ML19115A252: Difference between revisions

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

Page 17 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 5 Page 3 of 3 Event

Description:

Controlling NR Tave Fails High (I: OATC, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/028 Section 4A Crew Response:

SRO/OATC 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

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. (next page)

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).

Examiner Note: Crew Brief opportunity.

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

Page 18 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Page 19 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 6 Page 1 of 9 Event

Description:

21 gpm Primary to Secondary Leak in 1B SG (R: OATC, SRO)

Time Position Applicants 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 SRO will enter AP/1/A/1700/031 (Primary To Secondary Leakage)

AP/1/A/1700/031 (Primary to Secondary Leakage) rev 021 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 20 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 6 Page 2 of 9 Event

Description:

21 gpm Primary to Secondary Leak in 1B SG (R: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/0031 Crew Response:

SRO 4.1 IAAT primary to secondary leak rate is 25 gpm ( 36,000 gpd),

THEN GO TO Unit 1 EOP.

OATC/BOP 4.2 IAAT either of the following exists for 1RIA-54:

__ is in High alarm

__ inoperable THEN perform Steps 4.3 - 4.4.

RNO: GO TO Step 4,5 4.5 Initiate notification of the following:

__ OSM to reference the following:

OMP 1-14 (Notifications)

__ 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]

4.8 Dispatch AO to reroute Unit 1 CSAE drains to the CST per OP/1-2/A/1106/016 (Condenser Vacuum System).

4.9 Initiate Encl 5.2 (Reduction of Secondary Leakage and Cross-Unit Contamination).(page 28) 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).

This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the Lead Examiner.

Page 21 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 6 Page 3 of 9 Event

Description:

21 gpm Primary to Secondary Leak in 1B SG (R: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/031 Crew Response:

SRO 4.87 Determine primary to secondary leakage rate using OAC point O1P1599 (EST TOTAL PRI TO SEC LEAK RATE).

OATC/BOP 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 24)

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

OP/1/A/1102/010 (Controlling Procedure for Unit Shutdown)

Examiner Note: Focus Brief opportunity.

Examiner Note: Per Encl 5.1, if the leak rate is > 150 gpd, the requirement is to be < 50% in one hour and Mode 3 in three hours.

Booth Cue: If asked, Unit 2 will continue actions in AP/31 after the SRO enters AP/29 Booth Cue: If the crew chooses to use the OP to shut down the unit, call as the SM and direct the crew to use AP/29 to shut down the Reactor.

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 22 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 6 Page 4 of 9 Event

Description:

21 gpm Primary to Secondary Leak in 1B SG (R: OATC, SRO)

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 MS line and the Powdex.

OATC/BOP 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 > 150 gpd SRO Required Action: Be in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and Mode 5 in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months TS 3.4.9 Pressurizer Condition A anytime Pressurizer exceeds 260 in Mode 1 or 2 Required Action: Restore level to within limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the Lead Examiner.

Page 23 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 6 Page 5 of 9 Event

Description:

21 gpm Primary to Secondary Leak in 1B SG (R: OATC, SRO)

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

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 26) 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 24 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 6 Page 6 of 9 Event

Description:

21 gpm Primary to Secondary Leak in 1B SG (R: OATC, SRO)

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

4.10 Verify both Main FDW pumps running.

SRO/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.

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 25 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 6 Page 7 of 9 Event

Description:

21 gpm Primary to Secondary Leak in 1B SG (R: OATC, SRO)

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

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

4.18 Start the TURBINE MOTOR SUCTION PUMP.

4.19 IAAT both of the following apply:

__ ICS in automatic

__ NI power is 18%

THEN deselect MAXIMUM RUNBACK.

4.20 Verify Turbine-Generator shutdown is required.

4.21 WHEN NI power 18%, THEN depress turbine TRIP pushbutton.

4.22 Verify all TURBINE STOP VALVES closed.

AP/1/A/1700/029 Encl 5.1 AP/29 Enclosure 5.1 (Support Actions During Rapid Unit Shutdown)

BOP 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.

8. Verify Turbine-Generator shutdown is required.

This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the Lead Examiner.

Page 26 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 6 Page 8 of 9 Event

Description:

21 gpm Primary to Secondary Leak in 1B SG (R: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/029 Encl. 5.1 Crew Response:

SRO/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-53

__ 1FDW-65

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

TS 3.10.1 STANDBY SHUTDOWN FACILITY Conditions A-E are applicable due to Reactor power being < 85%

which makes the SSF inoperable Required Action: Restore SSF systems to OPERABLE status (7 days)

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 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 6 Page 9 of 9 Event

Description:

21 gpm Primary to Secondary Leak in 1B SG (R: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/031 Encl. 5.2 Crew Response:

SRO/BOP AP/31 Encl 5.2

1. Verify AS header being supplied by Unit 2 or 3 RNO: Initiate Encl 5.33 (Swapping Aux Steam Header to Another Unit) of the Unit 1 EOP Examiner Note: The remaining steps in AP/31 Encl 5.2 are performed outside the control room by an Auxiliary Operator so they were not included.

EOP Encl 5.33 (Swapping Aux Steam Header to Another Unit)

1. Notify Secondary Chemist of AS header transfer

2. Adjust 1MS-126 & 1MS-129 controller setpoint to 280 psig

3. Notify unit CR that will be supplying AS of Unit 1 header setpoint reduction

4. Notify unit CR that will be supplying AS to perform transfer per the appropriate AS system procedure

5. WHEN notified by other unit to secure MS to AS, THEN continue

6. Ensure 1MS-126 & 1MS-129 controller in MANUAL

7. Reduce 1MS-126 & 1MS-129 valve position demand to zero

8. Close 1MS-24

9. Close 1MS-33

10. EXIT this enclosure 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 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 7 Page 1 of 12 Event

Description:

Spurious Turbine Trip, 1B SGTR (M: All)

Time Position Applicant's Actions or Behavior Plant Response:

Reactor trips 1SA-8/B-9 RM Process Monitor Radiation High 1SA8/D10 (RM CSAE EXHAUST RADIATION HIGH)

Crew Response:

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

The SRO will declare Emergency Dose Limits in effect once the transfer to the SGTR tab is made.

IMAs EOP Immediate Actions 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 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 of EFDW) Cooling (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 59,60), gpm)

Area monitor alarms (RIA-16/17)

This event is complete when the 1B SG is isolated, or when directed by the Lead Examiner.

Page 29 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 7 Page 2 of 12 Event

Description:

Spurious Turbine Trip, 1B SGTR (M: All)

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

Examiner Note: The crew may not recognize the SGTL has degraded into a SGTR initially so steps in the SA tab were included. When the crew recognizes the SGTR, they should transfer to the SGTR tab (Page 33) as directed by the Subsequent Actions, Parallel Action Page (Page 50).

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

RNO: 1. Open:

__ 1HP-24

__ 1HP-25

2. Secure makeup to LDST

3. IF CRDs are energized, THEN:

A. Initiate regulating control rod insertion to the IN LIMIT B. Dispatch one operator to open 600V CRD breakers:

__ 1X9-5C (U1 CRD NORM FDR BKR) (U1 Equip Rm)

__ 2X1-5B (U1 CRD ALT FDR BKR) (T3/Dd-28) 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)

This event is complete when the 1B SG is isolated, or when directed by the Lead Examiner.

Page 30 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 7 Page 3 of 12 Event

Description:

Spurious Turbine Trip, 1B SGTR (M: All)

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

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 42)

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.

This event is complete when the 1B SG is isolated, or when directed by the Lead Examiner.

Page 31 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 7 Page 4 of 12 Event

Description:

Spurious Turbine Trip, 1B SGTR (M: All)

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

4.27 Place switches in CLOSE:

__ 1FDW-31

__ 1FDW-40 4.28 Verify SFP Cooling: {42}

__ 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 1B SG is isolated, or when directed by the Lead Examiner.

Page 32 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 7 Page 5 of 12 Event

Description:

Spurious Turbine Trip, 1B SGTR (M: All)

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

1. Verify Rx tripped.

2. Maintain Pzr level 140 - 180 [175 - 215 acc] by initiating Encl 5.5 (Pzr and LDST Level Control). (Page 42)

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.

CT-2 4. Start:

__ A OUTSIDE AIR BOOSTER FAN

__ 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.

28. Secure any unnecessary offsite release paths. (Main Vacuum Pumps, TDEFDWP, Emergency Steam Air Ejector, etc.).

29. Verify Main FDW or EFDW controlling properly.

30. Open:

__ 1HP-24

__ 1HP-25 This event is complete when the 1B SG is isolated, or when directed by the Lead Examiner.

Page 33 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 7 Page 6 of 12 Event

Description:

Spurious Turbine Trip, 1B SGTR (M: All)

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

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)

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 NOTE 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 This event is complete when the 1B SG is isolated, or when directed by the Lead Examiner.

Page 34 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 7 Page 7 of 12 Event

Description:

Spurious Turbine Trip, 1B SGTR (M: All)

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

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.

CT-3 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]

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 41 - 43.

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.

This event is complete when the 1B SG is isolated, or when directed by the Lead Examiner.

Page 35 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 7 Page 8 of 12 Event

Description:

Spurious Turbine Trip, 1B SGTR (M: All)

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

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.

47. Initiate a cooldown as follows:

__ Decrease SG pressure to 835 - 845 psig using any of the following:

TBV setpoint adjusted to 710 - 720 psig TBVs in manual ADVs

__ Maximize cooldown rate limited only by the ability to maintain Pzr level > 100 [180 acc].

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 50 - 52.

RNO: GO TO Step 53.

50. Verify TBVs available for steaming affected SGs.

51. Open on all affected SGs:

1A SG 1B SG 1MS-17 1MS-26 This event is complete when the 1B SG is isolated, or when directed by the Lead Examiner.

Page 36 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 7 Page 9 of 12 Event

Description:

Spurious Turbine Trip, 1B SGTR (M: All)

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

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

54. Verify a SG without a tube leak is available to supply the Aux Steam 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.

This event is complete when the 1B SG is isolated, or when directed by the Lead Examiner.

Page 37 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 7 Page 10 of 12 Event

Description:

Spurious Turbine Trip, 1B SGTR (M: All)

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

69. GO TO applicable step based on number of RCPs operating:

Number of RCPs Applicable Operating Step 4 70 1,2 or 3 71 None 91

70. Stop one RCP in B loop

71. Verify steaming both SGs.

72. Verify SG to be isolated is being steamed to prevent overfill per Steps 49-52 CT-4 RNO: 1. Place the following in HAND and reduce demand to 0% on SG with largest tube rupture 1A SG 1B SG 1A TBVs 1B TBVs

2. GO TO Step 74

74. Verify ADVs being used to steam RNO: GO TO Step 76

76. Place in HAND and reduce demand to 0% on SG with largest tube rupture:

1A SG 1B SG 1FDW-35 1FDW-44 1FDW-32 1FDW-41 This event is complete when the 1B SG is isolated, or when directed by the Lead Examiner.

Page 38 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 7 Page 11 of 12 Event

Description:

Spurious Turbine Trip, 1B SGTR (M: All)

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

77. Place in MANUAL and close on SG with largest tube rupture 1A SG 1B SG 1FDW-315 1FDW-316

78. Verify SG to be isolated is being steamed to prevent overfill per Steps 49-52 RNO: 1. Close on the SG with the largest tube rupture:

1A SG 1B SG 1MS-17 1MS-26

2. GO TO Step 80

80. Verify ADVs being used to steam RNO: GO TO Step 82

82. Place control switch in CLOSE on SG with largest tube rupture:

1A SG 1B SG 1FDW-31 1FDW-40 1FDW-33 1FDW-42

83. Place control switch in OFF on SG with largest tube rupture:

1A SG 1B SG 1A 1B MDEFDWP MDEFDWP This event is complete when the 1B SG is isolated, or when directed by the Lead Examiner.

Page 39 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 7 Page 12 of 12 Event

Description:

Spurious Turbine Trip, 1B SGTR (M: All)

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

84. Close on SG with largest tube rupture:

1A SG 1B SG 1FDW-372 1FDW-382 1FDW-36 1FDW-45 1FDW-38 1FDW-47 1FDW-368 1FDW-369 1SD-2 1SD-5 1SD-27 1SD-290 1SD-358 1SD-418 1SD-420 1SD-419 1SD-421

85. Dispatch an operator to perform Encl 5.28 (Local SG Isolation) to complete isolation of SG with largest tube rupture

86. Verify both are closed:

__ 1MS-24

__ 1MS-33

87. Initiate AP/31 (Primary to Secondary Leakage) Encl 5.2 (Reduction of Secondary Leakage and Cross-Unit Contamination).

88. GO TO applicable step based on number of RCPs operating:

Number Of RCPs Applicable Operating Step 4 89 1, 2, or 3 191 None 91 This event is complete when the 1B SG is isolated, or when directed by the Lead Examiner.

Page 40 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 41 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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

1HP-25 following:

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 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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.

1HP-27

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 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 AD-LS-ALL-0006.

Page 50 of 52

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam CRITICAL TASKS CT-1 ICS must be taken to HAND and FDW adjusted to prevent tripping the reactor on RPS Low Pressure (1810 psig) or RPS Variable Low Pressure. Adjustment will be dependent on how much time it takes to place ICS in HAND.

CT-2 Outside Air Booster Fans are started to minimize radiation exposure to control room personnel. (Within 30 minutes of SGTR) TCA #20 CT-3 Decrease SCM ( 5-20°F) to decrease leak size prior to SG overfill (water in MS Line)

CT-4 Isolate steaming of the 1B SG within 20 minutes of RCS temperature decreasing below 532°F Page 51 of 52

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: 894 100% 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.

SASS is in Manual for calibration C GWD tank release is in progress per OP/1-2/A/1104/018 Just after or during a GWD release, 1SA-8/B-9 may alarm from RIA-32 sample point selected to 1 PRV System Filter Discharge. IF 1SA-8/B-9 is due to RIA 1 PRV System Filter Discharge, it can be considered an expected alarm Secondary AMSAC/DSS bypassed for calibration Unit 2 is supplying the AS header The Voltage Regulator is in Manual and ready to be placed back in Auto.

BOP is to perform OP/1/A/1106/001 Encl 4.8 to lower MVARs to 150 +/- 10 MVARs with the Voltage Regulator in AUTO.

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 ILT16-1 NRC Exam Facility: Oconee Scenario No.: 2 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________SRO

________________________ ________________________OATC

________________________ ________________________BOP Initial Conditions:

Reactor Power = 50%

Turnover:

SASS is in Manual AMSAC/DSS is Bypassed C GWD tank release is in progress Event Malfunction Event Event Type* Description No. No.

0a Override AMSAC/DSS Bypassed 0b Override SASS in Manual 1 Override C: BOP, SRO (TS) Pump RBNS (1LWD-1 Fails to Close)

MSS200 2 C: BOP, SRO (TS) Condenser Vacuum Leak MSS200D MPI050 3 I: OATC, SRO Loop B RCS Flow Fails Low MPI080 Oil Leak on Main Turbine Requires Manual Power 4 R: OATC, SRO Reduction 5 N: BOP, SRO Swap Auxiliaries Due to Oil Leak on B LP Turbine MEL220 1TB Lockout Causes a Loss of 1A2 and 1B2 RCPs 6 MPI290 C: OATC, SRO Requiring a Manual Reactor Trip MPI300 Large Break LOCA 1A LPI Pump Fails 7 MPS400 M: ALL 1B LPI Pump Fails to Start on ES (1B LPIP can be started manually)

Switch Will Not Stop 1A1 RCP When Securing Per Rule 2

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

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Scenario 2 Event Summary Event 1: When the crew takes the shift, they will be required to pump the Reactor Building Normal Sump due to high level. When the operator begins to secure the alignment, LWD-1 will fail to close. This will require the SRO to evaluate Tech Specs and enter the appropriate conditions.

Event 2: The condenser will experience a vacuum leak and will require the crew to start the Main Vacuum Pumps prior to the unit tripping on low condenser vacuum. After the crew dispatches operators to look for vacuum leaks, a report will be made to the control room and the SRO will be required to direct the AO to isolate the source of the leak. This will require the SRO to evaluate Tech Specs and enter the appropriate conditions.

Event 3: The Loop B RCS flow signal will fail low causing ICS to automatically re-ratio FDW.

The crew should perform Plant Transient Response and take the ICS Diamond and Feedwater Loop Masters to manual and re-ratio FDW to stabilize the plant.

Event 4: A report will be made to the control room that there is a large oil leak on the Main Turbine and there is no way to isolate the leak without shutting down the oil system.

The SRO will enter an Abnormal Procedure to rapidly shut down the unit with ICS in manual in order to take the turbine offline.

Event 5: During the power reduction from Event 4, the BOP operator will be required to swap auxiliary power to the startup transformer (CT-1) before the generator is taken offline.

Event 6: Once Reactor power has been decreased > 10% and auxiliary power has been transferred to CT-1, switchgear 1TB will lockout which will cause the loss of two RCPs. The Reactor will fail to automatically trip which will require an operator to manually trip the Reactor during Immediate Manual Actions.

Event 7: Shortly after the Reactor is tripped, an RCS leak will develop which will evolve into a Large Break LOCA within a short period of time. While performing Rule 2 due to the Loss of SCM, the 1A1 RCP will fail to trip from the control switch which will require the operator to de-energize the switchgear to remove power from the pump. The 1A LPI Pump will fail and the 1B LPI Pump will fail to receive an ES start signal which will require the operator to manually start the 1B LPI Pump to maintain core cooling.

Page 2 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 1 Page 1 of 2 Event

Description:

Pump RBNS (LWD-1 Fails to Close) (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior OP/1/A/1104/007 Encl 4.1 Crew response:

SRO directs the BOP to pump the Reactor Building Normal Sump in accordance with OP/1/A/1104/007 Enclosure 4.1.

SRO/BOP OP/1/A/1104/007, Encl. 4.1 (Pumping RBNS to 1 inch) rev 30 2.1 Verify required to lower RBNS to 1 3.1 Verify MWHUT level adequate to receive waste volume.

3.2 Position the following:

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

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

1A RB NORM SUMP PUMP 1B RB NORM SUMP PUMP NOTE Changes in LAWT levels may occur during pumping.

RIA Alarms may be indicative of gas leakage.

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

During outages, it is desirable to maintain RBNS > 6 for shielding to decrease dose rates in RBNS area.

3.4 WHEN RBNS is at desired level OR at 1" (low level alarm), ensure the following:

1A RB NORMAL SUMP PUMP "OFF".

1B RB NORMAL SUMP PUMP "OFF".

Examiner Note: 1LWD-1 will NOT close.

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

Close 1LWD-1 (RB NORMAL SUMP ISOLATION)

Close 1LWD-2 (RB NORMAL SUMP ISOLATION)

This event is complete when the SRO has referred to Tech Specs, or as directed by the Lead Examiner Page 3 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 1 Page 2 of 2 Event

Description:

Pump RBNS (LWD-1 Fails to Close) (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior Crew response:

Examiner Note: The crew should diagnose the failure of 1LWD-1 and the SRO will refer to Tech Specs. Since 1LWD-1 is a Containment Isolation Valve, the applicable Tech Spec is 3.6.3. Since this path has 2 Containment Isolation Valves, Condition A applies and the Completion Time is 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Booth Cue: If directed by the control room, SPOC will investigate the problem with 1LWD-1. Troubleshooting/repair of the valve will be turned over to the WCC and the valve is not expected to be returned to service on this shift.

TS 3.6.3 CONTAINMENT ISOLATION VALVES Condition A (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ) Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, one closed and de-activated non-power operated valve, closed manual valve, blind flange, or check valve with flow through the valve secured AND (Once per 31 days) Verify the affected penetration flow path is isolated for isolation devices outside containment.

This event is complete when the SRO has referred to Tech Specs, or as directed by the Lead Examiner Page 4 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 2 Page 1 of 2 Event

Description:

Condenser Vacuum Leak (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/027 Plant Response:

1SA-3/A-6 (Condenser Vacuum Low) will alarm at 25 Hg Crew Response:

The SRO may direct the BOP to refer to the Alarm Response Guide for 1SA-3/A-6 The SRO will enter AP/1/A/1700/027 (Loss of Condenser Vacuum) 1SA-3/A-6 (Condenser Vacuum Low) rev 061 3.1 Refer to AP/1/A/1700/027 (Loss of Condenser Vacuum)

AP/1/A/1700/027 (Loss of Condenser Vacuum) rev 007 4.1 Announce AP entry using the PA system.

4.2 IAAT both of the following apply:

__ Condenser vacuum 22 Hg

__ MODE 1 or 2 THEN trip the Rx.

4.3 Dispatch operators to perform the following:

__ Perform Encl 5.1 (Main Vacuum Pump Alignment)

__ Look for vacuum leaks CT-1 4.4 Ensure all available Main Vacuum Pumps operating (A, B, & C).

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

4.5 Ensure 1V-186 is closed.

4.6 Ensure Steam to Steam Air Ejector A, B, C > 255 psig.

4.7 Verify Steam Seal Header Press > 1.5 psig.

This event is complete when SRO reaches Step 4.10 of AP/27, or as directed by the Lead Examiner.

Page 5 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 2 Page 2 of 2 Event

Description:

Condenser Vacuum Leak (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/027 Crew Response:

OATC 4.8 Ensure all available CCW pumps operating.

Examiner Note: When the 4th CCW Pump is started, the LPSW Leakage Accumulator will alarm on the OAC requiring entry into TS 3.7.7 Condition B (7 days) Restore the LPSW WPS to OPERABLE status.

Booth Cue: Call Control Room as the AO sent out to look for vacuum leaks and report that a leak was found on the 1B Main FDW Pump pumping trap sight glass.

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

4.9 Verify Condensate flow 2300 gpm 4.10 Verify 1SSH-1 is closed 4.11 WHEN condenser vacuum is stable, AND Encl 5.1 (Main Vacuum Pump Alignment) is complete, THEN EXIT this procedure Booth Cue: IF/when asked about the status of Encl. 5.1, respond that using time compression, Encl. 5.1 is complete.

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

This event is complete when SRO reaches Step 4.10 of AP/27, or as directed by the Lead Examiner.

Page 6 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 3 Page 1 of 3 Event

Description:

Loop B RCS Flow Fails Low (I: OATC, SRO)

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

1SA-1/A-3 (1A Flux/Flow/Imb Trip) 1SA-2/A-4 (RC Loop A Flow Low) 1SA-2/A-5 (RC Total Flow Low) 1SA-2/C-11 (ICS Loss of OAC CTP Signal) 1SA-5/A-5 through D-5 (1A-1D RPS Trouble)

ICS will re-ratio FDW Crew Response:

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

OATC OATC should:

Communicate to the CRS the initial alarm (if applicable) followed by reactor power level and direction.

Place the appropriate ICS stations in manual (Diamond and both FDW Masters in this case) in manual if any of the following occur:

o NI power increasing above the pre-transient power level o Failed instrument is diagnosed o Invalid input exists and the CRS directs the ICS be placed in manual Remain focused on reactor power level and FDW response during the transient Note: The OATC will have to re-ratio and maintain total FDW flow pre-transient in order to stabilize power below the pre-transient level.

BOP The BOP should:

Determine if a valid ICS runback exists and inform the CRS Monitor plant response and verify operating limits NOT exceeded If ICS is placed in Manual, remain focused on RCS pressure, SG outlet pressure and RCS inventory SRO The CRS should:

Refer to AP/28 (ICS Instrument Failures)

Ensure FIN-24 (SPOC) is contacted to repair the failed instrument.

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

Page 7 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 3 Page 2 of 3 Event

Description:

Loop B RCS Flow Fails Low (I: OATC, SRO)

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

AP/1/A/1700/028 (ICS Instrument Failures) Rev 20 SRO/BOP 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 1.1 The following bands are to be established during manual control of plant conditions (as needed) but may be adjusted by the CRS if required 1.1.1 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%

1.1.2 Current Tave +/- 2°F 1.1.3 Current SG Outlet Pressure +/- 10 PSIG (N/A) 1.1.4 Delta Tc 0oF +/- 2°F 4.2 Initiate notification of the following:

__ OSM to reference the following:

OMP 1-14 (Notifications)

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

Page 8 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 3 Page 3 of 3 Event

Description:

Loop B RCS Flow Fails Low (I: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/028 Section 4E Crew Response:

SRO/OATC AP/1/A/1700/028, Section 4E (RCS Flow Failure)

NOTE The following will occur when an ICS RCS flow loop signal fails:

ICS RUNBACK Controlling Tave swaps to RCS loop with higher flow Delta Tc station re-ratios loop feedwater flows

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 flow input to ICS per AM/1/A/0326/020 (Control of Unit 1 Star Module Signal Selection Function).

__ Investigate and repair the failed RCS flow instrumentation.

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

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).

Booth Cue: If asked, Unit 2 will initiate the surveillance evaluation in accordance with PT/1/A/0600/001.

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

Examiner Note: Crew Brief opportunity.

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

Page 9 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Page 10 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 4 Page 1 of 2 Event

Description:

Oil Leak on Main Turbine Requires Manual Power Reduction (R: OATC, SRO)

Time Position Applicant's Actions or Behavior Booth Cue: To initiate this event, call the Control Room on 4911 and inform them as follows: "This is the WCC SRO. There is an oil leak on the north end of the Unit 1 B LP turbine. There is not a way to isolate the leak without shutting down the oil system".

Booth Cue: If needed, state that there is a significant amount of oil leaking from the LP turbine.

Booth Cue If asked for Unit 2 to handle the Spill Response procedure, respond that "Unit 2 will handle the Spill Response procedure".

SRO/OATC The SRO will initiate AP/29 (Rapid Unit Shutdown) to direct power reduction AP/1A/1700/029 (Rapid Unit Shutdown) rev 013 4.1 Initiate Encl 5.1 (Support Actions During Rapid Unit Shutdown) (page 13) 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 4.8 Verify ICS in AUTO (ICS is NOT in Auto)

Examiner Note: Focus Brief opportunity.

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

2. GO TO Step 4.10 Note: OATC reduces power by first reducing feedwater and then inserting control rods as necessary.

4.10 Verify both Main FDW pumps running:

RNO: GO TO Step 4.13 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.

This event is complete when Reactor power has been reduced > 10% and Auxiliaries have been transferred, or as directed by the Lead Examiner.

Page 11 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 4 Page 2 of 2 Event

Description:

Oil Leak on Main Turbine Requires Manual Power Reduction (R: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/029 AP/1/A/1700/029 (Rapid Unit Shutdown)

BOP/SRO 4.11 Adjust bias for first Main FDW pump desired to be shutdown (1B) until its 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.

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

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

__ Any of the following alarms 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.

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

4.18 Start the TURBINE MOTOR SUCTION PUMP.

4.19 IAAT both of the following apply:

__ ICS in automatic

__ NI power is 18%

THEN deselect MAXIMUM RUNBACK. (does NOT apply) 4.20 Verify Turbine-Generator shutdown is required (it is required) 4.21 WHEN NI power 18% THEN depress turbine TRIP pushbutton This event is complete when Reactor power has been reduced > 10% and Auxiliaries have been transferred, or as directed by the Lead Examiner.

Page 12 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 5 Page 1 of 2 Event

Description:

Swap Auxiliaries Due To Oil Leak on Main Turbine (N: BOP, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/029 Encl 5.1 AP/1/A/1700/029 Encl. 5.1 (Support Actions During Rapid Unit Shutdown)

SRO/BOP 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.

8. Verify Turbine-Generator shutdown is required. (It is required)

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 This event is complete when Auxiliaries have been transferred, or as directed by the Lead Examiner.

Page 13 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 5 Page 2 of 2 Event

Description:

Swap Auxiliaries Due To Oil Leak on Main Turbine (N: BOP, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/029 Encl 5.1

19. Notify CR SRO that Unit auxiliaries have been transferred SRO/BOP 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

__ 1FDW-53

__ 1FDW-65

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

23. Ensure the following are stopped:

__ 1A MSRH DRN PUMP

__ 1B MSRH DRN PUMP

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

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

26. IAAT load is 450 MWe, THEN perform Steps 27-30

27. Verify the 1C CBP operating

28. Stop the 1A and 1B CBPs

29. Place the control switch for one shutdown CBP in AUTO

30. Ensure CBP LOAD SHED DEFEAT switch to a running CBP

31. WHEN 400 MWe, THEN stop the following pumps

__ 1D1 HTR DRN PUMP

__ 1D2 HTR DRN PUMP

32. WHEN 325 MWe, THEN verify two HWPs operating

33. WHEN 225 MWe, THEN stop all but one HWP

34. Place control switch for one idle HWP in AUTO

35. Ensure HWP LOAD SHED DEFEAT switch is positioned to a running HWP

36. WHEN CTP DEMAND is < 20%, THEN Close 1MS-76 and 1MS-79

37. WHEN directed by CR SRO, THEN EXIT this enclosure This event is complete when Auxiliaries have been transferred, or as directed by the Lead Examiner.

Page 14 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 6 Page 1 of 1 Event

Description:

1TB Lockout Causes a Loss of 1A2 and 1B2 RCPs Requiring a Manual Reactor Trip (C: OATC, SRO)

Time Position Applicant's Actions or Behavior Plant Response:

1TB lockout will occur. This will cause a loss of 6900V power to the 1A2 and 1B2 RCPs. RPS alarms will occur indicating that the Reactor should have tripped, but it will remain at power.

Crew Response:

Recognize the Reactor should have tripped (< 3 RCPs operating with Reactor SRO/OATC power > 2% - OMP 1-18 Att. A), therefore manually trip the Reactor and then perform Immediate Manual Actions of the EOP.

3.1 Depress REACTOR TRIP pushbutton 3.2 Verify reactor power < 5% FP and decreasing 3.3 Depress turbine TRIP pushbutton 3.4 Verify all turbine stop valves closed 3.5 Verify RCP seal injection available BOP The BOP will perform a symptom check.

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 of EFDW) Cooling (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 59,60), gpm)

Area monitor alarms (RIA-16/17)

SRO The SRO will transfer to the Subsequent Actions Tab after IMAs and Symptoms Check are complete (page 16).

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

Page 15 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 6 Page 1 of 1 Event

Description:

1TB Lockout Causes a Loss of 1A2 and 1B2 RCPs Requiring a Manual Reactor Trip (C: OATC, SRO)

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

EOP Subsequent Actions Tab 4.1 Verify all control rods in Groups 1-7 fully inserted SRO/OATC 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 ADVs)

SRO/BOP 4.10 Verify 1RIA-40 operable with CSAE OFF-GAS BLOWER operating 4.11 GO TO Step 4.14 4.14 Verify 1MS-17 and 1MS-26 are closed RNO: Dispatch an operator with Encl 5.29 to verify all MSRVs have reseated 4.15 Verify ES is required RNO: 1. Initiate Encl 5.5 (Pzr and LDST Level Control)

2. GO TO Step 4.17 4.17 Open PCB-20 and PCB-21 4.18 Verify Generator Field Breaker open 4.19 Verify EXCITATION is OFF 4.20 Verify Aux Bldg and Turbine Bldg Instrument Air pressure 90 psig 4.21 Verify ICS/NNI power available 4.22 Verify all 4160V switchgear (1TC, 1TD, & 1TE) energized 4.23 Verify both SGs > 550 psig 4.24 Verify Main FDW operating This event is complete when the SRO reaches Step 4.10 of the Subsequent Actions tab, or as directed by the Lead Examiner.

Page 16 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 7 Page 1 of 10 Event

Description:

Large Break LOCA (M: ALL)

Time Position Applicant's Actions or Behavior Crew Response:

The SRO will direct the BOP to perform a Symptoms Check (OMP 1-18)

SRO/BOP 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 of EFDW) Cooling (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 59,60), gpm)

Area monitor alarms (RIA-16/17)

After verifying IMAs, the SRO will transfer to the Subsequent Actions Tab and review the Parallel Action page. (Page 56)

Examiner Note: Core SCM will indicate 0°F or superheated during this transient depending on when CFTs and LPI flow injects into the core. When the SRO reaches the decision point in the SA parallel action page, if superheated he should transfer to the Inadequate Core Cooling (ICC) tab (Page 18) or if saturated, he should transfer to the Loss of Subcooling Margin (LOSCM) tab (Page 20).

The SRO will direct one of the ROs to perform Enclosure 5.1 (ES Actuation)

(Page 28)

This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.

Page 17 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 7 Page 2 of 10 Event

Description:

Large Break LOCA (M: ALL)

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

SRO/OATC ICC Tab (ICC Parallel Actions on Page 57)

CAUTION ICC conditions should not exist unless multiple equipment and system failures have occurred. Some of the equipment used in this section may be the same equipment that has failed. It is expected that attempts to restore equipment operations will continue throughout this section. It is also expected that transition to OSAG will occur whenever conditions requiring the transition exist..

1. IAAT CETCs > 1200oF, AND TSC is ready to provide mitigation guidance, THEN:

A. Notify TSC to enter the OSAG.

B. EXIT this procedure.

2. Ensure full HPI and control per Rule 6 (HPI). (Page 27)

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

4. Open:

1LP-21 1LP-17

5. Start 1A LPI pump. (The 1A LPI pump will fail to start.)

RNO: 1. IF 1C LPI Pump is operating, THEN GO TO Step 8.

2. Close 1LP-17.

6. Open:

1LP-22 1LP-18 CT-4 7. Start 1B LPI pump. (1B LPI pump will start manually).

RNO: 1. IF 1C LPI Pump is operating, THEN GO TO Step 8.

2. Close 1LP-18 This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.

Page 18 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 7 Page 3 of 10 Event

Description:

Large Break LOCA (M: ALL)

Time Position Applicants Actions or Behavior ICC Tab Crew Response:

8. Verify two LPI pumps operating.

RNO: IF LPI/HPI piggyback is aligned, THEN maximize total LPI flow by throttling HPI flow as follows:

1C LPI pump only < 2900 gpm 1A or 1B LPI pump only < 3100 gpm

9. IAAT all exist:

1C LPI Pump off 1C LPI Pump available LPI required ECCS pump suction aligned to BWST 1A LPI Pump unavailable 1B LPI Pump unavailable THEN perform Steps 10-13.

RNO: GO TO Step 14

14. Open:

1CF-1 1CF-2

15. IAAT core SCM is 0°F, THEN GO TO LOCA CD tab (page 23)

Note: Core SCM will return to 0°F shortly after LPI flow has been established.

16. Verify any injection sources available:

HPI LPI CFTs

17. Open:

1RC-4 PORV This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.

Page 19 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 7 Page 4 of 10 Event

Description:

Large Break LOCA (M: ALL)

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

SRO LOSCM Tab

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

2. Verify LOSCM caused by excessive heat transfer.

RNO: GO TO Step 4.

4. 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 LOCA CD tab. (page 23)

5. Verify SSF activated per AP/25 with SSF RC Makeup required.

RNO: GO TO Step 7.

7. Verify all exist:

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

This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.

Page 20 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 7 Page 5 of 10 Event

Description:

Large Break LOCA (M: ALL)

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

LOSCM tab (continued) 8 GO TO Step 104.

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

105. Verify HPI forced cooling in progress.

RNO: Close 1RC-4 106. Close 1GWD-17, 1HP-1, 1HP-2, and 1RC-3 107. Verify either:

Core superheated Rx vessel head level at 0 RNO: GO TO Step 109 109. IAAT BWST level is 19', THEN initiate Encl 5.12 (ECCS Suction Swap to RBES).

CAUTION If TDEFDWP is being used for SG feed, reducing SG pressure below 250 psig can result in reduced pumping capability 110. Maintain SG pressure < RCS pressure utilizing either:

__ TBVs

__ ADVs 111. Verify any SG available for feeding/steaming.

112. Initiate Encl 5.16 (SG Tube-to-Shell T Control).

113. Verify indications of SGTR exist.

RNO: GO TO Step 116 116. Verify HPI forced cooling in progress.

RNO: GO TO Step 118 This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.

Page 21 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 7 Page 6 of 10 Event

Description:

Large Break LOCA (M: ALL)

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

NOTE If in boiler condenser cooling, the CETCs may have a saw tooth pattern, sometimes increasing and sometimes decreasing. The overall trend should be used to make this determination.

118. Verify CETCs trend decreasing.

119. Verify primary to secondary heat transfer is excessive.

RNO: GO TO Step 121 121. Verify indications of SGTR 25 gpm.

RNO: GO TO Step 123 123. Verify required RCS makeup flow within normal makeup capability.

RNO: GO TO LOCA CD tab (page 23)

This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.

Page 22 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 7 Page 7 of 10 Event

Description:

Large Break LOCA (M: ALL)

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

LOCA COOLDOWN Tab

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

2. Verify ES actuated.

3. GO TO Step 7.

7. Perform the following:

Ensure all RBCUs in low speed.

Open 1LPSW-18 Open 1LPSW-21 Open 1LPSW-24

8. Initiate Encl 5.35 (Containment Isolation).

9. Start all RB Aux fans.

10. IAAT either of the following exists:

LPI FLOW TRAIN A plus LPI FLOW TRAIN B 3400gpm Only one LPI header in operation with header flow 2900 gpm THEN GO TO Step 11.

11. Stop all RCPs

12. Dispatch an operator to perform the following:

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

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

__ Close 1XS2-F3D (1LP-104 Bkr (Post LOCA Boron Dilute))

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

14. Dispatch an operator to perform Encl 5.28 (Local SG Isolation) to isolate both SGs

15. IAAT Spent Fuel Cooling indicates:

__ Abnormal temperature increase

__ Abnormal level change

__ Abnormal SFC flow THEN initiate AP/35

16. Verify 1MS-24 and 1MS-33 are closed This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.

Page 23 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 7 Page 8 of 10 Event

Description:

Large Break LOCA (M: ALL)

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

Rule 2 LOSCM

1. IAAT all exist:

Any SCM 0°F Rx power 1%

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

CT-2 2. Stop all RCPs. 1A1 RCP will NOT trip using the switch RNO: 1. Place 1TA AUTO/MAN switch in MAN.

2. Place 1TB AUTO/MAN switch in MAN.

3. Open 1TA SU 6.9 KV FDR.

4. Open 1TB SU 6.9 KV FDR.

3. Notify CR SRO of RCP status.

4. Verify Blackout exists.

RNO: GO TO Step 6.

6. Open:

1HP-24 1HP-25

7. Start all available HPI pumps.

8. GO TO Step 13.

13. Open:

1HP-26 1HP-27

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

15. IAAT 2 HPI pumps operating, AND HPI flow in any header is in the Unacceptable Region of Figure 1 THEN perform Steps16-21.

RNO: GO TO Step 17 This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.

Page 24 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 7 Page 9 of 10 Event

Description:

Large Break LOCA (M: ALL)

Time Position Applicant's Actions or Behavior Rule 2

16. Open in the affected header:

1A Header 1B Header 1HP-410 1HP-409 SRO/BOP

17. IAAT flow limits are exceeded, Pump Operation Limit 1HPI pump/hdr 475 gpm (incl. seal injection for A hdr) 1A & 1B HPI Total flow of 950 pumps operating gpm (incl. seal with 1HP-409 open injection)

THEN perform Steps 18-20.

RNO: GO TO Step 21.

18. Place Diverse HPI in BYPASS.

This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.

Page 25 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 7 Page 10 of 10 Event

Description:

Large Break LOCA (M: ALL)

Time Position Applicant's Actions or Behavior Rule 2

19. Perform both:

Place ES CH 1 in MANUAL.

Place ES CH 2 in MANUAL.

SRO 20. Throttle HPI to maximize flow flow limit.

21. Notify CR SRO of HPI status.

22. Verify RCS pressure > 550 psig.

23. IAAT either exists:

LPI FLOW TRAIN A plus LPI FLOW TRAIN B 3400 gpm Only one LPI header in operations with header flow 2900 gpm THEN GO TO Step 24.

OATC RNO: GO TO Step 35.

24. 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.

25. Notify crew that performance of Rule 3 is NOT required due to LBLOCA.

BOP 26. WHEN directed by CR SRO, THEN EXIT.

This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.

Page 26 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 27 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam EOP Enclosure 5.1 (ES Actuation)

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 28 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 74.

8. __ Verify any RCP operating. __ GOTO Step 10.

9. Open:

__ 1HP-20

__ 1HP-21

10. __ IAAT any RCP is operating, __ GOTO Step 16.

AND ES Channels 5 and 6 actuate, THEN perform Steps 11 - 15.

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. __ Verify any RCP is operating __ GO TO Step 16

13. Open:

__ 1CC-7

__ 1CC-8

__ 1LPSW-15

__ 1LPSW-6

14. __ Ensure only one CC pump operating.

15. __ Ensure Standby CC pump in AUTO.

Page 29 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

16. __ IAAT ES Channels 3 & 4 are actuated, __ GO TO Step 54.

THEN GO TO Step 17.

17. __ Place Diverse LPI in BYPASS. __ Place Diverse LPI in OVERRIDE.

18. 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}

19. __ IAAT any LPI pump is operating against a shutoff head, THEN at the CR SRO's discretion, stop affected LPI pumps. {6, 22}

20. __ IAAT RCS pressure is < LPI pump __ GOTO Step 23.

shutoff head, THEN perform Steps 21 - 22.

21. Perform the following: 1. __ Stop 1A LPI PUMP.

__ Open 1LP-17. 2. __ Close 1LP-17.

__ Start 1A LPI PUMP.

22. Perform the following: 1. __ Stop 1B LPI PUMP.

__ Open 1LP-18. 2. __ Close 1LP-18.

__ Start 1B LPI PUMP. (CT-4)

Page 30 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

23. __ IAAT 1A and 1B LPI PUMPs are __ GO TO Step 26.

off / tripped, AND all exist:

__ RCS pressure < LPI pump shutoff head

__ 1LP-19 closed

__ 1LP-20 closed THEN perform Steps 24 - 25.

24. Open:

__ 1LP-9

__ 1LP-10

__ 1LP-6

__ 1LP-7

__ 1LP-17

__ 1LP-18

__ 1LP-21

__ 1LP-22

25. __ Start 1C LPI PUMP.

26. __ IAAT 1A LPI PUMP fails while operating, AND 1B LPI PUMP is operating, THEN close 1LP-17.

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

28. Start:

__ A OUTSIDE AIR BOOSTER FAN (CT- 3)

__ B OUTSIDE AIR BOOSTER FAN

29. Notify Unit 3 to start:

__ 3A OUTSIDE AIR BOOSTER FAN

__ 3B OUTSIDE AIR BOOSTER FAN Page 31 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

30. Verify open: __ IF CR SRO desires 1CF-1 and 1CF-2

__ 1CF-1 open,

__ 1CF-2 THEN open:

__ 1CF-1

__ 1CF-2

31. __ Verify 1HP-410 closed. 1. __ Place 1HP-120 in HAND.

2. __ Close 1HP-120.

32. __ Secure makeup to the LDST.

33. __ 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.

34. __ Verify Unit 2 turbine tripped. __ GOTO Step 37.

35. __ Close 2LPSW-139.

36. __ 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.

37. __ Close 1LPSW-139.

38. Place in FAIL OPEN:

__ 1LPSW-251 FAIL SWITCH

__ 1LPSW-252 FAIL SWITCH

39. __ Start all available LPSW pumps.

Page 32 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

40. Verify either: __ GOTO Step 42.

__ Three LPSW pumps operating

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

41. 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'.

42. __ 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.

43. __ Dispatch an operator to perform Encl 5.2 (Placing RB Hydrogen Analyzers In Service). (PS)

44. __ Select DECAY HEAT LOW FLOW ALARM SELECT switch to ON.

45. __ IAAT ES channels 5 & 6 have actuated, __ GOTO Step 47.

THEN perform Step 46.

NOTE RBCU transfer to low speed will NOT occur until 3 minute time delay is satisfied.

46. __ 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 33 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

47. __ IAAT ES channels 7 & 8 have actuated, __ GOTO Step 50.

THEN perform Steps 48 - 49.

48. 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.

49. __ 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.

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

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

52. __ IAAT conditions causing ES actuation have cleared, THEN initiate Encl 5.41 (ES Recovery).

53. __ WHEN CR SRO approves, THEN EXIT.

END Page 34 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Unit Status ES Channels 3 & 4 have NOT actuated.

54. Start:

__ A OUTSIDE AIR BOOSTER FAN CT-3

__ B OUTSIDE AIR BOOSTER FAN

55. Notify Unit 3 to start:

__ 3A OUTSIDE AIR BOOSTER FAN

__ 3B OUTSIDE AIR BOOSTER FAN

56. Verify open: __ IF CR SRO desires 1CF-1 and 1CF-2

__ 1CF-1 open, THEN open:

__ 1CF-2

__ 1CF-1

__ 1CF-2

57. __ Verify 1HP-410 closed. 1. __ Place 1HP-120 in HAND.

2. __ Close 1HP-120.

58. __ Secure makeup to the LDST.

59. __ 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.

60. __ Verify Unit 2 turbine tripped. __ GOTO Step 63.

61. __ Close 2LPSW-139.

62. __ 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.

63. __ Close 1LPSW-139.

Page 35 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

64. Place in FAIL OPEN:

__ 1LPSW-251 FAIL SWITCH

__ 1LPSW-252 FAIL SWITCH

65. __ Start all available LPSW pumps.

66. Verify either: __ GOTO Step 68.

__ Three LPSW pumps operating

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

67. 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'.

68. __ 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.

69. __ Dispatch an operator to perform Encl 5.2 (Placing RB Hydrogen Analyzers In Service). (PS )

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

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

72. __ IAAT conditions causing ES actuation have cleared, THEN initiate Encl 5.41 (ES Recovery).

73. __ WHEN CR SRO approves, THEN EXIT.

END Page 36 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

74. Open: 1. __ IF both BWST suction valves

__ 1HP-24 (1HP-24 and 1HP-25) are closed, THEN:

__ 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. __ GOTO Step 75.

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 76.

Page 37 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

75. __ Ensure at least two HPI pumps are operating.

76. Verify open: 1. __ IF HPI has been intentionally throttled,

__ 1HP-26 THEN GOTO Step 77.

__ 1HP-27 2. Open:

__ 1HP-26

__ 1HP-27 Page 38 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

77. __ 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 39 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

78. __ Verify any RCP operating. __ GOTO Step 80.

79. Open:

__ 1HP-20

__ 1HP-21

80. __ IAAT any RCP is operating, __ GOTO Step 86.

AND ES Channels 5 and 6 actuate, THEN perform Steps 81 - 85.

81. 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.

82. __ Verify any RCP operating __ GO TO Step 86

83. Open:

__ 1CC-7

__ 1CC-8

__ 1LPSW-15

__ 1LPSW-6

84. __ Ensure only one CC pump operating.

85. __ Ensure Standby CC pump in AUTO.

Page 40 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

86. __ IAAT ES Channels 3 & 4 are actuated, __ GO TO Step 124.

THEN GO TO Step 87.

87. __ Place Diverse LPI in BYPASS. __ Place Diverse LPI in OVERRIDE.

88. 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}

89. __ IAAT any LPI pump is operating against a shutoff head, THEN at the CR SRO's discretion, stop affected LPI pumps.{6, 22}

Page 41 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

90. __ IAAT RCS pressure is < LPI pump __ GOTO Step 93.

shutoff head, THEN perform Steps 91 - 92.

91. Perform the following: 1. __ Stop 1A LPI PUMP.

__ Open 1LP-17. 2. __ Close 1LP-17.

__ Start 1A LPI PUMP.

92. Perform the following: 1. __ Stop 1B LPI PUMP.

__ Open 1LP-18. 2. __ Close 1LP-18.

__ Start 1B LPI PUMP. (CT-4)

93. __ IAAT 1A and 1B LPI PUMPs are __ GO TO Step 96.

off / tripped, AND all exist:

__ RCS pressure < LPI pump shutoff head

__ 1LP-19 closed

__ 1LP-20 closed THEN perform Steps 94 -95.

94. Open:

__ 1LP-9

__ 1LP-10

__ 1LP-6

__ 1LP-7

__ 1LP-17

__ 1LP-18

__ 1LP-21

__ 1LP-22

95. __ Start 1C LPI PUMP.

96. __ IAAT 1A LPI PUMP fails while operating, AND 1B LPI PUMP is operating, THEN close 1LP-17.

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

Page 42 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

98. Start:

__ A OUTSIDE AIR BOOSTER FAN

__ B OUTSIDE AIR BOOSTER FAN

99. Notify Unit 3 to start:

__ 3A OUTSIDE AIR BOOSTER FAN

__ 3B OUTSIDE AIR BOOSTER FAN 100. Verify open: __ IF CR SRO desires 1CF-1 and 1CF-2

__ 1CF-1 open, THEN open:

__ 1CF-2

__ 1CF-1

__ 1CF-2 101. __ Verify 1HP-410 closed. 1. __ Place 1HP-120 in HAND.

2. __ Close 1HP-120.

102. __ Secure makeup to the LDST.

103. __ 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.

104. __ Verify Unit 2 turbine tripped. __ GOTO Step 107.

105. __ Close 2LPSW-139.

106. __ 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.

107. __ Close 1LPSW-139.

Page 43 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 108. Place in FAIL OPEN:

__ 1LPSW-251 FAIL SWITCH

__ 1LPSW-252 FAIL SWITCH 109. __ Start all available LPSW pumps.

110. Verify either: __ GOTO Step 112.

__ Three LPSW pumps operating

__ Two LPSW pumps operating when Tech Specs only requires two operable 111. 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'.

112. __ 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.

113. __ Dispatch an operator to perform Encl 5.2 (Placing RB Hydrogen Analyzers In Service). (PS) 114. __ Select DECAY HEAT LOW FLOW ALARM SELECT switch to ON.

115. __ IAAT ES channels 5 & 6 have actuated, __ GOTO Step 117.

THEN perform Step 114.

NOTE RBCU transfer to low speed will NOT occur until 3 minute time delay is satisfied.

116. __ 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 44 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 117. __ IAAT ES channels 7 & 8 have actuated, __ GOTO Step 120.

THEN perform Step 118 - 119.

118. 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.

119. __ 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.

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

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

122. __ IAAT conditions causing ES actuation have cleared, THEN initiate Encl 5.41 (ES Recovery).

123. __ WHEN CR SRO approves, THEN EXIT.

Page 45 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Unit Status ES Channels 3 & 4 have NOT actuated.

124. Start:

__ A OUTSIDE AIR BOOSTER FAN

__ B OUTSIDE AIR BOOSTER FAN 125. Notify Unit 3 to start:

__ 3A OUTSIDE AIR BOOSTER FAN

__ 3B OUTSIDE AIR BOOSTER FAN 126. Verify open: __ IF CR SRO desires 1CF-1 and 1CF-2

__ 1CF-1 open, THEN open:

__ 1CF-2

__ 1CF-1

__ 1CF-2 127. __ Verify 1HP-410 closed. 1. __ Place 1HP-120 in HAND.

2. __ Close 1HP-120.

128. __ Secure makeup to the LDST.

129. __ 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.

130. __ Verify Unit 2 turbine tripped. __ GOTO Step 133.

131. __ Close 2LPSW-139.

132. __ 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.

133. __ Close 1LPSW-139.

Page 46 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 134. Place in FAIL OPEN:

__ 1LPSW-251 FAIL SWITCH

__ 1LPSW-252 FAIL SWITCH 135. __ Start all available LPSW pumps.

136. Verify either: __ GOTO Step 138.

__ Three LPSW pumps operating

__ Two LPSW pumps operating when Tech Specs only requires two operable 137. 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'.

138. __ 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.

139. __ Dispatch an operator to perform Encl 5.2 (Placing RB Hydrogen Analyzers In Service). (PS )

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

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

142. __ IAAT conditions causing ES actuation have cleared, THEN initiate Encl 5.41 (ES Recovery).

143. __ WHEN CR SRO approves, THEN EXIT.

END Page 47 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 48 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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

1HP-25 following:

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 49 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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.

1HP-27

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 50 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 51 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 52 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 53 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 54 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 55 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 56 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ICC EP/1/A/1800/001 Parallel Actions Page 1 of 1 CONDITION ACTIONS

1. All 4160V SWGR de-energized after ICC tab is entered {13} GO TO Blackout tab. BLACKOUT

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

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

4. 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.

5. Individual available to make

Announce plant conditions using notifications PA system.

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

Notify plant staff that Emergency Dose Limits are in affect using PA system.

Page 57 of 60

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam CRITICAL TASKS CT-1 Ensure the Main Vacuum Pumps are operating prior to the low vacuum Turbine trip of 21.75 inches hg.

CT-2 (BWOG CT-1) Trip all RCPs RCPs must be secured within 2 minutes of RCS SCM reaching zero per Rule 2.

CT-3 (BWOG CT-27) Implementation of Control Room Habitability Guidance Start the Outside Air Booster Fans within 30 minutes of a LOCA. Not performing this action could result in Control Room habitability issues.

CT-4 Start 1B LPI Pump prior to reaching 700°F CETCs.

Page 58 of 60

SAFETY: Take a Minute UNIT 0 (OSM)

SSF Operable: No 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: 50% Mode: 1 Mode: 1 Gross MWE: 462 100% 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 SLC 16.7.2 SSF 0400 7 Days TS 3.10.1 Shift Turnover Items (CR SRO)

Primary Due to unanalyzed condition, the SSF should be considered INOPERABLE 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.

Rx power 50% and holding per dispatcher request with no plans to increase power this shift.

SASS is in Manual for calibration C GWD tank release is in progress per OP/1-2/A/1104/018 Just after or during a GWD release, 1SA-8/B-9 may alarm from RIA-32 sample point selected to 1 PRV System Filter Discharge. IF 1SA-8/B-9 is due to RIA 1 PRV System Filter Discharge, it can be considered an expected alarm The BOP is to pump the RBNS per OP/1/A/1104/007 Encl 4.1 due to high level Secondary AMSAC/DSS bypassed for calibration Unit 2 is supplying the AS header 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 71% Withdrawn control.

Human Performance Emphasis (OSM)

Procedure Use and Adherence

Page 60 of 60 Appendix D Scenario Outline Form ES D-1 ILT16-1 NRC Exam Facility: Oconee Scenario No.: 3 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________SRO

________________________ ________________________OATC

________________________ ________________________BOP Initial Conditions:

Reactor Power = 100%

Turnover:

SASS is in Manual AMSAC/DSS is Bypassed C GWD tank release is in progress Event Malfunction Event Event Type* Description No. No.

0a Override AMSAC/DSS Bypassed 0b Override SASS in Manual 1 Override C: BOP, SRO HPSW Jockey Pump Trips 2 Override C: OATC, SRO (TS) Inadvertent DPLIAS Actuation MPI500 3 I: OATC, SRO 1A THOT Fails High MPI171 4 MPS110 C: BOP, SRO (TS) 1HP-5 Fails Closed (Restore Letdown)

R: OATC, C: BOP, 1B1 RCP Lower Seal Failure (Requires Manual 5 MPS247 SRO (TS) Power Reduction)

Support Activities During Power Decrease and 6 N: BOP, SRO Securing 1B1 RCP MSS010 LOHT Requiring CBP Feed MSS020 Turbine Fails to Trip When Performing IMAs 7 MSS260 M: ALL Requiring EHC Pump Lockout MSS270 EFDW Restored From Unit 2 MSS330

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Scenario 3 Event Summary Event 1: This event will start with the HPSW Jockey Pump tripping off and the BOP will refer to the Alarm Response Guide for 1SA-9/D-8 (HPSW Jockey Pump Off). Once an operator is dispatched to investigate the cause of the trip, a report will be made to the crew that a scaffold builder accidentally bumped the Jockey Pump breaker. They will also be told that the pump breaker is closed and there is no damage to the Jockey Pump or its breaker. The crew will then restart the pump per the ARG.

Event 2: The crew will respond to 1SA-01/E-11 (Diverse LPI Trip) which will direct them to initiate AP/42 (Inadvertent ES Actuation). The crew will bypass Diverse LPI , secure the 1A and 1B LPI pumps, and close 1LP-17 and 1LP-18 (LPI Injection Valves). This will require the SRO to evaluate TS/SLC and enter the appropriate conditions Event 3: The 1A Loop THOT instrument will fail high which will cause FDW flow to increase and control rods to insert. They should perform Plant Transient Response and take the ICS Diamond and Feedwater Loop Masters to manual and re-ratio FDW to stabilize the plant before the Reactor trips Event 4: 1HP-5 will fail closed causing a loss of RCS letdown. The crew will enter AP/32 for a Loss of Letdown and minimize charging flow and seal injection to help control RCS inventory. The crew will restore letdown by dispatching an operator to manually open 1HP-5 locally which is a containment isolation valve. This requires an operator stationed locally at the valve in communication with the control room. This will require the SRO to evaluate Tech Specs and enter the appropriate conditions Event 5: The 1B1 RCP lower seal will fail and crew will refer to Alarm Response Guides which will direct entry into AP/16 (Abnormal RCP Operation). AP/16 will direct the crew to initiate a manual power reduction since ICS will be in manual. Once Reactor power is

< 70%, the 1B1 RCP will be secured. Once the RCP is secured, the OATC will have to manually re-ratio FDW to control Tc within a band of +/- 2°F. This will require the SRO to evaluate Tech Specs and enter the appropriate conditions Event 6: Once power has been reduced to < 70% in event 5, the BOP will secure the 1E1 and 1E2 Heater Drain Pumps and then secure the 1B1 RCP due to the seal failure.

Event 7: Both Main FDW Pumps will trip which will cause the Reactor to trip. During the performance of Immediate Manual Actions, the turbine will fail to trip which will require the OATC to secure the EHC pumps in order to close the Turbine Stop Valves. The 1A and 1B Motor Driven EFDW Pumps do not start on low SG level and the Turbine Driven EFDW Pump will trip on overspeed. Rule 3 (Loss of Main/Emergency FDW) will be initiated following a Symptoms Check which will establish Condensate Booster Pump feed to manually control RCS temperature and pressure. The SRO will transfer to the LOHT tab of the EOP to direct mitigation activities. Once RCS temperature and pressure are stabilized and Emergency FDW is aligned from Unit 2, the crew will initiate EFDW flow and feed the SGs per Rule 7 which will begin to establish a level in both SGs.

Page 2 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 1 Page 1 of 2 Event

Description:

HPSW Jockey Pump Trips (C: BOP, SRO)

Time Position Applicant's Actions or Behavior Plant Response:

1SA-9/A-8 HPSW Header A/B PRESS LOW 1SA-9/D-8 HPSW JOCKEY PUMP OFF OAC Alarm - O1D2146 (HPSW Jockey Pump) OFF HPSW header pressure decreases due to Jockey Pump trip Crew Response:

SRO/BOP Refer to ARG 1SA-9/D-8 3.1 Verify automatic action until jockey pump is restarted.

3.2 IF there is NO evidence of breaker and/or pump motor problem, attempt to restart jockey pump one time. If restart is unsuccessful, notify Maintenance Department.

Booth Cue: Once dispatched to investigate the Jockey Pump motor/breaker, wait two minutes and call back to report "A scaffold builder bumped the Jockey Pump BKR with a scaffold pole. There is no damage to the breaker and the breaker is closed". If asked about the status of the Jockey Pump, state that there are no problems evident with the Jockey Pump motor.

The crew may refer to ARG 1SA-9/A-8 3.1 Verify proper jockey pump operation 3.2 Refer to SLC 16.9.8a 3.3 Verify HPSW pumps start (start manually if NOT already in operation per OP/0/A/1104/011) when preset levels in EWST are reached 3.4 IF both HPSW Pumps NOT available, Go To EP/1/A/1800/001 Enclosure 5.31 for method of back charging the HPSW system.

3.5 IF HPSW Header Pressure continues to decrease AND Elevated Storage Tank Level is NOT dropping; i.e., altitude valve stuck closed and jockey pump not providing adequate supply, manually start a HPSW Pump.

Refer to OP/0/A/1104/011 (High Pressure Service Water).

3.6 Refer to AP/1-2/A/1700/030 (Aux Building Flood) 3.7 Investigate and correct reason for excessive HPSW usage 3.8 Verify BASE and STANDBY HPSW Pumps stop at 80,000 gals This event is complete when the Jockey Pump has been restarted, or as directed by the Lead Examiner.

Page 3 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 1 Page 2 of 2 Event

Description:

HPSW Jockey Pump Trips (C: BOP, SRO)

Time Position Applicant's Actions or Behavior Crew response:

3.9 IF manually started, return HPSW Pumps when NO longer needed SRO/BOP 3.9.1 Ensure B HPSW Pump in BASE 3.9.2 Ensure A HPSW Pump in STANDBY The crew may refer to the ARG for O1D2146 (HPSW Jockey Pump)

1. IF there is NO evidence of breaker and/or pump motor problem, THEN attempt to restart jockey pump one time. If restart is unsuccessful, contact SPOC.

2. Refer to OP/0/A/1104/011 (High Pressure Service Water)

This event is complete when the Jockey Pump has been restarted, or as directed by the Lead Examiner.

Page 4 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 2 Page 1 of 5 Event

Description:

Inadvertent DLPIAS Actuation (C: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/042 Plant Response:

1SA-01/E-11, Diverse LPI Trip 1SA-07/D-3, ES ODD VOTERS TROUBLE 1SA-07/E-3, ES EVEN VOTERS TROUBLE DLPIAS tripped red light Illuminated LPI Pumps start LPI injection aligned LPSW Pumps start Crew Response:

BOP ARG: 1SA-01/E-11 (Diverse LPI Trip) 3.1 Determine if DLPIAS condition exists (RCS pressure 462 psig).

3.2 IF RCS pressure is 462 psig, Go To EP/1/A/1800/001 (Emergency Operating Procedure).

3.3 IF ES condition does NOT exist, Initiate AP/1/A/1700/042 (Inadvertent ES Actuation).

3.4 Refer to OP/1/A/1105/014 (Control Room Instrumentation Operation And Information).

SRO/OATC AP/1/A/1700/042 (Inadvertent ES Actuation) rev 004 4.1 Verify any of the following have inadvertently actuated:

Diverse HPI ES Channel 1 ES Channel 2 RNO: GO TO Step 4.4 4.4 Verify any of the following have inadvertently actuated:

ES Channel 5 ES Channel 6 RNO: 1. IF ES Channel 1, ES Channel 2, or Diverse HPI have inadvertently actuated, AND it is desired to restore letdown, THEN initiate AP/42 Encl 5.2 (Letdown Restoration).

2. GO TO Step 4.10.

This event is complete when Enclosure 5.1 is completed and TS/SLCs have been addressed IAW step 4.25, or as directed by the Lead Examiner.

Page 5 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 2 Page 2 of 5 Event

Description:

Inadvertent DLPIAS Actuation (C: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/042 Crew Response:

4.10 Close the following:

SRO/OATC 1HP-24 1HP-25 NOTE If personnel are available, progression should continue while Encl 5.1 (Required Operator Actions) is in progress.

4.11 Ensure AP/42 Encl 5.1 (Required Operator Actions) is in progress.

(Page 8) 4.12 Verify any of the following have inadvertently actuated:

Diverse LPI ES Channel 3 ES Channel 4 4.13 Verify Diverse LPI has inadvertently actuated.

Examiner Note: Placing Diverse LPI in BYPASS will actuate Statalarm 1SA-01/E-10. This is an expected alarm.

4.14 Ensure DIVERSE LPI BYPASS is in BYPASS 4.15 Perform the following on all inadvertently actuated system(s):

Ensure ES CH-3 is in MANUAL (does not apply)

Ensure ES CH-4 is in MANUAL (does not apply) 4.16 Verify LPI was aligned in decay heat removal mode prior to ES actuation.

RNO: 1. Stop the following:

1A LPI PUMP 1B LPI PUMP

2. Simultaneously close the following:

1LP-17 1LP-18 4.17 Verify the Rx is critical.

This event is complete when Enclosure 5.1 is completed and TS/SLCs have been addressed IAW step 4.25, or as directed by the Lead Examiner.

Page 6 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 2 Page 3 of 5 Event

Description:

Inadvertent DLPIAS Actuation (C: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/042 Crew Response:

SRO/OATC CAUTION Do NOT add demin water to counter the boration until RCS boron concentration stabilizes to prevent a positive reactivity event.

Note: The crew may initiate EOP Encl 5.5 for inventory control. These steps are included beginning on (page 42) if necessary.

NOTE ICS in Auto means ICS is in control of Tave and Rx power.

4.18 Verify ICS in Auto 4.19 Verify control rods are outside the desired control band (they are not)

RNO: GO TO Step 4.21 4.21 Verify any of the following have inadvertently actuated:

ES Channel 1 Diverse HPI RNO: GO TO Step 4.24 4.24 Notify SPOC to investigate and repair the cause of the inadvertent ES actuation, as necessary.

4.25 Initiate logging TS/SLC Entry/Exit, as applicable, in accordance with Encl 5.4 (TS/SLC Requirements). (see page 9) 4.26 WHEN all the following exist:

Reason for inadvertent ES Channel or Diverse HPI/LPI actuation has been resolved ES Channel or Diverse HPI/LPI reset is desired OSM concurs THEN continue.

This event is complete when Enclosure 5.1 is completed and TS/SLCs have been addressed IAW step 4.25, or as directed by the Lead Examiner.

Page 7 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 2 Page 4 of 5 Event

Description:

Inadvertent DLPIAS Actuation (C: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/042 Encl 5.1 Crew Response:

SRO/BOP AP/1/A/1700/042 Encl 5.1 (Required Operator Actions) 1 Initiate announcement of AP Entry using the PA system.

NOTE If channels are bypassed or in override, 1SA-1/A-10 (ES 1 Trip) and 1SA-1/B-10 (ES 2 Trip) will be off even though the channel may have actuated.

2 Verify any of the following have inadvertently actuated:

Diverse HPI ES Channel 1 ES Channel 2 RNO: GO TO Step 5 5 Verify any of the following have inadvertently actuated:

ES Channel 7 ES Channel 8 RNO: GO TO Step 9 9 Perform the following:

A. Open the following to restore RB RIAs:

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

1) Select OFF for RB RIA sample pump.

2) Start the RB RIA sample pump.

10 Verify any of the following have inadvertently actuated:

Diverse HPI ES Channel 1 RNO: GO TO Step 12 12 EXIT this enclosure.

This event is complete when Enclosure 5.1 is completed and TS/SLCs have been addressed IAW step 4.25, or as directed by the Lead Examiner.

Page 8 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 2 Page 5 of 5 Event

Description:

Inadvertent DLPIAS Actuation (C: OATC, SRO) (TS)

Time Position Applicant's Actions or Behavior Crew Response:

Examiner Note: SLC 16.7.6 will apply due to the automatic actuation logic SRO being blocked if any Diverse Actuation system is in OVERRIDE or BYPASS.

SLC 16.7.6 (Diverse Actuation Systems)

Condition A (7 days) Restore DLPIAS to FUNCTIONAL status.

Examiner Note: If OAC alarm is received for LPSW leakage accumulator, TS 3.7.7 will apply.

TS 3.7.7 (LPSW System)

Condition B (7 days) Restore the LPSW WPS to OPERABLE status.

Examiner Note: The RB RIA sample pump will be stopped and started by the BOP per AP/42 Encl 5.1 Step 9. TS 3.4.15 will apply while the sample pump is OFF.

TS 3.4.15 (RCS Leakage Detection Instrumentation)

Condition B (Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) Analyze grab samples of the containment atmosphere OR (Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) Perform SR 3.4.13.1 AND (30 days) Restore required containment atmosphere radioactivity monitor to OPERABLE status This event is complete when Enclosure 5.1 is completed and TS/SLCs have been addressed IAW step 4.25, or as directed by the Lead Examiner.

Page 9 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 3 Page 1 of 4 Event

Description:

1A Thot Fails High (I: OATC, SRO)

Time Position Applicant's Actions or Behavior Plant Response:

1A Th will fail HIGH Tave will indicate HIGH Feedwater flow will increase Control Rods will insert 1SA-2/B-3 (RC Hot Leg Temp High) 1SA-2/B-4 (RC Average Temperature High/Low) 1SA-2/A-12 (ICS Tracking)

Crew Response:

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

OATC OATC should:

Communicate to the CRS the initial alarm (if applicable) followed by reactor power level and direction.

Place the appropriate ICS stations in manual (Diamond and both FDW CT-1 Masters in this case) in manual if any of the following occur:

o NI power increasing above the pre-transient power level o Failed instrument is diagnosed o Invalid input exists and the CRS directs the ICS be placed in manual Remain focused on reactor power level and FDW response during the transient Note: The OATC will have to reduce FDW in order to stabilize power below the pre-transient level.

BOP The BOP should:

Determine if a valid ICS runback exists and inform the CRS Monitor plant response and verify operating limits NOT exceeded If ICS is placed in Manual, remain focused on RCS pressure, SG outlet pressure and RCS inventory SRO The CRS should:

Refer to AP/28 (ICS Instrument Failures)

Ensure FIN-24 (SPOC) is contacted to repair the failed instrument.

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

Page 10 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 3 Page 2 of 4 Event

Description:

1A Thot Fails High (I: OATC, SRO)

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

AP/1/A/1700/028 (ICS Instrument Failures) Rev 20 BOP 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 1.1 The following bands are to be established during manual control of plant conditions (as needed) but may be adjusted by the CRS if required 1.1.1 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%

1.1.2 Current Tave +/- 2°F 1.1.3 Current SG Outlet Pressure +/- 10 PSIG (N/A) 1.1.4 Delta Tc 0oF +/- 2°F 4.2 Initiate notification of the following:

__ OSM to reference the following:

OMP 1-14 (Notifications)

__ 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.

This event is complete when the SRO 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 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 3 Page 3 of 4 Event

Description:

1A Thot Fails High (I: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/028 Encl 4A Crew Response:

SRO/OATC 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 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 SRO 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 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 3 Page 4 of 4 Event

Description:

1A Thot Fails High (I: OATC, SRO)

Time Position Applicant's Actions or Behavior AP/1/A/1700/028 Section 4A 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.

(see next page)

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).

Booth Cue: If the crew asks, Unit 2 will perform the surveillance evaluation.

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).

Examiner Note: Crew Brief opportunity.

Examiner Note: If RCS pressure decreases below 2125 psig, TS 3.4.1 will apply if Reactor power stabilizes at 96 (inside the steady state band of 4%) during Plant Transient Response.

TS 3.4.1 RCS Pressure, Temperature, & Flow DNB Limits Condition A (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) One or more RCS DNB parameters not within limits Required Action: Restore RCS DNB parameter(s) to within limit This event is complete when the SRO 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 ILT16-1 NRC Exam Page 14 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 4 Page 1 of 4 Event

Description:

1HP-5 Fails Closed (Restore Letdown) (C:BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/032 Plant Response:

OAC alarm: HPI LETDOWN FLOW Letdown flow = 0 gpm 1HP-5 indicates closed Crew Response:

SRO should enter AP/1/A/1700/032 (Loss of Letdown)

SRO/BOP AP/1/A/1700/032 (Loss of Letdown) rev 006 NOTE This AP may be performed by an RO if the EOP is also in progress. The Procedure Director should resume directing the actions of this AP as soon as EOP actions allow.

4.1 Place 1HP-120 in HAND and reduce demand to zero.

4.2 Position the standby HPI pump switch to OFF.

CAUTION RCP individual seal return valves will close if seal injection is < 22 gpm with CC flow < 575 gpm.

4.3 Throttle 1HP-31, preferably in AUTO, to establish SEAL INLET HDR FLOW to the appropriate value:

CC TOTAL Throttle HPI FLOW Seal flow to:

> 575 gpm 12-15 gpm 575 gpm 24-25 gpm NOTE The running HPI pump may operate below 65 gpm for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . HPI pump time of operation below minimum flow is cumulative.

4.4 Verify HPI pump flow 65 gpm. Note: Flow will be < 65 gpm.

30 + ___ +___ = ___ gpm Recirc + SI + MU RNO: Log beginning time for HPI pump flow below minimum.

4.5 Initiate makeup to LDST as required.

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

Page 15 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 4 Page 2 of 4 Event

Description:

1HP-5 Fails Closed (Restore Letdown) (C:BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/032 Crew Response:

SRO/OATC 4.6 Initiate notification of the following :

__ OSM to reference the following:

OMP 1-14 (Notifications)

__ STA 4.7 Verify 1HP-5 closed.

4.8 Dispatch an operator to 1HP-5 (Letdown Isolation) (East Pen Rm) to establish communication with Control Room.

NOTE Tech Spec 3.4.9 applies when indicated Pzr level > 260 (corrected value for 285).

Conditions where it is known that letdown CANNOT be restored do not require waiting until 260 to begin a Rapid Shutdown.

4.9 IAAT either of the following exist:

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

4.10 IAAT Pzr level 375, THEN trip Rx.

4.11 Determine the cause of loss of letdown AND GO TO designated mitigation Step:

Reason for Loss of GO TO Letdown Step 1HP-5 failed closed 4.12 Actual LD Temp high LD interlock failure LD line leak 4.28 Both LD Coolers isolated Other 4.12 Close 1HP-6.

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

Page 16 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 4 Page 3 of 4 Event

Description:

1HP-5 Fails Closed (Restore Letdown) (C:BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/032 Crew Response:

4.13 Close 1HP-7.

4.14 Open 1HP-5 (1HP-5 will NOT open from the control room).

RNO: 1. Notify operator dispatched to 1HP-5 to:

A. Manually open 1HP-5 (LETDOWN ISOLATION)(East Pen Rm).

Booth Cue: When notified to open 1HP-5, FIRE TIMER 13 to manually open 1HP-5. Wait at least 15 seconds and report back that 1HP-5 is manually open.

SRO/OATC B. Maintain continuous communication with Control Room.

2. IF 1HP-5 is manually open, THEN enter TS 3.6.3. (see page 18) 4.15 Place the CC system in operation.

4.16 Verify letdown temperature < 135°F.

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

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

4.19 Open 1HP-6 4.20 Adjust 1HP-7 to control desired letdown flow.

4.21 Re-establish normal makeup through 1HP-120.

Examiner Note: Normal makeup may include placing 1HP-120 in AUTO.

4.22 Verify any purification IX in service.

4.23 Notify SPOC to initiate repairs on 1HP-5.

4.24 Re-establish normal RCP seal injection flow.

4.25 Position the standby HPI pump switch to AUTO.

4.26 WHEN repairs are compete on 1HP-5 (LETDOWN ISOLATION)

(East Pen Rm), THEN perform the following:

A. Locally turn 1HP-5 handwheel fully clockwise.

B. EXIT TS 3.6.3.

4.27 EXIT Examiner Note: 1HP-5 will not be repaired for this scenario.

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

Page 17 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 4 Page 4 of 4 Event

Description:

1HP-5 Fails Closed (Restore Letdown) (C:BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior SRO TS 3.6.3 CONTAINMENT ISOLATION VALVES Condition A (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ) Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, one closed and de-activated non-automatic power operated valve, closed manual valve, blind flange, or check valve with flow through the valve secured AND (Once per 31 days) Verify the affected penetration flow path is isolated.

Note: Penetration flow paths except for 48 inch purge valve penetration flow paths may be un-isolated intermittently under administrative controls.

TS 3.6.3 Bases, Administrative Controls:

The opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following:

(1) stationing an operator, who is in constant communication with control room, at the valve controls, (2) instructing this operator to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment (Ref. 5).

Examiner Note: If pressurizer level exceeds 260 inches, TS 3.4.9 would also be entered.

TS 3.4.9 PRESSURIZER Condition A (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ) Restore Pressurizer water level to within limit Examiner Note: If RCS pressure decreases below 2125 psig, TS 3.4.1 will apply if Reactor power stabilizes at 96 (inside the steady state band of 4%) during Plant Transient Response in Event 3.

TS 3.4.1 RCS Pressure, Temperature, & Flow DNB Limits 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 This event is complete when the Standby HPI pump is placed in AUTO, or as directed by the Lead Examiner.

Page 18 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 5/6 Page 1 of 10 Event

Description:

1B1 RCP Lower Seal Failure (Requires Manual Power Reduction)

(R: OATC, C:BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior Plant Response:

1SA-06/C-5 (RC PUMP 1B1 SEAL CAVITY PRESS HI/LOW)

OAC Alarm RCP 1B1 LOWER SEAL CAVITY PRESSURE HI HI OAC Alarm RCP 1B1 UPPER SEAL CAVITY PRESSURE HI HI OAC Alarm 1B1 UPPER & LOWER SEAL P SRO/BOP Crew response:

Refer to the ARGs 3.1 Upper/Lower Seal Cavity Pressure High 3.1.1 Go To AP/1/A/1700/016, Abnormal RCP Operation, for limits and required action 3.2 Upper/Lower Seal Cavity Pressure Low 3.2.1 IF in Mode 1 or 2, Go To AP/1/A/1700/016, Abnormal RCP Operation, for limits and required action AP/1/A/1700/016 (Abnormal RCP Operation) rev 033 4.1 IAAT any RCP meets immediate trip criteria of Encl 5.1 (RCP Immediate Trip Criteria), THEN perform Steps 4.2 - 4.11.

(Immediate trip criteria will NOT be met)

RNO: GO TO Step 4.12.

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 (see page 22)

Examiner Note: It is acceptable for the SRO to take either procedure path to secure the 1B1 RCP. Step 4.16 is page 20.

4.13 Verify Rx Power > 70%

4.14 Initiate Encl 5.2 (Rapid Power Reduction) (see page 25) 4.15 WHEN Rx Power is 70%,

THEN GO TO Step 4.2 This event is complete when 1B1 RCP is secured and Tc is within 0 +/- 2°F, or as directed by the Lead Examiner.

Page 19 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 5/6 Page 2 of 10 Event

Description:

1B1 RCP Lower Seal Failure (Requires Manual Power Reduction)

(R: OATC, C:BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/016 Crew Response:

4.2 Verify MODE 1 or 2 SRO/BOP 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 4.8 Verify FDW masters in Auto CAUTION Total FDW flow should be maintained constant to prevent changes in core reactivity RNO: 1. Stop affected pump

2. Manually adjust FDW masters to achieve desired Tc

3. GO TO Step 4.29 4.29 IAAT any of the following indicate external RCP seal leakage:

__ 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 26) 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

__ 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)

This event is complete when 1B1 RCP is secured and Tc is within 0 +/- 2°F, or as directed by the Lead Examiner.

Page 20 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 5/6 Page 3 of 10 Event

Description:

1B1 RCP Lower Seal Failure (Requires Manual Power Reduction)

(R: OATC, C:BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/016 4.32 IAAT either of the following has exceeded 260°F including transient SRO/BOP 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.

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.

This event is complete when 1B1 RCP is secured and Tc is within 0 +/- 2°F, or as directed by the Lead Examiner.

Page 21 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 5/6 Page 4 of 10 Event

Description:

1B1 RCP Lower Seal Failure (Requires Manual Power Reduction)

(R: OATC, C:BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/016 Alternate Path from Step 4.12 SRO/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 4A Seal Failure 4B Abnormal Vibration 4C High or Low Oil Pot Level 4D Loss of Seal Return 4E Abnormal RCP Temperatures AP/1/A/1700/016 Section 4A (RCP Seal Failure)

1. IAAT any RCP meets immediate trip criteria of Encl 5.1, THEN perform Steps 2-11 (Immediate trip criteria will NOT be met)

RNO: GO TO Step 12

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

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)

13. Verify the following are open:

__ 1HP-20

__ 1HP-21 This event is complete when 1B1 RCP is secured and Tc is within 0 +/- 2°F, or as directed by the Lead Examiner.

Page 22 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 5/6 Page 5 of 10 Event

Description:

1B1 RCP Lower Seal Failure (Requires Manual Power Reduction)

(R: OATC, C:BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/016

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

SRO/BOP 1HP-232 (1B1 RCP)

NOTE A single failed seal can transport debris to the other seals and damage them. A RCP with a failed seal should be secured as quickly as plant conditions allow.

Use diverse indications, such as changes in other seal pressures, to ensure abnormal parameter is not a single instrument failure. For any seal failure, upper and lower seal cavity pressures should change from normal value.

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

RCS Pressure P across any seal

> 1000 psig 100 psid 1000 psig 35 psid OR shut down of an RCP is desired, THEN perform Steps 16-26 to shut down the affected RCP.

16. Verify MODE 1 or 2

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

18. Verify Rx power is 70% as indicated on all Nis Examiner Note: Focus Brief opportunity RNO: 1. Direct an RO to initiate Encl 5.2 (Rapid Power Reduction)

(see page 25)

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

19. Verify any SG on Low Level Limits RNO: GO TO Step 22 This event is complete when 1B1 RCP is secured and Tc is within 0 +/- 2°F, or as directed by the Lead Examiner.

Page 23 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 5/6 Page 6 of 10 Event

Description:

1B1 RCP Lower Seal Failure (Requires Manual Power Reduction)

(R: OATC, C:BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/016

22. Verify FDW masters in Auto CAUTION Total FDW flow should be maintained constant to prevent changes in core reactivity BOP Examiner Note: Focus Brief opportunity.

OATC RNO: 1. Stop the affected pump

2. Manually adjust FDW masters to achieve desired Tc

3. GO TO Step 25

25. Initiate Encl. 4.3 (Special Instructions for < 4 RCP Operation) of OP/1/A/1102/004 (Operation at Power). (see page 26)

26. Initiate the following notifications:

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

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

__ Notify SOC if load reduction was required.

__ Notify Chemistry to take RCS boron samples on a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months frequency.

27 IAAT a 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) 28 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.

This event is complete when 1B1 RCP is secured and Tc is within 0 +/- 2°F, or as directed by the Lead Examiner.

Page 24 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 5/6 Page 7 of 10 Event

Description:

1B1 RCP Lower Seal Failure (Requires Manual Power Reduction)

(R: OATC, C:BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/016 Encl 5.2 SRO/OATC AP/16 Enclosure 5.2 (Rapid Power Reduction)

1. Verify ICS in AUTO RNO: 1. Notify SRO to provide target power level, average power reduction rate, and control bands, as required

2. Initiate manual power reduction to 70%

3. WHEN Rx Power 70% as indicated by all Nis , THEN notify CRS

4. Stop the following pumps:

BOP

__ 1E1 HTR DRN PUMP

__ 1E2 HTR DRN PUMP

5. GO TO Step 7

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 Examiner Note: Once Reactor power is reduced to below 85%, the SSF must be declared inoperable and therefore Tech Spec 3.10.1 applies.

TS 3.10.1 STANDBY SHUTDOWN FACILITY (SSF)

Conditions A-E (7 Days) Restore to OPERABLE status This event is complete when 1B1 RCP is secured and Tc is within 0 +/- 2°F, or as directed by the Lead Examiner.

Page 25 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 5/6 Page 8 of 10 Event

Description:

1B1 RCP Lower Seal Failure (Requires Manual Power Reduction)

(R: OATC, C:BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior OP/1/A/1102/004 Encl 4.3 OP/1/A/1102/004 (Operations At Power) Encl 4.3 (Special Instructions For < 4 RCP Operations) Rev 147 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.

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.

This event is complete when 1B1 RCP is secured and Tc is within 0 +/- 2°F, or as directed by the Lead Examiner.

Page 26 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 5/6 Page 9 of 10 Event

Description:

1B1 RCP Lower Seal Failure (Requires Manual Power Reduction)

(R: OATC, C:BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior OP/1/A/1102/004 Encl 4.3 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.

This event is complete when 1B1 RCP is secured and Tc is within 0 +/- 2°F, or as directed by the Lead Examiner.

Page 27 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 5/6 Page 10 of 10 Event

Description:

1B1 RCP Lower Seal Failure (Requires Manual Power Reduction)

(R: OATC, C:BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior OP/1/A/1102/004 Encl 4.3 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.

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."

This event is complete when 1B1 RCP is secured and Tc is within 0 +/- 2°F, or as directed by the Lead Examiner.

Page 28 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 7 Page 1 of 9 Event

Description:

LOHT Requiring CBP Feed (M: All)

Time Position Applicant's Actions or Behavior Plant Response:

Both MFWPs trip Reactor Trips MD EFDWPs do NOT start TD EFDWP overspeeds and trips Crew Response:

SRO SRO directs the OATC to perform IMAs and the BOP to perform a Symptom Check IMAs EOP Immediate Actions OATC 3.1 Depress REACTOR TRIP pushbutton 3.2 Verify reactor power < 5% FP and decreasing 3.3 Depress turbine TRIP pushbutton 3.4 Verify all turbine stop valves closed CT-2 RNO: Place both EHC pumps in PULL TO LOCK 3.5 Verify RCP seal injection available SYMPTOM CHECK BOP The BOP will perform a Symptom Check:

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 of EFDW) Cooling (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 59,60), gpm)

Area monitor alarms (RIA-16/17)

BOP will perform Rule 3 due to a loss of ALL Feedwater: (Page 33)

This event is complete when EFDW is established from Unit 2, or as directed by the Lead Examiner.

Page 29 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 7 Page 2 of 9 Event

Description:

LOHT Requiring CBP Feed (M: All)

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

SRO will transfer to the Subsequent Actions tab of the EOP.

SRO will refer to Subsequent Actions Parallel Actions Page and transfer to the LOHT tab.. (see page 40)

SRO will refer to the LOHT Parallel Actions Page and direct an RO to announce plant conditions and notify the SM to reference the Emergency Plan and AD-LS-ALL-0006 (page 41)

Loss of Heat Transfer Tab (LOHT)

1. Ensure Rule 3 is in progress or complete NOTE Transfer to LOSCM tab is NOT required if RCS heats to the point where core SCM = 0F.

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 exist:

__ RCS pressure reaches 2300 psig OR NDT limit

__ PZR level reaches 375" (340" acc)

THEN GO TO Step 4 NOTE: 1A1 RCP provides the best Pzr spray.

RNO: 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 or Encl. 5.27 reports EFDW available THEN GO TO Step 50

50. Verify EFDW or PSW flow has been re-established to any SG per Rule 3 or Encl. 5.27 (it has not).

RNO: GO TO step 52.

This event is complete when EFDW is established from Unit 2, or as directed by the Lead Examiner.

Page 30 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 7 Page 3 of 9 Event

Description:

LOHT Requiring CBP Feed (M: All)

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

52. Verify Unit 1 EFDW available.

BOP RNO: GO TO step 56.

56. Confirm ability to feed any intact SG:

A. Throttle EFDW control valve on each intact SG until flow confirmed B. WHEN flow confirmed, THEN close valve on each intact SG

57. Perform a brief to discuss operator roles for restoring EFDW flow to the SGs.

58. Verify all:

Tcold > 510°F TBVs available

59. Verify Tcold 547°F Examiner Note: The crew will perform Step 59 based on where they stabilize RCS temperature during CBP feed.

RNO: 1. Set THP setpoint at 885 psig

2. GO TO step 62

60. Determine Psat for existing RCS temperature (RCS Psat)

61. Adjust THP setpoint to RCS Psat minus 140 psi:

Setpoint = RCS Psat (psia) - 140 psi = ______ psig

62. Place TBVs in AUTO for available SGs.

63. Initiate feed to available SGs per Rule 7 (SG Feed Control) (p. 38)

64. IAAT heat transfer is established in any SG, THEN GO TO Step 75.

75. Control feeding and steaming of available SGs to maintain SG level at setpoint and cooldown rate within Tech Spec limits:

Tcold 270°F: 50°F / 1/2 hour Tcold < 270°F: 25°F / 1/2 hour

76. Close all loop high point vents: (already closed) 1RC-155 1RC-156 1RC-157 1RC-158 This event is complete when EFDW is established from Unit 2, or as directed by the Lead Examiner.

Page 31 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 7 Page 4 of 9 Event

Description:

LOHT Requiring CBP Feed (M: All)

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

77. WHEN all SCMs are > 0°F, OR HPI flow is established, THEN continue.

78. Verify indications of SGTR 25 gpm.

RNO: GO TO step 80

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

81. Verify either:

Any SG isolated Any SG has an unisolable steam leak RNO: GO TO step 83.

83. GO TO Subsequent Actions.

EOP Subsequent Actions EOP Subsequent Actions 4.1 Verify all control rods in Groups 1-7 fully inserted.

4.2 Verify Main FDW in operation.

RNO: 1. Ensure Rule 3 is in progress or complete.

2. 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 4.10 Verify 1RIA-40 operable with CSAE OFF-GAS BLOWER operating.

4.11 GO TO Step 4.14 4.14 Verify 1MS-17 and 1MS-26 are closed RNO: Dispatch an operator with Encl 5.29 (MSRV Locations) to verify all MSRVs have reseated This event is complete when EFDW is established from Unit 2, or as directed by the Lead Examiner.

Page 32 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 7 Page 5 of 9 Event

Description:

LOHT Requiring CBP Feed (M: All)

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

Rule 3 (Loss of Main or Emergency FDW)

1. Verify loss of Main FDW and/or EFDW was due to TBF.

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 (HPI Forced Cooling)

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

5. Verify any EFDW pump operating.

RNO: GO TO Step 7

7. Place 1FDW-315 and 1FDW-316 in MANUAL and closed.

8. Verify both:

Any CBP operating TBVs available on an intact SG

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

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

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

12. Simultaneously position 1FDW-35 and 1FDW-44 (Startup Control Valves) to 10 - 20% open.

13. Perform the following:

Place 1FDW-31 and 1FDW-40 switches in CLOSE.

Close 1FDW-32 and 1FDW-41.

This event is complete when EFDW is established from Unit 2, or as directed by the Lead Examiner.

Page 33 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 7 Page 6 of 9 Event

Description:

LOHT Requiring CBP Feed (M: All)

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

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

CAUTION Until SGs are dry, lower SG pressure slowly to prevent overcooling.

CT-3 RNO: 1. Lower SG pressure in available SGs to 500 psig

2. Control FDW flow to stabilize RCS P/T by throttling the SU CVs and TBVs as necessary

3. Notify CRS that CBP feed is in progress

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

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

6. GO TO Step 16

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

17. Dispatch an operator to perform Encl. 5.26 (Manual Start of TD) (PS)

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

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

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

21. Notify alternate unit to:

Place both EFDW control valves in MANUAL and closed.

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.

Booth Cue: Notify crew that AO is in position at 1FDW-313.

Examiner Note: EFDW will be cross-connected with Unit 2.

This event is complete when EFDW is established from Unit 2, or as directed by the Lead Examiner.

Page 34 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 7 Page 7 of 9 Event

Description:

LOHT Requiring CBP Feed (M: All)

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

NOTE Procedure must continue while cross connects are being opened.

24. IAAT an operator is in position at 1FDW-313, AND Unit 1 TDEFDW Pump is NOT operating, THEN notify the operator to open:

1FDW-313 (1A EFDW Line Disch to 1A S/G X-conn) 1FDW-314 (1B EFDW Line Disch to 1B S/G X-conn)

Booth Cue: Once an AO is directed to open 1FDW 313 & 1FDW-314, FIRE TIMER 15 and notify crew 1FDW-313/314 and 2FDW-313/314 are open.

25. Verify either exists:

HPI Forced Cooling is maintaining core cooling CBP feed providing SG feed (applies)

26. WHEN either exists:

Unit 1 TDEFDW Pump running Alignment complete from alternate unit THEN notify CRS of the following:

Source of EFDW availability Rule 3 actions are continuing

27. IAAT CBPs were feeding the SGs, AND CBP feed has been lost, THEN:

Position TBVs as desired by CRS Close 1FDW-35 Close 1FDW-44

28. IAAT an EFDW valve CANNOT control in AUTO, OR manual operation of EFDW valve is desired to control flow/level, THEN perform steps 29 - 33.

RNO: GO TO Step 34

34. Verify any SCM 0°F.

RNO: IF overcooling, OR exceeding limits in Rule 7 (SG Feed Control),

THEN throttle EFDW , as necessary. (see page 38)

This event is complete when EFDW is established from Unit 2, or as directed by the Lead Examiner.

Page 35 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 7 Page 8 of 9 Event

Description:

LOHT Requiring CBP Feed (M: All)

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

35. Notify the alternate unit to:

SRO/OATC Monitor EFDW parameters BOP Maintain UST level > 7.5'.

Enter appropriate TS/SLC for EFDW valves closed in manual.

36. IAAT Unit 1 EFDW is in operation, THEN initiate Encl. 5.9 (Extended EFDW Operation). (applies if Unit 1 TDEFDW Pump running).

37. WHEN directed by CRS, THEN EXIT.

EOP Encl 5.9 Encl. 5.9 (Extended EFDW Operation)

1. Monitor EFDW parameters on EFW graphic display.

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

3. IAAT feeding both SGs with one MD EFDWP is desired, THEN perform Steps 4 - 7.

RNO: GO TO step 8.

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.

This event is complete when EFDW is established from Unit 2, or as directed by the Lead Examiner.

Page 36 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 7 Page 9 of 9 Event

Description:

Time Position Applicant's Actions or Behavior EOP Encl 5.9 Crew Response:

10. Verify 1 TD EFDW PUMP operating.

RNO: 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 CRS 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.

Examiner Note: The CRS will most likely direct the RO to suspend Encl. 5.9 at this point due to higher priorities.

This event is complete when EFDW is established from Unit 2, or as directed by the Lead Examiner.

Page 37 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Rule 7 Feed Flow Rates Page 38 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 39 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 stop excessive heat transfer GO TO EHT tab.

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 AD-LS-ALL-0006 (Reportability).

Page 40 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam LOHT 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. All of the following exist:

Any SCM = 0°F HPI forced cooling NOT in GO TO LOSCM tab. LOSCM progress Condition other than RCS heat-up is the cause of loss of subcooling

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

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

7. 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.

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

EDL OR SGTR > 25 gpm

9. Individual available to make Announce plant conditions using PA notifications system.

Notify OSM to reference the NOTIFY Emergency Plan and AD-LS-ALL-0006 (Reportability).

Page 41 of 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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

1HP-25 following:

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 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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.

1HP-27

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 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 51

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam CRITICAL TASKS CT-1 ICS must be taken to HAND and FDW adjusted to prevent tripping the reactor on RPS Low Pressure (1810 psig) or RPS Variable Low Pressure. Adjustment will be dependent on how much time it takes to place ICS in HAND.

CT-2 Lockout EHC pumps to manually trip the turbine prior to reaching Rule 8 (PTS) entry conditions (400°F)

CT-3 Establish CBP feed prior to reaching 2300 psig RCS pressure or 375 inches Pressurizer level 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: 893 100% 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.

SASS is in Manual for calibration C GWD tank release is in progress per OP/1-2/A/1104/018 Just after or during a GWD release, 1SA-8/B-9 may alarm from RIA-32 sample point selected to 1 PRV System Filter Discharge. IF 1SA-8/B-9 is due to RIA 1 PRV System Filter Discharge, it can be considered an expected alarm Secondary AMSAC/DSS bypassed for calibration Unit 2 is supplying the AS header 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 ILT16-1 NRC Exam Facility: Oconee Scenario No.: 4 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________SRO

________________________ ________________________OATC

________________________ ________________________BOP Initial Conditions:

Reactor Power = 3.5%

Turnover:

SASS is in Manual Event Malfunction Event Event Type* Description No. No.

0a Override SASS in Manual 0b Override Standby LPSW Pump Auto Start Circuit Disabled 1 N: OATC, SRO Makeup to LDST 100 Gallons 2 Override C: BOP, SRO 1C Hotwell Pump Casing Water Level Low A LPSW Pump Trips and C LPSW Pump Fails to 3 Override C: BOP, SRO (TS)

Auto Start 4 MSS470 C: BOP, SRO (TS) 1C RBCU Cooler Rupture 5 MPI150 I: OATC, SRO (TS) PZR A RTD Fails Low 6 MCR061 C: OATC, SRO Continuous Rod Withdrawal Small Break LOCA MPS400 7 M: ALL 1A MDEFDW Pump fails to start MPS400D ES Channel 3 Fails to go to Manual

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

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Scenario 4 Event Summary Event 1: As soon as the crew takes the shift, the OATC will perform OP/1/A/1103/004 Enclosure 4.6 (RCS Makeup From 1A and 1B BHUT) to add approximately 100 gallons to the LDST for RCS inventory control.

Event 2: The crew will receive alarms indicating that 1C Hotwell Pump casing water level is low. The associated Alarm Response Guides will require the BOP to start a standby HWP and secure the 1C HWP. The BOP will also bypass the Powdex System as directed by the ARG.

Event 3: The A LPSW Pump will trip. This will result in several alarms to alert the operator of the failure since the standby LPSW Pump will not auto start. The associated Alarm Response Guides will direct entry into AP/1/A/1700/024 (Loss of LPSW). AP guidance will be used to restore normal LPSW system parameters by manually starting the C LPSW Pump. This will require the SRO to evaluate Tech Specs and enter the appropriate conditions.

Event 4: Once the C LPSW pump is started, a cooling water line for the 1C Reactor Building Cooling Unit (RBCU) will rupture inside containment. The BOP will use guidance provided in the associated Alarm Response Guide to secure the 1C RBCU and isolate cooling water to stop the leak. If time permits, the crew may decide to begin pumping the RBNS (due to the LPSW leakage from the 1C RBCU Cooler). If so, they will use OP/1/A/1104/007 Enclosure 4.1 (Pumping RBNS to 1"). This will require the SRO to evaluate Tech Specs and enter the appropriate conditions.

Event 5: The A PZR RTD will fail low causing PZR levels 1 & 2 to indicate low. With SASS in manual, this will cause 1HP-120 to begin throttling open in an attempt to restore the indicated PZR level. Actual PZR level will start to increase and LDST level will begin to decrease. The OATC is expected to place 1HP-120 in Hand and stabilize PZR level. The crew will refer to OP/1/A/1105/014 which will direct them to select PZR Level Channel 3 as the controlling channel. The OATC should then return 1HP-120 to AUTO. This will require the SRO to evaluate Tech Specs and enter the appropriate conditions.

Event 6: Control Rods will begin to withdraw and Reactor power will begin to increase. The crew will perform Plant Transient Response (PTR) to evaluate plant response and determine the cause of the associated transient. The OATC will either place the Diamond in manual and insert Control Rods to stabilize Reactor power or trip the Reactor due to the power increase. If the crew promptly diagnoses the failure and does not trip the Reactor, the scenario will continue by initiating Event 7.

Page 2 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Scenario 4 Event Summary Event 7: Once the event is initiated, RCS pressure will begin to rapidly decrease and ES Channels 1 & 2 will actuate on low RCS pressure. Once ES Channels 1 and 2 have actuated, the SRO will direct an operator to perform EOP Enclosure 5.1 (ES Actuation). After a few minutes ES Channels 3-6 will also actuate. EOP Enclosure 5.1 will require all actuated ES Channels to be placed in manual but ES Channel 3 will fail to go to manual which will require the operator to place the Odd Voters in override. Shortly after ES Channels 1 & 2 actuate, the crew will observe at least one SCM indication 0°F which will require performing Rule 2 (Loss of SCM) and entry into the EOP LOSCM tab. Rule 2 requires the operator to stop all RCPs within 2 minutes of any SCM indication 0°F. While performing Rule 2, the 1A Motor Driven EFDW Pump will not start which will require the Turbine Driven EFDW Pump to be started. Rule 3 (Loss of Main or Emergency FDW) is performed as directed by Rule 2 to raise SG levels to the loss of SCM setpoint. EOP Enclosure 5.9 (Extended EFDW Operation) will be performed when directed by Rule 3.

Page 3 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 1 Page 1 of 5 Event

Description:

Makeup To LDST 100 Gallons (N: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1103/004 Encl 4.6 Crew response:

SRO directs the OATC to use the in progress procedure OP/1/A/1103/004 SRO (Soluble Poison Control) Enclosure 4.6 (RCS Makeup From 1A and 1B BHUT) beginning at Step 2.1 to makeup to the RCS from 1A and 1B BHUT.

OP/1/A/1103/004, Encl. 4.6 (RCS Makeup From 1A and 1B BHUT) rev 105 Examiner Note: Steps 3.1 -3.3 are complete and the crew will start at Step 3.4 below.

2.1 Perform appropriate section(s) to achieve desired results:

Perform Section 3 (Makeup From 1A and 1B BHUT) for RCS Makeup 3.1 Determine required RCS Makeup volume by performing the following:

3.1.1 IF desired, utilize Enclosure 4.1 (RCS Boron Change Calculation) 3.1.2 IF two Letdown Filters are available, perform the following:

A. Review Component Boron Log for out-of-service Letdown Filter boron B. Make appropriate adjustments to Makeup volumes for placing second Letdown Filter in service 3.1.3 Perform the following:

A. Review Component Boron Log for 1A RC Bleed Storage Header boron. {18}

B. Make appropriate adjustments to Makeup volumes based on 1A RC Bleed Storage Header boron {18}

3.1.4 Record required Makeup volume: 100 gallons

( 70 gals 1A BHUT and 30 gals DW) 3.2 Ensure required RCS Makeup volume and source acceptable. (R.M.)

3.3 IF predicted change in boron concentration per shift is expected to be 10 ppm, notify Primary Chemistry of the following:

Total Makeup volume to be added Expected Boron change from the addition OATC 3.4 IF two Letdown Filters are available, perform the following:

Open 1HP-17 (1A LETDOWN FILTER INLET)

Open 1HP-18 (1B LETDOWN FILTER INLET) 3.5 Ensure open 1HP-16 (LDST MAKEUP ISOLATION).

This event is complete when Step 3.27 is complete, or as directed by the Lead Examiner.

Page 4 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 1 Page 2 of 5 Event

Description:

Makeup To LDST 100 Gallons (N: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1103/004 Encl 4.6 Crew response:

Note: The crew may choose to perform the makeup with 1HP-15 in AUTO OATC or MANUAL.

3.6 IF Makeup with 1HP-15 in "AUTO" desired, perform the following:

3.6.1 Select "S" on 1HP-15 Controller.

3.6.2 Enter batch size on 1HP-15 Controller. (R.M.)

3.6.3 Place 1HP-15 Controller in "AUTO".

3.6.4 Ensure "P" on 1HP-15 Controller.

3.7 WHILE making up to Unit 1 LDST from 1A and 1B BHUT, monitor the following indications: (R.M.)

Appropriate ranged NIs Primary tank levels Neutron error (if applicable)

CRD position (if applicable) 3.8 IF AT ANY TIME abnormal condition(s) require stopping RCS Makeup, perform the following: (RM) 3.8.1 Stop 1A BLEED TRANSFER PUMP.

3.8.2 IF RCS Makeup stopped due to alarm(s) OR abnormal indication(s), notify CRS.

3.8.3 WHEN conditions allow RCS Makeup to continue, perform one of the following:

Start 1A BLEED TRANSFER PUMP.

Go To Step 3.13 to terminate the addition.

3.9 Start 1A BLEED TRANSFER PUMP.

3.10 Open 1CS-46 (1A RC BLEED XFER PUMP DISCH).

3.11 IF increased Makeup flow required, perform the following: (AB-1, Unit 1-BTP Room).

Throttle 1CS-48 (1A BHUT Recirc) to establish desired flow.

Ensure 90 - 125 psig on 1CS-PG-0084.

3.12 WHEN required volume is added, ensure stop 1A BLEED TRANSFER PUMP.

3.13 Close 1CS-46 (1A RC BLEED XFER PUMP DISCH). (R.M.)

This event is complete when Step 3.27 is complete, or as directed by the Lead Examiner.

Page 5 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 1 Page 3 of 5 Event

Description:

Makeup To LDST 100 Gallons (N: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1103/004 Encl 4.6 Crew Response:

OATC NOTE:

If during RCS Makeup the wrong volume is added, an CRS shall evaluate affect on reactivity and take action to minimize reactivity management events..

1HP-15 Controller volume will be different from volume based on LDST level change.

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

Verify correct volume added Notify CRSRO of incorrect volume added.

3.15 Reset 1HP-15 Controller for Normal Operation.

1. Select STOP on 1HP-15 Controller

2. Select START on 1HP-15 Controller

3. Ensure 1HP-15 Controller Start/Stop set to START

4. Ensure 1HP-15 Controller mode selector set to MANUAL

5. Ensure 1HP-15 Controller valve position set to 100% open

6. Ensure 1HP-15 Controller display selector set to P

7. Ensure 1HP-15 Controller display indicates 0 3.16 Record 1A BHUT boron in Component Boron Log for 1A RC Bleed Storage Header Note: The crew may choose to perform the makeup with 1HP-15 in AUTO or MANUAL.

3.17 IF Makeup with 1HP-15 in "AUTO" desired, perform the following:

3.16.1 Select "S" on 1HP-15 Controller.

3.16.2 Enter batch size on 1HP-15 Controller. (R.M.)

3.16.3 Place 1HP-15 Controller in "AUTO".

3.16.4 Ensure "P" on 1HP-15 Controller.

This event is complete when Step 3.27 is complete, or as directed by the Lead Examiner.

Page 6 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 1 Page 4 of 5 Event

Description:

Makeup To LDST 100 Gallons (N: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1103/004 Encl 4.6 Crew Response:

OATC NOTE: If feed and bleed occurred during first makeup, 1HP-16 closed when the addition batched out (does NOT apply) 3.18 Ensure open 1HP-16 (LDST MAKEUP ISOLATION) 3.19 IF AT ANY TIME abnormal condition(s) require stopping RCS Makeup, perform the following: (RM) 3.19.1 Stop 1B BLEED TRANSFER PUMP.

3.19.2 IF RCS Makeup stopped due to alarm(s) OR abnormal indication(s), notify CRS.

3.19.3 WHEN conditions allow RCS Makeup to continue, perform one of the following:

Start 1B BLEED TRANSFER PUMP.

Go To Step 3.22 to terminate the addition.

3.20 Start 1B BLEED TRANSFER PUMP.

3.21 Open 1CS-56 (1B RC BLEED XFER PUMP DISCH).

3.22 IF increased Makeup flow required, perform the following: (AB-1, Unit 1-BTP Room).

Throttle 1CS-58 (1A BHUT Recirc) to establish desired flow.

Ensure 90 - 125 psig on 1CS-PG-0085.

3.23 WHEN required volume is added, stop 1B BLEED TRANSFER PUMP.

3.24 Close 1CS-56 (1B RC BLEED XFER PUMP DISCH). (R.M.)

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

Verify correct volume added Notify CRS of incorrect volume added.

3.26 Reset 1HP-15 Controller for Normal Operation. (see page 6) 3.27 Close 1HP-16 (LDST MAKEUP ISOLATION).

This event is complete when Step 3.27 is complete, or as directed by the Lead Examiner.

Page 7 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 1 Page 5 of 5 Event

Description:

Makeup To LDST 100 Gallons (N: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1103/004 Encl 4.6 Crew Response:

3.28 Record RCS batch volume in narrative log.

OATC NOTE:

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

Only one Letdown Filter should be in service to prevent clogging both filters during startup.

3.29 IF desired to remove one Letdown Filter from service, perform the following: (Continue) 3.29.1 Verify > 10 minutes since LDST Makeup was secured. {8} (R.M.)

Examiner Note: Notify the crew that 10 minutes have elapsed.

3.29.2 Position one of the following:

Close 1HP-17 (1A LETDOWN FILTER INLET)

Close 1HP-18 (1B LETDOWN FILTER INLET) 3.29.3 Record RCS boron for out-of-service Letdown Filter in Component Boron Log 3.30 IF RCS sample for boron required, notify Chemistry to sample 3.31 IF increased Makeup flow from 1A BHUT was required, perform the following:

3.31.1 Start 1A BLEED TRANSFER PUMP 3.31.2 IF discharge pressure is NOT 90-110 psig, throttle 1CS-48 to obtain 90 - 110 psig on 1CS-PG-0084 3.31.3 Stop 1A BLEED TRANSFER PUMP 3.32 IF increased Makeup flow from 1B BHUT was required, perform the following:

3.32.1 Start 1B BLEED TRANSFER PUMP 3.32.2 IF discharge pressure is NOT 90-110 psig, throttle 1CS-58 to obtain 90 - 110 psig on 1CS-PG-0085 3.32.3 Stop 1B BLEED TRANSFER PUMP This event is complete when Step 3.27 is complete, or as directed by the Lead Examiner.

Page 8 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 2 Page 1 of 1 Event

Description:

1C Hotwell Pump 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)

Crew Response:

SRO The SRO should direct the BOP to refer to ARG 1SA-9/E-5 Alarm Response Guide 1SA-9/E-5 (HWP C Casing Water Level Low) rev 047 BOP 3.1 IF '1C' HWP is in operation, then immediately:

Start a standby HWP.

Trip '1C' HWP.

Note: When the 1C HWP is tripped, OAC alarm 1C HWP LOCA/LS OFF will actuate and the crew may place the LOCA Load Shed switch to an operating Hotwell pump per the OAC alarm response guide.

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 9 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 3 Page 1 of 3 Event

Description:

A LPSW Pump Trips and C LPSW Pump Fails to Auto Start (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior Plant response:

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

OAC Alarm LPSW HDR Pressure LO LO OAC Alarm LPSW leakage accumulator level OAC Alarm LO LO RCP MTR Cooler Inlet HDR LPSW LPSW Header A/B Pressure Gauge indicates low Crew Response:

SRO/BOP The SRO should direct the BOP to refer to ARG 1SA-9/A-9 The OATC may refer to the OAC alarm response BOP ARG 1SA-9/A-9 (LPSW Header A Press Low) rev 047 3.1 Refer to AP/1/A/1700/024 (Loss of LPSW) (next page) 3.2 Have Unit 2 refer to AP/2/A/1700/024 (Loss of LPSW).

OATC OAC Alarm Response

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

2. Notify engineering

3. Refer to TS 3.7.7 OAC Alarm Response

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

2. Refer to AP/1/A/1700/024 (Loss of LPSW)

3. Notify Engineering

4. Refer to Tech Spec 3.7.7 Examiner Note: The SRO may direct an RO to start the C LPSW pump per OMP 1-18 prior to entering AP/24.

Examiner Note: The SRO may direct an RO to start the C LPSW pump per OAC alarm response prior to entering AP/24.

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

Page 10 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 3 Page 2 of 3 Event

Description:

A LPSW Pump Trips and C LPSW Pump Fails to Auto Start (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/024 Crew Response:

AP/1/A/1700/024 (Loss of LPSW) rev 028 SRO/BOP NOTE Unit 1 normally handles LPSW System operation unless otherwise directed by the CRS 4.1 Verify Unit 1 is going to handle LPSW system operations.

4.2 IAAT any LPSW pump is cavitating, THEN perform Steps 4.3 - 4.4 RNO: GO TO Step 4.5 4.5 Verify LPSW pressure 70 psig 4.6 Ensure Unit 1/2 Standby LPSW Pump Auto Start Circuit in Disable NOTE If an LPSW pump is stopped due to cavitation, it is NOT available until filled and vented.

4.7 IAAT a non-operating LPSW pump is available AND pump start is desired, THEN start the available pump (C LPSW Pump will start).

Examiner Note: When the C LPSW pump is manually started, TIMER 4 will auto actuate after 5 seconds to initiate Event 4.

4.8 IAAT LPSW to all RBCUs has been isolated, AND LPSW header pressure is > 25 psig, THEN perform Step 4.9 RNO: GO TO Step 4.10 4.10 Verify normal LPSW System operation is restored.

NOTE 1LPSW-1054, 1055, 1061, and 1062 will close to isolate RB Auxiliary Coolers on low LPSW pressure.

If RB Auxiliary Coolers are aligned for outage cooling with the portable chiller, sliding links have been positioned such that 1LPSW-1054, 1055, 1061, and 1062 will NOT close.

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

Page 11 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 3 Page 3 of 3 Event

Description:

A LPSW Pump Trips and C LPSW Pump Fails to Auto Start (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/024 Crew Response:

SRO/BOP 4.11 Verify that RB Auxiliary Coolers have isolated:

1LPSW-1054 closed 1LPSW-1055 closed 1LPSW-1061 closed 1LPSW-1062 closed RNO: GO TO Step 4.14 4.14 EXIT this procedure SRO TS 3.7.7 (LOW PRESSURE SERVICE WATER SYSTEM)

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

Condition B (7 days) Restore the LPSW WPS to OPERABLE status.

TS 3.3.28 (LPSW PUMP AUTO START CIRCUITRY)

Condition A (7 days) Restore LPSW standby pump auto-start circuitry to OPERABLE status.

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

Page 12 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 4 Page 1 of 3 Event

Description:

1C RBCU Cooler Rupture (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior Plant Response:

1SA-9/D-9 (LPSW RBCU C Cooler Rupture) 1SA-9/A-6 (RB Normal Sump Level High/Low)

RB normal sump level will increase 1C RBCU LPSW flow indicator indicates low on 1VB2 Crew Response:

SRO/BOP ARG for 1SA-9/D-9 (RBCU C Cooler Rupture) rev 047 3.1 Verify alarm is valid by checking RBCU 1C Inlet Flow and RBCU 1C delta flow.

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

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

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

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

3.6.1 Isolate the 1C RBCU Cooler as follows:

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

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

C. Evaluate TS 3.6.3 Condition C (does NOT apply)

D. Evaluate TS 3.6.5 for inoperable RBCU (page 15)

E. Continue to monitor RBNS level for increase.

F. IF RBNS level is still increasing, notify Engineering to evaluate further isolation of 1C RBCU.

This event is complete when the 1C RBCU rupture is isolated and the SRO has referred to TS, or as directed by the Lead Examiner.

Page 13 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 4 Page 2 of 3 Event

Description:

1C RBCU Cooler Rupture (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior Crew Response:

ARG 1SA-9 / D-9 (RBCU C Cooler Rupture) (cont.):

BOP 3.6.2 Refer to Technical Specifications 3.6.3 Refer to SLC 16.9.12 (Does NOT apply) 3.6.4 Refer to OP/1/A/1104/010 (LPSW) 3.6.5 Refer to OP/1/A/1104/015 (RB Cooling System)

Examiner Note: The crew may decide to pump the RB Normal Sump. If so, see the steps below from OP/1/A/1104/007 (LWD System) Enclosure 4.1 (Pumping RBNS to 1")

OP/1/A/1104/007 Enclosure 4.1 (Pumping RBNS 1 Inch) rev 030 BOP 3.1 Verify MWHUT level adequate to receive waste volume.

3.2 Position the following:

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

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

1A RB NORM SUMP PUMP 1B RB NORM SUMP PUMP 3.4 WHEN RBNS is at desired level OR at 1" (low level alarm), ensure the following:

1A RB NORMAL SUMP PUMP "OFF".

1B RB NORMAL SUMP PUMP "OFF".

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

Close 1LWD-1 (RB NORMAL SUMP ISOLATION)

Close 1LWD-2 (RB NORMAL SUMP ISOLATION)

SRO This event is complete when the 1C RBCU rupture is isolated and the SRO has referred to TS, or as directed by the Lead Examiner.

Page 14 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 4 Page 3 of 3 Event

Description:

1C RBCU Cooler Rupture (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior Crew Response:

Note: TS 3.6.3 Condition C does not apply since no Containment Isolation Valves are inoperable.

SRO TS 3.6.5 REACTOR BUILDING SPRAY AND COOLING SYSTEMS Condition B (7 days and 14 days from discovery of failure to meet LCO)

Restore reactor building cooling train to OPERABLE status.

TS 3.4.15 (RCS LEAKAGE DETECTION INSTRUMENTATION)

Condition A (Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) Perform SR 3.4.13.1 AND (30 days) Restore required containment sump level indication to OPERABLE status This event is complete when the 1C RBCU rupture is isolated and the SRO has referred to TS, or as directed by the Lead Examiner.

Page 15 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 5 Page 1 of 2 Event

Description:

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

Time Position Applicant's Actions or Behavior Booth Cue: If needed, call the BOP to request the following: This is Secondary Chemistry. I need you to report steam flow to Unit 1 E Heaters as read on the gauge on 1VB1". This will help to ensure the OATC will take actions for the PZR RTD failure.

Plant Response:

OAC alarm (RC PZR level 1&3 mismatch)

OAC alarm (RC PZR level 2&3 mismatch)

Statalarm 1SA-02/C-3 (RC Pressurizer Level High/Low)

PZR level 1 and 2 indicates 95 inches PZR level 3 indicates 120 inches and slowly increasing Crew Response:

BOP/SRO Refer to ARG 1SA-02/C-3 (RC Pressurizer Level High/Low): rev 033 3.1 Check alternate PZR level indications..

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

Examiner Note: The RO may take 1HP-120 to MANUAL to control Pzr level. If so, they should place it in AUTO after the failure is addressed.

Examiner Note: The SRO may direct the OATC to select PZR level 3 prior to referencing OP/1/A/1105/014.

3.1 Refer to the following procedures as required:

AP/1/A/1700/002 (Excessive RCS Leakage)

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

AP/1/A/1700/032 (Loss of Letdown) 3.4 Refer to Technical Specification 3.4.9 (Pressurizer) (does not apply) 3.5 Refer to Technical Specification 3.3.8 (PAM Instrumentation) (Page 17) 3.6 Refer to OP/1/A/1105/014 Control Room Instrumentation Operation And Information.

This event is complete when PZR level 3 has been selected, 1HP-120 is in Auto, and the SRO has referred to TS, or as directed by the Lead Examiner.

Page 16 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 5 Page 2 of 2 Event

Description:

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

Time Position Applicant's Actions or Behavior Crew Response:

OP/1/A/1105/014 Enclosure 4.11 (SASS Information) rev 042 SRO/OATC 3.2 SASS (Smart Automatic Signal Selector) Manual Operation 3.2.1 IF "MISMATCH" light is on and "TRIP A" or "TRIP B" light is on, a SASS trip has occurred.

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

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

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

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

(Select Pzr Level #3) 3.2.3 Initiate a Work Request to repair faulty signal TS 3.3.8 POST ACCIDENT MONITORING (PAM) INSTRUMENTATION SRO Condition A (30 days) Restore required channel to OPERABLE status.

This event is complete when PZR level 3 has been selected, 1HP-120 is in Auto, and the SRO has referred to TS, or as directed by the Lead Examiner.

Page 17 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 6 Page 1 of 1 Event

Description:

Continuous Rod Withdrawal (C: OATC, SRO)

Time Position Applicant's Actions or Behavior Plant response:

Control Rods withdrawing without operator action SRO/OATC NI-5 thru NI-8 indicate increasing reactor power SURs on Wide Range NIs increasing Crew Response:

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

The OATC should:

Verbalize to the SRO reactor power level and direction of movement Place the Diamond and both FDW Masters in MANUAL and insert control rods to stabilize the plant Remain focused on reactor power level during the transient in order to stabilize reactor power pre-transient power level The BOP should:

Determine if a valid ICS runback signal exists and report no valid (ICS) runback and then monitor RCS pressure and inventory Contact FIN-24 (SPOC) to investigate the continuous rod withdrawal Examiner Note: The OATC may elect to trip the Reactor during this transient per OMP 1-18 Attachment J (Plant Transient Response).

OMP 1-18 Attachment J states the following:

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

Reactor power level approaches any operating limit Reactor power level exceeds the pre-transient power level by greater than 5% AND the cause of the power change is NOT understood, OR is NOT controllable Any time plant conditions are considered uncontrollable or unsafe Examiner/Booth Cue: If the crew does NOT manually trip the Reactor, then once they have completed PTR, FIRE TIMER 7 to initiate Event 7 when directed by the Lead Examiner.

This event is complete once the Reactor has tripped or as directed by the Lead Examiner.

Page 18 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 7 Page 1 of 9 Event

Description:

Small Break LOCA (M: ALL)

Time Position Applicant's Actions or Behavior Plant response:

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

RCS pressure and PZR level decreasing ES 1-6 actuate RCS subcooling margin will indicate 0°F Reactor Building level increasing Crew response:

SRO/OATC The SRO will direct the OATC to perform IMAs.

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.

SRO/BOP The SRO will direct the BOP to perform a Symptoms Check.

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)

OATC/BOP SRO will transfer from the Subsequent Actions Tab to the LOSCM tab (page 20) from the Parallel Actions Page (page 57) to direct crew activities.

Once the RCS saturates, one of the ROs will perform Rule 2 (page 23).

BOP/OATC The RO not performing Rule 2 will begin performing Enclosure 5.1 due to ES actuation (page 28).

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

Page 19 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 7 Page 2 of 9 Event

Description:

Small Break LOCA (M: ALL)

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

LOSCM tab

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

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

4. 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 LOCA CD tab.

5. Verify SSF activated per AP/25 with SSF RC Makeup required.

RNO: GO TO Step 7

7. Verify all exist:

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

8. GO TO Step 104.

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

Page 20 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 7 Page 3 of 9 Event

Description:

Small Break LOCA (M: ALL)

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

SRO LOSCM tab (continued) 104. Open 1AS-40 while closing 1MS-47.

105. Verify HPI forced cooling in progress.

RNO: Close 1RC-4 106. Close 1GWD-17, 1HP-1, 1HP-2, and 1RC-3 107. Verify either:

Core superheated Rx vessel head level at 0 RNO: GO TO Step 109 109. IAAT BWST level is 19', THEN initiate Encl 5.12 (ECCS Suction Swap to RBES).

CAUTION If TDEFDWP is being used for SG feed, reducing SG pressure below 250 psig can result in reduced pumping capability 110. Maintain SG pressure < RCS pressure utilizing either:

__ TBVs

__ ADVs 111. Verify any SG available for feeding/steaming.

112. Initiate Encl 5.16 (SG Tube-to-Shell T Control).

113. Verify indications of SGTR exist.

RNO: GO TO Step 116 116. Verify HPI forced cooling in progress.

RNO: GO TO Step 118 118. Verify CETCs trend decreasing.

119. Verify primary to secondary heat transfer is excessive.

RNO: GO TO Step 121 121. Verify indications of SGTR 25 gpm.

RNO: GO TO Step 123 123. Verify required RCS makeup flow within normal makeup capability.

RNO: GO TO LOCA CD tab (page 22)

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

Page 21 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 7 Page 4 of 9 Event

Description:

Small Break LOCA (M: ALL)

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

LOCA Cooldown Tab

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

2. Verify ES actuated.

3. GO TO Step 7.

4. Verify two LPI pumps operating.

RNO: IF any HPI pump is operating, AND LPI/HPI piggyback is aligned, THEN maximize total LPI flow < 3100 gpm by throttling HPI flow.

5. Notify Unit 3 to start the following:

3A Outside Air Booster Fan 3B Outside Air Booster Fan CT-2 6. Start the following: (should already be started in Encl. 5.1 step 28)

(Page 31)

A Outside Air Booster Fan B Outside Air Booster Fan

7. Perform the following:

Ensure all RBCUs in low speed.

Open 1LPSW-18 Open 1LPSW-21 Open 1LPSW-24

8. Initiate Encl 5.35 (Containment Isolation).

9. Start all RB Aux fans.

10. IAAT either of the following exists:

LPI FLOW TRAIN A plus LPI FLOW TRAIN B 3400gpm Only one LPI header in operation with header flow 2900 gpm THEN GO TO Step 11.

RNO: GO TO Step 43 43 Initiate Encl 5.36 (Equipment Alignment For Plant Shutdown)

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

Page 22 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 7 Page 5 of 9 Event

Description:

Small Break LOCA (M: ALL)

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

OATC/BOP Rule 2 (Loss of SCM)

1. IAAT all the following exist:

Any SCM 0°F Rx power 1%

2 minutes elapsed since loss of SCM THEN perform steps 2 & 3 CT-1 2. Stop all RCPs

3. Notify CRS of RCP status.

4. Verify Blackout exists.

RNO: GO TO Step 6

6. Open 1HP-24 & 25

7. Start all available HPI Pumps

8. GO TO step 13.

13. Open 1HP-26 & 27

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

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

RNO: GO TO step 17

17. IAAT flow limits are exceeded THEN perform Steps 18 - 20 RNO: GO TO Step 21

18. Place Diverse HPI in BYPASS.

19. Perform both:

Place ES CH 1 in MANUAL.

Place ES CH 2 in MANUAL.

20. Throttle HPI to maximize flow flow limit.

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

Page 23 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 7 Page 6 of 9 Event

Description:

Small Break LOCA (M: ALL)

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

BOP/OATC Rule 2 ( Loss of SCM) (Continued)

21. Notify CRS of HPI status.

22. Verify RCS pressure >550 psig

23. IAAT either exists:

LPI FLOW TRAIN A plus LPI FLOW TRAIN B 3400 gpm Only one LPI header in operation with header flow 2900 gpm THEN GO TO Step 24.

RNO: GO TO Step 35

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

B. Notify CRS the ADVs are being aligned for use.

36. Select OFF for both Digital Channels on AFIS HEADER A

37. Select OFF for both Digital Channels on AFIS HEADER B

38. Verify any EFDW pump operating.

RNO: Place 1FDW 315 and 1FDW-316 in MANUAL and close.

39. Start MD EFDW pumps on all intact SGs:

1A MD EFDWP (1A MD EFDWP will not start) 1B MD EFDWP RNO: Start 1 TD EFDW PUMP

40. Verify any EFDW pump operating.

41. Verify both SGs intact.

42. Establish 300 gpm EFDW flow to each SG

43. Verify both MD EFDWPs operating. (the 1A MD EFDWP did not start)

RNO: 1. IF 1TD EFDW PUMP is operating, OR NO Main FDW pumps operating, GO TO Step 45

2. GO TO Step 47

45. Trip both Main FDW pumps.

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

Page 24 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 7 Page 7 of 9 Event

Description:

Small Break LOCA (M: ALL)

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

Rule 2 ( Loss of SCM) (Continued)

46. Place FDW block valve switches in CLOSE:

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

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

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

49. Notify CRS of SG feed status.

CAUTION If 1 TD EFDW PUMP is being used for SG feed and Unit 1 is supplying the Auxiliary Steam header, reducing SG pressure below 250 psig can result in reduced pumping capability.

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

RCS pressure using either:

TBVs Dispatch two operators to perform Encl 5.24 (operation of the ADVs)

51. Verify any Main FDW pump operating.

RNO: GO TO Step 58.

58. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete. (page 26)

59. WHEN directed by CRS, THEN EXIT.

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

Page 25 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 7 Page 8 of 9 Event

Description:

Small Break LOCA (M: ALL)

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

SRO/OATC Rule 3 (Loss of Main or Emergency Feedwater)

1. Verify loss of Main FDW/EFDW is due to TBF.

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 (HPI Forced Cooling)

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

5. Verify any EFDW pump operating.

6. GO TO Step 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 0F RNO: IF overcooling OR exceeding limits in Rule 7, THEN throttle EFDW as necessary.

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

46. WHEN directed by CRS, THEN EXIT.

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

Page 26 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 7 Page 9 of 9 Event

Description:

Small Break LOCA (M: ALL)

Time Position Applicant's Actions or Behavior EOP Encl 5.9 Crew Response:

EOP Encl 5.9 (Extended EFDW Operation)

1. Monitor EFDW parameters on EFW graphic display.

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

3. IAAT feeding both SGs with one MD EFDWP is desired, THEN perform steps 4 - 7.

RNO: GO TO Step 8

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

10. Verify 1 TD EFDW PUMP operating.

RNO: 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.

Note: The SRO should determine that continuing in Encl 5.9 is not a priority at this time and direct the RO from the LOSCM Tab of the EOP.

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

Page 27 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam EOP Enclosure 5.1 (ES Actuation)

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 28 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 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 74.

8. __ Verify any RCP operating. __ GOTO Step 10.

9. Open:

__ 1HP-20

__ 1HP-21

10. __ IAAT any RCP is operating, __ GOTO Step 16.

AND ES Channels 5 and 6 actuate, THEN perform Steps 11 - 15.

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. __ Verify any RCP is operating __ GO TO Step 16

13. Open:

__ 1CC-7

__ 1CC-8

__ 1LPSW-15

__ 1LPSW-6

14. __ Ensure only one CC pump operating.

15. __ Ensure Standby CC pump in AUTO.

Page 29 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

16. __ IAAT ES Channels 3 & 4 are actuated, __ GO TO Step 54.

THEN GO TO Step 17.

17. __ Place Diverse LPI in BYPASS. __ Place Diverse LPI in OVERRIDE.

18. 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}

19. __ IAAT any LPI pump is operating against a shutoff head, CT-3 THEN at the CR SRO's discretion, stop affected LPI pumps. {6, 22}

20. __ IAAT RCS pressure is < LPI pump __ GOTO Step 23.

shutoff head, THEN perform Steps 21 - 22.

21. Perform the following: 1. __ Stop 1A LPI PUMP.

__ Open 1LP-17. 2. __ Close 1LP-17.

__ Start 1A LPI PUMP.

22. Perform the following: 1. __ Stop 1B LPI PUMP.

__ Open 1LP-18. 2. __ Close 1LP-18.

__ Start 1B LPI PUMP.

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Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

23. __ IAAT 1A and 1B LPI PUMPs are __ GO TO Step 26.

off / tripped, AND all exist:

__ RCS pressure < LPI pump shutoff head

__ 1LP-19 closed

__ 1LP-20 closed THEN perform Steps 24 - 25.

24. Open:

__ 1LP-9

__ 1LP-10

__ 1LP-6

__ 1LP-7

__ 1LP-17

__ 1LP-18

__ 1LP-21

__ 1LP-22

25. __ Start 1C LPI PUMP.

26. __ IAAT 1A LPI PUMP fails while operating, AND 1B LPI PUMP is operating, THEN close 1LP-17.

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

28. Start:

__ A OUTSIDE AIR BOOSTER FAN CT- 2

__ B OUTSIDE AIR BOOSTER FAN

29. Notify Unit 3 to start:

__ 3A OUTSIDE AIR BOOSTER FAN

__ 3B OUTSIDE AIR BOOSTER FAN Page 31 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

30. Verify open: __ IF CR SRO desires 1CF-1 and 1CF-2

__ 1CF-1 open,

__ 1CF-2 THEN open:

__ 1CF-1

__ 1CF-2

31. __ Verify 1HP-410 closed. 1. __ Place 1HP-120 in HAND.

2. __ Close 1HP-120.

32. __ Secure makeup to the LDST.

33. __ 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: