 is closed.

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

SRO/BOP/

The SRO will initiate AP/i/A/i700/042 Inadvertent ES Actuation OATC 4.1 Verify jjy of the following have inadvertently actuated:

Diverse HPI (not actuated)

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

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

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

ES Channel 5 (not actuated)

ES Channel 6 (not actuated)

RNO: 1. IF ES Channel 1, ES Channel 2, or Diverse HPI have inadvertently actuated, AND it is desired to restore letdown, THEN initiate AP/42 End 5.2 (Letdown Restoration) (see page 5)

2. GOTOStep4.i0 4.10 Close 1HP-24 and 1HP-25 4.11 Ensure AP/42 End 5.1 (Required Operator Actions) is in progress (see page 4)

Page 2 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: I Page 2 of 5 Event

Description:

Inadvertent ES Channel I Actuation (TS)

Time__[ Position Applicants Actions or Behavior Crew Response:

SROIBOP/

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

Diverse LPI ES Channel 3 ES Channel 4 RNO: GO TO Step 4.17 4.17 Verify the Rx is critical 4.18 Verify ICS in Auto Examiner Note: Desired control band is 100% withdrawn for upper limit and Rod Insertion Limit for lower limit 4.19 Verify control rods are outside the desired control band RNO: GO TO Step 4.21 4.21 Verify y of the following have inadvertently actuated:

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

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

Ensure ES ELECTRICAL 1 is in MANUAL 4.23 Dispatch an operator to perform End 5.3 (SSF Restoration) 4.24 Notify SPOC to investigate and repair the cause of the inadvertent ES actuation, as necessary 4.25 Initiate logging TS/SLC Entry/Exit, as applicable, lAW End 5.4 (TS/SLC Requirements) (See page 6 for detailed information) 4.26 WHEN of the following exist:

Reason for inadvertent ES Channel or Diverse HPI/LPI actuation has need resolved ES Channel or Diverse HPI/LPI reset is desired OSM concurs THEN continue Examiner Note: See page 6 for applicable Tech Spec information.

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

Page3of44

Appendix D Scenario Outline Form ES-D-1 ILT4I June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: I Page 3 of 5 Event

Description:

Inadvertent ES Channel I Actuation (TS)

Time__j Position

[ Applicants Actions or Behavior Crew Response:

OATC/BOP/ AP/1/A11700/042 Enclosure 5.1 Required Operator Actions OATC 1 Initiate announcement of AP entry using the PA system 2 Verify j2Y of the following have inadvertently actuated:

Diverse HPI (not actuated)

ES Channel I ES Channel 2 (not actuated) 3 Open the following:

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

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

ES Channel 7 (not actuated)

ES Channel 8 (not actuated)

RNO: GO TO Step 9 9 Perform the following:

A. Open the following to restore RB RIAs:

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

1. Select OFF for RB RIA sample pump

2. Start the RB RIA sample pump

10. Verify y of the following have inadvertently actuated:

Diverse HPI (not actuated)

ES Channel 1

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

• Unit 2, Unit3, and Security

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

Page4of44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: I Page 4 of 5 Event

Description:

Inadvertent ES Channel I Actuation (TS)

Time Position Applicants Actions or Behavior Crew Response:

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

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

5. Open the following:

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

6. Close 1HP-6

7. Close 1HP-7

8. Verify letdown temperature < 135°F

9. Open 1HP-5

10. Adjust 1HP-7 for 20 gpm letdown

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

12. Open IHP-6

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

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

A. Open the following:

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

15. IAAT letdown bleed is NO longer desired, THEN position 1HP-I4 to NORMAL

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

Page 5of44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: I Page 5 of 5 Event

Description:

Inadvertent ES Channel I Actuation (TS)

Time Position Applicants Actions or Behavior Crew Response:

SRO AP/1/A/1700/042 Enclosure 5.4 (TSISLC Requirements)

Any ES Channel

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

ES Channel I or 2

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

Condition B (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for grab samples) (30 days)

• TS 3.10.1 (Standby Shutdown Facility(SSF)) for SSF inoperability due to the SSF power loss (ES Channel 1 only)

Conditions A through E all apply (7 days)

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

Condition A (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)

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

Page 6 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 2 Page 1 of 4 Event

Description:

1A2 RCP High Vibration Time Position Applicants Actions or Behavior Plant response:

• ISA-09/D-2, RC PUMP Vibration High Crew response:

BOP Refer to the ARG:

3.1 Verify vibration reading on RCP QAC Display Group RCP 3.2 IF indications of both RCPs in a Loop are trending up together without any changes to RCS conditions (Temp/Press), swap Vibration Monitor power supplies as follows (NIA) 3.3 IF MODE 1 or 2, initiate AP/1/A1700/016 (Abnormal Reactor Coolant Pump Operation).

AP/16 SRO/BOP 4.1 IAAT any RCP Immediate Trip Criteria (ITC) met, perform Steps 4.2 -

4.11 RNO: GO TO step 4.12.

Examiner Note: There are two success paths through AP/1 6 that will both result in securing the RCP. If crew/candidate decides that with the slow increase in vibrations, reaching the ITC is not imminent they will proceed as shown below. If they decide they are approaching trip criteria or desire to trip the RCP, they will proceed (after step 4.12) lAW page 10. Either path is acceptable.

4.12 IAAT either of the following apply:

• Any RCP approaching immediate trip criteria

• It is desired to secure a RCP THEN perform Steps 4.13 -4.15. (See page 10)

RNO: GO TO step 4.16 4.16 Announce AP entry on plant page 4.17 Notify OSM to request evaluation by RCP Component Engineer.

4.18 IAAT the failure is identified, THEN GO TO the applicable section: (GO TO Section 4B- Abnormal Vibration on next page)

This event is complete when the 1A2 RCP has been secured or as directed by the lead examiner.

Page 7 of 44

Appendix D Scenario Outline Form ES-D-1 ILT4I June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 2 Page 2 of 4 Event

Description:

1A2 RCP High Vibration Time Position Applicants Actions or Behavior SRO/BOP SECTION 4B (Abnormal RCP Vibration)

1. IAAT any RCP Immediate Trip Criteria (ITC) met, perform Steps 2 - 11 RNO: GO TO step 12

12. Verify RCP vibration indication is available for monitoring in Control Room.

13. Monitor RCS flow for indication of degradation.

14. Verify all CETCs <630°F. (Turn-on code ITC)

15. Monitor RCP parameters for operational abnormalities:

OAC Display: (Turn-on Code RCP)

• Motor bearing temperatures

• Seal return temperature

• Seal return flow

• RCP motor input power Loose Parts Monitor I Examiner Cue: No abnormal noise or sounds on LPM.

16. IAAT high vibration exists per statalarm 1 SA-91D-2, (RC PUMP VIBRATION HIGH)

AND vibration continues to increase with the potential to exceed trip criteria THEN perform Steps 17 27. -

17. Verify Mode 1 or 2

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

19. Verify Rx power is <70% on all Nis.

SRO/OATC RNO: 1. Direct an RO to initiate End 5.2 (Rapid Power Reduction).

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

(See page 9 for performance of End 5.2)

20. Verify any SG on Low Level Limits RNO: GO TO step 23

23. Verify FDW masters in Auto.

24. Stop the affected RCP

25. Verify ICS re-ratios feedwater to establish desired ATc This event is complete when the 1A2 RCP has been secured or as directed by the lead examiner.

Page 8 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 2 Page 3 of 4 Event

Description:

1A2 RCP High Vibration Time Position Applicants Actions or Behavior End 5.2 (Rapid Power Reduction)

SRO/OATC 1. Verify ICS in AUTO

2. Initiate MAXIMUM RUNBACK to 70% as indicated by all Nls 3 WHEN Rx Power is

. 70% as indicated by all NIs, THEN press MAXIMUM RUNBACK to stop runback.

4. Notify CR SRO that Rx Power is 70%.

5. Adjust CTPD SET to match CTP DEMAND.

6. Stop the following pumps:

1EI HTR DRN PUMP 1E2 HTR DRN PUMP

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

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

9. EXIT this enclosure.

This event is complete when the 1A2 RCP has been secured or as directed by the lead examiner.

Page9of44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 2 Page 4 of 4 Event

Description:

1A2 RCP High Vibration Time Position Applicants Actions or Behavior Examiner Note: Alternate procedure path continued from Page 7 SRO/BOPI 4.13. Verify Rx Power> 70%.

OATC 4.14. Initiate End 5.2 (Rapid Power Reduction).

(See page 9 for performance of End 5.2) 4.15 WHEN Rx Power is 70%,

THEN GO TO Step 4.2.

4.2. Verify Mode 1 or 2 4.3. Verify Rx power is < 70% on all Nis.

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

4.5. Verify any SG on Low Level Limits.

RNO: Go to step 4.8 4.8. Verify FDW masters in Auto.

4.9. Stop the affected RCP.

4.10 Verify ICS re-ratios feedwater to establish desired ATc.

4.11 GOTOStep4.26 4.26 Initiate End 4.3 (Special Instructions for <4 RCP Operation) of OP/i/All 102/004 (Operation at Power).

This event is complete when the 1A2 RCP has been secured or as directed by the lead examiner.

Page 10 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 3 Page 1 of 2 Event

Description:

Turbine inadvertently trips to HAND requiring FDW and Rx to be placed in Time Position ApplicanVs Actions or Behavior Plant Response:

Statalarms:

• 1 SA-2/A-1 2, ICS Tracking

• 1 SA-2/C-12, ICS H/A Station on Man Crew Response:

• Refer to ARG for above alarms.

• IF Turbine Master Trips to Hand for unknown reason, refer to BOP AP/1 tA/I 700/028 (I CS Instrument Failure).

AP/28

4. Subsequent Actions 4.1 Provide control bands as required.

SRO/OATC/

BOP 4.2 Initiate notification of the following:

OSM to reference the following:

• OMP 1-14 (Notifications)

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

RNO: GO TO Step 4.5.

4.4 Notify Rx Engineering and discuss the need for a maneuvering plan.

4.5 Use the following, as necessary, to determine the applicable section from table in Step 4.6:

• OAC alarm video

• QAC display points

• Control Board indications

• SPOC assistance, as needed Note: From table selections 4A through 4P the crew should pick 40 4.6 GO TO the applicable section per the following table:

• 40 Turbine Master Trips to Hand for Unknown Reason When FDW Masters and Diamond are in MANUAL, or when directed by the Lead Examiner this event is completed.

Page 11 of44

Appendix D Scenario Outline Form ES-D-1 ILT4I June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 3 Page 2 of 2 Event

Description:

Turbine inadvertently trips to HAND requiring FDW and Rx to be placed in Time Position Applicants Actions or Behavior SRO Unit Status The Turbine Master has tripped to Hand for Unknown Reasons. Any required Plant Transient Response actions have been taken and TPB is the pre transient power level.

NOTE If the Turbine Master is the only ICS station in Hand, the unit is vulnerable to grid disturbances due to the remainder of the lOS stations being in Auto.

Section 40 Turbine Master Trips to Hand for Unknown Reason SRO/OATC

1. Simultaneously place the following to HAND:

• 1AFDW MASTER

• 1BFDWMASTER

2. Place the DIAMOND in MANUAL.

3. Notify SPOC to investigate the cause of the Turbine Master tripping to Hand.

NOTE:

Operating bands shall be provided on the following parameters: Core Thermal Power, Turbine Header Pressure, and Tave.

If the unit is stable, it is acceptable to pull control rods to maintain Tave.

Oversight is required by SOMP 01-02.

Extended operation with the ICS in manual will require either deboration or withdrawing control rods to maintain Tave. Utilize the Power Maneuver Program to determine the required deboration.

4. WHEN the reason for the Turbine Master tripping to Hand is understood, AND it is desired to restore ICS to Auto, THEN GO TO OP/i/All 102/004 A End (Placing ICS Stations To Auto).

When FDW Masters and Diamond are in MANUAL, or when directed by the Lead Examiner this event is completed.

Page 12 of44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: ...2_ Event No.: 4 Page 1 of 6 Event

Description:

RCS Leak 80 gpm requiring manual power reduction (TS)

Time Position Applicants Actions or Behavior Plant Response:

Alarms:

• OAC RB Normal Sump Temp HI HI

• 1SA-91A-6 (RB NORMAL SUMP HIGH/LOW)

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

Control Board Indications

• PZR and LDST level deceasing

• RC makeup flow increasing

• RB normal sump level increasing Crew Response:

SRO The SRO may refer to TS 3.4.13 (RCS Operational 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.

Examiners Note:

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

The crew may determine that Immediate Manual Action Step 3.2 of APIO2 applies and close 1 HP-5 prior to the SRO entering AP/02.

SRO enters AP/2 (Excessive RCS Leakage)

AP/02 Immediate Manual Actions SRO/BOP 3.1 Verify HPI operating 3.2 IAAT RC makeup flow is> 100 gpm, AND Pzr level is decreasing, THEN close 1 HP-5 This event is complete when RCS leak rate has been determined and the crew transitions to AP129 or as directed by the lead Examiner.

Page 13of44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 4 Page 2 of 6 Event

Description:

RCS Leak 80 gpm requiring manual power reduction (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 35)

Booth Cue: If requested by crew, use Manual Valves to close I CS-48 and report that using time compression, ICS-48 is closed.

4.2 Announce AP entry using the PA system 4.3 IAAT LPI DHR in service, AND RCS leakage> LDST makeup capability

( 50 gpm) THEN GO TO AP/26 4.4 Initiate the following notifications:

OSM to reference the following:

• RP/1 000/001 (Emergency Classification)

• OMP 1-14 (Notifications)

• End 5.9 (Oversight Guidelines)

STAand RP This event is complete when RCS leak rate has been determined and the crew transitions to AP129 or as directed by the lead Examiner.

Page 14 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11, 2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 4 Page 3 of 6 Event

Description:

RCS Leak 80 gpm requiring manual power reduction (TS)

Time Position Applicants Actions or Behavior Crew response:

4.5 Monitor the following trends to determine leak area (AB or RB) and trend SRO/BOP for degradation:

• T6APO2

• T6WASTE

• RIAs ExaminerlBooth Note: AP/1/A/1700/018 entry conditions will also be met due to RB RIA alarms. If the crew asks, Unit 2 will perform AP/1 8 (Abnormal Release of Radioactivity) actions.

4.6 Verify specific leak location is identified RNO: Notify WCC SRO to initiate End 5.2 (Primary Leak Check) and of the leak area (AB or RB), if known.

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 4.7 Initiate End 5.1 (Leak Rate Determination)

(See page 18 for actions of End 5.1) 4.8 WHEN leak area/failure is identified, THEN GO TO applicable step that best fits leak area/failure q Area! Symptoms Step Failure Rx Bldg t RB RIAs 4.53 t RBNS rate NO RCP seal failure indications 4.53 IAAT in MODE 1 AND leak is> LDST makeup capability from IA BHUT, THEN initiate a shutdown using AP/29 (Rapid Unit Shutdown)

Note: The 80 gpm leak is NOT greater than LDST makeup capability from IA BHUT.

This event is complete when RCS leak rate has been determined and the crew transitions to AP!29 or as directed by the lead Examiner.

Page 15 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: Event No.: Page 4 of 6 Event

Description:

RCS Leak 80 gpm requiring manual power reduction (TS)

Time Position ApplicanVs Actions or Behavior Crew response:

4.54 IAAT leak rate is 10 gpm, THEN discontinue pumping RBNS.

SRO/BOP 4.55 IAAT either of the following conditions exist:

• RCS pressure < 50 psig and RCS leakage> 10 gpm

• RCS pressure> 50 psig and RCS leakage> 1 gpm THEN perform Steps 4.56 4.59 4.56 Verify the RB is occupied. (It is not)

RNO: GO TO Step 4.58

4. 58 Verify LPI DHR in service (It is not)

RNO: GO TO Step 4.60 4.60 Verify RB pressure> 3 psig.

RNO: Maximize RB Cooling by performing the following:

• Ensure all available RBCUs operating in HIGH.

• Open ILPSW-18.

• Open 1LPSW-21.

• Open 1 LPSW-24.

4.61 IAAT RB is accessible to locate the leak, THEN GO TO Step 4.62 RNO: GO TO Step 77 4.77 Verify 1 HP-5 is closed (Should have been closed as part of IMAs) 4.78 Place standby CC pump switch in OFF This event is complete when RCS leak rate has been determined and the crew transitions to AP129 or as directed by the lead Examiner.

Page 16of44

Appendix D Scenario Outline Form ES-D-1 ILT41 June11, 2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 4 Page 5 of 6 Event

Description:

RCS Leak 80 gpm requiring manual power reduction (TS)

Time Position Applicants Actions or Behavior NOTE Statalarm, 1 SA-9C-1 (CC COMP COOLING RETURN FLOW LOW) will alarm when the letdown coolers are isolated 4.79 Close the following:

SRO/BOP

• 1CC-ill HP-i 1CC-2I1HP-2 4.80 Verify leak is isolated (it will not be).

RNO:

1. Perform the following to shutdown and depressurize the RCS:

SRO A. Initiate shutdown by one of the following as necessary:

• AP129 (Rapid Unit Shutdown)

• OP/i/All 102/004 (Operation at Power)

B. Initiate OPI1/A111021010 (Controlling Procedure For Unit Shutdown) to continue shutdown and depressurization.

2. WHEN conditions permit, THEN EXIT this procedure.

Booth Cue: If the crew selects the OP to do the shutdown, call them as OSM and in form them that a more rapid shutdown is desired and that they should use AP/29 to do the shutdown.

jçminer Note: AP129 actions begin on page 19 as Event #5.1 This event is complete when RCS leak rate has been determined and the crew transitions to AP129 or as directed by the lead Examiner.

Page 17 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: ...2_ Event No.: Page 6 of 6 Event

Description:

RCS Leak 80 gpm requiring manual power reduction (TS)

Time Position Applicants Actions or Behavior Enclosure 5.1

1. Stabilize RCS Temperature BOP/OATC

2. Notify WCC to secure all primary draining/RB washdown evolutions if applicable.

NOTE Depending on leak location, leakage may NOT be detected by all the formulas. One or more of the following methods may be necessary to determine RCS leak rate.

3. Calculate leak rate using the following, as required:

Examiners Note: There are several other methods to calculate leakage rate.

While one of the two below will most likely be used, depending on plant conditions they may not be the only correct methods available.

Method #1: Calculation of RCS Volume Loss:

LeakRate= ÷ - -

MU SI LD TSR Where: MU = makeup Flow SI = Seal Inlet Hdr Flow LD = Letdown Flow TSR = Total Seal Return Flow Method #2: LDST Level Change:

Leak Rate = (LDST level chane) x (31 gal/inch) + BTP Flowrate (gpm)

(minutes)

Leak Rate = (inches) x 31 gal/inch + gpm = gpm

4. Notify OSM and SRO of calculated leak rate.

This event is complete when RCS leak rate has been determined and the crew transitions to AP129 or as directed by the lead Examiner.

Page 18 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 5 Page 1 of 1 Event

Description:

Manual Power Reduction Time Position Applicants Actions or Behavior AP/29 (Rapid Unit Shutdown) 4.1 Initiate End 5.1 (Support Actions During Rapid Unit Shutdown)

SRO/BOP 4.2 Announce AP entry using the PA system.

4.3 IAAT both of the following apply:

SRO/OATC It is desired to stop power decrease.

_CTP> 18%

THEN perform Steps 4.4 4.7 (Does NOT apply now)

RNO: GO TO Step 4.8 4.8 Verify ICS in AUTO (It is NOT 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 until its suction flow is 1 X 1 6 Ibm/hr less than remaining Main FDW pump suction flow.

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

This event is complete when a 10% power change in manual has taken place or as directed by the lead Examiner.

Page 19 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 6 Page 1 of 1 Event

Description:

Turbine fails to trip when performing IMAs requiring EHC pumps lockout

__Time Position Applicants Actions or Behavior Plant response:

• 1SA-9/A-6, RB Reactor Building Normal Sump Level High/Low

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

• 1 SA-2/D-3, RC Press High/Low

• A SBLOCA will result in a reactor trip.

• The Main Turbine should trip but does not. This will result in a reduction of steam pressure in both SGs until actions are taken to trip the turbine.

This will result in RCS overcooling until the turbine is tripped.

Crew response:

• SRO will enter the EOP.

SRO

• OATC will perform Immediate Manual Actions OATC

• OATC will perform IMAs 3.1 Depress REACTOR TRIP pushbutton.

3.2 Verify reactor power < 5% FP and decreasing.

3.3 Depress turbine TRIP pushbutton.

• Note: The OATC should diagnose that the turbine did not trip and then perform the RNO step which will stop and lock out both EHC pumps. This will cause the turbine to trip. (CT-18) 3.4 Verify all turbine stop valves closed.*

RNO: Place both EHC pumps in PULL TO LOCK.

3.5 Verify RCP seal injection available.

Event is complete when EHC pumps have been tripped or when directed by the Lead Examiner.

Page 20 of 44

Appendix D Scenario Outline Form ES-D-1 ILT4I June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 7 Page 1 of 11 Event

Description:

SBLOCA, Switch will not stop IAI RCP when securing RCPs per Rule 2 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

• Reactor Trip

• RCS subcooling margin will indicate 0°F Crew response:

OATC/BOP

• Trip the Reactor due to MU being beyond Normal Makeup Capability (160 gpm).

• The SRO will direct the OATC to perform IMAs and the BOP a symptom check.

• OATC will perform IMAs per Event 6

• The BOP will perform a symptom check Examiners Note: The SRO will transfer to the Subsequent Actions Tab and then use the Parallel Actions page transfer to go to the LOSCM tab to direct SRO crew activities. LOSCM tab begins on page 31.

OATC/BOP Once the RCS saturates, one of the ROs will perform Rule 2 which begins on next page. Rule 2 will direct performing Rule 3 which will direct performing Enclosure 5.9.

The RO not performing Rule 2 will begin performing Enclosure 5.1 due to ES actuation. Enclosure 5.1 begins on page 27.

Page 21 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 7 Page 2 of 11 Event

Description:

SBLOCA, Switch will not stop IAI RCP when securing RCPs per Rule 2 Time Position ApplicanVs Actions or Behavior RCS saturates; obtain SRO concurrence to perform Rule 2 OATC/BOP Rule 2 ( Loss of SCM)

1. IAAT all the following exist:

• Any SCM 0°F

• Rxpower1%

• 2 minutes elapsed since loss of SCM THEN perform steps 2 & 3 Examiners Note: IAI RCP will not stop which will require performing the RNO to de-energize 4160v switchgear

2. Stop all RCPs Ct-I: (Trip ALL RCPs within 2 minutes)

RNO: 1. Place ITA AUTO/MAN switch in MAN.

2. Place ITB AUTO/MAN switch in MAN.

3._Open 1TA SU 6.9KV FDR.

4. _Open 1TB SU 6.9 KV FDR.

3. Notify CR SRO of RCP status

4. Verify Blackout exists.

RNO: GO TO Step 6

6. Open 1 HP-24 & 25

7. Start all available HPI pumps.

8.GOTOStepl3

13. Open 1HP-26&27

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

15. IAAT> 2 HPI pumps operating and HPI flow in any header is in Unacceptable Region of Fig. 1, THEN perform Steps 16-21.

RNO: GOTOStepl7

17. IAAT flow limits are exceeded THEN perform Steps 18 20 -

RNO: GO TO Step 21

21. Notify CR SRO of HPI status.

Page 22 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June11, 2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 7 Page 3 of 11 Event

Description:

SBLOCA, Switch will not stop IAI RCP when securing RCPs per Rule 2 Time Position Applicants Actions or Behavior OATC/BOP 22. Verify RCS pressure >550 psig.

23. 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 24.

RNO: GO TO Step 35

35. IAAT TBVs are unavailable, THEN A Dispatch two operators to perform End 5.24 (Operation of ADVs)

B Notify CR SRO the ADVs are being aligned for use.

36/37. Select OFF on both Digital Channels on AFIS HEADER A&B if not actuated

38. Verify any EFDW pump operating.

39. Start MD EFDW pumps on all intact SGs:

• 1AMDEFDWP

• 1BMDEFDWP

40. Verify any EFDW pump operating.

41. Verify both SGs intact.

42. Establish 300 gpm EFDW flow to each SG

43. Verify both MD EFDWPs operating.

44. Place TD EFDW PUMP in PULL TO LOCK.

45. Trip both Main FDW pumps.

46. Place FDW block valve switches in CLOSE:

• 1FDW-33

• 1FDW-31

• IFDW-42

• 1FDW-40

47. Utilize Rule 7 (SG Feed Control) to feed all intact SGs to the appropriate SG Level Control Point using available feed sources; EFDW/Main FDW.

48. IAAT SG Level Control Point is reached, Then maintain SG Level Control Point by feeding and steaming as necessary.

49. Notify CR SRO of SG feed status.

Page 23 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 7 Page 4 of 11 Event

Description:

SBLOCA, Switch will not stop IAI RCP when securing RCPs per Rule 2 Time__[ Position Applicants Actions or Behavior CAUTION OATC/BOP If I TD EFDW PUMP is being used for SG feed and Unit 1 is supplying the Auxiliary Steam header, reducing SG pressure below 250 psig can result in reduced pumping capability.

50. IAAT SG pressure is> RCS pressure, THEN reduce SG pressure <

RCS pressure using either:

TBVs Dispatch two operators to perform End 5.24 (operation of the ADV5)

51. Verify any Main FDW pump operating.

RNO: GO TO Step 58.

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

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

Page 24 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 7 Page 5 of 11 Event

Description:

SBLOCA, Switch will not stop IAI RCP when securing RCPs per Rule 2 Time Position Applicants Actions or Behavior Rule 3 due to loss of Main Feedwater as directed by Rule 2 OATC/BOP 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/CB P/Emergency), AND any of the following exist:

• RCS pressure reaches 2300 psig OR NDT limit

• Pzr level reaches 375 [340 acc]

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

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

5. Verify any EFDW pump operating.

6. GOTO Step 37.

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

RNO: GO TO Step 43

43. Verify any SCM 0°F.

44. IAAT Unit 1 EFDW is in operation, THEN initiate End 5.9 (Extended EFDW Operation). (See page 26)

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

Page 25 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 7 Page 6 of 11 Event

Description:

SBLOCA, Switch will not stop IAI RCP when securing RCPs per Rule 2 Time Position Applicants Actions or Behavior BOP/OATC End 5.9 (Extended EFDW Operation) as directed by Rule 3

1. Monitor EFDW parameters on EFW graphic display.

2. IAAT UST level is <4, THEN GO TO Step 120

3. IAAT feeding both SGs with one MD EFDWP is desired, THEN perform Steps 47.

RNO: GO TO Step 8

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

• Makeup with demin water.

• Place CST pumps in AUTO.

9. IAAT aH the following exist:

• Rapid cooldown NOT in progress

• MD EFDWP operating for each available SG

• EFDW flow in each header < 600 gpm THEN place 1 TD EFDW PUMP switch in PULL TO LOCK.

10. Verify 1 TD EFDW PUMP operating.

RNO: GO TO Step 12 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.

Page 26 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 7 Page 7 of 11 Event

Description:

SBLOCA, Switch will not stop IAI RCP when securing RCPs per Rule 2 Time Position Applicants Actions or Behavior Crew Response:

EXAMINER NOTE: Initially, ES Channels 1 and 2 will actuate when RCS pressure decreases below 1600 psig. When Reactor Building pressure increases to > 3 psig, ES Channels 3-6 will actuate. The exact path through End. 5.1 is somewhat dependant on timing of ES 3-6 in conjunction with the pace of progress through the enclosure. If the RO reaches Step 15 prior to ES 3&4 actuation, the procedure directs going to Step 53. When ES Channel 3&4 actuate, the RO should review IAAT Steps 3, 9, 10, and 15 and perform any required actions With ES-i in Manual due to event 1, Diverse HPI will position Channel 1 ES components to their ES positions.

EOP Enclosure 5.1, ES Actuation OATC/BOP

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

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

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

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

4. Place Diverse HPI in BYPASS

5. Perform both:

• Place ES CH I in MANUAL

• Place ES CH 2 in MANUAL

6. Verify Rule 2 in progress or complete

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

9. IAAT all exist:

• Voter associated with ES channel is in OVERRIDE

• An ES channel is manually actuated

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

10. lAATy RCP is operating, AND ES Channels 5 and 6 actuate, THEN perform Steps 11-14 RNO: GOTOStep15 Page 27 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 7 Page 8 of 11 Event

Description:

SBLOCA, Switch will not stop IAI RCP when securing RCPs per Rule 2 Time Position Applicants Actions or Behavior EOP Enclosure 5.1, ES Actuation (continued)

15. IAAT ES Channels 3 & 4 are actuated, THEN GO TO Step 16 OATC/BOP RNO: GO TO Step 53 (Step 53 is on page 29 if that direction is taken)

16. Place Diverse LPI in BYPASS

17. Perform both:

• Place ES CH 3 in MANUAL

• Place ES CH 4 in MANUAL

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

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

RNO: GOTOStep22

22. IAAT 1A and lB LPI PUMPs are off/tripped, AND all of the following exist:

• RCS pressure < LPI pump shutoff head

• 1 LP-1 9 closed

• I LP-20 closed THEN perform Steps 23 24 -

RNO: GO TO Step 25

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

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

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

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

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

30. Verify I HP-41 0 closed

31. Secure makeup to the LDST

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

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

3. IF 1 HP-20 fails to close and no RCPs operating, THEN close IHP-228, 1HP-226, 1HP-232, & 1HP-230

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

33. Verify Unit 2 turbine tripped Page 28 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 7 Page 9 of 11 Event

Description:

SBLOCA, Switch will not stop IAI RCP when securing RCPs per Rule 2 Time Position ApplicanVs Actions or Behavior EOP Enclosure 5.1, ES Actuation OATC/BOP RNO: GO TO Step 36

36. Close 1LPSW-139

37. Place in FAIL OPEN:

ILPSW-251 FAIL SWITCH 1LPSW-252 FAIL SWITCH

38. Start all available LPSW pumps

39. Verify either:

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

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

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

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

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

44. IAAT ES channels 5 & 6 have actuated THEN perform Step 45 Note: RBCU transfer to low speed will NOT occur until 3 minute time delay is satisfied.

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

46. IAAT ES channels 7 & 8 have actuated, THEN perform Step 47-48 RNO: GO TO Step 49

49. Notify U2 CR SRO that SSF is inoperable due to OTS1-1 open 50 Ensure any turnover sheet compensatory measures for Es actuation are complete as necessary.

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

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

EXAMINER NOTE: The following steps may be required depending on how quick the RO gets to Step 15 of End 5.1. If the RO reaches Step 15 prior to ES 3&4 actuation, the procedure directs going to Step 53. When ES Channel 3&4 actuate, the RO should return to IAAT Steps 3, 9, 10, and 15 and perform any required actions (see page 27).

53. Start A and B OUTSIDE AIR BOOSTER FANS

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

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

56. Verify 1HP-410 closed

57. Secure makeup to the LDST Page 29 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 7 Page 10 of ii Event

Description:

SBLOCA, Switch will not stop IAI RCP when securing RCPs per Rule 2 Time Position Applicants Actions or Behavior EOP Enclosure 5.1, ES Actuation

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

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

3. IF 1 HP-20 fails to close and no RCPs operating, THEN close 1HP-228, 1HP-226, 1HP-232, & 1HP-230

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

59. Verify Unit 2 turbine tripped RNO: GO TO Step 62

62. Close 1 LPSW-i 39

63. Place in FAIL OPEN:

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

64. Start all available LPSW pumps.

65. Verify either:

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

66. Open:

1 LPSW-4 1 LPSW-5

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

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

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

70 Ensure any turnover sheet compensatory measures for ES actuation are complete as necessary.

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

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

Page 30 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 7 Page 11 of 11 Event

Description:

SBLOCA, Switch will not stop IAI RCP when securing RCPs per Rule 2 Time Position Applicants Actions or Behavior SRO SRO will transfer to the LOSCM tab.

LOSCM tab SRO/BOPI 1. Ensure Rule 2 (Loss of SCM) is in progress or complete.

OATC 2. Verify Station ASW feeding any SG.

RNO: GO TO Step 4

4. Verify LOSCM caused by excessive heat transfer.

RNO: GO TO Step6

6. 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 LOCA CD tab.

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

• SSF RC Makeup

• SSF Aux Service Water RNO: GO TO Step 9

9. Verify all of the following exist:

• NO RCPs operating

• HPI flow in both HPI headers

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

10. GOTOStep89.

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

90. Verify HPI forced cooling in progress.

RNO: Close I RC-4

91. Close 1GWD-17, 1HP-1, IHP-2, and IRC-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).

This event is complete when the SRO goes from Step 10 to Step 89 or as directed by the lead examiner.

Page 31 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 8 Page 1 of 3 Event

Description:

LBLOCA Time Position Applicants Actions or Behavior Plant Response:

RCS pressure decreases rapidly Core and Loop Subcooling Margins indicate 0 or -0 (flashing)

ES Channels 1-8 if not previously actuated will now actuate OATC/BOP Crew response:

• RO performing End. 5.1, ES Actuation, must recognize the IAAT Step 19 will need to be performed and LPI Pumps restarted. (CT-4 Initiate LPI)

The RO will return to step 19, and perform steps 19, 20, and 21 to initiate LPI flow. See steps below.

19. IAAT RCS pressure is < LPI pump shutoff head, THEN perform Steps 0- 0.

20. Perform the following:

Open 1LP-17.

SROIOATC/ Start 1A LPI PUMP.

21. Perform the following:

Open 1LP-18.

Start 1 B LPI PUMP.

• SRO may direct an RO to perform a Symptoms Check:

• Crew should recognize that LOSCM IAAT Step 6 now exists.

LOSCM IAAT Step 6:

6. IAAT either of the following exists:

• LPI FLOW TRAIN A plus LPI FLOW TRAIN B 3400 gpm

• Only one LPI header in operation with hdr flow 2900 gpm THEN GO TO LOCA CD tab (next page).

Examiner Note: At the beginning of a LBLOCA, the Core may superheat for a brief period of time. If it does and is noted by the crew, the SRO will choose to go to the ICC tab lAW the Parallel Actions page. This path can be followed on page 34 (page 3 of this event). Otherwise, continue as shown below.

This event is completed when transfer to LOCA CD tab has been made or when directed by the lead examiner, Page 32 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 OpTest No.: ILT4I Scenario No.: 2 Event No.: 8 Page 2 of 3 Event

Description:

LBLOCA Time Position Applicants Actions or Behavior SRO/OATC/ LOCA CD tab BOP

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

2. Verify ES actuated.

3. GOTOStep7

7. Perlorm the following:

• Ensure all RBCUs in low speed.

• Open 1LPSW-18.

• Open 1LPSW-21.

• Open 1 LPSW-24.

8. Initiate End 5.35 (Containment Isolation).

9. Start all RB Aux fans This event is completed when transfer to LOCA CD tab has been made or when directed by the lead examiner, Page 33 of 44

Appendix D Scenario Outline Form ES-D-l ILT41 June 11,2012 Op-Test No.: ILT4I Scenario No.: 2 Event No.: 8 Page 3 of 3 Event

Description:

LBLOCA Time Position Applicants Actions or Behavior ICC Tab

1. IAAT CETCs> 1200°F, SRO/OATC/

AND TSC is ready to provide mitigation guidance, BOP THEN perform the following:

A. Notify TSC to enter the OSAG.

B. EXIT this procedure.

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

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

4. Open:

• 1LP-21

• 1LP-17

5. Start IA LPI Pump.

6. Open:

• 1LP-22

• 1LP-18

7. Start lB LPI Pump

8. Verify two LPI pumps operating.

9. IAAT all the following exist:

• lCLPIPumpoff

• 10 LPI Pump available

• LPI required

• ECCS pump suction aligned to BWST

• 1A LPI Pump unavailable

• 1 B LPI Pump unavailable THEN perform Steps 10 13. -

RNO: GO TO step 14

14. Open:

1 CF-i 1CF-2

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

This event is completed when transfer to LOCA CD tab has been made or when directed by the lead examiner, Page 34 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June11, 2012 Page 1 of 8 EXAMINER NOTE At any time during this scenario the operator may choose to use Enclosure 5.5 to maintain RCS inventory control. See excerpt below.

ENCLOSURE 5.5 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Maintaining Pzr level >100 [180 acc] will ensure Pzr heater bundles remain covered.

1. Utilize the following as necessary to maintain IF 1 HP-26 will NOT open, desired Pzr level: THEN throttle 1 HP-41 0 to maintain

. 1A HPI Pump desired Pzr level.

. IBHPI Pump

. 1HP-26

. 1HP-7

. 1HP-120 setpoint or valve demand

. IHP-5

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

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

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

A. Open:

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

C. Notify SRO.

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

Page 35 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Page 2of8 ENCLOSURE 5.5 (cont.)

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

6. IAAT 1C HPI PUMP is required, GO TO Step 10.

THEN perform Steps 7-9.

7. Open: 1._ IF both BWST suction valves

• 1HP-24 (1HP-24 and 1HP-25) are closed, THEN perform the following:

• 1HP-25 A. Start 1A LPI PUMP.

B. Start lB LPI PUMP.

C. Open:

1LP-15 1LP-16 1LP-9 1LP-i0 1LP-6 1LP-7 D. IF two LPI Pumps are running to provide HPI pump suction, THEN secure one LPI pump.

E. Dispatch an operator to open 1 HP-363 (Letdown Line To LPI Pump Suction Block) (A-i-hg, Ui LPI Hatch Rm, N end).

F. GO TO Step 8.

2._ IF only one BWST suction valve (1 HP-24 or 1 HP-25) is open, THEN perform the following:

A. IF three HPI pumps are operating, THEN secure lB HPI PUMP.

B. IF <2 HPI pumps are operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers.

C._ GOTO Step 9.

Page 36 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Page3of8 ENCLOSURE 5.5 (cont.)

ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

8. Start 1 C HPI PUMP. IF at least two HPI pumps are operating, THEN throttle 1 HP-409 to maintain desired Pzr level.

9. Throttle the following as required to I . IF at least two HPI pumps are operating, maintain desired Pzr level: AND 1 HP-26 will NOT open,

.hIJ THEN throttle 1HP-4lOto maintain

. I I 26

- desired Pzr level.

. 1HP-27 2._ IF 1A HPI PUMP and 1 B HPI PUMP are operating, AND I HP-27 will NOT open, THEN throttle 1HP-409 to maintain desired Pzr level.

Page 37 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Page4of8 ENCLOSURE 5.5 (cont.)

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

10. IAAT LDST jyj CANNOT be GO TO Step 12.

maintained, THEN perform Step 11.

11. Perform the following: 1._ IF BWST suction valves

. Open 1 HP-24. (1 HP-24 and 1 HP-25) are closed, THEN perform the following:

. Open 1 HP-25.

A. Start 1A LPI PUMP.

• Close 1HP-16.

B. Start lB LPI PUMP.

C. Open:

1LP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D. IF two LPI Pumps are running jjy to provide HPI pump suction, THEN secure one LPI pump.

E. Dispatch an operator to open 1 HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, Ui LPI Hatch Rm, N end).

F. GO TO Step 12.

2._ IF only one BWST suction valve (1HP-24 or 1HP-25) is open, AND three 1-IPI pumps are operating, THEN secure lB HPI PUMP.

Page 38 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11, 2012 Page 5of8 ENCLOSURE 5.5 (cont.)

ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

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

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

. Open 1HP-i7.

. Open 1HP-i8

14. IAAT ll of the following exist: GO TO Step 34.

. Letdown isolated

. LPSW available

. Letdown restoration desired

• THEN perform**Steps* 533. £411

15. Open: 1._ Notify CR SRO that letdown CANNOT be

. 1CC-7 restored due to inability to restart the CC

. 1CC-8 system.

2._ GOTO Step 34.

16. Ensure only one CC pump running.

17. Place the non-running CC pump in AUTO.

18. Verify are open: I . IF I HP-i is closed due to 1 HP-3 failing to

. 1HP-1 close,

. 1HP-2 THEN GOTO Step 20.

2._ IF 1HP-2 is closed due to 1HP-4 failing to close, THEN GO TO Step 20.

19. GO TO Step 22.

NOTE Verification of leakage requires visual observation of East Penetration Room.

20. Verify letdown line leak in East GO TO Step 22.

Penetration Room has occurred.

21. GOTO Step 34.

Page 39 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 Page6of8 ENCLOSURE 5.5 (cont.)

ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

22. Monitor for unexpected conditions while restoring letdown.

23. Verify both letdown coolers to be placed 1._ IF 1A letdown cooler is to be placed in in service, service, THEN open:

IHP-1 1 HP-3 2._ IF lB letdown cooler is to be placed in service, THEN open:

1 HP-2 1 HP-4 3._ GO TO Step 25.

24. Open:

. 1HP-1

. 1HP-2

. 1HP-3

. 1HP-4

25. Verify at least one letdown cooler is Perform the following:

aligned. A. Notify CR SRO of problem.

B. Step 34.

26. Close 1 HP-6.

27. Close IHP-7.

28. Verify letdown temperature < 125°F. 1._ Open IHP-13.

2.Close:

I HP-8 1HP-9&11 3._ IF y deborating IX is in service, THEN perform the following:

A. Select IHP-14 to NORMAL.

B. Close 1HP-16.

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

Page 40 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June11, 2012 Page 7of8 ENCLOSURE 5.5 (cont.)

I ACTIONIEXPECTED RESPONSE RESPONSE NOTOBTAINED I

29. Open 1HP-5.

30. Adjust 1 HP-7 for 20 gpm letdown.

31. WHEN letdown temperature is <1 25° F, THEN place LETDOWN HI TEMP INTLK BYP switch to NORMAL.

32. Open 1HP-6.

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

NOTE AP/32 (Loss of Letdown) provides direction to cool down the RCS to offset increasing pressurizer level.

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

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

A. Obtain SRO concurrence to reduce running HPI pumps.

B. Secure the desired HPI pumps.

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

36. IAAT all the following conditions exist:

. Makeup from BWST NOT required

. LDST level > 55

. All control rods inserted

. Cooldown Plateau NOT being used THEN close:

. 1HP-24

. 1HP-25 Page 41 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June11, 2012 Page 8 of 8 ENCLOSURE 5.5 (cont.)

ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

37. Verify 1CS-48 (1A BHUT Recirc) has GO TO Step 39.

been closed to provide additional makeup flow to LDST.

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

A. Stop 1A BLEED TRANSFER PUMP.

B. Locally position 1CS-48 (1A BHUT Recirc) one turn open (A 1-107, Unit 1 RC Bleed Transfer Pump Rm.).

C. Close 10S-46.

D. Start 1A BLEED TRANSFER PUMP.

E. Locally throttle 1CS-48 (1A BHUT Recirc) to obtain 90 110 psig discharge pressure.

F. Stop 1A BLEED TRANSFER PUMP.

39. Verify two Letdown Filters in service, GO TO Step 41.

AND only one Letdown filter is desired.

40. Perform of the following:

. Place 1HP-17 switch to CLOSE.

. Place 1HP-18 switch to CLOSE.

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

... END.

Page 42 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 CRITICAL TASKS

1. CT-I, Trip ALL RCPs (Page 22)

2. CT-4, Initiate LPI (Page 32)

3. CT-18, Trip the Turbine (EHC Pumps PTL (Page 20)

4. CT-27, Implementation of Control Room Habitability Guidance (Page 28)

Page 43 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 SAFETY: Take a Minute UNIT 0 (OSM)

SSF Operable: Yes I KHLJs Operable: N Ui UG, U2 OH LCTs Operable: 2

- - 1 Fuel Handlina: No UNIT STATUS (CR SRO)

Unit I Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 85% Mode: 1 Mode: 1 Gross MWE: 778 100% Power 100% Power RCS Leakage: 0.024 gpm EFDW Backup: Yes EFDW Backup: Yes RBNS Rate:0.0l gpm Technical SpecificationslSLC Items (CR SRO)

ComponentlTrain OOS Restoration TSISLC #

DatelTime Required DatelTime TDEFWP 24 hrs ago 48 hrs from now Condition B Shift Turnover Items (CR SRO)

Primary

. SASS in Manual for I&E

. Maintain Letdown Flow 71 gpm for Letdown Cooler performance evaluation Secondary

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

• Holding power at 85% while monitoring 1A FDWP due to issues with oil coolers. Have the OSM notify component engineer immediately if any unusual alarms/indications occur.

Reactivity Management CR SRO)

R2 Reactivity management controls RCS Boron: 6 ppmB Gp 7 Rod Position: 78% established in the Control Room per SOMP 01-02 Human Performance Emphasis (OSM)

Procedure Use and Adherence Page 44 of 44

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 3i9p))

Facility: Oconee Scenario No.: 3 rI Op-Test No.: 1 Examiners: Operators:

Initial Conditions:

. ReactorPower=3% Unit 2: 100%, Unit 3: 100%

Turnover:

. Waiting on revised maneuvering plan from Reactor Engineering to continue with power increase

. Leave both Letdown Filters in service until 100% per Primary Chemistry

. Perform 5 Minute Delith Using Deborating IX per OP/i/All 103/004 C Enclosure 4.4 beginning at step 2.8.

Event Malfunction Event No. No. E vent T ype

• Description Oa Override ES Channel 3 will not go to Manual following actuation Ob MPI300 Block All Rx Trips except Manual Oc Override AFIS Disabled 1 N: OATC, SRO 5 Minute Delith Using Deborating IX 2 MSS200 C, BOP, SRO Vacuum Leak 3 Override SRO TS PZR Level 3 fails low requiring application of Tech Spec 3.3.8 (TS) 4 MSS45O C: BOP, SRO (TS) 1C RBCU Rupture (TS) 5 MPSO9O C: OATC SRO 1HP-120 (RC Volume Control) Fails CLOSED 6 Override C: BOP, SRO Vent 1 B CFT to QT 7 MEL22O 1TB Lockout causes a loss of 1A2 and 1B2 RCP C: OATC SRO requiring a Manual Reactor Trip 1 B MSLB in the reactor building 8 MSS36O M: ALL ES-3 fails to go to Manual for securing LPI pumps (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: I Page 1 of 2 Event

Description:

5 Minute Delith Using Deborating IX Time Position Applicants Actions or Behavior Crew Response:

SRO Turnover should direct OATC to perform OP/i/Ni 103/004 C Enclosure 4.4 to place Unit 1 Deborating IX in service for a 5 minute Delith beginning at Step OATC 2.8.

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

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

. Appropriate ranged NIs

. Primary tank levels

. Neutron error

. CRD position

. IX run-time for proper chemistry control 2.9 Align Unit 1 Deborating IX for service:

2.9.1 Verify closed 1CS-32 & 37 (SPARE DEBOR IX INLET & OUTLET) 2.9.2 Ensure closed 1CS-26 (LETDOWN TO RC BHUT) 2.9.3 Open 1 CS-27 (DEBOR IX INLET) 2.9.4 Verify 1 HP-i 5 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 may be performed in any order 2.11 IF sample is desired AND Unit I Deborating IX will be in service for> 20 minutes, notify Chemist to begin flush for sample of Unit I Deborating IX effluent. (R.M.)

This event is complete when the crew reaches Step 2.17, or as directed by the Lead Examiner.

Page2of38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: I Page 2 of 2 Event

Description:

5 Minute Delith Using Deborating IX Time Position Applicants Actions or Behavior j

Crew Response:

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 1CS-26 (LETDOWN TO RC BHUT)

_2.14.2 WHEN complete, close 1CS-26 (LETDOWN TO RC BHUT) 2.15 IF sample is desired AND Unit 1 Deborating IX has been in service for> 20 minutes, prior to completing run time ensure Chemist has sampled Unit 1 Deborating IX effluent (R.M.)

ExaminerlBooth Note: Event 2 (Vacuum leak) should be initiated about 2 minutes into the delith.

2.16 WHEN run time is complete, perform the following:

2.16.1 Position 1 HP-i 4 (LDST BYPASS) to NORMAL

_2.i6.2 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 Examiner.

Page 3 of 38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: 2 Page 1 of 1 Event

Description:

Vacuum Leak Time Position Applicants Actions or Behavior Plant Response:

• 1 SA-3/A-6, Condenser Vacuum Low (25 Hg)

Crew response:

I SA-3/A-6, Condenser Vacuum Low 3.1 Refer to AP/21N1 700/027 AP/1/A11700/027 (Loss of Condenser Vacuum)

SRO/BOP 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.

4.3 Dispatch operators to perform the following:

Perform End 5.1 (Main Vacuum Pump Alignment)

Look for vacuum leaks 4.4 Ensure available Main Vacuum Pumps operating (A, B, & C)

Booth Cue: After all MVPs are running, using TIME COMPRESSION, call the Control Room to notify the operator that the Main Vacuum Pumps are aligned to Unit 1.

4.5 Ensure 1V-186 is closed 4.6 Ensure Steam to Steam Air Ejector A, B, C > 255 psig 4.7 Verify Steam Seal Header Press> 1.5 psig 4.8 Ensure all available CCW pumps operating Booth Cue: Call Control Room as the NEO sent out to look for vacuum leaks and report that a leak was found on 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 SRO reaches Step 4.10 of AP1027, or as directed by the lead examiner.

Page4of38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: 3 Page 1 of 2 Event

Description:

PZR Level 3 fails low requiring application of Tech Spec 3.3.8 (TS)

Time Position

[ ApplicanVs Actions or Behavior Plant Response:

Statalarms:

• ISA-02/C-3 (RC PRESSURIZER LEVEL HIGH/LOW)

Board indications:

• PZR LVL 3 Level indicator on UB1 failed low Crew Response:

Refer to ARG ISA-02/C-3 (RC PRESSURIZER LEVEL HIGH/LOW)

OATC/BOP

1. Alarm Setpoint Low = 200 water

2. Automatic Action None Examiner Note: The crew should note, by looking at PZR level 1 & 2 indications, that this is an instrument failure only and no actual change in PZR level has occurred.

NOTE The crew may refer to PT/1/A/0600/001 Periodic Instrument Surveillance which is located in the OSMs office. The crew may dispatch contact SPOC to determine the cause of the PZR level channel 3 failure.

3. Manual Action 3.1 Check alternate PZR level indications.

3.2 Check for proper Makeup/Letdown flows and adjust as necessary.

SRO 3.3 Refer to the following procedures as required: NIA o . AP/i/AI1 700/002 (Excessive RCS Leakage) o . AP/1/A/1700/014 (Loss of Normal HPI Makeup and/or RCP Seal Injection) o . AP/1/A11700/032 (Loss of Letdown).

3.4 Refer to Technical Specification 3.4.9. NIA 3.5 Refer to Technical Specification 3.3.8.

3.6 Refer to OP/i/Ni 105/014 (Control Room Instrumentation Operation And Information). Determines section 4.11 is applicable section (next page)

Examiner Note: The failure of PZR LVL 3 requires the SRO to make a Tech Sec determination. The applicable Tech Spec is 3.3.8 Condition A. The Completion Time is 30 days to restore the failed channel to operable status.

This event is complete when PZR level 3 is determined to be an instrument failure and the SRO has made the Tech Spec determination ,or as directed by the Lead Examiner.

Page 5 of 38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: 3 Page 2 of 2 Event

Description:

PZR Level 3 fails low requiring application of Tech Spec 3.3.8 (TS)

Time Position Applicants Actions or Behavior Crew Response (cont):

OP/i/Ni 105/014 Section 4.11 SASS Information BOP NOTE:

An instantaneous mismatch (rapid mismatch >6%) can occur and clear immediately. This will cause only a red Trip light to illuminate without an amber Mismatch light or QAC mismatch alarm. The green Auto light will also be off.

3.1 SASS (Smart Automatic Signal Selector) Auto Operation 3.1.1 SASS for Pzr level looks at Pzr level 1, 2, or 3. If level 1 or 2 fails, SASS will AUTO swap to Pzr level 3.

3.1.2 IF AUTO light is off, MISMATCH light is on, and TRIP A or TRIP B light is on, a SASS trip has occurred.

A. Controlling signal will be signal which does NOT have a TRIP light illuminated.

NOTE: Failure to swap switch to valid signal could result in failed signal feeding through if SASS is reset before signal is repaired.

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

3.1.3 IF AUTO light is off and 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 (for parameters in ICS Cabinet

1. 8).

3.1.4 Initiate a Work Request to repair faulty signal.

NOTE: Since PZR level 3 will not be repaired during this scenario, the rest of Section 4.il is N/A This event is complete when PZR level 3 is determined to be an instrument failure and the SRO has made the Tech Spec determination , or as directed by the Lead Examiner.

Page6of38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: 4 Page 1 of 2 Event

Description:

IC RBCU Rupture (TS)

Time Position Applicants Actions or Behavior Plant Response:

• ISA-9/D-9, LPSW RBCU C Cooler Rupture

• 1SA-9/A-6, RB Normal Sump Level High/Low

• RB normal sump level will increase

• 1 C RBCU LPSW flow indicator indicates low on VB2 Crew Response:

ARG for 1SA-91D-9 (Manual Actions)

SRO/BOP 3.1 Verify alarm is valid by checking RBCU 1C Inlet Flow and RBCU 1C delta flow.

3.2 Verify 1 LPSW-24 (RBCU 1 C Outlet) open 3.3 Verify adequate LPSW flow is available; check LPSW pump operation 3.3.1 Verify ILPSW-22 (1C RBCU INLET) is open.

3.3.2 IF 1 LPSW-22 (IC RBCU INLET) is NOT open, refer to Technical Specifications and Selected Licensee Commitments 3.4 Monitor RBNS Level for any unexplained increase 3.5 IF RBNS Level is increasing AND ES has actuated, notify Chemistry to sample RBNS for boron to determine if a cooler rupture has occurred.

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

NOTE: This sequence prevents having to call LPSW and Containment inoperable per SLC 16.9.12.

3.6.1 Isolate the 1C RBCU Cooler as follows:

A. Close 1LPSW-22 (1C RBCU INLET).

B. Close 1LPSW-24 (RBCU 1C OUTLET).

C. Perform TS 3.6.3 Condition C (C.1 = 4 hrs & C.2 31 days) for SRO closed containment system (as required).

D. Enter TS 3.6.5 Condition B (7 days and 14 days from discovery of failure to meet LCO) 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 1C RBCU.

This event is complete when the IC RBCU rupture is isolated, or as directed by the lead examiner.

Page7of38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: Event No.: 4 Page 2 of 2 Event

Description:

IC RBCU Rupture (TS)

Time Position Applicants Actions or Behavior Crew Response (cont.):

EXAMINER NOTE: The crew may decide to pump the RB Normal Sump. If so, see the steps below from OP/I/NI 104/007 LWD System, Enclosure 4.1 Pumping RBNS to 6 SRO 3.6.2 Refer to Technical Specifications 3.6.3 Refer to SLC 16.9.12 OP/11N1104/007 Enclosure 4.1 BOP 3.1 Verify MWHUT level adequate to receive waste volume.

3.2 Position the following:

• Ensure open 1 LWD-1 (RB NORMAL SUMP ISOLATION)

• Ensure open 1 LWD-2 (RB NORMAL SUMP ISOLATION) 3.3 Start one or both of the following:

• IA RB NORM SUMP PUMP

• lB RB NORM SUMP PUMP NOTE:*

Changes in LAWT levels may occur during pumping.

RIA Alarms may be indicative of gas leakage.

If RBNS level was above 14 when pumps were started, a level increase following securing the RBNS pumps may occur. {7}

3.4 WHEN RBNS is at desired level OR at 6 (low level alarm), ensure the following:

• 1A RB NORMAL SUMP PUMP OFF

• lB RB NORMAL SUMP PUMP OFF.

3.5 IF required to close the valves, position the following:

• Close ILWD-1 (RB NORMAL SUMP ISOLATION)

• Close 1 LWD-2 (RB NORMAL SUMP ISOLATION)

This event is complete when the IC RBCU rupture is isolated, or as directed by the lead examiner.

Page 8 of 38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: 5 Page 1 of 2 Event

Description:

IHP-120 (RC Volume Control) Fails CLOSED Time__[ Position Applicants Actions or Behavior Note: This event should be initiated once ARG ISA-91D9 has been reference in event #4.

Plant Response:

• RCS makeup flow goes to 10 gpm (HPI Warming Flow)

• PZR level begins to decrease

• LDST level begins to increase

• Valve position demand for 1HP-120 begins to increase to the 100%

demand value and valve position indication will indicate closed (green light)

• 1SA-02/ B-i, HP LETDOWN TANK LEVEL HIGH/LOW, will illuminate after several minute time delay Crew Response:

SRO/OATC The crew may refer to ARG 1 SA-02/B-1, HP LETDOWN TANK LEVEL HIGH/LOW and perform the required actions.

3.1 Instrument Failed:

3.1.1 Compare alternate channels to verify alarm validity:

• O1A1 042 LDST LEVEL 1

• O1AI 043 LDST LEVEL 2 3.2 Verify LDST pressure does not exceed LDST level/pressure operability requirement per OP/i/All 104/002, (HPI System).

3.3 IF High Level alarm is received:

3.3.1 Bleed as required by OP/i/Ni 103/004 (Soluble Poison Concentration Control).

EXAMINER NOTE: Enclosure 4.8 may be performed at any time the crew OATC desires to reduce inventory. Enclosure 4.6 is performed if they desire to makeup/batch. See page 31 OP/1/A/1i03/004, Soluble Poison Concentration Control (Enclosure 48 Reducing RCS Inventory) 2.1 Verify HPI System operating.

2.2 Ensure open 1CS-26 (LETDOWN TO RC BHUT).

2.3 Ensure open 1CS-41 (1A RC BHUT INLET).

2.4 Position 1HP-14 (LDST BYPASS) to BLEED.

2.5 WHEN desired LDST level achieved, position 1HP-14 to NORMAL.

SRO/OATC/ Refer to AP/i/Ni700/014, Loss of Normal Makeup and/or RCP Seal Injection BOP 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)

This event is complete when Pzr level is returned to normal band (200-230), or as directed by the Lead Examiner.

Page9of38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.:ILT4I Scenario No.: 3 Event No.: 5 Page 2 of 2 Event

Description:

IHP-120 (RC Volume Control) Fails CLOSED Time Position Applicants Actions or Behavior Examiner Note: The crew may initiate EOP End 5.5 for RCS inventory control due LDST level increase (see page 23)

Crew Response:

SRO/OATC/ AP/1/A/1700/014, Loss of Normal Makeup and/or RCP Seal Injection BOP 3.2 IAAT loss of suction to operating HPI pumps is indicated:

• Motor amps low or cycling

• Discharge pressure low or cycling

• Abnormal LDST level trend THEN GO TO Step 3.3 RNO: GO TO Step 4.7 4.7 Announce AP entry using PA System 4.8 Verify y HPI pump operating 4.9 Verify RCP seal injection or HPI makeup line leak indicated by y of the following:

• Report of line leak

• Abnormal LDST level decrease

• 1 RIA-32 (AUX BLDG GAS)

• 1RIA-45 (NORM VENT GAS)

• RB RlAs in alarm

• Abnormal RBNS level increase

• Abnormal LAWT or HAWT level increase RNO: GOTOStep4.11 4.11 Verify RCP seal injection flow exists to y RCP 4.12 Verify 1HP-120 operable in AUTO RNO: 1. Attempt to operate 1HP-120 in HAND

2. IF 1HP-120 fails to operate, THEN GO TO Step 4.176 4.176 Perform the following as necessary to maintain Pzr level > 200

• Close 1HP-6

• Throttle 1HP-7

• Throttle 1HP-26 4.177 Place 1HP-120 in HAND and close 4.178 Notify SPOC to investigate and repair 1HP-120 4.179 WHEN 1HP-120 is repaired, THEN slowly re-establish flow through 1HP-120 Note: IHP-120 will remain failed for the remainder of the scenario.

This event is complete when Pzr level is returned to normal band (200-230), or as directed by the Lead Examiner.

Page 10 of 38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: 6 Page 1 of 1 Event

Description:

Vent lB CFT to QT Time Position Applicants Actions or Behavior Plant Response:

Statalarms:

• ISA-08!A-12 (CORE FLOOD TANK B PRESSURE HIGH/LOW) o Alarm Setpoint High Alarm 615 psig increasing pressure.

Board indications:

• All CFT B pressure indications are 615 psig Crew Response:

Refer to ARG 1SA-081A-12 (CORE FLOOD TANK B PRESSURE HIGH/LOW)

SRO/BOP Automatic Action: None ARG for ISA-08/A-12 (Manual Actions) 3.1 Refer to OP/1/A/1104/001 (Core Flooding System) to adjust pressure as necessary.

OP/1/A11104/001 Enclosure 4.13 (Lowering lB CFT Pressure)

Booth Cue: If asked, the High Pressure N 2 Header is in service.

NEO may be dispatched to determine if N 2 might be leaking into the CFT.

3.1 Verify high pressure nitrogen header in service.

3.2 RCS > 800 psig.

3.3 Verify lB CFT 610 psig:

EXAMINER NOTE: If the CFT pressure rise is not mitigated in a timely manner the consequence will be CFT pressure exceeding 625 psig. Then TS 3.5.1 Condition B will apply. Completion time is 1 hr.

3.4 Review TS 3.5.1 (CFTs).

3.5 IF RB is open for entry, perform the following: NIA 3.6 Station an Operator at 1XP-R2B (1CF-6 Bkr).

3.7 Remove White Tag and close 1XP-R2B (1 CF-6 Bkr).

NOTE: 1 CF-6 must be throttled with a series of small bumps to switch. 1 CF-6 may NOT indicate throttled as CFT pressure begins to decrease.

3.8 Throttle 1CF-6 (lB CFT VENT).

3.9 IF AT ANY TIME QT approaches 5 psig, perform the following:

3.9.1 Close 1CF-6 (lB CFT VENT).

3.9.2 Depressurize QT per OP/1/A11104/017 (Enclosure 4.4) 3.9.3 IF I B OFT depressurization needs to continue, throttle 1 OF-6 3.10 WHEN OFT pressure is acceptable, close ICF-6 (lB OFT VENT) switch.

This event is complete when ICF-6 is closed to vent the Quench Tank in step 3.9.1, or as directed by the Lead Examiner.

Page 11 of38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: 7 Page 1 of I Event

Description:

ITB Lockout causes a loss of 1A2 and 1B2 RCP requiring a Manual Reactor Trip Time Position Applicants Actions or Behavior Plant Response:

ITB lockout will occur. This will cause a loss of 6900V power to the 1A2 and 1 B2 RCP. RPS alarms will occur indicating that the Reactor should have tripped, but it will remain at power.

Crew Response:

Recognizes the reactor should have tripped (<3 RCPs operating with OATC Reactor power >2%. OMP 1-18 Att. A), therefore manually trips the Reactor and then perform Immediate Manual Actions of the EOP.

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.

EXAMINER NOTE: The steam line break is automatically fired when the rods hit the bottom from the manual Rx trip. With an Excessive Heat Transfer in progress the SRO should not get an opportunity to take any of the Subsequent actions in the SA Tab.

. The BOP will perform a symptom check. See Event #8 below for BOP expected results of symptom check.

This event is complete when an operator has manually tripped the Reactor and the IMAs have been performed, or as directed by the lead examiner.

Pagel2of38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: 8 Page 1 of 10 Event

Description:

I B MSLB in the reactor building, ES-3 fails to go to Manual for securing LPI pumps Time Position Applicants Actions or Behavior Plant response:

• iSA-i/A-i, B-i, C-i, D-1, RP Channel Trip

• 1 SA-21D-3, RC Press High/Low

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

• The 1A RBCU will fail to start in Low speed on ES Channel 5 actuation

• ES Channels 1-8 will actuate Crew response:

SROBOP BOP will perform a Symptoms Check (per OMP 1-18 Attachment C)

• Reactivity Control o Power Range NIs <5% and decreasing

• ICC/Loss of Subcooling Margin (SCM) o If any SCM 0°F, perform Rule 2

• Loss of Heat Transfer (LOHT) o Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW)

• Excessive Heat Transfer (EHT) o Uncontrolled Main Steam Line(s) pressure decrease

• Steam Generator Tube Rupture o CSAE off-gas alarms, process RIAs (RIA-40, 59, 60), area RlAs (RIA 16/17)

BOP performs Rule #5 (Main Steam Line Break) after receiving concurrence from the SRO (details on page 16)

Examiners Note: The crew may recognize that ES channels 3 and 4 did not automatically actuate and the CR SRO may direct manual actuation.

Page 13of38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: 8 Page 2 of 10 Event

Description:

I B MSLB in the reactor building, ES-3 fails to go to Manual for securing LPI pumps Time__[__Position Applicants Actions or Behavior SRO SRO refers to Parallel Actions page of the Subsequent Actions Tab and transfers to the Excessive Heat Transfer Tab SRO will direct performance of EOP Enclosure 5.1 (ES Actuation) (details begin on page 19)

The SRO will direct Excessive Heat Transfer Tab actions The SRO will direct an RO to make a PA announcement and notify the OSM to reference the Emergency Plan and NSD-202 SRO/BOP Crew Response:

/OATC EOP Excessive Heat Transfer Tab (EHT)

1. Verify jy 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 ll affected SGs:

• 1 FDW-41 and 1 FDW-44(for 1 B SG)

4. Close the following on all affected SGs:

• 1FDW-382, IMS-26, IMS-76, 1MS-36, 1MS-84, 1FDW-369

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

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

7. Throttle HPI per Rule 6 (HPI) (CT-5)

Note: HPI flow must be throttled and RCS temperature controlled to prevent a solid Pzr and subsequent operation of the PORV.

8. Verify letdown in service.

RNO: IF desired to restore letdown, THEN initiate End 5.5 (Pzr and LDST Level Control) (see page 23)

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

10. Open the following on a intact SGs

• 1FDW-372, 1FDW-368, and 1MS-17

11. Start MDEFDWP associated with a intact SGs

• IAMDEFDWP Page 14 of 38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: 8 Page 3 of 10 Event

Description:

lB MSLB in the reactor building, ES-3 fails to go to Manual for securing LPI pumps Time Position Applicants Actions or Behavior SROIBOPI 12. Feed and steam intact SGs to stabilize RCS PIT using either of the following:

OATC

• TBVs

• Dispatch two operators to perform End 5.24 (Operation of the ADV5)

13. GOTOStep32

32. Verify y of the following:

HPI has operated in the injection mode while NO RCPs were operating A cooldown below 400°F at> 100°F/hr has occurred RNO: GOTOStep34

34. Verify 1 MS-24 and 1 MS-33 are closed

35. Open 1AS-8

36. Close 1SSH-9

37. Perform the following notifications:

• Notify Chemistry to determine RCS boron concentration and to sample RBES for boron.

• 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 aM the following exist:

• ES Bypass Permit satisfied

• AIISCMs>0°F

• RCS pressure controllable THEN bypass ES as necessary RNO: GO TO Step 41

41. Verify jy SG is dry

42. Minimize SCM using the following methods as necessary:

De-energize all Pzr heaters Use Pzr spray Throttle HPI to maintain Pzr level> 100 [180 acc]

Use PORV This event is complete when the SRO reaches step 32 or as directed by the lead examiner Page 15 of 38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: 8 Page 4 of 10 Event

Description:

I B MSLB in the reactor building, ES-3 fails to go to Manual for securing LPI pumps Tim Position Applicants Actions or Behavior e

EOP Rule 5 BOP/OATC 1. Perform the following on affected headers:

• Initiate AFIS lB SG Digital Channels 1 and 2

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

EXAMINER NOTE: Overcooling must be stopped prior to violating NDT limits. The critical task is to stop feeding the affected SG.

• Trip both Main FDW pumps

• Close 1FDW-316, 1FDW-42, and IFDW-40

2. Verify 1 TD EFDW PUMP operating.

RNO: IF MD EFDWP for the intact SG is operating, THEN GO TO Step 5.

5. Verify 1 B SG is an affected SG.

6. Open 1AS-40 while closing I MS-47.

7. WHEN overcooling is stopped, THEN adjust steaming of unaffected SG to maintain CETCs constant using either of the following:

• TBVs

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

8. WHEN fl of the following exist:

Core SCM >0° F Rx Pwr 1%

Pzr Level increasing, THEN continue

9. Verify ES HPI actuated

10. Place Diverse HPI in BYPASS

11. Place ES CH I and ES CH 2 in MANUAL

12. Perform the following to stabilize RCS PIT:

• Throttle HPI

• Reduce IHP-120 setpointto>100 (180 ACC)

• Adjust steaming of unaffected SG (1 B SG) to maintain CETCs constant

13. WHEN CETCs have stabilized, THEN resume use of Tc for RCS temperature control

14. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete (see next page)

15. Ensure Rule 8 (Pressurized Thermal Shock (PTS)) is in progress or complete

16. WHEN directed by CR SRO, THEN EXIT this rule Page 16of38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: 8 Page 5 of 10 Event

Description:

I B MSLB in the reactor building, ES-3 fails to go to Manual for securing LPI pumps Time Position [ Applicants Actions or Behavior EOP Rule 3 OATC/BOP 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 any EFDW pump operating.

6. GO TO Step 37.

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

RNO: GO TO Step 43

43. Verify any SCM 0°F.

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.

Examiners Note: The crew will recognize that RB pressure has exceeded 3 psig due to the MSLB and therefore be required to manually control SG levels at 60 inches XSUR Page 17 of 38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: 8 Page 6 of 10 Event

Description:

I B MSLB in the reactor building, ES-3 fails to go to Manual for securing LPI pumps

__Time Position Applicants Actions or Behavior OATC/BOP End 5.9 (Extended EFDW Operation) as directed by Rule 3

1. Monitor EFDW parameters on EFW graphic display.

2. IAAT UST level is <4, THEN GO TO Step 120

3. IAAT feeding SGs with one MD EFDWP is desired, THEN perform Steps 4-7 RNO: GO TO Step8

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

• Makeup with demin water.

• Place CST pumps in AUTO.

9. IAAT the following exist:

• Rapid cooldown NOT in progress

• MD EFDWP operating for each available SG

• EFDW flow in each header < 600 gpm THEN place I TD EFDW PUMP switch in PULL TO LOCK.

10. Verify I TD EFDW PUMP operating.

RNO: GO TO Step 12 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 and EOP activities.

Page 18 of 38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: 8 Page 7 of 10 Event

Description:

lB MSLB in the reactor building, ES-3 fails to go to Manual for securing LPI pumps Time Position Applicants Actions or Behavior EOP Enclosure 5.1 (ES Actuation)

OATC/BOP

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.

EXAMINER NOTE: ES channels 3 & 4 did not actuate as expected therefore the crew must depress TRIP on ES channels 3 &4 if they have not already been actuated RNO: Depress TRIP on affected ES logic channels that have NOT previously been actuated

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

4. Place Diverse HPI in BYPASS

5. Place ES CH I and ES CH 2 in MANUAL

6. Verify Rule 2 in progress or complete.

RNO: GO TO Step 73

73. Open 1HP-24 and IHP-25

74. Ensure at least two HPI pumps are operating

75. Verify 1HP-26 and 1HP-27 are open NOTE TO EXAMINER: Conditions not met to require opening I HP-41 0 or 1 HP-409. No operator action required at this time by step 76.

76. 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:

J I Header q I B Header 1HP-410 1HP-409

77. Verify y RCP operating

78. Open 1HP-20 and 1HP-21 Page 19 of 38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: 8 Page 8 of 10 Event

Description:

lB MSLB in the reactor building, ES-3 fails to go to Manual for securing LPI pumps Time Position Applicants Actions or Behavior EOP Enclosure 5.1 (ES Actuation)

OATC/BOP

79. IAAT all exist:

Voter associated with ES channel is in OVERRIDE An ES channel is manually actuated Components on that channel required manipulation THEN depress RESET on the required channel

80. IAAT y RCP is operating, AND ES Channels 5 and 6 actuate, THEN perform Steps 81 84 -

81. Place ES CH 5 and ES CH 6 in MANUAL

82. Open:

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

83. Ensure only one CC pump operating

84. Ensure Standby CC pump in AUTO

85. IAAT ES Channels 3 & 4 are actuated, THEN GO TO Step 86

86. Place Diverse LPI in BYPASS Examiners Note: ES-3 will NOT go to MANUAL and will require override of the Odd Voters per the RNO.

87. Place ES CH 3 and ES CH 4 in MANUAL RNO:

NOTE Voter OVERRIDE affects all channels of the affected ODD and/or EVEN channels.

In OVERRIDE, all components on the affected ODD and/or EVEN channels can be manually operated from the component switch.

1. IF ES CH 3 fails to go to MANUAL, THEN place ODD voter in OVERRIDE

2. IF ES CH 4 fails to go to MANUAL, THEN place EVEN voter in OVERRIDE.

Page 20 of 38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: 8 Page 9 of 10 Event

Description:

lB MSLB in the reactor building, ES-3 fails to go to Manual for securing LPI pumps Time Position Applicants Actions or Behavior EOP Enclosure 5.1 (ES Actuation)

CAUTION OATC/BO P LPI pump damage may occur if operated in excess of 30 minutes against shutoff head

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

89. IAAT RCS pressure is < LPI pump shutoff head, THEN perform Steps 90 91 RNO: GO TO Step 92

92. IAAT IA and I B LPI PUMPs are off/tripped, AND all of the following exists RNO: GO TO Step 95

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

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

97. Start A and B OUTSIDE AIR BOOSTER FANS

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

99. Verify 1CF-1 and 1CF-2 are open 100. Verify IHP-410 closed 101. Secure makeup to the LDST Note:

IA & lB LPI pumps, IHP-26, IHP-20, and IHP-2I will not be in its ES position due to being repositioned by the operators.

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

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

3. IF I HP-20 fails to close and no RCPs operating, THEN close IHP-228, 1HP-226, 1HP-232, & 1HP-230

4. Notify SRO to evaluate components NOT is ES position and initiate action to place in ES position if desired Page 21 of 38

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: ILT4I Scenario No.: 3 Event No.: 8 Page 10 of 10 Event

Description:

lB MSLB in the reactor building, ES-3 fails to go to Manual for securing LPI pumps Time Position Applicants Actions or Behavior EOP Enclosure 5.1 (ES Actuation)

OATC/BOP 103. Verify Unit 2 turbine tripped RNO: GOTOStep 106 106. Close I LPSW-1 39 107. Place ILPSW-251 and 1LPSW-252 FAIL SWITCH in FAIL OPEN 108. Start all available LPSW pumps 109. Verify either:

Three LPSW pumps operating Two LPSW pumps operating when TS only requires two operable 110. Open 1 LPSW-4 and 1 LPSW-5 111. IAAT BWST level 19, THEN initiate End 5.12 (ECCS Suction Swap to RBES) 112. Dispatch an operator to perform End 5.2 (Placing RB Hydrogen Analyzers In Service) (PS) 113. Select DECAY HEAT LOW FLOW ALARM SELECT switch to ON 114. IAAT ES channels 5 & 6 have actuated, THEN perform Step 115 115. Verify aH ES channel 5 & 6 components in the ES position RNO: Notify SRO to evaluate components NOT in ES position initiate action to place in ES position if desired Note: ICC-7, ICC-8, ILPSW-6, and ILPSW-15 will not be in the ES position.

116. IAAT ES channels 7 & 8 have actuated, THEN perform Step 117 118 117 Place ES CH 7 and ES CH 8 in Manual 118. Verify all ES channel 7 & 8 components are in the ES position 119. Notify U2 CR SRO that SSF is inoperable due to OTS1 -1 open 120 Ensure any turnover sheet compensatory measures for Es actuation are complete as necessary 121. IAAT conditions causing ES actuation have cleared, THEN initiate End 5.41 (ES Recovery) 122. WHEN CR SRO approves, THEN EXIT this enclosure This event is complete when the SRO reaches step 32 of the EHT tab or as directed by the lead examiner Page 22 of 38

Appendix D Scenario Outline Form ES-D-2 Page 1 of 8 NOTE At any time during this scenario the operator may choose to use Enclosure 5.5 to maintain RCS inventory control. See below.

ENCLOSURE 5.5 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Maintaining Pzr level >100 [180 acc] will ensure Pzr heater bundles remain covered.

1. Utilize the following as necessary to maintain IF I HP-26 will NOT open, desired Pzr level: THEN throttle I HP-41 0 to maintain

. 1A HPI Pump desired Pzr level.

. 1BHPI Pump

. 1HP-26

. 1HP-7

. 1 HP-i 20 setpoint or valve demand

. 1HP-5

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

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

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

A. Open:

1CS-26 1CS-41 B. Position 1HP-I4 to BLEED.

C. Notify SRO.

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

Page 23 of 38

Appendix D Scenario Outline Form ES-D-2 Page 2of8 ENCLOSURE 5.5 (cont.)

I ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

6. IAAT IC HPI PUMP is required, GO TO Step 10.

THEN perform Steps 7-9.

7. Open: 1._ IF both BWST suction valves

• 1HP-24 (1HP-24 and 1HP-25) are closed, THEN perform the following:

• 1 HP-25 A. Start 1A LPI PUMP.

B. Start lB LPI PUMP.

C. Open:

1LP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D. IF two LPI Pumps are running Qjjy to provide HPI pump suction, THEN secure one LPI pump.

E. Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, Ui LPI Hatch Rm, N end).

F. GO TO Step 8.

2._ IF only one BWST suction valve (1HP-24 or 1HP-25) is open, THEN perform the following:

A. IF three HPI pumps are operating, THEN secure lB HPI PUMP.

B. IF <2 HPI pumps are operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers.

C._ GOTO Step 9.

Page24of38

Appendix D Scenario Outline Form ES-D-2 Page3of8 ENCLOSURE 5.5 (cont.)

ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

8. Start 1C HPI PUMP. IF at least two HPI pumps are operating, THEN throttle 1 HP-409 to maintain desired Pzr level.

9. Throttle the following as required to 1 . IF at least two HPI pumps are operating, maintain desired Pzr level: AND 1 HP-26 will NOT open, THEN throttle IHP-410 to maintain

desired Pzrlevel.

2._ IF IA HPI PUMP and 1 B HPI PUMP are operating, AND I HP-27 will NOT open, THEN throttle 1 HP-409 to maintain desired Pzr level.

Page 25 of 38

Appendix D Scenario Outline Form ES-D-2 Page4of8 ENCLOSURE 5.5 (cont.)

ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

10. IAAT LDST vel CANNOT be GO TO Step 12.

maintained, THEN perform Step 11.

ii. Perform the following: 1._ IF both BWST suction valves

• Open 1 HP-24. (1HP-24 and 1HP-25) are closed, THEN perform the following:

• Open 1 HP-25.

A. Start 1A LPI PUMP.

• Close 1HP-16.

B. Start lB LPI PUMP.

C. Open:

1LP-15 ILP-16 1LP-9 1LP-i0 1LP-6 1LP-7 D. IF two LPI Pumps are running jy to provide HPI pump suction, THEN secure one LPI pump.

E. Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-i-i i9, Ui LPI Hatch Rm, N end).

F. GO TO Step 12.

2._ IF only one BWST suction valve (1HP-24 or 1HP-25) is open, AND three HPI pumps are operating, THEN secure lB HPI PUMP.

Page 26 of 38

Appendix D Scenario Outline Form ES-D-2 Page 5of8 ENCLOSURE 5.5 (cont.)

ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

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

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

. Open IHP-17.

. Open 1HP-18

14. IAAT of the following exist: GO TO Step 34.

. Letdown isolated

. LPSW available

. Letdown restoration desired THE N perform Steps 15- 33. .

15. Open: 1 . Notify CR SRO that letdown CANNOT be

. 1CC-7 restored due to inability to restart the CC

. 1 CC-8 system.

2._ GO TO Step 34.

16. Ensure only one CC pump running.

17. Place the non-running CC pump in AUTO.

18. Verify i2 are open: 1 . IF I HP-I is closed due to I HP-3 failing to

. IHP-1 close,

. 1 HP-2 THEN GO TO Step 20.

2._ IF IHP-2 is closed due to IHP-4 failing to close, THEN GO TO Step 20.

19. GOTO Step 22.

NOTE Verification of leakage requires visual observation of East Penetration Room.

20. Verify letdown line leak in East GO TO Step 22.

Penetration Room has occurred.

21. GOTO Step 34.

Page 27 of 38

Appendix D Scenario Outline Form ES-D-2 Page6of8 ENCLOSURE 5.5 (cont.)

ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

22. Monitor for unexpected conditions while restoring letdown.

23. Verify both letdown coolers to be placed 1. IF IA letdown cooler is to be placed in in service, service, THEN open:

1 HP-i 1 HP-3 2._ IF lB letdown cooler is to be placed in service, THEN open:

1 HP-2 1 HP-4 3._ GOTO Step 25.

24. Open:

. 1HP-i

. 1HP-2

. 1HP-3

. 1HP-4

25. Verify at least one letdown cooler is Perform the following:

aligned. A. Notify CR SRO of problem.

B. Step 34.

26. Close 1HP-6.

27. Close IHP-7.

28. Verify letdown temperature < 125°F. I._ Open 1HP-I3.

2. Close:

1 HP-8 1HP-9&ii 3._ IF y deborating IX is in service, THEN perform the following:

A. IHP-14 to NORMAL.

B. 1HP-16.

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

Page 28 of 38

Appendix D Scenario Outline Form ES-D-2 Page 7of8 ENCLOSURE 5.5 (cont.)

ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED

29. Open 1HP-5.

30. Adjust 1 HP-7 for 20 gpm letdown.

31. WHEN letdown temperature is < 125°F, THEN place LETDOWN HI TEMP INTLK BYP switch to NORMAL.

32. Open 1HP-6.

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

NOTE AP132 (Loss of Letdown) provides direction to cool down the RCS to offset increasing pressurizer level.

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

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

A. Obtain SRO concurrence to reduce running HPI pumps.

B. Secure the desired HPI pumps.

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

36. IAAT the following conditions exist:

. Makeup from BWST NOT required

. LDST level > 55

. A control rods inserted

. Cooldown Plateau NOT being used THEN close:

. 1HP-24

. 1HP-25 Page 29 of 38

Appendix D Scenario Outline Form ES-D-2 Page 8of8 ENCLOSURE 5.5 (cont.)

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

37. Verify 1CS-48 (1A BHUT Recirc) has GO TO Step 39.

been closed to provide additional makeup flow to LDST.

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

A. Stop 1A BLEED TRANSFER PUMP.

B. Locally position 1CS-48 (1A BHUT Recirc) one turn open (A 1-107, Unit I RC Bleed Transfer Pump Rm.).

C. Close 1 CS-46.

D. Start IA BLEED TRANSFER PUMP.

E. Locally throttle 1CS-48 (1A BHUT Recirc) to obtain 90 110 psig discharge pressure.

F. Stop 1A BLEED TRANSFER PUMP.

39. Verify two Letdown Filters in service, GO TO Step 41.

AND only one Letdown filter is desired.

40. Perform of the following:

. Place IHP-17 switch to CLOSE.

. Place 1HP-18 switch to CLOSE.

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

• .. END.

Page 30 of 38

Appendix D Scenario Outline Form ES-D-2 Enclosure 4.6 opil /A/I 103/004 RCS Makeup From l And lB BRUT Page 2 of?

3. Makeup From IA and lB BIIUT NOTE:

• Adding the wrong volume of Makeup to RCS caii change final RCS boron and cause unanticipated reactivity changes. (R.M.)

• Placing an idle Letdown Filter in seivice can affect core reactivity by adding 60 gals of water at a different boron concentration. {S} R.M.)

• IA RC Bleed Storage Header can affect core reactivity by adding 60 gals of water at different boron than IA BHUT boron. {18} (R.M.)

3.1 Determine required RCS Makeup volume from each source by performing the following:

(R.M.)

3.1.1 IF desired. utilize Enclosure 4.1 (RC.S Boron Change Calculation) 3.1.2 IF two Letdown Filters are available AND one is NOT in service. perform the following: {9)

A. Review Component Boron Log for out-of-service Letdown Filter boron B. Make appropriate adjustments to Makeup volumes for placing second Letdown Filter in service 3.1.3 Perform the following A. Review Component Boron Log for 1A RC Bleed Storage Header boron.

{ 18)

B. Make appropriate adjustments to Makeup volumes based on 1A RC Bleed Storage Header boron 118) 3.1.4 Record required Makeup volume:__________________ gallons 3.2 Ensure required RCS Makeup vohune and source acceptable. (R.M.)

SRO 3.3 Notii Primar Chemistty of the following:

• Total Makeup volume to be added.

• Expected Boron change from the addition, Person Notified Date Page 31 of 38

Appendix D Scenario Outline Form ES-D-2 Enclosure OP/i/All 103/004 RCS Makeup From IA And lB BHUT Page 3 of 7 3.4 IF two Letdown Filters are available. perform the following:

• Open 1HP-l 7 (IA LETDOWN FILTER INLET)

• Open IHP-18 (lB LETDOWN FILTER INLET) 3.5 Ensure open 1HP-l 6 (LDST MAKEUP ISOLATION).

3.6 Makeup with 1HP-15 in 1 AUTO desired. perfonn the following:

3.6.1 Select S on 1HP-15 Controller.

3.6.2 Enter batch size on IHP-15 Controller. R.M.)

3.6.3 Place 1HP-15 Controller iii AUTO.

3.6.4 Ensure P on 1HP15 Controller.

3.7 WHILE making up to Unit 1 LDST from 1A and lB BHUT, monitor the following indications: {28} (R.M.)

• Appropriate ranged Xis

• Primary tank levels

• IF applicable. Neutron eior

• IF applicable. CRD position 3.8 IF AT ANY TIME abnormal condition(s) require stopping RCS Makeup. perfonri the following: {RM} {17}

3.8.1 Stop 1A BLEED TRANSFER PUMP.

3.8.2 IF RCS Makeup stopped due to alarm(s) abnormal indication(s).

notifr CRSRO.

3.8.3 WHEN conditions allow RCS Makeup to continue, perform one of the following:

• Start IA BLEED TRANSFER PUMP.

• Go To Step 3.13 to terminate the addition.

3,9 Start 1A BLEED TRANSFER PUMP.

NOTE: If only one Letdown Filter in seiice. 1 HP-iS may require tlottling for high P.

3.10 Open ICS-46 (IA RC BLEED XFER PUMP DISCH).

Page 32 of 38

Appendix D Scenario Outline Form ES-D-2 Enclosure 46 op/LA, 1103/003 RCS Makeup From IA And 18 BRUT Page 4 of 7

3. 11 IF increased Makeup flow required. perfonu the following: (Unit I BTP Rm).

• Throttle 1CS-48 (1A BHUT Recirc) to establish desired flow.

• Ensure 90 125 psig on ICS-PG-0084.

3.12 WHEN required volume is added. stop l BLEED TRANSFER PUMP.

3.13 Close ICS-46 (l RC BLEED ER PUMP DISCH). (R,M.)

NOTE:

• If during RCS Makeup the wrong volume is added, an SRO shall evaluate affect on reactivity and take action to minimize reactivity nianagement events. (R.MJ

• I HP-IS Controller volume will be different from volume based on LDST level change. {22}

3.14 Perfonn one of the followina: (R.Mj

• Verify correct volume added

• Notify CRSRO of incorrect volume added.

31 S Reset 1 HP 15 Controller for Nonnal Operation.

3.16 Record l BHUT boroii in Component Boron Log for l RC Bleed Storage Header.

(1SJ (R.M.j 3.17 IF Makeup with 1HP- 15 in AUTO desired. perfonu the following:

3,17.1 Select on 1HP-l 5 Controller.

3.17.2 Enter batch size on 1HP-1 5 Controller. (R.M.)

3.17.3 Place 1 HP- 15 Controller in 3.17.4 Ensure selected on 1 HP 15 Controller.

Page 33 of 38

Appendix D Scenario Outline Form ES-D-2 Enclosure 4,6 103/004 Op RCS Makeup From IA And lB BRUT Page 5 of 7 3.18 IF AT ANY TEIE abnormal condition(s) require stopping RCS Makeup. perform the following: (RM} (17) 3.18.1 Stop lB BLEED TRANSFER PUMP.

3.18.2 IF RCS Makeup stopped clue to alarm(s) OR abnormal indication(s).

notir CRSRO.

3.18.3 WREN conditions allow RCS Makeup to continue, perform one of the following:

• Start [B BLEED TRANSFER PUMP.

• Go To Step 3.23 to terminate the addition.

3.19 Start LB BLEED TRANSFER PUMP.

NOTE: If only one Letdown Filter in service. IHP-l 5 may require throttling for high tIP.

3.20 Opexi LCS-56 (LB RC BLEED XFER PUMP DISCH).

3.2 1 IF increased Makeup flow required. perforni the following: (Unit 1 -BTP Rn).

• Tluottle 1 CS-58 (13 BHUT Recire) to establish desired flow.

• Ensure 90- 125 psig on ICS-PG-0085.

3.22 WHEN required volume is added, stop lB BLEED TRANSFER PUMP.

3.23 Close ICS-56 (lB RC BLEED XFER PUMP DISCH). (P.M.)

NOTE:

• If during RCS Makeup the wrong volume is added, an SRO shall evaluate affect on reactivity and take action to minimize reactivity management events. (R.M.)

• 1 HP-i 5 Controller volume will be different from volume based on LDST level change. (22) 3.24 Perform one of the following: (R.M.

• Veri1 correct volume added

• Notify CRSRO of incorrect volume added.

3.25 Reset 1HP- 15 Controller for Normal Operation.

3.26 Close IHP-16 (LDST MAKEUP ISOLATION).

Page 34 of 38

Appendix D Scenario Outline Form ES-D-2 Eiiclosur op 1 i. io 004 RCS Makeup From IA And lB BHUT Page 6 of 7 3.27 Record RCS batch volumes in AutoLo2.

NOTE:

• I B Letdown Filter is prefetTeci filter to leave in service tbr ALARA.

Only one Letdown Filter should be in service to prevent cloging both filters during startup 3.28 IF desired to remove Letdown Filter from service, perform the following: (Coittinue) 3.28.1 Verify> 10 minutes since LDST Makeup was secured. (8} (R.M.)

3.28.2 Position one of the following:

• Close 1HP-17 (IA LETDOWN FILTER INLET)

• Close 1HP-18 (lB LETDOWN FILTER INLET) 3.28.3 Record RCS boron for out-of-service Letdown Filter in Component Boron Log. {9} R.M.)

3.29 IF RCS sample for boron required. notify Chemistry to sample. (RM.)

Person Notified Date 3.30 IF increased Makeup flow from 1 A BHUT was required. perform the following:

3.30.1 Stall 1A BLEED TRANSFER PUMP.

3.30.2 discharge Iressu e is NOT 90 110 psig. throttle 1CS-48 (IA BHUT Recire) to obtain 90 110 psig oil ICS-PG-0084, (Unit I BTP Rni) 3.30,3 Stop IA BLEED TRANSFER PUMP.

3.31 increased Makeup flow from lB BHUT was required. perfonn the following:

3.31.1 Stail lB BLEED TRANSFER PUMP.

3.31.2 IF discharge pressure is NOT 90 110 psig. throtile 1CS-5$ UB BHUT Recirc) to obtain 90 110 psig oil ICS-PG-008$. (Unit I BTP Rm) 3.31.3 Stop lB BLEED TRANSFER PUMP.

Page35of38

Appendix D Scenario Outline Form ES-D-2 ElicIoslare 4.6 OP/i/All 1031004 RCS Makeup From l Mid lB BHUT Page 7 of 7

4. Throttling 1HP-15 NOTE: If only one Letdown Filter in senice. 1HP- 15 may require throttling for high P. { 11 }

4. 1 Ensure 1HP-1 5 Controller in MANUAL.

4.2 Throttle 1HP- 15 as desired to control Makeup flow. { 11 }

5. Reducing RCS inventory 5.1 Ensure open ICS-26 (LETDOWN TO RC BHUT).

5.2 Ensure open 1CS-41 (1A RC BHTJT INLETt.

5.3 Position 1HP-i4 (LDST BYPASS) to t1 BLEED t

5.4 WHEN desired LDST level achieved, position 1HP-14 (LDST BYPASS) to t

HNORMALL Page 36 of 38

CRITICAL TASKS CT-17, Isolate overcooling SG (Page 16)

CT-5, Control HPI (Page 14)

Page 37 of 38

Appendix D Scenario Outline Form ES-D-1 ILT41 June 11,2012 SAFETY: Take a Minute UNIT 0 (OSM)

SSF Operable: Yes N KHUs Operable: - -

N Ui UG, U2 OH LCTs Operable: 2 1 Fuel Handling: No UNIT STATUS (CR SRO)

Unit I Simulator Other Units Mode: 2 Unit 2 Unit 3 Reactor Power: 3% Mode: I Mode: 1 Gross MWE: 0 100% Power 100% Power RCS Leakage: 0.024 gpm EFDW Backup: Yes EFDW Backup: Yes RBNS Rate: 0.01 gpm Technical SpecificationslSLC Items (CR SRO)

ComponentlTrain OOS Restoration Required TSISLC #

DatelTime DatelTime Shift Turnover Items (CR SRO)

Primary

. Tave=547°F

. Waiting on revised maneuvering plan from Reactor Engineering to continue with power increase

. Leave both Letdown Filters in service until 100% per Primary Chemistry

• Perform 5 Minute Delithiation Using Deborating IX per 0P111A111031004 C Enclosure 4.4 beginning at step 2.8.

Secondary

• 1 SSH-i, 1 SSH-3, I SD-2, 1 SD-5, 1 SD-i 40, 1 SD-303, 1 SD-355, I SD-356 and I SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event.

Reactivity Management CR SRO)

R2 Reactivity management controls RCS Boron = 1752 ppmb Gp 7 Rod Position: 28% established in the Control Room per SOMP 01-02 Human Performance Emphasis (OSM)

Procedure Use and Adherence Page 38 of 38