ML17174B289

__ 1HP-230 4.123 Open 1HP-21.

4.124 IAAT SEAL INLET HDR FLOW 32 gpm, THEN place 1HP-31 in AUTO.

4.125 Monitor RCP seal parameters.

4.126 Maintain RCP seal injection flows as required.

4.127 Log thermal cycle of 1A HPI header.

4.128 WHEN conditions permit, THEN EXIT this procedure.

TS 3.5.2 HIGH PRESSURE INJECTION (HPI)

Condition A.1 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) Restore HPI pump to OPERABLE status.

This event is complete when 1HP-31 is placed in AUTO or when directed by the Lead Examiner.

Page 10 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 3 Page 1 of 3 Event

Description:

Loop B Tc Fails low (I: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/028 Plant Response:

Loop "1B" Tc Dixson meter low (520°F)

Loop "1B" T Dixson meter reads 70°F

Tc meter reads low (+10°F; A loop Hot)

Controlling NR Tave digital display reads 570°F

Controlling Tave Chessell display reads 570°F

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

1SA-2/B-5, RC COLD LEG DIFF TEMP HIGH

1SA-2/A-12, ICS Tracking SRO/OATC Crew Response:

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

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

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

Note: The OATC will have to re-ratio FDW to maintain Tc 0°F + 2°F.

The CRS should:

Refer to AP/28, ICS Instrument Failures Ensure SPOC is contacted to repair the failed instrument.

AP/1/A/1700/028, ICS Instrument Failures Rev 20 4.1 Provide control bands as required. (OMP 1-18 Att. I)

OMP 1-18 Attachment I:

1. Plant Conditions Stable or TPB < Pre-transient Conditions

NI Power + 1% not to exceed the pre-transient or allowable power. If at the pre-transient or allowable level, band is NI Power - 1%.

Current Tave + 2°F.

Current SG Outlet Pressure + 10 PSIG (N/A)

Delta Tc 0 oF + 2°F.

This event is complete when the CRS reaches step 6 (WHEN) in AP/28 Section 4A, or as directed by the Lead Examiner.

Page 11 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 3 Page 2 of 3 Event

Description:

Loop B Tc Fails low (I: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/028 Crew Response:

SRO/OATC 4.2 Initiate notification of the following:

__ OSM to reference the following:

OMP 1-14 (Notifications)

Emergency Plan

__ STA 4.3 Verify a power transient 5% has occurred.

RNO: GO TO Step 4.5.

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

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

OAC alarm video

OAC display points

Control Board indications

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

Section Failure 4A RCS Temperature AP/1/A/1700/028, Section 4A, RCS Temperature Failure NOTE

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

Unit to TRACK due to Rx Cross Limits

Control Rod insertion

Feedwater flow increase

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

Unit to TRACK due to Rx Cross Limits

Control Rod withdrawal

Feedwater flow decrease

Feedwater re-ratio This event is complete when the CRS reaches step 6 (WHEN) in AP/28 Section 4A, or as directed by the Lead Examiner.

Page 12 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 3 Page 3 of 3 Event

Description:

Loop B Tc Fails low (I: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/028 SRO/OATC Crew Response:

1. Ensure the following in HAND:

__ 1A FDW MASTER

__ 1B FDW MASTER

2. Ensure DIAMOND in MANUAL.

3. Notify SPOC to perform the following:

__ Select a valid RCS Tave and Delta Tc input to ICS per AM/1/A/0326/020 (Control of Unit 1 Star Module Signal Selection Function).

__ Investigate and repair the failed RCS temperature instrumentation.

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

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

RNO: Initiate a Surveillance Evaluation in accordance with PT/1/A/0600/001 (Periodic Instrument Surveillance) and OP/1/A/1105/014 (Control Room Instrumentation Operation And Information).

6. WHEN notified by SPOC that a valid RCS Tave and Delta Tc input have been restored to ICS, THEN GO TO OP/1/A/1102/004 A Encl (Placing ICS Stations To Auto).

This event is complete when the CRS reaches step 6 (WHEN) in AP/28 Section 4A, or as directed by the Lead Examiner.

Page 13 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 4 Page 1 of 7 Event

Description:

Group 1 Rod 6 Control Rod drops requiring Manual power reduction (C: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/001 Plant Response:

Group 1 Rod 6 drops into the core

Statalarm 1SA-2/A-10 (CRD GLOBAL SYSTEM FAULT)

Statalarm 1SA-2/B-10 (CRD ASYMMETRIC ROD POSITION ERROR)

Statalarm 1SA-2/D-9 (CRD OUT INHIBIT)

Statalarm 1SA-4/C-1 (QUADRANT POWER TILT) (in at 2 minutes)

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

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

Crew Response:

SRO/OATC Crew should perform Plant Transient Response (PTR) and determine that no manual FDW adjustments are required and that a runback condition exists but due to ICS being in manual it is not occurring.

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

The BOP reports expected AUTO Runback did not occur, and monitors RCS pressure and inventory and inserts Control Rods as needed.

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

SRO should enter AP/1/A/1700/001 (Unit Runback)

AP/1/A/1700/001 Rev 15 4.1 GO TO the most limiting section per the following table:

Section Runback 4H Asymmetric Control Rod (1%/min to 55%power)

AP/1/A/1700/001 Section 4H

1. IAAT a more limiting runback occurs, THEN GO TO Subsequent Actions Step 4.1.

2. IAAT more than one control rod is dropped or misaligned 6.5% (9) from the group average, THEN trip the Rx.

This event is complete when Rx Power has decreased to < 55%, or as directed by the lead examiner.

Page 14 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 4 Page 2 of 7 Event

Description:

Group 1 Rod 6 Control Rod drops requiring Manual power reduction (C: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/001 NOTE SRO/OATC NIs should NOT be calibrated per guidelines contained in OP/1/A/1102/004 (Operation at Power) due to actual power re-distribution within the core as a result of a dropped/misaligned rod.

3. Verify Rx is critical.

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

5. Verify Rx runback to 55% core thermal power in progress.

CTPD set at 55%

ASYMETRIC RODS Runback Light lit

CTP Demand decreasing

Reactor power will decrease when the runback catches up with the initial power decrease from the dropped rod.

RNO: 1. Initiate power reduction to 55% core thermal power at 1%/min.

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

A. Trip reactor.

B. GO TO Unit 1 EOP.

6. Initiate Encl 5.1 (Control of Plant Equipment During Shutdown). (Page 19)

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

7. Notify SPOC to perform the following:

__ Investigate cause of dropped or misaligned control rod.

__ Prepare to reduce the following trip setpoints:

RPS Flux/Flow-Imbalance

RPS High Flux This event is complete when Rx Power has decreased to < 55%, or as directed by the lead examiner.

Page 15 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 4 Page 3 of 7 Event

Description:

Group 1 Rod 6 Control Rod drops requiring Manual power reduction (C: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/001 Crew Response:

SRO/OATC

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

__ TS 3.1.4 (Control Rod Group Alignment Limits)

__ TS 3.1.5 (Safety Rod Position Limits)

__ TS 3.2.3 (Quadrant Power Tilt)

Booth Cue: When SM is contacted, inform the team that the SM is occupied on Unit 3 and cannot verify TS requirements at this time.

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

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

Examiner Note: Shutdown Margin will be adequate

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

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

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

RCPs Maximum NI Power (% FP) 3 40 4 55 THEN reduce power until all NIs are the Maximum NI Power limit for the operating RCP combination per Encl 5.4 (Power Reduction).

This event is complete when Rx Power has decreased to < 55%, or as directed by the lead examiner.

Page 16 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 4 Page 4 of 7 Event

Description:

Group 1 Rod 6 Control Rod drops requiring Manual power reduction (C: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/001 Crew Response:

SRO/OATC

13. WHEN all NIs are < the Maximum NI Power limit for the operating RCP combination, THEN notify SPOC to reduce RPS trip setpoints per AM/1/A/0315/017 (TXS RPS Channel A, B, C, And D Parameter Changes For Abnormal/Normal Operating Conditions.)

NOTE Due to the power decrease initiated in this AP, the current plant configuration must be compared to the normal plant configuration in OP/1/A/1102/004 (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.

14. Initiate OP/1/A/1102/004 (Operation at Power) power reduction enclosure.

NOTE The following will prevent a potential MODE change from MODE 2 to MODE 1 if unit power stabilizes < 5%.

15. IAAT reactor power is 5%, THEN GO TO the following as necessary to shutdown the reactor prior to rod recovery.

OP/1/A/1102/10 (Controlling Procedure for Unit Shutdown)

OP/1/A/1102/004 (Operation at Power)

16. IAAT another runback has or should have occurred, THEN GO TO Subsequent Actions.

17. WHEN the control rod is repaired, THEN perform the following:

A. __ Notify Duty Reactor Engineer for any necessary maneuvering limits.

B. __ GO TO OP/1/A/1105/019 (Control Rod Drive System) to recover the control rod.

This event is complete when Rx Power has decreased to < 55%, or as directed by the lead examiner.

Page 17 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 4 Page 5 of 7 Event

Description:

Group 1 Rod 6 Control Rod drops requiring Manual power reduction (C: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/001 Crew Response:

SRO TS 3.1.4 CONTROL ROD GROUP ALIGNMENT LIMITS Condition A (1hour) Restore control rod alignment or verify SDM

( 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) Reduce Thermal Power to < 60% of allowable Thermal Power.

(10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months ) RPS trip setpoints must be reduced based on flux and flux/flow imbalance to < 65.5% of the allowable thermal power.

TS 3.1.5 SAFETY ROD POSITION LIMITS Condition A (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ) Verify SDM and declare associated control rod INOPERABLE.

TS 3.2.3 QUADRANT POWER TILT Condition A if QPT is greater than the steady state limit (+3.5) and less than or equal to the transient limit (+7.11)

(10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months ) RPS trip setpoints must be reduced > 2% RTP for each 1% of QPT greater than the steady state limit (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) QPT restored to less than or equal to the steady state limit Condition B Possible - QPT greater than the transient limit (+7.11) and less than or equal to the maximum limit (+16.55) due to misalignment of a Control Rod or an APSR (30 minutes) Reduce Thermal Power > 2% RTP from Allowable Thermal Power for each 1% of QPT greater than the steady state limit.

(2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) Restore QPT to less than or equal to the transient limit.

TS 3.10.1 STANDBY SHUTDOWN FACILITY (SSF)

Conditions A-E (7 days) Restore to operable status Once Reactor Power is reduced to below 85% the SSF must be declared inoperable and therefore Tech Spec 3.10.1 applies. Conditions A-E should be entered.

Examiner Note: SDM will be verified using PT/1/A/1103/015, Encl 13.18 (Page 36) and Curve for Control Rod Position Setpoints, 1 Inoperable Rod, 4 Pump Flow, BOC to EOC from the COLR (Page 37).

This event is complete when Rx Power has decreased to < 55%, or as directed by the lead examiner.

Page 18 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 4 Page 6 of 7 Event

Description:

Group 1 Rod 6 Control Rod drops requiring Manual power reduction (C: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/001 AP/1/A/1700/001 Enclosure 5.1 SRO/OATC BOP 1. IAAT SRO determines all appropriate actions have been taken, AND the runback is complete, THEN EXIT this Enclosure.

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

3. Start the following pumps:

__ 1A FDWP SEAL INJECTION PUMP

__ 1A FDWP AUXILIARY OIL PUMP

__ 1B FDWP AUXILIARY OIL PUMP

__ 1B FDWP SEAL INJECTION PUMP

4. WHEN CTP < 80%, THEN stop the following pumps: {3} {4}

__ 1E1 HTR DRN PUMP

__ 1E2 HTR DRN PUMP

5. WHEN CTP 65%, THEN continue this Enclosure.

6. Place the following in MANUAL and close:

__ 1FDW-65 NOTE:

1B FDWP is the preferred pump to shut down first.

7. Verify both Main FDWPs operating.

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

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

10. GO TO Step 12.

This event is complete when Rx Power has decreased to < 55%, or as directed by the lead examiner.

Page 19 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 4 Page 7 of 7 Event

Description:

Group 1 Rod 6 Control Rod drops requiring Manual power reduction (C: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/001 Crew Response:

SRO/OATC

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

BOP __ 1B Main FDW pump is first pump to be shut down

__ Any of the following alarms occur:

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

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

THEN trip 1B Main FDW Pump.

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

__ 1A Main FDW pump is first pump to be shut down

__ Any of the following alarms occur:

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

1SA-16/A-2 (FWP A FLOW BELOW MIN),

THEN trip 1A Main FDW Pump.

14. IAAT the operating FDWP suction flow < 1.5 x 106 lb/hr, THEN slowly throttle the associated recirc control valve to establish 2300 - 6000 gpm total Condensate flow:

1FDW-53

1FDW-65

15. Maintain Pzr level between 220 - 250.

16. IAAT load is 550 MWe, THEN perform Steps 17 - 18.

17. Stop the following: {3}

__ 1A MSRH DRN PUMP

__ 1B MSRH DRN PUMP

18. Place the following in DUMP: {3}

__ 1HD-37

__ 1HD-52 This event is complete when Rx Power has decreased to < 55%, or as directed by the lead examiner.

Page 20 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 5 Page 1 of 2 Event

Description:

Spray valve fails open (C: BOP, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/044 Plant Response:

RCS pressure decreasing below 2155 psig

1RC-1 Indicates OPEN

1SA-2/D-3, RC PRESS HIGH/LOW Crew Response:

SRO/BOP

BOP should recognize that 1RC-1 is open and push the CLOSE pushbutton (This is an IMA in AP/44)

SRO should direct entry into AP/1/A/1700/044 Abnormal Pressurizer Pressure Control AP/1/A/1700/044 Abnormal Pressurizer Pressure Control Rev 4 IMAs 3.1 IAAT PORV is open, AND RC pressure is < setpoint (2400 psig (HIGH) or 480 psig (LOW)), THEN close 1RC-4.

3.2 IAAT RC pressure < 2155 psig, AND 1RC-1 indicates open, THEN select 1RC-1 to CLOSE. [1RC-1 will NOT close]

3.3 IAAT all the following conditions exist:

__ RC pressure < 2155 psig

__ RC pressure decreasing without a corresponding decrease in PZR Level THEN close 1RC-3.

CT-1 Subsequent Actions 4.1 Announce AP entry using the PA system.

4.2 GO TO the applicable step per the following table:

Failure Caused RCS Pressure Step Decrease 4.3 Increase 4.18 Examiner Note: TS 3.4.1 may apply depending on crew response to the failure.

TS 3.4.1, REACTOR COOLANT SYSTEM Condition A (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) Restore RCS DNB parameter(s) to within limit.

COLR DNB Limit = 2125 psig This event is complete when the BOP closes 1RC-3 and stabilizes RCS pressure, or as directed by the Lead Examiner.

Page 21 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 5 Page 2 of 2 Event

Description:

Spray valve fails open (C: BOP, SRO)

Time Position Applicant's Actions or Behavior Crew Response: AP/1/A/1700/044 4.3 Verify 1RC-4 is closed.

SRO/BOP RNO: IF PORV is open, AND 1RC-4 has failed to close, THEN perform the following:

A. __ Dispatch an operator to open 1DIB Panelboard breaker

24.

B. __ Manually trip the reactor.

C. __ Initiate AP/02 (Excessive RCS Leakage).

4.4 Verify 1RC-3 is closed.

NOTE 1RC-3 must NOT be allowed to be closed for 36 minutes at a time to avoid a thermal transient in piping between 1RC-3 and the PZR spray nozzle.

4.5 Position 1RC-3 as required to maintain RC pressure within desired band.

4.6 GO TO Step 4.13.

4.13 Verify PZR heaters maintaining RCS pressure within desired band.

4.14 Notify SPOC to repair malfunctioning component.

4.15 Ensure requirements of following are met:

__ TS 3.4.1 (RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling Limits)

__ TS 3.4.9 (Pressurizer)

__ TS 3.4.12 (Low Temperature Overpressure Protection System)

__ SLC 16.5.1 (Reactor Coolant System Vents) 4.16 WHEN repairs complete, THEN place following components in desired position for current plant conditions as determined by CR SRO:

__ 1RC-1

__ 1RC-3

__ 1RC-4

__ PZR heater bank #1

__ PZR heater bank #2

__ PZR heater bank #3

__ PZR heater bank #4 4.17 __ WHEN directed by CR SRO, THEN EXIT this procedure.

This event is complete when the BOP closes 1RC-3 and stabilizes RCS pressure, or as directed by the Lead Examiner.

Page 22 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 6 Page 1 of 1 Event

Description:

Lowering EHC pressure, Standby EHC pump fails to start (C: BOP,SRO)

Time Position Applicant's Actions or Behavior 1SA-3/E-2 Plant Response:

1SA-3/E-2 EHC Hydraulic Header Pressure Low SRO/BOP Crew Response:

SRO will direct the BOP to refer to the ARG:

1SA-3/E-2 NOTE: Standby pump starts at 1350 psig decreasing.

3.1 Verify standby pump is running.

Examiner Note: Per AD-OP-ALL-1000, Conduct of Operations, Section 5.17.2 Expectations: Written procedures are not necessary for situations where: (3) Conditions exist which may require timely actions due to failure of automatic control systems.

In this situation, the standby EHC pump should be started in order to prevent an automatic Turbine/Reactor trip due to low EHC pressure.

This event is complete when the STBY EHC pump is started, or when directed by the lead examiner.

Page 23 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 1 of 12 Event

Description:

LOHT (CBPs trip) (M: All)

Time Position Applicant's Actions or Behavior Plant Response:

Both MFWPs trip

Reactor Trips

MD EFDWPs do NOT start SRO

TD EFDWP overspeeds and trips Crew Response:

SRO directs the OATC to perform IMAs and the BOP to perform a Symptom Check

If the RCS saturates, the crew will perform Rule 2 (Loss of SCM)

(Page 28)

IMAs OATC EOP Immediate Actions Rev 40 3.1 Depress REACTOR TRIP pushbutton.

3.2 Verify reactor power < 5% FP and decreasing.

3.3 Depress the turbine TRIP pushbutton 3.4 Verify all turbine stop valves closed.

3.5 Verify RCP seal injection available.

SYMPTOM CHECK BOP The BOP will verify the following:

Power Range NIs NOT < 5% Rule 1, ATWS/Unanticipated Nuclear Power Range NIs NOT decreasing Power Production Any SCM < 0°F Rule 2, Loss Of SCM Loss of Main and Emergency FDW Rule 3, Loss of Main or Emerg FDW (including unsuccessful manual initiation Rule 4, Initiation of HPI Forced Cooling of EFDW) (Inability to feed SGs and > 2300 psig, NDT limit reached, or PZR level > 375")

Uncontrolled Main steam line(s) Rule 5, Main Steam Line Break pressure decrease CSAE Offgas alarms None (SGTR Tab is entered when Process monitor alarms (RIA-40, identified SG Tube Leakage > 25 gpm) 59,60),

Area monitor alarms (RIA-16/17)

BOP will perform Rule 3 due to a loss of ALL feedwater: (Page 26)

SRO will review IMAs and transfer to the Subsequent Actions Tab.

This event is complete as directed by the Lead Examiner.

Page 24 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 2 of 12 Event

Description:

LOHT (CBPs trip) (M: All)

Time Position Applicant's Actions or Behavior SUBSEQUENT ACTIONS TAB Crew Response:

The SRO will transfer to the Subsequent Actions tab of the EOP and SRO/OATC review the Parallel Action (Yellow) page.(Page 47)

The SRO will transfer to the Loss of Heat Transfer (LOHT) tab due to the loss of Main and Emergency feedwater.

LOHT TAB

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

NOTE Transfer to LOSCM tab is NOT required if RCS heats to the point where core SCM = 0°F.

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/PSW),

AND any of the following exists:

__ RCS pressure reaches 2300 psig OR NDT limit

__ Pzr level reaches 375 [340 acc]

THEN GO TO Step 4.

RNO:

NOTE 1A1 RCP provides the best Pzr spray.

1. Reduce operating RCPs to one pump/loop.

2. WHEN any exists:

__ EFDW or PSW SG feed 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 Encl 5.27 (Alternate Methods for Controlling EFDW Flow) reports EFDW available THEN GO TO Step 50.

Examiner Note: The SRO will remain at this point of the procedure until RCS pressure = 2300 psig at which time IAAT step 3 will apply which will direct the SRO to GO TO step 4 (Page 30).

This event is complete when the SRO has transferred to the HPI CD tab, or as directed by the Lead Examiner.

Page 25 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 3 of 12 Event

Description:

LOHT (CBPs trip) (M: All)

Time Position Applicant's Actions or Behavior Rule 3 Crew Response

1. Verify loss of MFDW and/or EFDW was due to any of the following:

__ Turbine Building Flooding

__ Actions taken to increase SG level due to Turbine Building Flooding RNO: GO TO Step 3.

3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency/PSW),

AND any of the following exist:

__ RCS pressure reaches 2300 psig OR NDT limit

__ Pzr level reaches 375 [340 acc]

CT-2 THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).(Page 34)

Booth Cue: Record time when criteria for Rule 4 is met ________

Booth Cue: Record time when Rule 4 is initiated ________

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

5. Verify any EFDW pump operating. [No EFDW pumps will be operating]

RNO: GO TO Step 7.

7. Place in MANUAL and close:

__ 1FDW-315

__ 1FDW-316

8. Verify both:

__ Any CBP operating [None will be operating]

__ TBVs available on an intact SG RNO: GO TO Step 16

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

RNO: __ GO TO Step 18.

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

19. Dispatch an operator to open:

__ 2FDW-313 (2A EFDW Line Disch To 2A S/G X-Conn)

__ 2FDW-314 (2B EFDW Line Disch To 2B S/G X-Conn)

This event is complete when the SRO has transferred to the HPI CD tab, or as directed by the Lead Examiner.

Page 26 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 4 of 12 Event

Description:

LOHT (CBPs trip) (M: All)

Time Position Applicant's Actions or Behavior Rule 3 Crew Response:

20. Dispatch an operator to 1FDW-313 and have them notify the CR when BOP in position.

21. Notify alternate unit to:

A. __ Place both EFDW control valves in manual and closed.

B. __ Start their TD EFDW PUMP.

22. IAAT SGs are NOT being fed from any source, AND PSW SG feed available, THEN establish SG feed from PSW using Encl 5.45 (PSW Feed and RCP Seals).

23. WHEN either exists:

__ Operator is in position at 1FDW-313

__ Unit 1 TD EFDW PUMP has been manually started THEN continue.

Examiner Note:

EFW from another source will NOT be made available. Rule 3 progress will stop at this point.

This event is complete when the SRO has transferred to the HPI CD tab, or as directed by the Lead Examiner.

Page 27 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 5 of 12 Event

Description:

LOHT (CBPs trip) (M: All)

Time Position Applicant's Actions or Behavior Rule 2 Crew Response:

1. IAAT all exist:

OATC/BOP

__ Any SCM 0°F

__ Rx power 1%

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

2. Stop all RCPs

3. Notify CRS of RCP status

4. Verify Blackout exists RNO: GO TO Step 6

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

7. Start all available HPI pumps

8. GO TO Step 13

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

14. Verify at least two HPI pumps are operating using two diverse indications RNO: GO TO Step 27

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

28. Verify RCS pressure > 550 psig

29. IAAT either exists:

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

__ Only one LPI header in operation with header flow 2900 gpm THEN GO TO Step 34 This event is complete when the SRO transfers to the HPI CD tab, or as directed by the Lead Examiner.

Page 28 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 6 of 12 Event

Description:

LOHT (CBPs trip) (M: All)

Time Position Applicant's Actions or Behavior Rule 2

30. Dispatch two operators to perform Encl 5.24 (Operation of ADVs) (PS)

OATC/BOP

31. Verify 1SA-2/C-8 (AFIS HEADER A INITIATED) lit RNO: Select OFF for both digital channels on AFIS HEADER A

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

33. Notify CRS:

__ Suspend Rule 3 (Loss of Main or Emergency FDW) until directed by LOSCM tab

__ Degraded HPI exists

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

Page 29 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 7 of 12 Event

Description:

LOHT (CBPs trip) (M: All)

Time Position Applicant's Actions or Behavior LOHT TAB Crew Response:

Examiner Note: When the criteria for IAAT step 3 is met, the SRO will SRO/OATC proceed to step 4:

BOP NOTE SCM may be lost when the PORV is opened. Transition to LOSCM tab is NOT required.

4. PERFORM Rule 4 (Initiation of HPI Forced Cooling). (Page 34)

CT-2

5. Verify all:

__ At least two HPI pumps operating [ONE HPI pump operating]

__ Acceptable HPI flow exists in both HPI headers per Rule 4 (Initiation of HPI Forced Cooling)

__ PORV open

__ 1RC-4 open RNO: 1. IF any HPI pump is providing injection flow, THEN GO TO Step 7.

2. GO TO Step 12.

7. Verify SSF-ASW available.

8. Dispatch a licensed operator to perform Encl 5.34 (Aligning SSF-ASW for SG Feed).

Examiner Note: Stop the RO from leaving the Control Room and notify him/her that Unit 2 will perform Encl 5.34.

9. Verify PSW supplying power to reactor vessel head and RCS loop vents.

RNO: Locally close (Unit 1 Cable Rm):

__ 1SKJ-08 (1RC-155/1RC-156)

__ 1SKK-08 (1RC-157/1RC-158)

__ 1SKL-08 (1RC-159/1RC-160)

Examiner Note: After being notified as an AO to close breakers for 1RC-155 through 1RC-160, wait one minute and Fire Timer 15 to close the breakers and then notify the control room that the breakers are closed.

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

Page 30 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 8 of 12 Event

Description:

LOHT (CBPs trip) (M: All)

Time Position Applicant's Actions or Behavior LOHT TAB Crew Response:

10. Open:

SRO/OATC

__ 1RC-155 BOP __ 1RC-156 CT-3 __ 1RC-157

__ 1RC-158

__ 1RC-159

__ 1RC-160

11. GO TO HPI CD tab.

HPI CD TAB HPI Cooldown Tab

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

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 all of the following exist:

__ PORV open

__ 1RC-4 open

__ Two HPI trains injecting

__ CETCs < 640°F RNO: 1.__ IF RCS vents (hot leg and vessel head) are open, THEN GO TO Step 4.

4. Perform the following:

__ Ensure all RBCUs in low speed.

__ Open 1LPSW-18.

__ Open 1LPSW-21.

__ Open 1LPSW-24.

5. __ Initiate Encl 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 31 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 9 of 12 Event

Description:

LOHT (CBPs trip) (M: All)

Time Position Applicant's Actions or Behavior HPI CD TAB Crew Response:

6. IAAT all the following exist:

SRO/OATC

__ Any RBS pump operating BOP __ RB pressure < 3 psig

__ < 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months into event

__ Reactor Engineering confirms Condition Zero or Condition One per RP/0/B/1000/018 (Core Damage Assessment)

THEN stop all RBS pumps.

7. Start:

__ A Outside Air Booster Fan

__ B Outside Air Booster Fan

8. Notify Unit 3 to start:

__ 3A Outside Air Booster Fan

__ 3B Outside Air Booster Fan

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

RNO: __ Select OFF for both digital channels on AFIS HEADER A.

10. Verify 1SA-2/D-8 (AFIS HEADER B INITIATED) lit.

RNO: __ Select OFF for both digital channels on AFIS HEADER B.

11. Verify indications of SGTR > 25 gpm.

RNO: GO TO Step 17.

17. IAAT any SG with a tube rupture that has NOT reached the level at which water enters the steam lines (per Encl 5.21 (Full Range SG Level For Water In Steam Lines)) approaches either of the following:

__ 1000 psig

__ Overfill:

Any SCM < 0°F: Loss of SCM setpoint

All SCMs > 0°F: 285 [315 acc] XSUR THEN perform Steps 18 - 20.

RNO: GO TO Step 21.

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

Page 32 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 10 of 12 Event

Description:

LOHT (CBPs trip) (M: All)

Time Position Applicant's Actions or Behavior HPI CD TAB Crew Response:

21. IAAT RCS pressure is > 1000 psig, AND any of the following exist:

SRO/OATC

__ A SG with a tube rupture is at the level at which water enters the BOP steam lines (per Encl 5.21 (Full Range SG Level For Water In Steam Lines)

__ A SG with a tube rupture approaches 1000 psig THEN open:

__ 1RC-155

__ 1RC-156

__ 1RC-157

__ 1RC-158

__ 1RC-159

__ 1RC-160

22. Secure makeup to the LDST.

23. Notify Chemistry of the following:

A. __Sample RCS boron hourly, or as often as possible, until MODE 5.

B. __Letdown status.

24. IAAT Chemistry reports that boron sample CANNOT be obtained, THEN notify TSC to provide guidance to obtain boron sample.

25. Initiate determination of minimum required boron concentration for MODE 5 using either of the following:

__ Reactor Engineer

__ PT/1/A/1103/015 (Reactivity Balance Procedure)

26. IAAT required boron concentration for MODE 5 is determined, THEN initiate Encl 5.11 (RCS Boration).

NOTE Encl 5.12 (ECCS Suction Swap to RBES) requests an LPI discharge sample which is representative of RBES boron after ECCS suction has been swapped to RBES.

27. IAAT ECCS suction is swapped to RBES, AND RBES boron is decreasing, THEN notify TSC.

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

Page 33 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 11 of 12 Event

Description:

LOHT (CBPs trip) (M: All)

Time Position Applicant's Actions or Behavior Rule 4 SRO/OATC Crew Response:

BOP Rule 4 HPI Forced Cooling

1. Verify any HPI pump powered from 1TC, 1TD, or 1TE can be operated.

2. Open:

__ 1HP-24

__ 1HP-25

3. Start all available HPI pumps. [C HPI Pump will NOT start]

4. Open:

__ 1HP-26

__ 1HP-27

5. Open 1RC-4.

6. Verify flow exists in any HPI header.

7. Perform the following:

A. __ Place 1RC-66 SETPOINT SELECTOR to OPEN.

B. __ Depress 1RC-66 OPEN PERMIT pushbutton.

8. Verify at least two HPI pumps operating.

RNO: 1. __ IF NO HPI pumps are operating, THEN:

A. __ Stop all RCPs.

B. __ Position 1RC-66 SETPOINT SELECTOR to HIGH.

C. __ GO TO Step 14.

2. __ IF 1HP-26 is closed, AND either of the following exists:

__ 1A HPI PUMP operating

__ 1B HPI PUMP operating THEN open 1HP-410.

3. __ GO TO Step 10.

10. Verify flow exists in any HPI header.

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

Page 34 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 1 Event No.: 7 Page 12 of 12 Event

Description:

LOHT (CBPs trip) (M: All)

Time Position Applicant's Actions or Behavior Rule 4 Crew Response:

SRO/OATC BOP 11. Perform the following:

A. __ Place 1RC-66 SETPOINT SELECTOR to OPEN.

B. __ Depress 1RC-66 OPEN PERMIT pushbutton.

12. Verify > one RCP operating.

NOTE 1A1 RCP provides the best Pzr spray and is preferred to be left running in case recovery from HPI forced cooling is performed and a Pzr bubble drawn.

13. Stop all but one RCP.

14. IAAT the following limits are exceeded, Pump Operation Limit 1 HPI pump/hdr 475 gpm (incl. seal injection for A hdr) 1A & 1B HPI pumps Total flow of 950 gpm operating with 1HP-409 (incl. seal injection) open THEN throttle HPI to maximize flow < flow limit.

15. De-energize all Pzr heaters.

16. Close 1HP-5.

17. Close:

__ TBVs

__ 1FDW-35

__ 1FDW-44

18. IAAT all HPI is lost, THEN:

A. __ Stop all RCPs.

B. __ Position 1RC-66 SETPOINT SELECTOR to HIGH.

19. __ WHEN directed by CRS, THEN EXIT.

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

Page 35 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 13.18 Rev 37 PT/1/A/1103/015 Shutdown margin Calculation at Power Page 1 of 1 Performed By: __________Date: ________ Time: __________

1. Purpose 1.1 The purpose of this enclosure is to perform a shutdown margin calculation while at power.

2. Procedure NOTE: Step 2.1 applies only to control rod Groups 1 through 6. Group 7 and the APSRs may be positioned as required.

____2.1 IF any rod groups are NOT at 100% wd (other than Group 7 and the APSRs) due to CRD movement PT:

____2.1.1 Verify that only one group is NOT at 100% wd.

____2.1.2 Verify that the inserted group is 95% wd.

NOTE: For a dropped rod/stuck rod scenario, utilize the 1 inoperable rod graphs in the COLR.

The rod position used should be the position of the controlling group (if the dropped/stuck rod is in the controlling group, the rod positions of the remaining rods in that group should be used, NOT the group average).

____2.2 Verify one of the following:

____ ____ 2.2.1 Available shutdown margin is > 1.00% /K. This is shown by verifying that IV the control rod position and power level are within the Acceptable Region or the Restricted Region on the appropriate curve for the number of RC Pumps and Inoperable rods in the COLR.

OR

____ ____2.2.2 Appropriate actions are taken per TS 3.1.4, 3.1.5, and 3.2.1.

IV Page 36 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Page 37 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Rule 6 HPI HPI Pump Throttling Limits

HPI must be throttled to prevent violating the RV-P/T limit.

HPI pump operation must be limited to two HPIPs when only one BWST suction valve (1HP-24 or 1HP-25) is open.

HPI must be throttled 475 gpm/pump (including seal injection for A header) when only one HPI pump is operating in a header.

Total HPI flow must be throttled 950 gpm including seal injection when 1A and 1B HPI pumps are operating with 1HP-409 open.

Total HPI flow must be throttled < 750 gpm when all the following exist:

- LPI suction is from the RBES

- piggyback is aligned

- either of the following exist:

only one piggyback valve is open (1LP-15 or 1LP-16)

only one LPI pump operating

HPI may be throttled under the following conditions:

HPI Forced Cooling in Progress: HPI Forced Cooling NOT in Progress:

All the following conditions must exist: All the following conditions must exist:

Core SCM > 0

All WR NIs 1%

CETCs decreasing

Core SCM > 0

Pzr level increasing

SRO concurrence required if throttling following emergency boration HPI Pump Minimum Flow Limit

Maintain 170 gpm indicated/pump. This is an instrument error adjusted value that ensures a real value of 65 gpm/pump is maintained. HPI pump flow less than minimum is allowed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Page 38 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control 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 IF 1HP-26 will NOT open, maintain desired Pzr level: THEN throttle 1HP-410 to maintain

1A HPI Pump desired Pzr level.

1B HPI 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 1A BHUT, THEN perform the following:

A. Open:

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

C. Notify SRO.

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

Page 39 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control 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 1B LPI PUMP.

C. Open:

1LP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D. IF two LPI Pumps are running only 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, U1 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 1B 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 40 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

8. Start 1C HPI PUMP. IF at least two HPI pumps are operating, THEN throttle 1HP-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 1HP-26 will NOT open, 1HP-26 THEN throttle 1HP-410 to maintain desired Pzr level.

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

Page 41 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED 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 1HP-24. (1HP-24 and 1HP-25) are closed, THEN perform the following:

Open 1HP-25.

Close 1HP-16. A. Start 1A LPI PUMP.

B. Start 1B LPI PUMP.

C. Open:

1LP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D. IF two LPI Pumps are running only 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, U1 LPI Hatch Rm, N end).

F. GO TO Step 13.

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

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

12.__ Operate Pzr heaters as required to maintain heater bundle integrity.

Page 42 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

13. 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-1-107, Unit 1 RC Bleed Transfer Pump Rm.).

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

Open 1HP-17.

Open 1HP-18

15. IAAT all of the following exist: GO TO Step 35.

Letdown isolated LPSW available Letdown restoration desired THEN perform Steps 16 - 34. {41}

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

2. GO TO Step 35.

17. Ensure only one CC pump running.

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

19. Verify both are open: 1. IF 1HP-1 is closed due to 1HP-3 failing to 1HP-1 close, 1HP-2 THEN GO TO Step 21.

2. IF 1HP-2 is closed due to 1HP-4 failing to close, THEN GO TO Step 21.

20. GO TO Step 23.

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

21. Verify letdown line leak in East GO TO Step 23.

Penetration Room has occurred.

22. GO TO Step 35.

Page 43 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

23. Monitor for unexpected conditions while restoring letdown.

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

1HP-1 1HP-3

2. IF 1B letdown cooler is to be placed in service, THEN open:

1HP-2 1HP-4

3. GO TO Step 26.

25. Open:

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

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

aligned.

A. Notify CR SRO of problem.

B. GO TO Step 35.

27. Close 1HP-6.

28. Close 1HP-7.

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

2. Close:

1HP-8 1HP-9&11

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

A. Select 1HP-14 to NORMAL.

B. Close 1HP-16.

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

Page 44 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

30. Open 1HP-5.

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

32. WHEN letdown temperature is

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

33. Open 1HP-6.

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

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

35. 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).

36. 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.

37. 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 45 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

38. Verify 1CS-48 (1A BHUT Recirc) has GO TO Step 40.

been closed to provide additional makeup flow to LDST.

39. 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 1CS-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.

40. Verify two Letdown Filters in service, GO TO Step 42.

AND only one Letdown filter is desired.

41. Perform one of the following:

Place 1HP-17 switch to CLOSE.

Place 1HP-18 switch to CLOSE.

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

Page 46 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Subsequent Actions EP/1/A/1800/001 Parallel Actions Page 1 of 1 CONDITION ACTIONS

1. PR NIs 5% FP OR GO TO UNPP tab. UNPP NIs NOT decreasing

2. All 4160V SWGR de-energized GO TO Blackout tab. BLACKOUT

{13}

3. Core SCM indicates superheat GO TO ICC tab. ICC

4. Any SCM = 0°F GO TO LOSCM tab. LOSCM

5. Both SGs intentionally isolated to GO TO EHT tab.

stop excessive heat transfer

6. Loss of heat transfer (including LOHT loss of all Main and Emergency GO TO LOHT tab.

FDW)

7. Heat transfer is or has been GO TO EHT tab. EHT excessive

8. Indications of SGTR 25 gpm GO TO SGTR tab. SGTR

9. Turbine Building flooding NOT GO TO TBF tab. TBF caused by rainfall event

10. Inadvertent ES actuation occurred Initiate AP/1/A/1700/042 (Inadvertent ES ES Actuation).

11. Valid ES actuation has occurred Initiate Encl 5.1 (ES Actuation). ES or should have occurred

12. Power lost to all 4160V SWGR

Initiate AP/11 (Recovery from Loss and any 4160V SWGR of Power).

re-energized ROP

IF Encl 5.1 (ES Actuation) has been initiated, THEN reinitiate Encl 5.1.

13. RCS leakage > 160 gpm with Notify plant staff that Emergency Dose EDL letdown isolated Limits are in affect using PA system.

14. Individual available to make

Announce plant conditions using notifications PA system.

Notify OSM to reference the NOTIFY Emergency Plan and NSD 202 (Reportability).

Page 47 of 49

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam CRITICAL TASKS CT-1 1RC-3 (Spray Block Valve) must be closed before tripping the reactor on low RCS pressure.

CT-2 HPI Forced Cooling must be initiated within 5 minutes of when the initiation criteria has been met (TCA = 5 min).

CT-3 RCS Loop and Head vents must be opened to maximize HPI pump flow due to degraded HPI prior to performing step 4 in the HPI CD tab.

Page 48 of 49

SAFETY: Take a Minute UNIT 0 (OSM)

SSF Operable: Yes KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 2 Fuel Handling: No UNIT STATUS (CR SRO)

Unit 1 Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 100% Mode: 1 Mode: 1 Gross MWE: 895 100% Power 100% Power RCS Leakage: 0.01 gpm EFDW Backup: Yes EFDW Backup: Yes No WCAP Action RBNS Rate: 0.01 gpm Technical Specifications/SLC Items (CR SRO)

Component/Train OOS Restoration TS/SLC #

Date/Time Required Date/Time AMSAC/DSS 0300 7 Days 16.7.2 Shift Turnover Items (CR SRO)

Primary

Due to unanalyzed condition, the SSF should be considered INOP for Unit 1 if power levels are reduced below 85%. Evaluations must be performed prior to declaring the SSF operable following a return to power (after going below 85%).

1RIA-3 and 5 removed from RB.

Control Rod Movement PT (PT/1/A/0600/015 ) is to be performed for GP 1 ONLY.

During the Control Rod Movement PT, Unit 2 CRS will assume the oversight role for Unit 1.

Unit 1 CRS will assume the role of the dedicated Reactivity Management SRO.

Secondary

Feedwater valve DP selected to A1 and B2 for maintenance

AMSAC/DSS bypassed

ICS Diamond and FDW Masters are in HAND for performance of Control Rod Movement PT.

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

Reactivity Management (CR SRO)

Gp 7 Rod Position: Batch additions as required for volume RCS Boron 83 ppmB 92% Withdrawn control.

Human Performance Emphasis (OSM)

Procedure Use and Adherence

Appendix D Scenario Outline Form ES D-1 ILT48 NRC Exam Facility: Oconee Scenario No.: 2 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________SRO

________________________ ________________________OATC

________________________ ________________________BOP Initial Conditions:

Reactor Power = 100%

Turnover:

Feedwater valve DP selected to 1A1 and 1B2 for maintenance

AMSAC/DSS bypassed Event Malfunction Event Event Type* Description No. No.

0a Override EBOP Fails to Auto Start 0b 0c 1 5 Minute Delithiation Using Deborating IX N: OATC, SRO 2 MPS290 C: BOP, SRO (TS) 1C CCW Pump trips 3 MCS004 I: OATC, SRO Controlling NR Tave Fails HIGH (586ºF) 1B Main FDW Pump Active Thrust Bearing C: BOP, R: OATC, 4 Override Temperature HIGH Requiring manual power SRO (TS) reduction and MFW Pump trip Bearing Oil Header Pressure LOW, EBOP fails to 5 Override C: BOP, SRO AUTO Start Turbine Oil Header Pressure low, Manual Turbine MSS010 Trip, ATWS 6 M: ALL Override

1A HPI pump trips, 1B HPI pump fails to AUTO start 7

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Scenario 2 Event Summary Event 1: The OATC will perform a 5 minute delithiation using the deborating IX using OP/1/A/1103/004C Deborating IXs, Encl. 4.4 Unit 1 Deborating IX For RCS De-lith (Rx At Power).

Event 2: CCW pump 1C will trip. The crew should address OAC Alarms and determine that the 1C CCW pump has tripped. The SRO should recognize Tech Spec for LPSW accumulator low level. Vacuum will start to decrease until CCW pump 1D is started.

Event 3: Controlling Tave will fail High causing ICS to insert control rods and increase feedwater flow. The crew should perform Plant Transient Response and take the ICS Diamond and Feedwater Loop Masters to MANUAL and stabilize the plant before the reactor trips.

Event 4: 1B MFWP thrust bearing temperature alarm will come in. Temperature will slowly increase requiring the crew to perform a manual power reduction to secure the 1B MFWP.

Event 5: Turbine oil header pressure will start decreasing causing an alarm. The EBOP will have to be started manually to prevent a turbine trip.

Event 6: Turbine oil header pressure will decrease again requiring a reactor/turbine trip but control rods will not insert automatically or manually from the control room. The 1A HPI pump will trip and the 1B HPI pump will fail to start in AUTO. It can be manually started.

Approximately 4 minutes after an operator is dispatched to open RPS breakers, the reactor will trip.

Page 2 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 1 Page 1 of 6 Event

Description:

5 Minute Delith Using Deborating IX (N: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1103/004C Crew response:

SRO SRO directs the OATC to perform OP/1/A/1103/004C Deborating IXs, Encl. 4.4 Unit 1 Deborating IX For RCS De-lith (Rx At Power).

OP/1/A/1103/004C, Encl. 4.4 Rev 25 OATC NOTE:

This procedure affects reactivity management by placing IX and Letdown Filter in service causing possible RCS boron change. (R.M.)

Unit 1 Deborating IX can affect RCS boron because it contains 1200 gal of borated water. (R.M.)

NOTE:

If IX boron is within acceptable limits, IX may be placed in service with minimal reactivity affects (no CRD movement). (R.M.)

Cation resin is used for de-lith. Cation resin will NOT remove boron from RCS. (R.M.)

2.1 IF RCS < 100 ppm AND IX boron as listed in Demineralizer Log Sheet is more than + 5 ppm of current RCS boron but is within + 25 ppm of current RCS boron, perform the following: {7}: [NA]

2.1.1 Determine RCS boron change resulting from placing IX in service (assume 1200 gal addition at boron listed in Demineralizer Log Sheet).

2.1.2 Determine RCS makeup sources and volumes required to compensate for RCS boron changes per OP/1/A/1103/004 (Soluble Poison Control).

2.1 .3 Go To Step 2.4.

Examiner Note: RCS Boron is 83 ppm.

This event is complete when the de-lith is complete or when directed by the lead examiner.

Page 3 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 1 Page 2 of 6 Event

Description:

5 Minute Delith Using Deborating IX (N: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1103/004C Crew response:

OATC NOTE:

Cation resin is used for de-lith. Cation resin will NOT remove boron from RCS. (R.M.)

If IX boron is within acceptable limits, IX may be placed in service with minimal reactivity affects. (R.M.)

Acceptable 'Demineralizer Log Sheet' boron for placing IX in service without rinsing is determined as follows: (R.M.) {4}

RCS Boron Concentration Acceptable Demin Log Sheet Value

> 100 ppm + 50 ppm of current RCS boron

< 100 ppm +5 ppm of current RCS boron 2.2 IF Unit 1 Deborating IX boron status is NOT acceptable to place in service, perform Enclosure 4.5 (Unit 1 Deborating IX Rinse To MWHUT) until acceptable boron results are achieved. (R.M.). [NA]

2.3 Unit 1 Deborating IX has acceptable boron status to be placed in service.

(R.M.)

NOTE: Placing an idle Letdown Filter in service can affect core reactivity by adding ~ 60 gals of water at a different boron concentration. (R.M.) {5} {6}

2.4 IF two Letdown Filters are available AND NOT already in service, perform the following: (R.M.) {6}

2.4.1 Review Component Boron Log for out-of-service Letdown Filter boron.

2.4.2 Determine RCS boron based on placing second Letdown Filter in service.

2.4.3 RCS boron ___83___ ppm 2.4.4 IF RCS makeup is required to achieve acceptable boron, determine RCS makeup sources and volumes per OP/1/A/1103/004 (Soluble Poison Control). [NA]

This event is complete when the de-lith is complete or when directed by the lead examiner.

Page 4 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 1 Page 3 of 6 Event

Description:

5 Minute Delith Using Deborating IX (N: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1103/004C Crew response:

OATC 2.5 Perform one of the following (for all applicable steps 2.1 through 2.4):

Verify acceptable RCS boron.

Ensure appropriate RCS makeup plans determined to ensure acceptable boron.

2.6 Perform one of the following:

IF two Letdown Filters available, perform the following:

Ensure 1HP-17 (1A LETDOWN FILTER INLET) switch to "OPEN" Ensure 1HP-18 (1B LETDOWN FILTER INLET) switch to "OPEN"

IF only one Letdown Filter available, verify Letdown pressure < 105 psig.

2.7 IF RCS makeup is required to ensure acceptable boron, makeup per OP/1/A/1103/004 (Soluble Poison Control). [NA]

NOTE: Anytime IX is placed in service CRD movement may result. (R.M.)

2.8 WHILE placing Unit 1 Deborating IX in service, monitor the following indications: (R.M.) {20}

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). {17}

2.9.3 Open 1CS-27 (DEBOR IX INLET).

2.9.4 Verify 1HP-15 Controller in "MANUAL".

2.9.5 Ensure open 1HP-16 (LDST MAKEUP ISOLATION).

This event is complete when the de-lith is complete or when directed by the lead examiner.

Page 5 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 1 Page 4 of 6 Event

Description:

5 Minute Delith Using Deborating IX (N: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1103/004C Crew response:

OATC 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 desired by Chemistry AND Unit 1 Deborating IX will be in service for > 20 minutes, notify Chemist to begin flush for sample of Unit 1 Deborating IX effluent. (R.M.)

Person Notified Date 2.12 IF unexpected changes are noted, perform the following: (R.M.)

Continue enclosure to remove Unit 1 Deborating IX from service.

Notify CRS 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).

NOTE: Opening 1CS-26 will remove Unit 1 Deborating IX from 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 required by Chemistry 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.)

Person Notified Date This event is complete when the de-lith is complete or when directed by the lead examiner.

Page 6 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 1 Page 5 of 6 Event

Description:

5 Minute Delith Using Deborating IX (N: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1103/004C Crew response:

OATC 2.16 WHEN desired to remove Unit 1 Deborating IX from service, perform the following:

2.16.1 Position 1HP-14 (LDST BYPASS) to "NORMAL".

2.16.2 Ensure closed 1HP-16 (LDST MAKEUP ISOLATION).

2.16.3 Perform one of the following: (R.M.)

Verify correct IX run time per Step 1.2.

Notify Chemistry for evaluation.

Person Notified Date 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 Narrative Log.

NOTE: 1B Letdown Filter is the preferred filter to leave in service for ALARA.

2.18 IF desired, remove one Letdown Filter from service:

2.18.1 Verify > 10 minutes since normal Letdown alignment. (R.M.) {5}

2.18.2 Perform one of the following:

Position 1HP-17 (1A LETDOWN FILTER INLET) switch to "CLOSE".

Position 1HP-18 (1B LETDOWN FILTER INLET) switch to "CLOSE".

2.18.3 Record RCS boron for out-of-service Letdown Filter in Component Boron Log. (R.M.) {6}

This event is complete when the de-lith is complete or when directed by the lead examiner.

Page 7 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 1 Page 6 of 6 Event

Description:

5 Minute Delith Using Deborating IX (N: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1103/004C Crew response:

OATC 2.19 IF Unit 1 Deborating IX will NOT be used within the next seven days, perform the following: (R.M.)

NOTE: IA supply valves should be closed on idle IX(s) to reduce chance of placing wrong IX in service due to human error. (R.M.) {8}

2.19.1 Close IA-3092 (1CS-27 IA Isolation). (A-2-Rm 214) 2.19.2 Bleed off pressure from operator using petcocks. (A-2-Rm 214)

NOTE: Petcock should be left in the throttled position to ensure pressure does NOT build up over time.

2.19.3 Ensure petcock left in the throttled position.

2.19.4 Place a "T/O SHEET" CR tag on 1CS-27 (DEBOR IX INLET) switch.

2.20 Record in Demineralizer Log Sheet for Unit 1 Deborating IX either of the following: (R.M.)

IF Unit 1 Deborating IX sample was NOT taken, record current RCS boron.

IF Unit 1 Deborating IX sample was taken, record IX effluent.

This event is complete when the de-lith is complete or when directed by the lead examiner.

Page 8 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 2 Page 1 of 2 Event

Description:

CCW pump trip (C, BOP, SRO)(TS)

Time Position Applicant's Actions or Behavior OP/1/A/1104/012 A Plant Response:

OAC Alarms:

LPSW LEAKAGE ACCUMULATOR LEVEL LO LO (< 20 inches)

1C CCW LOCA/LS OFF

ESV Tank Vacuum HI

Condenser Vacuum will start decreasing SRO/BOP Crew Response:

Examiner Note: The OAC LPSW Leakage Accumulator LO LO condition is TS 3.7.7. Condition B entry criteria. This alarm will clear when the D CCW pump is started.

The crew should recognize the need to start the 1D CCW pump and position the LOCA Load Shed select switch to a running CCW pump.

OP/1/A/1104/012 A Rev 18 2.1 Verify seal water aligned to CCW Pump to be started per OP/0/A/1104/052 (SSW System).

NOTE: Do NOT operate CCW Pumps in the same header until adjacent CCW Pump discharge valves have fully repositioned to prevent CCW Pump discharge valve malfunction. {3}

2.2 IF this is the first CCW Pump to be started, verify closed CCW Pump discharge valves on adjacent CCW Pumps.

2.3 Verify closed discharge valve on CCW Pump to be started.

This event is complete when a CCW pump is started in the same header as the CCW pump that tripped and the Tech Spec determination has been made or when directed by the lead examiner.

Page 9 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 2 Page 2 of 2 Event

Description:

CCW pump trip (C, BOP, SRO)(TS)

Position Applicant's Actions or Behavior OP/1/A/1104/012 A Crew Response:

NOTE:

CCW Pump starts when discharge valve 20% open.

ESV Tank low vacuum alarms may occur during CCW Pump start. {1}

SRO/BOP

LPSW Leakage Accumulator level is a function of LPSW System pressure. When CCW Pump status is changed, LPSW Leakage Accumulator level may exceed the limits of SR 3.7.7.1 until LPSW system pressure stabilizes. As a result, momentary entry into TS 3.7.7 Condition 'B' may be necessary.

2.4 Start desired CCW Pump: ____________.

2.5 Verify CCW Pump discharge valve opens.

Examiner Note: CCWP LOAD SHED DEFEAT switch may be positioned per the Alarm Response Guide.

2.6 Ensure CCWP LOAD SHED DEFEAT switch is positioned to a running CCW Pump.

TS 3.7.7 LOW PRESSURE SERVICE WATER (LPSW) SYSTEM Condition B (7 days) Restore the LPSW WPS to OPERABLE status.

This event is complete when a CCW pump is started in the same header as the CCW pump that tripped and the Tech Spec determination has been made or when directed by the lead examiner.

Page 10 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 3 Page 1 of 3 Event

Description:

Controlling NR Tave Fails HIGH (586ºF) (I: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/028 Plant Response:

Controlling NR Tave digital display reads 587.1°F

Controlling Tave Chessell display reads 587.1°F

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

1SA-2/A12 ICS Tracking

1SA-2/C11 ICS Loss of OAC CTP Signal

Control Rods will insert and FDW flow will increase

RCS pressure will decrease Crew Response:

SRO/OATC

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

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

Place the Diamond and both FDW Masters in manual and position as CT-1 necessary to stabilize the plant. (decrease FDW)

Note: The OATC will have to reduce FDW in order to stabilize power below the pre-transient level.

The CRS should:

Refer to AP/28, ICS Instrument Failures Ensure SPOC is contacted to repair the failed instrument.

AP/1/A/1700/028, ICS Instrument Failures Rev 20 4.1 Provide control bands as required. (OMP 1-18 Att. I)

OMP 1-18 Attachment I:

1. Plant Conditions Stable or TPB < Pre-transient Conditions

NI Power + 1% not to exceed the pre-transient or allowable power. If at the pre-transient or allowable level, band is NI Power - 1%.

Current Tave + 2°F.

Current SG Outlet Pressure + 10 PSIG (N/A)

Delta Tc 0 oF + 2°F.

This event is complete when the CRS reaches step 6 (WHEN) in AP/28 Section 4A, or as directed by the Lead Examiner.

Page 11 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 3 Page 2 of 3 Event

Description:

Controlling NR Tave Fails HIGH (586ºF) (I: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/028 Crew Response:

4.2 Initiate notification of the following:

SRO/OATC __ OSM to reference the following:

OMP 1-14 (Notifications)

Emergency Plan

__ STA 4.3 Verify a power transient 5% has occurred.

RNO: GO TO Step 4.5.

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

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

OAC alarm video

OAC display points

Control Board indications

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

Section Failure 4A RCS Temperature AP/1/A/1700/028, Section 4A, RCS Temperature Failure NOTE

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

Unit to TRACK due to Rx Cross Limits

Control Rod insertion

Feedwater flow increase

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

Unit to TRACK due to Rx Cross Limits

Control Rod withdrawal

Feedwater flow decrease

Feedwater re-ratio This event is complete when the CRS reaches step 6 (WHEN) in AP/28 Section 4A, or as directed by the Lead Examiner.

Page 12 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 3 Page 3 of 3 Event

Description:

Controlling NR Tave Fails HIGH (586ºF) (I: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/028 Crew Response:

SRO/OATC

1. Ensure the following in HAND:

__ 1A FDW MASTER

__ 1B FDW MASTER

2. Ensure DIAMOND in MANUAL.

3. Notify SPOC to perform the following:

__ Select a valid RCS Tave and Delta Tc input to ICS per AM/1/A/0326/020 (Control of Unit 1 Star Module Signal Selection Function).

__ Investigate and repair the failed RCS temperature instrumentation.

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

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

RNO: Initiate a Surveillance Evaluation in accordance with PT/1/A/0600/001 (Periodic Instrument Surveillance) and OP/1/A/1105/014 (Control Room Instrumentation Operation And Information).

6. WHEN notified by SPOC that a valid RCS Tave and Delta Tc input have Been restored to ICS, THEN GO TO OP/1/A/1102/004 A Encl (Placing ICS Stations To Auto).

This event is complete when the CRS reaches step 6 (WHEN) in AP/28 Section 4A, or as directed by the Lead Examiner.

Page 13 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 4 Page 1 of 5 Event

Description:

1B Main FDW Pump Active Thrust Bearing Temperature HIGH Requiring manual power reduction and MFW Pump trip (C: BOP, R: OATC, SRO)(TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/029 Plant response:

OAC Alarm O1A0928 FWPT 1B ACTIVE THRUST BEARING TEMP Crew Response:

Refer to OAC Alarm Response for O1A0928 for HI-HI temperature > 200°F HI-HI: 1) If temperature cannot be maintained below HI-HI setpoint, refer to OP/1/A/1106/002 B (FDWPT Operation) to remove FDWP from service

2) Refer to OP/1/A/1102/004 (Operation at Power)

3) Notify Component Engineer Booth cue: If contacted, respond as the Component Engineer and recommend that the 1B FDWPT be removed from service as soon as possible.

SRO/OATC/

BOP Booth cue: If contacted, respond as the SM and recommend reducing power using AP/1/A/1700/029 (Rapid Unit Shutdown) to remove the 1B FDWPT from service as soon as possible Booth cue: If an AO is dispatched, he should report that there is a strong scorching oil smell around the 1B FDWPT and the bearing housing is hot to the touch.

Examiner Note: The SRO will refer to AP/1/A/1700/029 (Rapid Unit Shutdown) to reduce power to below 65% in order to secure the 1B MFW Pump.

Examiner Note: If the power decrease is stopped close to 65%,

Runback alarm may actuate as FDW stabilizes.

The BOP should refer to OP/1/A/1106/002 B (FDWPT Operation)

(Page 18)

AP/1/A/1700/029 (Rapid Unit Shutdown)Rev 13 NOTE The CR SRO should read this procedure and it should NOT be used when EOP entry conditions exist.

4.1 Initiate Encl 5.1 (Support Actions During Rapid Unit Shutdown).

(Page 17)

This event is complete when the BOP secures the 1B MFW Pump, or as directed by the Lead Examiner.

Page 14 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 4 Page 2 of 5 Event

Description:

1B Main FDW Pump Active Thrust Bearing Temperature HIGH Requiring manual power reduction and MFW Pump trip (C: BOP, R: OATC, SRO)(TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/029 Crew Response:

4.2 Announce AP entry using the PA system.

SRO/OATC 4.3 IAAT both of the following apply:

__ It is desired to stop power decrease BOP

__ CTP > 18 %

THEN perform Steps 4.4 - 4.7.

RNO: GO TO Step 4.8.

Examiner Note: Power decrease will be stopped when power is lowered to < 65%.

4.4 Verify ICS in AUTO. [ICS is in MANUAL]

RNO: 1. __ Stop manual power reduction.

2. __ GO TO Step 4.6.

NOTE Due to the power decrease initiated in this AP, the current plant configuration must be compared to the normal plant configuration in OP/1/A/1102/004 (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.

4.6 Initiate OP/1/A/1102/004 (Operation at Power) power reduction enclosure.

4.7 WHEN conditions permit, THEN perform one of the following:

__ Depress MAXIMUM RUNBACK to resume power reduction.

__ GO TO appropriate operating procedure for continued operation.

4.8 Verify ICS in AUTO. [ICS is in MANUAL]

RNO: 1. __ Initiate manual power reduction to desired power level.

2. __ GO TO Step 4.10.

4.10 Verify both Main FDW pumps running.

This event is complete when the BOP secures the 1B MFW Pump, or as directed by the Lead Examiner.

Page 15 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 4 Page 3 of 5 Event

Description:

1B Main FDW Pump Active Thrust Bearing Temperature HIGH Requiring manual power reduction and MFW Pump trip (C: BOP, R: OATC, SRO)(TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/029 Crew Response:

NOTE SRO/OATC

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

To lower 1B Main FDW Pump suction flow, bias is adjusted counter-BOP 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 Suction flow is 1 x 106 lbm/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:

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

__ Any of the following alarms actuate and remain in alarm:

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

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

THEN trip 1B Main FDW Pump.

Examiner Note: SRO may direct a trip of the 1B Main FDW pump to prevent equipment damage and not utilize the OP.

Examiner Note: When < 65% power, IAAT step 4.3 applies which directs the performance of step 4.4-4.7 on the previous page.

TS 3.10.1 STANDBY SHUTDOWN FACILITY (SSF)

Conditions A-E (7 days) Restore to operable status Once Reactor Power is reduced to below 85% the SSF must be declared inoperable and therefore Tech Spec 3.10.1 applies.

Conditions A-E should be entered.

This event is complete when the BOP secures the 1B MFW Pump, or as directed by the Lead Examiner.

Page 16 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 4 Page 4 of 5 Event

Description:

1B Main FDW Pump Active Thrust Bearing Temperature HIGH Requiring manual power reduction and MFW Pump trip (C: BOP, R: OATC, SRO)(TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/029 Crew Response:

Enclosure 5.1, Support Actions During Rapid Unit Shutdown

1. Notify WCC SRO to initiate Encl 5.2 (WCC SRO Support During Rapid SRO/BOP Unit Shutdown).

2. Start the following pumps:

__ 1A FDWP SEAL INJECTION PUMP

__ 1A FDWP AUXILIARY OIL PUMP

__ 1B FDWP AUXILIARY OIL PUMP

__ 1B FDWP SEAL INJECTION PUMP

3. WHEN CTP is 80%, THEN continue.

4. Stop 1E1 HTR DRN PUMP.

5. Place 1HD-254 switch to OPEN.

6. Stop 1E2 HTR DRN PUMP.

7. Place 1HD-276 switch to OPEN.

8. Verify Turbine-Generator shutdown is required.

RNO: GO TO Step 20.

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

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

__ 1FDW-65 This event is complete when the BOP secures the 1B MFW Pump, or as directed by the Lead Examiner.

Page 17 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 4 Page 5 of 5 Event

Description:

1B Main FDW Pump Active Thrust Bearing Temperature HIGH Requiring manual power reduction and MFW Pump trip (C: BOP, R: OATC, SRO)(TS)

Time Position Applicant's Actions or Behavior OP/1/A/1106/002 B SRO/OATC/

BOP Crew Response:

OP/1/A/1106/002 B (FDWPT Operation) Encl 4.9 Shutdown Of 1B FDWPT Rev 38 2.1 IF this is first FDWPT to be shutdown:

[It is the 1st FDWPT to be shutdown]

2.1.1 Verify 1SA-5/E-1 (FWPT / RX TRIP ALERT) NOT in alarm.

2.1.2 Position the following:

A. Ensure 1FDW-53 (1A FDWP RECIRC CONTROL) in "MANUAL" B. Ensure Closed 1FDW-53 (1A FDWP RECIRC CONTROL)

C. Ensure 1FDW-65 (1B FDWP RECIRC CONTROL) in "MANUAL" D. Ensure Closed 1FDW-65 (1B FDWP RECIRC CONTROL) 2.2 IF in FDW Heatup, perform the following: [N/A]

2.3 Ensure running 1B FDWP AUXILIARY OIL PUMP.

2.4 IF 1A FDWP is NOT isolated for maintenance, start 1A FDWP AUXILIARY OIL PUMP.

2.5 Place 1B MAIN FDW PUMP (ICS) in "HAND".

2.6 Slowly run 1B MAIN FDW PUMP demand signal to minimum.

2.7 IF required, verify 1A FDWPT picks up load by observing FDWPT suction flow instruments.

2.8 Immediately trip 1B FDWPT from FW TURB 1B TRIP/RESET switch.

Verify closed 1B FDWPT HP stop valve

Verify closed 1B FDWPT LP stop valve This event is complete when the BOP secures the 1B MFW Pump, or as directed by the Lead Examiner.

Page 18 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.:ILT48 Scenario No.: 2 Event No.: 5 Page 1 of 1 Event

Description:

Bearing Oil Header Pressure LOW, EBOP fails to AUTO Start ( C: BOP, SRO)

Time Position Time 1SA-3/E-7 Plant Response:

1SA-3/E7 BEARING OIL HEADER PRESSURE LOW

OAC alarm TGOP RUNNING Crew Response:

1SA-3/E-7 BEARING OIL HEADER PRESSURE LOW Rev 59 3.1 Verify Turning Gear Oil Pump has started.

SRO/ 3.2 Check BEARING HEADER pressure gauge at Turbine Front Standard.

BOP NOTE: EBOP will also start on a loss of power to Turning Gear Oil Pump Examiner Note: EBOP will fail to start automatically.

3.3 IF BEARING HEADER pressure < 15 psig, verify EBOP is on.

3.3.1 IF EBOP has NOT started, start EBOP.

[the BOP will start the EBOP]

3.4 IF BEARING HEADER pressure is still < 15 psig:

3.4.1 TRIP THE TURBINE 3.4.2 Place Turbine Turning Gear switch in PULL TO LOCK.

3.5 Check all 12 bearings and verify oil drain flow.

3.6 Check Main Shaft Pump discharge and suction pressure.

3.7 Check Oil Cooler flow sight glass for flow indication and for cooler leakage.

3.8 Check booster pump valve and pressure switch set points.

Examiner Note: Approximately one minute after the EBOP is started, it will trip on overload. Approximately one minute after the EBOP trips, the main turbine will trip.

This event is complete when the OATC attempts to trip the reactor, or as directed by the Lead Examiner.

Page 19 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 6 Page 1 of 7 Event

Description:

Turbine Oil Header Pressure low, Manual Turbine Trip, ATWS (M: All)

Time Position Applicant's Actions or Behavior EOP Plant response:

1SA-3/E-7 BEARING OIL HEADER PRESSURE LOW

Statalarm 1SA-01/A-1, B-1, C-1, D-1 (RP Channel A-D Trip)

Crew response:

Recognize that the Reactor did NOT trip

Attempt to trip the reactor manually SRO

SRO will direct the OATC to perform IMAs and the BOT to perform a symptom check.

IMAs EOP Immediate Actions Rev 40 OATC 3.1 Depress REACTOR TRIP pushbutton. [Will not trip the reactor]

3.2 Verify reactor power < 5% FP and decreasing.

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

(Page 21)

SYMPTOM CHECK BOP The BOP will verify the following:

Power Range NIs NOT < 5% Rule 1, ATWS/Unanticipated Nuclear Po Power Range NIs NOT decreasing Production Any SCM < 0°F Rule 2, Loss Of SCM Loss of Main and Emergency FDW Rule 3, Loss of Main or Emerg FDW (including unsuccessful manual initiation of Rule 4, Initiation of HPI Forced Cooling EFDW) (Inability to feed SGs and > 2300 psig, N limit reached, or PZR level > 375")

Uncontrolled Main steam line(s) pressure Rule 5, Main Steam Line Break decrease CSAE Offgas alarms None (SGTR Tab is entered when Process monitor alarms (RIA-40, 59,60), identified SG Tube Leakage > 25 gpm)

Area monitor alarms (RIA-16/17)

BOP will inform the SRO:

No symptoms to report except that Power Range NIs are > 5%, OATC is performing Rule 1.

This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.

Page 20 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 6 Page 2 of 7 Event

Description:

Turbine Oil Header Pressure low, Manual Turbine Trip, ATWS (M: All)

Time Position Applicant's Actions or Behavior RULE 1 OATC CREW RESPONSE:

Rule 1

1. Verify any Power Range NI 5% FP.

2. Initiate manual control rod insertion to the IN LIMIT.

3. Verify Main FDW is feeding the SGs.

4. __ Notify CRS to GO TO UNPP tab. (Page 23)

5. Open:

__ 1HP-24

__ 1HP-25 RNO: IF both are closed:

__ 1HP-24

__ 1HP-25 THEN GO TO Step 32.

6. Ensure at least one operating:

__ 1A HPI PUMP [1A HPIP is trippped]

__ 1B HPI PUMP [1B HPI Pump has to be started manually]

7. Start 1C HPI PUMP.

8. Open:

__ 1HP-26

__ 1HP-27 This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.

Page 21 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 6 Page 3 of 7 Event

Description:

Turbine Oil Header Pressure low, Manual Turbine Trip, ATWS (M: All)

Time Position Applicant's Actions or Behavior RULE 1 Crew Response:

OATC

9. Dispatch one operator without wearing Arc Flash PPE to open 600V CRD CT-2 breakers: {33}

__ 1X9-5C (U-1 CRD Norm Fdr Bkr) (U1 Equipment Rm)

__ 2X1-5B (U-1 CRD Alternate Fdr Bkr) (T-3/Dd-28)

Examiner Note: When the operator is dispatched to open CRD breakers, a 4 minute timer will be initiated to open the CRD breakers.

10. Verify only two HPI pumps operating.

11. EXIT.

This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.

Page 22 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 6 Page 4 of 7 Event

Description:

Turbine Oil Header Pressure low, Manual Turbine Trip, ATWS (M: All)

Time Position Applicant's Actions or Behavior UNPP Tab Crew Response:

SRO/BOP

1. Ensure Rule 1 (ATWS / Unanticipated Nuclear Power Production) is in progress or complete.

2. Verify Main FDW is operating and in AUTO.

3. IAAT Main FDW is NOT operating, THEN:

A. __ Trip the turbine-generator.

B. __ Start all available EFDW pumps.

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

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

RNO: GO TO Step 7.

5. Depress turbine TRIP pushbutton.

6. Verify all turbine stop valves closed.

7. Verify any wide range NI > 1% FP.

8. Open 1RC-4.

9. Verify 1HP-5 open.

10. Maximize letdown using 1HP-7 while maintaining letdown temperature

< 120°F.

11. Verify Main FDW available.

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

13. Verify overcooling in progress. [Over cooling is NOT in progress]

RNO: GO TO Step 16.

This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.

Page 23 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 6 Page 5 of 7 Event

Description:

Turbine Oil Header Pressure low, Manual Turbine Trip, ATWS (M: All)

Time Position Applicant's Actions or Behavior UNPP Tab SRO/OATC Crew Response:

16. Secure makeup to LDST. {8}

17. WHEN all wide range NIs are <1% FP, AND decreasing, THEN continue.

18. Control RCS temperature as follows:

__ Tave < 555°F- Adjust SG pressure as necessary to stabilize RCS temperature using either:

TBVs

Dispatch two operators to perform Encl 5.24 (Operation of the ADVs). (PS)

__ Tave > 555°F

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

19. Throttle HPI per Rule 6 (HPI). (Page 27)

20. WHEN RCS pressure < 2300 psig, THEN continue.

21. Verify PORV closed.

22. Adjust letdown flow as desired.

23. Verify RCP seal injection available.

24. GO TO Subsequent Actions.

This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.

Page 24 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 6 Page 6 of 7 Event

Description:

Turbine Oil Header Pressure low, Manual Turbine Trip, ATWS (M: All)

Time Position Applicant's Actions or Behavior SUBSEQUENT ACTIONS Tab SRO/OATC Crew Response:

BOP 4.1 Verify all control rods in Groups 1 - 7 fully inserted.

4.2 Verify Main FDW in operation.

4.3 Verify either:

__ Main FDW overfeeding causing excessive temperature decrease.

__ Main FDW underfeeding causing SG level decrease below setpoint.

RNO: GO TO Step 4.5.

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

RNO: GO TO Step 4.9.

4.9 IAAT TBVs CANNOT control SG pressure at desired setpoint, AND TBVs NOT intentionally isolated, THEN manually control pressure in affected SGs using either:

__ TBVs

__ Dispatch two operators to perform Encl 5.24 (Operation of the ADVs) (PS) 4.10 Verify 1RIA-40 operable with CSAE OFF-GAS BLOWER operating.

4.11 GO TO Step 4.14.

4.14 Verify both are closed:

__ 1MS-17

__ 1MS-26 4.15 Verify ES is required.

RNO: 1. __ Initiate Encl 5.5 (Pzr and LDST Level Control) (Page 28)

2. __ GO TO Step 4.17.

4.17 Open:

__ PCB 20

__ PCB 21 This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.

Page 25 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 2 Event No.: 6 Page 7 of 7 Event

Description:

Turbine Oil Header Pressure low, Manual Turbine Trip, ATWS (M: All)

Time Position Applicant's Actions or Behavior SUBSEQUENT ACTIONS Tab Crew Response:

SRO/OATC BOP 4.18 Verify Generator Field Breaker open.

4.19 Verify EXCITATION is OFF.

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

4.21 Verify ICS/NNI power available.

4.22 Verify all 4160V switchgear (1TC, 1TD & 1TE) energized.

4.23 Verify both SGs > 550 psig.

4.24 Verify Main FDW operating.

4.25 Verify any RCP operating.

4.26 Verify AP/0/A/1700/025 (SSF EOP) Encl (Unit 1 OATC Actions During Fire) in progress or complete.

RNO: Ensure SGs approaching 25 - 35 [55 - 65 acc] S/U level.

4.27 Place switches in CLOSE:

__ 1FDW-31

__ 1FDW-40 This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.

Page 26 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Rule 6 HPI HPI Pump Throttling Limits

HPI must be throttled to prevent violating the RV-P/T limit.

HPI pump operation must be limited to two HPIPs when only one BWST suction valve (1HP-24 or 1HP-25) is open.

HPI must be throttled 475 gpm/pump (including seal injection for A header) when only one HPI pump is operating in a header.

Total HPI flow must be throttled 950 gpm including seal injection when 1A and 1B HPI pumps are operating with 1HP-409 open.

Total HPI flow must be throttled < 750 gpm when all the following exist:

- LPI suction is from the RBES

- piggyback is aligned

- either of the following exist:

only one piggyback valve is open (1LP-15 or 1LP-16)

only one LPI pump operating

HPI may be throttled under the following conditions:

HPI Forced Cooling in Progress: HPI Forced Cooling NOT in Progress:

All the following conditions must exist: All the following conditions must exist:

Core SCM > 0

All WR NIs 1%

CETCs decreasing

Core SCM > 0

Pzr level increasing

CRS concurrence required if throttling following emergency boration HPI Pump Minimum Flow Limit

Maintain 170 gpm indicated/pump. This is an instrument error adjusted value that ensures a real value of 65 gpm/pump is maintained. HPI pump flow less than minimum is allowed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Page 27 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control 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 IF 1HP-26 will NOT open, maintain desired Pzr level: THEN throttle 1HP-410 to maintain

1A HPI Pump desired Pzr level.

1B HPI 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 1A BHUT, THEN perform the following:

A. Open:

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

C. Notify SRO.

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

Page 28 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control 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 1B LPI PUMP.

C. Open:

1LP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D. IF two LPI Pumps are running only 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, U1 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 1B 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 29 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

8. Start 1C HPI PUMP. IF at least two HPI pumps are operating, THEN throttle 1HP-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 1HP-26 will NOT open, 1HP-26 THEN throttle 1HP-410 to maintain desired Pzr level.

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

Page 30 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED 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 1HP-24. (1HP-24 and 1HP-25) are closed, THEN perform the following:

Open 1HP-25.

Close 1HP-16. A. Start 1A LPI PUMP.

B. Start 1B LPI PUMP.

C. Open:

1LP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D. IF two LPI Pumps are running only 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, U1 LPI Hatch Rm, N end).

F. GO TO Step 13.

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

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

12.__ Operate Pzr heaters as required to maintain heater bundle integrity.

Page 31 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

13. 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-1-107, Unit 1 RC Bleed Transfer Pump Rm.).

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

Open 1HP-17.

Open 1HP-18

15. IAAT all of the following exist: GO TO Step 35.

Letdown isolated LPSW available Letdown restoration desired THEN perform Steps 16 - 34. {41}

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

2. GO TO Step 35.

17. Ensure only one CC pump running.

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

19. Verify both are open: 1. IF 1HP-1 is closed due to 1HP-3 failing to 1HP-1 close, 1HP-2 THEN GO TO Step 21.

2. IF 1HP-2 is closed due to 1HP-4 failing to close, THEN GO TO Step 21.

20. GO TO Step 23.

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

21. Verify letdown line leak in East GO TO Step 23.

Penetration Room has occurred.

22. GO TO Step 35.

Page 32 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

23. Monitor for unexpected conditions while restoring letdown.

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

1HP-1 1HP-3

2. IF 1B letdown cooler is to be placed in service, THEN open:

1HP-2 1HP-4

3. GO TO Step 26.

25. Open:

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

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

aligned.

A. Notify CR SRO of problem.

B. GO TO Step 35.

27. Close 1HP-6.

28. Close 1HP-7.

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

2. Close:

1HP-8 1HP-9&11

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

A. Select 1HP-14 to NORMAL.

B. Close 1HP-16.

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

Page 33 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

30. Open 1HP-5.

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

32. WHEN letdown temperature is

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

33. Open 1HP-6.

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

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

35. 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).

36. 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.

37. 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 34 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

38. Verify 1CS-48 (1A BHUT Recirc) has GO TO Step 40.

been closed to provide additional makeup flow to LDST.

39. 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 1CS-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.

40. Verify two Letdown Filters in service, GO TO Step 42.

AND only one Letdown filter is desired.

41. Perform one of the following:

Place 1HP-17 switch to CLOSE.

Place 1HP-18 switch to CLOSE.

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

Page 35 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation Rev 40 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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 GO TO Step 8.

MD EFDWP is desired, THEN perform Steps 4 - 7.

4. Place EFDW control valve on SG with NO EFDW flow to MANUAL and closed:

1A SG 1B SG 1FDW-315 1FDW-316

5. Locally open:

1FDW-313 (1A EFDW Line Disch To 1A S/G X-Conn) (T-1, 1' N of M-16, 18' up) 1FDW-314 (1B EFDW Line Disch To 1B S/G X-Conn) (T-1, 3' S of M-24, 10' up)

6. Ensure a MD EFDWP is operating.

7. Throttle EFDW control valve on SG with NO EFDW flow to establish appropriate level per Rule 7 (SG Feed Control):

1A SG 1B SG 1FDW-315 1FDW-316

8. Perform as required to maintain UST level

> 7.5':

Makeup with demin water.

Place CST pumps in AUTO.

9. IAAT all 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.

Page 36 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

10. Verify 1 TD EFDW PUMP operating. GO TO Step 12.

11. Start TD EFDWP BEARING OIL COOLING PUMP.

NOTE

Loss of the condensate system for 25 minutes results in cooling down to LPI using the ADVs.

If NO HWPs are operating, continuing this enclosure to restore the condensate system is a priority unless the CR SRO deems EOP activities higher priority. The 25 minute criterion is satisfied when a HWP is started and 1C-10 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.

13. IAAT it is determined that condensate flow CANNOT be restored within 25 minutes, THEN GO TO Step 90.

14. Verify any HWP operating. 1. Place all CBP control switches to OFF.

2. GO TO Step 20.

15. Verify any CBP operating. 1. IF AP/11 restarted a HWP, THEN GO TO Step 22.

2. GO TO Step 41.

16. Verify 1C COND BOOSTER PUMP 1. Ensure only one CBP is operating.

operating.{12}

2. GO TO Step 18.

17. Stop: {12}

1A COND BOOSTER PUMP 1B COND BOOSTER PUMP

18. Ensure only one HWP is operating.

19. GO TO Step 44.

Page 37 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

20. Verify a loss of power event caused the GO TO Step 24.

loss of the secondary system.

21. Ensure AP/11 (Recovery From Loss of Power) is in progress.

22. WHEN AP/11 (Recovery From Loss of Power) has restored 600v load centers, AND a HWP is operating, THEN dispatch an operator to start all CBP Aux Oil Pumps. (T-1/J-21)

23. WHEN notified that all CBP Aux Oil pumps are operating, THEN GO TO Step 41.

24. Place all HWP control switches to OFF.

25. Place all CBP control switches to OFF.

26. Place valve switches to close until valve Continue.

travel is initiated:

1FDW-4 1FDW-9

27. Start: Start as necessary:

1A FDWP AUXILIARY OIL PUMP 1A FDWP EMERGENCY BRNG OIL 1B FDWP AUXILIARY OIL PUMP PUMP 1B FDWP EMERGENCY BRNG OIL PUMP

28. Verify both: 1. IF both FDW pumps have BRG LUBE FWPT A BRG LUBE OIL OIL PRESS < 4 psig, PRESS > 4 psig THEN GO TO Step 90.

FWPT B BRG LUBE OIL 2. Perform for the FDW pump that has BRG PRESS > 4 psig LUBE OIL PRESS < 4 psig:

Close 1FDW-1 for 1A FDW pump.

Close 1FDW-6 for 1B FDW pump.

29. Place in MANUAL and close:

1FDW-53 1FDW-65 Page 38 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

30. Place 1C-10 FAIL SWITCH in MANUAL.

31. Close 1C-10.

32. Make plant page to clear basement and third floor of non-essential personnel.

33. Start one HWP.

34. Verify < 25 minutes elapsed since loss 1. Stop all HWPs.

of condensate.

2. GO TO Step 90.

35. Throttle 1C-10 controller 10% open to satisfy 25 minute system restart criteria.

36. WHEN FWP SUCT HDR PRESS (1VB3) is 100 psig, THEN open 1C-10.

37. Place 1C-10 FAIL SWITCH in FAIL OPEN.

38. Dispatch an operator to start all CBP Aux Oil Pumps. (T-1/J-21)

39. Maximize total recirc flow < 1200 gpm with one of the following:

1FDW-53 1FDW-65

40. WHEN five minutes have elapsed, AND notified that all CBP Aux Oil pumps are operating, THEN continue procedure.

41. Start a second HWP.

42. Start 1C COND BOOSTER PUMP. {12} Start one available CBP.

43. Stop one operating HWP.

44. Place control switch for one secured HWP in AUTO.

45. Place control switch for one secured CBP in AUTO.

Page 39 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

46. Perform the following:

Position HWP LOAD SHED DEFEAT switch to a running HWP.

Position CBP LOAD SHED DEFEAT switch to a running CBP.

47. Place in MANUAL:

1FDW-53 1FDW-65

48. Establish 2300 - 6000 gpm total recirc flow with one of the following:

1FDW-53 1FDW-65

49. IAAT UST level CANNOT be maintained > 8.5',

THEN locally open 1C-899 (Cond Recirc To UST Riser Throttle)

(T-1/J-23).

50. IAAT UST level increases > 11',

THEN perform as required:

Throttle demin water Locally throttle 1C-899 (Cond Recirc To UST Riser Throttle)

(T-1/J-23)

51. Verify closed: GO TO Step 58.

1FDW-4 1FDW-9 Page 40 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

52. Position switches in CLOSE:

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

53. Ensure closed:

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

54. Locally open:

1FDW-5 (1A FDWP Discharge Bypass)

(T-1/SE of D-24 12' up) 1FDW-10 (1B FDWP Discharge Bypass) (T-1/N of D-26 9' up)

55. WHEN FWP DISCH HDR PRESS (1VB3) is approximately equal to either of the following:

O1A1014 (FDWP 1A DISCHARGE PRESS)

O1A1391 (FDWP 1B DISCHARGE PRESS)

THEN open:

1FDW-4 1FDW-9 Page 41 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

56. Locally close:

1FDW-5 (1A FDWP Discharge Bypass)

(T-1/SE of D-24 12' up) 1FDW-10 (1B FDWP Discharge Bypass) (T-1/N of D-26 9' up)

NOTE Windmill protection may have required closure of FDW pump suction valve.

57. Verify open: 1. IF required, notify the WCC SRO to 1FDW-1 initiate investigation.

1FDW-6 2. Note on Turnover sheet that FDW pump associated with closed valve is not available for use until problem resolved.

58. IAAT it is desired to re-establish Main FDW, THEN initiate Encl (Re-establishing Main FDW) of OP/1/A/1106/002 (Condensate And FDW System).

59. IAAT EFDW has been secured per Encl (Re-establishing Main FDW) of OP/1/A/1106/002 (Condensate And FDW System),

THEN EXIT.

Page 42 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

60. WHEN UST level is < 4',

THEN dispatch two operators to perform Encl 5.24 (Operation of the ADVs) in preparation for loss of vacuum. (PS)

61. Verify power available to 1V-186 by Dispatch an operator to be in position at using valve position indicating light. 1V-186 (Vacuum Breaker)

(T-3, catwalk at 1C2 waterbox).

NOTE 1C-573 will be closed after vacuum is broken.

62. Dispatch an operator with a safety harness to 1C-573 (MD EFDWPs Suction From UST) (T-1, SW of E-24, 8' above floor) to:

Unlock and remove chain from 1C-573.

Establish communication with Control Room.

63. WHEN UST level is < 3',

THEN continue.

64. Open 1V-186. Notify operator to open 1V-186 (Main Condenser Vacuum Breaker)

(T-3, catwalk at 1C2 waterbox).

65. Stop all main vacuum pumps.

66. Stop all CBPs.

67. Stop all HWPs.

68. Close: Dispatch an operator to close:

1MS-47 1MS-49 (1A CSAE Steam Supply) 1AS-40 (T-3/F-26) 1MS-58 (1B CSAE Steam Supply)

(T-3/G-26) 1MS-67 (1C CSAE Steam Supply)

(T-3/H-26)

Page 43 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE

1C-573 is open unless Step 75 has been completed.

While EFDW is secured, a transfer to LOHT is required only when directed by this enclosure or Rule 4 (Initiation of HPI Forced Cooling) conditions are met.

69. IAAT UST level is < 1', GO TO Step 72.

AND 1C-573 (MD EFDWPs Suction From UST) is open, THEN perform Steps 70 - 71.

70. Perform the following:

Stop 1A MD EFDWP.

Stop 1B MD EFDWP.

71. Verify 1C-391 open. 1. Stop 1TD EFDW PUMP.

2. Close:

1FDW-315 1FDW-316

72. Perform the following:

A. Reduce MD EFDWP flow to

< 440 gpm per pump.

B. Notify crew of MD EFDWP flow limit while aligned to hotwell.

NOTE Vacuum gage or computer can be used. Vacuum is broken when either start to flat line. Do NOT change scale on computer trend once started.

73. WHEN vacuum is broken, THEN continue.

Page 44 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

74. IAAT MD EFDWPs are operating, GO TO Step 78.

OR available to operate, THEN PERFORM Steps 75 - 77.

75. Locally close 1C-573 1. IF 1TD EFDW PUMP is operating, (MD EFDWPs Suction From UST) OR operable, (T-1, SW of E-24, 8' above floor). THEN GO TO Step 78.

2. IF NO EFDW pumps are operating, THEN:

A. Notify CR SRO that a LOHT exists from loss of EFDW suction source.

B. Notify CR SRO that Rule 3 will be performed to cross connect with alternate unit.

C. Consider all U1 EFDW pumps inoperable, AND GO TO Rule 3.

76. Verify MD EFDWPs were stopped due GO TO Step 78.

to UST level < 1'.

77. Perform the following:

A. Restart all MD EFDWPs that were stopped due to UST level < 1'.

B. Resume feeding available SGs.

Page 45 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

78. Verify 1 TD EFDW PUMP operating. GO TO Step 82.

79. Dispatch operator to 1C-157 (TD EFDWP Suction From UST) to establish communication with CR (T-1/C-20).

80. WHEN operator in place at 1C-157, THEN continue.

81. Stop 1 TD EFDW PUMP.

82. Locally close 1C-157 (TD EFDWP 1. IF NO EFDW pumps are operating, Suction From UST) (T-1/C-20). THEN:

A. Notify CR SRO that a LOHT exists from loss of EFDW suction source.

B. Notify CR SRO that Rule 3 will be performed to cross connect with alternate unit.

C. Consider all U1 EFDW pumps inoperable, AND GO TO Rule 3.

2. GO TO Step 84.

83. Open 1C-391. 1. Attempt to locally open 1C-391 (TD EFDWP Suction From Hotwell)

(T-1/C-20).

2. IF 1C-391 CANNOT be opened, AND NO EFDW pumps are operating, THEN:

A. Notify CR SRO that a LOHT exists from loss of EFDW suction source.

B. Notify CR SRO that Rule 3 will be performed to cross connect with alternate unit.

C. Consider all U1 EFDW pumps inoperable, AND GO TO Rule 3.

Page 46 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation

84. IAAT 1 TD EFDW PUMP operation is desired, AND all exist:

Hotwell level is > 1.

Vacuum is broken.

1 TD EFDW PUMP successfully aligned to hotwell.

THEN:

A. Start 1 TD EFDW PUMP.

B. Feed available SGs as required.

85. Dispatch an operator to open:

1C-188 (Hotwell Emerg Makeup #1 Control Bypass) (T-1/W of E-24). {18}

1C-912 (UST Riser To HW Emerg Makeup #2 Auto Isol Bypass)

(T-1/G-23)

86. Notify TSC to evaluate methods to maintain secondary inventory including strategies located in EM 5.1 (Engineering Emergency Response Plan) and EM 5.2 (Evaluation By Station Management in the TSC -

Beyond Design Basis Mitigation Strategies).

Page 47 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

87. IAAT hotwell level is 1, THEN:

A. Stop all EFDWPs.

B. Consider all U-1 EFDW pumps inoperable, AND GO TO Rule 3.

NOTE

This step provides general plant directions for the SRO and Management team. The user shall continue after the notification has been made.

Swapping from TBVs to ADVs prevents overfilling the hotwell/condenser.

Securing steam seals limits the water (condensation) that reaches the oil systems. Vacuum must be broken to secure steam seals.

Engineering will determine when to allow secondary system restart.

Beginning a cooldown assumes HPI is operating. If the SSF is supplying seals, then further discussion with the Management team should be undertaken prior to cooldown.

88. Notify the CR SRO to direct the following as time and resources allow:

Transfer steam control from TBVs to ADVs.

Operate ADVs per U1 EOP Encl 5.24 (Operation of ADVs).

Begin Unit cool down to LPI per OP/1/A/1102/010 (Controlling Procedure For Unit Shutdown) using the ADVs.

Break vacuum per OP/1-2/A/1106/016 (Condenser Vacuum System).

Secure Steam Seals per OP/1/A/1106/13 (Steam Seal System).

89. WHEN directed by CR SRO, THEN EXIT.

Page 48 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Subsequent Actions EP/1/A/1800/001 Parallel Actions Page 1 of 1 CONDITION ACTIONS

1. PR NIs 5% FP OR GO TO UNPP tab. UNPP NIs NOT decreasing

2. All 4160V SWGR de-energized GO TO Blackout tab. BLACKOUT

{13}

3. Core SCM indicates superheat GO TO ICC tab. ICC

4. Any SCM = 0°F GO TO LOSCM tab. LOSCM

5. Both SGs intentionally isolated to GO TO EHT tab.

stop excessive heat transfer

6. Loss of heat transfer (including LOHT loss of all Main and Emergency GO TO LOHT tab.

FDW)

7. Heat transfer is or has been GO TO EHT tab. EHT excessive

8. Indications of SGTR 25 gpm GO TO SGTR tab. SGTR

9. Turbine Building flooding NOT GO TO TBF tab. TBF caused by rainfall event

10. Inadvertent ES actuation occurred Initiate AP/1/A/1700/042 (Inadvertent ES ES Actuation).

11. Valid ES actuation has occurred Initiate Encl 5.1 (ES Actuation). ES or should have occurred

12. Power lost to all 4160V SWGR

Initiate AP/11 (Recovery from Loss and any 4160V SWGR of Power).

re-energized ROP

IF Encl 5.1 (ES Actuation) has been initiated, THEN reinitiate Encl 5.1.

13. RCS leakage > 160 gpm with Notify plant staff that Emergency Dose EDL letdown isolated Limits are in affect using PA system.

14. Individual available to make

Announce plant conditions using notifications PA system.

Notify OSM to reference the NOTIFY Emergency Plan and NSD 202 (Reportability).

Page 49 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam CRITICAL TASKS CT-1 ICS must be taken to HAND and FDW adjusted to prevent tripping the reactor.

Adjustment will be dependent on how much time it takes to place ICS in HAND.

CT-2 Take the reactor subcritical (i.e. < 1% WR) prior to exiting the UNPP tab.

Page 50 of 51

SAFETY: Take a Minute UNIT 0 (OSM)

SSF Operable: Yes KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 2 Fuel Handling: No UNIT STATUS (CR SRO)

Unit 1 Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 100% Mode: 1 Mode: 1 Gross MWE: 895 100% Power 100% Power RCS Leakage: 0.01 gpm EFDW Backup: Yes EFDW Backup: Yes No WCAP Action RBNS Rate: 0.01 gpm Technical Specifications/SLC Items (CR SRO)

Component/Train OOS Restoration TS/SLC #

Date/Time Required Date/Time AMSAC/DSS 0300 7 Days 16.7.2 Shift Turnover Items (CR SRO)

Primary

Due to unanalyzed condition, the SSF should be considered INOP for Unit 1 if power levels are reduced below 85%. Evaluations must be performed prior to declaring the SSF operable following a return to power (after going below 85%).

1RIA-3 and 5 removed from RB.

OATC is to perform a 5 minute Delith using OP/1/A/1103/004C (Deborating IXs) Encl. 4.4 (Unit 1 Deborating IX For RCS De-lith (Rx At Power))

Secondary

Feedwater valve DP selected to A1 and B2 for maintenance

AMSAC/DSS bypassed

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

Reactivity Management (CR SRO)

Gp 7 Rod Position: Batch additions as required for volume RCS Boron 83 ppmB 92% Withdrawn control.

Human Performance Emphasis (OSM)

Procedure Use and Adherence

Appendix D Scenario Outline Form ES D-1 ILT48 NRC Exam Facility: Oconee Scenario No.: 3 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________SRO

________________________ ________________________OATC

________________________ ________________________BOP Initial Conditions:

Reactor Power = 100%

Turnover:

Feedwater valve DP selected to 1A1 and 1B2 for maintenance

AMSAC/DSS bypassed Event Malfunction Event Event Type* Description No. No.

0a 0b 0c 1A RBCU high vibration, secure 1A and start 1B 1 Override C: BOP, SRO (TS)

RBCU 2 MSI231 I: OATC, SRO 1A FDW Valve DP Signal Fails Low C: BOP, R: OATC 3 MPS450 1B1 RCP Hi Vib, Power reduction SRO (TS) 4 MPI281 I: OATC, SRO Tc fails 5 Updater C: BOP, SRO 1HP-14 fails to BLEED 6 MPS020 R: OATC, SRO (TS) 20 gpm Pri-Sec leak in 1B SG requires Manual S/D 1TA Lockout, 1B SGTR MPS020 7 M: ALL

TBV on intact SG trips to MANUAL Updater

1HP-26 fails closed

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Scenario 3 Event Summary:

Event 1: 1A RBCU will develop a vibration and alarm on the OAC. The OAC alarm response guide will direct the operator to attempt to reset the alarm and then secure the RBCU. The crew will contact engineering who will direct starting of the 1B RBCU in High speed. The RBCU will start in low speed first, then de-energize and change to High speed.

Event 2: The feedwater valve DP will fail low causing feedwater pump speed to increase. The OATC will have to take MFWPs to MANUAL and reduce FWPT speed. The crew will perform AP/28 (ICS Instrumentation Failures). ICS will be returned to AUTO.

Event 3: RCP 1B1 will experience high vibration that will require using AP/16 (RCP Malfunction) to perform a power reduction to below 70% to remove from service.

Event 4: When the 1B1 RCP is tripped, Tc will fail and feedwater will not re-ratio. The OATC may attempt to control Tc with the Tc controller in MANUAL but this will not work either. The OATC will then be required to take both FDW LOOP MASTERS to HAND in order to re-ratio feedwater.

Event 5: 1HP-14 will fail in the BLEED position. Crew will be required to enter AP/2, (Excessive RCS Leakage). The crew will close 1HP-6 and throttle 1HP-7 to maintain Pzr Level.

Event 6: A 20 gpm SGTL in the 1B SG will require entry into AP/31, (Primary to Secondary Leakage) and perform a rapid unit shutdown using AP/29 (Rapid Unit Shutdown) with ICS in MANUAL.

Event 7: Bus 1TA will lockout. This will cause the 1A1 RCP to de-energize and the Reactor to trip (only 2 RCPs operating). When the reactor trips, the SGTL will degrade into a 200 gpm SGTR. The TBV on the 1A SG will trip to MANUAL. 1HP-26 will not open requiring the crew to open 1HP-410 to inject into the RCS.

Page 2 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 1 Page 1 of 2 Event

Description:

1A RBCU high vibration, secure 1A and start 1B RBCU (C, BOP, SRO)(TS)

Time Position Applicant's Actions or Behavior Plant Response:

OAC alarm:

O1D1361, RBCU FAN 1A VIB SRO/BOP Crew Response:

BOP will Refer to OAC ARG (O1D1361, RBCU FAN 1A VIB)

1. Depress the RBCU OAC Vibration Alarm Reset Pushbutton

[It will not reset]

2. If the alarm doesnt clear, stop the RBCU.

[BOP will secure the 1A RBCU]

[Alarm will not reset until the ALARM RESET P/B is depressed]

3. Notify Engineering for an evaluation Booth cue: Using time compression as SM & engineering request that 1B RBCU be started in HIGH SPEED.

OP/1/A/1104/015 OP/1/A/1104/015 Reactor Building Cooling System, Rev 42 Encl 4.3 (RBCU Operation), Section 4, Starting RBCUs NOTE: When starting RBCUs or changing LPSW flows, RB pressure will change as RB temperature changes.

4.1 Verify RB pressure within limits of PT/1/A/0600/001 (Periodic Instrument Surveillance).

4.2 Begin monitoring RB absolute pressure. (OAC Turn On Code: 1RBPA) {8}

4.3 IF personnel inside containment, announce over plant page that starting RBCU(s). {11}

NOTE: Starting RBCUs can affect the following: RBCU bearing temperatures, RBCU vibration, RBNS level, 1RIA-47 level, RB pressure/temperature.

4.4 Place desired switch to "HIGH" or "LOW":

1A RBCU 1B RBCU 1C RBCU This event is complete when 1B RBCU is started, or as directed by the Lead Examiner.

Page 3 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 1 Page 2 of 2 Event

Description:

1A RBCU high vibration, secure 1A and start 1B RBCU (C, BOP, SRO)(TS)

Time Position Applicant's Actions or Behavior OP/1/A/1104/015 Crew Response:

BOP NOTE:

When changing LPSW flows, RB pressure will change as RB temperature changes.

Each RBCU must have 550 gpm Inlet Flow or 750 gpm Outlet Flow to meet flow requirements of SLC 16.9.12.

4.5 Position valves as required for RB cooling:

1LPSW-18 (1A RBCU OUTLET)

1LPSW-21 (1B RBCU OUTLET)

1LPSW-24 (1C RBCU OUTLET)

TS 3.6.5, REACTOR BUILDING SPRAY AND COOLING TRAINS Condition B (7 days) Restore reactor building cooling train to OPERABLE status.

This event is complete when 1B RBCU is started, or as directed by the Lead Examiner.

Page 4 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 2 Page 1 of 6 Event

Description:

1A FDW Valve DP Signal Fails Low (I, OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/028 Plant Response:

FDW pump speed increases

FDW Control Valves will throttle closed to limit flow

FDW Pump discharge pressure increases SRO/OATC Crew Response:

Crew should perform Plant Transient Response (PTR).

OATC should place both FDW pump ICS stations in MANUAL and reduce FDW pump speed to ~ pre-transient valve.

The OATC may take the Diamond & both FDW Masters to HAND

SRO will enter AP/1/A/1700/028, ICS Instrumentation Failure Examiner Note: OATC may take FDW Loop Masters and Diamond to HAND as well. These are standard PTR actions.

AP/1/A/1700/028 Rev 20 4.1 Provide control bands as required.

4.2 Initiate notification of the following:

__ OSM to reference the following:

OMP 1-14 (Notifications)

Emergency Plan

__ STA 4.3 Verify a power transient 5% has occurred.

RNO: GO TO Step 4.5.

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

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

OAC alarm video

OAC display points

Control Board indications

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

Section Failure 4H Feedwater Valve P This event is complete when a valid Feedwater Valve DP input to ICS has been selected and ICS is returned to AUTO, or when directed by the lead examiner.

Page 5 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 2 Page 2 of 6 Event

Description:

1A FDW Valve DP Signal Fails Low (I, OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/028 Crew Response:

SRO/OATC AP/28, Section 4H NOTE

If Feedwater Valve P failed high, both MFDWPs go to low speed stop.

If Feedwater Valve P failed low, the following will occur:

Both MFDWPs go to high speed stop

Feedwater control valves close to reduce increased Feedwater flow

Feedwater pump(s) may trip on high discharge pressure

1. Ensure the following in HAND:

__ 1A MAIN FDW PUMP

__ 1B MAIN FDW PUMP

2. Notify SPOC to investigate and repair the failed Feedwater Valve DP instrumentation.

Booth Cue: When notified as SPOC, inform the crew that all work is complete on 1A2 FDW Valve dp and 1A2 FDW Valve dp is now a valid signal.

3. Select a valid Feedwater Valve DP input to ICS with selector switch.

4. WHEN a valid Feedwater Valve DP input has been restored to ICS, THEN GO TO OP/1/A/1102/004 A Encl 4.4 (Placing ICS Stations To Auto).

Examiner Note: Crew should select 1A2 FDW Valve dp and return ICS to AUTO.

OP/1/A/1102/004 A Encl 4.4 Rev 10 1.1 Verify CTP 3%

1.2 Review PT/0/A/1103/020 1.3 Ensure dedicated operator assigned to monitor/operate ICS 1.4 Perform pre-job brief including precautions from SOMP 1-02 (Reactivity Management) and applicable Limits & Precautions of PT/0/A/1103/020 (Power Maneuvering Predictions) (R.M.)

1.5 Ensure R2 reactivity management controls are established in Control Room per SOMP 1-02 (Reactivity Management)

This event is complete when a valid Feedwater Valve DP input to ICS has been selected and ICS is returned to AUTO, or when directed by the lead examiner.

Page 6 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 2 Page 3 of 6 Event

Description:

1A FDW Valve DP Signal Fails Low (I, OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1102/004 A Crew Response:

SRO/OATC OP/1/A/1102/004 A Encl 4.4 Section 2 2.1 Ensure "RATE SET" thumbwheels at 0.0.

2.2 IF TURBINE MASTER is in HAND, perform Section 3 (N/A) 2.3 IF either TBV is in HAND, perform Section 4 (N/A) 2.4 IF REACTOR MASTER OR DIAMOND is in manual, perform Section 5 Examiner Note: Section 5 may or may NOT be needed based on actions taken during PTR OP/1/A/1102/004 A Encl 4.4 Section 5 5.1 IF Rx Master is in HAND, perform the following: (N/A) 5.2 IF both SGs are off of Level Control, perform the following:

5.2.1 IF selected Tave (O1E2086) is different from Tave setpoint (O1E2087) by more than +/- 0.15°F, perform the following:

A. Simultaneously ensure 1A & 1B FDW Masters in HAND NOTE: Cycling the setpoint selector may result in a Star Module failure. This is expected for this condition and entry into AP/28 (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: (N/A)

D. On REACTOR MASTER adjust Tave setpoint (O1E2078) towards selected Tave (O1E2086) 5.2.2 Verify selected Tave is within +/- 0.15°F of Tave setpoint 5.3 IF either SG is on Level Control, adjust Tave setpoint (O1E2087) to 579°F 5.4 Place DIAMOND in AUTO 5.5 Return to Section 2 (Procedure)

This event is complete when a valid Feedwater Valve DP input to ICS has been selected and ICS is returned to AUTO, or when directed by the lead examiner.

Page 7 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 2 Page 4 of 6 Event

Description:

1A FDW Valve DP Signal Fails Low (I, OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1102/004 A Crew Response:

SRO/OATC OP/1/A/1102/004 A Encl 4.4 Section 2 2.5 IF DELTA Tc is in HAND, perform Section 6 (N/A) 2.6 IF STM GENERATOR MASTER or either FDW MASTER is in HAND, perform Section 7 (Placing FDW To Auto)

Section 7 may or may NOT be needed based on actions taken during PTR OP/1/A/1102/004 A Encl 4.4 Section 7 7.1 IF SG Master is in HAND, perform the following: (N/A) 7.2 IF 1A OR 1B FDW Master is NOT in AUTO, perform the following:

7.2.1 Select 1A & 1B FDW MASTERs to "MEAS VAR" 7.2.2 IF both 1A AND 1B FDW Master Measured Variables are on the caret:

A. Select 1A & 1B FDW MASTERs to "POS" B. Simultaneously ensure 1A & 1B FDW MASTERs in AUTO 7.2.3 IF 1A OR 1B FDW Master Measured Variable is NOT on the caret (N/A) 7.3 Return to Section 2 (Procedure)

OP/1/A/1102/004 A Encl 4.4 Section 2 2.7 IF any FDW valves are in HAND, perform Section 8 (N/A) 2.8 IF either Main FDW Pump is in HAND, perform Section 9 This event is complete when a valid Feedwater Valve DP input to ICS has been selected and ICS is returned to AUTO, or when directed by the lead examiner.

Page 8 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 2 Page 5 of 6 Event

Description:

1A FDW Valve DP Signal Fails Low (I, OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1102/004 A Crew Response:

SRO/OATC OP/1/A/1102/004 A Encl 4.4 Section 9 9.1 IF lowest FDW valve P is NOT 35 psid, adjust either of the following until the lowest FDW valve P 35 psid: (R.M.)

1A MAIN FDW PUMP

1B MAIN FDW PUMP 9.2 Verify lowest FDW VALVE P 35 psid.

9.3 IF 1A MAIN FDW PUMP operating in "HAND", place 1A MAIN FDW PUMP (ICS) in "AUTO".

9.4 IF 1B MAIN FDW PUMP operating in "HAND", place 1B MAIN FDW PUMP (ICS) in "AUTO".

9.5 Return to Section 2 (Procedure).

OP/1/A/1102/004 A Encl 4.4 Section 2 2.9 Verify ICS in full Auto.

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

2.10 IF NOT being controlled by another procedure, perform the following:

2.10.1 IF THP (O1E2088) is NOT 885 psig, slowly adjust THP Setpoint (O1E2089) to 885 psig. (R.M.)

2.10.2 IF Tave Setpoint (O1E2087) is NOT at 579°F, slowly adjust Tave Setpoint to 579°F. (R.M.)

2.10.3 IF Delta Tc is NOT 0.0, adjust Delta Tc Setpoint (O1E2091) to 0.0°F. (R.M.)

2.11 IF both FDWP suction flows are NOT within 1 x 10 6 lb/hr of each other, adjust FDWP BIAS per Enclosure 4.3 (Adjusting FDWP BIAS).

This event is complete when a valid Feedwater Valve DP input to ICS has been selected and ICS is returned to AUTO, or when directed by the lead examiner.

Page 9 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 2 Page 6 of 6 Event

Description:

1A FDW Valve DP Signal Fails Low (I, OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1102/004 A Crew Response:

SRO/OATC OP/1/A/1102/004 A Encl 4.4 Section 2 2.12 IF desired, adjust CTP as follows: (R.M.)

2.12.1 Review current mechanical maneuvering rates per PT/0/A/1103/020 (Power Maneuvering Predictions).

2.12.2 IF desired to increase power, perform the following:

A. WHEN ICS has been in full Auto (Integrated Mode) for > 10 minutes, continue at Step 2.12.3. {6}

2.12.3 Ensure selected "HOLD".

2.12.4 Ensure desired setting selected ("%/MIN" or "%/HR") on "RATE" pushbuttons.

2.12.5 Ensure desired rate selected on "RATE SET" thumbwheels.

2.12.6 Insert desired CTPD SET using "INCREASE/DECREASE" pushbuttons.

2.12.7 Ensure "HOLD" is NOT selected.

2.12.8 WHEN desired CTP is achieved, return "RATE SET" thumbwheels to 0.0.

This event is complete when a valid Feedwater Valve DP input to ICS has been selected and ICS is returned to AUTO, or when directed by the lead examiner.

Page 10 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3 Page 1 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO)

Time Position Applicant's Actions or Behavior Plant Response:

1SA9/D-2 RC Pump Vibration High in alarm SRO/OATC

OAC 1B1 RCP VIB Alarm BOP 1SA9/D-2 Crew Response:

SRO will direct the BOP to refer to ARG 1SA-9/D-2 1SA-9/D-2 3.1 Use one of the following means to verify RCP vibration conditions:

Verify vibration reading on RCP OAC Display Group RCP.

IF the OAC is unavailable, verify the alarm by referring to RCP Vibration Monitoring Chart Recorder (ON1RCCR0430). (RCP Panel on 6th floor AHU Room)

NOTE: Vibration indication of both RCPs in a Loop trending up together without any changes to RCS conditions (Temp/Press) is a symptom of a Vibration Monitor power supply failure.

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: [Only 1 RCP experiencing vibrations] NA 3.3 IF MODE 1 or 2, initiate AP/1/A/1700/016 (Abnormal Reactor Coolant Pump Operation).

NOTE: Vibrations are expected to increase due to changing RCS temperature/pressure.

3.4 IF MODE 3, 4 or 5 AND vibration increase is NOT due to changing RCS temperature/pressure, initiate AP/1/A/1700/016 (Abnormal Reactor Coolant Pump Operation).

3.5 Monitor RCP parameters.

3.6 Contact PM2 Group for analysis of RCP parameters and to install additional monitoring equipment.

3.7 Initiate a CR for Engineering to document potential vibration effects on RCS Piping.

This event is complete when the 1B1 RCP is tripped, or when directed by the lead examiner.

Page 11 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3 Page 2 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/016 Crew Response:

SRO/OATC AP/1/A/1700/016 Abnormal Reactor Coolant Pump Operation Rev 33 BOP 4.1 IAAT any RCP meets immediate trip criteria of Encl 5.1 (RCP Immediate Trip Criteria), THEN perform Steps 4.2 - 4.11.

[Vibrations will NOT meet the immediate trip criteria]

RNO: GO TO Step 4.12.

NOTE If affected RCP has a seal failure, and immediate trip criteria not met, then continue to Section 4A (Seal Failure) to ensure Seal Failure guidance steps are read. Section 4A (Seal Failure) contains steps to quickly secure affected RCP should the need arise.

4.12 IAAT either of the following apply:

__ Any RCP approaching immediate trip criteria of Encl 5.1 (RCP Immediate Trip Criteria)

__ There is an immediate need to stop a RCP at this time THEN perform Steps 4.13 - 4.15.

RNO: GO TO Step 4.16.

Examiner Note: The SRO may decide to remove the RCP from service at this time and proceed to step 4.13. It they do not, they will proceed to Step 4.16 per the RNO (Page 16).

4.13 Verify Rx Power > 70%.

4.14 Initiate Encl 5.2 (Rapid Power Reduction). (Page 19) 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% as indicated 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.

This event is complete when the 1B1 RCP is tripped, or when directed by the lead examiner.

Page 12 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 3 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO)

Tc fails (I: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/016 Crew Response:

SRO/OATC BOP Booth Cue: If the crew does not secure the 1B1 RCP, call the control room as the SM and report that Engineering recommends securing the 1B1 RCP.

4.8 Verify FDW masters in Auto.

4.9 Stop the affected RCP.

4.10 Verify ICS re-ratios feedwater to establish desired Delta Tc.

Examiner Note: ICS will NOT re-ratio feedwater correctly, this is Event 4.

RNO:

1. Place DELTA Tc station in HAND.

2. Manually adjust DELTA Tc station to achieve desired Delta Tc.

Examiner Note: DELTA Tc controller will not function in HAND which will require the OATC to place both FDW Loop Masters in HAND to control DELTA Tc.

OATC CAUTION Total feedwater flow should be maintained constant to prevent changes in core reactivity.

3. IF DELTA Tc station does NOT control, THEN perform the following:

A. Place the following in HAND:

__ 1A FDW MASTER

__ 1B FDW MASTER B. Manually adjust FDW masters to achieve desired Delta Tc.

4. IF there has been a failure of the DELTA Tc controller, THEN notify SPOC to repair.

Examiner Note: If the crew does not re-ratio FDW soon enough, QPT may exceed the COLR values and require entry into TS 3.2.3 (Page 15) 4.11 GO TO Step 4.29.

Event 3 is complete when the 1B1 RCP is tripped, Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Page 13 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 4 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO)

Tc fails (I: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/016 Crew Response:

SRO/OATC 4.29 IAAT any of the following indicate external RCP seal leakage:

BOP __ RB RIAs increasing or in alarm

__ RCS Tave constant with LDST level decreasing more than normal

__ Quench Tank level rate increasing

__ RB Normal Sump rate increasing

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

4.30 Initiate Encl 4.3 (Special Instructions for < 4 RCP Operation) of OP/1/A/1102/004 (Operation at Power). (Page 20) 4.31 IAAT either of the following conditions is met:

__ a RCP has been shut down for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , {9}

__ a RCP with high oil level has been shut down THEN close the associated RCP motor cooler inlet/outlet valve:

__ 1LPSW-7&8 (1A1 RCP)

__ 1LPSW-9&10 (1B1 RCP)

__ 1LPSW-13&14 (1A2 RCP)

__ 1LPSW-11&12 (1B2 RCP) 4.32 IAAT either of the following has exceeded 260°F including transient situations:

__ O1A1253 - O1A1256 (RCP UPPER SEAL HOUSING TEMP)

__ O1A1910 - O1A1913 (RCP SEAL RETURN TEMP)

THEN closely monitor seal parameters for degradation until an Engineering evaluation is completed due to potential for seal ring and elastomer damage.

NOTE Operating experience has shown that failure of RC Pump components located internal to the RCS can create loose debris which can lead to fuel clad failures. These type RC Pump failures may cause Loose Parts Monitor alarms immediately and increased RCS radioactivity later.

4.33 Verify 1RIA 57 or 1RIA 58 have increased.

RNO: GO TO Step 4.35.

Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Page 14 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 5 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO)

Tc fails at (I: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/016 Crew Response:

SRO/OATC BOP 4.35 IAAT a RCP has been tripped due to exceeding Immediate Trip Criteria on a RCP motor, THEN contact RCP engineer prior to restart.

4.36 IAAT both are met:

__ There has been a failure of the DELTA Tc controller

__ The DELTA Tc controller has been repaired THEN initiate OP/1/A/1102/004 A Encl (Placing ICS Stations To Auto).

4.37 Verify any RCP that was shut down had a high vibration alarm.

4.38 Initiate a PIP for Engineering to document potential vibration effects on RCS piping.

4.39 WHEN conditions permit, THEN EXIT this procedure.

TS 3.10.1 STANDBY SHUTDOWN FACILITY (SSF), Once Reactor Power is reduced below 85% the SSF must be declared inoperable.

Conditions A-E (7 Days) Restore to operable status.

TS 3.2.3 QUADRANT POWER TILT (possible if operator does not re-ratio feedwater correctly).

Condition A:

(2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) Reduce THERMAL POWER > 2% RTP from the ALLOWABLE THERMAL POWER for each 1% of QPT greater than the steady state limit.

(10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months ) Reduce nuclear overpower trip setpoints, based on flux and flux/flow imbalance, 2% RTP for each 1% of QPT greater than the steady state limit.

(24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from discovery of failure to meet LCO) Restore QPT to less than or equal to the steady state limit.

Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Page 15 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 6 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO)

Tc fails at (I: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/016 Crew Response:

SRO/OATC Alternate Path from Step 4.12 BOP 4.16 Announce AP entry using the PA system.

4.17 Notify OSM to request evaluation by RCP Component Engineer.

4.18 IAAT the failure is identified, THEN GO TO the applicable section per the following table:

Section Failure 4B Abnormal Vibration Section 4B Abnormal Vibration

1. IAAT any RCP meets immediate trip criteria of Encl 5.1 (RCP Immediate Trip Criteria), THEN perform Steps 2 - 11.

RNO: GO TO Step 12. [RCP Vibrations will NOT reach trip criteria]

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

16. IAAT high vibration exists per statalarm 1SA-9/D-2, (RC PUMP VIBRATION HIGH) AND vibration continues to increase with the potential to exceed trip criteria THEN perform Steps 17 - 27.

RNO: GO TO Step 28.

17. Verify MODE 1 or 2.

Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Page 16 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 7 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO)

Tc fails at (I: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/016 Crew Response:

SRO/OATC BOP 18. Verify three RCPs will remain operating after affected RCP is tripped.

19. Verify Rx power is 70% as indicated on all NIs.

RNO: 1.__Direct an RO to initiate Encl 5.2 (Rapid Power Reduction)

(Page 19) 2.__WHEN Rx power is < 70% on all NIs, THEN continue this procedure.

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 Tc.

RNO:

1. __ Place DELTA Tc station in HAND.

2. __ Manually adjust DELTA Tc station to achieve desired Tc.

CAUTION Total feedwater flow should be maintained constant to prevent changes in core reactivity.

Examiner Note: ICS will NOT re-ratio feedwater correctly, this is Event 4.

3. __ IF DELTA Tc station does NOT control, THEN perform the following:

A. Place the following in HAND:

__ 1A FDW MASTER

__ 1B FDW MASTER B. __ Manually adjust FDW masters to achieve desired Tc.

4. __ IF there has been a failure of the DELTA Tc controller, THEN notify SPOC to repair.

26. Initiate Encl 4.3 (Special Instructions for < 4 RCP Operation) of OP/1/A/1102/004 (Operation at Power). (Page 20)

Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Page 17 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 8 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO)

Tc fails at (I: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/016 Crew Response:

SRO/OATC 27. Initiate the following notifications:

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

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

__ Notify SOC if load reduction was required.

__ Notify Chemistry to take RCS boron samples on a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months frequency.

NOTE Operating experience has shown that failure of RC Pump components located internal to the RCS can create loose debris which can lead to fuel clad failures. These type RC Pump failures may cause Loose Parts Monitor alarms immediately and increased RCS radioactivity later.

28. Verify 1RIA-57 or 1RIA-58 have increased.

RNO: GO TO Step 30.

30. IAAT an RCP has been shut down for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , THEN close the associated RCP motor cooler inlet/outlet valve:

__ 1LPSW-7&8 (1A1 RCP)

__ 1LPSW-9&10 (1B1 RCP)

__ 1LPSW-13&14 (1A2 RCP)

__ 1LPSW-11&12 (1B2 RCP)

31. IAAT a RCP has been tripped due to exceeding Immediate Trip Criteria on a RCP motor, THEN contact RCP engineer prior to restart.

32. IAAT both are met:

__ There has been a failure of the DELTA Tc controller

__ The DELTA Tc controller has been repaired THEN initiate OP/1/A/1102/004 A Encl (Placing ICS Stations To Auto).

33. Initiate a PIP for Engineering to document potential vibration effects on RCS piping.

34. WHEN conditions permit, THEN EXIT this procedure.

Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Page 18 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 9 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO)

Tc fails (I: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/016 Crew Response:

SRO/OATC Encl 5.2 Rapid Power Reduction BOP NOTE

This enclosure should be performed by an RO.

The step to verify ICS in AUTO means that the ICS is capable of responding to a MAXIMUM RUNBACK signal.

1. Verify ICS in AUTO.

2. Initiate MAXIMUM RUNBACK to 70%

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 1E1 and 1E2 HTR DRN PUMPs

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

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

9. EXIT this enclosure.

Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Page 19 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 10 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO)

Tc fails (I: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1102/004 Crew Response:

SRO/OATC OP/1/A/1102/004 OPERATIONS AT POWER, Encl 4.3 Special Instructions BOP For < 4 RCP Operations Rev 144 2.1 IF conditions permit, log the current quadrant power tilt and the position of the TC controller prior to securing a RCP during power operations.

NOTE:

Instructions for performing OAC trends are located in Working With Trends enclosure of OP/0/A/1103/020 A (Operator Aid Computer Use).

Only the first 6 points will be displayed initially; press "Page Down" key to see second 6 points.

2.2 Using turn-on code T6 3RCP, digitally trend the following data at one minute intervals:

Point ID Description O1P0889 CORE THERMAL POWER BEST O1P0877 INCORE IMBALANCE O1E3335 API GROUP AVE FOR GROUP 7 O1E3336 API GROUP AVE FOR GROUP 8 O1P0737 INCORE TILT QUADRANT W-X O1P0738 INCORE TILT QUADRANT X-Y O1P0739 INCORE TILT QUADRANT Y-Z O1P0740 INCORE TILT QUADRANT Z-W O1I0828 RC COLD LEG A1 TEMP O1I0829 RC COLD LEG A2 TEMP O1I0830 RC COLD LEG B1 TEMP O1I0831 RC COLD LEG B2 TEMP 2.3 After steady state conditions are attained, perform the following:

2.3.1 Check NI calibration.

2.3.2 IF NI calibration is NOT within requirements of Limit and Precaution Step 2.2.6, calibrate NIs to Thermal Power Best. (R.M.)

NOTE: The 100% Power Imbalance curves also apply for runs at reduced power.

2.4 Maintain Control Rod position and Power Imbalance within COLR limits.

Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Page 20 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 11 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO)

Tc fails (I: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1102/004 Crew Response:

SRO/OATC BOP NOTE: The Maximum Allowed Power Setpoint (Pmax) is reduced when operating for extended periods with a 3 RC Pump Configuration as a conservative action.

2.5 Perform the following:

2.5.1 IF expected to operate for an extended period of time with only 3 RCPs operating, notify I&E to adjust Flux/ Imbalance /Flow trip setpoints for 3 RCP operation per AM/1/A/0315/017 (TXS RPS Channels A, B, C, And D Parameter Changes For Abnormal/Normal Operating Conditions). (R.M.)

Person Notified Date 2.5.2 IF AT ANY TIME Quadrant Power Tilt problems exist, notify I&E to Adjust Flux/Imbalance/Flow trip setpoints as required to comply with TS 3.2.3 per AM/1/A/0315/017 (TXS RPS Channels A, B, C, And D Parameter Changes For Abnormal/Normal Operating Conditions). (R.M.)

Person Notified Date NOTE:

Operations Management/Reactor Engineering Group should be consulted for value to use for high flux alarm setpoint.

Instructions for Adjusting Alarm Setpoints On The NI Recorder are in OP/0/A/1108/001 (Curves And General Information).

2.6 Adjust high flux alarm setpoint per Operations Management/Reactor Engineering Group recommendations. (Alarm setpoint is adjusted on the NI Recorder). (R.M.)

NOTE: 'D' bleed pressure may NOT be high enough to run the FDWP turbines.

2.7 Maintain Auxiliary Steam available to the FDWP turbines.

2.8 IF 1SSH-9 (SSH DISCH CTRL BYPASS) is being used to control Steam Seal Header pressure, throttle 1SSH-9 as required to maintain desired SSH pressure during the load reduction to secure an RCP.

Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Page 21 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 3/4 Page 12 of 12 Event

Description:

1B1 RCP Hi Vib, Power reduction (C: BOP, SRO)

Tc fails (I: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1102/004 Crew Response:

SRO/OATC BOP NOTE:

RCS pressure decrease in the loop with two RCPs running is expected. This may cause acceptance criteria of PT/1/A/0600/001 (Periodic Instrument Surveillance) NOT to be met.

2.9 Place note on CR turnover sheet indicating the following:

"Be aware of the effect of the indicated pressure on the margin to trip setpoint for the Reactor Protective System trips associated with RCS pressure."

Event 4 is complete when the OATC adjusts DTc to within 0+2°F, or when directed by the lead examiner.

Page 22 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 5 Page 1 of 4 Event

Description:

1HP-14 fails to BLEED (C: BOP, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/002 Plant Response:

OAC alarm: 1HP-14 = BLEED

OAC alarm: 1HP-14 LDST BYPASS (NOT NORMAL)

1SA-2/B1 LDST LEVEL HI/LOW may actuate if operators are slow to recognize the failure.

Crew Response:

SRO/BOP The SRO should initiate AP/1/A/1700/002 (Excessive RCS Leakage)

AP/1/A/1700/002 (Excessive RCS Leakage) Rev 015 3.1 Verify HPI operating 3.2 IAAT RC makeup flow is > 100 gpm, AND Pzr level is decreasing, THEN close 1HP-5 Examiner Note: If 1HP-5 is closed , Encl 5.5 will used to re-open when required.

3.3 IAAT all the following exist: (N/A)

__ RCS leakage > 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 NOTE Other than a SGTR, 1HP-26 should NOT need to be opened with the reactor critical.

4.1 Initiate Pzr and LDST level makeup using Unit 1 EOP Encl 5.5 as necessary. (Page 46) 4.2 Announce AP entry using PA system 4.3 IAAT LPI DHR in service, AND RCS leakage > LDST makeup capability

( 50 gpm), THEN GO TO AP/26 (N/A)

Event 5 is complete when the standby HPI pump switch is returned to AUTO, or as directed by the Lead Examiner.

Page 23 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 5 Page 2 of 4 Event

Description:

1HP-14 fails to BLEED (C: BOP, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/002 Crew Response:

4.4 Initiate the following notifications:

__ OSM to reference the following:

RP/0/A/1000/001 (Emergency Classification)

OMP 1-14 (Notifications)

SRO/BOP

Encl 5.9 (Oversight Guidelines)

__ STA

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

__ T6 AP/02

__ T6 WASTE

__ RIAs 4.6 Verify specific leak location is identified 4.7 Initiate Encl 5.1 (Leak Rate Determination)

Leak Rate = _____ + _____ - _____ - _____ = _____

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

Area/ Symptoms Step Failure 1HP-14 1HP-14 failed in BLEED position 4.155 failure LDST level 1A BHUT level 4.155 Verify 1A LD Filter in service RNO: 1. IF 1A LD Filter is out of service for maintenance, THEN restore 1A LD Filter per in progress procedure (N/A)

2. Open 1HP-17 4.156 Close 1HP-6 Event 5 is complete when the standby HPI pump switch is returned to AUTO, or as directed by the Lead Examiner.

Page 24 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 5 Page 3 of 4 Event

Description:

1HP-14 fails to BLEED (C: BOP, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/002 Crew Response:

NOTE Tech Spec 3.4.9 applies when indicated Pzr level > 260" (corrected value for 285")

4.157 Adjust 1HP-7, as needed, to control:

SRO/BOP

BLEED flow out of failed 1HP-14

Pzr level 4.158 Dispatch an operator to open 1HP-196 (Filter Diversion Inlet) (A-2-LDST Hatch Area) 4.159 Verify CC system in operation 4.160 Position the standby HPI pump switch to OFF 4.161 Initiate monitoring RCP parameters 4.162 Throttle 1HP-31 to establish 12 - 15 gpm SEAL INLET HDR FLOW Booth Cue: When directed to open 1HP-196, use MAN VALVES to open, and notify crew that `HP-196 is open.

4.163 WHEN 1HP-196 (Filter Diversion Inlet) is open, THEN close 1CS-26 4,164 Close the following:

__ 1CS-27

__ 1CS-32 & 37 4.165 Open 1HP-6 4.166 Throttle 1HP-31 to establish 32 gpm SEAL INLET HDR FLOW 4.167 Adjust 1HP-7 to establish desired letdown flow 4.168 Position standby HPI pump switch to AUTO 4.169 WHEN 1HP-14 has been repaired, THEN perform the following:

A. Ensure 1HP-14 in NORMAL B. Open 1HP-26 C. Ensure HPI valves are aligned such that a letdown path will be present after 1HP-196 is closed D. Close 1HP-196 Examiner Note: 1HP-14 will NOT be repaired.

Event 5 is complete when the standby HPI pump switch is returned to AUTO, or as directed by the Lead Examiner.

Page 25 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 5 Page 4 of 4 Event

Description:

1HP-14 fails to BLEED (C: BOP, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/039 Crew Response:

Examiner Note: AP/39 (Unintentional Boration) may be entered if 1HP-24 and/or 1HP-25 is opened to mitigate a suspected leak (1HP-14 failing to bleed).

AP/1/A/1700/039 Unintentional Boration Rev 2 SRO/BOP CAUTION Do NOT add demin water to counter the boration until RCS boron concentration stabilizes to prevent a positive reactivity event.

4.1 Announce AP entry using PA system.

4.2 IAAT CTP < 6%, THEN perform the following:

A. __ Trip the Rx.

B. __ GO TO Unit 1 EOP.

4.3 IAAT all the following exist:

__ ICS is in Automatic

__ Control rods approach upper limit of desired operating band THEN perform the following:

A. __ Establish desired shutdown rate.

B. __ Decrease CTP demand setpoint, as necessary.

C. Adjust shutdown rate, as necessary, to maintain control rods within the desired band.

4.4 IAAT all the following exist:

__ ICS is in Manual

__ Tave is outside the control band THEN manually adjust FDW, as necessary, to maintain Tave within the control band until both SGs are on Low Level Limits.

4.5 IAAT a power decrease is initiated, THEN initiate Encl 5.1 (Unit Shutdown Support Actions).

4.6 Take action to identify and terminate the boration, as necessary.

4.7 Verify the source of the boration has been identified and terminated.

Event 5 is complete when the standby HPI pump switch is returned to AUTO, or as directed by the Lead Examiner.

Page 26 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 6 Page 1 of 8 Event

Description:

20 gpm Pri-Sec leak in 1B SG requires Manual S/D (R: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/031 Plant Response:

1SA-8/A-9 (RM AREA MONITOR RADIATION HIGH)

1SA-8/E-10 (N-16 RM PRIMARY TO SECONDARY TUBE LEAK)

1SA-8/D-10 (RM CSAE EXHAUST RADIATION HIGH)

1SA-8/B-9 (RM PROCESS MONITOR RADIATION HIGH)

1RIA-40 in alarm

1RIA 60 in alarm and indicating 20 gpm Crew Response:

SRO OATC/BOP SRO will enter AP/1/A/1700/031 Primary To Secondary Leakage Rev 21 AP/1/A/1700/031 NOTE The total primary to secondary leak rate can be determined by the following means:

OAC point O1P1599 (EST TOTAL PRI TO SEC LEAKRATE) if OAC primary to secondary leak rate calculation available (including 1RIA-40 operable with CSAE OFF-GAS BLOWER operating).

Sum of 1RIA-59 and 1RIA-60 readings if both operable and reactor power >

40%.

Allowable leakage per Tech Spec 3.4.13 is 150 gpd through any one SG.

Estimated SGTR leak rate formula:

Leak rate = ____ + ____ - ____ - ____ = ____

MU SI LD TSR Where:

MU = Makeup Flow SI = Seal Inlet Hdr Flow LD = Letdown TSR = Total Seal Return Flow If the EOP is NOT already in progress, entry will be directly to the SGTR tab.

RIA-59 / 60 and RIA-16 / 17 on the unaffected SG may indicate up to 2 % of the value of the detector on the affected SG due to radiation shine from the steam line carrying radioactive steam from the SG with the tube leak.

This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the lead examiner.

Page 27 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 6 Page 2 of 8 Event

Description:

20 gpm Pri-Sec leak in 1B SG requires Manual S/D (R: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/031 Crew Response:

SRO 4.1 IAAT primary to secondary leak rate is 25 gpm ( 36,000 gpd), THEN OATC/BOP GO TO Unit 1 EOP.

4.2 IAAT either of the following exists for 1RIA-54:

__ is in High alarm

__ inoperable THEN perform Steps 4.3 - 4.4.

NOTE The white tags can be created and hung after the TBS pump breakers are opened.

4.3 Dispatch an operator to open and white tag the following:

__ 1XD-R3C (1A TURBINE BUILDING SUMP PUMP BKR)

__ 1XE-R3D (1B TURBINE BUILDING SUMP PUMP BKR) 4.4 Notify Secondary Chemistry to perform the following:

__ Obtain a TBS sample.

__ Recommend TBS release path.

4.5 Initiate notification of the following:

__ OSM to reference the following:

OMP 1-14 (Notifications)

Emergency Plan

__ STA NOTE 1RIA-59 and 1RIA-60 are considered inoperable below 40% power.

4.6 IAAT notified by Chemistry that 1RIA-40 is inoperable because the minimum detection limit is too high, AND 1RIA-59 or 1RIA-60 is inoperable, THEN perform Encl 5.9 (1RIA-40 Inoperable Due to Failure to Meet Minimum Detectable Limit).

4.7 IAAT primary to secondary leakage exceeds 30 gpd, THEN perform Steps 4.8 - 4.9.

[Pri-Sec leak rate 21 gpm]

This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the lead examiner.

Page 28 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 6 Page 3 of 8 Event

Description:

20 gpm Pri-Sec leak in 1B SG requires Manual S/D (R: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/031 Crew Response:

SRO 4.8 Dispatch AO to reroute Unit 1 CSAE drains to the CST per OATC/BOP OP/1-2/A/1106/016 (Condenser Vacuum System).

4.9 Initiate Encl 5.2 (Reduction of Secondary Leakage and Cross-Unit Contamination).

4.10 IAAT tube leakage is large enough to be indicated by an increase in normal RC makeup flow or a decrease in Pzr level, THEN GO TO Step 4.86.

4.86 Verify OAC primary to secondary leak rate calculation available (including 1RIA-40 operable with CSAE OFFGAS BLOWER operating).

4.87 Determine primary to secondary leakage rate using OAC point O1P1599 (EST TOTAL PRI TO SEC LEAK RATE).

4.88 GO TO Step 4.93.

4.93 Initiate log readings from the following every 15 minutes in the Auto Log:

1RIA-16

1RIA-17

1RIA-40

1RIA-59 (when Rx power > 40 %)

1RIA-60 (when Rx power > 40 %)

4.94 Initiate a unit shutdown to meet requirements of Encl 5.1 (Unit Shutdown Requirements) using the following, as applicable:

AP/29 (Rapid Unit Shutdown) (Page 31)

OP/1/A/1102/004 (Operation at Power)

OP/1/A/1102/010 (Controlling Procedure for Unit Shutdown)

Booth Cue: If asked, Unit 2 will continue actions in AP/31 4.95 IAAT primary to secondary leakage increases, THEN modify shutdown as required by Encl 5.1 (Unit Shutdown Requirements).

4.96 Notify OSM to refer to Tech Spec. 3.10.1 Basis to determine SSF operability.

This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the lead examiner.

Page 29 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 6 Page 4 of 8 Event

Description:

20 gpm Pri-Sec leak in 1B SG requires Manual S/D (R: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/031 Crew Response:

SRO 4.97 Notify plant personnel, using the PA system, to stay clear of the affected OATC/BOP MS line and the powdex.

4.98 Notify Radwaste to stop all liquid releases in progress until sample results assures release rates within limits.

4.99 Stop all gaseous releases in progress until sample results assure release rates within limits.

4.100 IAAT all the following exist:

__ Primary to secondary leak rate < 100 gpd (< 0.0694 gpm)

__ 1RIA-40 inoperable

__ Rx Power 40 %

THEN notify RP and Primary Chemistry to sample CSAE off-gas and RCS every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.101 Make up to the UST only as necessary to maintain UST level > 7.5 '.

4.102 Notify the following that a shutdown is in progress due to primary to secondary leakage:

__ RP

__ Primary Chemistry

__ Secondary Chemistry 4.103 Verify affected SG identified.

4.104 Verify entry into this procedure was due to one of the following:

__ Tube leakage large enough to be indicated by an increase in normal RC makeup flow or a decrease in Pzr level

__ Tritium sample indicating 75 gpd primary to secondary leak TS 3.4.13 RCS OPERATIONAL LEAKAGE, Condition B due to Primary to Secondary LEAKAGE not within limit (12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s/36 hours) Be in Mode 3 / Mode 5.

This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the lead examiner.

Page 30 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 6 Page 5 of 8 Event

Description:

20 gpm Pri-Sec leak in 1B SG requires Manual S/D (R: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/029 Crew Response:

SRO AP/1/A/1700/029 Rapid Unit Shutdown Rev 13 OATC/BOP NOTE The CR SRO should read this procedure and it should NOT be used when EOP entry conditions exist.

4.1 Initiate Encl 5.1 (Support Actions During Rapid Unit Shutdown) (Page 33) 4.2 Announce AP entry using the PA system 4.3 IAAT both of the following apply:

__ It is desired to stop power decrease

__ CTP > 18 %

THEN perform Steps 4.4 - 4.7 RNO: GO TO Step 4.8 4.4 Verify ICS in AUTO RNO: 1. Stop manual power reduction

2. GO TO Step 4.6 NOTE Due to the power decrease initiated in this AP, the current plant configuration must be compared to the normal plant configuration in OP/1/A/1102/004 (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.

4.6 Initiate OP/1/A/1102/004 (Operation at Power) power reduction enclosure 4.7 WHEN conditions permit, THEN perform one of the following:

__ Depress MAXIMUM RUNBACK to resume power reduction

__ GO TO appropriate operating procedure for continued operation 4.8 Verify ICS in AUTO RNO: 1. Initiate manual power reduction to desired power level

2. GO TO Step 4.10 This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the lead examiner.

Page 31 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 6 Page 6 of 8 Event

Description:

20 gpm Pri-Sec leak in 1B SG requires Manual S/D (R: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/029 Crew Response:

SRO 4.10 Verify both Main FDW pumps running.

OATC/BOP NOTE

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

To lower 1B 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 Suction flow is 1 x 106 lbm/hr less than remaining Main FDW pump suction flow.

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

Examiner Note: Power should already be < 70% due to the power reduction to remove a RCP from service.

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

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

__ Any of the following alarms actuate and remain in alarm:

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

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

THEN trip 1B Main FDW Pump.

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

__ 1A Main FDW Pump is first pump to be shut down

__ Any of the following alarms actuate and remain in alarm:

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

FWP A FLOW BELOW MIN (1SA-16/A-2)

THEN trip 1A Main FDW Pump.

4.15 Verify Turbine-Generator shutdown is required.

4.16 Start the TURBINE TURNING GEAR OIL PUMP.

This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the lead examiner.

Page 32 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 6 Page 7 of 8 Event

Description:

20 gpm Pri-Sec leak in 1B SG requires Manual S/D (R: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/029 Crew Response:

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

OATC/BOP 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.

4.21 __ WHEN NI power 18%, THEN depress turbine TRIP pushbutton.

4.22 __ Verify all TURBINE STOP VALVES closed.

Enclosure 5.1 Support Actions During Rapid Unit Shutdown

1. Notify WCC SRO to initiate Encl 5.2 (WCC SRO Support During Rapid Unit Shutdown).

2. Start the following pumps:

__ 1A FDWP SEAL INJECTION PUMP

__ 1A FDWP AUXILIARY OIL PUMP

__ 1B FDWP AUXILIARY OIL PUMP

__ 1B FDWP SEAL INJECTION PUMP

3. WHEN CTP is 80%, THEN continue.

4. Stop 1E1 HTR DRN PUMP.

5. Place 1HD-254 switch to OPEN.

6. Stop 1E2 HTR DRN PUMP.

7. Place 1HD-276 switch to OPEN.

This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the lead examiner.

Page 33 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 6 Page 8 of 8 Event

Description:

20 gpm Pri-Sec leak in 1B SG requires Manual S/D (R: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/029 Crew Response:

8. Verify Turbine-Generator shutdown is required.

OATC/BOP

9. Place the following transfer switches to MAN:

__ 1TA AUTO/MAN

__ 1TB AUTO/MAN

10. Close 1TA SU 6.9 KV FDR.

11. Verify 1TA NORMAL 6.9 KV FDR opens.

12. Close 1TB SU 6.9 KV FDR.

13. Verify 1TB NORMAL 6.9 KV FDR opens.

14. Place the following transfer switches to MAN:

__ MFB1 AUTO/MAN

__ MFB2 AUTO/MAN

15. Close E11 MFB1 STARTUP FDR.

16. Verify N11 MFB1 NORMAL FDR opens.

17. Close E21 MFB2 STARTUP FDR.

18. Verify N21 MFB2 NORMAL FDR opens.

19. Notify CR SRO that Unit auxiliaries have been transferred.

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

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

__ 1FDW-65

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

This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the lead examiner.

Page 34 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 1 of 10 Event

Description:

1TA Lockout, 1B SGTR (M: All)

Time Position Applicant's Actions or Behavior EOP Plant Response:

Rx Trip

1SA-8/B-9 RM Process Monitor Radiation High

1SA8/D10 (RM CSAE EXHAUST RADIATION HIGH)

Crew Response:

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

SRO IMAs EOP Immediate Actions Rev 40 OATC 3.1 Depress REACTOR TRIP pushbutton.

3.2 Verify reactor power < 5% FP and decreasing.

3.3 Depress the turbine TRIP pushbutton 3.4 Verify all turbine stop valves closed.

3.5 Verify RCP seal injection available.

SYMPTOM CHECK The BOP will verify the following:

Power Range NIs NOT < 5% Rule 1, ATWS/Unanticipated Nuclear Po Power Range NIs NOT decreasing Production BOP Any SCM < 0°F Rule 2, Loss Of SCM Loss of Main and Emergency FDW Rule 3, Loss of Main or Emerg FDW (including unsuccessful manual initiation of Rule 4, Initiation of HPI Forced Cooling EFDW) (Inability to feed SGs and > 2300 psig, N limit reached, or PZR level > 375")

Uncontrolled Main steam line(s) pressure Rule 5, Main Steam Line Break decrease CSAE Offgas alarms None (SGTR Tab is entered when identif Process monitor alarms (RIA-40, 59,60), SG Tube Leakage > 25 gpm)

Area monitor alarms (RIA-16/17)

SRO will review IMAs and transfer to the Subsequent Actions Tab.

This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Page 35 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 2 of 10 Event

Description:

1TA Lockout, 1B SGTR (M: All)

Time Position Applicant's Actions or Behavior Subsequent Actions Tab Crew Response:

SRO Examiner Note: The crew may not recognize the SGTL has degraded into a OATC/BOP SGTR initially so steps in the SA tab were included. When the crew recognizes the SGTR, they should transfer to the SGTR tab (Page 39) as directed by the Subsequent Actions, Parallel Action Page (Page 54).

4.1 Verify all control rods in Groups 1 - 7 fully inserted.

4.2 Verify Main FDW in operation.

4.3 Verify either:

__ Main FDW overfeeding causing excessive temperature decrease.

__ Main FDW underfeeding causing SG level decrease below setpoint.

RNO: __ GO TO Step 4.5.

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

RNO: __ GO TO Step 4.9.

4.9 IAAT TBVs CANNOT control SG pressure at desired setpoint, AND TBVs NOT intentionally isolated, THEN manually control pressure in affected SGs using either:

__ TBVs

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

Examiner Note: The 1A TBVs have failed closed in AUTO. They can be operated in MANUAL.

4.10 Verify 1RIA-40 operable with CSAE OFF-GAS BLOWER operating.

4.11 GO TO Step 4.14.

4.14 Verify both are closed:

__ 1MS-17

__ 1MS-26 This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Page 36 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 3 of 10 Event

Description:

1TA Lockout, 1B SGTR (M: All)

Time Position Applicant's Actions or Behavior Subsequent Actions Tab Crew Response:

SRO 4.15 Verify ES is required.

OATC/BOP RNO: 1. __ Initiate Encl 5.5 (Pzr and LDST Level Control).(Page 46)

2. __ GO TO Step 4.17.

4.17 Open:

__ PCB 20

__ PCB 21 4.18 Verify Generator Field Breaker open.

4.19 Verify EXCITATION is OFF.

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

4.21 Verify ICS/NNI power available.

4.22 Verify all 4160V switchgear (1TC, 1TD & 1TE) energized.

4.23 Verify both SGs > 550 psig.

4.24 Verify Main FDW operating.

4.25 Verify any RCP operating.

4.26 Verify AP/0/A/1700/025 (SSF EOP) Encl (Unit 1 OATC Actions During Fire) in progress or complete.

RNO: Ensure SGs approaching 25 - 35 [55 - 65 acc] S/U level.

4.27 Place switches in CLOSE:

__ 1FDW-31

__ 1FDW-40 4.27 Place switches in CLOSE:

__ 1FDW-31

__ 1FDW-40 This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Page 37 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 4 of 10 Event

Description:

1TA Lockout, 1B SGTR (M: All)

Time Position Applicant's Actions or Behavior Subsequent Actions Tab Crew Response:

SRO 4.28 Verify SFP Cooling: {42}

OATC/BOP __ SFP Cooling in service

__ SFP level normal 4.29 Verify all SCMs > 0°F.

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

RNO: __ GO TO Step 4.32.

4.32 Verify heat transfer exists.

4.33 Verify primary to secondary heat transfer has been excessive.

RNO: __ GO TO Step 4.35.

4.35 Verify indications of SGTR 25 gpm.

4.36 GO TO SGTR tab.

Examiner Note: The crew should recognize that the SGTL has degraded to a SGTR at this point.

This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Page 38 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 5 of 10 Event

Description:

1TA Lockout, 1B SGTR (M: All)

Time Position Applicant's Actions or Behavior SGTR Tab Crew Response:

SRO OATC/BOP 1. Verify Rx tripped.

2. Maintain Pzr level 140 - 180 [175 - 215 acc] by initiating Encl 5.5 (Pzr and LDST Level Control). (Page 46)

Examiner Note: 1HP-26 has failed in the closed position.

3. Ensure Parallel Actions Page reviewed.

NOTE The remainder of this page may be given to an RO. The Procedure Director may continue.

4. Start:

__ A OUTSIDE AIR BOOSTER FAN CT-1 __ B OUTSIDE AIR BOOSTER FAN

5. Notify Unit 3 to start:

__ 3A OUTSIDE AIR BOOSTER FAN

__ 3B OUTSIDE AIR BOOSTER FAN

6. Perform the following:

A. __ Monitor RIAs 16 and 17 to identify all SGs with a tube rupture.

B. __ Inform SRO of results.

7. Dispatch an operator to open:

__ 1XD-R3C (A Turb Bldg Sump Pump Bkr) (T-1, G-27)

__ 1XE-R3D (B Turb Bldg Sump Pump Bkr) (T-1, J-27)

8. Notify RP to survey both MS lines for radiation.

9. GO TO Step 28.

This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Page 39 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 6 of 10 Event

Description:

1TA Lockout, 1B SGTR (M: All)

Time Position Applicant's Actions or Behavior SGTR Tab Crew Response:

28. Secure any unnecessary offsite release paths. (Main Vacuum Pumps, OATC/BOP TDEFDWP, Emergency Steam Air Ejector, etc.).

29. Verify Main FDW or EFDW controlling properly.

30. Open:

__ 1HP-24

__ 1HP-25

31. Secure makeup to LDST.

32. Maintain both SG pressures < 950 psig using either:

__ TBVs

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

Examiner Note: 1A TBVs have tripped to HAND.

33. IAAT all the following exist:

__ All SCMs > 0°F

__ ES Bypass Permit satisfied

__ RCS pressure controllable THEN perform Steps 34 - 35.

34. Bypass applicable ES:

To Bypass HPI:

__ Bypass HPI CH A, B, C To Bypass LPI:

__ Bypass LPI CH A, B, C

35. Bypass applicable Diverse ES:

To Bypass HPI:

__ Bypass Diverse HPI To Bypass LPI:

__ Bypass Diverse LPI This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Page 40 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 7 of 10 Event

Description:

1TA Lockout, 1B SGTR (M: All)

Time Position Applicant's Actions or Behavior SGTR Tab Crew Response:

SRO NOTE OATC/BOP Leak rate prior to reducing SCM is input to Cool Down Plateau at Steps 103 and 203.

36. Estimate SGTR leak rate:

_____ + _____ - _____ - _____ = _____ gpm MU SI LD TSR LR Where: MU =Makeup Flow SI =Seal Inlet Hdr Flow LD =Letdown Flow TSR =Total Seal Return Flow LR =Leak Rate

37. Verify any RCP operating.

38. Maintain RCP NPSH during the reduction of SCM:

OAC

Encl 5.18 (P/T Curves)

NOTE

If normal pzr spray is available, efforts should be made to minimize core SCM 15°F IF allowed by RCP NPSH requirements.

If normal pzr spray is NOT available, minimize core SCM as low as safely achievable.

39. Reduce and maintain core SCM at minimum using any/all of the following methods:

__ De-energize all Pzr heaters

__ Use Pzr spray

__ Maintain Pzr level 140 - 180 [175 - 215 acc]

This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Page 41 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 8 of 10 Event

Description:

1TA Lockout, 1B SGTR (M: All)

Time Position Applicant's Actions or Behavior SGTR Tab SRO Crew Response:

OATC/BOP NOTE

The rate of fill of the SG with the tube rupture should be considered when deciding to use alternate depressurization methods.

Pzr spray, if available, is preferred to maintain SCM at minimum after using the PORV. This will prevent repetitive cycling of the PORV.

40. IAAT RCS de-pressurization methods are inadequate in minimizing core SCM, THEN perform Step 40 - 42.

NOTE BWST temperature should be used in determining Pzr spray nozzle T.

Computer point O1P3367 provides Pzr spray nozzle T information.

41. Verify Pzr spray nozzle T 410°F.

42. Close:

__ 1LWD-1

__ 1LWD-2

43. Cycle PORV as necessary.

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

RNO: __ Select OFF for both digital channels on AFIS HEADER A.

45. Verify 1SA-2/D-8 (AFIS HEADER B INITIATED) lit.

RNO: __ Select OFF for both digital channels on AFIS HEADER B.

46. Verify RCS temperature > 532°F.

NOTE Close monitoring of RCS pressure is essential during the cooldown if ES has not been bypassed. Slowing the cooldown and stopping Pzr spray momentarily may be needed as ES Bypass Permit is approached to avoid ES actuation.

This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Page 42 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 9 of 10 Event

Description:

1TA Lockout, 1B SGTR (M: All)

Time Position Applicant's Actions or Behavior SGTR Tab Crew Response:

47. Initiate a cooldown as follows:

OATC/BOP __ Decrease SG pressure to 835 - 845 psig using any of the following:

TBV setpoint adjusted to 710 - 720 psig

TBVs in manual

ADVs

__ Maximize cooldown rate limited only by the ability to maintain Pzr level

> 100 [180 acc].

48. WHEN SG pressure is 835 - 845 psig, THEN adjust SG pressure as necessary to maintain an RCS temperature band of 525°F - 532°F.

49. IAAT any affected SG approaches overfill:

Any SCM 0°F: LOSCM setpoint

All SCMs > 0°F: 285 [315 acc] XSUR THEN perform Steps 49 - 51.

RNO: __ GO TO Step 52.

50. Verify TBVs available for steaming affected SGs.

51. Open on all affected SGs:

1A SG 1B SG 1MS-17 1MS-18 NOTE Steaming a SG to prevent overfill should continue even if Tech Spec cooldown rates are exceeded.

52. Steam affected SGs to prevent overfill.

53. Verify at least one open:

__ 1MS-24

__ 1MS-33 This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Page 43 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 3 Event No.: 7 Page 10 of 10 Event

Description:

1TA Lockout, 1B SGTR (M: All)

Time Position Applicant's Actions or Behavior SGTR Tab Crew Response:

54. Verify a SG without a tube leak is available to supply the Aux Steam OATC/BOP header.

55. Open on the SG without a tube leak:

1A SG 1B SG 1MS-24 1MS-33

56. Close on the SG with a tube leak:

1A SG 1B SG 1MS-24 1MS-33

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

58. Close on all affected SGs:

1A SG 1B SG 1MS-79 1MS-76 1MS-82 1MS-84 1MS-35 1MS-36

59. Close 1SSH-9.

60. Verify one SG isolated due to steam leak.

RNO: __GO TO Step 68.

68. Verify all SCMs > 0°F.

69. GO TO applicable step based on number of RCPs operating:

Number of RCPs Applicable Operating Step 4 69 1,2 or 3 70 None 90

71. Verify steaming both SGs.

RNO: __ GO TO Step 87.

87. Initiate AP/31 (Primary to Secondary Leakage) Encl 5.2 (Reduction of Secondary Leakage and Cross-Unit Contamination).

This event is complete when the crew minimizes core SCM, or when directed by the lead examiner.

Page 44 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Rule 6 HPI HPI Pump Throttling Limits

HPI must be throttled to prevent violating the RV-P/T limit.

HPI pump operation must be limited to two HPIPs when only one BWST suction valve (1HP-24 or 1HP-25) is open.

HPI must be throttled 475 gpm/pump (including seal injection for A header) when only one HPI pump is operating in a header.

Total HPI flow must be throttled 950 gpm including seal injection when 1A and 1B HPI pumps are operating with 1HP-409 open.

Total HPI flow must be throttled < 750 gpm when all the following exist:

- LPI suction is from the RBES

- piggyback is aligned

- either of the following exist:

only one piggyback valve is open (1LP-15 or 1LP-16)

only one LPI pump operating

HPI may be throttled under the following conditions:

HPI Forced Cooling in Progress: HPI Forced Cooling NOT in Progress:

All the following conditions must exist: All the following conditions must exist:

Core SCM > 0

All WR NIs 1%

CETCs decreasing

Core SCM > 0

Pzr level increasing

SRO concurrence required if throttling following emergency boration HPI Pump Minimum Flow Limit

Maintain 170 gpm indicated/pump. This is an instrument error adjusted value that ensures a real value of 65 gpm/pump is maintained. HPI pump flow less than minimum is allowed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Page 45 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control 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 IF 1HP-26 will NOT open, maintain desired Pzr level: THEN throttle 1HP-410 to maintain

1A HPI Pump desired Pzr level.

1B HPI 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 1A BHUT, THEN perform the following:

A. Open:

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

C. Notify SRO.

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

Page 46 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control 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 1B LPI PUMP.

C. Open:

1LP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D. IF two LPI Pumps are running only 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, U1 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 1B 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 47 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

8. Start 1C HPI PUMP. IF at least two HPI pumps are operating, THEN throttle 1HP-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 1HP-26 will NOT open, 1HP-26 THEN throttle 1HP-410 to maintain desired Pzr level.

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

Page 48 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED 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 1HP-24. (1HP-24 and 1HP-25) are closed, THEN perform the following:

Open 1HP-25.

Close 1HP-16. A. Start 1A LPI PUMP.

B. Start 1B LPI PUMP.

C. Open:

1LP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D. IF two LPI Pumps are running only 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, U1 LPI Hatch Rm, N end).

F. GO TO Step 13.

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

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

12.__ Operate Pzr heaters as required to maintain heater bundle integrity.

Page 49 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

13. 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-1-107, Unit 1 RC Bleed Transfer Pump Rm.).

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

Open 1HP-17.

Open 1HP-18

15. IAAT all of the following exist: GO TO Step 35.

Letdown isolated LPSW available Letdown restoration desired THEN perform Steps 16 - 34. {41}

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

2. GO TO Step 35.

17. Ensure only one CC pump running.

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

19. Verify both are open: 1. IF 1HP-1 is closed due to 1HP-3 failing to 1HP-1 close, 1HP-2 THEN GO TO Step 21.

2. IF 1HP-2 is closed due to 1HP-4 failing to close, THEN GO TO Step 21.

20. GO TO Step 23.

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

21. Verify letdown line leak in East GO TO Step 23.

Penetration Room has occurred.

22. GO TO Step 35.

Page 50 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

23. Monitor for unexpected conditions while restoring letdown.

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

1HP-1 1HP-3

2. IF 1B letdown cooler is to be placed in service, THEN open:

1HP-2 1HP-4

3. GO TO Step 26.

25. Open:

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

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

aligned.

A. Notify CR SRO of problem.

B. GO TO Step 35.

27. Close 1HP-6.

28. Close 1HP-7.

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

2. Close:

1HP-8 1HP-9&11

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

A. Select 1HP-14 to NORMAL.

B. Close 1HP-16.

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

Page 51 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

30. Open 1HP-5.

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

32. WHEN letdown temperature is

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

33. Open 1HP-6.

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

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

35. 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).

36. 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.

37. 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 52 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

38. Verify 1CS-48 (1A BHUT Recirc) has GO TO Step 40.

been closed to provide additional makeup flow to LDST.

39. 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 1CS-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.

40. Verify two Letdown Filters in service, GO TO Step 42.

AND only one Letdown filter is desired.

41. Perform one of the following:

Place 1HP-17 switch to CLOSE.

Place 1HP-18 switch to CLOSE.

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

Page 53 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Subsequent Actions EP/1/A/1800/001 Parallel Actions Page 1 of 1 CONDITION ACTIONS

1. PR NIs 5% FP OR GO TO UNPP tab. UNPP NIs NOT decreasing

2. All 4160V SWGR de-energized GO TO Blackout tab. BLACKOUT

{13}

3. Core SCM indicates superheat GO TO ICC tab. ICC

4. Any SCM = 0°F GO TO LOSCM tab. LOSCM

5. Both SGs intentionally isolated to GO TO EHT tab.

stop excessive heat transfer

6. Loss of heat transfer (including LOHT loss of all Main and Emergency GO TO LOHT tab.

FDW)

7. Heat transfer is or has been GO TO EHT tab. EHT excessive

8. Indications of SGTR 25 gpm GO TO SGTR tab. SGTR

9. Turbine Building flooding NOT GO TO TBF tab. TBF caused by rainfall event

10. Inadvertent ES actuation occurred Initiate AP/1/A/1700/042 (Inadvertent ES ES Actuation).

11. Valid ES actuation has occurred Initiate Encl 5.1 (ES Actuation). ES or should have occurred

12. Power lost to all 4160V SWGR

Initiate AP/11 (Recovery from Loss and any 4160V SWGR of Power).

re-energized ROP

IF Encl 5.1 (ES Actuation) has been initiated, THEN reinitiate Encl 5.1.

13. RCS leakage > 160 gpm with Notify plant staff that Emergency Dose EDL letdown isolated Limits are in affect using PA system.

14. Individual available to make

Announce plant conditions using notifications PA system.

Notify OSM to reference the NOTIFY Emergency Plan and NSD 202 (Reportability).

Page 54 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam SGTR EP/1/A/1800/001 Parallel Actions Page 1 of 1 CONDITION ACTIONS

1. AFTER Rx trip pushbutton Depressed:

PR NIs 5% FP GO TO UNPP tab. UNPP OR NIs NOT decreasing

2. All 4160V SWGR de-energized GO TO Blackout tab. BLACKOUT

{13}

3. Core SCM indicates superheat GO TO ICC tab. ICC

4. Any SCM = 0°F, AND HPI forced IF NOT previously performed, THEN LOSCM cooling NOT in progress GO TO LOSCM tab.

5. Both SGs intentionally isolated to GO TO EHT tab.

stop excessive heat transfer

6. Loss of heat transfer LOHT GO TO LOHT tab.

7. Heat transfer is or has been GO TO EHT tab. EHT excessive

8. Indications of SGTR in another SG RETURN TO beginning of SGTR tab. SGTR after SGTR tab initiated

9. Inadvertent ES actuation occurred Initiate AP/1/A/1700/042 (Inadvertent ES Actuation). ES

10. Valid ES actuation has occurred or Initiate Encl 5.1 (ES Actuation). ES should have occurred

11. Power lost to all 4160V SWGR

Initiate AP/11 (Recovery from Loss of and any 4160V SWGR Power).

re-energized

IF Encl 5.1 (ES Actuation) has been ROP initiated, THEN reinitiate Encl 5.1.

14. Individual available to make

Announce plant conditions using PA notifications system.

Notify OSM to reference the Emergency Plan and AD-LS-ALL-0006 NOTIFY (Notification/Reportability Evaluation). And

Notify plant staff that Emergency Dose EDL Limits are in affect using PA system.

Page 55 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam CRITICAL TASKS CT-1 Outside Air Booster Fans are started to minimize radiation exposure to control room personnel. (Within 30 minutes of SGTR) TCA #20 Page 56 of 57

SAFETY: Take a Minute UNIT 0 (OSM)

SSF Operable: Yes KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 2 Fuel Handling: No UNIT STATUS (CR SRO)

Unit 1 Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 100% Mode: 1 Mode: 1 Gross MWE: 895 100% Power 100% Power RCS Leakage: 0.01 gpm EFDW Backup: Yes EFDW Backup: Yes No WCAP Action RBNS Rate: 0.01 gpm Technical Specifications/SLC Items (CR SRO)

Restoration Component/Train OOS TS/SLC #

Required Date/Time Date/Time AMSAC/DSS 0300 7 Days 16.7.2 Shift Turnover Items (CR SRO)

Primary

Due to unanalyzed condition, the SSF should be considered INOP for Unit 1 if power levels are reduced below 85%. Evaluations must be performed prior to declaring the SSF operable following a return to power (after going below 85%).

1RIA-3 and 5 removed from RB.

Secondary

Feedwater valve DP selected to A1 and B2 for maintenance

AMSAC/DSS bypassed

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

Reactivity Management (CR SRO)

Gp 7 Rod Position: Batch additions as required for volume RCS Boron 83 ppmB 92% Withdrawn control.

Human Performance Emphasis (OSM)

Procedure Use and Adherence

Appendix D Scenario Outline Form ES D-1 ILT48 NRC Exam Facility: Oconee Scenario No.: 4 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________SRO

________________________ ________________________OATC

________________________ ________________________BOP Initial Conditions:

Reactor Power = Critical below POAH Turnover:

LDST pressure low

Unit startup in progress Event Malfunction Event Event Type* Description No. No.

0a 0b 0d 0c Pressurize LDST with H2 (1H-1 will fail open 1 Override requiring LDST vent to return to C: BOP, SRO (TS) acceptable LDST pressure) 2 R: OATC, SRO Increase power to 6-7%

3 Override C: BOP, SRO 1B FWPT Auxiliary Oil Pump Trip 4 Override C: BOP, SRO 1C HWP Casing Water Level Low 5 SRO (TS) TD EFDWP oil sump dry 6 Override C: OATC, SRO PORV fails open 7 MCR022 C: OATC, SRO Dropped Control Rod(s) requiring a reactor trip 1A MSLB inside containment MSS270 8 M: ALL

1B MD EFDW fails to start in AUTO MSS360

1C HPIP fails to start on ES

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Scenario 4 Event Summary Event 1: The BOP will increase the pressure in the LDST using OP/1/A/1106/017. 1H-1 (Hydrogen to LDST valve) will fail open resulting in overpressurization of the LDST. This will cause all HPI pumps to be declared INOPERABLE until pressure is reduced.

Event 2: The OATC will increase power from below POAH to ~ 6 - 7 %.

Event 3: The Auxiliary Oil Pump for the 1A FWPT will trip causing the Emergency Oil Pump to start. Per the ARG, the candidate will attempt to start the Auxiliary Oil Pump which will fail.

Shortly afterwards, the alarm for FWPT 1A Emergency Oil Pump Overload will alarm which will require the candidate to attempt to start the Auxiliary Oil Pump. Not being able to start it, they will be directed to stop the Turning Gear Oil Pump and Emergency Oil pump.

Event 4: The 1C HWP will receive a casing low level alarm. This will require the BOP to start a standby HWP and secure the 1C HWP.

Event 5: An AO reports that the TD EFDWP oil sump is dry. The SRO will address Tech Specs. The SRO should direct the OATC to place the TD EFDW pump switch in Pull To Lock (PTL).

Event 6: The PORV will fail open causing RCS pressure to decrease rapidly. The operator will be required to close 1RC-4 (PORV Block valve) in order to stop the pressure decrease.

Event 7: Two control rods will fall into the core requiring a manual reactor trip.

Event 8: When the reactor trips, a steam line break will occur inside containment. The 1B MD EFDW pump will not start when the MFWPs trip so it will require manual start in order to feed the 1B SG. 1C HPIP will fail to start on ES which will require the operators to open 1HP-409 to provide flow to the B HPI header if required.

Page 2 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 1 Page 1 of 4 Event

Description:

Pressurize LDST with H2 (1H-1 will fail open requiring LDST vent to return to acceptable LDST pressure) (C: BOP, SRO)(TS)

Time Position Applicant's Actions or Behavior OP/1/A/1106/017 Crew Response:

SRO directs the BOP to add H2 to the LDST using OP/1/A/1106/017 (Hydrogen System) Enclosure 4.5 (Unit 1 LDST H2 Addition).

OP/1/A/1106/017 Rev 122 BOP 2.1 Notify Chemistry of hydrogen addition prior to adding hydrogen. {21}

Person Notified Date NOTE:

OP/0/A/1108/001 (Curves And General Information) and computer may be referred to for LDST Pressure vs Level curve. {7}

LDST Maximum Pressure vs Indicated Level Curve should NOT be exceeded when pressurizing LDST.

If Unit 1 is shutdown and will be placed in MODE 5, Nitrogen should be added to LDST to maintain LDST Pressure vs Level.

If Unit 1 is shutdown and will NOT be placed in MODE 5, Hydrogen should be added to LDST to maintain LDST Pressure vs Level.

2.2 Immediately prior to pressurization determine lowest reading of diverse LDST level indications: _____ inches.

2.3 For existing LDST level determine LDST Pressure allowable per LDST Pressure vs Level curve: _____ psig.

2.4 Notify Operator at H2 Cage to pressurize primary hydrogen.

NOTE: Operator should be in constant communication with CR to close 1H-26 if 1H-1 fails open.

BOOTH CUE: When directed to open 1H-26, use Manual Valves and position 1H-93 approximately 20% open 2.5 Direct Operator to open 1H-26 (LDST Block). (A-2-N of LDST Rm)

This event is complete when LDST pressure is returned to within limit, or when directed by the lead examiner.

Page 3 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 1 Page 2 of 4 Event

Description:

Pressurize LDST with H2 (1H-1 will fail open requiring LDST vent to return to acceptable LDST pressure) (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior OP/1/A/1106/017 Crew Response:

SRO Examiner/Booth Note: Once LDST pressure is being increased, 1H-1 (LDST SUPPLY) will fail open.

2.6 Direct Operator to use explosive detector to monitor the following:

Pressurized, non-welded H2 piping and fittings within local area of addition

Loop seal (A-2-N of LDST Rm) 2.7 Cycle 1H-1 (H2 TO LDST) as required to pressurize LDST per LDST Pressure vs Level curve.

Booth Note: When 1H-1 is opened, Fire Timer 1 to fail it open.

2.8 WHEN Hydrogen addition complete, ensure closed 1H-1 (H2 TO LDST).

Examiner Note: BOP should determine that 1H-1 has failed open and direct the AO to close 1H-26.

2.9 Direct Operator to close 1H-26 (LDST Block). (A-2-N of LDST Rm)

Booth Note: 1H-26 will NOT be closed until LDST pressure is outside the acceptable range.

1SA-02/D-2, HP Approaching LDST Operating Limits, actuates

BOP refers to the ARG.

1SA-2/D-2 1SA-2/D-2 Rev 33 3.1 Verify LDST pressure/level are within the acceptable operating region of the LDST PRESSURE vs. LEVEL enclosure in OP/0/A/1108/001 (Curves and General Information). (Page 6)

[It will NOT be within limits and will require Both Trains of HPI be declared INOPERABLE. TS 3.5.2]

3.2 IF necessary, vent LDST to GWD per OP/1/A/1104/002 (HPI System).

3.3 IF necessary, add hydrogen to establish desired LDST pressure per OP/1/A/1106/017 (Hydrogen System).

This event is complete when LDST pressure is returned to within limit, or when directed by the lead examiner.

Page 4 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 1 Page 3 of 4 Event

Description:

Pressurize LDST with H2 (1H-1 will fail open requiring LDST vent to return to acceptable LDST pressure) (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior OP/1/A/1104/002 Crew Response:

SRO directs the BOP to vent LDST to GWD per OP/1/A/1104/002 (HPI System), Encl. 4.16, (Lowering LDST Pressure)

OP/1/A/1104/002 (HPI System), Encl. 4.16, (Lowering LDST Pressure)Rev 167 BOP 3.1 Close 1GWD-20 (LDST Vent Blk). (A-2-LDST Hatch Area) 3.2 Open 1GWD-19 (LDST VENT).

CAUTION: LDST pressure should be within curves of Enclosure "LDST Pressure Vs Level" of OP/0/A/1108/001 (Curves and General Information).

NOTE: If LDST pressure is < 30 psig, leakage from BWST into HPI System may occur. (R.M.)

3.3 Throttle open 1GWD-20 (LDST Vent Blk) until LDST pressure begins to slowly decrease and GWD system can maintain vent header. (A-2-LDST Hatch Area) 3.4 IF required, start Standby GWD Compressor per OP/1-2/A/1104/018 (GWD System).

3.5 WHEN desired LDST pressure obtained, close 1GWD-19 (LDST VENT).

3.6 IF started, stop Standby GWD Compressor.

3.7 Throttle 1/4 turn open 1GWD-20 (LDST Vent Blk). (A-2-LDST Hatch Area)

TS 3.5.2, HIGH PRESSURE INJECTION Condition C.2 (3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ) Verify by administrative means that the ADV flow path for each steam generator is OPERABLE.

Condition C.3 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) Restore HPI train to Operable status.

Condition H (Immediately) Enter LCO 3.0.3 TS 3.0.3 (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) be in Mode 3 This event is complete when LDST pressure is returned to within limit, or when directed by the lead examiner.

Page 5 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 1 Page 4 of 4 Event

Description:

Pressurize LDST with H2 (1H-1 will fail open requiring LDST vent to return to acceptable LDST pressure) (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior OP/0/A/1108/001 SRO BOP This event is complete when LDST pressure is returned to within limit, or when directed by the lead examiner.

Page 6 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 2 Page 1 of 5 Event

Description:

Increase power to 6-7 % (R: OATC, SRO)

Time Position Applicant's Actions or Behavior Examiner Note: During the power increase, the Unit 1 CRS will assume the role of the dedicated Reactivity Management SRO.

SRO OP/1/A/1102/001 Crew Response:

SRO directs the OATC to increase power to 7% using OP/1/A/1102/001 (Controlling Procedure for Unit Startup), Encl. 4.7, starting at step 3.36 OP/1/A/1102/001 (Controlling Procedure for Unit Startup), Encl. 4.7, Step 3.36 Rev 309 NOTE:

Point Of Adding Heat (POAH) is normally achieved from 0.05 to 0.15%

power on Wide Range Indications. {27}

When POAH is achieved: TBVs will begin to open, 1HP-120 will begin to close, TAVE will increase, and SUR will decrease with negative Moderator Temperature Coefficient. (R.M.)

Wide Range indications are used since Source Range NIs saturate. (R.M.)

OATC 3.36 Begin reactor power increase to 0.5 - 1.0 % at 0.5 DPM SUR. (R.M.)

3.37 WHEN above POAH, begin reactor power increase to 2.5 - 3.5 %. (R.M.)

3.38 WHILE power increases, begin increasing 1HP-120 (RC VOLUME CONTROL) setpoint to establish 215" to 225" PZR Level.

NOTE:

TAVE error is blocked when on Low Level Limit and TAVE is < setpoint.

Core reactivity effects are minimized with Rx in automatic. (R.M.)

3.39 WHEN at 2.5 - 3.5 % Power, perform the following: (R.M.)

3.39.1 Place REACTOR MASTER to "AUTO".

3.39.2 Place DIAMOND to "AUTO".

3.39.3 Ensure TURBINE MASTER Setpoint to 880 - 890 psig.

3.40 Perform the following:

Ensure complete Enclosure "Prior To Entry Into MODE 1" of PT/1/A/0630/001 (Mode Change Verification). {55}

Review mechanical maneuvering rates and allowable ramp rates in PT/0/A/1103/020 (Power Maneuvering Guidelines). {54} (R.M.)

This event is complete when power is stable at 6-7%, or when directed by the lead examiner.

Page 7 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 2 Page 2 of 5 Event

Description:

Increase power to 6-7 % (R: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1102/001 Crew Response:

OATC 3.41 IF AT ANY TIME all the following:

All operable T Cold indications > 550°F

SSF inoperable only due to low decay heat, notify SM the SSF is Available for Unit 1.

3.42 Ensure acceptable point status for plant startup for MODE 1:

OAC Alarm Screen Review

OAC Point Processing Log NOTE: OAC Points can be found on Turn-On Code FDW02 3.43 Set temporary alarms on the following:

OAC Point O1E2129 (FDW LOOP A COMPOSITE VALVE DEMAND) temporary alarm set at 9.8%.

OAC Point O1E2130 (FDW LOOP B COMPOSITE VALVE DEMAND) temporary alarm set at 9.8%.

Note on Turnover sheet temporary alarms set on Composite Valve Demand NOTE:

At Composite Valve Demand of 8.8% decreasing, ICS removes a valve sequencing bias that forces the Startup Control valves open to approximately 90% and the Main Control Valves to close.

At Composite Valve Demand of 9.8% increasing, ICS inserts a valve sequencing bias that forces the Startup Control valves to close to approximately 10% and the Main Control Valves to open.

When Composite Valve Demand valve sequencing bias is inserted at 9.8%

on a power increase and then decreases below 8.8%, the unit is subject to a possible FDW transient due to the valve sequencing bias being inserted and then subsequently removed. A power change may be required to stabilize FDW flow above OR below sequencing bias setpoints.

This event is complete when power is stable at 6-7%, or when directed by the lead examiner.

Page 8 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 2 Page 3 of 5 Event

Description:

Increase power to 6-7 % (R: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1102/001 Crew Response:

OATC 3.44 WHILE power change is in progress, monitor the following indications:

Appropriate ranged NIs

Neutron error

RCS Loop T (Curve for "Loop T Vs Reactor Power" is in PT/1/A/0600/001)

FDW Flow (Curve for "Expected Feedwater Flow Per Header Vs Reactor Power" is in OP/0/A/1108/001)

OAC Point O1E2129 (FDW LOOP A COMPOSITE VALVE DEMAND)

OAC Point O1E2130 (FDW LOOP B COMPOSITE VALVE DEMAND) 3.45 Begin power increase to 6% to 7% per Enclosure 4.16 (CTP Adjustments)

(Page 10) 3.46 Ensure 'E' Heater outlet temperature being maintained at upper end of 100-180°F band.

3.47 WHILE power increasing in this enclosure, throttle to maintain 2300 to 6000 gpm on operating FDWP:

1FDW-53 (1A FDWP RECIRC CONTROL)

1FDW-65 (1B FDWP RECIRC CONTROL) 3.48 WHEN Reactor Power is > 5%, perform the following:

Ensure MODE 1 selected on OAC.

Ensure MODE 1 selected for Unit 1 in TSAIL.

Announce on Plant Page "Unit 1 has entered MODE 1".

Notify Assistant Outage Manager of Unit 1 entry into MODE 1.

________________________ _____/______

Person Notified Date / Time

Remove note from turnover sheet: "When in MODE 2, evaluate or restrict evolutions involving MS, FDW, and EFDW to minimize changes to RCS temperature and reactor power." (R.M.)

Remove note from turnover sheet: "In MODE 1 or 2, except during PT/0/A/0711/001 (ZPPT), if either loop TAVE is < 532°F, perform SR 3.4.2.1 per PT/1/A/0600/001 (Periodic Instrument Surveillance)".

Begin Primary to Secondary Leakage Monitoring During Startup per OP/0/A/1106/031 (Primary to Secondary Leak Rate Monitoring and Instrumentation).

This event is complete when power is stable at 6-7%, or when directed by the lead examiner.

Page 9 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 2 Page 4 of 5 Event

Description:

Increase power to 6-7 % (R: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1102/001 Crew Response:

OATC 3.49 Perform the following per PT/0/A/0230/001 (Radiation Monitor Check):

Ensure 1RIA-48 alarm setpoints adjusted for Mode 1.

Ensure 1RIA-49 alarm setpoints adjusted for Mode 1.

3.50 Ensure complete one of the following to secure minimum FDW Flow to SGs:

IF in progress, Enclosure 4.10 (Providing Minimum FDW Flow to SGs)

IF in progress, Enclosure "Providing Minimum FDW Flow to SGs" of OP/1/A/1102/010 (Controlling Procedure For Unit Shutdown).

OP/1/A/1102/001 Enclosure 4.16 (CTP Adjustments) 2.1 Verify REACTOR MASTER in AUTO 2.2 Verify Diamond in AUTO 2.3 IF expected power change < 1%, ensure R2 reactivity management control established per SOMP 1-02 2.4 IF expected power change > 1%, ensure R1 reactivity management control established per SOMP 1-02 3.1 WHILE enclosure is in progress, monitor the following indications:

Appropriate NIs

Neutron error

FDW flow 3.2 IF AT ANY TIME hold in power is desired, ensure HOLD selected 3.3 IF AT ANY TIME hold in power is NOT required, ensure HOLD is NOT selected This event is complete when power is stable at 6-7%, or when directed by the lead examiner.

Page 10 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 2 Page 5 of 5 Event

Description:

Increase power to 6-7 % (R: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1102/001 Crew Response:

OATC OP/1/A/1102/001 Enclosure 4.16 (CTP Adjustments) 3.4 IF change in power/rate is desired, perform the following:

3.4.1 Review the following regarding current power change:

Appropriate :controlling enclosure of this procedure

PT/0/A/1103/020 (Power Maneuvering Predictions)

IF in progress, PT/0/A/0811/001 (Power Escalation Test)

IF available, Maneuvering Plan

COLR for CRD Groups 5-8 position limits, Imbalance, & QPT 3.4.2 Ensure HOLD is selected 3.4.3 Ensure selected %/MIN or %/HR on RATE SET pushbutton 3.4.4 Ensure desired rate selected on RATE SET thumbwheels 3.4.5 Ensure rate selected is within above limits 3.4.6 Insert desired CTPD SET using INCREASE/DECREASE pushbuttons 3.4.7 Ensure CTPD SET is within above limits 3.4.8 Ensure HOLD is NOT selected 3.4.9 WHEN desired CTP is achieved, select 0.0 on RATE SET thumbwheels This event is complete when power is stable at 6-7%, or when directed by the lead examiner.

Page 11 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 3 Page 1 of 1 Event

Description:

1B FWPT Auxiliary Oil Pump Trip (C, BOP, SRO)

Time Position Applicant's Actions or Behavior Plant Response:

1SA-8/B-7 FWPT B HYDRAULIC PRESSURE LOW

1SA-8/C-6 FWPT B EMERGENCY OIL PUMP RUN in alarm

FWPT B Emergency Oil Pump starts SRO/BOP Crew Response:

SRO will direct the BOP to refer to 1SA-08/C-6.

1SA-08/C-3 1SA-08/C-6 FWPT B EMERGENCY OIL PUMP RUN Rev 35 3.1 Verify that B FWPT emergency oil pump is running.

3.2 IF applicable, verify B FWPT is still on turning gear. [It will be]

3.3 Try to restart B FWPT auxiliary oil pump. [It will fail to start]

3.4 IF restart fails, notify Maintenance for repairs.

Booth Cue: Approximately 2 minutes after firing timer 3, Timer 12 will auto actuate which will trip the Emergency Oil Pump and cause 1SA-08/C-7, (FWPT B EMERGENCY OIL PUMP OVERLOAD) to alarm.

Booth Cue: If dispatched as AO to investigate 1B FWPT, notify crew that all oil pumps are off and the FDWPT is on the turning gear.

Report that the TG motor is much noisier than normal.

1SA-08/C-7 1SA-08/C-7 FWPT B EMERGENCY OIL PUMP OVERLOAD 3.1 IF available, start Auxiliary Oil Pump and stop Emergency Oil Pump.

3.2 IF AOP is NOT available, stop Turning Gear Motor and emergency Bearing Oil Pumps.

3.3 Notify Maintenance for repairs.

3.4 As soon as EBOP OR Auxiliary Oil Pump becomes available, start pump and place Turbine on Turning Gear.

This event is complete when Turning Gear Motor is secured, or as directed by the Lead Examiner.

Page 12 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 4 Page 1 of 1 Event

Description:

1C HWP Casing Water Level Low (C: BOP, SRO)

Time Position Applicant's Actions or Behavior 1SA-9/E-5 Plant Response:

1SA-9/E-5 HWP C CASING WATER LEVEL LOW

OAC Alarm LOCA Load Shed Crew Response:

SRO/BOP BOP will address the ARG 1SA-9/E-5 Rev 47 3.1 IF '1C' HWP is in operation, then immediately:

Start a standby HWP.

Trip '1C' HWP.

Bypass Powdex. [Open 1C-14/1C-15]

Decrease load.

3.2 Monitor hotwell level.

3.3 Determine cause of low level alarm (possible suction filter clogging) and initiate corrective action necessary to return pump to normal operation.

Examiner Note: The crew may use OP/1/A/1106/002 (Condensate and FDW System) to bypass Powdex OP/1/A/1106/002 Enclosure 4.19 (Placing Powdex In/Out of Service) Rev 169 3.1 IF Powdex is to be removed from service for an extended period of time AND condensate system will NOT be shutdown, perform the following:

3.1.1 Ensure MSDD System in service 3.1.2 Notify Chemist that Powdex will be removed from service for an extended period of time 3.2 Ensure Open 1C-14/1C-15 (POL DEMIN BYPASS CONTROL) 3.3 Place note on Turnover sheet that Powdex has been removed from service 3.4 Notify Chemist that Powdex has been removed from service This event is complete when the standby HWP has been started, or as directed by the lead examiner.

Page 13 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 5 Page 1 of 1 Event

Description:

TD EFDWP oil sump dry (SRO)(TS)

Time Position Applicant's Actions or Behavior Plant response:

Simulator Operator call the Control Room as the WCC SRO and report that the Basement AO found the Unit 1 TD EFDWP oil sump with no oil SRO indicating on the dipstick. Report that the WCC and FIN-24 are investigating the situation to determine the cause of the problem. No oil has been found leaking from any equipment.

Crew response:

SRO should make the decision to place TD EFDWP in Pull to Lock.

TS 3.3.14 EMERGENCY FEEDWATER (EFW) PUMP INITIATION CIRCUITRY Condition B.1 (Immediately) Declare the affected EFW pump inoperable.

TS 3.7.5 EMERGENCY FEEDWATER (EFW) SYSTEM Condition B.1 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) Restore turbine driven EFW pump and EFW flow path to OPERABLE status.

SRO refer to TS 3.3.14 Condition B.

Declare the affected EFWP inoperable Immediately

SRO refer to TS 3.7.5 Condition B1 Restore TD EFDWP within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Booth Cue: If asked, inform crew that the TD was on the purifier last shift.

Booth Cue: If crew does not place TD EFDWP in PTL, then at direction of lead examiner, call as WCC SRO and direct the crew to place Unit 1 TDEFDWP switch in PTL per R&R.

Examiner Note: Ensure the Pzr is saturated prior to initiating Event 6.

This event is complete when the Tech Spec determination has been made or when directed by the lead examiner.

Page 14 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 6 Page 1 of 2 Event

Description:

PORV fails open (C: OATC, SRO)(TS)

Time Position Applicant's Actions or Behavior Examiner Note: Ensure Pzr saturated prior to Event 6.

AP/1/A/1700/044 Plant Response:

1SA-18/A1 ( Pressurizer Relief Valve Flow) in alarm

1RC-66 indicates open

Acoustic monitor indicates 1RC-66 open

RCS pressure decreasing Crew Response:

SRO/OATC

OATC should recognize that RCS pressure is below PORV setpoint and close the PORV Block Valve (1RC-4). This is an Immediate Action from AP/44 Abnormal Pressurizer Pressure Control.

SRO should enter AP/1/A/1700/044 AP/1/A/1700/044 Abnormal Pressurizer Pressure Control Rev 4 Immediate Manual Actions CT-1 3.1 IAAT PORV is open, AND RC pressure is < setpoint (2400 psig (HIGH) or 480 psig (LOW)), THEN close 1RC-4.

3.2 IAAT RC pressure < 2155 psig, AND 1RC-1 indicates open, THEN select 1RC-1 to CLOSE.

3.3 IAAT all the following conditions exist:

__ RC pressure < 2155 psig

__ RC pressure decreasing without a corresponding decrease in PZR level THEN close 1RC-3.

Subsequent Actions 4.1 Announce AP entry using the PA system.

4.2 GO TO the applicable step per the following table:

Failure Caused Step RCS Pressure Decrease 4.3 Increase 4.18 This event is complete when 1RC-4 is closed and RCS pressure is stable, or as directed by the lead examiner.

Page 15 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 6 Page 2 of 2 Event

Description:

PORV fails open (C: OATC, SRO)(TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/044 Crew Response:

SRO/OATC 4.3 Verify 1RC-4 is closed.

4.4 Verify 1RC-3 is closed.

NOTE 1RC-3 must NOT be allowed to be closed for 36 minutes at a time to avoid a thermal transient in piping between 1RC-3 and the PZR spray nozzle.

4.5 Position 1RC-3 as required to maintain RC pressure within desired band.

4.6 GO TO Step 4.13.

4.13 Verify PZR heaters maintaining RCS pressure within desired band.

4.14 Notify SPOC to repair malfunctioning component.

4.15 Ensure requirements of following are met:

__ TS 3.4.1 (RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling Limits)

__ TS 3.4.9 (Pressurizer)

__ TS 3.4.12 (Low Temperature Overpressure Protection System)

__ SLC 16.5.1 (Reactor Coolant System Vents) 4.16 WHEN repairs complete, THEN place following components in desired position for current plant conditions as determined by CR SRO:

__ 1RC-1

__ 1RC-3

__ 1RC-4

__ PZR heater bank #1

__ PZR heater bank #2

__ PZR heater bank #3

__ PZR heater bank #4 TS 3.4.1, REACTOR COOLANT SYSTEM Condition A (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) Restore RCS DNB parameter(s) to within limit.

COLR DNB Limit = 2125 psig This event is complete when 1RC-4 is closed and RCS pressure is stable, or as directed by the lead examiner.

Page 16 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 7 Page 1 of 1 Event

Description:

Dropped Control Rod(s) requiring a reactor trip (C: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/001 SRO/OATC Plant Response:

Group 6 Rod 3 drops into the core

Group 6 Rod 6 drops into the core

Statalarm 1SA-2/A-10 (CRD GLOBAL TROUBLE)

Statalarm 1SA-2/B-10 (CRD ASYMMETRIC ROD POSITION ERROR)

Statalarm 1SA-2/D-9 (CRD OUT INHIBIT)

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

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

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

Crew Response:

Crew should recognize 2 dropped control rods and trip the reactor in accordance with OMP 1-18 If the crew does not recognize the 2nd dropped control rod, they will enter AP/1/A/1700/001 (Unit Runback)

AP/1/A/1700/001 (Unit Runback) Rev15 NOTE

If more than one runback condition exists, ICS will respond by selecting the fastest runback rate and the lowest load limit. The most limiting runback will be the one with the fastest runback rate and the shortest duration.

It is possible for a FDWP to become unable to feed the SGs but not be tripped. In this case a signal would not be sent to RPS or the EFDWP start circuit.

4.1 GO TO the most limiting section per the following table:

4H Asymmetric Control Rod (1% / min to 55% power)

1. IAAT a more limiting runback occurs, THEN GO TO Subsequent Actions Step 4.1.

2. IAAT more than one control rod is dropped or misaligned 6.5% (9) from the group average, THEN trip the Rx.

This event is complete when the reactor is manually tripped, or as directed by the lead examiner.

Page 17 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 1 of 9 Event

Description:

1A MSLB inside containment (M: All)

Time Position Applicant's Actions or Behavior EOP Plant Response:

SRO/OATC

1SA-2/D-3, RC Press High/Low BOP

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

Crew Response:

Examiner Note: Crew will be performing IMAs and Subsequent Actions as a result of the manual reactor trip due to two dropped control rods.

IMAs EOP Immediate Actions Rev 40 3.1 Depress REACTOR TRIP pushbutton.

3.2 Verify reactor power < 5% FP and decreasing.

3.3 Depress the turbine TRIP pushbutton 3.4 Verify all turbine stop valves closed.

3.5 Verify RCP seal injection available.

SYMPTOM CHECK The BOP will verify the following:

Power Range NIs NOT < 5% Rule 1, ATWS/Unanticipated Nuclear Po Power Range NIs NOT decreasing Production Any SCM < 0°F Rule 2, Loss Of SCM Loss of Main and Emergency FDW Rule 3, Loss of Main or Emerg FDW (including unsuccessful manual initiation of Rule 4, Initiation of HPI Forced Cooling EFDW) (Inability to feed SGs and > 2300 psig, N CT-2 limit reached, or PZR level > 375")

Uncontrolled Main steam line(s) pressure Rule 5, Main Steam Line Break decrease CSAE Offgas alarms None (SGTR Tab is entered when identif Process monitor alarms (RIA-40, 59,60), SG Tube Leakage > 25 gpm)

Area monitor alarms (RIA-16/17)

Examiner note: BOP should manually start the 1B MD EFDWP.

BOP will perform Rule 5 (Main Steam Line Break) (Page 25)

SRO will review IMAs and transfer to the Subsequent Actions Tab.

This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Page 18 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 2 of 9 Event

Description:

1A MSLB inside containment (M: All)

Time Position Applicant's Actions or Behavior Subsequent Actions Tab Crew Response:

SRO will review the Subsequent Action Tab Parallel Action (Yellow) page SRO/OATC (Page 70) and transfer to the Excessive Heat Transfer (EHT)Tab.

EHT Tab SRO will review the EHT Tab Parallel Action (Yellow) page and determine that ES has actuated and direct the OATC to perform Encl. 5.1 ES Actuation (Page 50)

1. Verify any SG pressure < 550 psig.

[1A SG should be < 550 psig at this point]

2. Ensure Rule 5 (Main Steam Line Break) in progress or complete.

3. Place the following in HAND and decrease demand to zero on all affected SGs:

1A SG 1B SG 1FDW-32 1FDW-41 1FDW-35 1FDW-44

4. Close the following on all affected SGs:

1A SG 1B SG 1FDW-372 1FDW-382 1MS-17 1MS-26 1MS-79 1MS-76 1MS-35 1MS-36 1MS-82 1MS-84 1FDW-368 1FDW-369

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

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

RNO: GO TO Step 9.

7. Throttle HPI per Rule 6 (HPI).

8. Verify letdown in service.

RNO: __ IF desired to restore letdown, THEN initiate Encl 5.5 (Pzr and LDST Level Control). (Page 42)

This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Page 19 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 3 of 9 Event

Description:

1A MSLB inside containment (M: All)

Time Position Applicant's Actions or Behavior EHT Tab Crew Response:

SRO/OATC 9. Verify any SG has an intact secondary boundary (intact SG).

[1B SG is intact]

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

10. Open the following on all intact SGs:

1A SG 1B SG 1FDW-372 1FDW-382 1FDW-368 1FDW-369 1MS-17 1MS-26

11. Start MDEFDWP associated with all intact SGs:

1A SG 1B SG 1A 1B MDEFDWP MDEFDWP

12. Feed and steam all intact SGs to stabilize RCS P/T using either:

TBVs

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

13. GO TO Step 32.

32. Verify any:

__ HPI has operated in the injection mode while NO RCPs were operating

__ A cooldown below 400°F at > 100°F/hr has occurred RNO: GO TO Step 34.

33. Initiate Rule 8 (Pressurized Thermal Shock (PTS)).

34. Verify both closed:

__ 1MS-24

__ 1MS-33 This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Page 20 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 4 of 9 Event

Description:

1A MSLB inside containment (M: All)

Time Position Applicant's Actions or Behavior EHT Tab Crew Response:

SRO/OATC 35. Open 1AS-8.

36. Close 1SSH-9.

37. Perform notifications:

__ Notify Chemistry to determine RCS boron concentration.

__ Notify Secondary Chemistry to check for indications of SGTR. {2}

__ Notify RP to check for indications of SGTR.

38. IAAT RCS boron is determined to be insufficient for adequate SDM, THEN initiate Encl 5.11 (RCS Boration).

39. IAAT all exist:

__ ES Bypass Permit satisfied

__ All SCMs > 0°F

__ RCS pressure controllable THEN perform Steps 40 - 41.

RNO: GO TO Step 42.

40. Bypass applicable ES:

To Bypass HPI:

__ Bypass HPI ES CH A,B,C To Bypass LPI:

__ Bypass LPI ES CH A,B,C

41. Bypass applicable Diverse ES:

To Bypass HPI:

__ Bypass Diverse HPI To Bypass LPI:

__ Bypass Diverse LPI

42. Verify any SG is dry.

NOTE

Minimizing SCM reduces tensile stress on the SG.

PORV should be used if Pzr spray is not available.

Procedure progression may continue when actions to minimize SCM are in progress.

This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Page 21 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 5 of 9 Event

Description:

1A MSLB inside containment (M: All)

Time Position Applicant's Actions or Behavior EHT Tab Crew Response:

SRO/OATC 43. Maintain minimum 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

44. Verify any RCP operating.

RNO: GO TO Step 46.

45. Maintain RCP NPSH.

OAC

Encl 5.18 (P/T Curves)

46. Initiate Encl 5.16 (SG Tube-to-Shell T Control).

NOTE RCP 1A1 provides the best Pzr spray.

47. IAAT all exist:

__ < one RCP operating in any loop

__ All SCMs > 0°F

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

48. IAAT all exist:

__ RBS actuated

__ RB pressure < 10 psig

__ 1RIA-57 NOT in alarm

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

49. IAAT Tcold approaches 470°F, AND all RCPs are operating, THEN ensure

< four RCPs are operating.

50. IAAT BWST level is 19', THEN initiate Encl 5.12 (ECCS Suction Swap to RBES).

51. Verify all SCMs > 0°F.

This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Page 22 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 6 of 9 Event

Description:

1A MSLB inside containment (M: All)

Time Position Applicant's Actions or Behavior EHT Tab Crew Response:

SRO/OATC 52. Verify indications of SGTR 25 gpm.

RNO: __ GO TO Step 54.

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

55. Verify either:

__ Any SG isolated

__ Any SG has an unisolable steam leak

56. GO TO FCD tab.

Forced Cooldown Tab

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

Tcold 270°F: 50°F / 1/2 hr

Tcold < 270°F: 25°F / 1/2 hr THEN GO TO EHT tab.

2. Verify letdown in service.

RNO:

1. __ Ensure CC System in operation.

2. __ IF 1A Letdown Cooler available, THEN open the following:

__ 1HP-1

__ 1HP-3

3. __ IF 1B Letdown Cooler available, THEN open the following:

__ 1HP-2

__ 1HP-4

4. Close the following:

__ 1HP-6

__ 1HP-7

5. __ Open 1HP-5.

6. __ Adjust 1HP-7 for 20 gpm letdown.

7. __ Open 1HP-6.

8. __ Adjust 1HP-7 to control desired letdown flow.

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

4. IAAT Tcold approaches 470°F, THEN ensure < four RCPs operating.

This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Page 23 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 7 of 9 Event

Description:

1A MSLB inside containment (M: All)

Time Position Applicant's Actions or Behavior Forced Cooldown Tab Crew Response:

SRO/OATC 5. IAAT Tcold approaches 300°F, THEN ensure < three RCPs operating.

6. IAAT all the following exist:

__ ES Bypass Permit satisfied

__ All SCMs > 0°F

__ RCS pressure controllable THEN perform Steps 7 - 8.

7. Bypass applicable ES:

To Bypass HPI:

__ Bypass HPI ES CH A,B,C To Bypass LPI:

__ Bypass LPI ES CH A,B,C

8. Bypass applicable Diverse ES:

To Bypass HPI:

__ Bypass Diverse HPI To Bypass LPI:

__ Bypass Diverse LPI

9. IAAT any SG is < 700 psig, AND AFIS is NOT actuated on that SG, THEN select OFF on both Digital Channels 1&2 for that header:

A Header B Header DIG CH 1 OFF DIG CH 1 OFF DIG CH 2 OFF DIG CH 2 OFF

10. Stabilize RCS temperature.

11. Close 1HP-26.

12. Stop 1C HPI Pump.

13. Adjust 1HP-120 for desired setpoint.

This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Page 24 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 8 of 9 Event

Description:

1A MSLB inside containment (M: All)

Time Position Applicant's Actions or Behavior RULE 5 Crew Response:

BOP 1. Perform on affected headers:

A Header B Header On AFIS HEADER A, On AFIS HEADER B, depress CH. 1 INIT. depress CH. 1 INIT.

On AFIS HEADER A, On AFIS HEADER B, depress CH. 2 INIT. depress CH. 2 INIT.

Select OFF for Select OFF for 1A MD EFDWP. 1B MD EFDWP.

Trip both Main Trip both Main FDWPTs. FDWPTs.

Close 1FDW-315. Close 1FDW-316.

Place 1FDW-33 Place 1FDW-42 switch switch to CLOSE. to CLOSE.

Place 1FDW-31 Place 1FDW-40 switch switch to CLOSE. to CLOSE.

Close 1PSW-22. Close 1PSW-24.

Close 1PSW-23. Close 1PSW-25.

Examiner Note: The 1B MD EFDW Pump failed to start automatically.

2. Verify 1 TD EFDW PUMP operating.

RNO:

1__IF MD EFDWP for the intact SG is operating SG is operating, THEN GO TO Step 5. [IT WILL NOT BE OPERATING]

2.__Start 1 TD EFDW PUMP.

3. Verify 1 TD EFDW PUMP is feeding affected SGs. [1FDW-315 is closed]

RNO:

GO TO Step 5.

5. Verify 1B SG is an affected SG.

RNO:

GO TO Step 7.

This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Page 25 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 9 of 9 Event

Description:

1A MSLB inside containment (M: All)

Time Position Applicant's Actions or Behavior RULE 5 Crew Response:

BOP 7. WHEN overcooling is stopped, THEN adjust steaming of unaffected SG to maintain CETCs constant using either:

__ TBVs

__ Dispatch two operators to perform Encl 5.24 (Operation of the ADVs).

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

8. WHEN all exist:

__ Core SCM > 0°F

__ Rx power 1%

__ Pzr level increasing THEN continue.

9. Verify ES HPI actuated.

10. Place Diverse HPI in BYPASS.

11. Perform both:

__ Place ES CH 1 in MANUAL.

__ Place ES CH 2 in MANUAL.

12. Perform the following to stabilize RCS P/T:

__ Throttle HPI.

__ Reduce 1HP-120 setpoint to control at >100 [180 acc].

__ Adjust steaming of unaffected SG as necessary 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. (Page 27)

15. Ensure Rule 8 (Pressurized Thermal Shock (PTS)) is in progress or complete.

16. WHEN directed by CRS, THEN EXIT.

This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Page 26 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Op-Test No.: ILT48 Scenario No.: 4 Event No.: 8 Page 10 of 9 Event

Description:

1A MSLB inside containment (M: All)

Time Position Applicant's Actions or Behavior RULE 3 Crew Response:

OATC/BOP 1. Verify loss of MFDW and/or EFDW was due to any of the following:

__ Turbine Building Flooding

__ Actions taken to increase SG level due to Turbine Building Flooding RNO: GO TO Step 3.

3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency/PSW),

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. [1B MD EFDWP should be manually started.]

5. Verify any EFDW pump operating.

6. GO TO Step 38.

38. IAAT an EFDW valve CANNOT control in AUTO, OR manual operation of EFDW valve is desired to control flow/level, THEN perform Steps 39 - 43.

RNO: GO TO Step 44.

44. Verify any SCM < 0oF.

45. IAAT Unit 1 EFDW is in operation, THEN initiate Encl 5.9 (Extended EFDW Operation). (Page 28).

46. WHEN directed by CRS, THEN EXIT.

This event is complete when the crew has transferred to the FCD tab, or as directed by the lead examiner.

Page 27 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation Rev 40 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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 GO TO Step 8.

MD EFDWP is desired, THEN perform Steps 4 - 7.

4. Place EFDW control valve on SG with NO EFDW flow to MANUAL and closed:

1A SG 1B SG 1FDW-315 1FDW-316

5. Locally open:

1FDW-313 (1A EFDW Line Disch To 1A S/G X-Conn) (T-1, 1' N of M-16, 18' up) 1FDW-314 (1B EFDW Line Disch To 1B S/G X-Conn) (T-1, 3' S of M-24, 10' up)

6. Ensure a MD EFDWP is operating.

7. Throttle EFDW control valve on SG with NO EFDW flow to establish appropriate level per Rule 7 (SG Feed Control):

1A SG 1B SG 1FDW-315 1FDW-316

8. Perform as required to maintain UST level

> 7.5':

Makeup with demin water.

Place CST pumps in AUTO.

9. IAAT all 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.

Page 28 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

10. Verify 1 TD EFDW PUMP operating. GO TO Step 12.

11. Start TD EFDWP BEARING OIL COOLING PUMP.

NOTE

Loss of the condensate system for 25 minutes results in cooling down to LPI using the ADVs.

If NO HWPs are operating, continuing this enclosure to restore the condensate system is a priority unless the CR SRO deems EOP activities higher priority. The 25 minute criterion is satisfied when a HWP is started and 1C-10 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.

13. IAAT it is determined that condensate flow CANNOT be restored within 25 minutes, THEN GO TO Step 90.

14. Verify any HWP operating. 1. Place all CBP control switches to OFF.

2. GO TO Step 20.

15. Verify any CBP operating. 1. IF AP/11 restarted a HWP, THEN GO TO Step 22.

2. GO TO Step 41.

16. Verify 1C COND BOOSTER PUMP 1. Ensure only one CBP is operating.

operating.{12}

2. GO TO Step 18.

17. Stop: {12}

1A COND BOOSTER PUMP 1B COND BOOSTER PUMP

18. Ensure only one HWP is operating.

19. GO TO Step 44.

Page 29 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

20. Verify a loss of power event caused the GO TO Step 24.

loss of the secondary system.

21. Ensure AP/11 (Recovery From Loss of Power) is in progress.

22. WHEN AP/11 (Recovery From Loss of Power) has restored 600v load centers, AND a HWP is operating, THEN dispatch an operator to start all CBP Aux Oil Pumps. (T-1/J-21)

23. WHEN notified that all CBP Aux Oil pumps are operating, THEN GO TO Step 41.

24. Place all HWP control switches to OFF.

25. Place all CBP control switches to OFF.

26. Place valve switches to close until valve Continue.

travel is initiated:

1FDW-4 1FDW-9

27. Start: Start as necessary:

1A FDWP AUXILIARY OIL PUMP 1A FDWP EMERGENCY BRNG OIL 1B FDWP AUXILIARY OIL PUMP PUMP 1B FDWP EMERGENCY BRNG OIL PUMP

28. Verify both: 1. IF both FDW pumps have BRG LUBE FWPT A BRG LUBE OIL OIL PRESS < 4 psig, PRESS > 4 psig THEN GO TO Step 90.

FWPT B BRG LUBE OIL 2. Perform for the FDW pump that has BRG PRESS > 4 psig LUBE OIL PRESS < 4 psig:

Close 1FDW-1 for 1A FDW pump.

Close 1FDW-6 for 1B FDW pump.

29. Place in MANUAL and close:

1FDW-53 1FDW-65 Page 30 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

30. Place 1C-10 FAIL SWITCH in MANUAL.

31. Close 1C-10.

32. Make plant page to clear basement and third floor of non-essential personnel.

33. Start one HWP.

34. Verify < 25 minutes elapsed since loss 1. Stop all HWPs.

of condensate.

2. GO TO Step 90.

35. Throttle 1C-10 controller 10% open to satisfy 25 minute system restart criteria.

36. WHEN FWP SUCT HDR PRESS (1VB3) is 100 psig, THEN open 1C-10.

37. Place 1C-10 FAIL SWITCH in FAIL OPEN.

38. Dispatch an operator to start all CBP Aux Oil Pumps. (T-1/J-21)

39. Maximize total recirc flow < 1200 gpm with one of the following:

1FDW-53 1FDW-65

40. WHEN five minutes have elapsed, AND notified that all CBP Aux Oil pumps are operating, THEN continue procedure.

41. Start a second HWP.

42. Start 1C COND BOOSTER PUMP. {12} Start one available CBP.

43. Stop one operating HWP.

44. Place control switch for one secured HWP in AUTO.

45. Place control switch for one secured CBP in AUTO.

Page 31 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

46. Perform the following:

Position HWP LOAD SHED DEFEAT switch to a running HWP.

Position CBP LOAD SHED DEFEAT switch to a running CBP.

47. Place in MANUAL:

1FDW-53 1FDW-65

48. Establish 2300 - 6000 gpm total recirc flow with one of the following:

1FDW-53 1FDW-65

49. IAAT UST level CANNOT be maintained > 8.5',

THEN locally open 1C-899 (Cond Recirc To UST Riser Throttle)

(T-1/J-23).

50. IAAT UST level increases > 11',

THEN perform as required:

Throttle demin water Locally throttle 1C-899 (Cond Recirc To UST Riser Throttle)

(T-1/J-23)

51. Verify closed: GO TO Step 58.

1FDW-4 1FDW-9 Page 32 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

52. Position switches in CLOSE:

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

53. Ensure closed:

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

54. Locally open:

1FDW-5 (1A FDWP Discharge Bypass)

(T-1/SE of D-24 12' up) 1FDW-10 (1B FDWP Discharge Bypass) (T-1/N of D-26 9' up)

55. WHEN FWP DISCH HDR PRESS (1VB3) is approximately equal to either of the following:

O1A1014 (FDWP 1A DISCHARGE PRESS)

O1A1391 (FDWP 1B DISCHARGE PRESS)

THEN open:

1FDW-4 1FDW-9 Page 33 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

56. Locally close:

1FDW-5 (1A FDWP Discharge Bypass)

(T-1/SE of D-24 12' up) 1FDW-10 (1B FDWP Discharge Bypass) (T-1/N of D-26 9' up)

NOTE Windmill protection may have required closure of FDW pump suction valve.

57. Verify open: 1. IF required, notify the WCC SRO to 1FDW-1 initiate investigation.

1FDW-6 2. Note on Turnover sheet that FDW pump associated with closed valve is not available for use until problem resolved.

58. IAAT it is desired to re-establish Main FDW, THEN initiate Encl (Re-establishing Main FDW) of OP/1/A/1106/002 (Condensate And FDW System).

59. IAAT EFDW has been secured per Encl (Re-establishing Main FDW) of OP/1/A/1106/002 (Condensate And FDW System),

THEN EXIT.

Page 34 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

60. WHEN UST level is < 4',

THEN dispatch two operators to perform Encl 5.24 (Operation of the ADVs) in preparation for loss of vacuum. (PS)

61. Verify power available to 1V-186 by Dispatch an operator to be in position at using valve position indicating light. 1V-186 (Vacuum Breaker)

(T-3, catwalk at 1C2 waterbox).

NOTE 1C-573 will be closed after vacuum is broken.

62. Dispatch an operator with a safety harness to 1C-573 (MD EFDWPs Suction From UST) (T-1, SW of E-24, 8' above floor) to:

Unlock and remove chain from 1C-573.

Establish communication with Control Room.

63. WHEN UST level is < 3',

THEN continue.

64. Open 1V-186. Notify operator to open 1V-186 (Main Condenser Vacuum Breaker)

(T-3, catwalk at 1C2 waterbox).

65. Stop all main vacuum pumps.

66. Stop all CBPs.

67. Stop all HWPs.

68. Close: Dispatch an operator to close:

1MS-47 1MS-49 (1A CSAE Steam Supply) 1AS-40 (T-3/F-26) 1MS-58 (1B CSAE Steam Supply)

(T-3/G-26) 1MS-67 (1C CSAE Steam Supply)

(T-3/H-26)

Page 35 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE

1C-573 is open unless Step 75 has been completed.

While EFDW is secured, a transfer to LOHT is required only when directed by this enclosure or Rule 4 (Initiation of HPI Forced Cooling) conditions are met.

69. IAAT UST level is < 1', GO TO Step 72.

AND 1C-573 (MD EFDWPs Suction From UST) is open, THEN perform Steps 70 - 71.

70. Perform the following:

Stop 1A MD EFDWP.

Stop 1B MD EFDWP.

71. Verify 1C-391 open. 1. Stop 1TD EFDW PUMP.

2. Close:

1FDW-315 1FDW-316

72. Perform the following:

A. Reduce MD EFDWP flow to

< 440 gpm per pump.

B. Notify crew of MD EFDWP flow limit while aligned to hotwell.

NOTE Vacuum gage or computer can be used. Vacuum is broken when either start to flat line. Do NOT change scale on computer trend once started.

73. WHEN vacuum is broken, THEN continue.

Page 36 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

74. IAAT MD EFDWPs are operating, GO TO Step 78.

OR available to operate, THEN PERFORM Steps 75 - 77.

75. Locally close 1C-573 1. IF 1TD EFDW PUMP is operating, (MD EFDWPs Suction From UST) OR operable, (T-1, SW of E-24, 8' above floor). THEN GO TO Step 78.

2. IF NO EFDW pumps are operating, THEN:

A. Notify CR SRO that a LOHT exists from loss of EFDW suction source.

B. Notify CR SRO that Rule 3 will be performed to cross connect with alternate unit.

C. Consider all U1 EFDW pumps inoperable, AND GO TO Rule 3.

76. Verify MD EFDWPs were stopped due GO TO Step 78.

to UST level < 1'.

77. Perform the following:

A. Restart all MD EFDWPs that were stopped due to UST level < 1'.

B. Resume feeding available SGs.

Page 37 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

78. Verify 1 TD EFDW PUMP operating. GO TO Step 82.

79. Dispatch operator to 1C-157 (TD EFDWP Suction From UST) to establish communication with CR (T-1/C-20).

80. WHEN operator in place at 1C-157, THEN continue.

81. Stop 1 TD EFDW PUMP.

82. Locally close 1C-157 (TD EFDWP 1. IF NO EFDW pumps are operating, Suction From UST) (T-1/C-20). THEN:

A. Notify CR SRO that a LOHT exists from loss of EFDW suction source.

B. Notify CR SRO that Rule 3 will be performed to cross connect with alternate unit.

C. Consider all U1 EFDW pumps inoperable, AND GO TO Rule 3.

2. GO TO Step 84.

83. Open 1C-391. 1. Attempt to locally open 1C-391 (TD EFDWP Suction From Hotwell)

(T-1/C-20).

2. IF 1C-391 CANNOT be opened, AND NO EFDW pumps are operating, THEN:

A. Notify CR SRO that a LOHT exists from loss of EFDW suction source.

B. Notify CR SRO that Rule 3 will be performed to cross connect with alternate unit.

C. Consider all U1 EFDW pumps inoperable, AND GO TO Rule 3.

Page 38 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation

84. IAAT 1 TD EFDW PUMP operation is desired, AND all exist:

Hotwell level is > 1.

Vacuum is broken.

1 TD EFDW PUMP successfully aligned to hotwell.

THEN:

A. Start 1 TD EFDW PUMP.

B. Feed available SGs as required.

85. Dispatch an operator to open:

1C-188 (Hotwell Emerg Makeup #1 Control Bypass) (T-1/W of E-24). {18}

1C-912 (UST Riser To HW Emerg Makeup #2 Auto Isol Bypass)

(T-1/G-23)

86. Notify TSC to evaluate methods to maintain secondary inventory including strategies located in EM 5.1 (Engineering Emergency Response Plan) and EM 5.2 (Evaluation By Station Management in the TSC -

Beyond Design Basis Mitigation Strategies).

Page 39 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

87. IAAT hotwell level is 1, THEN:

A. Stop all EFDWPs.

B. Consider all U-1 EFDW pumps inoperable, AND GO TO Rule 3.

NOTE

This step provides general plant directions for the SRO and Management team. The user shall continue after the notification has been made.

Swapping from TBVs to ADVs prevents overfilling the hotwell/condenser.

Securing steam seals limits the water (condensation) that reaches the oil systems. Vacuum must be broken to secure steam seals.

Engineering will determine when to allow secondary system restart.

Beginning a cooldown assumes HPI is operating. If the SSF is supplying seals, then further discussion with the Management team should be undertaken prior to cooldown.

88. Notify the CR SRO to direct the following as time and resources allow:

Transfer steam control from TBVs to ADVs.

Operate ADVs per U1 EOP Encl 5.24 (Operation of ADVs).

Begin Unit cool down to LPI per OP/1/A/1102/010 (Controlling Procedure For Unit Shutdown) using the ADVs.

Break vacuum per OP/1-2/A/1106/016 (Condenser Vacuum System).

Secure Steam Seals per OP/1/A/1106/13 (Steam Seal System).

89. WHEN directed by CR SRO, THEN EXIT.

Page 40 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Rule 6 HPI HPI Pump Throttling Limits

HPI must be throttled to prevent violating the RV-P/T limit.

HPI pump operation must be limited to two HPIPs when only one BWST suction valve (1HP-24 or 1HP-25) is open.

HPI must be throttled 475 gpm/pump (including seal injection for A header) when only one HPI pump is operating in a header.

Total HPI flow must be throttled 950 gpm including seal injection when 1A and 1B HPI pumps are operating with 1HP-409 open.

Total HPI flow must be throttled < 750 gpm when all the following exist:

- LPI suction is from the RBES

- piggyback is aligned

- either of the following exist:

only one piggyback valve is open (1LP-15 or 1LP-16)

only one LPI pump operating

HPI may be throttled under the following conditions:

HPI Forced Cooling in Progress: HPI Forced Cooling NOT in Progress:

All the following conditions must exist: All the following conditions must exist:

Core SCM > 0

All WR NIs 1%

CETCs decreasing

Core SCM > 0

Pzr level increasing

SRO concurrence required if throttling following emergency boration HPI Pump Minimum Flow Limit

Maintain 170 gpm indicated/pump. This is an instrument error adjusted value that ensures a real value of 65 gpm/pump is maintained. HPI pump flow less than minimum is allowed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Page 41 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control 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 IF 1HP-26 will NOT open, maintain desired Pzr level: THEN throttle 1HP-410 to maintain

1A HPI Pump desired Pzr level.

1B HPI 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 1A BHUT, THEN perform the following:

A. Open:

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

C. Notify SRO.

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

Page 42 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control 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 1B LPI PUMP.

C. Open:

1LP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D. IF two LPI Pumps are running only 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, U1 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 1B 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 43 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

8. Start 1C HPI PUMP. IF at least two HPI pumps are operating, THEN throttle 1HP-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 1HP-26 will NOT open, 1HP-26 THEN throttle 1HP-410 to maintain desired Pzr level.

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

Page 44 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED 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 1HP-24. (1HP-24 and 1HP-25) are closed, THEN perform the following:

Open 1HP-25.

Close 1HP-16. A. Start 1A LPI PUMP.

B. Start 1B LPI PUMP.

C. Open:

1LP-15 1LP-16 1LP-9 1LP-10 1LP-6 1LP-7 D. IF two LPI Pumps are running only 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, U1 LPI Hatch Rm, N end).

F. GO TO Step 13.

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

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

12.__ Operate Pzr heaters as required to maintain heater bundle integrity.

Page 45 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

13. 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-1-107, Unit 1 RC Bleed Transfer Pump Rm.).

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

Open 1HP-17.

Open 1HP-18

15. IAAT all of the following exist: GO TO Step 35.

Letdown isolated LPSW available Letdown restoration desired THEN perform Steps 16 - 34. {41}

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

2. GO TO Step 35.

17. Ensure only one CC pump running.

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

19. Verify both are open: 1. IF 1HP-1 is closed due to 1HP-3 failing to 1HP-1 close, 1HP-2 THEN GO TO Step 21.

2. IF 1HP-2 is closed due to 1HP-4 failing to close, THEN GO TO Step 21.

20. GO TO Step 23.

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

21. Verify letdown line leak in East GO TO Step 23.

Penetration Room has occurred.

22. GO TO Step 35.

Page 46 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

23. Monitor for unexpected conditions while restoring letdown.

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

1HP-1 1HP-3

2. IF 1B letdown cooler is to be placed in service, THEN open:

1HP-2 1HP-4

3. GO TO Step 26.

25. Open:

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

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

aligned.

A. Notify CR SRO of problem.

B. GO TO Step 35.

27. Close 1HP-6.

28. Close 1HP-7.

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

2. Close:

1HP-8 1HP-9&11

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

A. Select 1HP-14 to NORMAL.

B. Close 1HP-16.

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

Page 47 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

30. Open 1HP-5.

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

32. WHEN letdown temperature is

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

33. Open 1HP-6.

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

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

35. 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).

36. 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.

37. 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 48 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

38. Verify 1CS-48 (1A BHUT Recirc) has GO TO Step 40.

been closed to provide additional makeup flow to LDST.

39. 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 1CS-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.

40. Verify two Letdown Filters in service, GO TO Step 42.

AND only one Letdown filter is desired.

41. Perform one of the following:

Place 1HP-17 switch to CLOSE.

Place 1HP-18 switch to CLOSE.

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

Page 49 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam EOP Enclosure 5.1 (ES Actuation)Rev 40 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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

Actuation Associated ES Setpoint Channel (psig) 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 NOTE actuation setpoints have actuated. Voter OVERRIDE extinguishes the TRIPPED light on the associated channels that have auto actuated. Pressing TRIP on channels previously actuated will reposition components that may have been throttled or secured by this Enclosure.

__ 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. __ Place Diverse HPI in OVERRIDE.

5. Perform both: NOTE

__ Place ES CH 1 in MANUAL.

Voter OVERRIDE affects all channels of the

__ Place ES CH 2 in MANUAL. 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 1 fails to go to MANUAL, THEN place ODD voter in OVERRIDE.

2. __ IF ES CH 2 fails to go to MANUAL, THEN place EVEN voter in OVERRIDE.

Page 50 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

6. __ 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.

7. __ Verify Rule 2 in progress or complete. __ GOTO Step 73.

8. __ Verify any RCP operating. __ GOTO Step 10.

9. Open:

__ 1HP-20

__ 1HP-21

10. __ IAAT any RCP is operating, __ GOTO Step 15.

AND ES Channels 5 and 6 actuate, THEN perform Steps 11 - 14.

11. Perform all: NOTE

__ Place ES CH 5 in MANUAL.

Voter OVERRIDE affects all channels of the

__ Place ES CH 6 in MANUAL. 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 5 fails to go to MANUAL, THEN place ODD voter in OVERRIDE.

2. __ IF ES CH 6 fails to go to MANUAL, THEN place EVEN voter in OVERRIDE.

12. Open:

__ 1CC-7

__ 1CC-8

__ 1LPSW-15

__ 1LPSW-6

13. __ Ensure only one CC pump operating.

14. __ Ensure Standby CC pump in AUTO.

Page 51 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

15. __ IAAT ES Channels 3 & 4 are actuated, __ GO TO Step 53.

THEN GO TO Step 16.

16. __ Place Diverse LPI in BYPASS. __ Place Diverse LPI in OVERRIDE.

17. Perform both: NOTE

__ Place ES CH 3 in MANUAL.

Voter OVERRIDE affects all channels of the

__ Place ES CH 4 in MANUAL. 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.

CAUTION LPI pump damage may occur if operated in excess of 30 minutes against a shutoff head. {6}

18. __ IAAT any LPI pump is operating against a shutoff head, THEN at the CR SRO's discretion, stop affected LPI pumps. {6, 22}

19. __ IAAT RCS pressure is < LPI pump __ GOTO Step 22.

shutoff head, THEN perform Steps 20 - 21.

20. Perform the following: 1. __ Stop 1A LPI PUMP.

__ Open 1LP-17. 2. __ Close 1LP-17.

__ Start 1A LPI PUMP.

21. Perform the following: 1. __ Stop 1B LPI PUMP.

__ Open 1LP-18. 2. __ Close 1LP-18.

__ Start 1B LPI PUMP.

Page 52 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

22. __IAAT 1A and 1B LPI PUMPs are __ GO TO Step 25.

off / tripped, AND all exist:

__ RCS pressure < LPI pump shutoff head

__ 1LP-19 closed

__ 1LP-20 closed THEN perform Steps 23 - 24.

23. Open:

__ 1LP-9

__ 1LP-10

__ 1LP-6

__ 1LP-7

__ 1LP-17

__ 1LP-18

__ 1LP-21

__ 1LP-22

24. __ Start 1C LPI PUMP.

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

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

27. Start:

__ A OUTSIDE AIR BOOSTER FAN

__ B OUTSIDE AIR BOOSTER FAN

28. Notify Unit 3 to start:

__ 3A OUTSIDE AIR BOOSTER FAN

__ 3B OUTSIDE AIR BOOSTER FAN Page 53 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

29. Verify open: __ IF CR SRO desires 1CF-1 and 1CF-2

__ 1CF-1 open,

__ 1CF-2 THEN open:

__ 1CF-1

__ 1CF-2

30. __ Verify 1HP-410 closed. 1. __ Place 1HP-120 in HAND.

2. __ Close 1HP-120.

31. __ Secure makeup to the LDST.

32. __ Verify all ES channel 1 - 4 components 1. __ IF 1HP-3 fails to close, are in the ES position. THEN close 1HP-1.

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

3. __ IF 1HP-20 fails to close, AND NO RCPs operating, THEN close:

4. __ Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired.

33. __ Verify Unit 2 turbine tripped. __ GOTO Step 36.

34. __ Close 2LPSW-139.

35. __ Verify total LPSW flow to Unit 2 LPI __ Reduce LPSW to Unit 2 LPI coolers to coolers 6000 gpm. obtain total LPSW flow 6000 gpm.

36. __ Close 1LPSW-139.

37. Place in FAIL OPEN:

__ 1LPSW-251 FAIL SWITCH

__ 1LPSW-252 FAIL SWITCH

38. __ Start all available LPSW pumps.

Page 54 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

39. Verify either: __ GOTO Step 41.

__ Three LPSW pumps operating

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

40. Open: __ IF both are closed:

__ 1LPSW-4 __ 1LPSW-4

__ 1LPSW-5 __ 1LPSW-5 THEN notify SRO to initiate action to open at least one valve prior to BWST level 19'.

41. __ IAAT BWST level 19', 1. __ Display BWST level using OAC Turn-on THEN initiate Encl 5.12 (ECCS Suction Code "SHOWDIG O1P1600".

Swap to RBES). 2. __ Notify crew of BWST level IAAT step.

42. __ Dispatch an operator to perform Encl 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, __ GOTO Step 46.

THEN perform Step 45.

NOTE RBCU transfer to low speed will NOT occur until 3 minute time delay is satisfied.

45. __ Verify all ES channel 5 & 6 components __ Notify SRO to evaluate components NOT are in the ES position. in ES position and initiate action to place in ES position if desired.

Page 55 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

46. __ IAAT ES channels 7 & 8 have actuated, __ GOTO Step 49.

THEN perform Steps 47 - 48.

47. Perform all: NOTE

__ Place ES CH 7 in MANUAL.

Voter OVERRIDE affects all channels of the

__ Place ES CH 8 in MANUAL. 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 7 fails to go to MANUAL, THEN place ODD voter in OVERRIDE.

2. __ IF ES CH 8 fails to go to MANUAL, THEN place EVEN voter in OVERRIDE.

48. __ Verify all ES channel 7 & 8 components __ Notify SRO to evaluate components NOT are in the ES position. in ES position and initiate action to place in ES position if desired.

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 Encl 5.41 (ES Recovery).

52. __ WHEN CR SRO approves, THEN EXIT.

- - END ***

Page 56 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Unit Status ES Channels 3 & 4 have NOT actuated.

53. Start:

__ A OUTSIDE AIR BOOSTER FAN

__ B OUTSIDE AIR BOOSTER FAN

54. Notify Unit 3 to start:

__ 3A OUTSIDE AIR BOOSTER FAN

__ 3B OUTSIDE AIR BOOSTER FAN

55. Verify open: __ IF CR SRO desires 1CF-1 and 1CF-2

__ 1CF-1 open,

__ 1CF-2 THEN open:

__ 1CF-1

__ 1CF-2

56. __ Verify 1HP-410 closed. 1. __ Place 1HP-120 in HAND.

2. __ Close 1HP-120.

57. __ Secure makeup to the LDST.

58. __ Verify all ES channel 1 & 2 components 1. __ IF 1HP-3 fails to close, are in the ES position. THEN close 1HP-1.

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

3. __ IF 1HP-20 fails to close, AND NO RCPs operating, THEN close:

4. __ Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired.

59. __ Verify Unit 2 turbine tripped. __ GOTO Step 62.

60. __ Close 2LPSW-139.

61. __ Verify total LPSW flow to Unit 2 LPI __ Reduce LPSW to Unit 2 LPI coolers to coolers 6000 gpm. obtain total LPSW flow 6000 gpm.

62. __ Close 1LPSW-139.

Page 57 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

63. Place in FAIL OPEN:

__ 1LPSW-251 FAIL SWITCH

__ 1LPSW-252 FAIL SWITCH

64. __ Start all available LPSW pumps.

65. Verify either: __ GOTO Step 67.

__ Three LPSW pumps operating

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

66. Open: __ IF both are closed:

__ 1LPSW-4 __ 1LPSW-4

__ 1LPSW-5 __ 1LPSW-5 THEN notify SRO to initiate action to open at least one valve prior to BWST level 19'.

67. __ IAAT BWST level 19', 1. __ Display BWST level using OAC Turn-on THEN initiate Encl 5.12 (ECCS Suction Code "SHOWDIG O1P1600".

Swap to RBES). 2. __ Notify crew of BWST level IAAT step.

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

69. __ Notify U2 CR SRO that SSF is inoperable due to OTS1-1 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 Encl 5.41 (ES Recovery).

72. __ WHEN CR SRO approves, THEN EXIT.

- - END ***

Page 58 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

73. Open: 1. __ IF both BWST suction valves

__ 1HP-24 (1HP-24 and 1HP-25) are closed,

__ 1HP-25 THEN:

A. __ Start 1A LPI PUMP.

B. __ Start 1B LPI PUMP.

C. Open:

__ 1LP-15

__ 1LP-16

__ 1LP-9

__ 1LP-10

__ 1LP-6

__ 1LP-7 D. __ IF two LPI Pumps are running only 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, U1 LPI Hatch Rm, N end).

F. __ GOTO Step 74.

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

A. __ IF three HPI pumps are operating, THEN secure 1B 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 75.

Page 59 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

74. __ Ensure at least two HPI pumps are operating.

75. Verify open: 1. __ IF HPI has been intentionally throttled,

__ 1HP-26 THEN GOTO Step 76.

__ 1HP-27 2. Open:

__ 1HP-26

__ 1HP-27 Page 60 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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

1A Header 1B Header 1HP-410 1HP-409 Figure 1 Required HPI Flow Per Header HPI Pump Runout Unacceptable Region Region (excluding seal For 1 injection) Pump In Header (including seal injection for A header)

Page 61 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

77. __ Verify any RCP operating. __ GOTO Step 79.

78. Open:

__ 1HP-20

__ 1HP-21

79. __ IAAT any RCP is operating, __ GOTO Step 84.

AND ES Channels 5 and 6 actuate, THEN perform Steps 800 - 83.

80. Perform all: NOTE

__ Place ES CH 5 in MANUAL.

Voter OVERRIDE affects all channels of the

__ Place ES CH 6 in MANUAL. 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 5 fails to go to MANUAL, THEN place ODD voter in OVERRIDE.

2. __ IF ES CH 6 fails to go to MANUAL, THEN place EVEN voter in OVERRIDE.

81. Open:

__ 1CC-7

__ 1CC-8

__ 1LPSW-15

__ 1LPSW-6

82. __ Ensure only one CC pump operating.

83. __ Ensure Standby CC pump in AUTO.

Page 62 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

84. __ IAAT ES Channels 3 & 4 are actuated, __ GO TO Step 122.

THEN GO TO Step 855.

85. __ Place Diverse LPI in BYPASS. __ Place Diverse LPI in OVERRIDE.

86. Perform both: NOTE

__ Place ES CH 3 in MANUAL.

Voter OVERRIDE affects all channels of the

__ Place ES CH 4 in MANUAL. 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.

CAUTION LPI pump damage may occur if operated in excess of 30 minutes against a shutoff head. {6}

87. __ IAAT any LPI pump is operating against a shutoff head, THEN at the CR SRO's discretion, stop affected LPI pumps.{6, 22}

Page 63 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

88. __ IAAT RCS pressure is < LPI pump __ GOTO Step 91.

shutoff head, THEN perform Steps 89 - 90.

89. Perform the following: 1. __ Stop 1A LPI PUMP.

__ Open 1LP-17. 2. __ Close 1LP-17.

__ Start 1A LPI PUMP.

90. Perform the following: 1. __ Stop 1B LPI PUMP.

__ Open 1LP-18. 2. __ Close 1LP-18.

__ Start 1B LPI PUMP.

91. __ IAAT 1A and 1B LPI PUMPs are __ GO TO Step 94.

off / tripped, AND all exist:

__ RCS pressure < LPI pump shutoff head

__ 1LP-19 closed

__ 1LP-20 closed THEN perform Steps 92 -93.

92. Open:

__ 1LP-9

__ 1LP-10

__ 1LP-6

__ 1LP-7

__ 1LP-17

__ 1LP-18

__ 1LP-21

__ 1LP-22

93. __ Start 1C LPI PUMP.

94. __ IAAT 1A LPI PUMP fails while operating, AND 1B LPI PUMP is operating, THEN close 1LP-17.

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

Page 64 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

96. Start:

__ A OUTSIDE AIR BOOSTER FAN

__ B OUTSIDE AIR BOOSTER FAN

97. Notify Unit 3 to start:

__ 3A OUTSIDE AIR BOOSTER FAN

__ 3B OUTSIDE AIR BOOSTER FAN

98. Verify open: __ IF CR SRO desires 1CF-1 and 1CF-2

__ 1CF-1 open,

__ 1CF-2 THEN open:

__ 1CF-1

__ 1CF-2

99. __ Verify 1HP-410 closed. 1. __ Place 1HP-120 in HAND.

2. __ Close 1HP-120.

100. __ Secure makeup to the LDST.

101. __ Verify all ES channel 1 - 4 components 1. __ IF 1HP-3 fails to close, are in the ES position. THEN close 1HP-1.

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

3. __ IF 1HP-20 fails to close, AND NO RCPs operating, THEN close:

4. __ Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired.

102. __ Verify Unit 2 turbine tripped. __ GOTO Step 105.

103. __ Close 2LPSW-139.

104. __ Verify total LPSW flow to Unit 2 LPI __ Reduce LPSW to Unit 2 LPI coolers to coolers 6000 gpm. obtain total LPSW flow 6000 gpm.

105. __ Close 1LPSW-139.

Page 65 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 106. Place in FAIL OPEN:

__ 1LPSW-251 FAIL SWITCH

__ 1LPSW-252 FAIL SWITCH 107. __ Start all available LPSW pumps.

108. Verify either: __ GOTO Step 110.

__ Three LPSW pumps operating

__ Two LPSW pumps operating when Tech Specs only requires two operable 109. Open: __ IF both are closed:

__ 1LPSW-4 __ 1LPSW-4

__ 1LPSW-5 __ 1LPSW-5 THEN notify SRO to initiate action to open at least one valve prior to BWST level 19'.

110. __ IAAT BWST level 19', 1. __ Display BWST level using OAC Turn-on THEN initiate Encl 5.12 (ECCS Suction Code "SHOWDIG O1P1600".

Swap to RBES). 2. __ Notify crew of BWST level IAAT step.

111. __ Dispatch an operator to perform Encl 5.2 (Placing RB Hydrogen Analyzers In Service). (PS) 112. __ Select DECAY HEAT LOW FLOW ALARM SELECT switch to ON.

113. __ IAAT ES channels 5 & 6 have actuated, __ GOTO Step 115.

THEN perform Step 114.

NOTE RBCU transfer to low speed will NOT occur until 3 minute time delay is satisfied.

114. __ Verify all ES channel 5 & 6 components __ Notify SRO to evaluate components NOT are in the ES position. in ES position and initiate action to place in ES position if desired.

Page 66 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 115. __ IAAT ES channels 7 & 8 have actuated, __ GOTO Step 118.

THEN perform Step 116 - 117.

116. Perform all: NOTE

__ Place ES CH 7 in MANUAL.

Voter OVERRIDE affects all channels of the

__ Place ES CH 8 in MANUAL. 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 7 fails to go to MANUAL, THEN place ODD voter in OVERRIDE.

2. __ IF ES CH 8 fails to go to MANUAL, THEN place EVEN voter in OVERRIDE.

117. __ Verify all ES channel 7 & 8 components __ Notify SRO to evaluate components NOT are in the ES position. in ES position and initiate action to place in ES position if desired.

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

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

120. __ IAAT conditions causing ES actuation have cleared, THEN initiate Encl 5.41 (ES Recovery).

121. __ WHEN CR SRO approves, THEN EXIT.

Page 67 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Unit Status ES Channels 3 & 4 have NOT actuated.

122. Start:

__ A OUTSIDE AIR BOOSTER FAN

__ B OUTSIDE AIR BOOSTER FAN 123. Notify Unit 3 to start:

__ 3A OUTSIDE AIR BOOSTER FAN

__ 3B OUTSIDE AIR BOOSTER FAN 124. Verify open: __ IF CR SRO desires 1CF-1 and 1CF-2

__ 1CF-1 open,

__ 1CF-2 THEN open:

__ 1CF-1

__ 1CF-2 125. __ Verify 1HP-410 closed. 1. __ Place 1HP-120 in HAND.

2. __ Close 1HP-120.

126. __ Secure makeup to the LDST.

127. __ Verify all ES channel 1 & 2 components 1. __ IF 1HP-3 fails to close, are in the ES position. THEN close 1HP-1.

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

3. __ IF 1HP-20 fails to close, AND NO RCPs operating, THEN close:

4. __ Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired.

128. __ Verify Unit 2 turbine tripped. __ GOTO Step 131.

129. __ Close 2LPSW-139.

130. __ Verify total LPSW flow to Unit 2 LPI __ Reduce LPSW to Unit 2 LPI coolers to coolers 6000 gpm. obtain total LPSW flow 6000 gpm.

131. __ Close 1LPSW-139.

Page 68 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 132. Place in FAIL OPEN:

__ 1LPSW-251 FAIL SWITCH

__ 1LPSW-252 FAIL SWITCH 133. __ Start all available LPSW pumps.

134. Verify either: __ GOTO Step 136.

__ Three LPSW pumps operating

__ Two LPSW pumps operating when Tech Specs only requires two operable 135. Open: __ IF both are closed:

__ 1LPSW-4 __ 1LPSW-4

__ 1LPSW-5 __ 1LPSW-5 THEN notify SRO to initiate action to open at least one valve prior to BWST level 19'.

136. __ IAAT BWST level 19', 1. __ Display BWST level using OAC Turn-on THEN initiate Encl 5.12 (ECCS Suction Code "SHOWDIG O1P1600".

Swap to RBES). 2. __ Notify crew of BWST level IAAT step.

137. __ Dispatch an operator to perform Encl 5.2 (Placing RB Hydrogen Analyzers In Service). (PS )

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

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

140. __ IAAT conditions causing ES actuation have cleared, THEN initiate Encl 5.41 (ES Recovery).

141. __ WHEN CR SRO approves, THEN EXIT.

- - END ***

Page 69 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam Subsequent Actions EP/1/A/1800/001 Parallel Actions Page 1 of 1 CONDITION ACTIONS

1. PR NIs 5% FP OR GO TO UNPP tab. UNPP NIs NOT decreasing

2. All 4160V SWGR de-energized GO TO Blackout tab. BLACKOUT

{13}

3. Core SCM indicates superheat GO TO ICC tab. ICC

4. Any SCM = 0°F GO TO LOSCM tab. LOSCM

5. Both SGs intentionally isolated to GO TO EHT tab.

stop excessive heat transfer

6. Loss of heat transfer (including LOHT loss of all Main and Emergency GO TO LOHT tab.

FDW)

7. Heat transfer is or has been GO TO EHT tab. EHT excessive

8. Indications of SGTR 25 gpm GO TO SGTR tab. SGTR

9. Turbine Building flooding NOT GO TO TBF tab. TBF caused by rainfall event

10. Inadvertent ES actuation occurred Initiate AP/1/A/1700/042 (Inadvertent ES ES Actuation).

11. Valid ES actuation has occurred Initiate Encl 5.1 (ES Actuation). ES or should have occurred

12. Power lost to all 4160V SWGR

Initiate AP/11 (Recovery from Loss and any 4160V SWGR of Power).

re-energized ROP

IF Encl 5.1 (ES Actuation) has been initiated, THEN reinitiate Encl 5.1.

13. RCS leakage > 160 gpm with Notify plant staff that Emergency Dose EDL letdown isolated Limits are in affect using PA system.

14. Individual available to make

Announce plant conditions using notifications PA system.

Notify OSM to reference the NOTIFY Emergency Plan and NSD 202 (Reportability).

Page 70 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam EHT EP/1/A/1800/001 Parallel Actions Page 1 of 1 CONDITION ACTIONS

1. PR NIs 5% FP OR GO TO UNPP tab. UNPP NIs NOT decreasing

2. All 4160V SWGR de-energized GO TO Blackout tab. BLACKOUT

3. Core SCM indicates superheat GO TO ICC tab. ICC

4. Any SCM = 0°F AND HPI forced IF LOSCM tab has NOT been entered LOSCM cooling NOT in progress due to current EHT event THEN GO TO LOSCM tab.

5. Both SGs intentionally isolated to RETURN TO beginning of EHT tab.

stop excessive heat transfer after EHT tab initiated LOHT

6. Loss of heat transfer AND at least one SG NOT isolated GO TO LOHT tab.

7. Indications of excessive RETURN TO beginning of EHT tab. EHT heat transfer in another SG after EHT tab initiated

8. Inadvertent ES actuation occurred Initiate AP/1/A/1700/042 (Inadvertent ES ES Actuation).

9. Valid ES actuation has occurred Initiate Encl 5.1 (ES Actuation). ES or should have occurred

10. Power lost to all 4160V SWGR

Initiate AP/11 (Recovery from Loss and any 4160V SWGR of Power).

re-energized ROP

IF Encl 5.1 (ES Actuation) has been initiated, THEN reinitiate Encl 5.1.

11. RCS leakage > 160 gpm with Notify plant staff that Emergency Dose EDL letdown isolated Limits are in affect using PA system.

OR SGTR .> 25 gpm

12. Individual available to make

Announce plant conditions using notifications PA system.

Notify OSM to reference the NOTIFY Emergency Plan and AD-LS-ALL-0006 (Notification

/Reportability Evaluation).

Page 71 of 73

Appendix D Required Operator Actions Form ES-D-2 ILT48 NRC Exam CRITICAL TASKS CT-1 The PORV must be isolated to isolate the source of RCS leakage and to prevent a reactor trip.

CT-2 The 1B MD EFDW Pump must be started in order to supply feedwater to the intact SG for heat removal to preclude initiation of HPI Forced Cooling.

Page 72 of 73

SAFETY: Take a Minute UNIT 0 (OSM)

SSF Operable: Yes KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 2 Fuel Handling: No UNIT STATUS (CR SRO)

Unit 1 Simulator Other Units Mode: 2 Unit 2 Unit 3 Reactor Power: Below POAH Mode: 1 Mode: 1 Gross MWE: 0 100% Power 100% Power RCS Leakage: 0.01 gpm EFDW Backup: Yes EFDW Backup: Yes No WCAP Action RBNS Rate: 0.01 gpm Technical Specifications/SLC Items (CR SRO)

Component/Train OOS Restoration TS/SLC #

Date/Time Required Date/Time SSF 2 days ago / 0400 5 days / 0400 3.10.1 A,B,C,D,E Shift Turnover Items (CR SRO)

Primary

Due to unanalyzed condition, the SSF should be considered INOP for Unit 1 if power levels are reduced below 85%. Evaluations must be performed prior to declaring the SSF operable following a return to power (after going below 85%).

1RIA-3 and 5 removed from RB.

Pressurize LDST with H2 per OP/1/A/1106/017 Encl. 4.5.

Increase Reactor power to ~7% per OP/1/A/1102/001 Encl. 4.7 beginning at step 3.36.

During the Reactor power increase, Unit 2 CRS will assume the oversight role for Unit 1.

Unit 1 CRS will assume the role of the dedicated Reactivity Management SRO.

Secondary

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

Temporary OAC alarms set on FDW Loop A and B Composite Valve Demand @ 9.8% per OP/1/A/1102/001 Encl. 4.7.

Reactivity Management (CR SRO)

Gp 7 Rod Position: Batch additions as required for volume RCS Boron 1778 ppmB 5% Withdrawn control.

Human Performance Emphasis (SM)

Procedure Use and Adherence

RO-102 Page 1 of 12 REGION II JOB PERFORMANCE MEASURE RO-102 RESPOND TO A BORON DILUTION EVENT Alternate Path: No Alt Path Failure: ____________________________________________________________

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

RO-102 Page 2 of 12 REGION II JOB PERFORMANCE MEASURE Task Title : Respond to a Boron Dilution Event Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 15 min K/A Rating(s):

System: APE 024 K/A: AA1.04 Rating: 3.6*/3.7 Task Standard:

The applicant shall borate the RCS In Accordance With AP/1/A/1700/003 (Boron Dilution)

References:

AP/1/A/1700/003 (Boron Dilution) Rev 14 Tools/Equipment/Procedures Needed:

AP/1/A/1700/003 (Boron Dilution)

=========================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

RO-102 Page 3 of 12 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS

1. RECALL SNAP 206

2. Import JPM RO-102 Sim Files

3. GO TO RUN

RO-102 Page 4 of 12 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS Unit 1 startup in progress following a 28 day refueling outage Reactor Power = 70%

Control Rods have been inserting due to RCS temperature increasing The Control Room SRO has determined that a boron dilution event is occurring INITIATING CUE The Control Room SRO has directed you to perform AP/3 (Boron Dilution)

RO-102 Page 5 of 12 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP Verify one of the following:

__ All control rods inserted.

__ RV head removed. ___ SAT STANDARD: Candidate determines that neither condition applies.

1 4.1 ___ UNSAT Continues to Step 4.1 RNO COMMENTS:

IF ICS is in Auto, THEN ensure the following:

__ Rx power < 100%

__ Control rods responding as necessary

___ SAT STANDARD: Candidate determines that reactor power is 4.1 approximately 70% and control rods are inserting due 2 to RCS temperature increasing.

RNO ___ UNSAT Continues to step 4.2 COMMENTS:

Make the following notifications:

__ PA announcement of the event including required RB evacuation

__ Notify OSM to reference the following:

RP/0/A/1000/001 (Emergency Classification)

NSD-202 (Reportability)

___ SAT

OMP 1-14 (Notifications) 3 4.2 STANDARD: Candidate makes PA announcement and notifies the

___ UNSAT OSM to reference procedures.

Continues to step 4.3 COMMENTS:

RO-102 Page 6 of 12 Verify HPI in operation.

STANDARD: Candidate verifies that the A HPIP is in operation. ___ SAT 4 4.3 Continues to step 4.4

___ UNSAT COMMENTS:

Verify Rx at power.

STANDARD: Candidate verifies that reactor power is 70%. ___ SAT 5 4.4 Continues to step 4.5

___ UNSAT COMMENTS:

Notify Chemistry to sample the following for boron concentration:

RCS

LDST

___ SAT STANDARD: Candidate notifies Chemistry to sample RCS & LDST boron concentration.

6 4.5 ___ UNSAT Continues to step 4.6 COMMENTS:

Verify both RC bleed transfer pumps stopped.

STANDARD: Candidate verifies that 1A and 1B Bleed Transfer

___ SAT Pumps are off on 1AB1: Green lights lit and Red lights off.

7 4.6

___ UNSAT Continues to step 4.7 COMMENTS:

RO-102 Page 7 of 12 Place 1HP-14 in NORMAL.

STANDARD: 1HP-14 (LDST BYPASS) should already be in NORMAL: Red light lit, Green light off. ___ SAT 8 4.7 Continues to step 4.8 ___ UNSAT COMMENTS:

Close 1HP-16.

STANDARD: 1HP-16 (LDST MAKEUP ISOLATION) should already ___ SAT be closed: Green light lit, Red light off.

9 4.8 Continues to step 4.9 ___ UNSAT COMMENTS:

Verify all demineralizers out of service.

STANDARD: Candidate determines that a demineralizer IS in ___ SAT service.

10 4.9 Continues to Step 4.9 RNO. ___ UNSAT COMMENTS:

RO-102 Page 8 of 12

1. __ IF any purification IX is in service, THEN perform the following:

A. __ Open 1HP-13.

B. __ Close 1HP-8.

C. __ Close 1HP-9 & 11.

2. __ IF any deborating IX is in service, [NONE IN SERVICE]

THEN perform the following:

A. __ Close 1CS-27.

B. __ Close 1CS-32 & 37.

C. __ Open 1CS-26. *CRITICAL STEP STANDARD: Candidate determines that a purification IX IS in 4.9 service and:

11 ___ SAT RNO Opens 1HP-13 (PURIFICATION IX BYPASS).

Red light lit, Green light off.

___ UNSAT Closes 1HP-8 (PURIFICATION IX INLET).

Red light off, Green light lit.

Closes 1HP-9 & 11 (SPARE PURIF IX INOUT &

OUTLET).

Red light off, Green light lit.

Continues to step 4.10.

COMMENTS:

Verify control rods are within allowable limits of the COLR.

STANDARD: Candidate references the COLR and determines that

___ SAT Group 7 control rods are in the Restricted Operation region of the COLR.

12 4.10

___ UNSAT Continues to step 4.12 COMMENTS:

RO-102 Page 9 of 12 Open one of the following valves to borate from the BWST:

__ 1HP-24

__ 1HP-25 STANDARD: *Candidate opens either 1HP-24 (1A HPI BWST *CRITICAL SUCTION) or 1HP-25 (1B HPI BWST SUCTION) STEP Red light lit, Green light off for the valve chosen.

13 4.12 Examiner Note: Critical portion is to open at least one of the ___ SAT valves to initiate boration.

___ UNSAT Booth Cue: Fire T01 when 1HP-24 or 1HP-25 is open.

Continues to step 4.13 COMMENTS:

Align letdown to 1A BHUT:

__ Open 1CS-26.

__ Open 1CS-41.

__ Place 1HP-14 in BLEED.

STANDARD: Candidate:

Opens 1CS-26 ( LETDOWN TO RC BHUT)

Red light lit, Green light off. ___ SAT 14 4.13 Opens 1CS-41 ( 1A RC BHUT INLET)

Red light lit, Green light off. ___ UNSAT Places 1HP-14 in BLEED Green light lit, Red light off.

Continues to step 4.14 COMMENTS:

Start the standby CC pump.

STANDARD: Candidate rotates the standby CC pump to the START position and verifies red light lit and green light off. ___ SAT 15 4.14 Continues to step 4.15 ___ UNSAT COMMENTS:

RO-102 Page 10 of 12 Throttle 1HP-7 to maximize letdown.

STANDARD: Candidate will adjust 1HP-7 (LETDOWN CONTROL) to increase letdown flow from 78 gpm to 100 to 120 ___ SAT 16 4.15 gpm

___ UNSAT Continues to step 4.16 COMMENTS:

Throttle the following as required to maintain PZR level 200 - 260:

__ 1HP-120

__ 1HP-26 STANDARD: Candidate will throttle 1HP-120 (RC Volume Control) ___ SAT or 1HP-26 (1A HP INJECTION) as needed to maintain 17 4.16 Pzr level 200 - 260.

___ UNSAT COMMENTS:

END TASK TIME STOP: ________

RO-102 Page 11 of 12 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

11 This step removes the source of De-Boration (a demineralizer that was not boron saturated).

13 This step injects borated water (BWST) to the RCS to stop control rod insertion.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Unit 1 startup in progress following a 28 day refueling outage Reactor Power = 70%

Control Rods have been inserting due to RCS temperature increasing The Control Room SRO has determined that a boron dilution event is occurring INITIATING CUE The Control Room SRO has directed you to perform AP/3 (Boron Dilution)

RO-202 Page 1 of 11 REGION II JOB PERFORMANCE MEASURE RO-202 REMOVE 1A LETDOWN COOLER FROM SERVICE Alternate Path: No Alt Path Failure: ____________________________________________________________

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

RO-202 Page 2 of 11 REGION II JOB PERFORMANCE MEASURE Task Title : Remove 1A Letdown Cooler From Service Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 15 minutes K/A Rating(s):

System: 004 K/A: Generic 2.2.2 Rating: 4.6/4.1 Task Standard:

Remove 1A Letdown Cooler from service and completely isolate the cooler utilizing OP/1/A/1104/002 (HPI System) Enclosure 4.5 (Operation of Letdown Coolers)

References:

OP/1/A/1104/002 (HPI System) Rev 167 Tools/Equipment/Procedures Needed:

OP/1/A/1104/002 (HPI System) Enclosure 4.5 (Operation of Letdown Coolers)

OP/1/A/1104/002 (HPI System) Limits and Precautions

=========================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

RO-202 Page 3 of 11 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS

1. RECALL SNAP 207

2. IMPORT FILES for RO-202

3. UPDATE status board to show RCS boron at 89 ppm

4. PROVIDE a copy of the following:

OP/1/A/1104/002 Encl 4.5 beginning at Step 3.5 with steps 3.1 through 3.4 signed off.

OP/1/A/1104/002 Limits & Precautions.

5. Place a clean copy of OMP 2-02 Attachment G in the Component Boron Concentration Log and ensure previous copy used for this JPM is removed.

6. Go to RUN and wait for 1RIA-50 to alarm and acknowledge before allowing the student to enter the simulator.

RO-202 Page 4 of 11 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS Unit 1 is at 100%

The 1A Letdown Cooler has developed a 0.5 gpm leak Unit 1 CC Surge Tank level is increasing at 4 inches per hour Unit 1 CC Surge Tank level has been lowered to allow for in-leakage It is NOT desired to valve in the spare CC Cooler It is NOT desired to place a Purification IX in service OP/1/A/1104/002 Enclosure 4.5 is complete up to Step 3.5 INITIATING CUE The Control Room SRO directs you to completely isolate the 1A Letdown Cooler per OP/1/A/1104/002 Enclosure 4.5 beginning at Step 3.5

RO-202 Page 5 of 11 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP WHILE removing the 1A Letdown Cooler from service, monitor the following:

Letdown Cooler CC outlet temperature

Letdown temperature

Letdown flow STANDARD: Monitor Letdown Cooler CC outlet temperature by ___ SAT referencing OAC graphic display.

Monitor Letdown temperature by referencing Letdown 1 3.5 temperature gauge located on 1UB1 or OAC graphic ___ UNSAT display.

Monitor Letdown flow by referencing Letdown flow gauge located on 1UB1 or OAC graphic display.

Candidate continues to Step 3.6 COMMENTS:

NOTE:

Throttling 1HP-7 does NOT affect reactivity management since IXs are NOT in service. (R.M.)

Changing Letdown Flow < 10 gpm / minute minimizes Letdown Cooler leaks:

IF 1HP-1/CC-1 are open, reduce Letdown flow to minimum by throttling closed 1HP-7 (LETDOWN CONTROL). ___ SAT STANDARD: Determine that 1HP-1/1CC-1 are open by observing 2 3.6 red open light illuminated and green closed light OFF.

___ UNSAT Reduce Letdown flow by rotating 1HP-7 setpoint dial located on 1UB1 counterclockwise until the valve is closed.

Candidate continues to Step 3.7.

COMMENTS:

RO-202 Page 6 of 11 Verify Letdown Flow < 87 gpm.

STANDARD: Verifies letdown flow on 1UB1 is < 87 gpm ___ SAT Candidate continues to Step 3.8.

3 3.7

___ UNSAT COMMENTS:

Ensure closed 1HP-1/1CC-1 (1A LETDOWN COOLER INLET).

STANDARD: Locate 1HP-1/1CC-1 switch on 1UB1 and rotates CRITICAL control switch clockwise to the closed position. STEP Verify 1HP-1 closes by observing the red open light OFF and green closed light illuminated.

___ SAT 4 3.8 Verify 1CC-1 closes by observing the red open light OFF and green closed light illuminated.

___ UNSAT Candidate continues to Step 3.9.

COMMENTS:

Record date/time 1HP-1/1CC-1 closed: _______/_______

STANDARD: Record todays date/time.

___ SAT 5 3.9 Candidate continues to Step 3.10.

COMMENTS: ___ UNSAT

RO-202 Page 7 of 11 NOTE:

Maximum Letdown Flow is 87 gpm with one Letdown Cooler in service.

Changing Letdown Flow < 10 gpm / minute minimizes Letdown Cooler leaks.

Letdown temperature should NOT exceed 120°F for extended periods of time.

Step 3.10 may be performed as many times as required.

IF required, slowly adjust 1HP-7 (Letdown Control) as required to perform the following: (Continue) ___ SAT

To provide normal letdown flow of 68-80 gpm.

6 3.10

To maintain Letdown Cooler CC outlet temperature < 225°F.

___ UNSAT STANDARD: Adjust 1HP-7 as necessary to maintain letdown flow 68-80 gpm and maintain Letdown Cooler CC outlet temperature < 225°F.

Adhere to the Note above and limits letdown flow

< 125 gpm and prevent letdown temperature from exceeding 120°F for extended periods of time.

Candidate continues to Step 3.11.

COMMENTS:

IF required, valve in spare CC Cooler to maintain Letdown Cooler CC outlet temperature < 225°F per OP/1/A/1104/008 (Component Cooling System).

STANDARD: Recognize from the Initial Conditions that it is NOT desired to place the spare CC Cooler in service. ___ SAT 7 3.11 Candidate continues to Step 3.12.

___ UNSAT Examiner Cue: If the candidate asks, inform him/her that it is NOT desired to place the spare CC Cooler in service.

COMMENTS:

RO-202 Page 8 of 11 Record boron in Component Boron Concentration Log for 1A Letdown Cooler. (R.M.) (Continue)

STANDARD: Record current RCS boron concentration, Date, Time, and Initials in the Component Boron Concentration Log (OMP 2-02 Attachment G) for the 1A Letdown ___ SAT 8 3.12 Cooler.

Candidate continues to Step 3.13. ___ UNSAT COMMENTS:

IF desired, place a Purification IX in service per OP/1/A/1103/004 B (Purification IXs). (R.M.)

STANDARD: Recognize from the Initial Conditions that it is NOT desired to place a Purification IX in service.

___ SAT 9 3.13 Candidate continues to Step 3.14.

Examiner Cue: If the candidate asks, inform him/her that it is

___ UNSAT NOT desired to place a Purification IX in service.

COMMENTS:

RO-202 Page 9 of 11 IF complete cooler isolation required, perform one of the following:

3.14.1 IF CC Surge Tank level rate of increase is 3/hour, close 1HP-3 (1A LETDOWN COOLER OUTLET).

3.14.2 IF CC Surge Tank level rate of increase is < 3/hour, perform the following:

NOTE: 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prevents forming a vacuum in cooler as piping cools down.

A. Verify 1HP-1/1CC-1 (1A LETDOWN COOLER INLET) closed for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

B. Close 1HP-3 (1A LETDOWN COOLER OUTLET).

STANDARD: Recognize from the Initial Conditions that CC Surge Tank level rate of increase is 3/hour and locates CRITICAL 10 3.14 1HP-3 control switch on 1UB1 and rotates switch in STEP the clockwise (closed) direction.

Verify 1HP-3 green closed light illuminates and red

___ SAT open light extinguishes.

Examiner Cue: If the candidate asks, inform him/her that the CC leak rate remains unchanged. ___ UNSAT Examiner Cue: Inform the candidate that another operator will complete this procedure.

COMMENTS:

END TASK TIME STOP: ________

RO-202 Page 10 of 11 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

4 Step 3 is required to isolate the 1A CC Cooler from the RCS to prevent in-leakage.

10 Step 9 is required to fully isolate the 1A CC Cooler due to leakage being greater than 3 per hour

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Unit 1 is at 100%

The 1A Letdown Cooler has developed a 0.5 gpm leak Unit 1 CC Surge Tank level is increasing at 4 inches per hour Unit 1 CC Surge Tank level has been lowered to allow for in-leakage It is NOT desired to valve in the spare CC Cooler It is NOT desired to place a Purification IX in service OP/1/A/1104/002 Enclosure 4.5 is complete up to Step 3.5 INITIATING CUE The Control Room SRO directs you to completely isolate the 1A Letdown Cooler per OP/1/A/1104/002 Enclosure 4.5 beginning at Step 3.5

RO-304a Page 1 of 13 REGION II JOB PERFORMANCE MEASURE RO-304a PERFORM RULE 2 FOLLOWING A LOSCM Alternate Path: Yes Alt Path Failure: ES Channel 2 Fails to go to MANUAL Time Critical: Yes Time Critical Criteria: Secure RCPs within 2 minutes of losing SCM Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

RO-304a Page 2 of 13 REGION II JOB PERFORMANCE MEASURE Task

Title:

Perform Rule 2 following a LOSCM Task Number: N/A Alternate Path: Yes Time Critical: Yes Validation Time: 10 minutes K/A Rating(s):

System: E/APE 011 K/A: EA2.11 Rating: 3.9/4.3 Task Standard:

Perform a symptom check and initiate Rule 2. Trip RCPs within 2 minutes. Place EVEN Voters in Override and throttle HPI flow to within limits. .

References:

EP/1/A/1800/001 (Emergency Operating Procedure) Rev 40C Tools/Equipment/Procedures Needed:

EP/1/A/1800/001 (Emergency Operating Procedure) Rule 2 (Loss of SCM)

=========================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

RO-304a Page 3 of 13 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS

1. RECALL SNAP 208

2. IMPORT FILES for RO-304a

3. Go to RUN when directed by the Lead Examiner

RO-304a Page 4 of 13 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS The Reactor was operating at 100% power The Reactor has just tripped You are the BOP Reactor Operator INITIATING CUE As the BOP, perform a Symptoms Check NOTE: Portions of this JPM are time critical.

RO-304a Page 5 of 13 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP Perform a Symptoms Check CRITICAL STEP STANDARD: Candidate performs a Symptoms Check and determines that a Loss of SCM has occurred due to any SCM 0°F and initiates Rule 2 in accordance with OMP 1-18 Attachment C. ___ SAT 1

Examiner Cue: As the SRO, if asked, concur with performing Rule 2 ___ UNSAT COMMENTS:

IAAT all exist:

__ Any SCM 0°F

__ Rx power 1%

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

STANDARD: Candidate determines that SCM is 0°F by observing the indications on the ICCM plasma display and/or standout SCM displays both located on 1UB1. ___ SAT 2 1 Candidate verifies Rx power is 1% by observing the Power Range and/or Wide Range NIs located on 1UB1. ___ UNSAT Candidate determines that 2 minutes has elapsed since the loss of SCM.

Candidate continues to step 2.

COMMENTS:

RO-304a Page 6 of 13 Stop all RCPs.

CRITICAL STANDARD: Stop all RCPs by locating the RCP switches located STEP on 1AB1 and rotate the switches to the TRIP position.

Verify that the green stop light is LIT and pump amps ___ SAT 3 2 go to zero.

Candidate continues to step 3. ___ UNSAT COMMENTS:

Notify CRS of RCP status.

STANDARD: Notify CRS that all RCPs have been secured.

___ SAT Examiner Cue: As the SRO, acknowledge the report of RCP status.

4 3

___ UNSAT Candidate continues to step 4.

COMMENTS:

Verify Blackout exists.

STANDARD: Determine that a blackout does not exist by observing power available on the Main Feeder Bus volt meters located on 1AB1.

___ SAT 5 4 Candidate continues to the RNO column and determine the correct procedure path is to GO TO Step 6. ___ UNSAT COMMENTS:

RO-304a Page 7 of 13 Open:

__ 1HP-24

__ 1HP-25 STANDARD: Verify that the above valves are open by observing ___ SAT their red open light LIT and green light off on 1UB1.

6 6 Note: These valves will already be open due to ES actuation.

___ UNSAT Candidate continues to step 7.

COMMENTS:

Start all available HPI pumps.

STANDARD: Verify that all three HPI pumps are operating by observing their red lights lit and green lights off .

___ SAT 7 7 Note: All HPI pumps will be operating due to ES actuation.

Candidate continues to step 8. ___ UNSAT COMMENTS:

GO TO Step 13

___ SAT STANDARD: Proceed to Step 13 8 8

___ UNSAT COMMENTS:

Open:

__ 1HP-26

__ 1HP-27 STANDARD: Verify that the above valves are open by observing their red open light LIT on 1UB1. ___ SAT 9 13 Note: These valves will already be open due to ES actuation.

___ UNSAT Candidate continues to step 14.

COMMENTS:

RO-304a Page 8 of 13 Verify at least two HPI pumps are operating using two diverse indications

___ SAT STANDARD: All 3 HPIPs will be operating due to ES actuation.

10 14 Candidate continues to step 15.

___ UNSAT COMMENTS:

IAAT 2 HPI pumps operating, AND HPI flow in any header is in the Unacceptable Region of Figure 1 THEN perform Steps 16 - 21.

STANDARD: Determine that HPI flow is NOT in the unacceptable

___ SAT region per Figure 1.

11 15 Candidate goes the RNO step and continues to step

___ UNSAT 17.

COMMENTS:

IAAT flow limits are exceeded, Pump Operation Limit 1 HPI pump/hdr 475 gpm (incl. seal injection for A hdr) 1A & 1B HPI Total flow of 950 gpm pumps operating (incl. seal injection) CRITICAL with 1HP-409 open STEP THEN perform Steps 18 - 20.

17 ___ SAT 12 STANDARD: Determine that 1B HPI Header flow is > 475 gpm by observing the 1B HPI Header Flow gauge located on ___ UNSAT 1UB1.

Candidate continues to step 18.

COMMENTS:

RO-304a Page 9 of 13 Place Diverse HPI in BYPASS.

STANDARD: Depresses the DIVERSE HPI BYPASS BYPASS ___ SAT pushbutton on 1UB1.

13 18 Candidate continues to step 19. ___ UNSAT COMMENTS:

[ALTERNATE PATH]

Perform both:

__ Place ES CH 1 in MANUAL.

__ Place ES CH 2 in MANUAL.

___ SAT STANDARD: Places ES CH 1 in MANUAL and recognizes that ES 14 19 CH 2 fails to go to MANUAL.

___ UNSAT Candidate continues to step 19 RNO.

COMMENTS:

1. __ IF ES CH 1 fails to go to MANUAL, THEN place ODD voter in OVERRIDE.

CRITICAL

2. __ IF ES CH 2 fails to go to MANUAL, THEN place EVEN voter in STEP OVERRIDE.

19 ___ SAT 15 STANDARD: Places the EVEN Voter in OVERRIDE.

RNO Candidate continues to step 20. ___ UNSAT COMMENTS:

Throttle HPI to maximize flow flow limit. CRITICAL STEP STANDARD: Throttles 1HP-27 to maximize HPI flow to less than 475 gpm.

___ SAT 16 20 Candidate continues to step 21.

___ UNSAT COMMENTS:

RO-304a Page 10 of 13 Notify CRS of HPI status.

STANDARD: Candidate notifies SRO that 1HP-27 has been ___ SAT throttled.

17 21 Candidate continues to step 22. ___ UNSAT COMMENTS:

Verify RCS pressure > 550 psig.

STANDARD: Determines that RCS pressure is < 550 psig. ___ SAT 18 22 Candidate continues to RNO.

___ UNSAT COMMENTS:

Ensure ES Channels 3 and 4 actuated.

STANDARD: ES Channels 3 and 4 actuated when the LOCA ___ SAT occurred.

22 19 RNO Candidate continues to step 23. ___ UNSAT COMMENTS:

IAAT either exists:

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

__ Only one LPI header in operation with header flow 2900 gpm THEN GO TO Step 24. ___ SAT 20 23 STANDARD: Determines that total LPI flow exceeds 3400 gpm.

___ UNSAT Candidate continues to step 24.

COMMENTS:

RO-304a Page 11 of 13 Perform the following:

__ Place 1FDW-315 in MANUAL and close.

__ Place 1FDW-316 in MANUAL and close.

__ Place 1FDW-35 in HAND and close.

__ Place 1FDW-44 in HAND and close.

___ SAT STANDARD: Places the above controllers in MANUAL/HAND and 21 24 closes their respective valves.

___ UNSAT COMMENTS:

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

STANDARD: Notifies crew that performance of Rule 3 is NOT ___ SAT required.

22 25

___ UNSAT COMMENTS:

WHEN directed by CRS, THEN EXIT.

STANDARD: Notifies CRS that the step has been reached to exit the

___ SAT Rule.

23 26

___ UNSAT COMMENTS:

END TASK TIME STOP: ________

RO-304a Page 12 of 13 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

1 Rule 2 should be selected based on the symptoms.

3 RCPs are required to be stopped within 2 minutes of a loss of SCM.

12 1B HPI Header flow must be reduced 475 gpm for pump runout.

15 Must place Even Voter in override to be able to throttle 1HP-27.

16 Must throttle 1HP-27 to prevent damage due to runout.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS The Reactor was operating at 100% power.

The Reactor has just tripped.

You are the BOP Reactor Operator.

INITIATING CUE As the BOP, perform a Symptoms Check.

NOTE: Portions of this JPM are time critical.

RO-503 Page 1 of 9 REGION II JOB PERFORMANCE MEASURE RO-503 PUMP THE QUENCH TANK Alternate Path: No Alt Path Failure: ____________________________________________________________

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

RO-503 Page 2 of 9 REGION II JOB PERFORMANCE MEASURE Task

Title:

Pump the Quench Tank Task Number: N/A Alternate Path: No Time Critical: No Validation Time: 10 minutes K/A Rating(s):

System: 007 K/A: A1.01 Rating: 2.9/3.1 Task Standard:

Utilize OP/1/A/1104/017 Enclosure 4.1 to lower Quench Tank level to a band of 75 to 78 inches and isolate the flowpath to 1A Bleed Holdup Tank.

References:

OP/1/A/1104/017 (Quench Tank Operation) Rev 48 Tools/Equipment/Procedures Needed:

OP/1/A/1104/017 Limits & Precautions OP/1/A/1104/017 Enclosure 4.1 (Pumping QT)

=========================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

RO-503 Page 3 of 9 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS

1. RECALL SNAP 210

2. Place T/O sheet tags on QT Drain Pump and Component Drain Pump

3. Update Boron Status board to show:

Last 1A BHUT boron sample as being > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months old

1A BHUT Boron = 2553 ppm

RCS Boron = 2414 ppm

4. Provide a copy of OP/1/A/1104/017 Enclosure 4.1 with the following:

Limits & Precautions

Steps 1.1 through 1.4 signed off

5. Go to RUN when directed by the Lead Examiner

RO-503 Page 4 of 9 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS Unit 1 is Shutdown Unit 1 Quench Tank level is 86 inches Quench Tank is aligned to 1A BHUT .1 (Pumping QT) of OP/1/A/1104/017 (Quench Tank Operation) is in progress and complete up to Step 2.1 In preparation for an upcoming test, Unit 1 Quench Tank level is required to be within a band of 75 to 78 inches INITIATING CUE The CRS directs you to use the COMPONENT DRAIN PUMP and the QUENCH TANK DRAIN PUMP to pump the Quench Tank to 1A BHUT beginning at Step 2.1 of Enclosure 4.1 of OP/1/A/1104/017 to a Quench Tank level of ~ 77 inches.

RO-503 Page 5 of 9 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP CRITICAL Ensure open:

STEP

__ 1CS-5 (COMPONENT DRN PUMP SUCTION)

__ 1CS-6 (COMPONENT DRN PUMP SUCTION)

STANDARD: Ensure 1CS-5 and 1CS-6 are open by taking the ___ SAT control switches located on 1AB1 to the open position and verifying red open light illuminated and green 1 2.1 ___ UNSAT closed light OFF.

Candidate continues to Step 2.2.

COMMENTS:

IF QT level will be maintained in normal operating band:

2.2.1 IF desired, start COMPONENT DRAIN PUMP.

2.2.2 IF desired, start QUENCH TANK DRAIN PUMP.

2.2.3 At desired level, perform the following: ___ SAT

Ensure stopped COMPONENT DRAIN PUMP

Ensure stopped QUENCH TANK DRAIN PUMP ___ UNSAT 2.2.4 IF pump(s) automatically stop, ensure QT level 80 inches.

2 2.2 STANDARD: Recognize from the Initial Conditions that this step is not applicable due to pumping the QT below 80 inches. Marks this step as Not Applicable (N/A).

Candidate continues to Step 2.3 COMMENTS:

RO-503 Page 6 of 9 IF QT level is to be reduced below low level setpoint of 80 inches, perform the following:

2.3.1 Ensure RCS pressure < 45 psig.

2.3.2 *IF desired, place COMPONENT DRAIN PUMP to BYPASS

CRITICAL 2.3.3 *IF desired, place QUENCH TANK DRAIN PUMP to BYPASS STEP 2.3.4 *At desired level (75 to 78 inches), perform the following:

Ensure stopped COMPONENT DRAIN PUMP

Ensure stopped QUENCH TANK DRAIN PUMP ___ SAT STANDARD: Determine from the Initial Conditions that QT level will be reduced below 80 inches

___ UNSAT Locate RCS pressure from the Low Range Cooldown Pressure indication on 1UB2 and ensures that RCS pressure is < 45 psig.

Place the COMPONENT DRAIN PUMP switch in the BYPASS position AND Pull the switch up.

Place the QUENCH TANK DRAIN PUMP switch in 3 2.3 the BYPASS position AND Pull the switch up.

Stop the COMPONENT DRAIN PUMP and the QUENCH TANK DRAIN PUMP by rotating the switch to STOP when QT level reaches 75 inches.

Note: The low level cut-off for the Component Drain Pump and Quench Tank Drain Pump will trip the pumps at 80 inches if the pump switches are not taken to BYPASS and pulled up (similar to a PTL position).

Note: The candidate must start either the COMPONENT DRAIN PUMP or the QUENCH TANK DRAIN PUMP in the bypass position to complete the task. The candidates instructions were to use both pumps.

Candidate continues to Step 2.4 COMMENTS:

RO-503 Page 7 of 9

CRITICAL Perform the following:

STEP

__ *Close 1CS-5 (COMPONENT DRN PUMP SUCTION)

__ *Close 1CS-6 (COMPONENT DRN PUMP SUCTION)

___ SAT STANDARD: Close 1CS-5 and 1CS-6 by placing each control switch in the closed position. The green closed light illuminates and the red open light extinguishes.

4 2.4

___ UNSAT Candidate continues to Step 2.5 Note: Closing EITHER 1CS-5 or 1CS-6 satisfies the Critical Step.

COMMENTS:

IF 1A BHUT boron sample > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months old AND QT pumped to 1A BHUT, perform the following:

2.5.1 Verify closed 1CS-46 (1A RC BLEED XFER PUMP DISCHARGE).

2.5.2 Dispatch NEO to observe 1A Bleed Transfer Pump discharge pressure.(1CS-PG-0084)

___ SAT 2.5.3 Start 1A BLEED TRANSFER PUMP.

Booth Cue: When called, report as AO: I am standing by to

___ UNSAT read 1A BTP discharge pressure at 1CS-PG-0084.

STANDARD: Verifies 1CS-46 (1A RC BLEED XFER PUMP DISCHARGE) is closed by observing green closed light illuminated and red open light off.

5 2.5 Candidate dispatches a AO to observe 1A Bleed Transfer Pump discharge pressure.(1CS-PG-0084).

Candidate starts 1A BLEED TRANSFER PUMP and observes red light illuminated and green light off.

Examiner Cue: When 1A BLEED TRANSFER PUMP is started inform the candidate that another operator will continue this procedure.

COMMENTS:

END TASK TIME STOP: ________

RO-503 Page 8 of 9 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

1 Step is required to align the flow path from the QT to 1A BHUT.

3 This step is required to begin the level decrease in the Quench Tank. Placing the switch in the BYPASS position is required to decrease QT level below 80 inches. Ensuring both pumps are secured is required to prevent pumping the QT below 75 inches.

4 This step isolates the flow path from the QT to 1A BHUT

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Unit 1 is Shutdown Unit 1 Quench Tank level is 86 inches Quench Tank is aligned to 1A BHUT .1 (Pumping QT) of OP/1/A/1104/017 (Quench Tank Operation) is in progress and complete up to Step 2.1 In preparation for an upcoming test, Unit 1 Quench Tank level is required to be within a band of 75 to 78 inches INITIATING CUE The CRS directs you to use the COMPONENT DRAIN PUMP and the QUENCH TANK DRAIN PUMP to pump the Quench Tank to 1A BHUT beginning at Step 2.1 of Enclosure 4.1 of OP/1/A/1104/017 to a Quench Tank level of ~ 77 inches.

RO-602 Page 1 of 10 REGION II JOB PERFORMANCE MEASURE RO-602 RESTORE SECONDARY LOADS AFTER LOSS OF OFFSITE POWER Alternate Path: No Alt Path Failure: ____________________________________________________________

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

RO-602 Page 2 of 10 REGION II JOB PERFORMANCE MEASURE Task

Title:

Restore Secondary Loads After Loss of Offsite Power Task Number: N/A Alternate Path: No Time Critical: No Validation Time: 15 minutes K/A Rating(s):

System: 062 K/A: A4.01 Rating: 3.3/3.1 Task Standard:

Properly align secondary loads following a loss of offsite power by procedure.

References:

AP/1/A/1700/011 (Recovery From Loss of Power) Rev 55 Tools/Equipment/Procedures Needed:

AP/1/A/1700/011 (Recovery From Loss of Power)

=========================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

RO-602 Page 3 of 10 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS

1. RECALL SNAP 213

2. IMPORT RO-602 files

3. PROVIDE a copy of AP/11 signed off up to step 4.27

RO-602 Page 4 of 10 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS A Switchyard Isolation has occurred from 100% power A Load Shed has NOT occurred All 4160 volt switchgear has been re-energized by the overhead power path from a Keowee Hydro unit 5 minutes have elapsed since the loss of offsite power Condensate system operation is desired AP/1/A/1700/011 (Recovery From Loss of Power) is in progress and completed up to step 4.27 INITIATING CUE The CRS directs you to continue AP/1/A/1700/011 (Recovery From Loss of Power) beginning at step 4.27

RO-602 Page 5 of 10 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP Verify both:

__ Condensate flow has been lost for < 25 minutes

__ Condensate system operation is desired

___ SAT STANDARD: Candidate recognizes from the initial conditions that Condensate flow has been lost for 5 minutes and that ___ UNSAT 1 4.27 Condensate system operation is desired COMMENTS:

___ SAT Place all HWP control switches to OFF STANDARD: Candidate places the 1A, 1B, and 1C HWP switches in ___ UNSAT the OFF position located on 1AB1.

2 4.28 COMMENTS:

Place all CBP control switches to OFF STANDARD: Candidate places the 1A and 1C CBP switches in the

___ SAT OFF position located on 1AB1.

3 4.29 COMMENTS: ___ UNSAT

RO-602 Page 6 of 10 Place in MANUAL and close:

__ 1FDW-65

___ SAT STANDARD: Candidate places the 1FDW-53 and 1FDW-65 Moore 4 4.30 controllers in MANUAL and ensures the valves are closed located on 1VB3. ___ UNSAT COMMENTS:

Place 1C-10 FAIL SWITCH in MANUAL CRITICAL STEP STANDARD: Candidate places the 1C-10 FAIL SWITCH in MANUAL located on 1VB1. ___ SAT 5 4.31 COMMENTS: ___ UNSAT Close 1C-10 CRITICAL STEP STANDARD: Candidate places the 1C-10 Moore controller in MANUAL and ensures the valves is closed located on ___ SAT 1VB1.

6 4.32

___ UNSAT COMMENTS:

Make plant page to clear basement and third floor of non-essential personnel

___ SAT STANDARD: Candidate makes a PA announcement to clear the turbine building basement and third floor of non-essential personnel. ___ UNSAT 7 4.33 COMMENTS:

RO-602 Page 7 of 10 Start one HWP CRITICAL STEP STANDARD: Candidate starts one Hotwell pump by rotating the control switch to the start positon and observing the ___ SAT red light lit and green light off located on 1AB1.

8 4.34

___ UNSAT COMMENTS:

Verify < 25 minutes elapsed since loss of condensate STANDARD: Candidate verifies that < 25 minutes have elapsed ___ SAT since the loss of condensate.

9 4.35

___ UNSAT COMMENTS:

Throttle 1C-10 controller 10% open to satisfy 25 minute system CRITICAL restart criteria.

STEP STANDARD: Candidate throttles the 1C-10 Moore controller to ___ SAT 10% open.

10 4.36

___ UNSAT COMMENTS:

WHEN FWP SUCT HDR PRESS (1VB3) is 100 psig, THEN open 1C-10

___ SAT STANDARD: Candidate locates FWP SUCT HDR PRESS gauge located on 1VB3 and ensures the gauge increase to 100 psig and then opens 1C-10 using the Moore ___ UNSAT 11 4.37 controller located on 1VB1.

COMMENTS:

RO-602 Page 8 of 10 Place 1C-10 Fail Open Switch in FAIL OPEN STANDARD: Candidate places the 1C-10 FAIL OPEN SWITCH in ___ SAT FAIL OPEN located on 1VB1.

12 4.38

___ UNSAT COMMENTS:

Maximize total recirc flow < 1200 gpm with one of the following: