ML17193A361

302 Final Items 2B - Delay Release 2 Yrs

ML17193A361
Person / Time
Site:	Oconee
Issue date:	07/12/2017
From:	NRC/RGN-II
To:
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Download: ML17193A361 (448)

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Appendix D Scenario Outline Form ES D-1 ILT16-2 NRC Exam Facility: Oconee Scenario No.: 1 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________ SRO

________________________ ________________________ OATC

________________________ ________________________ BOP Initial Conditions:

• Reactor Power = 75%

Turnover:

• SASS is in Manual for calibration

• AMSAC/DSS is bypassed for calibration

• PT/0/A/0610/017 is in progress to perform functional verification of SL breakers Event Malfunction Event Event Type* Description No. No.

0a Override AMSAC/DSS Bypassed 0b Override SASS in Manual 0c Override Standby CC Pump Auto Start 1 N: BOP, SRO Functional Verification of SL Breakers 1A CC Pump Trips & Standby CC Pump Fails to Auto 2 MPS290 C: BOP, SRO Start 3 Override I: BOP, SRO 1NI-5 Power Failure 1A HPI Pump Trips & 1B HPI Pump Fails to Auto 4 Override C: OATC, SRO (TS)

Start MPI040 5 MPI070 I: OATC, SRO Loop 1A RC Flow Fails Low MPS031 6 MPS031D R: OATC, SRO (TS) 80 gpm RCS Leak / Manual Power Reduction MPS031D Small Break LOCA 7 MPS150 M: ALL

• 1C HPI Pump Fails to Start on ES Override

• 1HP-24 Fails Closed

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

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam SCENARIO 1 EVENT

SUMMARY

Event 1: When the crew takes the shift, the SRO will direct the BOP to perform PT/0/A/0610/017 Enclosure 13.11 (Functional Verification Of SL Breaker(s). The SRO will enter TS 3.8.1 Condition D by procedure and then the BOP will perform a functional check of SL1 and SL2 breakers.

Event 2: The operating Component Cooling Pump (1A CC Pump) will trip and the Standby CC Pump (1B CC Pump) will fail to auto start. The BOP will reference an Alarm Response Guide which will direct manually starting the Standby CC Pump. Since there will be no CC flow until the Standby CC Pump is started, Letdown temperature will begin to increase and 1HP-5 will automatically close on high Letdown temperature (135°F). The SRO will then enter AP/1/A/1700/032 (Loss of Letdown) to restore Letdown.

Event 3: 1NI-5 will lose DC power which will result in 1NI-5 reading 0% power. The BOP will reference an Alarm Response Guide which will direct the crew to bypass the 1A RPS channel in accordance with OP/1/A/1105/014 (Control Room Instrumentation Operation and Information).

Event 4: The operating High Pressure Injection Pump (1A HPI Pump) will trip and the Standby HPI Pump (1B HPI Pump) will fail to auto start. The SRO will enter AP/1/A/1700/014 (Loss of Normal HPI Makeup and/or RCP Seal Injection) to start the Standby (1B) HPI Pump and re-establish normal HPI Makeup and RCP Seal Injection. The SRO will enter TS 3.5.2 Condition A for the inoperable HPI Pump.

Event 5: 1A Loop RCS Flow instrument will fail low which will cause ICS to re-ratio Feedwater in an attempt to restore the primary to secondary heat balance. Once alarms are received, the crew will perform Plant Transient Response to stabilize the plant. The OATC will re-ratio Feedwater to restore the heat balance. Once the plant is stable, the SRO will enter AP/1/A/1700/028 (ICS Instrument Failures) and ensure the appropriate ICS stations are in manual and BOP will perform an instrument surveillance for the failed instrumentation.

Event 6: The RCS will develop an unidentified leak of approximately 80 gpm. Once alarms are received, the SRO will enter AP/1/A/1700/002 (Excessive RCS Leakage). Since the RCS leak will be greater than Letdown Storage Tank makeup capability from 1A Bleed Holdup Tank, the crew will initiate AP/1/A/1700/029 (Rapid Unit Shutdown) and manually shutdown the unit. The SRO will enter TS 3.4.13 Conditions A & B.

Event 7: Once Reactor power has been decreased > 10% and auxiliary power has been transferred to the Startup Transformer in Event 6, the RCS leak will propagate into a Small Break LOCA. The 1C HPI Pump will fail to automatically start and 1HP-24 will fail closed when ES actuates. The SRO will Transfer to the LOSCM tab of the EOP.

One RO will perform Rule 2 (Loss of SCM) and the other RO will perform EOP Enclosure 5.1 (ES Actuation).

Page 2 of 59

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

Description:

Functional Verification of SL Breakers (N: BOP, SRO)

Time Position Applicants Actions or Behavior PT/0/A/0610/017 Crew response:

SRO directs the BOP to perform PT/0/A/0610/017 Enclosure 13.11 (Functional SRO Verification Of SL Breakers)

BOP PT/0/A/0610/017 Encl 13.11 (Functional Verification of SL Breakers) rev 29 2.1 Perform the following:

• IF Unit 1 in MODE 1, 2, 3 or 4, enter TS 3.8.1 Condition D

• IF Unit 1 in MODE 5, 6 or during movement of recently irradiated fuel assemblies, AND Underground Power Path being credited as an emergency power source, enter TS 3.8.2 Condition B (N/A)

• IF Unit 2 in MODE 1, 2, 3 or 4, enter TS 3.8.1 Condition D

• IF Unit 2 in MODE 5, 6 or during movement of recently irradiated fuel assemblies, AND Underground Power Path being credited as an emergency power source, enter TS 3.8.2 Condition B (N/A)

• IF Unit 3 in MODE 1, 2, 3 or 4, enter TS 3.8.1 Condition D

• IF Unit 3 in MODE 5, 6 or during movement of recently irradiated fuel assemblies, AND Underground Power Path being credited as an emergency power source, enter TS 3.8.2 Condition B (N/A) 2.2 IF required, perform functional check of SL1 CT5 STBY BUS 1 FEEDER as follows:

2.2.1 Verify SL1 & SL2 TRIP INTERLOCK DEFEAT CH1 switch in CENTRAL position 2.2.2 Verify CT5 BUS 1 AUTO/MAN transfer switch in MAN 2.2.3 Close SL1 CT5 STBY BUS 1 FEEDER 2.2.4 Verify 4160V on STANDBY BUS 1 VOLTS (2AB3) 2.2.5 Open SL1 CT5 STBY BUS 1 FEEDER This event is complete when the SRO has exited TS 3.8.1 for Unit 1, or as directed by the Lead Examiner.

Page 3 of 59

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

Description:

Functional Verification of SL Breakers (N: BOP, SRO)

Time Position Applicants Actions or Behavior PT/0/A/0610/017 Crew response:

PT/0/A/0610/017 Encl 13.11 (Functional Verification of SL Breakers)

BOP 2.3 IF required, perform functional check of SL2 CT5 STBY BUS 2 FEEDER as follows:

2.3.1 Verify SL1 & SL2 TRIP INTERLOCK DEFEAT CH2 switch in "CENTRAL" position 2.3.2 Verify CT5 BUS 2 AUTO/MAN transfer switch in "MAN" 2.3.3 Close SL2 CT5 STBY BUS 2 FEEDER 2.3.4 Verify 4160V on STANDBY BUS 2 VOLTS (2AB3) 2.3.5 Open SL2 CT5 STBY BUS 2 FEEDER 2.4 Perform the following:

• IF entered on Unit 1, evaluate exiting TS 3.8.1 Condition 'D'

• IF entered on Unit 1, evaluate exiting TS 3.8.2 Condition 'B' (N/A)

• IF entered on Unit 2, evaluate exiting TS 3.8.1 Condition 'D'

• IF entered on Unit 2, evaluate exiting TS 3.8.2 Condition 'B' (N/A)

• IF entered on Unit 3, evaluate exiting TS 3.8.1 Condition 'D'

• IF entered on Unit 3, evaluate exiting TS 3.8.2 Condition 'B' (N/A)

This event is complete when the SRO has exited TS 3.8.1 for Unit 1, or as directed by the Lead Examiner.

Page 4 of 59

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

Description:

1A CC Pump Trips & Standby CC Pump Fails to Auto Start (C: BOP, SRO)

Time Position Applicants Actions or Behavior Plant response:

• 1SA-9/B-1 (CC CRD RETURN FLOW LOW)

• 1SA-9/C-1 (CC COMP COOLING RETURN FLOW LOW)

• 1SA-2/C-1 (LETDOWN TEMPERATURE HIGH)

• 1HP-5 (Letdown Isolation) will close due to high letdown temperature

• CC Total Flow Low

• Component Cooling Pressure Low Crew response:

BOP Refer to ARG 1SA-9/B-1 OR 1SA-9/C-1 ARG 1SA-09/B-1 ARG 1SA-09/B-1 3.1 IF ES 5 or 6 has actuated, (N/A) 3.2 IF 1CC-7 or 1CC-8 are closed, (N/A) 3.3 IF 1SA-09/C-1 is in alarm AND the Standby CC Pump did NOT start, perform the following:

3.3.1 Verify CC Surge Tank level > 12 3.3.2 Start Standby CC Pump 3.4 IF NO CC Pumps are operating, Go To AP/20 (Loss of Component Cooling)

ARG 1SA-09/C-1 ARG 1SA-09/C-1 3.1 IF ES 5 or 6 has actuated, (N/A) 3.2 IF 1CC-7 or 1CC-8 are closed, (N/A) 3.3 IF Standby CC Pump did NOT start, perform the following:

3.3.1 Verify CC Surge Tank level > 12 3.3.2 Start Standby CC Pump 3.4 IF NO CC Pumps are operating, Go To AP/20 (Loss of Component Cooling)

Examiner Note: Once the 1B CC pump is started, the SRO will refer to AP/32 (Loss of Letdown).

This event is complete when the Standby HPI Pump is placed back in Auto, or as directed by the Lead Examiner.

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

Description:

1A CC Pump Trips & Standby CC Pump Fails to Auto Start (C: BOP, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/032 Crew response:

AP/1/A/1700/032 (Loss of Letdown) rev 07 4.1 Verify a total loss of letdown exists SRO/BOP 4.2 Place 1HP-120 in HAND and reduce demand to zero 4.3 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.

4.4 Throttle 1HP-31 to establish 12 - 15 gpm SEAL INLET HDR FLOW NOTE: The running HPIP may operate below 65 gpm for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

HPIP time of operation below minimum flow is cumulative.

4.5 Verify HPI pump flow 65 gpm (30 gpm Recirc + ___ SI +___ MU)

RNO: Log beginning time for HPI pump flow below minimum 4.6 Initiate makeup to the LDST as required. (Using EOP Enclosure 5.5 or OP/1/A/1103/004 for batch additions) 4.7 Notify the OSM to reference OMP 1-14, Emergency Plan, and notify the STA 4.8 Verify 1HP-5 closed 4.9 Dispatch an operator to 1HP-5 to establish communication with the CR NOTE

• TS 3.4.9 applies when 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.

4.10 IAAT either of the following exist:

• PZR level > 260 inches 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) 4.11 IAAT PZR level 375 inches, THEN trip Rx 4.12 Determine the cause of loss of letdown:

Actual LD Temperature high: GO TO Step 4.29 This event is complete when the Standby HPI Pump is placed back in Auto, or as directed by the Lead Examiner.

Page 6 of 59

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

Description:

1A CC Pump Trips & Standby CC Pump Fails to Auto Start (C: BOP, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/032 Crew response:

4.29 Notify FIN24 to initiate repairs on failed equipment 4.30 IAAT letdown can be re-established, THEN perform Steps 4.30 - 4.44 4.31 Place CC System in operation 4.32 Close 1HP-6 BOP 4.33 Close 1HP-7 4.34 Open 1HP-1, 1HP-2, 1HP-3, and 1HP-4 4.35 Verify letdown temperature < 135°F RNO: 1. Open 1HP-13

2. Close 1HP-8, 1HP-9 & 11

3. Verify NO deborating IXs in service

4. Select LETDOWN HI TEMP INTLK BYP switch to BYPASS 4.36 Open 1HP-5 4.37 Throttle open 1HP-7 to establish 20 gpm 4.38 WHEN letdown temperature < 130°F, THEN place LETDOWN HI TEMP INTLK BYP switch in NORMAL 4.39 Open 1HP-6 4.40 Adjust 1HP-7 to control desired letdown flow 4.41 Re-establish normal makeup through 1HP-120 4.42 Re-establish normal RCP seal injection flow 4.43 Position the standby HPI pump switch to AUTO Examiner Note: This concludes the event. It is not required to put Purification IX in service at step 4.44 4.44 Verify any purification IX in service RNO: IF purification IX operation is desired, THEN initiate OP/1/A/1103/004 B to establish desired IX operation 4.45 EXIT this procedure Tech Spec 3.4.1 (RCS Pressure, Temperature, and Flow DNB Limits) requires RCS pressure to stay > 2125 psig when in MODE 1 Steady State. During Letdown flow perturbations in this event it is possible that RCS pressure goes below 2125 psig, If that occurs the SRO will enter TS 3.4.1 Condition A (One or more RCS DNB parameters not within limits) which has a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> completion time to restore parameter to within limits.

This event is complete when the Standby HPI Pump is placed back in Auto, or as directed by the Lead Examiner.

Page 7 of 59

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

Description:

1NI-5 Power Failure (I: BOP, SRO)

Time Position Applicants Actions or Behavior Plant response:

• 1SA-05/A-5 (1A RPS TROUBLE)

• 1SA-05/A-6 (1NI-5 PWR FAIL)

• 1SA-4/C-1 (QUADRANT POWER TILT) will alarm after couple minutes

• OAC alarm 1A RPS NI FLUX DEV

• OAC alarm 1NI-5 +15V POWER SUP

• OAC alarm 1NI-5 -15V POWER SUP

• OAC alarm NI FLUX #1 NI-5 MISMATCH 1SA-05/A-6 Crew response:

BOP The BOP will refer to Statalarm 1SA-5/A-6 (1NI-5 PWR FAIL)

ARG 1SA-05/A-6 (1NI-5 PWR FAIL) rev 19 3.1 IF all Wide Range AND Power Range Nuclear Instrument channels fail at power, AND the Reactor has NOT tripped, manually trip the Reactor 3.2 Refer to TS 3.3.1 3.3 IF the other three RPS channels are in service (NOT bypassed), bypass the channel per OP/1/A/1105/014 (Control Room Instrumentation Operation and Information) 3.4 Initiate Work Request for I&E to investigate cause and restore power BOP OP/1/A/1105/014 OP/1/A/1105/014 Encl 4.7 (Removal and Restoration of RPS Channels) rev 42 2.1 Verify one of the following:

2.1.1 A procedure requires RPS Channel to be placed in Trip or Bypass 2.1.2 Equipment failure requires RPS Channel to be placed in Trip or Bypass 2.2 Identify affected RPS Channel 1A (1A, 1B, 1C, 1D)

This event is complete when the 1A RPS Channel is placed in Manual Bypass, or as directed by the Lead Examiner.

Page 8 of 59

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

Description:

1NI-5 Power Failure (I: BOP, SRO)

Time Position Applicants Actions or Behavior OP/1/A/1105/014 Crew response:

OP/1/A/1105/014 Encl 4.7 (Removal and Restoration of RPS Channels)

NOTE: Placing RPS channel in Manual Bypass is preferred to minimize risk of Reactor trip.

3.1 IF affected RPS channel is NOT required per TS 3.3.1, perform one of the following:

3.1.1 IF Manual Bypass of affected RPS channel is desired, perform the following:

A. Obtain Key #314 B. Declare affected RPS Channel inoperable C. Place affected RPS Channel in MANUAL BYPASS keyswitch in BYP (Cab. 2, 4, 6, or 8)

Examiner Note: Statalarm 1SA-05/A-1 will actuate when the channel is placed in BYP 3.1.2 IF Manual Trip of affected RPS channel is desired, perform the following: (NOT desired to trip channel per the NOTE) 3.2 IF affected RPS channel is required per TS 3.3.1, perform the following:

(Channel is NOT required per TS 3.3.1) 3.3 IF RPS Channel removed from service due to equipment failure, perform the following:

• Initiate Work Request

• IF required per OMP 1-14 (Notifications), perform appropriate notifications Examiner Note: The SRO may announce TS 3.3.1 for tracking purposes.

This event is complete when the 1A RPS Channel is placed in Manual Bypass, or as directed by the Lead Examiner.

Page 9 of 59

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

Description:

1A HPI Pump Trips & 1B HPI Pump Fails to Auto Start (C: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior Plant response:

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

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

• RC Makeup Flow 0 gpm

• RCP SI flow 0 gpm

• 1A HPI Pump amps low = 0 amps

• PZR level will begin to decrease and LDST level will begin to increase Crew response:

SRO The SRO will enter AP/1/A/1700/014 (Loss of Normal HPI Makeup and/or RCP Seal Injection)

AP/1/A/1700/014 Crew response:

AP/1/A/1700/014 (Loss of Normal HPI Makeup and/or RCP Seal Inj) rev 18 SRO/OATC 3.1 IAAT RCP seal injection flow is lost, AND Component Cooling is lost, THEN perform the following:

A. Trip the Rx B. Stop all RCPs C. Initiate AP/25 (SSF EOP) 3.2 IAAT loss of suction to operating HPI pumps is indicated:

• Motor amps low or cycling

• Discharge pressure low or cycling

• Abnormal LDST level trend THEN GO TO Step 3.3 RNO: GO TO Step 4.7 4.7 Announce AP entry using PA System 4.8 Verify any HPI pump operating RNO: 1. Close 1HP-5

2. Place 1HP-120 in HAND and closed

3. Place 1HP-31 in HAND and closed

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

5. IF standby HPI pump started, THEN GO TO Step 4.111 This event is complete when Seal Inlet Header Flow is 32 gpm and 1HP-31 is in Auto (Step 4.124), or as directed by the Lead Examiner.

Page 10 of 59

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

Description:

1A HPI Pump Trips & 1B HPI Pump Fails to Auto Start (C: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/014 Crew response:

AP/1/A/1700/014 (Loss of Normal HPI Makeup and/or RCP Seal Inj) 4.111 Place 1HP-31 in HAND 4.112 Slowly open 1HP-31 until 8 gpm/RCP is achieved 4.113 Re-establish normal makeup through 1HP-120 4.114 Ensure proper operation of the Component Cooling System 4.115 Reduce 1HP-7 demand to 0%

4.116 Close 1HP-6 4.117 Open the following:

1HP-1 1HP-2 1HP-3 1HP-4 Booth Note: Crew may contact the WCC to direct AO to rack out the 1A HPIP breaker (wait 10 minutes and then Use Quick Strike to remove fuses and report that the 1A HPI pump has been tagged out).

4.118 Open 1HP-5 4.119 Throttle open 1HP-7 for 20 gpm letdown flow 4.120 Open 1HP-6 4.121 Adjust 1HP-7 for desired letdown flow 4.122 Open the following:1HP-228, 1HP-226,1HP-232, 1HP-230 4.123 Open 1HP-21 4.124 IAAT SEAL INLET HDR FLOW 32 gpm, THEN place 1HP-31 in AUTO 4.125 Monitor RCP seal parameters 4.126 Maintain RCP seal injection flows as required 4.127 Log thermal cycle of 1A HPI header 4.128 WHEN conditions permit, THEN EXIT this procedure Examiner Note: Crew may enter AP/16 (Abnormal RCP Operation) as a result of high seal return temperatures. Steps are on the next page.

This event is complete when Seal Inlet Header Flow is 32 gpm and 1HP-31 is in Auto (Step 4.124), or as directed by the Lead Examiner.

Page 11 of 59

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

Description:

1A HPI Pump Trips & 1B HPI Pump Fails to Auto Start (C: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/016 Crew response:

AP/1/A/1700/016 (Abnormal RCP Operation) rev 34 4.1 IAAT any RCP meets immediate trip criteria (does not)

RNO: GO TO Step 4.12 NOTE If affected RCP has a seal failure, and immediate trip criteria not met, then continue to Section 4A (Seal Failure) to ensure Seal Failure guidance steps are read. Section 4A (Seal Failure) contains steps to quickly secure affected RCP should the need arise.

4.12 IAAT either of the following apply:

__ Any RCP approaching immediate trip criteria of Encl 5.1

__ 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 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:

AP/16 (Abnormal RCP Operation) Section 4D

1. IAAT any RCP meets immediate trip criteria (does not)

RNO: GO TO Step 12

12. Monitor RCP parameters for abnormalities (Turn on Code RCP).

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

14. Open1HP-228, 1HP-226, 1HP-232, and 1HP-230

15. Verify either of the following conditions apply.. (not met)

RNO: GO TO Step 17 This event is complete when Seal Inlet Header Flow is 32 gpm and 1HP-31 is in Auto (Step 4.124), or as directed by the Lead Examiner.

Page 12 of 59

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

Description:

1A HPI Pump Trips & 1B HPI Pump Fails to Auto Start (C: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/016 Crew response:

AP/1/A/1700/016 (Abnormal RCP Operation) rev 34

17. Verify RCP seal return low flow alarms off RNO: Request that RCP Component Engineer provide the following:

• Immediate evaluation

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

Examiner Note: Due to sequence of events, SRO may not review the TS during the scenario. Follow-up questions may be required to ensure knowledge of this competency.

TS 3.5.2 HIGH PRESSURE INJECTION Condition A (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) Restore HPI pump to OPERABLE status This event is complete when Seal Inlet Header Flow is 32 gpm and 1HP-31 is in Auto (Step 4.124), or as directed by the Lead Examiner.

Page 13 of 59

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

Description:

Loop 1A RC Flow Fails Low (I: OATC, SRO)

Time Position Applicants Actions or Behavior Plant response:

• 1SA-02/A-3 (RC Loop A Flow Low)

• 1SA-02/A-5 (RC Total Flow Low)

• 1SA-02/A-11 (ICS Runback)

• 1SA-02/A-12 (ICS Tracking)

• 1SA-05/B-5 (1B RPS Trouble)

Crew response:

• When the Statalarms are received, the candidates should utilize the Plant Transient Response (PTR) process to stabilize the plant, which should include:

OATC/BOP o Placing ICS to HAND (Feedwater Masters and Diamond) o Inserting Control Rods as needed to control RCS pressure (Performed by the BOP) o Decreasing or re-ratio Feedwater to control Reactor power and delta Tcold (Performed by the OATC)

SRO may direct the OATC to perform the actions of the ARG for 1SA-02/A-3 Statalarm, but probably will move directly from PTR to AP/28.

ARG for 1SA-02/A-3 3.1. Ensure reactor power is reduced below the flux to flow minus imbalance trip ratio 3.2. Ensure Feedwater demand re-ratios properly Examiner Note: This failure will cause FDW flow to re-ratio. If the crew immediately recognizes it is an instrument failure and not an actual loss of flow, they may choose to adjust FDW and therefore prevent high delta Tc from being established causing high Quadrant Power Tilt values. The SRO should direct a band for delta Tc of 0 +/- 2°F as he establishes bands for parameters being manually controlled.

SRO directs performance of AP/1/A/1700/028, ICS Instrument Failures (see next page)

This event is complete when Step 5 of Section 4E is complete, or as directed by the Lead Examiner.

Page 14 of 59

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

Description:

Loop 1A RC Flow Fails Low (I: OATC, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/028 Crew response:

AP/1/A/1700/028 (ICS Instrument Failures) rev 20 4.1. Provide control bands as required 4.2. Initiate notification of the following:

• OSM to reference the following:

o OMP 1-14 (Notifications) o Emergency Plan

• STA 4.3. Verify a power transient 5% has occurred RNO: GO TO Step 4.5 Examiner Note: If power change was 5%, then step 4.4 will be performed. It depends on the speed of crew response to the failure.

4.4. Notify Rx Engineering and discuss the need for a maneuvering plan Booth Cue: We will develop 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 4B Turbine Header Pressure 4C Controlling NI 4D Feedwater Loop Flow 4E RCS Flow This event is complete when Step 5 of Section 4E is complete, or as directed by the Lead Examiner.

Page 15 of 59

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

Description:

Loop 1A RC Flow Fails Low (I: OATC, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/028 Plant response:

AP/1/A/1700/028 Section 4E (RCS Flow)

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 The RO will refer to Table 3 and determine that the surveillances can NOT be met as written with the failed instrument and therefore the SRO would ensure that a surveillance evaluation is initiated. (Surveillance is required in Mode 1, Steady State Operation. Steady State is defined as operation within a 4% (e.g. 88% - 92% RTP) power band for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)

5. Verify instrumentation surveillance in Encl 5.2 (ICS Instrument Surveillances) was performed satisfactorily as written Inform the SRO that the surveillance cannot be met as written Determine that a Surveillance Evaluation should be initiated Booth Cue: If crew requests Unit 2 to perform the surveillance evaluation, respond that "Unit 2 will perform the surveillance evaluation".

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: ICS will remain in Manual for the remainder of the scenario.

This event is complete when Step 5 of Section 4E is complete, or as directed by the Lead Examiner.

Page 16 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 1 Event No.: 6 Page 1 of 11 Event

Description:

80 GPM RCS Leak (Requires Manual Power Reduction) (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior Plant response:

• OAC RB Normal Sump Temp HI HI

• 1SA-9/A-6 (RB NORMAL SUMP HIGH/LOW)

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

• 1SA-8/E-9 (RM Reactor Building Normal Sump Isolate)

• PZR and LDST level deceasing

• RC makeup flow increasing

• RB normal sump level increasing Crew response:

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

TS 3.4.13 RCS OPERATIONAL LEAKAGE Condition A (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) Reduce leakage to within limits Condition B (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) Be in MODE 3 AND (36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />) Be in MODE 5 SRO

• The SRO will enter AP/1/A/1700/002 (Excessive RCS Leakage)

(next page)

This event is complete when Reactor power is decreased > 10% and either before or after auxiliaries have been transferred (NOT during), or as directed by the Lead Examiner.

Page 17 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 1 Event No.: 6 Page 2 of 11 Event

Description:

80 GPM RCS Leak (Requires Manual Power Reduction) (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/002 AP/1/A/1700/002 (Excessive RCS Leakage) rev 15 3.1 Verify HPI operating 3.2 IAAT RC makeup flow is > 100 gpm, AND Pzr level is decreasing, THEN close 1HP-5 3.3 IAAT all the following exist: (does not apply)

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

• Pzr level decreasing

• SG Tube Leakage NOT indicated

• LPI DHR NOT in service THEN perform the following:

A. Ensure Rx is tripped B. Initiate Unit 1 EOP 4.1 Initiate Pzr and LDST level makeup using Unit 1 EOP Encl 5.5, as necessary (page 47)

Booth Cue: If requested by the crew to close 1CS-48, wait two minutes and then use Manual Valves to close 1CS-48. Then call back to report that 1CS-48 is closed.

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

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

__ OSM to reference the following:

• RP/1000/001 (Emergency Classification)

• OMP 1-14 (Notifications)

• Encl 5.9 (Oversight Guidelines)

__ STA and RP This event is complete when Reactor power is decreased > 10% and either before or after auxiliaries have been transferred (NOT during), or as directed by the Lead Examiner.

Page 18 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 1 Event No.: 6 Page 3 of 11 Event

Description:

80 GPM RCS Leak (Requires Manual Power Reduction) (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/002 Crew response:

AP/1/A/1700/002 (Excessive RCS Leakage) 4.5 Monitor the following trends to determine leak area (AB or RB) and trend for degradation:

• T6 AP02

• T6 WASTE

• RIAs Examiner/Booth Note: AP/1/A/1700/018 entry conditions will also be met due to RB RIA alarms. If the crew asks, Unit 2 will perform AP/18 (Abnormal Release of Radioactivity) actions.

4.6 Verify specific leak location is identified RNO: Notify WCC SRO to initiate Encl 5.2 (Primary Leak Check) and of the leak area (AB or RB), if known Note: Crew should determine that the leak is in the Reactor Building due to RB RIAs increasing, RBNS rate increasing, and NO RCP seal failure indications.

4.7 Initiate Encl 5.1 (Leak Rate Determination)

(See page 24 for actions of Encl 5.1) 4.8 WHEN leak area/failure is identified, THEN GO TO applicable step that best fits leak area/failure Area/ Symptoms Step Failure Rx Bldg RB RIAs 4.53 RBNS rate NO RCP seal failure indications This event is complete when Reactor power is decreased > 10% and either before or after auxiliaries have been transferred (NOT during), or as directed by the Lead Examiner.

Page 19 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 1 Event No.: 6 Page 4 of 11 Event

Description:

80 GPM RCS Leak (Requires Manual Power Reduction) (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/002 Crew response:

4.53 IAAT in MODE 1 AND leak is > LDST makeup capability from 1A BHUT, THEN initiate a shutdown using AP/29 (Rapid Unit Shutdown)

(page 25)

Examiner Note: The 80 gpm leak will eventually be greater than LDST makeup capability from 1A BHUT so the SRO should initiate AP/29. (page 25) 4.54 IAAT leak rate is 10 gpm, THEN discontinue pumping RBNS 4.55 IAAT either of the following conditions exist:

• RCS pressure 50 psig and RCS leakage 10 gpm

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

RNO: GO TO Step 4.58

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

RNO: GO TO Step 4.60 4.60 Verify RB pressure 3 psig RNO: Maximize RB Cooling by performing the following:

• Ensure all available RBCUs operating in HIGH

• Open 1LPSW-18

• Open 1LPSW-21

• Open 1LPSW-24 This event is complete when Reactor power is decreased > 10% and either before or after auxiliaries have been transferred (NOT during), or as directed by the Lead Examiner.

Page 20 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 1 Event No.: 6 Page 5 of 11 Event

Description:

80 GPM RCS Leak (Requires Manual Power Reduction) (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/002 Crew response:

4.61 IAAT RB is accessible to locate the leak, THEN GO TO Step 4.62 RNO: GO TO Step 77 4.77 Verify 1HP-5 is closed RNO: GO TO Step 4.82 (next page) 4.78 Place standby CC pump switch in OFF NOTE Statalarm 1SA-9C-1 (CC COMP COOLING RETURN FLOW LOW) will alarm when the letdown coolers are isolated 4.79 Close the following:

__ 1CC-1/1HP-1

__ 1CC-2/1HP-2 4.80 Verify leak is isolated (it will not be)

RNO: 1. Perform the following to shutdown and depressurize the RCS A. Initiate shutdown by one of the following as necessary:

__ AP/29 (Rapid Unit Shutdown) (page 25)

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

B. Initiate OP/1/A/1102/010 (Controlling Procedure For Unit Shutdown) to continue shutdown and depressurization

2. WHEN conditions permit, THEN EXIT this procedure Booth Cue: If the crew elects to use the OP to shutdown the unit, call as the SM and inform the crew that a more rapid shutdown is desired.

This event is complete when Reactor power is decreased > 10% and either before or after auxiliaries have been transferred (NOT during), or as directed by the Lead Examiner.

Page 21 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 1 Event No.: 6 Page 6 of 11 Event

Description:

80 GPM RCS Leak (Requires Manual Power Reduction) (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/002 Crew response:

4.82 Isolate 1A Letdown Cooler by closing the following:

__ 1CC-1/1HP-1

__ 1HP-3 4.83 Verify leak is isolated RNO: 1. Restore 1A Letdown Cooler by performing the following:

A. Open 1HP-3 B. Open 1CC-1/1HP-1

2. GO TO Step 4.85 4.85 Isolate 1B Letdown Cooler by closing the following:

__ 1CC-2/1HP-2

__ 1HP-4 4.83 Verify leak is isolated RNO: 1. Restore 1B Letdown Cooler by performing the following:

A. Open 1HP-4 B. Open 1CC-2/1HP-2

2. GO TO Step 4.88 This event is complete when Reactor power is decreased > 10% and either before or after auxiliaries have been transferred (NOT during), or as directed by the Lead Examiner.

Page 22 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 1 Event No.: 6 Page 7 of 11 Event

Description:

80 GPM RCS Leak (Requires Manual Power Reduction) (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/002 Crew response:

NOTE

• It is desirable to isolate the LD line (to check for a leak), if the leak in the RB is so large that a RB entry (to locate leak) will not be made.

• The following steps to isolate letdown are performed at station management discretion dependent on the rate of leak. Isolating letdown will result in a complicated shutdown. Guidance is provided to restore letdown if leak is not isolated.

4.88 IAAT Station Management desires to isolate LD to determine if leak is downstream of 1HP-3 and 1HP-4, THEN GO TO Step 4.89 Booth Cue: If contacted as Station Management to determine if it is desired to isolate Letdown, state that It is not desired to isolate Letdown to determine if the leak is downstream of 1HP-3 and 1HP-4.

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

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

__ AP/29 (Rapid Unit Shutdown) (page 25)

__ OP/1/A/1102/004 (Operation At Power)

B. Initiate OP/1/A/1102/010 (Controlling Procedure For Unit Shutdown) to continue shutdown and depressurization

2. WHEN conditions permit, THEN EXIT this procedure Booth Cue: If the crew elects to use the OP to shutdown the unit, call as the SM and inform the crew that a more rapid shutdown is desired.

This event is complete when Reactor power is decreased > 10% and either before or after auxiliaries have been transferred (NOT during), or as directed by the Lead Examiner.

Page 23 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 1 Event No.: 6 Page 8 of 11 Event

Description:

80 GPM RCS Leak (Requires Manual Power Reduction) (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/002 Crew response:

AP/1/A/1700/002 Enclosure 5.1 (Leak Rate Determination)

1. Stabilize RCS Temperature

2. Notify WCC to secure all primary draining/RB washdown evolutions if applicable NOTE Depending on leak location, leakage may NOT be detected by all the formulas. One or more of the following methods may be necessary to determine RCS leak rate.

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

Examiner Note: There are several other methods to calculate leakage rate. While one of the two below will most likely be used, depending on plant conditions they may not be the only correct methods available.

Method #1: Calculation of RCS Volume Loss:

Leak Rate = ______ + ______ - ______ - ______ = ______

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

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

(minutes)

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

_____minutes

4. Notify SM and SRO of calculated leak rate This event is complete when Reactor power is decreased > 10% and either before or after auxiliaries have been transferred (NOT during), or as directed by the Lead Examiner.

Page 24 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 1 Event No.: 6 Page 9 of 11 Event

Description:

80 GPM RCS Leak (Requires Manual Power Reduction) (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/029 Crew response:

AP/1/A/1700/029 (Rapid Unit Shutdown) rev 13 4.1 Initiate Encl 5.1 (Support Actions During Rapid Unit Shutdown) (page 27) 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 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

__ GO TO appropriate operating procedure for continued operation to resume power reduction 4.8 Verify ICS in AUTO (ICS is NOT in Auto)

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.

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 This event is complete when Reactor power is decreased > 10% and either before or after auxiliaries have been transferred (NOT during), or as directed by the Lead Examiner.

Page 25 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 1 Event No.: 6 Page 10 of 11 Event

Description:

80 GPM RCS Leak (Requires Manual Power Reduction) (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/029 Crew response:

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 is decreased > 10% and either before or after auxiliaries have been transferred (NOT during), or as directed by the Lead Examiner.

Page 26 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 1 Event No.: 6 Page 11 of 11 Event

Description:

80 GPM RCS Leak (Requires Manual Power Reduction) (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/029 Crew response:

AP/1/A/1700/029 Enclosure 5.1

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 Reactor power is decreased > 10% and either before or after auxiliaries have been transferred (NOT during), or as directed by the Lead Examiner.

Page 27 of 59

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

Description:

Small Break LOCA (M: ALL)

Time Position Applicants Actions or Behavior Plant response:

• 1SA-2/D-3 (RC PRESS HI/LOW)

• RCS pressure and PZR level decreasing

• ES Channels 1-6 actuate

• RCS subcooling margin will indicate 0°F shortly after the Rx trips

• Reactor Building Emergency Sump level increasing Crew response:

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 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)

SRO will transfer from the Subsequent Actions Tab to the LOSCM tab (page 29) from the Parallel Actions Page (page 56) to direct crew activities Once the RCS saturates, one of the ROs will perform Rule 2 (page 33)

The RO not performing Rule 2 will begin performing Enclosure 5.1 due to ES actuation (page 38)

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

Page 28 of 59

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

Description:

Small Break LOCA (M: ALL)

Time Position Applicants Actions or Behavior LOSCM Tab Crew Response:

LOSCM tab rev 01

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)

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

Page 29 of 59

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

Description:

Small Break LOCA (M: ALL)

Time Position Applicants 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) (page 57)

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

Page 30 of 59

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

Description:

Small Break LOCA (M: ALL)

Time Position Applicants Actions or Behavior LOSCM Tab Crew response:

LOSCM tab (continued) 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 32)

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

Page 31 of 59

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

Description:

Small Break LOCA (M: ALL)

Time Position Applicants Actions or Behavior LOCA Cooldown Tab Crew Response:

LOCA Cooldown Tab rev 0

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 RNO: GO TO Step 43 43 Initiate Encl 5.36 (Equipment Alignment For Plant Shutdown)

44. IAAT all the following exist:

__ All SCMs > 0°F

__ RCS pressure > LPI shutoff head

__ Required HPI within normal makeup capability THEN GO TO Step 45 RNO: GO TO Step 48

45. Verify primary to secondary heat transfer exists This event is complete when the SRO transfers to the LOCA CD tab, or as directed by the Lead Examiner.

Page 32 of 59

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

Description:

Small Break LOCA (M: ALL)

Time Position Applicants Actions or Behavior Rule 2 Crew Response:

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 (within 2 minutes of LOSCM)

3. Notify CRS of RCP status

4. Verify Blackout exists RNO: GO TO Step 6

6. Open 1HP-24 & 25 CT-3 7. Start all available HPI Pumps (within 10 minutes of LOCA)

Examiner Note: The 1C HPI pump will fail to start on ES signal but will start manually.

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 33 of 59

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

Description:

Small Break LOCA (M: ALL)

Time Position Applicants Actions or Behavior Rule 2 Crew Response:

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

• 1B MD EFDWP

40. Verify any EFDW pump operating

41. Verify both SGs intact

42. Establish 300 gpm EFDW flow to each SG

43. Verify both MD EFDWPs operating

44. Place 1 TD EFDW PUMP in PULL TO LOCK

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 34 of 59

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

Description:

Small Break LOCA (M: ALL)

Time Position Applicants 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 36)

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 35 of 59

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

Description:

Small Break LOCA (M: ALL)

Time Position Applicants Actions or Behavior Rule 3 Crew Response:

Rule 3 (Loss of Main or Emergency Feedwater)

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

__ Turbine Building Flooding

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

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

AND any of the following exist:

• RCS pressure reaches 2300 psig or NDT limit

• PZR level reaches 375 (340 acc)

THEN PERFORM Rule 4 (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 0°F 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) (page 37)

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 36 of 59

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

Description:

Small Break LOCA (M: ALL)

Time Position Applicants 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. (page 29)

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

Page 37 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 38 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam EOP Enclosure 5.1 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 39 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam EOP Enclosure 5.1 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.

Page 40 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam EOP Enclosure 5.1 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 41 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam EOP Enclosure 5.1 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:

__ 1HP-228

__ 1HP-226

__ 1HP-232

__ 1HP-230

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 42 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam EOP Enclosure 5.1 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 43 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam EOP Enclosure 5.1 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 44 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam EOP Enclosure 5.1 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Unit Status ES Channels 3 & 4 have NOT actuated.

54. Start:

__ A OUTSIDE AIR BOOSTER FAN CT-2

__ 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:

__ 1HP-228

__ 1HP-226

__ 1HP-232

__ 1HP-230

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 45 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam EOP Enclosure 5.1 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 46 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 47 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 48 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 49 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 50 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 51 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 52 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 53 of 59

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

• *

• END * *

• Page 54 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Page 55 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 (Notification/Reportability Evaluation).

Page 56 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.16 SG Tube-to-Shell T Control NOTE

• SG tube-to-shell T is calculated by the OAC with points displayed on Loop P/T displays as indicated below:

1A SG T 1B SG T Bottom of Loop 'A' P/T display Bottom of Loop 'B' P/T display S/G TUBE/SHELL DT S/G TUBE/SHELL DT

• SG tube-to-shell T limits:

Stress OAC Indication Tensile Stress Limit

+130°F (Tubes colder than shell)

Compressive Stress

-70°F (Tubes hotter than shell)

1. IAAT any SG tube-to-shell T approaches either limit, THEN take appropriate action per the following:

Limit Action Approached Tensile GO TO Step 2 Compressive GO TO Step 50 Examiner Note: SG tube-to-shell T should not approach either limit for this scenario.

Page 57 of 59

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam CRITICAL TASKS CT-1 Secure all RCPs within two minutes of SCM 0°F per Rule 2 (BWOG CT-1)

CT-2 Start Outside Air Booster Fans within 30 minutes of initiation of LOCA (BWOG CT-27)

CT-3 Start 1C HPI Pump within 10 minutes of LOCA to provide flow in both headers to preclude quarter core cooling Page 58 of 59

SAFETY: Take a Minute UNIT 0 (OSM)

SSF Operable: No KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 2 Fuel Handling: No U2/U3: Yes UNIT STATUS (CR SRO)

Unit 1 Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 75% Mode: 1 Mode: 1 Gross MWE: 698 100% 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 Today/0300 7 Days SLC 16.7.2 SSF Today/0100 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

• SASS is in Manual for calibration Secondary

• AMSAC/DSS bypassed for calibration

• Unit 2 is supplying the AS header

• PT/0/A/0610/017 (Operability Test of 4160V Breakers) Encl 13.11 (Functional Verification Of SL Breaker(s) is in progress and complete up to Step 2.1 to perform functional verification of SL1 and SL2 breakers

• Keowee operability test was performed per PT/0/A/0620/009 (Keowee Hydro Operation) at 0700 today

• Unit 2 BOP will simulate performing CV during SL breaker testing

• 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 77% Withdrawn control.

Human Performance Emphasis (OSM)

Procedure Use and Adherence

Appendix D Scenario Outline Form ES D-1 ILT16-2 NRC Exam Facility: Oconee Scenario No.: 2 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________ SRO

________________________ ________________________ OATC

________________________ ________________________ BOP Initial Conditions:

• Reactor Power = 97%

Turnover:

• SASS is in Manual for calibration

• AMSAC/DSS is bypassed for calibration

• PT/1/A/0290/003 Encl 13.2 (Control Valve Movement At Power) in progress to test CV3 & CV4 Event Malfunction Event Event Type* Description No. No.

0a Override AMSAC/DSS Bypassed 0b Override SASS in Manual 1 N: BOP, SRO Turbine Control Valve Movement PT (CV3 & CV4) 2 Override C: BOP, SRO CCW Emergency Discharge Level Low 3 MPI121 I: BOP, SRO PZR Level 1 Fails Low 4 Override I: OATC, SRO (TS) Inadvertent ES Channel 3 Actuation 5 MPI281 I: OATC, SRO Tc Controller Failure One Dropped Control Rod (Group 1 Rod 6) Requiring 6 Override R: OATC, SRO (TS)

Manual Power Decrease MPI290 ATWS (Loss of 1TA Switchgear) 7 MPI300 M: ALL

• Turbine Fails to Trip MEL120

• 1HP-26 Fails Closed

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

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam SCENARIO 2 EVENT

SUMMARY

Event 1: When the crew takes the shift, the BOP will perform PT/1/A/0290/003 Enclosure 13.2 (Control Valve Movement At Power) to test Turbine Control Valves CV3 & CV4. Once the test is complete, the Turbine Bypass Valves (TBVs) will be closed, returned to automatic, and the Standby EHC pump will be secured and placed in automatic.

Event 2: An OAC alarm will indicate that CCW Emergency Discharge Level is low. This will require the BOP to re-prime the Condenser Emergency Discharge Line in accordance with OP/1/A/1104/012 Enclosure 4.4 (Repriming Condenser Emergency Discharge Line).

Event 3: Pressurizer Level 1 will fail low which will cause 1HP-120 (RCS Volume Control) to open in an attempt to restore indicated Pressurizer level. The BOP will select Pressurizer level 2 or Pressurizer level 3 to restore normal RCS makeup flow.

Event 4: Engineered Safeguards (ES) Channel 3 will inadvertently actuate which will cause the 1A LPI Pump to start, 1LP-17 to open, and C LPSW Pump to start. Once the crew determines that the ES actuation is not valid, the SRO will enter AP/1/A/1700/042 (Inadvertent ES Actuation) to restore the ES components to normal operation. The SRO will enter TS 3.3.7 and TS 3.7.7.

Event 5: The Tc Controller will fail causing 1A Feedwater flow to increase and 1B Feedwater flow to decrease. Once alarms are received, the crew will perform Plant Transient Response to stabilize the plant. Once the plant is stable, the SRO will enter AP/1/A/1700/028 (ICS Instrument Failures) and ensure the appropriate ICS stations are in manual.

Event 6: One Control Rod (Group 1 Rod 6) will fully insert. Once alarms are received, the crew will perform Plant Transient Response to stabilize the plant. The SRO will enter AP/1/A/1700/001 (Unit Runback). Since ICS is in manual (from event 5), the OATC will perform a manual power decrease to 55% power. The SRO will enter TS 3.1.4, TS 3.1.5, and TS 3.10.1.

Event 7: 1TA Switchgear will lockout and the Reactor will fail to trip automatically or manually (ATWS). The OATC will perform Rule 1 and the SRO will enter the UNPP tab of the EOP. The turbine will fail to trip using the Turbine Trip Pushbutton which will require the operator to lockout both EHC Pumps to prevent severe overcooling of the RCS.

1HP-26 will fail closed requiring 1HP-410 to be opened to allow full HPI flow from the BWST to borate the RCS and shutdown the Reactor.

Page 2 of 43

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

Description:

Turbine Control Valve Movement PT (N: BOP, SRO)

Time Position Applicants Actions or Behavior PT/1/A/0290/003 Crew response:

SRO directs the BOP to perform PT/1/A/0290/003 Encl 13.2 to test CV3 & CV4 PT/1/A/0290/003 Encl 13.2 (Control Valve Movement At Power) rev 15 2.5 IF AT ANY TIME reactor/turbine trip OR significant transient occurs, ensure Turbine Bypass Valves to AUTOMATIC NOTE: CV3 & CV4 testing is combined into single test with CV3 ramping closed and CV4 opening. When CV3 is fully tested, CV4 is disc dumped at < 6 % open to complete test.

2.6 IF CV3 and CV4 test required:

2.6.1 Select "Control Valve 3 & 4 Test" 2.6.2 Verify the following:

___ "Test Permissive" is ON for CV3

___ "Test Permissive" is ON for CV4 2.6.3 Record CV3 and CV4 pretest positions:

• CV3 pretest position:________ % Open

• CV4 pretest position: ________% Open 2.6.4 Select "Initiate CV3 and CV4 Test" 2.6.5 IF any of the following conditions occur, select "Abort CV3 &

CV4 Test" NI POWER changes > 2%

ICS Turbine Master trips to HAND Turbine vibration > 10 mils for > 5 seconds CAUTION: If CV3 remains in the closed position with the Test Failed indication "ON", initiating Abort Test could result in a reactivity management event.

2.6.6 IF "Test Failed" is "ON" AND CV3 is NOT fully closed, select "Abort CV3 & CV4 Test" This event is complete when the Standby EHC pump switch is placed in AUTO (step 2.9.5), or as directed by the Lead Examiner.

Page 3 of 43

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

Description:

Turbine Control Valve Movement PT (N: BOP, SRO)

Time Position Applicants Actions or Behavior PT/1/A/0290/003 Crew response:

PT/1/A/0290/003 Encl 13.2 (Control Valve Movement At Power)

NOTE: If a Control Valve remains closed after it has disc-dump, it may start going open at any time (i.e. 1 min, 5 min, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />,...). When the Control Valve starts going back open it will open at its normal rate. No transients are expected during this scenario since the EHC Control System will simply continue with the test logic and return the Control Valve to its normal position at the normal controlled test rate.

2.6.7 IF "Test Failed" is "ON" AND CV3 remained closed perform the following:

A. Do NOT select "Abort CV3 & CV4 Test" B. Notify WCC & Engineering that the (FASV) for the Control Valve under test is stuck in the energized state NOTE: Control Valves which are not in their normal position could result in asymmetrical loading on the Turbine bearings.

C. Monitor Turbine Vibrations closely if in this abnormal state 2.6.8 Perform EITHER for CV3:

A. Verify "Test Successful" indicated for CV3 B. IF "Test Successful" NOT indicated for CV3, verify CV3 moved towards closed position 2.6.9 Perform EITHER for CV4:

A. Verify "Test Successful" indicated for CV4 B. IF "Test Successful" NOT indicated for CV4, verify CV4 moved towards closed position This event is complete when the Standby EHC pump switch is placed in AUTO (step 2.9.5), or as directed by the Lead Examiner.

Page 4 of 43

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

Description:

Turbine Control Valve Movement PT (N: BOP, SRO)

Time Position Applicants Actions or Behavior PT/1/A/0290/003 Crew response:

PT/1/A/0290/003 Encl 13.2 (Control Valve Movement At Power)

NOTE:

• CV3 and CV4 test indicator resets after 20 seconds

• Test indicators reset is when "Test Permissive" is ON and all other Test Indicators are OFF 2.6.10 Verify CV3 test indicator reset 2.6.11 Verify CV4 test indicator reset 2.6.12 Verify CV3 within +/- 5.0% of pretest position 2.6.13 Verify CV4 within +/- 5.0% of pretest position 2.6.14 Perform the following:

Verify acceptance criteria met IF acceptance criteria NOT met, notify SRO Examiner Note: Steps 2.7 and 2.8 are not applicable.

2.9 Perform the following:

2.9.1 Ensure all Turbine Bypass Valves CLOSED 2.9.2 Verify CV-4 returns to its expected pre-test position (Reference step 2.4.1 or Encl 13.1 step 2.3.1)

Examiner Note: CV-4 should return to 4% open.

2.9.3 Ensure the following:

• 1A Turbine Bypass Valve AUTO

• 1B Turbine Bypass Valve AUTO 2.9.4 Stop Standby EHC pump 2.9.5 Place Standby EHC pump control switch to "AUTO" 2.9.6 IF required, make the following plant page announcement:

"Personnel can re-enter the Unit 1 Turbine Building" This event is complete when the Standby EHC pump switch is placed in AUTO (step 2.9.5), or as directed by the Lead Examiner.

Page 5 of 43

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

Description:

CCW Emergency Discharge Level Low (C: BOP, SRO)

Time Position Applicants Actions or Behavior Plant response:

• OAC alarm CCW EMER DISCHARGE LEVEL LOW Crew response:

The BOP will refer to OAC alarm response OAC Alarm OAC alarm CCW EMER DISCHARGE LEVEL LOW BOP 1. Reprime ECCW per OP/1/A/1104/012 (CCW System)

Booth Cue: If contacted as Unit 2 and/or Unit 3 about OAC alarm for CCW EMER DISCHARGE LEVEL LOW, state that the alarm indicates LOW.

OP/1/A/1104/012 Encl 4.4 OP/1/A/1104/012 (CCW System) Encl 4.4 (Repriming Condenser Emergency Discharge Line) rev 82 BOP Initial Conditions 1.1 Verify CCW System in service 1.2 Review Limits and Precautions Procedure 2.1 Ensure closed CCW-8 (EMERGENCY CCW DISCHARGE TO TAILRACE) 2.2 Open 1DP-F5C (CCW-8 Bkr (Emerg CCW Disch To Tailrace))

2.3 Open 1CCW 1-6 (WATERBOX EMERG DISCH) 2.4 Throttle open CCW-9 (EMERGENCY CCW DISCHARGE TO INTAKE CANAL) to provide vent path This event is complete when Step 2.6 is complete (CCW-8 Breaker is closed), or as directed by the Lead Examiner.

Page 6 of 43

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

Description:

CCW Emergency Discharge Level Low (C: BOP, SRO)

Time Position Applicants Actions or Behavior OP/1/A/1104/012 Crew response:

OP/1/A/1104/012 (CCW System) Encl 4.4 (Repriming Condenser BOP Emergency Discharge Line)

NOTE: Any units' O*D2673 point is acceptable to verify ECCW discharge piping full.

2.5 WHEN OAC indicates line is primed OR after 30 minutes:

2.5.1 Close CCW-9 (EMERGENCY CCW DISCHARGE TO INTAKE CANAL) 2.5.2 Close 1CCW 1-6 (WATERBOX EMERG DISCH) 2.5.3 IF OAC available, verify by OAC indication the following valves are closed:

• 1CCW-1 (CCW 1A1 Emer Disch) (CP O1D0299)

• 1CCW-2 (CCW 1A2 Emer Disch) (CP O1D0301)

• 1CCW-3 (CCW 1B1 Emer Disch) (CP O1D0303)

• 1CCW-4 (CCW 1B2 Emer Disch) (CP O1D0305)

• 1CCW-5 (CCW 1C1 Emer Disch) (CP O1D0307)

• 1CCW-6 (CCW 1C2 Emer Disch) (CP O1D0309) 2.5.4 IF OAC NOT available, verify locally the following valves are closed: (T-3, catwalk) (N/A) 2.6 Close 1DP-F5C (CCW-8 Bkr (Emerg CCW Disch To Tailrace))

This event is complete when Step 2.6 is complete (CCW-8 Breaker is closed), or as directed by the Lead Examiner.

Page 7 of 43

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

Description:

PZR Level 1 Fails Low (I: BOP, SRO)

Time Position Applicants Actions or Behavior Plant response:

• 1SA-02/C-3 (RC Pressurizer Level High/Low)

• 1SA-02/C-4 (RC Pressurizer Level Emerg High/Low)

• PZR level 1 indicates 0 inches

• 1HP-120 (RC Volume Control) throttles open

• Makeup flow increases ARG 1SA-02/C-3 Crew response:

The BOP will refer to Statalarm 1SA-02/C-3 and/or 1SA-02/C-4 BOP ARG 1SA-02/C-3 (RC Pressurizer Level High/Low) rev 33 3.1 Check alternate PZR level indications 3.2 Check for proper Makeup/Letdown flows and adjust to restore proper level 3.3 Refer to the following procedures as required:

• AP/1/A/1700/002 (Excessive RCS Leakage)

• AP/1/A/1700/014 (Loss of Normal HPI Makeup and/or RCP Seal Injection)

• AP/1/A/1700/032 (Loss of Letdown) 3.4 Refer to Technical Specification 3.4.9 3.5 Refer to Technical Specification 3.3.8 3.6 Refer to OP/1/A/1105/014 (Control Room Instrumentation Operation And Information)

ARG 1SA-02/C-4 BOP ARG 1SA-02/C-4 (RC Pressurizer Level Emerg High/Low) rev 33 3.1 Check alternate PZR level indications 3.2 Check for proper makeup/letdown flows and adjust to restore proper level 3.3 Refer to AP/1/A/1700/002 (Excessive RCS Leakage) and/or AP/1/A/1700/014 (Loss of Normal HPI Makeup and/or RCP Seal Injection) for additional instructions 3.4 IF PZR level decreases to less than 80", verify PZR heaters have deenergized, IF NOT, do so manually This event is complete when PZR level 2 or PZR level 3 is selected, or as directed by the Lead Examiner.

Page 8 of 43

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

Description:

PZR Level 1 Fails Low (I: BOP, SRO)

Time Position Applicants Actions or Behavior OP/1/A/1105/014 Crew response:

Examiner Note: The SRO may direct the BOP to select Pressurizer level 2 or level 3 (located on 1UB1) prior to referencing OP/1/A/1105/014 (Control Room Instrumentation Operation And Information).

Examiner Note: The SRO may direct the BOP to take manual control of 1HP-120 to control pressurizer level prior to referencing OP/1/A/1105/014 (Control Room Instrumentation Operation And Information).

OP/1/A/1105/014 Encl 4.11 (SASS Information) rev 42 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) 3.2.3 Initiate a Work Request to repair faulty signal This event is complete when PZR level 2 or PZR level 3 is selected, or as directed by the Lead Examiner.

Page 9 of 43

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

Description:

Inadvertent ES Channel 3 Actuation (I: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior Plant response:

• 1SA-01/C-10 (ES 3 TRIP)

• 1A LPI Pump starts

• 1LP-17 (1A LPI INJECTION) opens

• C LPSW Pump starts Crew response:

• The crew will determine that the ES actuation is not valid

• The SRO may direct the BOP to refer to ARG 1SA-01/C-10 (ES 3 TRIP)

• The SRO will enter AP/42 (Inadvertent ES Actuation) (page 11)

ARG 1SA-01/C-10 ARG 1SA-01/C-10 (ES 3 TRIP) rev 14 BOP 3.1 Determine if ES condition exists (RCS pressure 550 psig OR RB pressure 3.0 psig) 3.2 IF RCS pressure is 550 psig OR RB pressure is 3.0 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)

This event is complete when the SRO reaches Step 4.26, or as directed by the Lead Examiner.

Page 10 of 43

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

Description:

Inadvertent ES Channel 3 Actuation (I: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/042 Crew response:

AP/1/A/1700/042 (Inadvertent ES Actuation) rev 04 4.1 Verify any of the following have inadvertently actuated: (N/A)

__ Diverse HPI

__ ES Channel 1

__ ES Channel 2 RNO: GO TO Step 4.4 4.4 Verify any of the following have inadvertently actuated: (N/A)

__ 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). (N/A)

2. GO TO Step 4.10 4.10 Close the following:

__ 1HP-24 (already closed)

__ 1HP-25 (already closed)

NOTE If personnel are available, 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 13) 4.12 Verify any of the following have inadvertently actuated:

__ Diverse LPI (not actuated)

__ ES Channel 3

__ ES Channel 4 (not actuated) 4.13 Verify Diverse LPI has inadvertently actuated (N/A)

RNO: GO TO Step 4.15 OATC 4.15 Perform the following on all inadvertently actuated system(s):

__ Ensure ES CH-3 is in MANUAL

__ Ensure ES CH-4 is in MANUAL (N/A)

This event is complete when the SRO reaches Step 4.26, or as directed by the Lead Examiner.

Page 11 of 43

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

Description:

Inadvertent ES Channel 3 Actuation (I: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/042 Crew response:

AP/1/A/1700/042 (Inadvertent ES Actuation) 4.16 Verify LPI was aligned in decay heat removal mode prior to ES actuation OATC RNO: 1. Stop the following:

__ 1A LPI PUMP

__ 1B LPI PUMP (not operating)

2. Simultaneously close the following:

__ 1LP-17

__ 1LP-18 (already closed) 4.17 Verify the Rx is critical 4.18 Verify ICS in Auto 4.19 Verify control rods are outside the desired control band RNO: GO TO Step 4.21 4.21 Verify any of the following have inadvertently actuated:

__ ES Channel 1 (not actuated)

__ Diverse HPI (not actuated)

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) 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 the SRO reaches Step 4.26, or as directed by the Lead Examiner.

Page 12 of 43

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

Description:

Inadvertent ES Channel 3 Actuation (I: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/042 Encl 5.1 Crew response:

BOP AP/1/A/1700/042 Enclosure 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:

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 Examiner Note: The SRO may elect to NOT stop the RB RIA sample pump to prevent inadvertently entering TS 3.4.15 since ES Channel 3 actuation does not isolated the RB RIAs.

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 the SRO reaches Step 4.26, or as directed by the Lead Examiner.

Page 13 of 43

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

Description:

Inadvertent ES Channel 3 Actuation (I: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior Tech Specs Crew response:

SRO TS 3.3.7 ESPS AUTOMATIC ACTUATION OUTPUT LOGIC CHANNELS Condition A (1hour) Place associated component(s) in ES configuration OR (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) Declare the associated component(s) inoperable TS 3.7.7 LOW PRESSURE SERVICE WATER SYSTEM (LPSW)

Condition B (7 days) Restore the LPSW WPS to OPERABLE status If the RIA sample pump is turned off per AP/42 Encl 5.1 step 9, TS 3.4.15 Condition B will be entered while the sample pump is off.

TS 3.4.15 RCS LEAKAGE DETECTION INSTRUMENTATION Condition B (Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) Analyze grab samples of the containment atmosphere OR (Once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) Perform SR 3.4.13.1 AND Restore required containment atmosphere radioactivity monitor to OPERABLE status This event is complete when the SRO reaches Step 4.26, or as directed by the Lead Examiner.

Page 14 of 43

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

Description:

Tc Controller Failure (I: OATC, SRO)

Time Position Applicants Actions or Behavior Plant response:

• FDW flow will ratio incorrectly based on the failure

• A FDW flow will decrease causing A loop TC to increase

• B FDW flow will increase causing B loop TC to decrease

• This will cause actual TC to increase (become more positive). Failure to correctly adjust FDW flow will result in QPT alarms.

• 1SA-02/B-5 (RC Cold Leg Diff. Temperature High) will actuate if actual TC increases to +/- 5°F

• 1SA-02/C-9 (MS STM GEN B LEVEL High/Low) will actuate if 1B SG Operating Range Level reaches 86%

Crew response:

When the Statalarms are received, the crew should perform Plant Transient Response (PTR) to stabilize the plant

• Diagnose the TC failure by observing the TC meter on 1UB1

• The OATC will place the Diamond and Feedwater Masters to MANUAL and re-ratio feedwater using the Loop TC meters and/or OAC (RCS01) to return actual TC to near zero OATC The 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 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 SRO should:

• Refer to AP/28 (ICS Instrument Failures) (page 16)

• Ensure FIN-24 (SPOC) is contacted to repair the failed instrument This event is complete when the SRO reaches Step 4 of AP/28 Section 4F, or as directed by the Lead Examiner.

Page 15 of 43

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

Description:

Tc Controller Failure (I: OATC, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/028 Crew response:

AP/1/A/1700/028 (ICS Instrument Failures) rev 20 4.1 Provide control bands as required (OMP 1-18 Attachment I)

OATC/SRO 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)

• Emergency Plan

__ STA 4.3 Verify a power transient 5% has occurred RNO: GO TO Step 4.5 4.4 Notify Rx Engineering and discuss the need for a maneuvering plan 4.5 Use the following, as necessary, to determine the applicable section from table in Step 4.6:

• OAC alarm video

• OAC display points

• Control Board indications

• SPOC assistance, as needed This event is complete when the SRO reaches Step 4 of AP/28 Section 4F, or as directed by the Lead Examiner.

Page 16 of 43

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

Description:

Tc Controller Failure (I: OATC, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/028 Crew response:

AP/1/A/1700/028 (ICS Instrument Failures)

OATC/SRO 4.6 GO TO the applicable section per the following table:

Section Failure 4F Delta Tc AP/1/A/1700/028 Section 4F (Delta Tc Failure)

NOTE

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

• Delta Tc controller may re-ratio loop feedwater flows

• Possible ICS RUNBACK

1. Ensure the following in HAND:

__ 1A FDW MASTER

__ 1B FDW MASTER

__ DELTA Tc CAUTION Total feedwater flow should be maintained constant while individual loop flows are adjusted to establish the desired Tc. Maintaining total FDW flow constant will prevent unwanted changes in reactor power.

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

3. Notify SPOC to perform the following:

__ Investigate and repair the failed Delta Tc controller

4. WHEN notified by SPOC that Delta Tc controller has been repaired, THEN GO TO OP/1/A/1102/004 A Encl (Placing ICS Stations To Auto)

This event is complete when the SRO reaches Step 4 of AP/28 Section 4F, or as directed by the Lead Examiner.

Page 17 of 43

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

Description:

One Dropped Control Rod (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior Plant Response:

• Group 1 Rod 6 drops into the core

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

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

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

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

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

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

Crew Response:

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

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

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

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

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

AP/1/A/1700/001 AP/1/A/1700/001 (Unit Runback) rev 15 4.1 GO TO the most limiting section per the following table:

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

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

Page 18 of 43

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

Description:

One Dropped Control Rod (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/001 Section 4H Crew response:

AP/1/A/1700/001 Section 4H (Asymmetric Control Rod)

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

2. IAAT more than one control rod is dropped or misaligned 6.5% (9) from the group average, THEN trip the Rx NOTE NIs should NOT be calibrated per guidelines contained in OP/1/A/1102/004 (Operation at Power) due to actual power re-distribution within the core as a result of a dropped/misaligned rod.

3. Verify Rx is critical

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

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

• CTPD set at 55%

• ASYMETRIC RODS Runback Light lit

• CTP Demand decreasing

• Reactor power will decrease when the runback catches up with the initial power decrease from the dropped rod RNO: 1. Initiate power reduction to 55% core thermal power at 1%/min

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

A. Trip reactor B. GO TO Unit 1 EOP

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

(page 23)

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

7. Notify SPOC to perform the following:

__ Investigate cause of dropped or misaligned control rod.

__ Prepare to reduce the following trip setpoints:

• RPS Flux/Flow-Imbalance

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

Page 19 of 43

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

Description:

One Dropped Control Rod (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/001 Section 4H Crew response:

AP/1/A/1700/001 Section 4H (Asymmetric Control Rod)

8. Notify the OSM to ensure the requirements of the following Tech Specs are met: (page 22)

__ TS 3.1.4 (Control Rod Group Alignment Limits)

__ TS 3.1.5 (Safety Rod Position Limits)

__ TS 3.2.3 (Quadrant Power Tilt)

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

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

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

Examiner Note: Shutdown Margin will be adequate

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

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

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

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

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

Page 20 of 43

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 2 Event No.: 6 Page 4 of 7 Event

Description:

One Dropped Control Rod (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/001 Section 4H Crew response:

AP/1/A/1700/001 Section 4H (Asymmetric Control Rod)

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

NOTE Due to the power decrease initiated in this AP, the current plant configuration must be compared to the normal plant configuration in OP/1/A/1102/004 (Operation at Power) power reduction enclosure. Equivalent steps performed by this AP should be signed off as intent met. Any steps NOT performed by this AP must be evaluated in preparation for power increase or continued shutdown.

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

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

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

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

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

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

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

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

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

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

Page 21 of 43

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

Description:

One Dropped Control Rod (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/001 Crew response:

SRO TS 3.1.4 CONTROL ROD GROUP ALIGNMENT LIMITS Condition A (1hour) Restore control rod alignment or verify SDM (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) Reduce Thermal Power to 60% of allowable Thermal Power.

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

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

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

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

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

TS 3.10.1 STANDBY SHUTDOWN FACILITY (SSF)

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

Examiner Note: SDM will be verified using PT/1/A/1103/015, Encl 13.18 (Page 25) and Curve for Control Rod Position Setpoints, 1 Inoperable Rod, 4 Pump Flow, BOC to EOC from the COLR (Page 26).

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

Page 22 of 43

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

Description:

One Dropped Control Rod (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/001 Enclosure 5.1 Crew response:

AP/1/A/1700/001 Enclosure 5.1 (Control of Plant Equipment During Runback)

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

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

3. Start the following pumps:

__ 1A FDWP SEAL INJECTION PUMP

__ 1A FDWP AUXILIARY OIL PUMP

__ 1B FDWP AUXILIARY OIL PUMP

__ 1B FDWP SEAL INJECTION PUMP

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

__ 1E1 HTR DRN PUMP

__ 1E2 HTR DRN PUMP

5. WHEN CTP 65%, THEN continue this Enclosure

6. Place the following in MANUAL and close:

__ 1FDW-53

__ 1FDW-65 NOTE 1B FDWP is the preferred pump to shut down first.

7. Verify both Main FDWPs operating

8. Verify 1B FDWP to be shut down first

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

10. GO TO Step 12 This event is complete when Rx Power has decreased to < 55%, or as directed by the Lead Examiner.

Page 23 of 43

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

Description:

One Dropped Control Rod (R: OATC, SRO) (TS)

Time Position Applicants Actions or Behavior AP/1/A/1700/001 Enclosure 5.1 Crew response:

AP/1/A/1700/001 Enclosure 5.1 (Control of Plant Equipment During Runback)

12. 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 occur:

• 1SA-16/A-3 (FWP B FLOW MINIMUM)

• 1SA-16/A-4 (FWP B FLOW BELOW MIN)

THEN trip 1B Main FDW Pump

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

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

__ Any of the following alarms occur:

• 1SA-16/A-1 (FWP A FLOW MINIMUM)

• 1SA-16/A-2 (FWP A FLOW BELOW MIN)

THEN trip 1A Main FDW Pump

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

• 1FDW-53

• 1FDW-65

15. Maintain Pzr level between 220 - 250

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

17. Stop the following:

__ 1A MSRH DRN PUMP

__ 1B MSRH DRN PUMP

18. Place the following in DUMP:

__ 1HD-37

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

Page 24 of 43

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 13.18 rev 75 PT/1/A/1103/015 Shutdown margin Calculation at Power Page 1 of 1 Performed By: __________Date: ________ Time: __________

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

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

____ 2.1 IF any rod groups are NOT at 100% wd (other than Group 7 and the APSRs) due to CRD movement PT:

____ 2.1.1 Verify that only one group is NOT at 100% wd.

____ 2.1.2 Verify that the inserted group is 95% wd.

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

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

____ 2.2 Verify one of the following:

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

OR

____ ____ 2.2.2 Appropriate actions are taken per TS 3.1.4, 3.1.5, and 3.2.1.

IV Page 25 of 43

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Page 26 of 43

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

Description:

ATWS (Loss of 1TA Switchgear) (M: ALL)

Time Position Applicants Actions or Behavior Plant Response:

• Statalarms 1SA-01/A-1, B-1, C-1, D-1 (RPS Channel A-D Trip)

• 1SA-1/A-7, B-7, C-7, D-7 (RCP/Flux Trip) 1TA lockout will occur. This will cause a loss of 6900V power to the 1A1 and 1B1 RCPs. RPS alarms will occur indicating that the Reactor should have tripped, but it will remain at power. The crew will attempt to manually trip the Reactor but it will not trip from the control room.

Crew Response:

OATC Recognize the Reactor should have tripped and attempt to manually trip the Reactor in accordance with OMP 1-18 Attachment A (< 3 RCPs operating with Reactor power > 2%). Since the Reactor will not trip from the control room, the OATC will initiate Rule 1 while performing Immediate Manual Actions (IMAs) of the EOP.

IMMEDIATE MANUAL ACTIONS OATC 3.1 Depress REACTOR TRIP pushbutton [Reactor will NOT trip]

3.2 Verify reactor power < 5% FP and decreasing RNO: GO TO Rule 1 (ATWS/Unanticipated Nuclear Power Production)

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 inform the SRO:

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

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

Page 27 of 43

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

Description:

ATWS (Loss of 1TA Switchgear) (M: ALL)

Time Position Applicants Actions or Behavior UNPP Tab Crew response:

Examiner Note: Rule 1 will direct the OATC to notify the CRS to go to the UNPP tab UNPP Tab rev 0 BOP/SRO 1. Ensure Rule 1 (ATWS/Unanticipated Nuclear Power Production) is in progress or complete (page 32)

2. Verify Main FDW is operating and in AUTO RNO: IF Main FDW is operating in MANUAL, THEN adjust Main FDW flow, as necessary to control RCS temperature

3. IAAT Main FDW is NOT operating, THEN:

A. Trip the turbine-generator B. Start all available EFDW pumps C. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete

4. IAAT all power range NIs are < 5% FP, THEN perform Steps 5 - 6 RNO: GO TO Step 7

5. Depress turbine TRIP pushbutton [the turbine will NOT trip from P/B]

6. Verify all turbine stop valves closed CT-1 RNO: Place both EHC pumps in PULL TO LOCK

7. Verify any wide range NI > 1% FP

8. Open 1RC-4

9. Verify 1HP-5 open

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

< 120°F This event is complete when the crew transfers to Subsequent Actions, or as directed by the Lead Examiner.

Page 28 of 43

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

Description:

ATWS (Loss of 1TA Switchgear) (M: ALL)

Time Position Applicants Actions or Behavior UNPP Tab Crew response:

UNPP Tab

11. Verify Main FDW available

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

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

RNO: GO TO Step 16

16. Secure makeup to LDST

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

18. Control RCS temperature as follows:

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

• TBVs

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

__ Tave > 555°F

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

19. Throttle HPI per Rule 6 (HPI) (page 41)

20. WHEN RCS pressure < 2300 psig, THEN continue

21. Verify PORV closed

22. Adjust letdown flow as desired

23. Verify RCP seal injection available

24. GO TO Subsequent Actions (page 30)

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

Page 29 of 43

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 2 Event No.: 7 Page 4 of 6 Event

Description:

ATWS (Loss of 1TA Switchgear) (M: ALL)

Time Position Applicants Actions or Behavior SUBSEQUENT ACTIONS Tab Crew response:

Subsequent Actions Tab rev 01 4.1 Verify all control rods in Groups 1 - 7 fully inserted 4.2 Verify Main FDW in operation 4.3 Verify either:

__ Main FDW overfeeding causing excessive temperature decrease

__ Main FDW underfeeding causing SG level decrease below setpoint RNO: GO TO Step 4.5 4.5 IAAT Main FDW is operating, AND level in any SG is > 96% on the Operating Range, THEN perform Steps 4.6 - 4.8 RNO: GO TO Step 4.9 4.9 IAAT TBVs CANNOT control SG pressure at desired setpoint, AND TBVs NOT intentionally isolated, THEN manually control pressure in affected SGs using either:

__ TBVs

__ Dispatch two operators to perform Encl 5.24 (Operation of the ADVs) 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 33)

2. GO TO Step 4.17 4.17 Open:

__ PCB 20

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

Page 30 of 43

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

Description:

ATWS (Loss of 1TA Switchgear) (M: ALL)

Time Position Applicants Actions or Behavior SUBSEQUENT ACTIONS Tab Crew response:

Subsequent Actions Tab 4.18 Verify Generator Field Breaker open 4.19 Verify EXCITATION is OFF 4.20 Verify Aux Bldg and Turbine Bldg Instrument Air pressure 90 psig 4.21 Verify ICS/NNI power available 4.22 Verify all 4160V switchgear (1TC, 1TD & 1TE) energized 4.23 Verify both SGs > 550 psig 4.24 Verify Main FDW operating 4.25 Verify any RCP operating 4.26 Verify AP/0/A/1700/025 (SSF EOP) Encl (Unit 1 OATC Actions During Fire) in progress or complete RNO: Ensure SGs approaching 25 - 35 [55 - 65 acc] S/U level 4.27 Place switches in CLOSE:

__ 1FDW-31

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

Page 31 of 43

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

Description:

ATWS (Loss of 1TA Switchgear) (M: ALL)

Time Position Applicants Actions or Behavior RULE 1 Crew response:

Rule 1 OATC 1. Verify any Power Range NI 5% FP

2. Initiate manual control rod insertion to the IN LIMIT

3. Verify Main FDW is feeding the SGs

4. Notify CRS to GO TO UNPP tab (Page 28)

5. Open:

__ 1HP-24

__ 1HP-25

6. Ensure at least one operating:

__ 1A HPI PUMP

__ 1B HPI PUMP

7. Start 1C HPI PUMP

8. Open:

__ 1HP-26 [1HP-26 will NOT open]

__ 1HP-27 RNO: 1. IF 1HP-26 will NOT open, THEN open 1HP-410

2. IF at least two HPI pumps are operating, AND 1HP-27 will NOT open THEN:

A. Start the standby HPI pump B. Stop 1C HPI pump C. Open 1HP-409 CT-2 9. Dispatch one operator without wearing Arc Flash PPE to open 600V CRD breakers:

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

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

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

10. Verify only two HPI pumps operating

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

Page 32 of 43

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 33 of 43

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 34 of 43

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 35 of 43

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 36 of 43

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 37 of 43

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 38 of 43

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 39 of 43

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

• *

• END * *

• Page 40 of 43

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Page 41 of 43

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam CRITICAL TASKS CT-1 Lockout EHC Pumps to trip the Main Turbine prior to entry into PTS conditions (cooldown to < 400°F at > 100°F/hour)

CT-2 Prior to exiting the UNPP tab, take the Reactor subcritical (i.e. < 1% power on WR NIs)

Page 42 of 43

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: 97% Mode: 1 Mode: 1 Gross MWE: 821 100% 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 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

• SASS is in Manual for calibration

• Rx power 97% stable and ready to perform PT/1/A/0290/003 (Turbine Valve Movement) Encl 13.2 for CV3 & CV4 only.

• PT/1/A/0290/003 Encl 13.2 (Control Valve Movement At Power) is in progress and complete up to Step 2.5 to test CV3 & CV4

• Unit 1 will be maintaining 97% until Rx Engineering updates the maneuvering plan 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 89% Withdrawn control.

Human Performance Emphasis (OSM)

Procedure Use and Adherence

Appendix D Scenario Outline Form ES D-1 ILT16-2 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

• OP/1/A/1106/002B Encl 4.13 in progress to restore 1B Main FDW Pump from Handjack Event Malfunction Event Event Type* Description No. No.

0a Override AMSAC/DSS Bypassed 0b Override SASS in Manual 1 N: BOP, SRO Restore 1B Main FDW Pump From Handjack 2 MPS090 C: OATC, SRO 1HP-120 Fails Closed 3 Override C: BOP, SRO 1D1 HDP Low Oil Level (Auto Power Decrease) 4 MCS004 I: OATC, SRO Controlling NR Tave Fails High 5 Override C: BOP, SRO (TS) 1A2 RCP High Oil Level 6 R: OATC, SRO Manual Power Decrease MEL170 7 Override SRO (TS) CT-1 Lockout MEL090 `Switchyard Isolate 8 MEL180 M: ALL

• KHU-2 Emergency Lockout MSS330

• TD EFDW Pump fails to start in Auto

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

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam SCENARIO 3 EVENT

SUMMARY

Event 1: When the crew takes the shift, the SRO will direct the BOP to restore 1B Main FDW Pump from Handjack. Once proper operation of the FDW Pump Motor Gear Unit is verified, the 1B Main FDW Pump will be placed in automatic.

Event 2: 1HP-120 will fail closed which will cause RCS makeup to be lost. Pressurizer level will begin to decrease and Letdown Storage Tank level will begin to increase. Once the crew responds to the event and takes actions to stabilize RCS makeup and letdown, 1HP-120 will be repaired and the crew will place the valve back in automatic and restore normal operation.

Event 3: The 1D1 Heater Drain Pump (HDP) bearing temperatures will begin to increase due to low oil level. The OATC will perform a power decrease to 87% with ICS in automatic. The BOP will start 1A and 1B FDW Pump Seal Injection Pumps and Auxiliary Oil Pumps prior to securing the 1D1 HDP.

Event 4: Controlling Narrow Range Tave will fail high. FDW flow will increase and Control Rods will insert in an attempt to restore normal parameters. Once alarms are received, the crew will perform Plant Transient Response to stabilize the plant. The OATC will decrease Feedwater flow and the BOP will insert Control Rods to restore the heat balance. Once the plant is stable, the SRO will enter AP/1/A/1700/028 (ICS Instrument Failures) and ensure the appropriate ICS stations are in manual and the BOP will perform an instrument surveillance for the failed instrument.

Event 5: The crew will receive alarms indicating high oil level in the 1A2 RCP Lower Oil Pot.

The SRO will enter AP/1/A/1700/016 (Abnormal RCP Operation). Once the 1A2 RCP is secured, the OATC will be required to re-ratio FDW in order to stabilize the plant.

Event 6 The OATC will perform a manual power decrease to 70% prior to the BOP securing the 1A2 RCP.

Event 7: The CT-1 Transformer (Startup Transformer) will lockout causing PCB-17 and PCB-18 to trip open. This will require the SRO to enter TS 3.8.1.

Event 8: A Switchyard Isolation will occur and seconds later the Reactor will trip causing a Blackout. The SRO will enter the Blackout Tab of the EOP. The Turbine Driven Emergency Feedwater Pump (TD EFDWP) will not automatically start which will require an operator to manually start the pump to restore heat removal from the core.

Power will be restored in accordance with EOP Enclosure 5.38 (Restoration of Power) from a Keowee Hydro Unit.

Page 2 of 57

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

Description:

Restore 1B Main FDW Pump From Handjack (N: BOP, SRO)

Time Position Applicants Actions or Behavior OP/1/A/1106/002 B Encl 4.13 Crew response:

SRO directs the BOP to restore 1B Main FDW Pump from Handjack per OP/1/A/1106/002 B Enclosure 4.13 OP/1/A/1106/002 B Encl 4.13 (Taking 1B FDWPT Off Handjack) rev 39 BOP/SRO NOTE: If both FDWPT(s) are in HAND changes in FDW valve P can cause CTP to change 2.1 IF in Mode 1 OR Mode 2, perform the following:

2.1.1 WHILE enclosure is in progress monitor the following indications:

• Appropriate ranged NIs

• Neutron error

• RCS Loop T (curve for "Loop T Vs Reactor Power" is in PT/1/A/0600/001)

• FDW Flow (curve for "Expected Feedwater Flow Per Header Vs Reactor Power" is in OP/0/A/1108/001) 2.2 Remove "T/O SHEET" CR tag from 1B MAIN FDW PUMP (ICS) station 2.3 Run 1B MAIN FDW PUMP (ICS) station to "HSS" (high speed stop)

NOTE: Operator should locally verify Motor Gear Unit moves smoothly from low speed stop and back to high speed stop 2.4 Perform the following:

2.4.1 Establish communication with Operator at 1B FDWPT 2.4.2 Run 1B MAIN FDW PUMP (ICS) to low speed stop 2.4.3 Run 1B MAIN FDW PUMP (ICS) to high speed stop

( 1/8" from hard stop) 2.4.4 Verify Motor Gear Unit operated smoothly through entire operation Booth Cue: When asked, state that the MGU operated smoothly through the entire operation.

2.5 Turn 1B FDWP HANDJACK switch to "OFF" This event is complete when the 1B Main FDW Pump is placed in Auto (Step 2.15), or as directed by the Lead Examiner.

Page 3 of 57

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

Description:

Restore 1B Main FDW Pump From Handjack (N: BOP, SRO)

Time Position Applicants Actions or Behavior OP/1/A/1106/002 B Encl 4.13 Crew response:

OP/1/A/1106/002 B Encl 4.13 BOP/SRO NOTE: Changes in FDW valve P will cause swings in CTP. Decreases in FDW valve P will cause CTP to decrease 2.6 IF Unit 1 is in Mode 1 or 2 AND both FDWPT ICS stations are in "HAND" (N/A)

NOTE:

• Motor Gear Unit control indicated by FDWPT speed and/or suction flow decreasing

• Two successful decreases verifies control with Motor Gear Unit 2.7 2.7 Decrease 1B MAIN FDW PUMP (ICS) until 1B FDWPT controlled by 1B MAIN FDW PUMP (ICS) station 2.8 Increase 1B FDWP Motor Speed Changer 2.9 Verify 1B FDWPT speed does NOT increase 2.10 Position 1B FDWP MOTOR SPEED CHANGER to 'FR' under "RAISE" until 1B FDWP MOTOR SPEED CHANGER is at "HSS" 2.11 After 1B FDWP MOTOR SPEED CHANGER reaches "HSS", hold 1B FDWP MOTOR SPEED CHANGER switch in 'FR' for 3 to 5 seconds to make all contacts 2.12 IF Unit 1 is in Mode 3: (N/A) 2.13 IF Unit 1 is in Mode 1 or 2 with 1A FDWPT shutdown: (N/A)

NOTE: Changes in FDW valve P will cause swings in CTP. Decreases in FDW valve P will cause CTP to decrease 2.14 IF Unit 1 is in Mode 1 or 2 with 1A FDWPT operating but NOT in auto: (N/A) 2.15 IF Unit 1 is in Mode 1 or 2 with 1A FDWPT in auto:

2.15.1 Verify 1A MAIN FDW PUMP (ICS) in "AUTO" 2.15.2 Place 1B MAIN FDW PUMP (ICS) in "AUTO" 2.15.3 Verify ICS adjusts 1B FDWPT speed to balance suction flow 2.16 IF required, remove Turnover Sheet note for control of 1B FDWPT with Motor Speed Changer This event is complete when the 1B Main FDW Pump is placed in Auto (Step 2.15), or as directed by the Lead Examiner.

Page 4 of 57

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

Description:

1HP-120 Fails Closed (C: OATC, SRO)

Time Position Applicants Actions or Behavior Booth Cue: When directed by the Lead Examiner, call as the WCC SRO and request Battery 1CA voltage located on 1EB6. If asked, I&E needs the reading for data trending.

Plant Response:

• RCS makeup flow goes to 8 - 10 gpm (HPI Warming Flow)

• PZR level begins to decrease

• LDST level begins to increase

• Valve position demand for 1HP-120 will increase to the 100% demand value and valve position indication will indicate closed (green light)

• 1SA-02/ B-1 (HP LETDOWN TANK LEVEL HIGH/LOW) will illuminate after several minutes SRO Crew Response:

Examiner Note: If the 1HP-120 failure is recognized before the LDST Statalarm actuates, the SRO will make a direct entry into AP/14 (next page). Otherwise the crew may perform the ARG and OP below and enter AP/14 when the SRO determines the entry conditions are met.

BOP ARG 1SA-02/B-1 The crew may refer to ARG 1SA-02/B-1 (HP LETDOWN TANK LEVEL HIGH/LOW) and perform the required actions. rev 33 3.1 Instrument Failed:

3.1.1 Compare alternate channels to verify alarm validity:

• O1A1042 LDST LEVEL 1

• O1A1043 LDST LEVEL 2 3.2 Verify LDST pressure does not exceed LDST level/pressure operability requirement per OP/0/A/1108/001 (Curves and General Information).

3.3 IF High Level alarm is received:

3.3.1 Bleed as required by OP/1/A/1103/004 (Soluble Poison Concentration Control).

This event is complete when Step 4.186 of AP/14 is complete, or as directed by the Lead Examiner.

Page 5 of 57

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

Description:

1HP-120 Fails Closed (C: OATC, SRO)

Time Position Applicants Actions or Behavior OP/1/A/1103/004 Crew Response:

Examiner Note: The crew may perform Enclosure 4.8 as necessary to reduce inventory. Enclosure 4.6 is performed to makeup/batch.

OP/1/A/1103/004 Enclosure 4.8 (Reducing RCS Inventory) rev 105 2.1 Verify HPI System operating 2.2 Ensure open 1CS-26 (LETDOWN TO RC BHUT) 2.3 Ensure open 1CS-41 (1A RC BHUT INLET) 2.4 Position 1HP-14 (LDST BYPASS) to BLEED 2.5 WHEN desired LDST level achieved, position 1HP-14 to NORMAL Examiner Note: The crew may initiate EOP Encl 5.5 for RCS inventory control due LDST level increase (page 48)

AP/1/A/1700/014 AP/1/A/1700/014 (Loss of Normal Makeup and/or RCP Seal Injection) rev 18 OATC/SRO 3.1 IAAT RCP seal injection flow is lost, AND Component Cooling is lost, THEN perform the following:

A. Trip the Rx B. Stop all RCPs C. Initiate AP/25 (SSF EOP) 3.2 IAAT loss of suction to operating HPI pumps is indicated:

• Motor amps low or cycling

• Discharge pressure low or cycling

• Abnormal LDST level trend THEN GO TO Step 3.3 RNO: GO TO Step 4.7 4.7 Announce AP entry using PA System 4.8 Verify any HPI pump operating This event is complete when Step 4.186 of AP/14 is complete, or as directed by the Lead Examiner.

Page 6 of 57

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

Description:

1HP-120 Fails Closed (C: OATC, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/014 Crew Response:

AP/1/A/1700/014 4.9 Verify RCP seal injection or HPI makeup line leak indicated by any of OATC/SRO the following:

• Report of line leak

• Abnormal LDST level decrease

• 1RIA-32 (AUX BLDG GAS)

• 1RIA-45 (NORM VENT GAS)

• RB RIAs in alarm

• Abnormal RBNS level increase

• Abnormal LAWT or HAWT level increase RNO: GO TO Step 4.11 4.11 Verify RCP seal injection flow exists to any RCP 4.12 Verify 1HP-120 operable in AUTO RNO: 1. Attempt to operate 1HP-120 in HAND (will NOT operate)

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

• Close 1HP-6

• Throttle 1HP-7

• Throttle 1HP-26 4.177 Place 1HP-120 in HAND and close 4.178 Notify SPOC to investigate and repair 1HP-120 4.179 WHEN 1HP-120 is repaired, THEN slowly re-establish flow through 1HP-120 Examiner Note: 1HP-120 will be repaired after 15 minutes and prior to Event 4.

This event is complete when Step 4.186 of AP/14 is complete, or as directed by the Lead Examiner.

Page 7 of 57

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

Description:

1HP-120 Fails Closed (C: OATC, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/014 Crew Response:

OATC/SRO 4.180 Place 1HP-120 in AUTO 4.181 Close 1HP-26 4.182 Verify 1HP-122 (RC VOLUME CONTROL BYPASS) throttled RNO: GO TO Step 4.184 4.184 Verify 1HP-5 open Examiner Note: 1HP-6 may be open or closed based on the actions taken in Step 4.176 4.185 Verify 1HP-6 open RNO: 1. Throttle 1HP-7 for 20 gpm letdown flow

2. Open 1HP-6 4.186 Adjust 1HP-7 for desired letdown 4.187 WHEN conditions permit, THEN EXIT this procedure This event is complete when Step 4.186 of AP/14 is complete, or as directed by the Lead Examiner.

Page 8 of 57

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

Description:

1D1 HDP Low Oil Level (Auto Power Decrease) (C: BOP, SRO)

Time Position Applicants Actions or Behavior Plant response:

• OAC alarm HDP 1D1 Thrust Bearing Temp Hi

• OAC alarm HDP 1D1 MTR Lower Bearing Temp Hi-Hi Crew response:

Refer to the OAC Alarm Response:

• Remove the pump from service per OP/1/A/1106/002 D (HDP Operation)

The SRO will enter AP/1/A/1700/029 to reduce Reactor power 87% to secure the 1D1 Heater Drain Pump (page 10)

Booth Cue: If an AO is sent to look at the HDP, report as an AO, that the lower oil sight glass of the 1D1 HDP is empty. The oil has been contained in the HDP sump and cleanup is in progress.

SRO should direct BOP to secure the 1D1 HDP once Reactor power has been SRO reduced to 87%. FIN-24 (SPOC) should be notified to investigate and repair the oil leak.

OP/1/A/1106/002D The BOP should secure the 1D1 HDP per OP/1/A/1106/002 D Enclosure 4.4 BOP/SRO (Shutdown of 1D1 HDP) rev 13 2.1 Verify CTP DEMAND 87%

3.1 Stop 1D1 HTR DRN PUMP 3.2 Verify 1HD-190 (1D1 Flash Tank Emer Level Control) opens by observing computer indication (O1D2092) 3.3 Verify 1HD-208 (1D1 HDP RECIRC) switch in "AUTO" 3.4 IF 1D1 HD pump breaker is no longer required, rack out 1TE-7 (1D1 Heater Drain Tank Pump Mtr)

Note: The SRO may determine that tagging the 1D1 HDP breaker is not required at this time Note: The SRO may refer to RP/0/A/1000/017 (Spill Response)

Booth Cue: If asked, Unit 2 will implement RP/0/A/1000/017 (Spill Response)

This event is complete when the 1D1 HDP has been secured and 1HP-120 has been returned to AUTO, or when directed by the Lead Examiner.

Page 9 of 57

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

Description:

1D1 HDP Low Oil Level (Auto Power Decrease) (C: BOP, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/029 Crew response:

AP/1/A/1700/029 (Rapid Unit Shutdown) rev 13 BOP/SRO 4.1 Initiate Encl 5.1 (Support Actions During Rapid Unit Shutdown)

(page 12) 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 4.5 Deselect MAXIMUM RUNBACK 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 This event is complete when the 1D1 HDP has been secured and 1HP-120 has been returned to AUTO, or when directed by the Lead Examiner.

Page 10 of 57

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

Description:

1D1 HDP Low Oil Level (Auto Power Decrease) (C: BOP, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/029 Crew response:

4.8 Verify ICS in AUTO OATC/SRO 4.9 Depress MAXIMUM RUNBACK 4.10 Verify both Main FDW pumps running NOTE

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

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

• To lower 1A Main FDW Pump suction flow, bias is adjusted clockwise 4.11 Adjust bias for first Main FDW pump desired to be shutdown until suction flow is 1 x 106 lbm/hr less than remaining Main FDW pump suction flow 4.12 WHEN core thermal power is < 65% FP, THEN continue Examiner Note: If Reactor power is reduced below 85% during this event, TS 3.10.1 will apply.

TS 3.10.1 STANDBY SHUTDOWN FACILITY SRO 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)

BOOTH CUE: After 15 minutes and prior to Event 4, call as FIN24 and notify the crew that 1HP-120 had an air line fitting leak.

The fitting was tightened and the leak is repaired. 1HP-120 can be placed back in service.

This event is complete when the 1D1 HDP has been secured and 1HP-120 has been returned to AUTO, or when directed by the Lead Examiner.

Page 11 of 57

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

Description:

1D1 HDP Low Oil Level (Auto Power Decrease) (C: BOP, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/029 Enclosure 5.1 Crew response:

AP/29 Enclosure 5.1 (Support Actions During Rapid Unit Shutdown)

BOP/SRO

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

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 This event is complete when the 1D1 HDP has been secured and 1HP-120 has been returned to AUTO, or when directed by the Lead Examiner.

Page 12 of 57

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

Description:

1D1 HDP Low Oil Level (Auto Power Decrease) (C: BOP, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/029 Enclosure 5.1 Crew response:

AP/29 Enclosure 5.1 (Support Actions During Rapid Unit Shutdown)

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 This event is complete when the 1D1 HDP has been secured and 1HP-120 has been returned to AUTO, or when directed by the Lead Examiner.

Page 13 of 57

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

Description:

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

Time Position Applicants Actions or Behavior Plant response:

• Controlling NR Tave digital display reads 586°F

• Controlling Tave Chessell display reads 586°F

• 1SA-2/A-12 (ICS Tracking)

• 1SA-2/C-11 (ICS Loss of OAC CTP Signal)

• Control Rods will insert and FDW flow will increase

• RCS pressure will decrease Examiner Note: If Reactor power decreases below 85% during this event, the SRO will enter Tech Spec 3.10.1 Conditions A-E which all have a 7 day completion time (SSF OOS).

Crew response:

When the Statalarms are received, the crew should perform Plant Transient Response (PTR) to stabilize the plant OATC The OATC should:

• Communicate to the CRS the initial alarm (if applicable) followed by reactor power level and direction CT-1

• 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 Examiner 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 SRO should:

• Refer to AP/28 (ICS Instrument Failures) (page 15)

• Ensure FIN-24 (SPOC) is contacted to repair the failed instrument This event is complete when the SRO reaches Step 6 of Section 4A, or as directed by the Lead Examiner.

Page 14 of 57

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

Description:

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

Time Position Applicants Actions or Behavior AP/1/A/1700/028 Crew response:

AP/1/A/1700/028 (ICS Instrument Failures) rev 20 4.1 Provide control bands as required (OMP 1-18 Attachment I)

OATC/SRO 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)

• Emergency Plan

__ STA 4.3 Verify a power transient 5% has occurred RNO: GO TO Step 4.5.

4.4 Notify Rx Engineering and discuss the need for a maneuvering plan 4.5 Use the following, as necessary, to determine the applicable section from table in Step 4.6:

• OAC alarm video

• OAC display points

• Control Board indications

• SPOC assistance, as needed This event is complete when the SRO reaches Step 6 of Section 4A, or as directed by the Lead Examiner.

Page 15 of 57

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

Description:

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

Time Position Applicants Actions or Behavior AP/1/A/1700/028 Crew response:

AP/1/A/1700/028 (ICS Instrument Failures)

OATC/SRO 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

1. Ensure the following in HAND:

__ 1A FDW MASTER

__ 1B FDW MASTER

2. Ensure DIAMOND in MANUAL This event is complete when the SRO reaches Step 6 of Section 4A, or as directed by the Lead Examiner.

Page 16 of 57

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

3. Notify SPOC to perform the following:

OATC/SRO

__ 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 Examiner Note: This step will require the BOP to refer to Table 1 (RCS Temperature) of Enclosure 5.2 (next page) and determine if the surveillance for SR 3.4.1.2 can be met as it is written with the failed temperature instrument. Based on plant response to the failure the BOP will determine either:

1. The surveillance is not required to be met due to plant conditions (not steady state)

2. The surveillance can be met as written

3. The surveillance can NOT be met as written This information will be reported to the SRO when asked in Step 5.

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

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

This event is complete when the SRO reaches Step 6 of Section 4A, or as directed by the Lead Examiner.

Page 17 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Page 18 of 57

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

Description:

1A2 RCP High Oil Level (C: BOP, SRO)

Time Position Applicants Actions or Behavior Plant response:

• OAC alarm RCP 1A2 MTR LOWER OIL POT LEVEL Crew response:

BOP/SRO The BOP will refer to OAC alarm response guide for 1A2 RCP high oil level

1. If RCP operating and RCP was not started in the past 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, GO TO AP/1/A/1700/016 (Abnormal Reactor Coolant Pump Operation)

AP/1/A/1700/016 AP/1/A/1700/016 (Abnormal RCP Operation) rev 34 4.1 IAAT any RCP meets immediate trip criteria of Encl 5.1 (RCP Immediate Trip Criteria),

THEN perform Steps 4.2 - 4.11 RNO: GO TO Step 4.12 Examiner Note: In step 4.12, the crew may conservatively decide to secure the RCP because the oil pot level is threatening to go off-scale high. If so, they will proceed to step 4.13 (page 23) and will not end up in Section 4C. Either procedure path is acceptable.

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 (page 23)

RNO: GO TO Step 4.16 4.16 Announce AP entry using the PA system 4.17 Notify OSM to request evaluation by RCP Component Engineer This event is complete when the 1A2 RCP has been secured and Tc is 0 +/- 2°F, or as directed by the Lead Examiner.

Page 19 of 57

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

Description:

1A2 RCP High Oil Level (C: BOP, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/016 Crew response:

4.18 IAAT the failure is identified, BOP/SRO 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 4C AP/1/A/1700/016 Section 4C (High or Low Oil Pot Level)

1. IAAT any RCP meets immediate trip criteria of Encl 5.1 (RCP Immediate Trip Criteria), THEN perform Steps 2 - 11 RNO: GO TO Step 12 12 Start trending RCP oil pot levels (Turn-on Code "unitpump"RCPT3, example 1A2RCPT3)

NOTE

• RCP oil pot level indication range is +1.5 to -1.5 inches

• RCP motor oil pot temperatures and RCP motor guide bearing temperatures may be used to validate low oil pot level 13 IAAT oil pot level threatens to go off scale high or low for an operating RCP, THEN perform Steps 14 - 24 14 Verify MODE 1 or 2 15 Verify three RCPs will remain operating after affected RCP is tripped This event is complete when the 1A2 RCP has been secured and Tc is 0 +/- 2°F, or as directed by the Lead Examiner.

Page 20 of 57

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

Description:

1A2 RCP High Oil Level (C: BOP, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/016 Section 4C Crew response:

AP/1/A/1700/016 Section 4C BOP/SRO

16. Verify Rx power is 70% as indicated on all NIs RNO: 1. Direct an RO to initiate Encl 5.2 (Rapid Power Reduction) (page 29)

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

17. Verify any SG on Low Level Limits RNO: GO TO Step 20

20. Verify FDW Masters in Auto CAUTION Total feedwater flow should be maintained constant to prevent changes in core reactivity RNO: 1. Stop the affected RCP

2. Manually adjust FDW masters to achieve desired Tc

3. GO TO Step 23

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

24. Make 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> frequency This event is complete when the 1A2 RCP has been secured and Tc is 0 +/- 2°F, or as directed by the Lead Examiner.

Page 21 of 57

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

Description:

1A2 RCP High Oil Level (C: BOP, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/016 Section 4C Crew response:

AP/1/A/1700/016 Section 4C BOP/SRO 25 IAAT an RB fire exists, THEN perform Steps 26 - 29 RNO: GO TO Step 30 30 IAAT either of the following conditions is met:

__ a RCP with low oil level has been shut down for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />

__ 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) 31 IAAT a RCP has been tripped due to exceeding Immediate Trip Criteria on a RCP motor, THEN contact RCP engineer prior to restart 32 IAAT both are met:

__ There has been a failure of the DELTA Tc controller

__ The DELTA Tc controller has been repaired THEN initiate OP/1/A/1102/004 A Encl (Placing ICS Stations To Auto) 33 WHEN conditions permit, THEN EXIT this procedure.

This event is complete when the 1A2 RCP has been secured and Tc is 0 +/- 2°F, or as directed by the Lead Examiner.

Page 22 of 57

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

Description:

1A2 RCP High Oil Level (C: BOP, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/016 Alternate path from Step 4.12 Crew response:

Examiner Note: If the crew determines that It is desired to secure the 1A2 RCP in Step 4.12 due to oil levels going off-scale high, below lists the procedure path to secure the 1A2 RCP.

BOP/SRO 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 4.13 Verify Rx Power > 70%

4.14 Initiate Encl 5.2 (Rapid Power Reduction) (page 29) 4.15 WHEN Rx Power is 70%, THEN GO TO Step 4.2 4.2 Verify MODE 1 or 2 4.3 Verify Rx power is 70% as indicated on all NIs 4.4 Verify three RCPs will remain operating after affected RCP is tripped 4.5 Verify any SG on Low Level Limits RNO: GO TO Step 4.8 4.8 Verify FDW masters in Auto CAUTION Total feedwater flow should be maintained constant to prevent changes in core reactivity RNO: 1. Stop the affected RCP

2. Manually adjust FDW masters to achieve desired Tc

3. GO TO Step 4.29 This event is complete when the 1A2 RCP has been secured and Tc is 0 +/- 2°F, or as directed by the Lead Examiner.

Page 23 of 57

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

Description:

1A2 RCP High Oil Level (C: BOP, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/016 Alternate path from Step 4.12 Crew response:

AP/1/A/1700/016 BOP/SRO 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) 4.31 IAAT either of the following conditions is met:

__ a RCP has been shut down for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />

__ a RCP with high oil level has been shut down THEN close the associated RCP motor cooler inlet/outlet valve:

__ 1LPSW-7&8 (1A1 RCP)

__ 1LPSW-9&10 (1B1 RCP)

__ 1LPSW-13&14 (1A2 RCP)

__ 1LPSW-11&12 (1B2 RCP) 4.32 IAAT either of the following has exceeded 260°F including transient situations:

__ O1A1253 - O1A1256 (RCP UPPER SEAL HOUSING TEMP)

__ O1A1910 - O1A1913 (RCP SEAL RETURN TEMP)

THEN closely monitor seal parameters for degradation until an Engineering evaluation is completed due to potential for seal ring and elastomer damage This event is complete when the 1A2 RCP has been secured and Tc is 0 +/- 2°F, or as directed by the Lead Examiner.

Page 24 of 57

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

Description:

1A2 RCP High Oil Level (C: BOP, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/016 Alternate path from Step 4.12 Crew response:

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.

BOP/SRO 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 RNO: GO TO Step 4.39 4.39 WHEN conditions permit, THEN EXIT this procedure This event is complete when the 1A2 RCP has been secured and Tc is 0 +/- 2°F, or as directed by the Lead Examiner.

Page 25 of 57

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

Description:

1A2 RCP High Oil Level (C: BOP, SRO)

Time Position Applicants Actions or Behavior OP/1/A/1102/004 Encl 4.3 Crew response:

OP/1/A/1102/004 (Operations At Power) Encl 4.3 (Special Instructions For

< 4 RCP Operations) Rev 148 BOP/SRO 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 2.2 Perform one of the following: (Continue)

• Ensure TS 3.4.4 Condition A entered when fourth RCP secured

• Verify the following:

__ O1E4021 (1A RPS Var Flux Trip Value) set at 79.75%

__ O1E4022 (1A RPS Var Flux Trip Value) set at 79.75%

__ O1E4023 (1A RPS Var Flux Trip Value) set at 79.75%

__ O1E4024 (1A RPS Var Flux Trip Value) set at 79.75%

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 2.3 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 This event is complete when the 1A2 RCP has been secured and Tc is 0 +/- 2°F, or as directed by the Lead Examiner.

Page 26 of 57

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

Description:

1A2 RCP High Oil Level (C: BOP, SRO)

Time Position Applicants Actions or Behavior OP/1/A/1102/004 Encl 4.3 Crew response:

NOTE: The 100% Power Imbalance curves also apply for runs at reduced BOP/SRO power.

2.4 Maintain Control Rod position and Power Imbalance within COLR limits 2.5 IF NI calibration NOT within requirements of Limit and Precaution Step 2.2.6, calibrate NIs to Thermal Power Best 2.6 Perform the following per AM/1/A/0315/017 (TXS RPS Channels A, B, C, And D Parameter Changes For Abnormal/Normal Operating Conditions):

2.6.1 Notify I&E to reset RPS Overpower High Trip Setpoint for three RCP Operation Person Notified Date 2.6.2 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 Person Notified Date NOTE: The Maximum Allowed Power Setpoint (Pmax) is reduced when operating for extended periods when only three RCPs operating as a conservative action.

2.6.3 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 Person Notified Date 2.7 IF AT ANY TIME notified by I&E that RPS Overpower High Trip Setpoint adjusted for three RCP Operation, perform the following:

2.7.1 Verify the following:

__ O1E4021 (1A RPS Var Flux Trip Value) set at 79.75%

__ O1E4022 (1A RPS Var Flux Trip Value) set at 79.75%

__ O1E4023 (1A RPS Var Flux Trip Value) set at 79.75%

__ O1E4024 (1A RPS Var Flux Trip Value) set at 79.75%

2.7.2 Evaluate exiting TS 3.4.4 condition A This event is complete when the 1A2 RCP has been secured and Tc is 0 +/- 2°F, or as directed by the Lead Examiner.

Page 27 of 57

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

Description:

1A2 RCP High Oil Level (C: BOP, SRO)

Time Position Applicants Actions or Behavior OP/1/A/1102/004 Encl 4.3 Crew response:

2.8 Initiate review of PT/1/A/0600/001 (Periodic Instrument Surveillance) to BOP/SRO determine if any limits approached 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).

2.9 Adjust high flux alarm setpoint per Operations Management/Reactor Engineering Group recommendations. (Alarm setpoint is adjusted on the NI Recorder)

NOTE: 'D' bleed pressure may NOT be high enough to run the FDWP turbines.

2.10 Maintain Auxiliary Steam available to the FDWP turbines.

2.11 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 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.

2.12 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 the 1A2 RCP has been secured and Tc is 0 +/- 2°F, or as directed by the Lead Examiner.

Page 28 of 57

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

Description:

Manual Power Decrease (R: OATC, SRO)

Time Position Applicants Actions or Behavior AP/1/A/1700/016 Encl 5.2 Crew response:

The OATC will perform AP/1/A/1700/016 Encl 5.2 (Rapid Power Reduction) to reduce Reactor power < 70% to secure the 1A2 RCP AP/1/A/1700/016 Enclosure 5.2 (Rapid Power Reduction)

NOTE

• This enclosure should be performed by an RO

• The step to verify ICS in AUTO means that the ICS is capable of responding to a MAXIMUM RUNBACK signal OATC/SRO 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 CR SRO

4. Stop the following pumps:

__ 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period

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

9. EXIT this enclosure This event is complete when Rx power is < 70% on all NIs, or as directed by the Lead Examiner.

Page 29 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-lest No.: ILTI6-2 Scenario No.: 3 Event No.: 7 Page 1 of 1 Event

Description:

CT-I Lockout (SRO) (TS) lime Position Applicants Actions or Behavior Plant response:

• iSA-i 5/C-2 (EL SU SOURCE VOLT MONIT LOGIC UNDERVOLTAGE)

• SA-3/B-4 (Oconee White Startup Transformer Cli Tie PCB 17)

• SA-3/C-4 (Startup Transformer CT1 PCB 18)

• CT-i transformer will be de-energized

• PCB-17 and PCB-18 will trip open Crew response:

BOP The BOP will refer to Statalarm 1SA-i5/C-2 3.1 IF the start-up source was carrying the unit load fl the start-up breakers tripped, verify that power is supplied from the standby source 3.2 Refer to EPI1IN1800IOO1 (Emergency Operating Procedure) or API1/N170010i 1 (Recovery from Loss of Power) if required 3.3 IF only one phase trips, perform the following: (N/A) 3.4 Refer to TS 3.8.1 3.5 Return to the normal (preferable) or start-up source of power as soon as conditions permit Examiner Cue: If the crew trips the Reactor, Event 8 will auto actuate to initiate a Switchyard Isolation.

- Examiner Note: If the crew trips the Reactor, it will result in failure of a CT due to an unnecessary trip of the Reactor.

Booth Cue: If asked, U2 will perform the operability check of Keowee Hydro Unit.

The SRO will refer to Tech Specs (next page)

O4G. cr. io?.t &fc& $?v4 (2- I s 4 as.

14 7ti e14f) ,tc o S se.1-p k oe C!V% S ivf fioNLL4 0 O This event is complete when the SRO has determined Tech Specs, or as directed by the Lead Examiner.

Page 30 of 57

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

Description:

CT-1 Lockout (SRO) (TS)

Time Position Applicants Actions or Behavior Crew response:

SRO The SRO will refer to Tech Specs TS 3.8.1 AC SOURCES - OPERATING Condition A (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) Perform SR 3.8.1.3 AND (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) Align the emergency startup bus to share another units startup transformer AND (36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />) Restore transformer to OPERABLE status and normal startup bus alignment OR (36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />) Designate one unit sharing the startup transformer to be shutdown This event is complete when the SRO has determined Tech Specs, or as directed by the Lead Examiner.

Page 31 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 3 Event No.: 8 Page 1 of 16 Event

Description:

Switchyard Isolate (M: ALL)

Time Position Applicants Actions or Behavior Plant response:

• Switchyard Isolation occurs

• RCS Pressure increases

• Reactor will trip on RCS High Pressure (2345 psig)

• When the Reactor trips, a loss of power will occur due to KHU-2 lockout and CT-1 lockout Crew response:

• Crew may manually trip the reactor prior to reaching the RCS High Pressure setpoint

• SRO will direct the OATC to perform IMAs and the BOP to perform a symptom check IMMEDIATE MANUAL ACTIONS SRO The SRO will direct the OATC to perform IMAs 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 RNO: IF CC is unavailable, THEN immediately:

A. Stop all RCPs B. Notify CR SRO to initiate AP/25 SYMPTOM CHECK SRO The SRO will direct the BOP to perform a Symptoms Check.

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 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 Off-gas 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)

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

Page 32 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 3 Event No.: 8 Page 2 of 16 Event

Description:

Switchyard Isolate (M: ALL)

Time Position Applicants Actions or Behavior Crew response:

The SRO will direct the BOP to initiate AP/25 Examiner Note: When the BOP attempts to proceed to the SSF, inform him/her that a Unit 2 RO will perform AP/25 actions BLACKOUT TAB Blackout Tab rev 02 Examiner Note: When the Unit 2 CRS is notified to perform Unit 2 EOP Encl 5.42 (PSW Power and Pump Alignment), a booth instructor will enter the simulator to perform the enclosure. Performing this enclosure will have no effect on the outcome of the scenario.

Examiner Note: If asked as Unit 2 to perform Parallel Actions Page steps for turning off lights and opening doors in the control room, respond that Unit 2 will perform the steps.

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

2. Verify TDEFDWP feeding SGs

3. Direct RO to perform Encl 5.45 (PSW Feed and RCP Seals) to establish RCP seals (page 44)

4. Verify two ROs available to perform Control Room actions

5. Ensure Encl 5.45 (PSW Feed and RCP Seals) in progress or complete

6. Notify one RO to perform Encl 5.38 (Restoration of Power) (page 42)

7. Verify any:

__ Any SG is being fed from Emergency FDW or PSW

__ SSF or PSW is available to feed SGs

8. Verify both:

__ Blackout exists on all three units

__ PSW Power NOT available RNO: GO TO Step 10 This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.

Page 33 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 3 Event No.: 8 Page 3 of 16 Event

Description:

Switchyard Isolate (M: ALL)

Time Position Applicants Actions or Behavior BLACKOUT TAB Crew response:

10. Verify RCS temperature 550°F RNO: 1. Feed and steam available SGs, as necessary, to stabilize RCS P/T using one of the following:

__ TBVs

__ Dispatch two operators to perform Encl 5.24 (Operation of the ADVs) to prepare to steam intact SGs

2. GO TO Step 13

11. Verify feeding SGs with TDEFDW pump

12. Feed available SGs as necessary to stabilize RCS P/T in bands prescribed by Rule 7 (SG Feed Control)

NOTE

• Feeding SGs with EFDW is desired above HPI Forced Cooling. If a feed source becomes available, step 13 should be performed prior to re-performing Rule 3

• 100 gpm could cause overcooling if adequate decay heat levels do NOT exist

13. IAAT NO SGs are being fed, AND any source of EFDW (Unit 1 or another unit) becomes available, THEN perform Steps 14 - 18 RNO: GO TO Step 19 NOTE

• The EFW system operation is expected to last 2 - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during a three unit blackout without PSW power

• If battery power is lost and PSW power is not available, EFDW control will be lost

19. IAAT the SSF or PSW is available to feed SGs, AND EFDW from any source is insufficient to maintain stable RCS P/T, THEN perform one of the following:

__ Notify SSF operator that feeding SGs with SSF ASW is required (SSF CR x-2766)

__ Initiate Encl 5.45 (PSW Feed and RCP Seals) and feed SGs with PSW This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.

Page 34 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 3 Event No.: 8 Page 4 of 16 Event

Description:

Switchyard Isolate (M: ALL)

Time Position Applicants Actions or Behavior BLACKOUT TAB Crew response:

20. IAAT power is restored to any of the following:

__ 1TC

__ 1TD

__ 1TE THEN GO TO Step 21

21. Ensure any SG is being fed or action is being taken per Step 13

22. Verify SSF activated

23. Communicate status of SG feed and seal injection to SSF operator using x-2766, radio, or plant page

24. Initiate AP/11 (Recovery from Loss of Power) (page 38)

25. GO TO Subsequent Actions tab (page 36)

Examiner Note: The CRS may start over in the EOP when power is restored and re-perform IMAs and then transfer to Subsequent Actions. Either path is acceptable.

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

Page 35 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 3 Event No.: 8 Page 5 of 16 Event

Description:

Switchyard Isolate (M: ALL)

Time Position Applicants Actions or Behavior SUBSEQUENT ACTIONS TAB Crew response:

Subsequent Actions Tab 4.1 Verify all control rods in Groups 1 - 7 fully inserted 4.2 Verify Main FDW in operation 4.3 Verify either:

__ Main FDW overfeeding causing excessive temperature decrease

__ Main FDW underfeeding causing SG level decrease below setpoint RNO: GO TO Step 4.5 4.5 IAAT Main FDW is operating, AND level in any SG is > 96% on the Operating Range, THEN perform Steps 4.6 - 4.8 RNO: GO TO Step 4.9 4.9 IAAT TBVs CANNOT control SG pressure at desired setpoint, AND TBVs NOT intentionally isolated, THEN manually control pressure in affected SGs using either:

__ TBVs

__ Dispatch two operators to perform Encl 5.24 (Operation of the ADVs) 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 48)

2. GO TO Step 4.17 4.17 Open:

__ PCB 20

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

Page 36 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 3 Event No.: 8 Page 6 of 16 Event

Description:

Switchyard Isolate (M: ALL)

Time Position Applicants Actions or Behavior SUBSEQUENT ACTIONS TAB Crew response:

Subsequent Actions Tab 4.18 Verify Generator Field Breaker open 4.19 Verify EXCITATION is OFF 4.20 Verify Aux Bldg and Turbine Bldg Instrument Air pressure 90 psig 4.21 Verify ICS/NNI power available 4.22 Verify all 4160V switchgear (1TC, 1TD & 1TE) energized 4.23 Verify both SGs > 550 psig 4.24 Verify Main FDW operating 4.25 Verify any RCP operating 4.26 Verify AP/0/A/1700/025 (SSF EOP) Encl (Unit 1 OATC Actions During Fire) in progress or complete RNO: Ensure SGs approaching 25 - 35 [55 - 65 acc] S/U level 4.27 Place switches in CLOSE:

__ 1FDW-31

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

Page 37 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 3 Event No.: 8 Page 7 of 16 Event

Description:

Switchyard Isolate (M: ALL)

Time Position Applicants Actions or Behavior AP/1/A/1700/011 Crew response:

AP/1/A/1700/011 (Recovery From Loss of Power) rev 55 4.1 Announce AP entry using OMP 1-18 placard 4.2 IAAT all exist:

__ 1KI energized

__ Pzr level > 80 [180 acc]

__ Pzr heaters are desired THEN ensure Pzr heaters in AUTO 4.3 Verify load shed of inverters was performed per Unit 1 EOP Encl (Load Shed of Inverters During SBO)

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

__ 1SA-15/D-4 (EL LOAD SHED CHNL A LOGIC INITIATE)

__ 1SA-14/D-4 (EL LOAD SHED CHNL B LOGIC INITIATE) 4.10 Verify load shed is complete as indicated by LOAD SHED COMPLETE on any ES Channel (Channel 1 or 2) 4.11 Verify breakers closed:

__ 1TC INCOMING FDR BUS 1

__ 1TC INCOMING FDR BUS 2

__ 1TD INCOMING FDR BUS 1

__ 1TD INCOMING FDR BUS 2

__ 1TE INCOMING FDR BUS 1

__ 1TE INCOMING FDR BUS 2 4.12 Verify 1SA-15/E-6 (EL SWYD ISOLATION CONFIRMED CHNL A LOGIC) is OFF RNO: GO TO Step 4.15 4.15 Verify any Oconee unit receiving power form its normal source (1T, 2T, 3T)

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

Page 38 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 3 Event No.: 8 Page 8 of 16 Event

Description:

Switchyard Isolate (M: ALL)

Time Position Applicants Actions or Behavior AP/1/A/1700/011 Crew response:

AP/1/A/1700/011 (Recovery From Loss of Power) 4.15 Verify any Oconee unit receiving power form its normal source (1T, 2T, 3T)

RNO: GO TO Step 4.17 4.17 Verify load shed was initiated as indicated by either of the following statalarms on:

__ 1SA-15/D-4 (EL LOAD SHED CHNL A LOGIC INITIATE)

__ 1SA-14/D-4 (EL LOAD SHED CHNL B LOGIC INITIATE) 4.18 Verify ES has occurred RNO: GO TO Step 4.20 4.20 Simultaneously press RESET on both of the following pushbuttons to reset Main Feeder Bus Monitor Panel Load Shed Circuitry:

• MFB UNDERVOLTAGE CHANNEL 1 RESET

• MFB UNDERVOLTAGE CHANNEL 2 RESET 4.21 Verify load shed signal reset as indicated by both of the following statalarms off:

__ 1SA-15/D-4 (EL LOAD SHED CHNL A LOGIC INITIATE)

__ 1SA-14/D-4 (EL LOAD SHED CHNL B LOGIC INITIATE)

CAUTION Normal plant loads can overload the Auxiliary Transformer, CT-4, or CT-5 4.22 IAAT electrical loads are added, AND either MFB is energized by:

• CT-4

• CT-5

• Backcharged 1T THEN ensure transformer is within limits of the applicable enclosure:

Source Encl CT-4 5.1A CT-5 5.1B Transformer 1T 5.1C This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.

Page 39 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 3 Event No.: 8 Page 9 of 16 Event

Description:

Switchyard Isolate (M: ALL)

Time Position Applicants Actions or Behavior RULE 3 Crew response:

EOP Rule 3

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

__ Turbine Building Flooding

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

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

AND any of the following exist:

__ RCS pressure reaches 2300 psig OR NDT limit

__ Pzr level reaches 375 [340 acc]

THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling)

CT-2 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 0°F CAUTION ATWS events may initially require throttling to prevent exceeding pump limits and additional throttling once the Rx is shutdown to prevent overcooling RNO: IF overcooling, OR exceeding limits in Rule 7 (SG Feed Control),

THEN throttle EFDW, as necessary

45. IAAT Unit 1 EFDW is in operation, THEN initiate Encl 5.9 (Extended EFDW Operation) (page 41)

46. WHEN directed by CRS, THEN EXIT This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.

Page 40 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 3 Event No.: 8 Page 10 of 16 Event

Description:

Switchyard Isolate (M: ALL)

Time Position Applicants Actions or Behavior EOP Encl 5.9 Crew response:

EOP Enclosure 5.9 (Extended EFDW Operation) rev 01

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

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

Page 41 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 3 Event No.: 8 Page 11 of 16 Event

Description:

Switchyard Isolate (M: ALL)

Time Position Applicants Actions or Behavior EOP Encl 5.38 Crew response:

EOP Enclosure 5.38 (Restoration of Power) rev 0

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

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

4. Close 1HP-21

5. Verify any of the following energized:

__ MFB1

__ MFB2 RNO: GO TO Step 8

8. Verify CT-1 indicates 4160 volts RNO: GO TO Step 18

18. Verify both Standby Bus #1 and Standby Bus #2 are de-energized (0 volts)

19. Verify both Keowee units operating RNO: 1. Emergency start Keowee units:

__ KEOWEE EMER START CHANNEL A

__ KEOWEE EMER START CHANNEL B

2. IF NO Keowee units are operating, THEN perform the following:

A. Notify Keowee operator to restore a Keowee unit to operable status B. GO TO Step 38 Examiner Note: Keowee Hydro Unit 1 will be operating This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.

Page 42 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 3 Event No.: 8 Page 12 of 16 Event

Description:

Switchyard Isolate (M: ALL)

Time Position Applicants Actions or Behavior EOP Encl 5.38 Crew response:

EOP Enclosure 5.38

20. Verify both Keowee units in Oconee Control (statalarms on):

__ UNIT 1 OCONEE CONTROL (2SA-17/E-1)

__ UNIT 2 OCONEE CONTROL (2SA-18/E-1)

RNO: Notify Keowee Operator to place both Keowee units Master Transfer switches to remote

21. Verify both Keowee units operating RNO: 1. IF UNIT 1 EMER FDR ACB 3 is closed, AND Unit 1 Keowee is NOT operating, THEN open UNIT 1 EMER FDR ACB 3

2. IF UNIT 2 EMER FDR ACB 4 is closed, AND Unit 2 Keowee is NOT operating, THEN open UNIT 2 EMER FDR ACB 4 CT-3 22. Ensure one of the following is closed for an operating Keowee unit:

Unit 1 Unit 2 UNIT 1 UNIT 2 EMER FDR EMER FDR ACB 3 ACB 4

23. Verify 4160 volt power has been restored to the MFB

24. GO TO Step 35

35. Verify any of the following energized:

__ 1TC

__ 1TD

__ 1TE

36. Notify Unit 1 CRS of status of 4160V SWGR

37. EXIT this enclosure This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.

Page 43 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 3 Event No.: 8 Page 13 of 16 Event

Description:

Switchyard Isolate (M: ALL)

Time Position Applicants Actions or Behavior EOP Encl 5.45 Crew response:

EOP Enclosure 5.45 (PSW Feed and RCP Seals) rev 03 NOTE While running this enclosure along with a loss of power to HPIPs, Rule 4 should not be performed until SG feed has been established from some source

1. Verify Unit 2 EOP Encl 5.42 (PSW Power and Pump Alignment) in progress or complete RNO: Notify Unit 2 to PERFORM Unit 2 EOP Encl 5.42 (PSW Power and Pump Alignment)

Examiner Note: Once an RO notifies Unit 2 to perform EOP Encl 5.42, a booth instructor will enter the simulator to perform the enclosure. This enclosure will have no effect on the outcome of the scenario.

2. WHEN the Unit 1 PSW 4KV POWER AVAILABLE light lit, THEN continue

3. Verify it is desired to power HPI from PSW RNO: GO TO Step 9 NOTE There is a 40 second time delay in the swap from Normal to PSW power on HPIPs

4. Verify PSW SELECTED HPI PUMP selected to the 1A HPI pump RNO: GO TO Step 6

6. Verify PSW SELECTED HPI PUMP selected to the 1B HPI pump

7. Perform the following:

A. Place 1B HPI PUMP POWER TRANSFER to PSW B. Do NOT wait for the PSW power light, continue This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.

Page 44 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 3 Event No.: 8 Page 14 of 16 Event

Description:

Switchyard Isolate (M: ALL)

Time Position Applicants Actions or Behavior EOP Encl 5.45 Crew response:

EOP Enclosure 5.45

8. Place POWER TRANSFER switch to PSW on the following:

• 1HP-24

• 1HP-26

• 1RC-159/1RC-160

• 1RC-157/1RC-158

• 1RC-155/1RC-156

9. Position the switch for 1PSW-6 to open

10. Notify the CRS that PSW is aligned and ready to supply SG feed and RCP Seals

11. IAAT it is desired to supply PSW SG feed, THEN GO TO Step 42

12. IAAT it is desired to supply RCP seals, THEN GO TO Step 57 (page 46)

NOTE If RCS head vents, loop vents, or PORV have been opened, ACC levels must be used

13. IAAT Pzr level 85" (165" ACC), AND it is desired to power the Pzr heaters from PSW, THEN dispatch an operator to perform EOP Encl 5.46 (Aligning PZR Heaters From PSW)

14. IAAT notified that PSW is NO longer required, THEN GO TO Step 16

15. WHEN directed by CRS, THEN EXIT this enclosure This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.

Page 45 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 3 Event No.: 8 Page 15 of 16 Event

Description:

Switchyard Isolate (M: ALL)

Time Position Applicants Actions or Behavior EOP Encl 5.45 Crew response:

EOP Enclosure 5.45

57. IAAT notified that SSF Feed has been established or is capable of feeding SGs, THEN simultaneously close the PSW control valves:

__ 1PSW-22 (1A SG)

__ 1PSW-24 (1B SG)

58. IAAT PSW SG feed is aligned but NOT feeding, AND RCS pressure >

2300 psig, THEN PERFORM Step 43.

NOTE If RCS head vents, loop vents, or PORV have been opened, ACC levels must be used

59. IAAT feeding SGs with PSW AND Tc 550 - 555°F, THEN throttle the following valves, as required, to slowly raise SG levels to 240"- 260" XSUR (270" - 290" ACC) while maintaining Tc 550 - 555°F:

__ 1PSW-22 (1A SG)

__ 1PSW-24 (1B SG)

NOTE ES may have actuated requiring manual control of HPI

60. Perform the following:

__ Close 1HP-139

__ Open 1HP-24

__ Close 1HP-26

61. Ensure 1HP-120 in manual with demand at zero

62. Verify BWST available based on Control Room level indication This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.

Page 46 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 3 Event No.: 8 Page 16 of 16 Event

Description:

Switchyard Isolate (M: ALL)

Time Position Applicants Actions or Behavior EOP Encl 5.45 Crew response:

EOP Enclosure 5.45 NOTE

• HPI pump ammeter will not respond when HPI pump is powered from PSW

• When the SSF and PSW are both supplying seals it may not be possible to get 30 - 35 gpm flow through 1HP-140

63. Start an HPI Pump by positioning HPI PUMP START FROM PSW POWER to START

64. Throttle 1HP-140 to obtain as close to 30 - 35 gpm RCP Seal flow as possible NOTE RCS pressure higher than normal RCS operating pressure could restrict flow through 1HP-140

65. Maintain 30 - 35 gpm Seal Inlet Hdr Flow by throttling 1HP-140 as necessary

66. Close 1HP-5

67. Close 1HP-21 NOTE If RCS head vents, loop vents, or PORV have been opened, ACC levels must be used

68. IAAT Pzr level 85" (165" ACC), AND it is desired to power the Pzr heaters from PSW, THEN dispatch an operator to perform EOP Encl 5.46 (Aligning Pzr Heaters from PSW)

69. Notify CRS PSW RCP seals have been established This event is complete when the SRO transfers to the Subsequent Actions tab, or as directed by the Lead Examiner.

Page 47 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 57

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

• *

• END * *

• Page 55 of 57

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam CRITICAL TASKS CT-1 ICS must be taken to HAND and FDW flow 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 Start the TD EFDWP to supply Feedwater flow to the SGs for heat removal to preclude initiation of HPI Forced Cooling.

CT-3 Restore power from Keowee Hydro Unit 1 prior to the completion of EOP Enclosure 5.38 (BWOG CT-3).

Page 56 of 57

SAFETY: Take a Minute UNIT 0 (OSM)

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

Unit 1 Simulator Other Units Mode: 1 Unit 2 Unit 3 Reactor Power: 100% Mode: 1 Mode: 1 Gross MWE: 892 100% 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 Today/0300 7 Days SLC 16.7.2 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.

• SASS is in Manual for calibration Secondary

• AMSAC/DSS bypassed for calibration

• Unit 2 is supplying the AS header

• OP/1/A/1106/002B Encl 4.13 in progress to restore 1B Main FDW Pump from Handjack

• 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 Page 57 of 57

Appendix D Scenario Outline Form ES D-1 ILT16-2 NRC Exam Facility: Oconee Scenario No.: 4 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________ SRO

________________________ ________________________ OATC

________________________ ________________________ BOP Initial Conditions:

• Reactor Power = Critical below POAH Turnover:

• 1A CFT level high. Lower 1A CFT level per OP/1/A/1104/001 Encl 4.17

• Unit startup in progress. Increase Reactor power from below the POAH to 3.0% and place ICS in Auto per OP/1/A/1102/001 Encl 4.7 Event Malfunction Event Event Type* Description No. No.

0a Override AFIS Fails to Actuate 0b Override ES Channel 1 Fails to go to Manual 0c 1 N: BOP, SRO Lower 1A CFT Level 2 R: OATC, SRO Increase Power to 3.0% and Place ICS in Auto 3 Override C: BOP, SRO 1B FWPT Auxiliary Oil Pump Trip MPS061 4 C: BOP, SRO (TS) 1A Letdown Cooler Leak MPS061D 5 SRO (TS) TD EFDWP Oil Sump Dry 6 Override C: OATC, SRO 1RC-1 (PZR Spray Valve) Fails Open MCR022 Two Dropped Control Rod(s) Requiring a Reactor 7 MCR028 C: OATC, SRO Trip 1A MSLB Inside Containment MSS360 8 M: ALL

• AFIS Fails to Actuate

• ES Channel 1 Fails to go to Manual

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

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam SCENARIO 4 EVENT

SUMMARY

Event 1: When the crew takes the shift, the SRO will direct the BOP will lower the level in the 1A Core Flood Tank using OP/1/A/1104/001 Enclosure 4.17.

Event 2: The OATC will increase power from below the POAH to 3.0% and place ICS in automatic.

Event 3: The Auxiliary Oil Pump for the 1B FWPT will trip causing the Emergency Oil Pump to start. Per the Alarm Response Guide (ARG), the BOP will attempt to start the Auxiliary Oil Pump which will fail. Shortly afterwards, the alarm for FWPT 1B Emergency Oil Pump Overload will alarm which will require the candidate to attempt to start the Auxiliary Oil Pump. Not being able to start the pump, the ARG will direct the BOP to stop the Turning Gear Motor to prevent damaging the Feedwater Pump.

Event 4: The 1A Letdown Cooler will develop a leak. The SRO will enter AP/1/A/1700/018 (Abnormal Release of Radioactivity) and AP/1/A/1700/002 (Excessive RCS Leakage).

AP/1/A/1700/002 will isolate the 1A Letdown Cooler. The SRO will enter TS 3.4.13 Event 5: The Work Control Center SRO will contact the control room stating that an AO reports that the Turbine Driven Emergency FDW Pump oil sump indicates no oil on the dipstick. The SRO should direct the OATC to place the TD EFDW pump switch in Pull To Lock (PTL). The SRO will enter TS 3.7.5 for an inoperable TD EFDW Pump.

Event 6: The 1RC-1 (Pressurize Spray Valve) will fail open causing RCS pressure to unexpectedly decrease. The operator will be required to close 1RC-3 (Pressurizer Spray Block Valve) in order to stop the pressure decrease and prevent tripping the Reactor.

Event 7: Two control rods will drop into the core requiring a manual Reactor trip. Once the Reactor is manually tripped in accordance with OMP 1-18 (Implementation Standards During Abnormal and Emergency Events), Event 8 will automatically initiate.

Event 8: When the Reactor trips, a Main Steam Line Break on the 1A Steam Generator will occur inside containment. Engineered Safeguards (ES) Channels 1-6 will actuate on high Reactor Building pressure. The SRO will enter the Excessive Heat Transfer tab and one RO will initiate Rule 5 (MSLB) while the other RO initiates EOP Enclosure 5.1 (ES Actuation). The Automatic Feedwater Isolation System (AFIS) will fail to actuate which will require an operator to manually isolate Feedwater to the 1A SG to prevent overcooling the RCS and Reactor Core. ES Channel 1 will fail to go to manual which will require an operator to override the Odd Voters to take manual control of ES Channel 1 components.

Page 2 of 75

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

Description:

Lower 1A CFT Level (C: BOP, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1104/001 Encl 4.17 Crew Response:

OP/1/A/1104/001 Enclosure 4.17 (Lowering CFTs Level To MWHUT) rev 79 SRO 2.1 Open 1CF-38 (CF Drn to MWHUT Blk). (A-4-W Pent Rm) 2.2 IF required to decrease level in 1A CFT, perform the following:

2.2.1 Record 1A CFT level: _______ feet BOP 2.2.2 IF Containment Operability is required, enter Technical Specification 3.6.3 Condition 'A' 2.2.3 Open 1CF-3 (1A CFT SAMPLE & DRAIN) 2.2.4 IF Containment Operability is required, establish constant communication with CR and personnel near 1CF-7. (A-4-W Pent Rm) 2.2.5 Begin monitoring 1A CFT level and pressure 2.2.6 Throttle 1CF-7 (CF to MWHUTs). (A-4-W Pent Rm) 2.2.7 IF AT ANY TIME ES actuation occurs, perform the following:

• Notify personnel to close 1CF-7 (CF to MWHUTs). (A-4-W Pent Rm)

• Close 1CF-3 (1A CFT SAMPLE & DRAIN) 2.2.8 WHEN 1A CFT is at desired level, lock closed 1CF-7 (CF to MWHUTs). (A-4-W Pent Rm) 2.2.9 Close 1CF-3 (1A CFT SAMPLE & DRAIN) 2.2.10 IF entered, evaluate exiting Technical Specification 3.6.3 Condition 'A' 2.2.11 Verify 1A CFT level and pressure stable 2.3 IF required to decrease level in 1B CFT, perform the following: (N/A) 2.4 Close 1CF-38 (CFT Drn to MWHUT Blk) (A-4-W Pent Rm)

This event is complete when 1CF-38 is closed (Step 2.4), or when directed by the Lead Examiner.

Page 3 of 75

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

Description:

Increase Power to 3% and Place ICS in Auto (R: OATC, SRO)

Time Position Applicant's Actions or Behavior Examiner Note: During the power increase, the Unit 1 CRS will assume the role of the dedicated Reactivity Management SRO.

SRO OP/1/A/1102/001 Encl 4.7 Crew Response:

• SRO directs the OATC to increase power to 3% using OP/1/A/1102/001 (Controlling Procedure for Unit Startup), Encl. 4.7, starting at step 3.36 OP/1/A/1102/001 (Controlling Procedure for Unit Startup) Encl. 4.7 Step 3.36 rev 310 NOTE:

• Point Of Adding Heat (POAH) is normally achieved from 0.05 to 0.15% power on Wide Range Indications

• When POAH is achieved: TBVs will begin to open, 1HP-120 will begin to close, TAVE will increase, and SUR will decrease with negative Moderator Temperature Coefficient

• Wide Range indications are used since Source Range NIs saturate 3.36 Begin reactor power increase to 0.5 - 1.0 % at 0.5 DPM SUR OATC 3.37 WHEN above POAH, begin reactor power increase to 2.5 - 3.5%

3.38 WHILE power increases, begin increasing 1HP-120 (RC VOLUME CONTROL) setpoint to establish 215" to 225" PZR Level NOTE:

• TAVE error is blocked when on Low Level Limit and TAVE is

< setpoint

• Core reactivity effects are minimized with Rx in automatic 3.39 WHEN at 2.5 - 3.5 % Power, perform the following: (R.M.)

3.39.1 Place REACTOR MASTER to "AUTO" 3.39.2 Place DIAMOND to "AUTO" 3.39.3 Ensure TURBINE MASTER Setpoint to 880 - 890 psig 3.40 Perform the following:

• Ensure complete Enclosure "Prior To Entry Into MODE 1" of PT/1/A/0630/001 (Mode Change Verification)

• Review mechanical maneuvering rates and allowable ramp rates in PT/0/A/1103/020 (Power Maneuvering Guidelines)

This event is complete when power is 3% and ICS is in Auto (Step 3.39), or when directed by the Lead Examiner.

Page 4 of 75

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

Description:

Increase Power to 3% and Place ICS in Auto (R: OATC, SRO)

Time Position Applicant's Actions or Behavior OP/1/A/1102/001 Encl 4.7 Crew Response:

OATC 3.41 IF AT ANY TIME all the following:

• All operable T Cold indications > 550°F

• SSF inoperable only due to low decay heat, Notify SM the SSF is Available for Unit 1 SM notified:______________________ Time/Date:_______________

3.42 Ensure acceptable point status for plant startup for MODE 1:

• OAC Alarm Screen Review

• OAC Point Processing Log NOTE: OAC Points can be found on Turn-On Code FDW02 3.43 Set temporary alarms on the following:

• OAC Point O1E2129 (FDW LOOP A COMPOSITE VALVE DEMAND) temporary alarm set at 9.8%

• OAC Point O1E2130 (FDW LOOP B COMPOSITE VALVE DEMAND) temporary alarm set at 9.8%

• Note on Turnover sheet temporary alarms set on Composite Valve Demand This event is complete when power is 3% and ICS is in Auto (Step 3.39), or when directed by the Lead Examiner.

Page 5 of 75

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

Description:

1B FWPT Auxiliary Oil Pump Trip (C: BOP, SRO)

Time Position Applicant's Actions or Behavior Plant Response:

• 1SA-8/B-7 FWPT B HYDRAULIC PRESSURE LOW

• 1SA-8/C-6 FWPT B EMERGENCY OIL PUMP RUN in alarm

• FWPT B Emergency Oil Pump starts Crew Response:

SRO/BOP SRO will direct the BOP to refer to 1SA-08/C-6 1SA-08/C-3 1SA-08/C-6 FWPT B EMERGENCY OIL PUMP RUN rev 36 3.1 Verify that 1B FWPT emergency oil pump is running 3.2 IF applicable, verify 1B FWPT is still on turning gear [It will be]

3.3 Try to restart 1B FWPT auxiliary oil pump [It will fail to start]

3.4 IF restart fails, notify Maintenance for repairs Booth Cue: Approximately 2 minutes after firing timer 3, Timer 12 will auto actuate which will trip the Emergency Oil Pump and cause 1SA-08/C-7, (FWPT B EMERGENCY OIL PUMP OVERLOAD) to alarm.

Booth Cue: If dispatched as an AO to investigate 1B FWPT, notify crew that all oil pumps are off and the FDWPT is on the turning gear. Report that the TG motor is much noisier than normal.

1SA-08/C-7 1SA-08/C-7 FWPT B EMERGENCY OIL PUMP OVERLOAD 3.1 IF available, start Auxiliary Oil Pump and stop Emergency Oil Pump 3.2 IF AOP is NOT available, stop Turning Gear Motor and emergency Bearing Oil Pumps 3.3 Notify Maintenance for repairs 3.4 As soon as EBOP OR Auxiliary Oil Pump becomes available, start pump and place Turbine on Turning Gear This event is complete when Turning Gear Motor is secured, or as directed by the Lead Examiner.

Page 6 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 4 Event No.: 4 Page 1 of 8 Event

Description:

1A Letdown Cooler Leak (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior Plant Response:

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

• 1SA-09/D-1 (COMPONENT COOLING SURGE TANK HIGH/LOW)

Crew Response:

SRO/ BOP The SRO will direct the BOP to refer to ARG 1SA-08/B-9 1SA-08/B-9 1SA-08/B-9 rev 36 3.1.1 Determine radiation monitors in alarm.

3.1.2 IF radiation monitoring data from PMC is NOT in service, refer to OP/1/A/1103/026, (Loss of Sorrento Radiation Monitor).

Examiner Note: Steps 3.2 through 3.11 are IF statements for which RIA is in alarm. In this case, the crew determines the radiation monitor alarming is 1RIA-50, so step 3.4 applies 3.4 IF any of the following RIAs have valid alarms, GO TO AP/18 (Abnormal Release of Radioactivity).

1RIA-50 AP/1/A/1700/018 AP/1/A/1700/018 Abnormal Release of Radioactivity rev 23 (Can be performed by Unit 2 if AP/2 has been entered) 4.1 Perform the following:

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

Notify Shift Manager to reference the following:

• RP/0/A/1000/001 (Emergency Classification).

• NSD-202 (Reportability)

• OMP 1-14 (Notifications) 4.2 GO TO appropriate sections for any monitors in High or Alert alarm:

Examiner Note: Crew should go to Section 4I for 1RIA-50.

This event is complete when 1A Letdown cooler has been isolated or as directed by the Lead Examiner.

Page 7 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 4 Event No.: 4 Page 2 of 8 Event

Description:

1A Letdown Cooler Leak (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior SRO /BOP AP/1/A/1700/018 Crew Response:

AP/1/A/1700/018 Section 4I 1 Verify either of the following:

• CC SURGE TANK increasing 5/hour

• CC SURGE TANK off-scale high

2. Initiate AP/2 (Excessive RCS Leakage)

Examiner Note: Crew may enter AP/2 directly because the following entry condition is met: Reactor Coolant leakage into CC system at 5/hour on CC Surge Tank ( 0.65 gpm) or CC Surge Tank level off-scale high AP/1/A/1700/002 AP1/A/1700/002 (Excessive RCS Leakage) rev 15 Immediate Actions 3.1 Verify HPI operating 3.2 IAAT RC makeup flow is > 100 gpm, AND Pzr level is decreasing, THEN close 1HP-5 3.3 IAAT all the following exist:

• RCS leakage > NORMAL MAKEUP CAPABILITY (160 gpm) with letdown isolated

• Pzr level decreasing

• SG Tube Leakage NOT indicated

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

A. Ensure Rx is tripped B. Initiate Unit 1 EOP This event is complete when 1A Letdown cooler has been isolated or as directed by the Lead Examiner.

Page 8 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 4 Event No.: 4 Page 3 of 8 Event

Description:

1A Letdown Cooler Leak (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/002 Crew Response:

AP/1/A/1700/002 Subsequent Actions SRO /BOP NOTE Other than a SGTR, 1HP-26 should NOT need be open with the Rx critical.

4.1 Initiate Pzr and LDST level makeup using Unit 1 EOP Encl 5.5 (Pzr and LDST Level Control), as necessary (Page 44) 4.2 Announce AP entry using the PA system NOTE LPI DHR in service means that prior to the event the unit was shutdown with the decay heat drop line aligned for decay heat removal operation.

4.3 IAAT LPI DHR in service, AND RCS leakage > LDST makeup capability, THEN GO TO AP/26 (Loss of Decay Heat Removal) [N/A]

4.4 Initiate the following notifications:

__ OSM to reference the following:

• RP/0/A/1000/001 (Emergency Classification)

• OMP 1-14 (Notifications)

• Encl 5.9 (Oversight Guidelines)

__ STA

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

• "T6 AP02"

• "T6 WASTE"

• RIAs 4.6 Verify specific leak location is identified RNO: Notify WCC SRO to initiate Encl. 5.2 (Primary Leak Check) and of the leak area (AB or RB), if known This event is complete when 1A Letdown cooler has been isolated or as directed by the Lead Examiner.

Page 9 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 4 Event No.: 4 Page 4 of 8 Event

Description:

1A Letdown Cooler Leak (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior SRO /BOP AP/1/A/1700/002 Crew Response:

AP/1/A/1700/002 4.7 Initiate Encl 5.1 (Leak Rate Determination) (Page 13)

Examiner Note: This will calculate RCS leakage based on CC surge tank level increase and is a very gross calculation since there is no OAC point for CC surge tank level and therefore control room gauge must be used.

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

4.16 Verify all of the following:

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

• 1RIA-50 in alarm or increasing NOTE

• CC Surge Tank is hard piped to overflow to LAWT

• Chemicals from the CC system will rapidly exhaust demineralizers used to process LAWT water. Radwaste has limited storage capability and a Rx shutdown may be required if the leak CANNOT be isolated.

4.17 IAAT CC Surge Tank level is off-scale high, THEN notify Radwaste that the CC Surge Tank has overflowed to the LAWT NOTE

• Closing 1CC-7 and 1CC-8 will contain the RCS leak in the RB. Relief valves on the CC system will lift inside the RB when 1CC-7 and 1CC-8 are closed.

• 1CC-7 and 1CC-8 should be closed prior to letting RC to CC system leak fill the LAWT above the Hi/Hi OAC alarm (72 on O1A1352(Low Activity Waste Tank Level)).

• Flashing of the CC system may be indicated by CRD flow low or fluctuating, CC flow low or fluctuating, and RB Sump Level increase.

This event is complete when 1A Letdown cooler has been isolated or as directed by the Lead Examiner.

Page 10 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 4 Event No.: 4 Page 5 of 8 Event

Description:

1A Letdown Cooler Leak (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior SRO /BOP AP/1/A/1700/002 Crew Response:

AP/1/A/1700/002 4.18 IAAT RCS leakage is flashing the CC system, OR threatens to overflow the LAWT, THEN perform the following: (No flashing indicated)

A. Trip Rx B. Close 1HP-5 C. Close the following:

• 1CC-7

• 1CC-8

• 1CC-3

• 1CC-4

• 1CC-5

• 1CC-6 D. Initiate AP/32 (Loss of Letdown)

E. GO TO Step 4.24 NOTE RCS to CC leakage may be indicated by one RCP cooler outlet temperature increasing more than the others (use historical temperature trend) near the time of increase on 1RIA-50.

4.19 Verify leakage indicated by change in RCP cooler outlet temperatures (Turn-on code "GD AP02") [No leakage indicated]

RNO: GO TO Step 4.24 NOTE RCS leakage to CC in the letdown coolers may be indicated by a cooler outlet temperature increasing more than the other cooler. Due to CC system setup, letdown cooler CC outlet temperatures may be different. A historical OAC temperature trend may be required to determine if leakage exists and if actions taken are successful in leak isolation. If leaking cooler CANNOT be identified, the coolers will be isolated one at a time starting with the 1A Letdown Cooler.

4.24 Monitor letdown cooler outlet temperatures to determine which cooler is leaking (Turn-on code "GD AP02"):

• O1A0065 (LETDOWN COOLER 1A CC OUTLET TEMP)

• O1A0066 (LETDOWN COOLER 1B CC OUTLET TEMP)

This event is complete when 1A Letdown cooler has been isolated or as directed by the Lead Examiner.

Page 11 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No ILT16-2 Scenario No.: 4 Event No.: 4 Page 6 of 8 Event

Description:

1A Letdown Cooler Leak (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior SRO /BOP AP/1/A/1700/002 Crew Response:

AP/1/A/1700/002 4.25 GO TO the appropriate step to isolate affected cooler Letdown Cooler GO TO Step to be Isolated 1A 4.26 1B 4.33 Unknown 4.26 4.26 Verify 1B Letdown Cooler is isolated RNO: 1. Isolate the 1A Letdown Cooler by performing the following:

A. Close 1CC-1/1HP-1 B. Close 1HP-3

2. GO TO Step 4.31 4.31 Verify the leak isolation was successful:

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

• Decrease in RCS leakage 4.32 GO TO Step 4.44 4.44 Verify both the following are closed;

• 1CC-7

• 1CC-8 RNO: GO TO Step 4.46 4.46 WHEN conditions permit, THEN EXIT this procedure This event is complete when 1A Letdown cooler has been isolated or as directed by the Lead Examiner.

Page 12 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 4 Event No.: 4 Page 7 of 8 Event

Description:

1A Letdown Cooler Leak (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/002 SRO /BOP Crew Response:

AP/1/A/1700/002 Encl 5.1 (Leak Rate Determination)

1. Stabilize RCS Temperature

2. Notify WCC to secure all primary draining/RB washdown evolutions if applicable NOTE Depending on leak location, leakage may NOT be detected by all the formulas. One or more of the following methods may be necessary to determine RCS leak rate.

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

• Calculation of RCS Volume Loss:

Leak Rate = ______ + ______ - ______ - ______ = ______

MU SI LD TSR Where: MU = makeup Flow SI = Seal Inlet Hdr Flow LD = Letdown Flow TSR = Total Seal Return Flow

• LDST Level Change:

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

(minutes)

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

______minutes

• HAWT/LAWT Level Change: (Turn-on code LWD)

Leak Rate = (Change in HAWT/LAWT lvl) x (18 gal/inch) =(____inches) x 18 gal/inch =______ gpm (minutes)

• RBNS Level Change:

Leak Rate = (Change in RBNS level) x (15 gal/inch) = ( inches) x 15 gal/inch = ____ gpm (minutes) ____ minutes This event is complete when 1A Letdown cooler has been isolated or as directed by the Lead Examiner.

Page 13 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 4 Event No.: 4 Page 8 of 8 Event

Description:

1A Letdown Cooler Leak (C: BOP, SRO) (TS)

Time Position Applicant's Actions or Behavior AP/1/A/1700/002 Crew Response:

SRO /BOP

• RCS Leakage Calculation per PT/1/A/0600/010 (Reactor Coolant Leakage)

• Calculation of RCS Volume Loss:

Leak Rate = Makeup Flow rate with stable level = ____gpm NOTE Pressurizer 23.94 gal/inch Quench Tank: 34.94 gal/inch BWST: 7608 gal/foot SFP (Unit 1 & 2) 1512 gal/ 0.1 foot SFP/FTC (Unit 1&2) 2300 gal/inch Corer Flood Tank: 5 gal/ 0.01foot RB Normal Sump: 15 gal/inch LDST: 31.3 gal/inch CC Surge Tank Level: 7.8 gal/inch MWHUT: See OP/0.A/1108/001 (Curves and Gen Info)

• Tank Level Change:

Leak Rate = (Change level) x (Tank volume/height) = ( )x( ) = ____gpm (minutes) ____minutes

4. Notify OSM and SRO of calculated leak rate 3.4.13 RCS Operational Leakage SRO Condition A (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) Reduce leakage to within limits Examiner Note: TS will apply until the 1A Letdown Cooler is isolated This event is complete when 1A Letdown cooler has been isolated or as directed by the Lead Examiner.

Page 14 of 75

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

Description:

TD EFDWP oil sump dry (SRO) (TS)

Time Position Applicant's Actions or Behavior Plant response:

Simulator Operator call the Control Room as the WCC SRO and report that the Basement AO found the Unit 1 TD EFDWP oil sump with no oil indicating on the dipstick. Report that the WCC and FIN-24 are investigating the situation to determine the cause of the problem. No oil SRO has been found leaking from any equipment.

Crew response:

• SRO should make the decision to place TD EFDWP in Pull to Lock TS 3.3.14 EMERGENCY FEEDWATER (EFW) PUMP INITIATION CIRCUITRY (apples when the TD EFDWP is placed in PTL)

Condition B.1 (Immediately) Declare the affected EFW pump inoperable.

TS 3.7.5 EMERGENCY FEEDWATER (EFW) SYSTEM Condition B.1 (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) Restore turbine driven EFW pump and EFW flow path to OPERABLE status.

• SRO refer to TS 3.3.14 Condition B

• Declare the affected EFWP inoperable Immediately

• SRO refer to TS 3.7.5 Condition B Restore TD EFDWP within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Booth Cue: If asked, inform crew that the TD EFDWP was placed on the oil purifier last shift.

Examiner Note: The SRO may direct an RO to place the TD EFDW pump in Pull-To-Lock per AD-OP-ALL-1000 Step 5.6.3.3.b 5.6.3 Common Tasks

3. Written procedures are not necessary for situations where:

b. Prompt action is necessary to prevent the deterioration of plant conditions or components to a possibly unsafe or unstable level. If time permits, approval from the SM/CRS shall be obtained.

Booth Cue: If crew does not place TD EFDWP in PTL, then at direction of Lead Examiner, call as WCC SRO and direct the crew to place Unit 1 TDEFDWP switch in PTL per R&R.

Examiner Note: Ensure the Pzr is saturated prior to initiating Event 6.

This event is complete when the Tech Spec determination has been made or when directed by the Lead Examiner.

Page 15 of 75

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

Description:

Spray Valve Fails Open (C: OATC, SRO)

Time Position Applicant's Actions or Behavior Examiner Note: Ensure Pzr saturated prior to Event 6.

AP/1/A/1700/044 Plant Response:

• 1RC-1 indicates open

• OAC alarm indicating 1RC-1 is open

• RCS pressure decreasing Crew Response:

• OATC should recognize that RCS pressure is below the Pzr Spray Valve SRO/OATC setpoint and close the Pzr Spray Block Valve (1RC-3). This is an Immediate Action from AP/44 Abnormal Pressurizer Pressure Control.

• SRO should enter AP/1/A/1700/044 AP/1/A/1700/044 Abnormal Pressurizer Pressure Control rev 04 Immediate Manual Actions 3.1 IAAT PORV is open, AND RC pressure is < setpoint (2400 psig (HIGH) or 480 psig (LOW)), THEN close 1RC-4 3.2 IAAT RC pressure < 2155 psig, AND 1RC-1 indicates open, THEN select 1RC-1 to CLOSE 3.3 IAAT all the following conditions exist:

CT-1 __ RC pressure < 2155 psig

__ RC pressure decreasing without a corresponding decrease in PZR level THEN close 1RC-3 Subsequent Actions 4.1 Announce AP entry using the PA system 4.2 GO TO the applicable step per the following table:

Failure Caused Step RCS Pressure Decrease 4.3 Increase 4.18 This event is complete when 1RC-3 is closed and RCS pressure is stable, or as directed by the Lead Examiner.

Page 16 of 75

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

Description:

Spray Valve Fails Open (C: OATC, SRO)

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

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

A. Dispatch an operator to open 1DIB Panelboard breaker #24 B. Manually trip the reactor C. Initiate AP/02 (Excessive RCS Leakage) 4.4 Verify 1RC-3 is closed NOTE 1RC-3 must NOT be allowed to be closed for 36 minutes at a time to avoid a thermal transient in piping between 1RC-3 and the PZR spray nozzle.

4.5 Position 1RC-3 as required to maintain RC pressure within desired band 4.6 GO TO Step 4.13 4.13 Verify PZR heaters maintaining RCS pressure within desired band 4.14 Notify SPOC to repair malfunctioning component This event is complete when 1RC-3 is closed and RCS pressure is stable, or as directed by the Lead Examiner.

Page 17 of 75

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

Description:

Spray Valve Fails Open (C: OATC, SRO)

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

4.15 Ensure requirements of following are met:

SRO/OATC

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

__ TS 3.4.9 (Pressurizer)

__ TS 3.4.12 (Low Temperature Overpressure Protection System)

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

__ 1RC-1

__ 1RC-3

__ 1RC-4

__ PZR heater bank #1

__ PZR heater bank #2

__ PZR heater bank #3

__ PZR heater bank #4 This event is complete when 1RC-3 is closed and RCS pressure is stable, or as directed by the Lead Examiner.

Page 18 of 75

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

Description:

Two Dropped Control Rod(s) Requiring a Reactor Trip (C: OATC, SRO)

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

SRO/OATC

• Group 6 Rod 3 drops into the core

• Group 6 Rod 6 drops into the core

• Statalarm 1SA-2/A-10 (CRD GLOBAL TROUBLE)

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

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

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

• Statalarm 1SA-5/B-5 (1B RPS TROUBLE)

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

Crew Response:

• Crew should recognize 2 dropped control rods and trip the reactor in accordance with OMP 1-18 Examiner Note: Event 8 will auto actuate when the Reactor is tripped.

If the crew does not recognize the 2nd dropped control rod, they will enter AP/1/A/1700/001 (Unit Runback)

AP/1/A/1700/001 (Unit Runback) rev15 NOTE

• If more than one runback condition exists, ICS will respond by selecting the fastest runback rate and the lowest load limit. The most limiting runback will be the one with the fastest runback rate and the shortest duration.

• It is possible for a FDWP to become unable to feed the SGs but not be tripped. In this case a signal would not be sent to RPS or the EFDWP start circuit.

4.1 GO TO the most limiting section per the following table:

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

AP/1A/1700/001 Section 4H (Asymmetric Control Rod)

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

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

This event is complete when the Reactor is manually tripped, or as directed by the Lead Examiner.

Page 19 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 4 Event No.: 8 Page 1 of 10 Event

Description:

1A MSLB inside containment (M: All)

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

• 1SA-2/D-3 (RC Press High/Low)

• 1SA-02/A-9 (MS PRESS HIGH/LOW)

Crew Response:

Examiner Note: Crew will be performing IMAs and Subsequent Actions as a result of the manual Reactor trip due to two dropped control rods.

IMAs OATC EOP Immediate Actions rev 01 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.

BOP SYMPTOM CHECK The BOP will verify the following:

Power Range NIs NOT < 5% Rule 1, ATWS/Unanticipated Nuclear Power Power Range NIs NOT decreasing Production Any SCM < 0°F Rule 2, Loss Of SCM Loss of Main and Emergency FDW Rule 3, Loss of Main or Emerg FDW (including unsuccessful manual Rule 4, Initiation of HPI Forced Cooling initiation 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 identified Process monitor alarms (RIA-40, SG Tube Leakage > 25 gpm) 59,60),

Area monitor alarms (RIA-16/17)

BOP will perform Rule 5 (Main Steam Line Break) (page 27)

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

This event is complete when the crew has transferred to the FCD tab, or as directed by the Lead Examiner.

Page 20 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 4 Event No.: 8 Page 2 of 10 Event

Description:

1A MSLB inside containment (M: All)

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

SRO will review the Subsequent Action Tab Parallel Action (Yellow) page SRO/OATC (Page 72) and transfer to the Excessive Heat Transfer (EHT)Tab.

EHT Tab SRO will review the EHT Tab Parallel Action (Yellow) page (page 73) and determine that ES has actuated and direct the OATC to perform Encl. 5.1 ES Actuation (Page 52)

Excessive Heat Transfer (EHT) Tab rev 0

1. Verify any SG pressure < 550 psig.

[1A SG should be < 550 psig at this point]

2. Ensure Rule 5 (Main Steam Line Break) in progress or complete.

3. Place the following in HAND and decrease demand to zero on all affected SGs:

1A SG 1B SG 1FDW-32 1FDW-41 1FDW-35 1FDW-44

4. Close the following on all affected SGs:

1A SG 1B SG 1FDW-372 1FDW-382 1MS-17 1MS-26 1MS-79 1MS-76 1MS-35 1MS-36 1MS-82 1MS-84 1FDW-368 1FDW-369

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

6. IAAT core SCM is > 0°F, THEN perform Steps 7 and 8 RNO: GO TO Step 9

7. Throttle HPI per Rule 6 (HPI)

8. Verify letdown in service RNO: IF desired to restore letdown, THEN initiate Encl 5.5 (Pzr and LDST Level Control). (page 44)

This event is complete when the crew has transferred to the FCD tab, or as directed by the Lead Examiner.

Page 21 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 4 Event No.: 8 Page 3 of 10 Event

Description:

1A MSLB inside containment (M: All)

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

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

SRO/OATC [1B SG is intact]

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

10. Open the following on all intact SGs:

1A SG 1B SG 1FDW-372 1FDW-382 1FDW-368 1FDW-369 1MS-17 1MS-26

11. Start MDEFDWP associated with all intact SGs:

1A SG 1B SG 1A MDEFDWP 1B MDEFDWP

12. Feed and steam all intact SGs to stabilize RCS P/T using either:

• TBVs

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

Examiner Note: The crew should raise 1B SG level to 60 inches Extended Startup Range (ACC Level). ACC conditions are in effect due to RB pressure exceeding 3 psig.

13. GO TO Step 32

32. Verify any:

__ HPI has operated in the injection mode while NO RCPs were operating

__ A cooldown below 400°F at > 100°F/hr has occurred RNO: GO TO Step 34

33. Initiate Rule 8 (Pressurized Thermal Shock (PTS))

34. Verify both closed:

__ 1MS-24

__ 1MS-33 This event is complete when the crew has transferred to the FCD tab, or as directed by the Lead Examiner.

Page 22 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 4 Event No.: 8 Page 4 of 10 Event

Description:

1A MSLB inside containment (M: All)

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

35. Open 1AS-8 SRO/OATC

36. Close 1SSH-9

37. Perform notifications:

__ Notify Chemistry to determine RCS boron concentration

__ Notify Secondary Chemistry to check for indications of SGTR

__ Notify RP to check for indications of SGTR 38 IAAT RCS boron is determined to be insufficient for adequate SDM THEN initiate Encl 5.11 (RCS Boration)

39. IAAT all exist:

__ ES Bypass Permit satisfied

__ All SCMs > 0°F

__ RCS pressure controllable THEN perform Steps 40 - 41 RNO: GO TO Step 42

40. Bypass applicable ES:

To Bypass HPI:

__ Bypass HPI ES CH A,B,C To Bypass LPI:

__ Bypass LPI ES CH A,B,C

41. Bypass applicable Diverse ES:

To Bypass HPI:

__ Bypass Diverse HPI To Bypass LPI:

__ Bypass Diverse LPI

42. Verify any SG is dry.

NOTE

• Minimizing SCM reduces tensile stress on the SG

• PORV should be used if Pzr spray is not available

• Procedure progression may continue when actions to minimize SCM are in progress This event is complete when the crew has transferred to the FCD tab, or as directed by the Lead Examiner.

Page 23 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 4 Event No.: 8 Page 5 of 9 Event

Description:

1A MSLB inside containment (M: All)

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

43. Maintain minimum SCM using the following methods as necessary:

SRO/OATC __ De-energize all Pzr heaters

__ Use Pzr spray

__ Throttle HPI to maintain Pzr level > 100 [180 acc]

__ Use PORV

44. Verify any RCP operating RNO: GO TO Step 46.

45. Maintain RCP NPSH

• OAC

• Encl 5.18 (P/T Curves)

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

NOTE RCP 1A1 provides the best Pzr spray

47. IAAT all exist:

__ < one RCP operating in any loop

__ All SCMs > 0°F

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

48. IAAT all exist:

__ RBS actuated

__ RB pressure < 10 psig

__ 1RIA-57 NOT in alarm

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

49. IAAT Tcold approaches 470°F, AND all RCPs are operating, THEN ensure < four RCPs are operating

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

51. Verify all SCMs > 0°F This event is complete when the crew has transferred to the FCD tab, or as directed by the Lead Examiner.

Page 24 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 4 Event No.: 8 Page 6 of 10 Event

Description:

1A MSLB inside containment (M: All)

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

52. Verify indications of SGTR 25 gpm.

SRO/OATC RNO: GO TO Step 54 54 Verify required RCS makeup flow within normal makeup capability

55. Verify either:

__ Any SG isolated

__ Any SG has an unisolable steam leak

56. GO TO FCD tab Forced Cooldown Tab Rev 0

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

• Tcold 270°F: 50°F / 1/2 hr

• Tcold < 270°F: 25°F / 1/2 hr THEN GO TO EHT tab

2. Verify letdown in service RNO: 1. Ensure CC System in operation

2. IF 1A Letdown Cooler available, THEN open the following:

__ 1HP-1

__ 1HP-3

3. IF 1B Letdown Cooler available, THEN open the following:

__ 1HP-2

__ 1HP-4

4. Close the following:

__ 1HP-6

__ 1HP-7

5. Open 1HP-5

6. Adjust 1HP-7 for 20 gpm letdown

7. Open 1HP-6

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

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

4. IAAT Tcold approaches 470°F, THEN ensure < four RCPs operating This event is complete when the crew has transferred to the FCD tab, or as directed by the Lead Examiner.

Page 25 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 4 Event No.: 8 Page 7 of 10 Event

Description:

1A MSLB inside containment (M: All)

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

5 IAAT Tcold approaches 300°F, THEN ensure < three RCPs operating SRO/OATC

6. IAAT all the following exist:

__ ES Bypass Permit satisfied

__ All SCMs > 0°F

__ RCS pressure controllable THEN perform Steps 7 - 8

7. Bypass applicable ES:

To Bypass HPI:

__ Bypass HPI ES CH A,B,C To Bypass LPI:

__ Bypass LPI ES CH A,B,C

8. Bypass applicable Diverse ES:

To Bypass HPI:

__ Bypass Diverse HPI To Bypass LPI:

__ Bypass Diverse LPI

9. IAAT any SG is < 700 psig, AND AFIS is NOT actuated on that SG, THEN select OFF on both Digital Channels 1&2 for that header:

A Header B Header DIG CH 1 OFF DIG CH 1 OFF DIG CH 2 OFF DIG CH 2 OFF

10. Stabilize RCS temperature

11. Close 1HP-26

12. Stop 1C HPI pump

13. Adjust 1HP-120 for desired setpoint This event is complete when the crew has transferred to the FCD tab, or as directed by the Lead Examiner.

Page 26 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 4 Event No.: 8 Page 8 of 10 Event

Description:

1A MSLB inside containment (M: All)

Time Position Applicant's Actions or Behavior RULE 5 Crew Response:

Rule 5 (Main Steam Line Break) rev 01 BOP

1. Perform on affected headers:

A Header B Header CT-2 On AFIS HEADER A, On AFIS HEADER B, depress CH. 1 INIT. depress CH. 1 INIT.

On AFIS HEADER A, On AFIS HEADER B, depress CH. 2 INIT. depress CH. 2 INIT.

Select OFF for Select OFF for 1A MD EFDWP. 1B MD EFDWP.

Trip both Main Trip both Main FDWPTs. FDWPTs.

Close 1FDW-315. Close 1FDW-316.

Place 1FDW-33 Place 1FDW-42 switch switch to CLOSE. to CLOSE.

Place 1FDW-31 Place 1FDW-40 switch switch to CLOSE. to CLOSE.

Close 1PSW-22. Close 1PSW-24.

Close 1PSW-23. Close 1PSW-25.

2. Verify 1 TD EFDW PUMP operating.

RNO: 1. IF MD EFDWP for the intact SG is operating, THEN GO TO Step 5. [IT WILL BE OPERATING]

2. Start 1 TD EFDW PUMP

3. Verify 1 TD EFDW PUMP is feeding affected SGs

[1FDW-315 is closed]

RNO: GO TO Step 5

5. Verify 1B SG is an affected SG RNO: GO TO Step 7 This event is complete when the crew has transferred to the FCD tab, or as directed by the Lead Examiner.

Page 27 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 4 Event No.: 8 Page 9 of 10 Event

Description:

1A MSLB inside containment (M: All)

Time Position Applicant's Actions or Behavior RULE 5 Crew Response:

7. WHEN overcooling is stopped, THEN adjust steaming of unaffected SG BOP to maintain CETCs constant using either:

__ TBVs

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

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

8. WHEN all exist:

__ Core SCM > 0°F

__ Rx power 1%

__ Pzr level increasing THEN continue

9. Verify ES HPI actuated

10. Place Diverse HPI in BYPASS

11. Perform both:

__ Place ES CH 1 in MANUAL

__ Place ES CH 2 in MANUAL

12. Perform the following to stabilize RCS P/T:

__ Throttle HPI

__ Reduce 1HP-120 setpoint to control at >100 [180 acc]

__ Adjust steaming of unaffected SG as necessary to maintain CETCs constant

13. WHEN CETCs have stabilized, THEN resume use of Tc for RCS temperature control

14. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete (Page 29)

15. Ensure Rule 8 (Pressurized Thermal Shock (PTS)) is in progress or complete

16. WHEN directed by CRS, THEN EXIT This event is complete when the crew has transferred to the FCD tab, or as directed by the Lead Examiner.

Page 28 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Op-Test No.: ILT16-2 Scenario No.: 4 Event No.: 8 Page 10 of 10 Event

Description:

1A MSLB inside containment (M: All)

Time Position Applicant's Actions or Behavior RULE 3 Rev 1 Crew Response:

Rule 3 (Loss of Main of Emergency FDW)

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

__ Turbine Building Flooding

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

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

AND any of the following exist:

__ RCS pressure reaches 2300 psig OR NDT limit

__ Pzr level reaches 375 [340 acc]

THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling)

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

5. Verify any EFDW pump operating

6. GO TO Step 38

38. IAAT an EFDW valve CANNOT control in AUTO, OR manual operation of EFDW valve is desired to control flow/level, THEN perform Steps 39 - 43 RNO: GO TO Step 44

44. Verify any SCM 0oF CAUTION ATWS events may initially require throttling to prevent exceeding pump limits and additional throttling once the Rx is shutdown to prevent overcooling RNO: IF overcooling, OR exceeding limits in Rule 7 (SG Feed Control),

THEN throttle EFDW, as necessary

45. IAAT Unit 1 EFDW is in operation, THEN initiate Encl 5.9 (Extended EFDW Operation) (page 30)

46. WHEN directed by CRS, THEN EXIT This event is complete when the crew has transferred to the FCD tab, or as directed by the Lead Examiner.

Page 29 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.9 Extended EFDW Operation Rev 1 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

1. __ Monitor EFDW parameters on EFW graphic display.

2. __ IAAT UST level is < 4',

THEN GO TO Step 120.

3. __ IAAT feeding both SGs with one __ GO TO Step 8.

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

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

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

5. Locally open:

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

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

6. Ensure a MD EFDWP is operating.

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

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

8. Perform as required to maintain UST level

> 7.5':

Makeup with demin water.

Place CST pumps in AUTO.

9. IAAT all exist:

Rapid cooldown NOT in progress

__ MD EFDWP operating for each available SG

__ EFDW flow in each header

< 600 gpm THEN place 1 TD EFDW PUMP switch in PULL TO LOCK.

Page 30 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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

11. __ Start TD EFDWP BEARING OIL COOLING PUMP.

NOTE

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

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

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

12. __ Notify CR SRO to set priority based on the NOTE above and EOP activities.

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

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

2. GO TO Step 20.

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

2. GO TO Step 41.

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

operating.{12}

2. __ GO TO Step 18.

17. Stop: {12}

1A COND BOOSTER PUMP 1B COND BOOSTER PUMP

18. Ensure only one HWP is operating.

19. GO TO Step 44.

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Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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

loss of the secondary system.

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

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

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

24. Place all HWP control switches to OFF.

25. Place all CBP control switches to OFF.

26. Place valve switches to close until valve __ Continue.

travel is initiated:

1FDW-4 1FDW-9

27. Start: Start as necessary:

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

__ 1B FDWP AUXILIARY OIL PUMP PUMP

__ 1B FDWP EMERGENCY BRNG OIL PUMP

28. Verify both: 1.__ IF both FDW pumps have BRG LUBE

__ FWPT A BRG LUBE OIL OIL PRESS < 4 psig, PRESS > 4 psig THEN GO TO Step 90.

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

Close 1FDW-1 for 1A FDW pump.

Close 1FDW-6 for 1B FDW pump.

29. Place in MANUAL and close:

1FDW-53 1FDW-65 Page 32 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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

31. Close 1C-10.

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

33. Start one HWP.

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

of condensate.

2. __ GO TO Step 90.

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

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

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

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

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

1FDW-53 1FDW-65

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

41. Start a second HWP.

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

43. Stop one operating HWP.

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

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

Page 33 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

46. __ Perform the following:

__ Position HWP LOAD SHED DEFEAT switch to a running HWP.

__ Position CBP LOAD SHED DEFEAT switch to a running CBP.

47. Place in MANUAL:

1FDW-53 1FDW-65

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

1FDW-53 1FDW-65

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

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

(T-1/J-23).

50. __ IAAT UST level increases > 11',

THEN perform as required:

Throttle demin water

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

(T-1/J-23)

51. Verify closed: GO TO Step 58.

1FDW-4 1FDW-9 Page 34 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

52. Position switches in CLOSE:

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

53. Ensure closed:

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

54. __ Locally open:

1FDW-5 (1A FDWP Discharge Bypass)

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

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

• O1A1014 (FDWP 1A DISCHARGE PRESS)

• O1A1391 (FDWP 1B DISCHARGE PRESS)

THEN open:

1FDW-4 1FDW-9 Page 35 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

56. Locally close:

__ 1FDW-5 (1A FDWP Discharge Bypass)

(T-1/SE of D-24 12' up)

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

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

57. Verify open: 1. __ IF required, notify the WCC SRO to

__ 1FDW-1 initiate investigation.

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

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

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

THEN EXIT.

Page 36 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

60. __ WHEN UST level is < 4',

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

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

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

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

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

Unlock and remove chain from 1C-573.

Establish communication with Control Room.

63. __ WHEN UST level is < 3',

THEN continue.

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

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

65. Stop all main vacuum pumps.

66. Stop all CBPs.

67. Stop all HWPs.

68. Close: Dispatch an operator to close:

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

__ 1MS-58 (1B CSAE Steam Supply)

(T-3/G-26)

__ 1MS-67 (1C CSAE Steam Supply)

(T-3/H-26)

Page 37 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE

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

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

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

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

70. Perform the following:

Stop 1A MD EFDWP.

Stop 1B MD EFDWP.

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

2. Close:

__ 1FDW-315

__ 1FDW-316

72. Perform the following:

A. __ Reduce MD EFDWP flow to

< 440 gpm per pump.

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

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

73. __ WHEN vacuum is broken, THEN continue.

Page 38 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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

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

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

2. __ IF NO EFDW pumps are operating, THEN:

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

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

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

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

to UST level < 1'.

77. Perform the following:

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

B. Resume feeding available SGs.

Page 39 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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

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

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

81. Stop 1 TD EFDW PUMP.

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

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

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

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

2. GO TO Step 84.

83. Open 1C-391. 1. Attempt to locally open 1C-391 (TD EFDWP Suction From Hotwell)

(T-1/C-20).

2. IF 1C-391 CANNOT be opened, AND NO EFDW pumps are operating, THEN:

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

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

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

Page 40 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.9 Extended EFDW Operation

84. IAAT 1 TD EFDW PUMP operation is desired, AND all exist:

Hotwell level is > 1.

Vacuum is broken.

1 TD EFDW PUMP successfully aligned to hotwell.

THEN:

A. Start 1 TD EFDW PUMP.

B. Feed available SGs as required.

85. Dispatch an operator to open:

1C-188 (Hotwell Emerg Makeup #1 Control Bypass) (T-1/W of E-24). {18}

1C-912 (UST Riser To HW Emerg Makeup #2 Auto Isol Bypass)

(T-1/G-23)

86. Notify TSC to evaluate methods to maintain secondary inventory including strategies located in EM 5.1 (Engineering Emergency Response Plan) and EM 5.2 (Evaluation By Station Management in the TSC -

Beyond Design Basis Mitigation Strategies).

Page 41 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.9 Extended EFDW Operation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

87. IAAT hotwell level is 1, THEN:

A. Stop all EFDWPs.

B. Consider all U-1 EFDW pumps inoperable, AND GO TO Rule 3.

NOTE

• This step provides general plant directions for the SRO and Management team. The user shall continue after the notification has been made.

• Swapping from TBVs to ADVs prevents overfilling the hotwell/condenser.

• Securing steam seals limits the water (condensation) that reaches the oil systems. Vacuum must be broken to secure steam seals.

• Engineering will determine when to allow secondary system restart.

• Beginning a cooldown assumes HPI is operating. If the SSF is supplying seals, then further discussion with the Management team should be undertaken prior to cooldown.

88. Notify the CR SRO to direct the following as time and resources allow:

• Transfer steam control from TBVs to ADVs.

• Operate ADVs per U1 EOP Encl 5.24 (Operation of ADVs).

• Begin Unit cool down to LPI per OP/1/A/1102/010 (Controlling Procedure For Unit Shutdown) using the ADVs.

• Break vacuum per OP/1-2/A/1106/016 (Condenser Vacuum System).

• Secure Steam Seals per OP/1/A/1106/13 (Steam Seal System).

89. WHEN directed by CR SRO, THEN EXIT.

Page 42 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Rule 6 Rev 1 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Page 43 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.5 Rev 1 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 44 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.5 Pzr and LDST Level Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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

THEN perform Steps 7 - 9.

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

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

• 1HP-25 A. Start 1A LPI PUMP.

B. Start 1B LPI PUMP.

C. Open:

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

E. __ Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, U1 LPI Hatch Rm, N end).

F. GO TO Step 8.

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

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

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

C. GO TO Step 9.

Page 45 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 46 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 47 of 75

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

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

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Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 50 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 51 of 75

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

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Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 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.

__ GOTO Step 16.

12. Verify any RCP is operating.

13. Open:

__ 1CC-7

__ 1CC-8

__ 1LPSW-15

__ 1LPSW-6

14. __ Ensure only one CC pump operating.

15. __ Ensure Standby CC pump in AUTO.

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Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 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.

Page 54 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 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

__ B OUTSIDE AIR BOOSTER FAN

29. Notify Unit 3 to start:

__ 3A OUTSIDE AIR BOOSTER FAN

__ 3B OUTSIDE AIR BOOSTER FAN Page 55 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 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:

__ 1HP-228

__ 1HP-226

__ 1HP-232

__ 1HP-230

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.

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Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 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 57 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 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 58 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Unit Status ES Channels 3 & 4 have NOT actuated.

54. Start:

__ A OUTSIDE AIR BOOSTER FAN

__ 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:

__ 1HP-228

__ 1HP-226

__ 1HP-232

__ 1HP-230

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.

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Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 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 ***

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Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 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.

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Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 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 62 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 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 63 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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

79. Open:

__ 1HP-20

__ 1HP-21

80. __ IAAT ES Channels 5 and 6 is actuated, __ GOTO Step 86.

THEN perform Steps 81 - 85.

81. Perform the following for actuated channels: 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.

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Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 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 65 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 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.

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.

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Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 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:

__ 1HP-228

__ 1HP-226

__ 1HP-232

__ 1HP-230

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 67 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 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 116.

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 68 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 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 69 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 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:

__ 1HP-228

__ 1HP-226

__ 1HP-232

__ 1HP-230

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 70 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam Enclosure 5.1 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 71 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 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 (Notifications/Reportability Evaluation).

Page 72 of 75

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

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

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

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

4. Any SCM = 0°F AND HPI forced IF LOSCM tab has NOT been entered due LOSCM cooling NOT in progress to current EHT event THEN GO TO LOSCM tab.

5. Both SGs intentionally isolated to RETURN TO beginning of EHT tab.

stop excessive heat transfer after EHT tab initiated LOHT

6. Loss of heat transfer AND at least one SG NOT isolated GO TO LOHT tab.

7. Indications of excessive RETURN TO beginning of EHT tab. EHT heat transfer in another SG after EHT tab initiated

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

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

10. Power lost to all 4160V SWGR

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

re-energized ROP

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

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

OR SGTR .> 25 gpm

12. Individual available to make

• Announce plant conditions using notifications PA system.

• Notify OSM to reference the NOTIFY Emergency Plan and AD-LS-ALL-0006 (Notification /Reportability Evaluation).

Page 73 of 75

Appendix D Required Operator Actions Form ES-D-2 ILT16-2 NRC Exam CRITICAL TASKS CT-1 The PZR Spray Valve (1RC-1) must be isolated by closing 1RC-3 to stop the RCS pressure decrease to prevent a reactor trip.

CT-2 Manually isolate Feedwater to the 1A SG prior to entering PTS conditions (per Rule 8, a cooldown below 400°F at > 100°F/hour) to prevent overcooling the RCS and Reactor Core.

Page 74 of 75

SAFETY: Take a Minute UNIT 0 (OSM)

SSF Operable: Yes KHU's Operable: U1 - OH, U2 - LCTs Operable: 2 Fuel Handling: No for Units 2 and 3 UG UNIT STATUS (CR SRO)

Unit 1 Simulator Other Units Mode: 2 Unit 2 Unit 3 Reactor Power: Below POAH Mode: 1 Mode: 1 Gross MWE: 0 100% Power 100% Power RCS Leakage: 0.01 gpm EFDW Backup: Yes EFDW Backup: Yes No WCAP Action RBNS Rate: 0.01 gpm Technical Specifications/SLC Items (CR SRO)

Component/Train OOS Restoration TS/SLC #

Date/Time Required Date/Time SSF 2 days ago / 0400 5 days / 0400 TS 3.10.1 Cond A,B,C,D,E Shift Turnover Items (CR SRO)

Primary

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

• 1RIA-3 and 5 removed from RB.

• After turnover, the BOP is to lower 1A CFT level to 13 ft per OP/1/A/1104/001, Encl. 4.17. Then OATC is to continue in OP/1/A/1102/001 Encl 4.7 to increase Rx power.

• Increase Reactor power to 3% per OP/1/A/1102/001 Encl. 4.7 beginning at step 3.36. Once Rx power is 3% and step 3.39 is complete, hold further power increase and CRS return to oversight role until Rx Engineering updates the maneuvering plan.

• During the Reactor power increase, Unit 2 CRS will assume the oversight role for Unit 1.

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

Secondary

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

Reactivity Management (CR SRO)

Gp 7 Rod Position:

RCS Boron 1778 ppmB Batch additions as required per maneuvering plan 5% Withdrawn Human Performance Emphasis (SM)

Procedure Use and Adherence

RO-101b a Page 1 of 14 REGION II JOB PERFORMANCE MEASURE RO-101b ALIGN EMERGENCY BORATION DURING AN ATWS Alternate Path: Yes Alt Path Failure: HP-24/25 failed / A LPI pump failed / C HPI pump failed_____________________

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

Reviewed By: Date:

Approved By: Date:

RO-101b a Page 2 of 14 REGION II JOB PERFORMANCE MEASURE Task Title : Align Emergency Boration During an ATWS Task Number : N/A Alternate Path: Yes Time Critical: No Validation Time: 10 minutes K/A Rating(s):

System: BW/E13 K/A: EA 1.1 Rating: 3.4/3.2 Task Standard:

Candidate aligns emergency boration during an ATWS per Rule 1 (ATWS)

References:

EP/1/A/1800/001, Rule 1 (ATWS) (Rev. 0L)

Tools/Equipment/Procedures Needed:

EP/1/A/1800/001, Rule 1 (ATWS) (Rev. 0L)

=========================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

RO-101b a Page 3 of 14 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS

1. RECALL SNAP 211

2. IMPORT FILES for RO-101b

3. Go to RUN to acknowledge alarms

4. RESET flags on HPIPs / LPIPs

5. Go to FREEZE

6. ENSURE clean copy of Rule 1 in place on Control Board

7. Go to RUN when directed by Lead Examiner

RO-101b a Page 4 of 14 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS Unit 1 is at 100% power The CRS has determined that the reactor needs to be tripped INITIATING CUES The CRS directs you to trip the reactor and perform Immediate Manual Actions (IMAs).

RO-101b a Page 5 of 14 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP Depress REACTOR TRIP pushbutton.

STANDARD: Candidate performs EOP IMAs from memory (per ___ SAT OMP 1-18) and depresses the REACTOR TRIP pushbutton located on UB1.

1 Candidate continues to Step 2.

1 ___ UNSAT IMAs COMMENTS:

Verify reactor power < 5% FP and decreasing.

___ SAT STANDARD: Candidate performs EOP IMAs from memory and verifies reactor power < 5% and decreasing and 2 determines that reactor power is > 5% on all NIs.

2 ___ UNSAT IMAs Candidate performs Step 2 RNO.

COMMENTS:

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

___ SAT STANDARD: Candidate refers to Rule 1 Step 1.

2 3 RNO COMMENTS: ___ UNSAT IMAs

RO-101b a Page 6 of 14 Verify any Power Range NI 5% FP.

STANDARD: Candidate verifies any Power Range NI 5% FP and ___ SAT determines that all Power Range NIs are > 5% FP.

4 1 Candidate continues to Step 2.

___ UNSAT COMMENTS:

Initiate manual control rod insertion to the IN LIMIT. CRITICAL STEP STANDARD: Candidate initiates a manual control rod insertion by depressing the Manual pushbutton on the Diamond control panel and then locks the Control Rod Joystick

___ SAT in the INSERT (forward) position.

5 2 Candidate continues to Step 3.

___ UNSAT COMMENTS:

Verify Main FDW is feeding the SGs.

STANDARD: Candidate determines Main FDW is feeding the SGs. ___ SAT Candidate continues to Step 4.

6 3

___ UNSAT COMMENTS:

Notify CRS to GO TO UNPP tab STANDARD: Candidate notifies the CRS to go to the UNPP tab of ___ SAT the EOP.

7 4 Candidate continues to Step 5.

___ UNSAT COMMENTS:

RO-101b a Page 7 of 14 Open the following:

__ 1HP-24

___ SAT

__ 1HP-25 STANDARD: Candidate locates 1HP-24 and 1HP-25 on 1UB1 and rotates the switches to the open position. Candidate ___ UNSAT determines 1HP-24 and 1HP-25 do not open by 8 5 observing the green closed lights illuminated and the red open lights off.

Candidate continues to step 5 RNO.

COMMENTS:

ALTERNATE PATH IF both are closed:

___ SAT

__ 1HP-24

__ 1HP-25

___ UNSAT THEN GO TO Step 32.

5 9

RNO STANDARD: Candidate determines 1HP-24 and 1HP-25 are both closed by observing the green closed lights illuminated and the red open lights off.

Candidate continues to step 32.

COMMENTS:

RO-101b a Page 8 of 14 Dispatch one operator without wearing Arc Flash PPE to open 600V CRD breakers:

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

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

___ UNSAT STANDARD: Candidate dispatches one operator to open Unit 1 normal and alternate CRD feeder breakers without wearing Arc Flash PPE.

10 32 Candidate continues to Step 33.

BOOTH CUE: FIRE TIMER 01 to trip normal and alternate CRD breakers after 4 minute delay.

COMMENTS:

Start 1A LPI Pump.

___ SAT STANDARD: Candidate rotates the Control Switch for 1A LPI Pump to the start position. Candidate determines the 1A LPI Pump did not start by observing the red ON lights are off and/or 0 amps are indicated on the amp meter. ___ UNSAT 11 33 Candidate continues to Step 33 RNO.

COMMENTS:

1. *Start 1B LPI Pump. *CRITICAL

2. IF NO LPI pumps are operating, THEN:

STEP

a. __Open 1LP-6

b. __Open 1LP-7

c. __Start 1C LPI pump

___ SAT STANDARD: Candidate rotates the Control Switch for 1B LPI Pump to the start position. Candidate determines the 1B LPI ___ UNSAT 33 Pump starts by observing the red ON lights are 12 illuminated and/or amps are indicated on the amp RNO meter.

COMMENTS:

RO-101b a Page 9 of 14 Open: *CRITICAL

__*1LP-15 STEP

__*1LP-16

__*1LP-9 ___ SAT

__*1LP-10

__1LP-6 ___ UNSAT

__1LP-7 STANDARD: Candidate rotates the control switch for 1LP-15 to the open position and verifies the green closed light off and the red open light illuminated.

Candidate rotates the control switch for 1LP-16 to the open position and verifies the green closed light off and the red open light illuminated.

Candidate rotates the control switch for 1LP-9 to the open position and verifies the green closed light off and the red open light illuminated.

13 34 Candidate rotates the control switch for 1LP-10 to the open position and verifies the green closed light off and the red open light illuminated.

Candidate rotates the control switch for 1LP-6 to the open position and verifies the green closed light off and the red open light illuminated.

Candidate rotates the control switch for 1LP-7 to the open position and verifies the green closed light off and the red open light illuminated.

Examiner Note: The Critical step is to align sufficient valves to supply one header for HPI pump suction

[minimum of 1LP-9, 1LP-10, and (1LP-15 OR 1LP-16)].

COMMENTS:

RO-101b a Page 10 of 14 Dispatch an operator to open 1HP-363 (Letdown Line to LPI Pump Suction Block) (A-1-119, U1 LPI Hatch Area, 28 W of North door).

___ SAT STANDARD: Operator is dispatched to open 1HP-363.

___ UNSAT 14 35 BOOTH CUE: Use manual valves program to open 1HP-363.

COMMENTS:

Ensure at least one operating:

__ 1A HPI PUMP

__ 1B HPI PUMP ___ SAT STANDARD: Candidate ensures either the 1A or 1B HPI pump is ___ UNSAT operating.

15 36 Candidate continues to Step 37.

NOTE: The 1A HPI Pump is operating.

COMMENTS:

Start 1C HPI PUMP.

___ SAT STANDARD: Candidate rotates the 1C HPI pump switch to the CLOSE position and determines the pump did not start by observing the white open light illuminated and the ___ UNSAT red closed lights OFF and/or amps indicating 0 on the amp meter.

16 37 Candidate continues to Rule 1 Step 37 RNO.

COMMENTS:

RO-101b a Page 11 of 14

1. __ Start standby HPI pump. CRITICAL

2. __ IF at least two HPI pumps are operating, STEP THEN open 1HP-409.

___ SAT STANDARD: Candidate rotates the 1B HPI pump switch to the CLOSE position and determines the pump started by observing the white open light OFF and the red closed ___ UNSAT lights illuminated and/or amps indicated on the amp meter.

37 17 Candidate determines two HPI pumps are operating RNO and opens 1HP-409 by rotating the switch to the open position and verifying the green closed light off and the red open light illuminated.

Candidate continues to Rule 1 Step 38.

COMMENTS:

Open the following: *CRITICAL

__ *1HP-26 STEP

__ 1HP-27

___ SAT STANDARD: Candidate rotates the control switch to the open position for 1HP-26 and verifies the green closed light off and the red open light illuminated. (critical) ___ UNSAT 18 38 Candidate determines that 1HP-27 is already open Candidate continues to Step 39.

COMMENTS:

RO-101b a Page 12 of 14 Verify only two HPI pumps operating.

STANDARD: Candidate verifies two HPI pumps are operating by ___ SAT verifying the red ON lights are illuminated for the 1A and 1B HPI pumps and/or verify HPI pump motor

___ UNSAT amps are indicated for the operating HPI pumps.

19 39 COMMENTS:

END OF TASK TIME STOP: ________

RO-101b a Page 13 of 14 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

5 This step is required to initiate a manual control rod insertion and start adding negative reactivity to the core.

12 This step is required to align emergency boration from the BWST to add negative reactivity to the core.

13 This step is required to align emergency boration from the BWST to add negative reactivity to the core.

17 This step is required to ensure HPI flow in the "B" HPI header.

18 This step is required to ensure HPI flow in the "A" HPI header.

a CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Unit 1 is at 100% power The CRS has determined that the reactor needs to be tripped INITIATING CUES The CRS directs you to trip the reactor and perform Immediate Manual Actions (IMAs)

RO-204 h Page 1 of 11 REGION II JOB PERFORMANCE MEASURE RO-204 Align Letdown With 1HP-14 Failed in Bleed Alternate Path: No Alt Path

Description:

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

RO-204 h Page 2 of 11 REGION II JOB PERFORMANCE MEASURE Task Title : Align letdown with 1HP-14 failed in "Bleed Task Number :

Alternate Path: No Time Critical: No Validation Time: 10 minutes K/A Rating(s):

System: 002 K/A: A2.01 Rating: 4.3/4.4 Task Standard:

Students align letdown with 1HP-14 failed in the Bleed position IAW AP/1/A/1700/002 (Excessive RCS Leakage)

References:

AP/1/A/1700/002 (Excessive RCS Leakage)

EOP Enclosure 5.5 (PZR and LDST Level Control)

Tools/Equipment/Procedures Needed:

AP/1/A/1700/002 (Excessive RCS Leakage) (Rev. 15)

EOP Enclosure 5.5 (PZR and LDST Level Control) (0M, Rev. 01)

===================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

RO-204 h Page 3 of 11 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS

1. RECALL SNAP 212

2. IMPORT RO-204 simulator files

3. PLACE a clean copy of OMP 2-02 Attachment G for 1A Letdown Filter in component boron log notebook

4. ENSURE clean procedures in place for candidate

5. Go To RUN when directed by the Lead Examiner

====================================================================

Directions without a SNAP:

1. Initialize simulator to desired IC. (Example Recall IC-41 100% EOL)

2. Take any required action: (Example: Perform EOP Encl.5.1, stop RCPs, open pump breakers, throttle EFDW flow etc.)

3. Activate Malfunctions, Build Timers and Overrides as required:

(Example: Activate MPS400 @ 100% on AOR)

4. Acknowledge alarms and Freeze the Simulator at desired point

5. Save to a SNAP Number and password protect, as desired.

RO-204 h Page 4 of 11 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS

• Reactor power is 100%

• AP/1/A/1700/002 is in progress due to 1HP-14 failing in the BLEED position

• Another RO is making up to the LDST per Encl 5.5 of the EOP INITIATING CUE The CRS directs you to continue with AP/1/A/1700/002 (Excessive RCS Leakage) beginning at step 4.155

RO-204 h Page 5 of 11 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP Verify 1A LD Filter in service.

STANDARD: Student observes 1B Letdown (LD) Filter is in service ___ SAT and the 1A LD Filter is NOT in service using either the OAC or Control Board indications and goes to the 1 4.155 RNO.

___ UNSAT COMMENTS:

1. IF 1A LD Filter is OOS for maintenance, THEN restore 1A LD Filter per in progress procedure. (N/A)

2. Open 1HP-17 STANDARD: Student recognizes that 1A LD Filter is available.

• Student opens 1HP-17 and observes the red open *CRITICAL STEP light ON and the green closed light OFF.

4.155 2 ___ SAT RNO Examiner Cue: If asked, notify candidate that 1A Letdown filter is NOT OOS for maintenance.

___ UNSAT COMMENTS:

RO-204 h Page 6 of 11 Close 1HP-6 STANDARD: Student closes 1HP-6 and observes the red open light ___ SAT OFF and the green closed light ON.

3 4.156 COMMENTS: ___ UNSAT NOTE TS 3.4.9 applies when indicated PZR Level > 260 (corrected value for 285).

Adjust 1HP-7, as needed, to control: ___ SAT

• BLEED flow out of failed 1HP-14

• Pzr level 4 4.157 ___ UNSAT STANDARD: Student adjusts 1HP-7 as necessary to control PZR level.

Examiner Note: The candidate may or may NOT adjust 1HP-7 due to the other RO performing EOP Encl 5.5 COMMENTS:

Dispatch an operator to open 1HP-196 (Filter Diversion Inlet) (A LDST Hatch Area) CRITICAL STEP STANDARD: Student dispatches an AO to open 1HP-196

___ SAT Booth Cue: Open 1HP-196 with Manual Valves 5 4.158 COMMENTS: ___ UNSAT

RO-204 h Page 7 of 11 Verify CC System in Operation.

STANDARD: Student observes: ___ SAT

• At least one CC pump in operation

• CC return flow is > 575 gpm 6 4.159

___ UNSAT COMMENTS:

Position the standby HPI pump switch to OFF.

STANDARD: Student places the standby (1B) HPIP switch to OFF ___ SAT 7 4.160 COMMENTS:

___ UNSAT Initiate monitoring RCP parameters.

STANDARD: Student refers to OAC Turn-on Code RCP and control ___ SAT board indications to monitor RCP parameters.

Booth Cue: Notify the candidate that 1HP-196 is open.

8 4.161 ___ UNSAT COMMENTS:

RO-204 h Page 8 of 11 Throttle 1HP-31 to establish 12-15 gpm SEAL INLET HEADER FLOW.

___ SAT STANDARD: Student throttles 1HP-31 to establish 12-15 gpm.

9 4.162 COMMENTS: ___ UNSAT WHEN 1HP-196 (Filter Diversion Inlet) (A-2-LDST Hatch Area) is open, THEN close 1CS-26. CRITICAL STEP STANDARD: Student closes 1CS-26 and observes the red open light OFF and the green closed light ON.

___ SAT 10 4.163 COMMENTS:

___ UNSAT Close the following;

• 1CS-27

• 1CS-32 & 37 STANDARD: Student verifies 1CS-27, 1CS-32, and 1CS-37 are closed by observing the red open lights OFF and the ___ SAT 11 4.164 green closed lights ON.

COMMENTS: ___ UNSAT

RO-204 h Page 9 of 11 Open 1HP-6 CRITICAL STEP STANDARD: Student opens 1HP-6 and observes the red open light ON and the green closed light OFF.

___ SAT 12 4.165 COMMENTS:

___ UNSAT Throttle 1HP-31 to establish 32 gpm SEAL INLET HDR FLOW.

___ SAT STANDARD: Student throttles open 1HP-31 to establish 32 gpm SEAL INLET HDR FLOW.

13 4.166

___ UNSAT COMMENTS:

Adjust 1HP-7 to establish desired letdown flow.

___ SAT STANDARD: Student throttles open 1HP-7 to establish 70 - 80 gpm letdown flow.

14 4.167 Examiner Cue: If asked, inform the candidate to establish 75 gpm Letdown flow. ___ UNSAT COMMENTS:

Position the standby HPI pump switch to AUTO CRITICAL STANDARD: Student places the standby (1B) HPIP switch to AUTO STEP Examiner Cue: Notify the candidate that another operator will ___ SAT 15 4.168 continue with this procedure.

COMMENTS:

___ UNSAT END TASK TIME STOP: ________

RO-204 h Page 10 of 11 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

2 This step is required to align the alternate letdown flow path.

5 This step is required to align the alternate letdown flow path.

10 This step is required to isolate the flow path going to the BHUTs.

12 This step is required to return letdown flow to normal.

15 This step is required to protect the RCP seals by allowing the standby HPIP to automatically start if low seal injection flow (< 22 gpm) is detected.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS

• Reactor power is 100%

• AP/1/A/1700/002 is in progress due to 1HP-14 failing in the BLEED position

• Another RO is making up to the LDST per Encl 5.5 of the EOP INITIATING CUE The CRS directs you to continue with AP/1/A/1700/002 (Excessive RCS Leakage) beginning at step 4.155

RO-501a c Page 1 of 12 REGION II JOB PERFORMANCE MEASURE RO-501a ES CHANNELS 5 AND 6 RECOVERY Alternate Path: Yes Alt Path Failure: ______1A/1B CC Pumps, 1HP-5__________________________________

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: N/A Date:

Reviewed By: Date:

Approved By: Date:

RO-501a c Page 2 of 12 REGION II JOB PERFORMANCE MEASURE Task Title : ES Channels 5 and 6 Recovery Task Number :

Alternate Path: Yes Time Critical: No Validation Time: 8 minutes K/A Rating(s):

System: APE 069 K/A: AA2.01 Rating: 3.7/4.3 Task Standard:

ES Channels 5 and 6 are returned to normal using EOP Enclosure 5.41 (ES Recovery) and Letdown isolated using AP/1/A/1700/020 (Loss of Component Cooling).

References:

EOP Encl. 5.41 (ES Recovery)

AP/1/A/1700/020 (Loss of Component Cooling)

Tools/Equipment/Procedures Needed:

EOP Encl. 5.41 (ES Recovery) (Rev. 0Q)

AP/1/A/1700/020 (Loss of Component Cooling) (Rev. 12)

=========================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

RO-501a c Page 3 of 12 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS

1. RECALL SNAP 215

2. PLACE Letdown Temp Interlock Bypass to BYPASS to exit static check, then place back in NORMAL

3. IMPORT RO-501a files

4. Go to RUN and acknowledge alarms

5. Go to FREEZE

6. ENSURE clean procedures (EOP Encl. 5.41 and AP/20) in place for candidate

7. Go to RUN when directed by Lead Examiner

RO-501a c Page 4 of 12 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS A MSLB has occurred ES Channels 1 - 6 have actuated on High RB pressure EOP Encl. 5.1 (ES Actuation) is complete ALL ES Channels are being reset EOP Encl. 5.41 (ES Recovery) is complete through step 40 INITIATING CUES The CRS directs you to continue in EOP Encl. 5.41 (ES Recovery) beginning at step 41 to reset ES Channels 5 and 6.

RO-501a c Page 5 of 12 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP Verify reset of any of the following is desired:

• ES Channel 5 ___ SAT

• ES Channel 6

___ UNSAT STANDARD: Determines, from Initiating Cue, that reset of ES 1 41 Channels 5 and 6 is desired.

COMMENTS:

Verify Stat Alarms have cleared:

• 1SA-7/A-1 (1A1 ES TRIP)

• 1SA-7/B-1 (1B1 ES TRIP) ___ SAT

• 1SA-7/C-1 (1C1 ES TRIP)

• 1SA-7/A-2 (1A2 ES TRIP)

• 1SA-7/B-2 (1B2 ES TRIP) ___ UNSAT

• 1SA-7/C-2 (1C2 ES TRIP) 2 42 STANDARD: Determine that all of the above statalarms on 1SA-7 are clear by observing that their respective window lights are NOT illuminated.

COMMENTS:

Perform the following to reset ES (1UB1): CRITICAL STEP

• Depress RESET for CH 5.

• Depress RESET for CH 6.

___ SAT STANDARD: Candidate depresses the RESET pushbuttons for 3 43 Channels 5 and 6 located on 1UB1

___ UNSAT COMMENTS:

RO-501a c Page 6 of 12 Verify:

• CH 5 TRIPPED light off

• CH 6 TRIPPED light off

___ SAT STANDARD: Verifies white tripped lights OFF for ES Channels 5 4 44 and 6 ___ UNSAT COMMENTS:

Open:

• 1CC-7

• 1CC-8 ___ SAT STANDARD: Candidate verifies 1CC-7 and 1CC-8 are open by observing RED open lights ON and GREEN closed 5 45 ___ UNSAT lights OFF.

COMMENTS:

Ensure one CC pump is running in the ON position.

STANDARD: Rotates the switch for the 1B CC Pump to ON. ___ SAT EXAMINER NOTE: The 1B CC Pump will trip 30 seconds after 6 46 ___ UNSAT ES Channel 6 RESET P/B is depressed..

COMMENTS:

RO-501a c Page 7 of 12 ALTERNATE PATH IF NO CC pumps are operating, THEN perform the following:

1. Initiate AP/20 (Loss of Component Cooling).

2. GO TO Step 48.

STANDARD: Candidate initiates AP/20 (Loss of Component ___ SAT 46 Cooling) from either step 46 RNO or 1SA-9/B-1 or 7 1SA-9/C-1.

RNO

___ UNSAT EXAMINER CUE: Once AP/20 is initiated, inform candidate the CRS directs them to perform AP/20.

COMMENTS:

IAAT both of the following are lost:

• CC to RCPs

• RCP seal injection

___ SAT THEN perform the following:

A. Trip Rx B. Stop all RCPs AP/20 C. Initiate AP/25 (SSF EOP) ___ UNSAT 8

3.1 STANDARD

Determine RCP seal injection is available and proceed to step 3.2.

COMMENTS:

RO-501a c Page 8 of 12 NOTE If CRD stator cooling is lost, stator temperatures will reach 180°F in 4 minutes. CRD stator temperatures can be read on the OAC, turn-on code "1CRDTP". ___ SAT IAAT two CRD stator temperatures 180°F, THEN trip Rx. ___ UNSAT 9 3.2 STANDARD: Determine Rx is already tripped and proceed to step

4.1. COMMENTS

Verify at least one CC Pump operating.

___ SAT STANDARD: Determine NO CC Pumps are operating. Proceed to RNO.

___ UNSAT 10 4.1 COMMENTS:

1. IF either of the following:

• CC Pumps have been manually secured due to CC system leakage

• AP/2 directed initiation of AP/20 ___ SAT THEN GO TO step 4.12.

2. GO TO step 4.3

___ UNSAT 4.1 11 STANDARD: Determine CC Pumps were NOT secured due to RNO system leakage and AP/2 did NOT direct initiation of AP/20.

GO TO step 4.3.

COMMENTS:

RO-501a c Page 9 of 12 Open:

• 1CC-7 ___ SAT

• 1CC-8 STANDARD: Candidate verifies 1CC-7 and 1CC-8 are open by

___ UNSAT observing red open lights ON and green closed lights 12 4.3 OFF.

COMMENTS:

Verify > one CC Pump operating.

STANDARD: Determine NO CC Pumps are operating. Proceed to ___ SAT RNO.

13 4.4

___ UNSAT COMMENTS:

RO-501a c Page 10 of 12

1. IF CC Surge Tank level > 12",

THEN attempt to start a CC Pump (will NOT start) *CRITICAL

2. IF unable to start any CC Pump, STEP THEN perform the following:

A. Close 1HP-5 (will NOT close) ___ SAT B. IF 1HP-5 fails to close THEN perform the following:

___ UNSAT

• *Close 1HP-3 (critical)

• *Close 1HP-4 (critical)

C. Notify WCC SRO to initiate actions to regain a CC Pump.

D. Initiate AP/32 (Loss of Letdown).

STANDARD: Verify CC Surge Tank level > 12" and attempt to start a CC Pump. Determine neither CC Pump will start.

4.4 Place 1HP-5 switch to close. Determine 1HP-5 will not 14 RNO close by observing the red open light ON and the green closed light OFF.

Place the switches for 1HP-3 and 4 to close.

Determine 1HP-3 and 4 are closed by observing the green closed light ON and the red open light OFF.

Notify WCC SRO to initiate actions to regain a CC Pump.

Initiate AP/32.

EXAMINERS CUE: Another operator will continue with this procedure.

COMMENTS:

END TASK TIME STOP: ________

RO-501a c Page 11 of 12 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

3 This step is required to reset ES channels 5 & 6 so the associated components can be re-aligned for normal operation.

14 This step is required to isolate letdown.

c CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS A MSLB has occurred ES Channels 1 - 6 have actuated on High RB pressure EOP Encl. 5.1 (ES Actuation) is complete ALL ES Channels are being reset EOP Encl. 5.41 (ES Recovery) is complete through step 40 INITIATING CUES The CRS directs you to continue in EOP Encl. 5.41 (ES Recovery) beginning at step 41 to reset ES Channels 5 and 6.

RO-604 g Page 1 of 11 REGION II JOB PERFORMANCE MEASURE RO-604 Perform a Manual Start of KHU 1 Alternate Path: No Alt Path

Description:

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

RO-604 g Page 2 of 11 REGION II JOB PERFORMANCE MEASURE Task Title : Perform A Manual Start Of Keowee Hydro Unit 1 Task Number :

Alternate Path: No Time Critical: No Validation Time: 10 minutes K/A Rating(s):

System: 062 K/A: A4.07 Rating: 3.1/3.1 Task Standard:

Keowee Hydro Unit 1 is manually started and synchronized to the 230 KV switchyard.

References:

OP/0/A/1106/019 (Keowee Hydro At Oconee)

Tools/Equipment/Procedures Needed:

OP/0/A/1106/019 (Keowee Hydro At Oconee), Encl 4.5 (KHU-1 Manual Startup) (Rev. 101)

===================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

RO-604 g Page 3 of 11 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS

1. RECALL SNAP 216

2. IMPORT RO-604 simulator files

3. ENSURE KHU 1 in REMOTE

4. Go To RUN when directed by the Lead Examiner

====================================================================

Directions without a SNAP:

1. Initialize simulator to desired IC. (Example Recall IC-41 100% EOL)

2. Take any required action: (Example: Perform EOP Encl.5.1, stop RCPs, open pump breakers, throttle EFDW flow etc.)

3. Activate Malfunctions, Build Timers and Overrides as required:

(Example: Activate MPS400 @ 100% on AOR)

4. Acknowledge alarms and Freeze the Simulator at desired point

5. Save to a SNAP Number and password protect, as desired.

RO-604 g Page 4 of 11 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS Keowee Unit 1 is aligned to the Overhead.

Keowee Unit 1 is to be manually started and tied to the grid.

This is NOT an emergency.

OP/0/A/1106/19, Enclosure 4.5 (KHU-1 Manual Startup) is in progress INITIATING CUE The CRS directs you to continue with a manual start of Keowee Unit 1, and tie it to the grid with no load, per OP/0/A/1106/019, Enclosure 4.5 beginning at Step 2.1.

RO-604 g Page 5 of 11 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP NOTE: AC HP Lift Pump starts and Generator Cooling Water CRITICAL valve opens when Unit 1 MASTER SELECTOR in MAN. STEP Place UNIT 1 MASTER SELECTOR in MAN"

___ SAT STANDARD: Candidate positions UNIT 1 MASTER SELECTOR switch to "MAN". ___ UNSAT 1 2.1 Continue to Step 2.2 COMMENTS:

Place UNIT 1 SYNC 230 KV selector in "MAN".

CRITICAL STEP STANDARD: Candidate positions UNIT 1 SYNC 230 KV selector switch to "MAN".

___ SAT 2 2.2 Continue to Step 2.3

___ UNSAT COMMENTS:

RO-604 g Page 6 of 11 IF this is NOT an emergency situation, notify Keowee operator to activate the Tailrace Rising Water Alarm Test button on CB-5.

STANDARD: Candidate determines this is not an emergency ___ SAT situation and notifies Keowee Operator to activate the Tailrace Rising Water Alarm Test button on CB-5.

3 2.3 Booth cue: Keowee operator (Casey Holder) reports Tailrace

___ UNSAT Rising Water Alarm Test button on CB-5 is active.

Continue to Step 2.4 COMMENTS:

Place AND hold UNIT 1 LOCAL MASTER switch to "START" position for > 10 seconds until KHU starts. CRITICAL STEP STANDARD: Candidate rotates the UNIT 1 LOCAL MASTER switch to the "START" position for >10 seconds and verifies ___ SAT that the Turb 1 Gate Position increases on 2AB3.

4 2.4 ___ UNSAT Continue to Step 2.5 COMMENTS:

RO-604 g Page 7 of 11 WHEN TURBINE 1 GATE POSITION indicator settles out:

• CRITICAL STEP

• Momentarily place EXCITER STOP/START to "START".

• Verify EXCITER STOP/START Red START light ON, Green STOP light OFF.

___ SAT STANDARD: Candidate observes that the TURBINE 1 GATE POSITION has settled out and then:

o *Momentarily places EXCITER STOP/START to "START". ___ UNSAT o Observes EXCITER STOP/START Red START light ON, Green STOP light OFF and GEN FREQ 5 2.5 about 60 HZ and Keowee 1 Output volts about 13.8 KV.

Continue to Step 2.6 COMMENTS:

RO-604 g Page 8 of 11 IF required, synchronize KHU-1 to the grid:

CRITICAL 2.6.1 Verify open KPF-9 (KHU 1 FDR) STEP 2.6.2 Make the following adjustments concurrently as required:

• Using UNIT 1 AUTO VOLTAGE ADJUSTER, match KEOWEE 1 LINE VOLTS with KEOWEE 1 OUTPUT VOLTS when 13.8 KV ___ SAT SYNCHROSCOPE pointer is vertical.

• Adjust KHU-1 Generator speed with UNIT 1 SPEED CHANGER MOTOR until slow clockwise rotation of 13.8 KV SYNCHROSCOPE is established. ___ UNSAT CAUTION: To prevent possible equipment damage, it is important to realize that 5° is NOT equivalent to 5 minutes.

2.6.3 WHEN 13.8 KV SYNCHROSCOPE pointer is 5° before reaching vertical, close ACB 1 KEOWEE 1 GENERATOR BKR.

STANDARD: 2.6.1 Candidate verifies KPF-9 is open by observing the red closed light OFF and the white open light ON.

6 2.6 2.6.2 Candidate determines that KHU-1 is required to be synced to the grid and makes the following adjustments:

• UNIT 1 AUTO VOLTAGE ADJUSTER manipulated to match KEOWEE 1 LINE VOLTS with KEOWEE 1 OUTPUT VOLTS when 13.8 KV SYNCHROSCOPE pointer is vertical.

• KHU-1 Generator speed adjusted with UNIT 1 SPEED CHANGER MOTOR until slow clockwise rotation of 13.8 KV SYNCHROSCOPE is established.

2.6.3 ACB 1 KEOWEE 1 GENERATOR BKR switch is taken to close when the 13.8 KV SYNCHROSCOPE pointer is 5° before vertical, and candidate observes the red close light ON and the white open light OFF.

Continue to Step 2.7 COMMENTS:

RO-604 g Page 9 of 11 CAUTION: KHU-1 load should NOT be reduced below indicated zero (0) MWs.

___ SAT IF required, perform the following concurrently:

• Adjust load to zero (0) MWs with UNIT 1 SPEED CHANGER MOTOR.

• Adjust MVARS to zero (0) with UNIT 1 AUTO VOLTAGE ___ UNSAT ADJUSTER.

STANDARD: Candidate manipulates the UNIT 1 SPEED 7 2.7 CHANGER MOTOR as required to obtain (0) MWs and the UNIT 1 AUTO VOLTAGE ADJUSTER as required to obtain zero (0) MVARS.

COMMENTS:

END TASK TIME STOP: ________

RO-604 g Page 10 of 11 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

1 This step is required to manually start KHU-1.

2 This step is required to manually start KHU-1.

4 This step is required to start KHU-1.

5 This step is required to excite the KHU-1 generator.

6 This step is required to synchronize KHU-1 to the grid.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Keowee Unit 1 is aligned to the Overhead.

Keowee Unit 1 is to be manually started and tied to the grid.

This is NOT an emergency.

OP/0/A/1106/19, Enclosure 4.5 (KHU-1 Manual Startup) is in progress INITIATING CUE The CRS directs you to continue with a manual start of Keowee Unit 1, and tie it to the grid with no load, per OP/0/A/1106/019, Enclosure 4.5 beginning at Step 2.1.

RO-702 - d Page 1 of 12 REGION II JOB PERFORMANCE MEASURE RO-702 Adjust Radiation Monitor Setpoints Alternate Path: No Alt Path

Description:

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

RO-702 - d Page 2 of 12 REGION II JOB PERFORMANCE MEASURE Task Title : Adjust Radiation Monitor Setpoints Task Number :

Alternate Path: No Time Critical: No Validation Time: 25 minutes K/A Rating(s):

System: 073 K/A: A4.01 Rating: 3.9 / 3.9 Task Standard:

Adjust 1RIA-37 and 1RIA-38 for a GWD release per procedure.

References:

OP/1-2/A/1104/018, GWD system PT/0/A/230/01, Radiation Monitor Check Tools/Equipment/Procedures Needed:

OP/1-2/A/1104/018, GWD system, Encl. 4.9 and 4.10 (Rev. 78)

PT/0/A/230/01, Radiation Monitor Check, Encl. 13.6 (Rev. 172)

PT/1-2/A/0230/002, GWD Tank Release (Rev. 6)

===================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

RO-702 - d Page 3 of 12 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS

1. RECALL SNAP 217

2. ENSURE procedures in place for candidate

3. ENSURE OP/0/A/1108/001 Encl 4.3 is clean

4. Select plant HMI screen to GWD system

5. ENSURE Purged tag in place on GWD DISCH FLOW CONTROLLER

6. Go to RUN when directed by Lead Examiner

====================================================================

Directions without a SNAP:

1. Initialize simulator to desired IC. (Example Recall IC-41 100% EOL)

2. Take any required action: (Example: Perform EOP Encl.5.1, stop RCPs, open pump breakers, throttle EFDW flow etc.)

3. Activate Malfunctions, Build Timers and Overrides as required:

(Example: Activate MPS400 @ 100% on AOR)

4. Acknowledge alarms and Freeze the Simulator at desired point

5. Save to a SNAP Number and password protect, as desired.

RO-702 - d Page 4 of 12 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS Release of B GWD tank is desired No other GWRs in progress OP/1-2/A/1104/018, Enclosure 4.9 (GWD Tank Release) is in progress and completed up to Step 3.4 INITIATING CUES SRO directs you to continue the release of the B GWD tank beginning at Step 3.4 of Enclosure 4.9

RO-702 - d Page 5 of 12 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP Perform the following on Enclosure 4.10 (GWD Tank Sample Request):

3.4.1 Record Initial GWD Tank Pressure AND GWD Tank Volume 3.4.2 Record Start Date AND Time 3.4.3 Record background readings for 1RIA-37 AND 1RIA-38 STANDARD: Determine B GWD tank pressure is 65.3 psig by looking on ___ SAT either the OAC on the chart on 1VB1 and record on Enclosure 4.10.

Determine GWD Tank Volume is 6000 Ft by using the 3

curve in OP/1108/001 (General Curves and Information) ___ UNSAT and record on Enclosure 4.10.

1 3.4 Determine background readings for 1RIA-37 & 1RIA-38 by observing the RIA readings on the RIA View Node and record on Enclosure 4.10.

Note: The background readings should be as follows:

• 1RIA-37 Background reading is: 367 or 3.67E2 cps

• 1RIA-38 Background reading is: 11 or 1.1E1 cps Continue to Step 3.5 COMMENTS:

Record recommended 1RIA-37 and 38 Alert and High setpoints from Enclosure 4.10 (GWD Tank Sample Request):

• 1RIA-37 3.47 E5 cpm above background

• 1RIA-38 2.78 E2 cpm above background ___ SAT STANDARD: Obtain this information from the sample request and record in the procedure.

2 3.5

___ UNSAT Continue to Step 3.6 COMMENTS:

RO-702 - d Page 6 of 12 NOTE: If N2 was added to the most recently released GWD tank until 1RIA-37 indicated < 700 cpm, OR if the tanks radioactivity was

< 2.1E-05µCi/ml when it was released, the GWD piping is considered purged.

IF 1RIA-37 is out-of-service OR GWD piping NOT purged, verify the following per Enclosure 4.10 (GWD Tank Sample Request):

• Independent Data Entry Checks completed

___ SAT

• Independent Sample agrees with initial sample 3 3.6 STANDARD: Determine step does not apply and N/A the step. ___ UNSAT Continue to Step 3.7 Examiner Cue: If asked, inform the candidate that the GWD piping is purged.

COMMENTS:

NOTE: If N2 was added to the most recently released GWD tank until 1RIA-37 indicated < 700 cpm, OR if the tanks radioactivity was

< 2.1E-05µCi/ml when it was released, the GWD piping is considered purged.

CRITICAL STEP IF GWD piping purged, calculate actual setpoints as follows:

3.7.1 IF 1RIA-37 Operable, calculate Alert and High setpoints as follows:

___ SAT 3.67E2 cpm + 3.47E5 = 3.47E5 cpm 1RIA-37' Add to background' 1RIA-37 background value from Step 3.5 Alert and High ___UNSAT 4 3.7 alarm setpoints STANDARD: Calculate set points using formula above.

(3.47E5 to 3.48E5)

Continue to Step 3.8 COMMENTS:

RO-702 - d Page 7 of 12 IF 1RIA-38 Operable, calculate Alert and High setpoints as follows:

1.1E1 cpm + 2.78E2 = 2.89E2 cpm CRITICAL 1RIA-38' Add to background' 1RIA-38 STEP background value from Step 3.5 Alert and High alarm setpoints

___ SAT 5 3.8 STANDARD: Calculate set points using formula above (2.89E2).

Continue to Step 3.9

___UNSAT COMMENTS:

RO-702 - d Page 8 of 12 NOTE: If N2 was added to the most recently released GWD tank until 1RIA-37 indicated < 700 cpm, OR if the tanks radioactivity was

< 2.1E-05µCi/ml when it was released, the GWD piping is considered purged.

Adjust 1RIA-37 setpoints for release as follows:

3.9.1 Perform one of the following:

___ SAT A. IF all of the following:

• Calculated setpoints are < 1E+07 CPM

• 1RIA-37 operable

• GWD pipping purged ___ UNSAT Set alarms as follows:

• Set 1RIA-37 Alert setpoint at 3.47E5 cpm per PT/0/A/0230/001 (Radiation Monitor Check). (from Step 3.7.1)

• Set 1RIA-37 High setpoint at 3.47E5 cpm per PT/0/A/0230/001 (Radiation Monitor Check). (from Step 3.7.1)

NOTE: If GWD piping NOT purged on most recent release, RP independently verifies release data and 1RIA-37 setpoint is set at zero to allow the tank to be released.

6 3.9 B. IF any of the following: (N/A)

• Calculated setpoints are > 1E+07 CPM

• 1RIA-37 out-of-service

• GWD piping NOT purged STANDARD: Determine that calculated setpoints are < 1E+07 CPM, 1RIA-37 is operable, and GWD piping is purged and set 1RIA-37 alert and high setpoints at 3.47E5 per PT/0/A/0230/001 (see Step 7).

(3.47E5 to 3.48E5)

Continue to Step 3.10 COMMENTS:

RO-702 - d Page 9 of 12 PT/0/A/0230/001 Enclosure 13.6 (1RIA-37 and 1RIA-38 Setpoints) 1.1 Verify Unit 1&2 GWD Tank release planned per OP/1-2/A/1104/018 (GWD System)

CRITICAL NOTE: Each RIA procedure section may be performed in any STEP sequence.

2.1 Set process monitor setpoints as required ___ SAT 3.1 Document 1RIA-37 Alert setpoint per OP/1-2/A/1104/018:

3.47E5 CPM 3.2 Insert 1RIA-37 Alert setpoint from Step 3.1

___UNSAT 3.3 Document 1RIA-37 High setpoint per OP/1-2/A/1104/018:

7 3.47E5 CPM 3.4 Insert 1RIA-37 High setpoint from Step 3.3 STANDARD: Candidate documents the Alert and High setpoints for 1RIA-37 per OP/1-2/A/1104/018 (3.47E5 to 3.48E5)

Candidate inserts the Alert and High setpoints into 1RIA-37 (3.47E5 to 3.48E5)

COMMENTS:

RO-702 - d Page 10 of 12 Adjust 1RIA-38 setpoints for release as follows:

3.10.1 Perform one of the following:

A. IF calculated setpoints are < 1E+06 CPM AND 1RIA-38 operable, set alarms as follows:

• Set 1RIA-38 Alert setpoint at 2.89E2 cpm per PT/0/A/0230/001 (Radiation Monitor Check). (from Step 3.8)

• Set 1RIA-38 High setpoint at 2.89E2 cpm per ___ SAT PT/0/A/0230/001 (Radiation Monitor Check). (from Step 3.8)

NOTE: Due to type of radiation 1RIA-38 monitors, it is NOT sensitive enoughto perform an adequate N2 purge. ___ UNSAT 8 3.10 B. IF calculated setpoints are > 1E+06 CPM OR 1RIA-38 out of service, perform the following: (N/A)

STANDARD: Candidate documents the Alert and High setpoints for 1RIA-38 per OP/1-2/A/1104/018 (2.89E2)

Candidate inserts the Alert and High setpoints into 1RIA-37 (2.89E2) per PT/0/A/0230/001 (per Step 9)

COMMENTS:

PT/0/A/0230/001 Enclosure 13.6 (1RIA-37 and 1RIA-38 Setpoints) 4.1 Document 1RIA-38 Alert setpoint per OP/1-2/A/1104/018:

2.89E2 CPM CRITICAL 3.2 Insert 1RIA-38 Alert setpoint from Step 4.1 STEP 3.3 Document 1RIA-38 High setpoint per OP/1-2/A/1104/018:

2.89E2 CPM 3.4 Insert 1RIA-38 High setpoint from Step 4.3 ___ SAT 9 STANDARD: Candidate documents the Alert and High setpoints for 1RIA-38 per OP/1-2/A/1104/018 (2.89E2)

___UNSAT Candidate inserts the Alert and High setpoints into 1RIA-38 (2.89E2)

COMMENTS:

END TASK TIME STOP: ________

RO-702 - d Page 11 of 12 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

4 Required to ensure proper setpoint is calculated.

5 Required to ensure proper setpoint is calculated.

7 Required to set RIA to prevent station release above limits.

9 Required to set RIA to prevent station release above limits.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Release of B GWD tank is desired No other GWRs in progress OP/1-2/A/1104/018, Enclosure 4.9 (GWD Tank Release) is in progress and completed up to Step 3.4 INITIATING CUES SRO directs you to continue the release of the B GWD tank beginning at Step 3.4 of Enclosure 4.9

RO-805a f Page 1 of 14 REGION II JOB PERFORMANCE MEASURE RO-805a Perform Required Actions For a Turbine Building Flood Alternate Path: Yes Alt Path

Description:

______1CCW-12 will not close_______________________________

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

RO-805a f Page 2 of 14 REGION II JOB PERFORMANCE MEASURE Task Title : Perform Required Actions For A Turbine Building Flood Task Number :

Alternate Path: Yes Time Critical: No Validation Time: 10 minutes K/A Rating(s):

System: APE BW/A07 K/A: AA1.3 Rating: 3.3/3.5 Task Standard:

Perform required actions for a Turbine Building Flood in accordance with AP/10, Turbine Building Flood

References:

AP/1/A/1700/01010, Turbine Building Flood Tools/Equipment/Procedures Needed:

AP/1/A/1700/01010, Turbine Building Flood (Rev. 10)

===================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

RO-805a f Page 3 of 14 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS

1. RECALL SNAP 218

2. IMPORT files for RO-805a

3. ENSURE clean procedure in place for candidate

4. Go to RUN when directed by the Lead Examiner

====================================================================

Directions without a SNAP:

1. Initialize simulator to desired IC. (Example Recall IC-41 100% EOL)

2. Take any required action: (Example: Perform EOP Encl.5.1, stop RCPs, open pump breakers, throttle EFDW flow etc.)

3. Activate Malfunctions, Build Timers and Overrides as required:

(Example: Activate MPS400 @ 100% on AOR)

4. Acknowledge alarms and Freeze the Simulator at desired point

5. Save to a SNAP Number and password protect, as desired.

RO-805a f Page 4 of 14 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS Unit 1 was operating at 100% power Unit 2 is in cold shutdown The 2A1 condenser inlet expansion joint has ruptured and Turbine Building Basement water level is rising Unit 1 has been tripped and the EOP is being completed by other team members.

INITIATING CUE The CRS directs you to initiate Unit 1 AP/10 (Turbine Building Flood).

RO-805a f Page 5 of 14 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP Trip the Rx.

STANDARD: Depress the Rx trip pushbutton on 1UB1. Verify the ___ SAT RX is tripped by observing all control rods are inserted.

1 4.1 ___ UNSAT Continue to Step 4.2.

COMMENTS:

Place 1CCW-1-6 switch in PULL TO LOCK.

STANDARD: Candidate locates and places the control switch for 1CCW-1-6 in PULL TO LOCK. ___ SAT 2 4.2 Continue to Step 4.3.

___ UNSAT COMMENTS:

RO-805a f Page 6 of 14 NOTE Tripping the CCW pumps will cause loss of condenser vacuum which CRITICAL will result in TBVs failing closed and trip of the MFDWPs. STEP Ensure all CCW pumps are shutdown.

STANDARD: Candidate rotates the 1A, 1B, and 1C CCW pump switches to the TRIP position and verifies the red ___ SAT close lights extinguished and the white open lights 3 4.3 illuminated. (located on 1AB3)

Continue to Step 4.4. ___ UNSAT Examiner Cue: If the candidate initiates AP/24, notify them that another operator will perform AP/24 COMMENTS:

Press both of the following on the TURB BLDG FLOOD EMER CRITICAL CLOSING ALL CCWP DISCH VALVES control switch: STEP

• CLOSE 1

• CLOSE 2

___ SAT STANDARD: "CLOSE 1" and "CLOSE 2" on the TURB BLDG FLOOD EMER CLOSING ALL CCWP DISCH 4 4.4 VALVES control switch are both depressed. (located on 1AB3) ___ UNSAT Continue to Step 4.5.

COMMENTS:

RO-805a f Page 7 of 14 Verify all the following closed.

__ 1CCW-10

__ 1CCW-11

__ 1CCW-12

__ 1CCW-13 STANDARD: The green CLOSED lights for 1CCW-10, 11, and 13 are verified illuminated and the red OPEN lights for the same valves are verified extinguished. (located on ___ SAT 5 4.5 1AB3)

Determine that 1CCW-12 is NOT closed by observing the red open light lit on 1AB3. ___ UNSAT Continue to Step 4.5 RNO.

COMMENTS:

RO-805a f Page 8 of 14

[ALTERNATE PATH]

NOTE The control switches for the CCW pump discharge valves do not seal-in. The valves act as throttle valves unless the associated CCW pump switch is in the TRIP position.

Dispatch an operator to ensure all CCW pump discharge valves are closed (Equipment Rm):

• 1XS1-F2C (1CCW-10 Bkr 1A CCW Pump Disch)

• 1XS1-F3C (1CCW-13 Bkr 1D CCW Pump Disch) 4.5

• 1XS2-F2D (1CCW-11 Bkr 1B CCW Pump Disch) 6 RNO

• 1XS3-2E (1CCW-12 Bkr 1C CCW Pump Disch)

STANDARD: An operator is dispatched to the Equipment Room to ___ SAT ensure 1CCW-12 is closed.

Continue to Step 4.6.

___ UNSAT Booth cue: After 2 minutes call as the AO and inform candidate that 1CCW-12 will NOT close.

COMMENTS:

RO-805a f Page 9 of 14 NOTE Field tasks that may affect multiple units should be coordinated with Unit 2 and Unit 3.

Dispatch operators to ensure all three flood doors are closed and in the SECURED position from the AB side (A-1, at Unit 1, 2, and 3 stairwell entrances to TB): {2}

• Unit 1 Flood Door

• Unit 2 Flood Door

• Unit 3 Flood Door 7 4.6 STANDARD: Dispatch an AO to ensure all three flood doors are closed and in the SECURED position from the AB ___ SAT side.

Continue to Step 4.7.

___ UNSAT Booth cue: When called, inform candidate that an operator has been dispatched.

COMMENTS:

RO-805a f Page 10 of 14 Dispatch an operator to position the waterbox discharge valve switches (T-3, East of condenser catwalk):

• 1CCW-20 (1A1) switch to HAND

• 1CCW-20 (1A1) switch to CLOSE

___ SAT

• 1CCW-21 (1A2) switch to HAND

• 1CCW-21 (1A2) switch to CLOSE

• 1CCW-22 (1B1) switch to HAND

• 1CCW-22 (1B1) switch to CLOSE ___ UNSAT

• 1CCW-23 (1B2) switch to HAND

• 1CCW-23 (1B2) switch to CLOSE

• 1CCW-24 (1C1) switch to HAND

• 1CCW-24 (1C1) switch to CLOSE 8 4.7

• 1CCW-25 (1C2) switch to HAND

• 1CCW-25 (1C2) switch to CLOSE STANDARD: Candidate should dispatch an operator to place the above valves to HAND and CLOSE.

Continue to Step 4.8.

Booth Cue: When called, inform candidate that an operator has been dispatched.

COMMENTS:

RO-805a f Page 11 of 14 Verify all the following closed.

__ 1CCW-10

__ 1CCW-11

__ 1CCW-12

__ 1CCW-13 STANDARD: The green CLOSED lights for 1CCW-10, 11, and 13 ___ SAT are verified illuminated and the red OPEN lights for the same valves are verified extinguished. (located on 9 4.8 1AB3)

___ UNSAT Determine that 1CCW-12 is NOT closed by observing the red open light lit on 1AB3.

Continue to Step 4.8 RNO.

COMMENTS:

RO-805a f Page 12 of 14

[ALTERNATE PATH]

NOTE If the pipe cap cannot be removed by hand, then there is a strap wrench in the black tool box which is staged on the CCW Intake structure near catwalk.

Dispatch an operator to perform the following (ESV Trench, Intake):

• Remove pipe cap at 1CCW-26 (CCW Inlet High Point Vent). CRITICAL STEP

• Open 1CCW-26 (CCW Inlet High Point Vent).

4.8

• Remove pipe cap at 1CCW-28 (CCW Inlet High Point 10 Vent).

RNO

• Open 1CCW-28 (CCW Inlet High Point Vent).

___ SAT STANDARD: Candidate should dispatch an operator to position the above valves as directed.

___ UNSAT Continue to Step 4.9 Booth Cue: When called, inform candidate that an operator has been dispatched.

COMMENTS:

Open 1V-186 STANDARD: Candidate rotates the switch for 1V-186 to the open ___ SAT position until the red open light is illuminated and the green closed light is extinguished.

11 4.9 Examiner Cue: Another operator will continue this task.

___ UNSAT COMMENTS:

END TASK TIME STOP: ________

RO-805a f Page 13 of 14 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

3 This step is required to attempt to terminate the flooding and not contribute to the water level in the TB basement.

4 This step is required to attempt to terminate the flooding and not contribute to the water level in the TB basement.

10 This step is required to ensure CCW inlet piping is vented to break siphon.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Unit 1 was operating at 100% power Unit 2 is in cold shutdown The 2A1 condenser inlet expansion joint has ruptured and Turbine Building Basement water level is rising Unit 1 has been tripped and the EOP is being completed by other team members INITIATING CUE The CRS directs you to initiate Unit 1 AP/10 (Turbine Building Flood)

RO-P403 - b Page 1 of 15 REGION II JOB PERFORMANCE MEASURE RO-P403 Initiate HPI Forced Cooling Alternate Path: No Alt Path

Description:

Time Critical: Yes Time Critical Criteria: HPI Forced Cooling initiated within 5 minutes of criteria being met Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

RO-P403 - b Page 2 of 15 REGION II JOB PERFORMANCE MEASURE Task Title : Initiate HPI Forced Cooling Task Number :

Alternate Path: No Time Critical: Yes Validation Time: 10 minutes K/A Rating(s):

System: EPE 074 K/A: EA1.08 Rating: 4.2/4.2 Task Standard:

Perform Rule 4 (Initiate HPI Forced Cooling).

References:

EOP Rule 3 (Loss of Main or Emergency FDW)

EOP Rule 4 (Initiate HPI Forced Cooling)

TCA #26, Initiate HPI Forced Cooling when required Tools/Equipment/Procedures Needed:

EOP Rule 3 (Loss of Main or Emergency FDW) (Rev. 0L)

EOP Rule 4 (Initiate HPI Forced Cooling) (Rev. 0L)

(Note: Below this line is used only for Initial NRC Exams)

===================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

RO-P403 - b Page 3 of 15 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS

1. RECALL SNAP 214

2. IMPORT simulator files for RO-P403

3. ENSURE clean in-progress Rule 3 available for candidate

4. ENSURE clean Rule 4 in place on control board

5. Go to RUN when directed by lead examiner

====================================================================

Directions without a SNAP:

1. Initialize simulator to desired IC. (Example Recall IC-41 100% EOL)

2. Take any required action: (Example: Perform EOP Encl.5.1, stop RCPs, open pump breakers, throttle EFDW flow etc.)

3. Activate Malfunctions, Build Timers and Overrides as required:

(Example: Activate MPS400 @ 100% on AOR)

4. Acknowledge alarms and Freeze the Simulator at desired point

5. Save to a SNAP Number and password protect, as desired.

RO-P403 - b Page 4 of 15 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS

• Unit 1 has tripped following a total loss of feedwater

• IMAs are complete

• The crew has been performing Rule 3 (Loss of Main or Emergency FDW) to regain heat transfer

• CBP feed could NOT be established and PSW SG feed is NOT available

• Efforts to restore steam generator heat transfer per Rule # 3 have NOT been successful

• You are at the Step 23 (WHEN) step in Rule 3 (Loss of Main or Emergency FDW)

INITIATING CUE The CRS directs you to review outstanding IAAT Steps This JPM is Time Critical

RO-P403 b Page 5 of 15 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP IAAT NO SGs can be fed with FDW (Main/CBP/Emergency/PSW), AND any of the following exist:

• RCS pressure reaches 2300 psig OR NDT limit

• Pzr level reaches 375" [340" acc]

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

Rule STANDARD: Candidate announces the initiation of Rule 4.

3 1 IAAT Examiner Cue: If requested, provide concurrence (as CRS) for initiation ___ SAT of Rule 4.

Step 3 Examiner Note: This starts the 5 minute Time critical time clock. __ UNSAT Time = ___________.

COMMENTS:

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

Rule STANDARD: The candidate recognizes one HPI pump is in operation.

4 ___ SAT 2

Step COMMENTS:

1

__ UNSAT

RO-P403 b Page 6 of 15 OPEN the following:

• 1HP-24 CRITICAL

• 1HP-25 STEP STANDARD: The candidate:

• Rotates 1HP-24 switch on 1UB1 to the OPEN position and observes the red open light come ON and the green closed ___ SAT light go OFF.

3 2

• Rotates 1HP-25 switch on 1UB1 to the OPEN position and observes the red open light come ON and the green closed __ UNSAT light go OFF.

COMMENTS:

Start all available HPI pumps STANDARD: Candidate starts the 1B and 1C HPI pumps by rotating the 1B HPI pump control switch to the START position and rotating the 1C HPI pump control switch to the CLOSE position located ___ SAT on 1UB1.

4 3 COMMENTS: __ UNSAT

RO-P403 b Page 7 of 15 OPEN the following:

• CRITICAL

• *1HP-26 STEP

• 1HP-27 STANDARD: The candidate:

• Rotates and holds 1HP-26 switch on 1UB1 to the OPEN ___ SAT position and observes the green CLOSED light go OFF and 5 4 the red OPEN light come ON.

• Locates 1HP-27 ('1B' HP Injection) on 1UB1 and verifies red

'OPEN' light is ON, and the green 'CLOSED' light is OFF. __ UNSAT COMMENTS:

Open 1RC-4 STANDARD: The candidate locates 1RC-4 control switch on 1UB1 and verifies that the red "OPEN" indication is illuminated and the green "CLOSED" indication is extinguished.

___ SAT Examiner Note: This valve will already be open 6 5 COMMENTS: __ UNSAT VERIFY flow exists in any HPI header.

STANDARD: The candidate locates HPI Flow Train A and B flow meters on 1UB1 and flow is verified.

___ SAT 7 6 COMMENTS:

__ UNSAT

RO-P403 b Page 8 of 15 Perform the following:

A. Place 1RC-66 SETPOINT SELECTOR to OPEN *CRITICAL STEP B. Depress 1RC-66 OPEN PERMIT pushbutton STANDARD: The candidate: ___ SAT

• *Rotates 1RC-66 SETPOINT SELECTOR switch on 1UB1 to the OPEN position

• *Depresses 1RC-66 OPEN PERMIT pushbutton on 1UB1

__ UNSAT

• Verifies PORV is open by verifying that the red "OPEN" 8 7 indication is illuminated and the PORV Flow Statalarm (1SA18/A1) is in alarm.

EXAMINER NOTE: This stops the 5 minute Time Critical time clock.

Time = _____________.

COMMENTS:

Verify at least two HPI pumps operating.

___ SAT STANDARD: The candidate verifies that three HPI pumps are operating.

9 8 COMMENTS:

___ UNSAT

RO-P403 b Page 9 of 15 Verify flow in both HPI headers is in the acceptable region of Figure 1 (Required HPI Flow Per Header).

STANDARD: The candidate verifies flow in both HPI headers is in the

___ SAT acceptable region of Figure 1 below.

__UNSAT 10 9 COMMENTS:

Verify flow exists in any HPI header

___ SAT STANDARD: The candidate locates HPI Flow Train A and B flow meters on 1UB1. Loop A and Loop B flow is verified.

11 10 Examiner Note: This flow has already been verified in step 7

__ UNSAT COMMENTS:

RO-P403 b Page 10 of 15 Perform the following:

A. Place 1RC-66 SETPOINT SELECTOR to OPEN ___ SAT B. Depress 1RC-66 OPEN PERMIT pushbutton STANDARD:The candidate:

___ UNSAT

• Verifies 1RC-66 SETPOINT SELECTOR switch on 1UB1 in the OPEN position 12 11

• Depresses 1RC-66 OPEN PERMIT pushbutton on 1UB1

• Verifies PORV is open by verifying that the red "OPEN" indication is illuminated and the PORV Flow Statalarm (1SA18/A1) is in alarm.

Examiner Note: This flow has already been verified in step 8 COMMENTS:

Verify > one RCP operating.

STANDARD: Candidate determines that ALL RCPs are operating. ___ SAT 13 12 COMMENTS:

___ UNSAT NOTE:

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

Stop all but one RCP.

___ SAT 14 13 STANDARD: The candidate stops ALL but one RCP by rotating their control switches to OFF position.

___ UNSAT COMMENTS:

RO-P403 b Page 11 of 15 IAAT the following limits are exceeded

___ SAT

___ UNSAT 15 14 THEN throttle HPI to maximize flow flow limit.

STANDARD: The candidate verifies header flows less than the limits in the table above.

COMMENTS:

De-energize all PZR heaters. CRITICAL STEP STANDARD: The candidate:

• Rotates the PZR heater bank #1 switch on 1UB1 to the ___ SAT "OFF" position.

16 15

• Presses the OFF pushbutton controls for PZR heater banks 2, 3 and 4 on 1UB1

___ UNSAT COMMENTS:

RO-P403 b Page 12 of 15 Close 1HP-5 (LETDOWN ISOLATION) CRITICAL STEP STANDARD: The candidate:

• Rotates the switch for 1HP-5 on 1UB1 to the closed position. ___ SAT 17 16

• Observes the red OPEN light go off and the green CLOSED light come on.

___ UNSAT COMMENTS:

Close the following:

___ SAT

• __ TBVs

• __ 1FDW-35

• __ 1FDW-44

___ UNSAT STANDARD: The candidate places the TBVs in HAND and reduces demand to zero using the toggle switch OR if the Turbine Master is in 18 17 manual, verifies the TBVs are closed by observing the green closed light ON and the red open light OFF.

The candidate places 1FDW-35 and 1FDW-44 to HAND and reduce demands to zero using the toggle switches.

COMMENTS:

RO-P403 b Page 13 of 15 IAAT all HPI is lost,

___ SAT THEN:

A. Stop all RCPs B. Position 1RC-66 SETPOINT SELECTOR to HIGH ___ UNSAT 19 18 STANDARD: The candidate verifies HPI is available and operating and the IAAT step does not apply at this time.

COMMENTS:

WHEN directed by CRS,

___ SAT THEN EXIT.

___ UNSAT STANDARD: The candidate announces that Rule 4 is complete with outstanding IAATs and returns the Cue sheet to the examiner 20 19 indicating he has completed his JPM.

COMMENTS:

END TASK TIME STOP: ________

RO-P403 b Page 14 of 15 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

3 Step is required provide proper system alignment for HPI forced cooling flow 5 Step required to allow flow in both HPI headers 8 Step is required to open the PORV to initiate HPI forced cooling through the core (TCA

1. 26).

14 Step required to limit the heat input to the RCS 16 Step required to limit the heat input to the RCS 17 Step required to Reduce the amount of heat energy added to the RB Containment

RO-P403 - b Page 15 of 15 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS

• Unit 1 has tripped following a total loss of feedwater

• IMAs are complete

• The crew has been performing Rule 3 (Loss of Main or Emergency FDW) to regain heat transfer

• CBP feed could NOT be established and PSW SG feed is NOT available

• Efforts to restore steam generator heat transfer per Rule # 3 have NOT been successful

• You are at the Step 23 (WHEN) step in Rule 3 (Loss of Main or Emergency FDW)

INITIATING CUE The CRS directs you to review outstanding IAAT Steps This JPM is Time Critical

RO-S404a - e Page 1 of 15 REGION II JOB PERFORMANCE MEASURE RO-S404a Establish EFDW Flow Through Startup Valves Alternate Path: Yes Alt Path

Description:

____1FDW-315 failed closed_________________________________

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

RO-S404a - e Page 2 of 15 REGION II JOB PERFORMANCE MEASURE Task Title : Establish EFDW flow through Startup valves Task Number :

Alternate Path: Yes Time Critical: No Validation Time: 10 minutes K/A Rating(s):

System: APE-054 K/A: AA2.04 Rating: 4.2/4.3 Task Standard:

EFDW flow is established to the affected header through the startup valve.

References:

EOP Rule 3, (Loss of Main or Emergency FDW)

EOP Rule 7, (SG Feed Control)

EOP Enclosure 5.27, (Alternate Methods for Controlling EFDW Flow)

Tools/Equipment/Procedures Needed:

EOP Rule 3, (Loss of Main or Emergency FDW) (0L, Rev. 01)

EOP Rule 7, (SG Feed Control) (0L, Rev. 01)

EOP Enclosure 5.27, (Alternate Methods for Controlling EFDW Flow) (0O, Rev. 01)

===================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

RO-S404a - e Page 3 of 15 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS

1. RECALL SNAP 213

2. IMPORT files for RO-S404a

3. ENSURE clean procedure in place for candidate

4. WHEN directed by Lead Examiner, go to RUN

====================================================================

Directions without a SNAP:

1. Initialize simulator to desired IC. (Example Recall IC-41 100% EOL)

2. Take any required action: (Example: Perform EOP Encl.5.1, stop RCPs, open pump breakers, throttle EFDW flow etc.)

3. Activate Malfunctions, Build Timers and Overrides as required:

(Example: Activate MPS400 @ 100% on AOR)

4. Acknowledge alarms and Freeze the Simulator at desired point

5. Save to a SNAP Number and password protect, as desired.

RO-S404a - e Page 4 of 15 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS

• The reactor has just tripped from 25% power

• Immediate Manual Actions are complete INITIATING CUES The CRS directs you to perform a Symptoms Check

RO-S404a - e Page 5 of 15 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP Performs a Symptom Check

___ SAT STANDARD: Performs Symptom Check and determines that there are no symptoms to report but will perform Rule 3 due to a loss of Main Feedwater

___ UNSAT 1 EXAMINER CUE: CRS acknowledges performing Rule 3 due to a Loss of Main Feedwater.

COMMENTS:

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

__ Turbine Building Flooding.

__ actions taken to increase SG level due to Turbine Building Flooding.

STANDARD: Observes that TB Flooding is NOT occurring by 2SA-18/A- ___ SAT Rule 11 (Turbine BSMT Water Emergency High Level) NOT 3 illuminated.

2 (OP/2/A/6102/018)

Step 1 Candidate will perform RNO step and GO TO step 3. ___ UNSAT COMMENTS:

RO-S404a - e Page 6 of 15 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

___ SAT

• Pzr level reaches 375 [340 acc]

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

3 3 STANDARD: Candidate determines Rule 4 is not required. ___ UNSAT Continue to Step 4.

COMMENTS:

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

STANDARD: Observes MD EFDWP & TD EFDWP running with switch red lights on and normal discharge pressure.

Continue to Step 5. ___ SAT 4 4 COMMENTS:

___ UNSAT Verify any EFDW Pump is operating.

___ SAT STANDARD: Checks MD EFDWP & TD EFDWP red lights are on and Pumps have normal discharge pressure.

5 5 Continue to Step 6.

___ UNSAT COMMENTS:

RO-S404a - e Page 7 of 15 GO TO step 38.

STANDARD: GO TO step 38. ___ SAT COMMENTS:

6 6

___ UNSAT 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.

___ SAT STANDARD: Determines that 1FDW-315 is NOT controlling properly (1A SG level is < 30 and decreasing). Concludes that 1FDW-315 has failed closed.

7 38 Continue to Step 39. ___ UNSAT COMMENTS:

Place EFDW valve in MANUAL.

STANDARD: Place 1FDW-315 in MANUAL by depressing the A/M ___ SAT pushbutton on the Moore controller.

Continue to Step 40.

8 39 COMMENTS:

___ UNSAT

RO-S404a - e Page 8 of 15

[ALTERNATE PATH]

Control EFDW flow with EFDW valve in MANUAL.

STANDARD: Determine that 1FDW-315 will NOT control in MANUAL.

___ SAT Perform RNO, GO TO Step 42.

9 40 Continue to step 42 COMMENTS: ___ UNSAT Notify CRS that Encl 5.27 (Alternate Methods for Controlling EFDW Flow) is being initiated. CRITICAL STEP STANDARD: Removes Encl. 5.27 from EOP and initiates.

EXAMINER CUE: CRS acknowledges entry into Enclosure 5.27. ___ SAT 10 42 COMMENTS:

___ UNSAT Identify the failure:

1FDW-315 has failed CLOSED [GO TO Step 2]

___ SAT Encl. STANDARD: Candidate determines the next procedural step from table in Step 1.Continue to Step 2.

5.27 11 COMMENTS:

Step ___ UNSAT 1

RO-S404a - e Page 9 of 15 Verify 1A MD EFDWP is operating STANDARD: Candidate verifies 1A MD EFDWP is operating. Verify red ___ SAT light on and white light off and normal discharge pressure.

Continue to Step 3.

12 2 COMMENTS:

___ UNSAT Stop 1A MD EFDWP STANDARD: *Candidate places 1A MD EFDWP switch to OFF. *CRITICAL STEP Verify red light off and white light illuminated.

Continue to Step 4. ___ SAT 13 3 COMMENTS:

___ UNSAT Verify 1B MD EFDWP is operating.

STANDARD: Candidate verifies 1B MD EFDWP is operating.

Verify red light on and white light off and normal discharge ___ SAT pressure.

Continue to Step 5.

14 4

___ UNSAT COMMENTS:

RO-S404a - e Page 10 of 15 Place 1 TD EFDW Pump in PULL TO LOCK *CRITICAL STEP STANDARD: *Candidate places the U1 TD EFDW Pump in PULL to LOCK. Candidate verifies red light is OFF and green light is ON.

___ SAT Continue to Step 6.

15 5 COMMENTS:

___ UNSAT Place 1FDW-35 in HAND and set demand to 0%

CRITICAL STANDARD: Candidate places 1FDW-35 in HAND and uses toggle STEP switch to reduce demand to 0%.

Continue to Step 7. ___ SAT 16 6 COMMENTS:

___ UNSAT

• CRITICAL Close 1FDW-33 STEP STANDARD: *Candidate closes 1FDW-33.

Candidate verifies red light is OFF and green light is ON.

___ SAT Continue to Step 8.

17 7 COMMENTS:

___ UNSAT

RO-S404a - e Page 11 of 15 Verify 1A MD EFDWP will be used.

STANDARD: Candidate determines that the 1A MD EFDWP will be used.

Continue to Step 9. ___ SAT EXAMINER CUE: If candidate asks if 1A MD EFDWP will be used, state that the CRS directs using the 1A MD EFDWP.

18 8

___ UNSAT COMMENTS:

Open 1FDW-374

• CRITICAL STEP STANDARD: *Candidate locates and opens 1FDW-374.

Candidate observes green closed light off and red open ___ SAT light on.

19 9 Continue to Step 10.

COMMENTS:

___ UNSAT Verify the following:

• 1FDW-36 closed

• 1FDW-38 open

___ SAT STANDARD: Candidate determines 1FDW-36 is closed by observing the green closed light ON and red open light OFF on 1VB3 or uses OAC indication.

Candidate determines 1FDW-38 is open by observing the 20 10 ___ UNSAT green closed light OFF and red open light lit ON 1VB3 or uses OAC indication.

Continue to Step 11.

COMMENTS:

RO-S404a - e Page 12 of 15 Start 1A MD EFDWP

• CRITICAL STANDARD: *Candidate places 1A MD EFDWP switch to RUN. STEP Candidate verifies pump start by observing white light is OFF and red light is ON and proper discharge pressure. ___ SAT Continue to Step 12.

21 11 COMMENTS:

___ UNSAT NOTE:

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

Flow from a MD EFDWP through a S/U control valve should be read on the MDEFWP DISCH FLOW gauge. ___ UNSAT 100 gpm could cause overcooling if adequate decay heat levels do NOT exist.

Verify either of the following exists:

22 12

• HPI Forced Cooling is maintaining core cooling

• CBP Feed providing SG feed STANDARD: Candidate determines that neither condition is met and goes to the RNO.

Continue to Step 12 RNO.

COMMENTS:

RO-S404a - e Page 13 of 15 IF any SG is being fed, THEN perform the following:

• Throttle 1FDW-35 to establish a maximum of 100 gpm.

• Throttle 1FDW-35 to obtain desired SG level per Rule 7 (SG Feed Control)

• Notify CR SRO of SG Feed Status STANDARD: Candidate throttles 1FDW-35 to attain ~ 100 gpm flow *CRITICAL initially on MD EFWP DISCH FLOW gauge or OAC EFW STEP graphic, then throttles 1FDW-35 as necessary to establish ~

25 S/U level (per Rule 7 table 4)

___ SAT Rule 7 Table 4 (All SCMs > 0°F AND any RCP on) specifies the level to establish when using EFDWP is 30 (use MFDW setpoint if feeding via S/U CVs). The MFDW setpoint (i.e.

when using the S/U CVs) is 25 S/U level since RCS RNO temperature is > 500°F. ___ UNSAT 23 12 Examiner Note: The candidate does not need to establish this level to complete the JPM. 1FDW-35 must be open and SG level increasing.

Examiner Cue: Another operator will continue with this procedure.

COMMENTS:

END TASK TIME STOP: ________

RO-S404a - e Page 14 of 15 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

10 This step is required to ensure the correct procedure is used.

13 This step is required to ensure the valves will operate.

15 This step is required to ensure the valves will operate.

16 This step is required to align the MD EFDWP to the S/U header.

17 This step is required to align the MD EFDWP to the S/U header.

19 This step is required to align the MD EFDWP to the S/U header.

21 This step is required to start the 1A MD EFDWP and provide a SG feed source.

23 This step is required to establish flow to the 1A SG.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS

• The reactor has just tripped from 25% power

• Immediate Manual Actions are complete INITIATING CUES The CRS directs you to perform a Symptoms Check

(AO-701) j Page 1 of 9 REGION II JOB PERFORMANCE MEASURE AO-701 RESTORATION OF ICS AUTO POWER Administrative: No Alternate Path: Yes Alt Path

Description:

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

(AO-701) j Page 2 of 9 REGION II JOB PERFORMANCE MEASURE Task Title : Restoration of ICS Auto Power Task Number : N/A Alternate Path: Yes Time Critical: No Validation Time: 15 minutes K/A Rating(s):

System: BW/A02 K/A: AA1.1 Rating: 4.0/3.8 Task Standard:

ICS AUTO power is restored per AP/3/A/1700/023 (Loss of ICS Power)

References:

AP/3/A/1700/023 (Loss of ICS Power) Enclosure 5.2 (Restoration of ICS AUTO Power) (Rev. 23)

Tools/Equipment/Procedures Needed:

AP/3/A/1700/023 (Loss of ICS Power) Enclosure 5.2 (Restoration of ICS AUTO Power) (Rev. 23)

(Note: Below this line is used only for Initial NRC Exams)

===================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

(AO-701) j Page 3 of 9 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS None

(AO-701) j Page 4 of 9 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS Unit 3 operating at 100% power 3SA-2/B-11 (ICS AUTO POWER FAILURE) is actuated INITIATING CUE The Control Room SRO directs you to use AP/3/A/1700/023 (Loss of ICS Power) .2 (Restoration of ICS AUTO Power) to restore ICS AUTO power on Unit 3.

(AO-701) j Page 5 of 9 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP Verify the following breakers closed (Unit 3 Cable Rm):

__ 3KRA breaker #1 (100A 1P, ICS POWER PANELBOARD 3KI)

__ 3KI breaker #1 (30A 1P, AUTO POWER (ICS/ACS))

___ SAT STANDARD: Locate 3KRA panel board breaker #1 and verify it is closed.

Examiner Cue: Indicate to the candidate that 3KRA breaker #1 is CLOSED Locate 3KI panel board breaker #1 and verify it is closed 1 1 ___ UNSAT Examiner Cue: Indicate to the candidate that 3KI breaker #1 is tripped OPEN.

Continue Step 1 RNO COMMENTS:

1. Reset and close the affected breakers (Unit 3 Cable Rm):

__ 3KRA breaker #1 (100A 1P, ICS POWER PANELBOARD 3KI)

__ *3KI breaker #1 (30A 1P, AUTO POWER (ICS/ACS))

2. IF either of the above breakers fails to remain closed, THEN notify CR SRO to have SPOC assist in resetting and closing any open ___ SAT breakers

3. WHEN both of the above breakers are closed, THEN continue 1 STANDARD: Resets and closes 3KI BREAKER #1 by taking the ___ UNSAT 2

RNO breaker to the open position and then closing it.

Examiner Cue: Indicate to the candidate that 3KI breaker #1 is CLOSED.

COMMENTS:

(AO-701) j Page 6 of 9 ALTERNATE PATH NOTE The following step will require contacting Unit 3 Control Room Verify ICS AUTO power has been restored as indicated by 3SA-2/B-11 (ICS AUTO POWER FAILURE) off ___ SAT STANDARD: Contacts Unit 3 Control Room to verify ICS AUTO 3 2 power has been restored as indicated by 3SA-2/B-11 (ICS AUTO POWER FAILURE) off ___ UNSAT Examiner Cue: Inform candidate that 3SA-2/B-11 (ICS AUTO POWER FAILURE) remains actuated.

COMMENTS:

IF ICS AUTO power has NOT been restored, CRITICAL THEN bypass 3KI inverter as follows (KI BYP SW cabinet, Unit 3 STEP Equip Rm, North of col Q88)

A. Position SW#1 OFF (left switch)

B. Position SW#3 OFF (right switch) ___ SAT C. Position SW#2 ON (center switch)

STANDARD: Positions SW#1 to OFF (left switch).

Examiner Cue: Indicate to the candidate that SW#1 is OFF. ___ UNSAT 2

4 Positions SW#3 to OFF (right switch)

RNO Examiner Cue: Indicate to the candidate that SW#3 is OFF.

Positions SW#2 to ON (center switch Examiner Cue: Indicate to the candidate that SW#2 is ON.

COMMENTS:

(AO-701) j Page 7 of 9 Notify Unit 3 CR that all applicable steps of this enclosure have been completed STANDARD: Notify Unit 3 CR that all applicable steps of this enclosure have been completed. ___ SAT Examiner Cue: Inform candidate that the Control Room has been

___ UNSAT notified.

5 3 COMMENTS:

END TASK TIME STOP: ________

(AO-701) j Page 8 of 9 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

4 Step is required in proper sequence to align power to the 3KI bus.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Unit 3 operating at 100% power 3SA-2/B-11 (ICS AUTO POWER FAILURE) is actuated INITIATING CUE The Control Room SRO directs you to use AP/3/A/1700/023 (Loss of ICS Power) .2 (Restoration of ICS AUTO Power) to restore ICS AUTO power on Unit 3.

AO-804 i Page 1 of 9 REGION II JOB PERFORMANCE MEASURE AO-804 AO Actions for Control Room Evacuation Administrative: No Alternate Path: No Alt Path

Description:

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

AO-804 i Page 2 of 9 REGION II JOB PERFORMANCE MEASURE Task Title : AO Actions for Control Room Evacuation Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 12 minutes K/A Rating(s):

System: APE068 K/A: AA1.07 Rating: (4.1/4.2)

Task Standard:

AO actions for Control Room Evacuation are completed IAW AP/1/A/1700/050 Encl. 5.6.

References:

AP/1/A/1700/050 Tools/Equipment/Procedures Needed:

AP/1/A/1700/050, Encl. 5.6 (Rev. 03)

(Note: Below this line is used only for Initial NRC Exams)

===================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

AO-804 i Page 3 of 9 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS None

AO-804 i Page 4 of 9 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS A fire has occurred in Unit 1 and 2 Control Room AP/1/A/1700/050 (Challenging Plant Fire) has been initiated Unit 1 and 2 Control Rooms are being evacuated AP/1/A/1700/050, Encl. 5.6 (AP/EOP AO Actions for Control Room Evacuation) is in progress up to step 2.

INITIATING CUE The CRS directs you to continue in AP/1/A/1700/050, Encl. 5.6 (AP/EOP AO Actions for Control Room Evacuation), beginning at step 2.

AO-804 i Page 5 of 9 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP NOTE Dress out is NOT required. RP will be notified at completion of this CRITICAL Enclosure. STEP Locally close the following:

__ 1FDW-315 (1A S/G EFDW CONTROL) ___ SAT (A-4, E Pen Rm, 10' N of Qa-68 against RB Wall)

__ 1FDW-316 (1B S/G EFDW CONTROL)

(A-4, W Pen Rm, 4' NE of W-70a, 4' up)

___ UNSAT STANDARD: Candidate locates 1FDW-315 and 1FDW-316 and 1 2 simulates rotating the handwheel clockwise to a hard stop.

Examiner Cue: Inform candidate that each valve is closed following handwheel rotation in the clockwise direction.

COMMENTS:

AO-804 i Page 6 of 9 Open the following breakers (A-4/ East Pen Rm):

__ 1XH-3A (Pzr Htr Group E Bkr) (already open)

__ 1XH-4A (Pzr Htr Group H Bkr)

CRITICAL

__ 1XI-3A (Pzr Htr Group F Bkr)

STEP

__ 1XI-4A (Pzr Htr Group I Bkr)

__ 1XJ-2A (Pzr Htr Group D Bkr)

___ SAT

__ 1XJ-3A (Pzr Htr Group G Bkr) (already open)

__ 1XJ-4A (Pzr Htr Group J Bkr)

__ 1XK-1A (Pzr Htr Group A-K Bkr)

___ UNSAT STANDARD: Candidate locates and simulates opening the following breakers by rotating the breaker handle counter clockwise to the OFF position:

__ 1XH-3A (Pzr Htr Group E Bkr) 2 3

__ 1XH-4A (Pzr Htr Group H Bkr)

__ 1XI-3A (Pzr Htr Group F Bkr)

__ 1XI-4A (Pzr Htr Group I Bkr)

__ 1XJ-2A (Pzr Htr Group D Bkr)

__ 1XJ-3A (Pzr Htr Group G Bkr)

__ 1XJ-4A (Pzr Htr Group J Bkr)

__ 1XK-1A (Pzr Htr Group A-K Bkr)

COMMENTS:

AO-804 i Page 7 of 9 Notify the CRS in the SSF Encl 5.6, (AP/EOP AO Actions for Control Room Evacuation) actions are completed.

STANDARD: Candidate notifies the CRS in the SSF that Encl. 5.6 actions are completed.

___ SAT Examiner Cue: Inform the candidate that the CRS has been notified and another operator will continue with 3 4 the procedure. ___ UNSAT COMMENTS:

END TASK TIME STOP: ________

AO-804 i Page 8 of 9 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

1 This step is required to secure EFDW to prevent challenging operation of the SSF.

2 This step is required to secure Pressurizer Heaters to prevent challenging operation of the SSF.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS A fire has occurred in Unit 1 and 2 Control Room AP/1/A/1700/050 (Challenging Plant Fire) has been initiated Unit 1 and 2 Control Rooms are being evacuated AP/1/A/1700/050, Encl. 5.6 (AP/EOP AO Actions for Control Room Evacuation) is in progress up to step 2.

INITIATING CUE The CRS directs you to continue in AP/1/A/1700/050, Encl. 5.6 (AP/EOP AO Actions for Control Room Evacuation), beginning at step 2.

AO-S403 k Page 1 of 11 REGION II JOB PERFORMANCE MEASURE AO-S403 AO Actions for Supply of Water to SSF Administrative: No Alternate Path: No Alt Path

Description:

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

AO-S403 k Page 2 of 11 REGION II JOB PERFORMANCE MEASURE Task Title : AO Actions for Supply of Water to SSF Task Number :

Alternate Path: No Time Critical: No Validation Time: 25 minutes K/A Rating(s):

System: Gen K/A: 2.1.20 Rating: (4.6/4.6)

Task Standard:

Flow path from CCW Discharge back to CCW inlet is aligned in accordance with AP/0/A/1700/046, Encl.

5.9 (Supply of Water to SSF).

References:

AP/0/A/1700/046 (Extensive Damage Mitigation) (Rev. 10)

Tools/Equipment/Procedures Needed:

AP/0/A/1700/046, Encl. 5.9 (Supply of Water to SSF) (Rev. 10)

(Note: Below this line is used only for Initial NRC Exams)

===================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

AO-S403 k Page 3 of 11 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS None

AO-S403 k Page 4 of 11 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS Unit 2 refueling outage in progress. Unit 2 CCW Condenser inlet piping has just been isolated.

No tags are hung.

An explosion occurred that disabled the Unit 3 Control Room and operating crew.

AP/0/A/1700/046 (Extensive Damage Mitigation) was initiated.

Unit 3 is being maintained in hot shutdown from the SSF in accordance with AP/46.

The dedicated Submersible Pump is inoperable and cannot be installed.

Keowee Lake level is 798 feet.

INITIATING CUE The Unit 2 CRS directs you to perform AP/0/A/1700/046, Encl. 5.9 (Supply of Water to SSF),

beginning at step 7, to align the CCW Discharge back to the CCW inlet.

AO-S403 k Page 5 of 11 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP Locally open the following CCW crossover valves to align all units to Unit 2 and the SSF:

__ *1CCW-40 (UNIT 1 CROSSOVER TIE) (T-1/K-22) *CRITICAL

__ *2CCW-41 (UNIT 2 CROSSOVER TIE) (T-1/J-40) STEP

__ *3CCW-42 (UNIT 3 CROSSOVER TIE) (T-1/K-44/45)

__ 3CCW-94 (UNIT 3 CROSSOVER TIE) (T-1/K-50)

___ SAT STANDARD: Candidate opens the following valves by rotating the handwheel in the counter clockwise direction to a hard stop; ___ UNSAT 1 7

__ *1CCW-40 (UNIT 1 CROSSOVER TIE) (T-1/K-22)

__ *2CCW-41 (UNIT 2 CROSSOVER TIE) (T-1/J-40)

__ *3CCW-42 (UNIT 3 CROSSOVER TIE) (T-1/K-44/45)

__ 3CCW-94 (UNIT 3 CROSSOVER TIE) (T-1/K-50)

COMMENTS:

Verify both of the following:

__ Keowee Lake level > 791'

__ Flow path from CCW Discharge back to CCW Inlet is desired STANDARD: Candidate determines Keowee lake level is > 791 feet and the flow path from CCW Discharge back to CCW ___ SAT Inlet is desired from information contained on the cue sheet.

___ UNSAT 2 8 Examiner Cue: If asked, inform the candidate that Keowee lake level is > 791 feet and the flow path from CCW Discharge back to CCW Inlet is desired.

COMMENTS:

AO-S403 k Page 6 of 11 Locally open the following Unit 1 valves:

__ 1CCW-75 (CONDENSATE COOLERS CCW SUPPLY)

(T-1/F-25)

__ 1CCW-76 (1A CONDENSATE COOLER CCW INLET) CRITICAL (T-1/F-25) STEP

__ 1CCW-78 (1B CONDENSATE COOLER CCW INLET)

(T-1/F-25)

___ SAT

__ 1CCW-77 (1A CONDENSATE COOLER CCW OUTLET)

(T-1/E-25)

__ 1CCW-79 (1B CONDENSATE COOLER CCW OUTLET)

(T-1/E-25) ___ UNSAT

__ 1CCW-86 (CONDENSATE COOLERS CCW FLOW CONTROL BYPASS) (T-1/E-26)

STANDARD: The following valves are opened by rotating the handwheel in the counter clockwise to a hard stop, or verified open by the position indicator:

__ 1CCW-75 (CONDENSATE COOLERS CCW SUPPLY)

(T-1/F-25)

__ 1CCW-76 (1A CONDENSATE COOLER CCW INLET) 3 9 (T-1/F-25)

__ 1CCW-78 (1B CONDENSATE COOLER CCW INLET)

(T-1/F-25)

__ 1CCW-77 (1A CONDENSATE COOLER CCW OUTLET)

(T-1/E-25)

__ 1CCW-79 (1B CONDENSATE COOLER CCW OUTLET)

(T-1/E-25)

__ 1CCW-86 (CONDENSATE COOLERS CCW FLOW CONTROL BYPASS) (T-1/E-26)

COMMENTS:

AO-S403 k Page 7 of 11 Locally open the following Unit 2 valves:

__ 2CCW-75 (CONDENSATE COOLERS CCW SUPPLY)

(T-1/F-30) CRITICAL

__ 2CCW-76 (2A CONDENSATE COOLER CCW INLET) STEP (T-1/F-30)

__ 2CCW-78 (2B CONDENSATE COOLER CCW INLET)

(T-1/F-30) ___ SAT

__ 2CCW-77 (2A CONDENSATE COOLER CCW OUTLET)

(T-1/D-30)

__ 2CCW-79 (2B CONDENSATE COOLER CCW OUTLET)

(T-1/D-30, 4' W.) ___ UNSAT

__ 2CCW-86 (CONDENSATE COOLERS CCW FLOW CONTROL BYPASS) (T-1/ D-30, 4' W.)

STANDARD: The following valves are opened by rotating the handwheel in the counter clockwise to a hard stop, or verified open by the position indicator:

__ 2CCW-75 (CONDENSATE COOLERS CCW SUPPLY)

(T-1/F-30)

__ 2CCW-76 (2A CONDENSATE COOLER CCW INLET) 4 10 (T-1/F-30)

__ 2CCW-78 (2B CONDENSATE COOLER CCW INLET)

(T-1/F-30)

__ 2CCW-77 (2A CONDENSATE COOLER CCW OUTLET)

(T-1/D-30)

__ 2CCW-79 (2B CONDENSATE COOLER CCW OUTLET)

(T-1/D-30, 4' W.)

__ 2CCW-86 (CONDENSATE COOLERS CCW FLOW CONTROL BYPASS) (T-1/ D-30, 4' W.)

COMMENTS:

AO-S403 k Page 8 of 11 Locally open the following Unit 3 valves:

__ 3CCW-75 (CONDENSATE COOLERS CCW SUPPLY)

(T-1/F-44) CRITICAL

__ 3CCW-76 (2A CONDENSATE COOLER CCW INLET) STEP (T-1/F-44)

__ 3CCW-78 (2B CONDENSATE COOLER CCW INLET)

(T-1/F-44) ___ SAT

__ 3CCW-77 (2A CONDENSATE COOLER CCW OUTLET)

(T-1/D-44)

___ UNSAT

__ 3CCW-79 (2B CONDENSATE COOLER CCW OUTLET)

(T-1/D-44)

__ 3CCW-86 (CONDENSATE COOLERS CCW FLOW CONTROL BYPASS) (T-1/ D-43/44)

STANDARD: The following valves are opened by rotating the handwheel in the counter clockwise to a hard stop, or verified open by the position indicator:

__ 3CCW-75 (CONDENSATE COOLERS CCW SUPPLY)

(T-1/F-44)

__ 3CCW-76 (2A CONDENSATE COOLER CCW INLET) 5 11 (T-1/F-44)

__ 3CCW-78 (2B CONDENSATE COOLER CCW INLET)

(T-1/F-44)

__ 3CCW-77 (2A CONDENSATE COOLER CCW OUTLET)

(T-1/D-44)

__ 3CCW-79 (2B CONDENSATE COOLER CCW OUTLET)

(T-1/D-44)

__ 3CCW-86 (CONDENSATE COOLERS CCW FLOW CONTROL BYPASS) (T-1/ D-43/44)

COMMENTS:

AO-S403 k Page 9 of 11 Notify TSC to continue efforts to supply water to the Unit 2 CCW Inlet piping for extended SSF operation STANDARD: Candidate notifies the TSC to continue efforts to supply water to the Unit 2 CCW Inlet piping for

___ SAT extended SSF operation Examiner Cue: Inform the candidate the TSC has been notified.

6 12

___ UNSAT COMMENTS:

END TASK TIME STOP: ________

AO-S403 k Page 10 of 11 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

1 This step is required to align the flow path from the CCW Discharge back to the CCW Inlet.

3 This step is required to align the flow path from the CCW Discharge back to the CCW Inlet.

4 This step is required to align the flow path from the CCW Discharge back to the CCW Inlet.

5 This step is required to align the flow path from the CCW Discharge back to the CCW Inlet.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Unit 2 refueling outage in progress. Unit 2 CCW Condenser inlet piping has just been isolated.

No tags are hung.

An explosion occurred that disabled the Unit 3 Control Room and operating crew.

AP/0/A/1700/046 (Extensive Damage Mitigation) was initiated.

Unit 3 is being maintained in hot shutdown from the SSF in accordance with AP/46.

The dedicated Submersible Pump is inoperable and cannot be installed.

Keowee Lake level is 798 feet.

INITIATING CUE The Unit 2 CRS directs you to perform AP/0/A/1700/046, Encl. 5.9 (Supply of Water to SSF),

beginning at step 7, to align the CCW Discharge back to the CCW inlet.

ADM-110 1.1B Page 1 of 12 REGION II JOB PERFORMANCE MEASURE ADM-110 Diverse Verification of Reactor Power Administrative: Yes Alternate Path: No Alt Path

Description:

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

ADM-110 1.1B Page 2 of 12 REGION II JOB PERFORMANCE MEASURE Task Title : Diverse Verification of Reactor Power Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 15 minutes K/A Rating(s):

System: Gen K/A: 2.1.45 Rating: 4.3/4.3 Task Standard:

Compare the average NI Power Range Rx power to the average Loop delta T power and determine that they are NOT within 2% of each other.

References:

PT/1/A/0600/001 (Periodic Instrument Surveillance) (Rev. 337)

PT/0/A/0600/001 A (Loss of Computer)

Picture of front board indications Tools/Equipment/Procedures Needed:

PT/1/A/0600/001 (Periodic Instrument Surveillance) (Rev. 337)

Picture of front board indications (Note: Below this line is used only for Initial NRC Exams)

===================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

ADM-110 1.1B Page 3 of 12 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS None

ADM-110 1.1B Page 4 of 12 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS Unit 1 is at 80% RTP of Cycle 29 PT/1/A/0600/001 (Periodic Instrument Surveillance) Enclosure 13.1 (Mode 1&2) has just been initiated for your shift OAC is unavailable.

No OAC alarms are present.

Transient Monitor is unavailable INITIATING CUE The Time = 2000 requirements on page 1 of 29 of PT/1/A/0600/001 (Periodic Instrument Surveillance), Enclosure 13.1 (Mode 1&2) are being performed. The CRS directs you to perform Step 1 and determine if the procedural requirements are met that will allow signing Step 1 as complete. Document your answer below.

ADM-110 1.1B Page 5 of 12 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP 1 1 If Rx critical, perform the following: (R.M.)

Record Core Thermal Power Indication every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. (R.M.)

STANDARD: Candidate reviews the note prior to step 1.1 concerning priority of power Indications to use for surveillance and determines that A through E are not available due to the OAC and Transient Monitor being out of service.

Candidate refers to the attached graphic and averages the four NI power ranges to determine (%) Reactor ___ SAT Power in accordance with Note 1.1F as follows:

NI-5 = 80.1 NI-6 = 79.9 ___ UNSAT 2 1.1 NI-7 = 79.8 NI-8 = 80.0 80.1 + 79.9 + 79.8 + 80.0 = 319.8 / 4 = 79.95 Candidate records 79.95 in the % Reactor Power (R.M.) column at 2000 and initials the Step 1.1 (R.M.)

column at 2000.

COMMENTS:

Verify NO CTP OAC alarms OR CTP OAC alarm response in progress. (R.M.)

STANDARD: Candidate determines there are no CTP OAC alarms. ___ SAT The OAC is unavailable. Candidate initials the Step 1.2 (R.M.) column at 2000.

3 1.2 ___ UNSAT COMMENTS:

ADM-110 1.1B Page 6 of 12 Verify diverse reactor power indications within + 2% per one of the 4 1.3 following:

Compare the following: (refer to Note 1.1)

• OAC Calculated Thermal Power Best OR

• OAC Calculated Thermal Power Secondary (if above ~ 25%

power)

___ SAT OR

• OAC Calculated Thermal Power Primary (if below ~ 25%

power) versus ___ UNSAT 5 1.3.1

• OAC Calculated Thermal Power Delta T STANDARD: Candidate determines these indications are not available due to the OAC being out of service and proceeds to step 1.3.2.

COMMENTS:

ADM-110 1.1B Page 7 of 12 Compare the following:

CRITICAL

• Average of NI-5, NI-6, NI-7, and NI-8 (refer to Note 1.1.F) STEP OR

• PID A5081 ICS Calculated Thermal Power Best available

___ SAT from the Transient Monitor. See Note 1.1.E above.

versus

• Average two RC Loop Ts from RC Loop T gauge and use Enclosure "Loop T Vs Reactor Power" to determine percent power from T ___ UNSAT STANDARD: Candidate refers to the attached graphic and averages the four NI power ranges, or uses the value for reactor power recorded per step 1.1, since PID A5081 ICS Calculated Thermal Power Best is not available from 6 1.3.2 the Transient Monitor.

NI-5 = 80.1 NI-6 = 79.9 NI-7 = 79.8 NI-8 = 80.0 80.1 + 79.9 + 79.8 + 80.0 = 319.8 / 4 = 79.95

[Acceptable band = 79.9 - 80.0]

COMMENTS:

ADM-110 1.1B Page 8 of 12 Compare the following:

• Average of NI-5, NI-6, NI-7, and NI-8 (refer to Note 1.1.F)

CRITICAL OR STEP

• PID A5081 ICS Calculated Thermal Power Best available from the Transient Monitor. See Note 1.1.E above.

versus ___ SAT

• Average two RC Loop Ts from RC Loop T gauge and use Enclosure "Loop T Vs Reactor Power" to determine percent power from T ___ UNSAT

1.3.2 STANDARD

Candidate refers to the attached graphic and 7 averages the Loop A and Loop B T indications:

con't.

Loop A = 37.2 Loop B = 37.4 37.2 + 37.4 = 74.6 / 2 = 37.3°F

[Acceptable band = 37°F - 37.3°F]

COMMENTS:

Compare the following: CRITICAL

• Average of NI-5, NI-6, NI-7, and NI-8 (refer to Note 1.1.F) STEP OR

• PID A5081 ICS Calculated Thermal Power Best available ___ SAT from the Transient Monitor. See Note 1.1.E above.

versus

• Average two RC Loop Ts from RC Loop T gauge and use ___ UNSAT Enclosure "Loop T Vs Reactor Power" to determine percent power from T 1.3.2 8

con't.

STANDARD: Candidate refers to PT/1/A/0600/001, Enclosure13.11 (Loop T Vs Reactor Power), and using 37.3°F determines that Reactor Power from delta T is 85% ( + 2%).

COMMENTS:

ADM-110 1.1B Page 9 of 12 Compare the following:

• Average of NI-5, NI-6, NI-7, and NI-8 (refer to Note 1.1.F)

OR

• PID A5081 ICS Calculated Thermal Power Best available CRITICAL from the Transient Monitor. See Note 1.1.E above. STEP versus

• Average two RC Loop Ts from RC Loop T gauge and use ___ SAT Enclosure "Loop T Vs Reactor Power" to determine percent power from T

___ UNSAT STANDARD: Candidate compares the average of NI-5, NI-6, NI-7, and NI-8 (79.9 - 80%) to the percent power from T acquired from Enclosure 13.11 (Loop T Vs Reactor 1.3.2 Power) (85% +/- 2%), and determines the values are 9

con't. NOT within +/- 2%. Therefore step 1.3 cannot be signed off as complete.

EXAMINER NOTE: The candidate may stop prior to performing step 10 when they determine procedure step 1.3 cannot be signed off as complete. If so, the task will end here at step 9 and step 10 will not be performed.

COMMENTS:

ADM-110 1.1B Page 10 of 12 Verify CTPD set < 100%. (R.M.)

STANDARD: Candidate refers to the attached graphic of the Load Control Panel (LCP) and determines CTPD set = 80%.

Candidate initials the Step 1.4 (R.M.) column at 2000.

___ SAT EXAMINER NOTE: The candidate may stop prior to performing step 10 when they determine procedure step 1.3 cannot be signed off as complete. If so, 10 1.4 ___ UNSAT the task will end at step 9 and step 10 will not be performed.

COMMENTS:

END TASK TIME STOP: ________

ADM-110 1.1B Page 11 of 12 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

6 This step is required to determine % Rx Power from the average of NI-5, 6, 7, and 8.

7 This step is required to determine the correct T to use.

8 This step is required to determine % Rx Power from T.

9 This step is required to determine if the acceptance criteria for the step has been met.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Unit 1 is at 80% RTP of Cycle 29 PT/1/A/0600/001 (Periodic Instrument Surveillance) Enclosure 13.1 (Mode 1&2) has just been initiated for your shift OAC is unavailable.

No OAC alarms are present.

Transient Monitor is unavailable INITIATING CUE The Time = 2000 requirements on page 1 of 29 of PT/1/A/0600/001 (Periodic Instrument Surveillance), Enclosure 13.1 (Mode 1&2) are being performed. The CRS directs you to perform Step 1 and determine if the procedural requirements are met that will allow signing Step 1 as complete. Document your answer below.

RCS TEMPERATURES WITHDRAW POWER RANGE NIS NI 5 NI 6 NI 7 NI 8 LOOP TH TAVE TC TC NEUTRON ERROR REACTOR

% FP  % FP  % FP  % FP T

VESSEL LEVEL TRN A TRN B 80.1 79.9 79.8 80.0 37.2 596.9 579.3 561.6 00.0 0.46 000.0 70 620 620 620 100 +60 +60 +60 +60

+10 +5 125 125 125 125 610 610 610 60 +8 +4 600 600 600 80 100 +40 100 +40 100 +40 100 +40

+6 +3 I I L 50 L L L L L L L N N O O O 590 O O 590 O O 590 O O O O O O O O O +4 +2 W W 80 +20 80 +20 80 +20 80 +20 P P P P P P P P I I A A 580 580 580 N N T 60 T 40 A B A B A B C C ER E A B +2 +1 H H R 570 570 570 E E 0 0 0 0 S S 60 60 60 60 30 0 0 560 560 560 40

-2 -1 550 550 550 40 -20 40 -20 40 -20 40 -20 20

-4 -2 540 540 540 20 10 -6 -3 20 -40 20 -40 20 -40 20 -40 530 530 530

-8 -4 0 520 520 520 0 -60 -60 -60 -60 0 0 0 0

-10 -5 37.4 597.4 578.8 560.1 000.0 0.00 0.00 0.00 0.00 DEG F DEG F DEG F DEG F  % IMB  % IMB  % IMB  % IMB INSERT

RUNBACKS LOAD LIMITS REACTOR COOLANT ASYM FDW UNIT IN BY BY B\Y ON PUMP FLOW RODS PUMP TRACK FDW TURBINE REACTOR HIGH STATOR REACTOR GEN BKR PWR/ LOAD FDW TURBINE REACTOR 8 0 0 COOLANT TRIP TRIP UNBAL MANUAL MANUAL MANUAL CTP DEMAND C/FDW PRESSURE RATE SET 0 0  % / MIN

% / HR RATE RATE HOLD

% / Min  % / HR TURBINE LOAD TURBINE UNLOAD MAXIMUM RUNBACK 8 0 0 FAST INCREASE DECREASE SLOW CTPD SET

(ADM-111) 1.2R Page 1 of 11 REGION II JOB PERFORMANCE MEASURE ADM-111 Perform Manual RCS Leakage Calculation Administrative: Yes Alternate Path: No Alt Path

Description:

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

(ADM-111) 1.2R Page 2 of 11 REGION II JOB PERFORMANCE MEASURE Task Title : Perform Manual RCS Leakage Calculation Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 15 minutes K/A Rating(s):

System: Generic K/A: 2.1.20 Rating: 4.6/4.6 Task Standard:

RCS Leakage is calculated per the attached key.

References:

PT/0/A/0600/001A (Loss Of Computer) (Rev 42)

PT/1/A/0600/010 (Reactor Coolant Leakage) (Rev 95)

Tools/Equipment/Procedures Needed:

PT/1/A/0600/010 (Reactor Coolant Leakage) Encl. 13.3 (Manual RCS Leakage Calculation Data Sheet)

(Rev 95)

(Note: Below this line is used only for Initial NRC Exams)

=========================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

===================================================================================

Comments

(ADM-111) 1.2R Page 3 of 11 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS None

(ADM-111) 1.2R Page 4 of 11 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS Oconee Unit 1 OAC computer repairs are expected to be extended through turnover for hardware replacement.

The Loss of Computer procedure PT/0/A/0600/001A (Loss of Computer) is in progress, however an RCS Leakage Calculation has not been performed during this shift.

INITIATING CUES The CRS directs you to perform a manual RCS leakage calculation per PT/1/A/0600/010 (Reactor Coolant Leakage) Encl. 13.3 (Manual RCS Leakage Calculation Data Sheet) using the data collected below.

Manual RCS Leakage Data Parameter Initial Final Time 0015 0115 Pzr level 219.0 inches 220.7 inches Tave Indication 579.0°F 579.3°F Quench Tank Level 86.5 inches 86.5 inches LDST Level 76.7 inches 76.1 inches Power Range NI 100.0% 100.1%

RCS NR Pressure 2150 psig 2150 psig Group 7 Control Rod Position 92.7% 92.7%

(ADM-111) 1.2R Page 5 of 11 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP NOTE:

• If Tave is on-scale, use Tave. If Tave is off-scale, use Tcold

• If RCS NR Pressure is on-scale, use NR Pressure. If RCS NR Pressure is off-scale, use RCS WR Pressure Record Initial Data in "Table #1" Value Initial Data Minus Final Data Equals Change

___ SAT Pzr Lvl 219 Inches - inches = Inches (1)

RCS T 579 °F - °F = °F (2)

QT Lvl 86.5 inches - inches = Inches (3) ___ UNSAT LDST Lvl 76.7 inches - inches = Inches (4) 1 2.1 Rx Pwr 100.0  % -  % =  %

RCS P 2150 psig - psig = psig CR Pos 92.7  % -  % =  %

STANDARD: Student enters initial set of data into Table #1 of Enclosure 13.3 (Manual Leakage Calculation Data Sheet) from the initiating cue.

COMMENTS:

Record time Initial Data recorded: 0015

___ SAT STANDARD: Student enters 0015 (from initiating cue)

___ UNSAT 2 2.2 COMMENTS:

(ADM-111) 1.2R Page 6 of 11 After 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, record Final Data in "Table #1" Value Initial Data Minus Final Data Equals Change Pzr Lvl 219 Inches - 220.7 inches = Inches (1)

RCS T 579 °F - 579.3 °F = °F (2)

QT Lvl 86.5 inches - 86.5 inches = Inches (3) ___ SAT LDST Lvl 76.7 inches - 76.1 inches = Inches (4)

Rx Pwr 100.0  % - 100.1  % =  %

___ UNSAT RCS P 2150 psig - 2150 psig = psig 3 2.3 CR Pos 92.7  % - 92.7  % =  %

STANDARD: Student enters final set of data into Table #1 of Enclosure 13.3 (Manual Leakage Calculation Data Sheet) (from initiating cue)

COMMENTS:

Record time Final Data recorded: 0115

___ SAT STANDARD: Student enters 0115 4 2.4 COMMENTS:

___ UNSAT Record elapsed time: 60 minutes

___ SAT STANDARD: Student enters 60 minutes 5 2.5 COMMENTS: ___ UNSAT

(ADM-111) 1.2R Page 7 of 11 NOTE:

• Change = Initial - Final

• Negative sign (-) should be included with values as appropriate CRITICAL Calculate and record "Change" values in "Table # 1" STEP Value Initial Data Minus Final Data Equals Change

___ SAT Pzr Lvl 219 Inches - 220.7 inches = -1.7 nches (1)

RCS T 579 °F - 579.3 °F = -0.3 °F (2)

___ UNSAT QT Lvl 86.5inches - 86.5 inches = 0 Inches (3)

LDST Lvl 76.7inches - 76.1 inches = +0.6 inches (4) 6 2.6 Rx Pwr 100.0  % - 100.1  % = -0.1  %

RCS P 2150 psig - 2150 psig = 0 psig CR Pos 92.7  % - 92.7  % = 0  %

STANDARD: Student calculates the change in data and fills in Table 1 change column COMMENTS:

NOTE: Conversion Factor (6.831 inches/°F) must be positive (+)

value CRITICAL Calculate Corrected Pzr Level Change: STEP

-1.7 inches - (6.831 inches/°F X -0.3 °F) = +.349 inches (1) PZR Level Change Level Change due to Temp (2) Corrected PZR Level Change ___ SAT 7 2.7 STANDARD: -1.7 inches - (6.831 inches/°F X -.3°F) = +.349 inches

(+.340 to +.350) ___ UNSAT COMMENTS:

(ADM-111) 1.2R Page 8 of 11 Convert Corrected Pzr Level Change to gallons:

• CRITICAL

+.349 inches X 14.364 gallons / inch = +5.013 gallons STEP Corr PZR Lvl Change Conversion corr to 68°F PZR Vol Change

___ SAT STANDARD: +.349 inches X 14.364 gallons / inch = +5.013 gallons 8 2.8 (+.339 to + .359) (+4.883 to + 5.027)

___ UNSAT COMMENTS:

Convert QT Level Change to gallons: *CRITICAL 0 inches X 34.94 gallons / inch = 0 gallons STEP (3) QT Level Change Conversion corr to 68°F QT Vol Change

___ SAT 9 2.9 STANDARD: Determine there is no change for the QT

___ UNSAT COMMENTS:

Convert LDST Level Change to gallons: *CRITICAL

+0.6 inches X 30.956 gallons / inch = +18.574 gallons STEP (4) LDST Level Change Conversion corr to 68°F LDST Vol Change

___ SAT 10 2.10 STANDARD: +0.6 inches X 30.956 gallons / inch = +18.574 gallons (18.5 to 18.6)

___ UNSAT COMMENTS:

(ADM-111) 1.2R Page 9 of 11 Calculate Total Volume Change: *CRITICAL 5.013 gallons + 0 gallons + 18.574 gallons = 23.587 gallons STEP PZR Vol Change QT Vol Change LDST Vol Change Total Change

___ SAT 11 2.11 STANDARD: 5.013 gal + 0 gal + 18.574 gal = 23.587 gallons (4.883 - 5.027) (18.5-18.6) (23.383 - 23.627)

___ UNSAT COMMENTS:

Calculate "RCS Unidentified Leakage Rate": *CRITICAL 23.587 gallons ÷ 60 minutes Minutes = 0.393 gpm STEP Total Change (5) Duration RCS Leakage Rate

___ SAT 12 2.12 STANDARD: 23.587 gallons / 60 minutes = 0.393 gpm (23.383 - 23.627) (0.390 - 0.394)

___ UNSAT COMMENTS:

TIME STOP: ________

(ADM-111) 1.2R Page 10 of 11 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

6 Necessary data calculation to properly determine manual RCS leakage rate 7 Necessary data calculation to properly determine manual RCS leakage rate 8 Necessary data calculation to properly determine manual RCS leakage rate 9 Necessary data calculation to properly determine manual RCS leakage rate 10 Necessary data calculation to properly determine manual RCS leakage rate 11 Necessary data calculation to properly determine manual RCS leakage rate 12 Necessary data calculation to properly determine manual RCS leakage rate

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Oconee Unit 1 OAC computer repairs are expected to be extended through turnover for hardware replacement.

The Loss of Computer procedure PT/0/A/0600/001A (Loss of Computer) is in progress, however an RCS Leakage Calculation has NOT been performed during this shift.

INITIATING CUE The CRS directs you to perform a manual RCS leakage calculation per PT/1/A/0600/010 (Reactor Coolant Leakage) Encl. 13.3 (Manual RCS Leakage Calculation Data Sheet) using the data collected below.

Manual RCS Leakage Data Parameter Initial Final Time 0015 0115 Pzr level 219.0 inches 220.7 inches Tave Indication 579.0°F 579.3°F Quench Tank Level 86.5 inches 86.5 inches LDST Level 76.7 inches 76.1 inches Power Range NI 100.0% 100.1%

RCS NR Pressure 2150 psig 2150 psig Group 7 Control Rod Position 92.7% 92.7%

(ADM-205) 2R Page 1 of 11

• Similar to SRO JPM ADM-S204 and must be performed on the same day REGION II JOB PERFORMANCE MEASURE ADM-205 Determine LTOP Requirements Administrative: Yes Alternate Path: No Alt Path

Description:

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

(ADM-205) 2R Page 2 of 11 REGION II JOB PERFORMANCE MEASURE Task Title : Determine LTOP Requirements Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 30 minutes K/A Rating(s):

System: GENERIC K/A: 2.2.14 Rating: 3.9/4.3 Task Standard:

Per OP/1/A/1104/049, Low Temperature Overpressure Protection, based on conditions provided determine that logic paths required by Enclosure 4.13 will satisfy LTOP requirements.

References:

OP/1/A/1104/049 Low Temperature Overpressure Protection (LTOP)

OP/0/A/1108/001 Curves and General Information Tools/Equipment/Procedures Needed:

Unit 1 Conditions For Determining LTOP Requirements (Last page of JPM)

OP/1/A/1104/049 (Low Temperature Overpressure Protection) (Rev. 50)

OP/0/A/1108/001 Curves and General Information (Rev. 111)

(Note: Below this line is used only for Initial NRC Exams)

===================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

(ADM-205) 2R Page 3 of 11 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS None

(ADM-205) 2R Page 4 of 11 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS OP/1/A/1102/010 (Controlling Procedure for Unit Shutdown) is in progress for entering a refueling outage Plant conditions are as described in the attachment provided CRS has just been notified that the 1HP-120 travel stop is NOT installed correctly INITIATING CUE In accordance with Limit and Precaution 2.12 of OP/1/A/1104/049 (Low Temperature Overpressure Protection), determine if LTOP requirements are still met. Document your determination as directed in the Limit and Precaution.

Once you have completed the determination, sign and date in the blanks provided on .13 (LTOP Requirements Logic Diagram) and return it to the examiner.

(ADM-205) 2R Page 5 of 11 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP EXAMINER NOTE: The sequence of steps is NOT critical Determine if LTOP Train 1 requirements are met CRITICAL STEP STANDARD: Candidate Refers to OP/1/A/1104/049 (LTOP) Encl.

4.13 and attachment and circles or identifies the following: ___ SAT 1

• RC-4 open

___ UNSAT

• PORV Auto Operable COMMENTS:

Indicate the path that satisfies LTOP requirements for Train 1 STANDARD: Candidate should circle the plant/equipment configuration status and trace the logic path that ___ SAT satisfies Train 1 LTOP requirements as indicated on the attached key ___ UNSAT 2

COMMENTS:

(ADM-205) 2R Page 6 of 11 Determine if upper portion LTOP Train 2 requirements are met STANDARD: Candidate Refers to OP/1/A/1104/049 (LTOP) Encl.

4.13 and attachment and circles or identifies the following:

• 1A & 1B HPIPs racked out or in test, and tagged

• HPI START FROM PSW POWER CR switch tagged "Do Not Operate"

• 1C HPIP bkr racked out or in test, and tagged

• 1CF-1 Closed/handwheel tagged and bkr tagged open CRITICAL 3

• 1B CFT depressurized to < 373 psig STEP Examiner Note: Candidate may indicate additional equipment as meeting LTOP requirements, but only the ___ SAT equipment listed above that satisfies the logic of Enclosure 4.13 is critical. ___ UNSAT COMMENTS:

Indicate the path that satisfies LTOP requirements for the upper portion of Train 2 STANDARD: Candidate should circle the plant/equipment configuration status and trace the logic path that ___ SAT satisfies the upper portion of Train 2 LTOP 4 requirements as indicated on the attached key ___ UNSAT COMMENTS:

(ADM-205) 2R Page 7 of 11 Determine if lower portion LTOP Train 2 requirements are met STANDARD: Candidate Refers to OP/1/A/1104/049 (LTOP) Encl.

4.13 and attachment and circles or identifies the following:

• HPI NOT in operation and aligned via 1HP-120

• LTOP computer point O1L3153 not in alarm CRITICAL

• 1SA-2/C-3, C-4 cards not pulled/not in alarm STEP HIGH

• 1SA-18/A-3 card not pulled/not in alarm 5

• 1SA-18/A-4 card not pulled/not in alarm ___ SAT

• OAC operable

___ UNSAT

• 1N-121 Tagged Closed

• Pzr Htr Bank 4 Deactivated

• RCS pressure within limits

• Pzr level within limits COMMENTS:

Indicate the path that satisfies LTOP requirements for the lower portion of Train 2 STANDARD: Candidate should circle the plant/equipment configuration status and trace the logic path that ___ SAT satisfies the lower portion of Train 2 LTOP 6 requirements as indicated on the attached key ___ UNSAT COMMENTS:

Indicate that the logic path for LTOP requirements is satisfied CRITICAL STEP STANDARD: Candidate indicates that the logic paths for LTOP requirements are being satisfied in accordance with the attached key ___ SAT 7

___ UNSAT COMMENTS:

(ADM-205) 2R Page 8 of 11 Fill in the Performed By and Date/Time blanks STANDARD: Candidate completes the Performed By and Date/Time blanks ___ SAT 8 ___ UNSAT COMMENTS:

END TASK TIME STOP: ________

(ADM-205) 2R Page 9 of 11 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

1 Required to determine if Train 1 requirements are met 3 Required to determine if Train 2 requirements are met 5 Required to determine if Train 2 requirements are met 7 Required to determine if all LTOP requirements are met

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS OP/1/A/1102/010 (Controlling Procedure for Unit Shutdown) is in progress for entering a refueling outage Plant conditions are as described in the attachment provided CRS has just been notified that the 1HP-120 travel stop is NOT installed correctly INITIATING CUE In accordance with Limit and Precaution 2.12 of OP/1/A/1104/049 (Low Temperature Overpressure Protection), determine if LTOP requirements are still met. Document your determination as directed in the Limit and Precaution.

Once you have completed the determination, sign and date in the blanks provided on .13 (LTOP Requirements Logic Diagram) and return it to the examiner.

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

Unit 1 Conditions For Determining LTOP Requirements Procedures in progress:

OP/1/A/1102/010, Controlling Procedure for Unit Shutdown

• Encl. 4.10, S/D from Mode 3 to Mode 4 in progress RCS Parameters:

• Tc = 225°F slowly decreasing

• RCS Pressure = 285 psig decreasing

• Pressurizer Level = 218 inches decreasing slowly

• LPI operation (Series Mode) in progress Primary Systems/Components status:

• All HPI pumps are OFF

• 1B and 1C HPI Pumps are racked out and tagged

• 1A HPI Pump is racked in the TEST position and tagged

• HPI START FROM PSW POWER CR switch tagged "Do Not Operate"

• 1HP-26 and 1HP-27 are closed; hand wheels tagged and breakers tagged open

• 1HP-409 switch in CR has been tagged closed

• 1HP-410 switch in CR is closed but not tagged

• 1CF-1 is Closed / handwheel tagged and breaker tagged open

• 1CF-2 is Closed / handwheel tagged and breaker not tagged open

• 1A CFT pressure = 375 psig stable

• 1B CFT pressure = 368 psig stable

• Computer point O1L3153 is not in alarm

• Computer points O1X2285 and O1X2256 are locked out

• 1SA-2/C-3, 1SA-2/C-4, 1SA-18/A-3, and 1SA-18/A-4 cards are not pulled and not in alarm

• OAC is Operable

• 1N-121 is closed and tagged

• Pressurizer Heater Bank 4 is deactivated with breaker white tagged

• No dedicated LTOP Operator available

• An LTOP Vent path ( 3.6 square inches) is not established

• 1RC-4 is open

• PORV is operable with setpoint selected to LOW

ADM-305 3B Page 1 of 7 REGION II JOB PERFORMANCE MEASURE ADM-305 Determine Posting and Access Requirements of LPI Room Based on Plan View Administrative: Yes Alternate Path: No Alt Path Failure: ____________________________________________________________

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

Reviewed By: Date:

Approved By: Date:

ADM-305 3B Page 2 of 7 REGION II JOB PERFORMANCE MEASURE Task Title : Determine Posting and Access Requirements of LPI Room Based on Plan View Task Number : (N/A)

Alternate Path: (N/A)

Time Critical: No Validation Time: 15 minutes K/A Rating(s):

System: GEN K/A: 2.3.12 Rating: 3.2/3.7 Task Standard:

Determine that:

1. Area should be posted as a High Radiation Area

2. Continuous RP coverage is NOT required.

3. The total accumulated annual dose at completion of job is 1058 mrem.

References:

PD-RP-ALL-0001 Radiation Worker Responsibilities (Rev 4)

Survey Map of Room 61 Tools/Equipment/Procedures Needed:

PD-RP-ALL-0001 Radiation Worker Responsibilities (Rev 4)

Survey Map of Room 61

=========================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

ADM-305 3B Page 3 of 7 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS

1. NONE

ADM-305 3B Page 4 of 7 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS You are a Reactor Operator. An event has occurred which resulted in a significant change in the radiological conditions in Room 61 (LPI and RBS Pumps).

Your total whole body dose this year is 986 mrem.

INITIATING CUE Using the survey map provided, determine the following for Room 61:

• The RP related area posting(s) you would expect to encounter at the entry to Room 61

• If Continuous RP coverage is required for you to perform venting of the 1A LPI Pump

• If venting the 1A LPI pump takes two (2) hours, determine your total accumulated annual dose when the job is complete and you have exited the room based on the following:

o 10 minutes spent at 1A LPI Pump initiating the vent o 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 45 minutes spent in the LDWA o 5 minutes spent at 1A LPI Pump securing the vent

ADM-305 3B Page 5 of 7 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP Using the survey map provided, determine the area posting CRITICAL requirements. STEP STANDARD: Candidate reviews the survey map and determines: ___ SAT

• Based on an area around LPI sump pumps being 1 930 mr/hr (> 100 mr/hr at 30 cm), the area should ___ UNSAT be posted as a High Radiation Area (HRA).

COMMENTS:

Determine RP coverage required to vent the 1A LPI Pump CRITICAL STEP STANDARD: Candidate determines that continuous RP coverage is NOT required since the area is a HRA.

___ SAT 2

___ UNSAT COMMENTS:

Determine total accumulated annual dose after completion of job. CRITICAL STEP STANDARD: Candidate determines the dose as a result of the venting as follows:

___ SAT

.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> X 92 mr/hr = 23 mrem 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> X 28 mr/hr = 49 mrem ___ UNSAT 23 + 49 = 72 mrem 3

Determine the total accumulated annual dose following completion of the job.

986 + 72 = 1058 mrem COMMENTS:

END OF TASK TIME STOP: ________

ADM-305 3B Page 6 of 7 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

1 Determines General Area posting requirements for the room to be entered.

2 Determines RP continuous coverage requirements.

3 Determines total accumulated annual dose.

3.B CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS You are a Reactor Operator. An event has occurred which resulted in a significant change in the radiological conditions in Room 61 (LPI and RBS Pumps).

Your total whole body dose this year is 986 mrem.

INITIATING CUE Using the survey map provided, determine the following for Room 61:

• The RP related area posting(s) you would expect to encounter at the entry to Room 61

• If Continuous RP coverage is required for you to perform venting of the 1A LPI Pump

• If venting the 1A LPI pump takes two (2) hours, determine your total accumulated annual dose when the job is complete and you have exited the room based on the following:

o 10 minutes spent at 1A LPI Pump initiating the vent o 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 45 minutes spent in the LDWA o 5 minutes spent at 1A LPI Pump securing the vent

Room 61 LPI & RBS Pumps Survey # M-021506-17 Date/Time Today 0412 ROOM 61 LPI AND RB PUMPS N

AHU 1-6 *50

+30 98 1A 28 2

RBS Significant Dose Contributor STAIRS SUMP PUMPS 88 1

+1245

• 1947 95 92

+930 433 3 1C LPI 1A LPI 95 76 Summary of Highest Readings Comments: CONTACT RP REGARDING ANY ATTEMPTS TO CLEAN LPI ROOM SUMP Smears Air Samples & Wipes

1) 554 DPM/100 cm2 /g

2) 485 DPM/100 cm2 /g

3) 978 DPM/100 cm2 /g Symbol Legend (for example only) Type: Job Coverage Dose Rate

• 150 Contact Reading HS-50 Hot Spot RWP: 5036

+75 30 cm Reading RCA Posting Reactor Power = 100%

20 General Area Drip Bag 15 Smear 15 Air Sample 15 Wipe Unless otherwise noted, dose rates in mrem/hr.

Surveyor: W. Walters Approved by: N. Wriston, Date: Today

ADM-S108 1.2S Page 1 of 8 REGION II JOB PERFORMANCE MEASURE ADM-S108 Determine if SRO License Requirements are met Administrative: Yes Alternate Path: No Alt Path

Description:

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

ADM-S108 1.2S Page 2 of 8 REGION II JOB PERFORMANCE MEASURE Task Title : Determine if SRO License Requirements are met Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 15 minutes K/A Rating(s):

System: Gen K/A: 2.1.4 Rating: 3.3/3.8 Task Standard:

Completes Form 512-1 and determines requirements of NSD 512 are met.

References:

NSD 512 (Maintenance of RO/SRO NRC Licenses) (Rev. 07)

Tools/Equipment/Procedures Needed:

NSD 512 (Maintenance of RO/SRO NRC Licenses) (Rev. 07)

(Note: Below this line is used only for Initial NRC Exams)

===================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

ADM-S108 1.2S Page 3 of 8 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS None

ADM-S108 1.2S Page 4 of 8 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS You are a Shift Manager qualified SRO. Today is 10/29/16. Your work history for October of this year is as follows:

10/05/16 Worked 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> as Unit 3 BOP (day shift). Took turnover at beginning of shift and gave turnover at the end.

10/06/16 Worked 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as Unit 3 BOP (day shift). Took turnover at beginning of shift and gave turnover at end of shift.

10/07/16 Worked 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as Unit 3 OATC (day shift). Took turnover at beginning of shift and gave turnover at end of shift.

10/12/16 Worked 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as Unit 1 BOP (night shift). Took turnover at beginning of shift and gave turnover at end of shift.

10/13/16 Worked 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (night shift). Worked 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> as the SM and then 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> as WCC SRO. Took turnover at beginning and gave turnover at the end for his SM position and his WCC SRO position .

10/14/16 Worked 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as Unit 1 CR SRO (night shift). Took turnover at beginning of shift and gave turnover at end of shift.

10/20/16 Worked 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as Unit 3 OATC (day shift). Took turnover at beginning of shift and gave turnover at end of shift.

INITIATING CUE The SM directs you to review your work history for October, complete Section 3 of form NSD 512-1 based on the above work history, and determine if you meet NSD 512 requirements to maintain an active license for the following quarter for the following positions. Circle the appropriate response.

OATC YES NO BOP YES NO CRS YES NO SM YES NO

ADM-S108 1.2S Page 5 of 8 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP Evaluate 10/05/16 work period. CRITICAL STEP STANDARD: Determines that requirement is not met; <12hrs worked in position. ___ SAT 1

COMMENTS:

___ UNSAT Evaluate 10/06/16 work period.

CRITICAL STEP STANDARD: Determines that requirement is met and adds this period to Form 512-1. Required position for 12 hrs. with 2 Turnover at beginning and end of shift. ___ SAT COMMENTS:

___ UNSAT Evaluate 10/07/16 work period.

CRITICAL STEP STANDARD: Determines that requirement is met and adds this period to Form 512-1. Required position for 12 hrs. with 3 Turnover at beginning and end of shift. ___ SAT COMMENTS:

___ UNSAT Evaluate 10/12/16 work period.

CRITICAL STEP STANDARD: Determines that requirement is met and adds this period to Form 512-1. Required position for 12 hrs. with Turnover at beginning and end of shift. ___ SAT 4

___ UNSAT COMMENTS:

ADM-S108 1.2S Page 6 of 8 Evaluate 10/13/16 work period. CRITICAL STEP STANDARD: Determines that requirement is not met since 9 of the 5 hours were not at a required position (WCC SRO). ___ SAT COMMENTS:

___ UNSAT Evaluate 10/14/16 work period.

CRITICAL STEP STANDARD: Determines that requirement is met and adds this period to Form 512-1. Required position for 12 hrs. with 6 ___ SAT Turnover at beginning and end of shift.

COMMENTS:

___ UNSAT Evaluate 10/20/16 work period.

CRITICAL STEP STANDARD: Determines that requirement is met and adds this period to Form 512-1. Required position for 12 hrs. with 7 ___ SAT Turnover at beginning and end of shift.

COMMENTS:

___ UNSAT Compares credited time vs minimum requirements.

CRITICAL STANDARD: Determines that 5 12-hr shifts at a required position STEP have been completed and that the NSD-512 requirement of at least 1 shift/qtr at an SRO position

___ SAT (SM or CRS) is also met; so the individual meets the requirements to maintain their license active for the 8

OATC, BOP, CRS, and SM positions. Candidate should circle YES for all four of the above positions. ___ UNSAT COMMENTS:

TIME STOP: ________

ADM-S108 1.2S Page 7 of 8 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

1 Required to determine if minimum On Shift Experience requirements of NSD 512 have been met.

2 Required to determine if minimum On Shift Experience requirements of NSD 512 have been met.

3 Required to determine if minimum On Shift Experience requirements of NSD 512 have been met.

4 Required to determine if minimum On Shift Experience requirements of NSD 512 have been met.

5 Required to determine if minimum On Shift Experience requirements of NSD 512 have been met.

6 Required to determine if minimum On Shift Experience requirements of NSD 512 have been met.

7 Required to determine if minimum On Shift Experience requirements of NSD 512 have been met.

8 Required to make the determination regarding the minimum license requirement.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS You are a Shift Manager qualified SRO. Today is 10/29/16. Your work history for October of this year is as follows:

10/05/16 Worked 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> as Unit 3 BOP (day shift). Took turnover at beginning of shift and gave turnover at the end.

10/06/16 Worked 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as Unit 3 BOP (day shift). Took turnover at beginning of shift and gave turnover at end of shift.

10/07/16 Worked 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as Unit 3 OATC (day shift). Took turnover at beginning of shift and gave turnover at end of shift.

10/12/16 Worked 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as Unit 1 BOP (night shift). Took turnover at beginning of shift and gave turnover at end of shift.

10/13/16 Worked 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (night shift). Worked 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> as the SM and then 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> as WCC SRO. Took turnover at beginning and gave turnover at the end for his SM position and his WCC SRO position .

10/14/16 Worked 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as Unit 1 CR SRO (night shift). Took turnover at beginning of shift and gave turnover at end of shift.

10/20/16 Worked 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as Unit 3 OATC (day shift). Took turnover at beginning of shift and gave turnover at end of shift.

INITIATING CUE The SM directs you to review your work history for October, complete Section 3 of form NSD 512-1 based on the above work history, and determine if you meet NSD 512 requirements to maintain an active license for the following quarter for the following positions. Circle the appropriate response.

OATC YES NO BOP YES NO CRS YES NO SM YES NO

ADM-S204 2S Page 1 of 11

• Similar to RO JPM ADM-205 and must be performed on the same day REGION II JOB PERFORMANCE MEASURE ADM-S204 Determine LTOP Requirements and Required Actions Administrative: Yes Alternate Path: No Alt Path

Description:

Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

ADM-S204 2S Page 2 of 11 REGION II JOB PERFORMANCE MEASURE Task Title : Determine LTOP Requirements and Required Actions Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 35 minutes K/A Rating(s):

System: GENERIC K/A: 2.2.14 Rating: 3.9/4.3 Task Standard:

Based on conditions provided, determine that logic paths required by OP/1/A/1104/049, Low Temperature Overpressure Protection, Enclosure 4.13 are NOT satisfied and Tech Spec 3.4.12 Condition F must be entered.

References:

OP/1/A/1104/049 Low Temperature Overpressure Protection (LTOP) (Rev. 50)

OP/0/A/1108/001 Curves and General Information (Rev. 111)

Tools/Equipment/Procedures Needed:

Unit 1 Conditions For Determining LTOP Requirements (Last page of JPM)

OP/1/A/1104/049 (Low Temperature Overpressure Protection) (Rev. 50)

OP/0/A/1108/001 Curves and General Information (Rev. 111)

Tech Spec 3.4.12 (Low Temperature Overpressure Protection (LTOP) System)

(Note: Below this line is used only for Initial NRC Exams)

===================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

ADM-S204 2S Page 3 of 11 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS None

ADM-S204 2S Page 4 of 11 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS OP/1/A/1102/010 (Controlling Procedure for Unit Shutdown) is in progress for entering a refueling outage Plant conditions are as described in the attachment provided CRS has just been notified that the 1HP-120 travel stop is NOT installed correctly INITIATING CUE In accordance with Limit and Precaution 2.12 of OP/1/A/1104/049 (Low Temperature Overpressure Protection), determine if LTOP requirements are still met. Document your determination as directed in the Limit and Precaution.

Once you have completed the determination, sign and date in the blanks provided on .13 (LTOP Requirements Logic Diagram) and list Tech Spec required actions, if any, below.

ADM-S204 2S Page 5 of 11 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP EXAMINER NOTE: The sequence of steps is NOT critical Determine if LTOP Train 1 requirements are met CRITICAL STEP STANDARD: Candidate Refers to OP/1/A/1104/049 (LTOP) Encl.

4.13 and attachment and circles the following: ___ SAT 1

• RC-4 open

• PORV Auto Operable

___ UNSAT COMMENTS:

Indicate the path that satisfies LTOP requirements for Train 1 STANDARD: Candidate should circle the plant/equipment ___ SAT configuration status and trace the logic path that satisfies Train 1 LTOP requirements as indicated on the attached key ___ UNSAT 2

COMMENTS:

ADM-S204 2S Page 6 of 11 Determine if upper portion LTOP Train 2 requirements are met STANDARD: Candidate Refers to OP/1/A/1104/049 (LTOP) Encl.

4.13 and attachment and circles the following:

• 1A & 1B HPIPs racked out or in test, and tagged

• HPI START FROM PSW POWER CR switch tagged "Do Not Operate" CRITICAL

• 1C HPIP bkr racked out or in test, and tagged STEP

• 1CF-1 Closed/handwheel tagged and bkr tagged open

• 1B CFT depressurized to < 373 psig ___ SAT 3

Examiner Note: Candidate may indicate additional equipment as

___ UNSAT meeting LTOP requirements, but only the equipment listed above that satisfies the logic of Enclosure 4.13 is critical.

COMMENTS:

Indicate the path that satisfies LTOP requirements for the upper portion of Train 2 STANDARD: Candidate should circle the plant/equipment configuration status and trace the logic path that ___ SAT satisfies the upper portion of Train 2 LTOP 4 requirements as indicated on the attached key

___ UNSAT COMMENTS:

ADM-S204 2S Page 7 of 11 Determine if lower portion LTOP Train 2 requirements are met CRITICAL STANDARD: Candidate Refers to OP/1/A/1104/049 (LTOP) Encl. STEP 4.13 and attachment and circles the following:

• HPI NOT in operation and aligned via 1HP-120

• LTOP computer point O1L3153 not in alarm ___ SAT

• 1SA-2/C-3, C-4 cars not pulled/not in alarm HIGH

• 1SA-18/A-3 card not pulled/not in alarm

___ UNSAT

• 1SA-18/A-4 card not pulled/not in alarm

• OAC operable 5

• Pzr Htr Bank 4 Deactivated

• RCS pressure within limits

• Pzr level within limits Candidate determines the lower portion of Train 2 is NOT satisfied due to 1N-121 being closed only (NOT tagged closed).

COMMENTS:

Indicate the path that satisfies LTOP requirements for the lower portion of Train 2

___ SAT STANDARD: Candidate determines the lower portion of Train 2 is not satisfied due to 1N-121 being closed only (NOT 6 tagged closed). ___ UNSAT COMMENTS:

Indicate that the logic path for LTOP requirements is satisfied CRITICAL STEP STANDARD: Candidate determines the logic path for LTOP requirements is NOT satisfied due to 1N-121 being closed only (NOT tagged closed). ___ SAT 7

COMMENTS:

___ UNSAT

ADM-S204 2S Page 8 of 11 Fill in the Performed By and Date/Time blanks

___ SAT STANDARD: Candidate completes the Performed By and Date/Time blanks

___ UNSAT 8

COMMENTS:

Determine required actions.

STANDARD: Candidate determines compensatory measures to CRITICAL monitor for initiation of an LTOP event (dedicated STEP LTOP operator) must be established within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, in accordance with Tech Spec 3.4.12 Cond. F.

___ SAT 9

___ UNSAT COMMENTS:

END TASK TIME STOP: ________

ADM-S204 2S Page 9 of 11 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

1 Required to determine if Train 1 requirements are met 3 Required to determine if Train 2 requirements are met 5 Required to determine if Train 2 requirements are met 7 Required to determine if all LTOP requirements are met 9 Required to determine required actions.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS OP/1/A/1102/010 (Controlling Procedure for Unit Shutdown) is in progress for entering a refueling outage Plant conditions are as described in the attachment provided CRS has just been notified that the 1HP-120 travel stop is NOT installed correctly INITIATING CUE In accordance with Limit and Precaution 2.12 of OP/1/A/1104/049 (Low Temperature Overpressure Protection), determine if LTOP requirements are still met. Document your determination as directed in the Limit and Precaution.

Once you have completed the determination, sign and date in the blanks provided on .13 (LTOP Requirements Logic Diagram) and list Tech Spec required actions, if any, below.

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

Unit 1 Conditions For Determining LTOP Requirements Procedures in progress:

OP/1/A/1102/010, Controlling Procedure for Unit Shutdown

• Encl. 4.10, S/D from Mode 3 to Mode 4 in progress RCS Parameters:

• Tc = 225°F slowly decreasing

• RCS Pressure = 285 psig decreasing

• Pressurizer Level = 218 inches decreasing slowly

• LPI operation (Series Mode) in progress Primary Systems/Components status:

• All HPI pumps are OFF

• 1B and 1C HPI Pumps are racked out and tagged

• 1A HPI Pump is racked in the TEST position and tagged

• HPI START FROM PSW POWER CR switch tagged "Do Not Operate"

• 1HP-26 and 1HP-27 are closed; hand wheels tagged and breakers tagged open

• 1HP-409 switch in CR has been tagged closed

• 1HP-410 switch in CR is closed but not tagged

• 1CF-1 is Closed / handwheel tagged and breaker tagged open

• 1CF-2 is Closed / handwheel tagged and breaker not tagged open

• 1A CFT pressure = 375 psig stable

• 1B CFT pressure = 368 psig stable

• Computer point O1L3153 is not in alarm

• Computer points O1X2285 and O1X2256 are locked out

• 1SA-2/C-3, 1SA-2/C-4, 1SA-18/A-3, and 1SA-18/A-4 cards are not pulled and not in alarm

• OAC is Operable

• 1N-121 is closed

• Pressurizer Heater Bank 4 is deactivated with breaker white tagged

• No dedicated LTOP Operator available

• An LTOP Vent path ( 3.6 square inches) is not established

• 1RC-4 is open

• PORV is operable with setpoint selected to LOW

ADM-S405 4S Page 1 of 15 REGION II JOB PERFORMANCE MEASURE ADM-S405 Determine Emergency Classification and Protective Action Recommendations Administrative: Yes Alternate Path: No Alt Path

Description:

Time Critical: Yes Time Critical Criteria: ________________________________________________________

Prepared By: Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:

ADM-S405 4S Page 2 of 15 REGION II JOB PERFORMANCE MEASURE Task Title : Determine Emergency Classification and Protective Action Recommendations Task Number : N/A Alternate Path: No Time Critical: Yes Validation Time: 30 minutes K/A Rating(s):

System: Gen K/A: 2.4.38 Rating: 2.4/4.4 Task Standard:

Appropriate classification is determined and associated Emergency Notification Form is completed.

References:

RP/0/A/1000/01, Emergency Classification (Rev. 05)

RP/0/A/1000/02, Control Room Emergency Coordinator Procedure (Rev. 11)

RP/0/A/1000/015A, Offsite Communications From The Control Room BASIS Document (Volume A, Section D of the Emergency Plan)

Tools/Equipment/Procedures Needed:

RP/0/A/1000/01, Emergency Classification (Rev. 05)

RP/0/A/1000/02, Control Room Emergency Coordinator Procedure (Rev. 11)

(Note: Below this line is used only for Initial NRC Exams)

===================================================================

Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

ADM-S405 4S Page 3 of 15 SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS None

ADM-S405 4S Page 4 of 15 READ TO OPERATOR DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS Time: 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago:

• The Oconee County Sheriff reported that a large group of anti-nukes had assembled at the Visitor Center CURRENT CONDITIONS

• ALL three Units at 100% power

• Oconee County Sheriff reports that an explosion has occurred at the Keowee Hydro Dam, however the dam shows only minor damage with no breach

• Keowee personnel report no visible damage to the KHUs

• Security Shift Supervisor notifies the SM that security is responding to armed adversaries in the vicinity of the Unit 1 Main Transformer INITIATING CUE You are to perform the required actions of the Emergency Coordinator by referring to RP/0/A/1000/01, Emergency Classification:

1. Determine Emergency Classification at present time.

2. Complete appropriate Emergency Notification Form (ENF) for the current conditions.

Inform the examiner when you have made the classification.

THIS IS A TIME CRITICAL JPM Note: Do not use Emergency Coordinators judgment as the basis for classifying the event. When required, an operator will maintain the Emergency Coordinators Log and assume the duties of the Control Room Offsite Communicator.

ADM-S405 4S Page 5 of 15 START TIME: _______

SEQ PROC DESCRIPTION STEP STEP Classify the Event STANDARD: Refer to RP/0/A/1000/01 (Emergency Classification) CRITICAL Enclosure 4.6 (Fire/Explosions and Security Actions). STEP Classify the event as a Site Area Emergency(4.6.S.1) due to the following:

___ SAT A HOSTILE ACTION is occurring or has occurred within the PROTECTED AREA as reported by Security Shift Supervision 1 ___ UNSAT STOP TIME #1: Time SAE Declared __________

(Actual time) (SAT is < Start Time + 15 minutes)

COMMENTS:

Commence the Off-Site Notification Form.

STANDARD: Go to RP/0/A/1000/002 (Control Room Emergency ___ SAT Coordinator Procedure) and initiate procedure by determining symptoms for entry exist and check Step 1.1

___ UNSAT 2 1.1 COMMENTS:

IF an EAL exists, Declare the appropriate Emergency Classification level.

Classification __SAE_____ (UE, ALERT, SAE, GE)

___ SAT Time Declared: _________

___ UNSAT STANDARD: Candidate documents SAE and time declared from step 1.

3 2.1 COMMENTS:

ADM-S405 4S Page 6 of 15 IF a Security event is in progress THEN GO TO Step 2.4

___ SAT STANDARD: Determine Step 2.2 does apply and GO TO Step 2.4

___ UNSAT 4 2.2 COMMENTS:

Direct Control Room Offsite Communicator(s) to perform the following:

• Record Name _______________________

• REFER TO RP/0/A/1000/015 A (Offsite Communications From The ___ SAT Control Room), Immediate Actions steps 2.1 and 2.2 AND Enclosure 4.7 (Guidelines for Manually Transmitting a Message) in preparation for notifying offsite agencies. ___ UNSAT 5 2.4 STANDARD: Any name (real or imaginary) is acceptable.

Continue to step 2.5 COMMENTS:

IF AT ANY TIME changing plant conditions require an emergency classification upgrade, ...

STANDARD: An upgrade is not expected. Candidate should circle the step ___ SAT number and continue to step 2.6.

6 2.5

___ UNSAT COMMENTS:

ADM-S405 4S Page 7 of 15 NOTE: If more than one EAL of a classification level is met, use the EAL description of the most interest to offsite agencies.

Additional message sheets listing other information of interest to CRITICAL offsite agencies (e.g. transporting injured personnel) may be sent, STEP if needed.

For the case of more than one unit with different EAL entry

___ SAT conditions, the SM would declare the highest applicable EAL on the initial ENF to meet the time limit.

7 2.6 ___ UNSAT Obtain the applicable Emergency Notification Form (ENF) from the control room and complete as follows:

STANDARD: Initial Site Area Emergency form # 4.6.S.1 isselected and candidate continues to Step 2.6.1.

COMMENTS:

IF pre-printed forms are NOT available , perform the following:

A. Manually perform initial notification per RP/0/A/1000/015 A, enclosure for ___ SAT Guidelines for Manually Completing an Initial Message.

B. GO TO Step 2.7.

STANDARD: Candidate determines pre-printed forms are available and this ___ UNSAT step does not apply.

8 2.6.1 Continues to step 2.6.2 COMMENTS:

ADM-S405 4S Page 8 of 15 Ensure EAL # and description as determined by RP/0/A/1000/001 matches Line 4.

STANDARD: Candidate ensures EAL # on line 4 is 4.6.S.1 and EAL ___ SAT description is Hostile Action within the Protected Area.

Current plant conditions DO NOT threaten public safety.

9 2.6.2 Continues to step 2.6.3. ___ UNSAT COMMENTS:

Enter message # - Beginning at one, message numbers will increment every CRITICAL message, regardless of whether it is an UPGRADE.

STEP STANDARD: Candidate enters 1 as the message #. ___ SAT Continues to step 2.6.4.

10 2.6.3

___ UNSAT COMMENTS:

Line 1 - Mark appropriate box "Drill", "Actual Declaration" or "Termination" STANDARD: Candidate marks Drill in line 1.

Continues to step 2.6.5.

___ SAT 11 2.6.4 COMMENTS:

___ UNSAT

ADM-S405 4S Page 9 of 15 Line 4 - Time and date of declaration (Refer to time in Step 2.1)

CRITICAL STEP STANDARD: Candidate enters today's date and declaration time from step 2.1. ___ SAT 12 2.6.5 Continues to step 2.6.6.

COMMENTS: ___ UNSAT

ADM-S405 4S Page 10 of 15 NOTE:

• An EMERGENCY RELEASE is defined as an unplanned, quantifiable, airborne radiological release to the environment attributable to the emergency event.

• Some examples of conditions where airborne releases would be considered In-Progress are provided below. Not all bullets are CRITICAL required.

STEP

• This list is not intended to be all inclusive.

• The SM should then evaluate whether the release in-progress is considered attributable to the emergency event. If a ___ SAT radiological release was occurring prior to the emergency event and the radioactive release rate did NOT change because of the emergency event, then a release is NOT In-Progress and ENF line 5 would be marked None.

___ UNSAT Release Source Potential Indications SG Tube Leak

• 1,2,3 RIA-40 in alarm or rising

• Steam pressure maintained or rising in an isolated SG

• Level maintained or rising in an isolated SG Release from Unit Vent

• 1,2,3 RIA-45 or 46 in alarm or rising

• Notified by RP of significant release to the unit vent Release from Containment

• Containment pressure greater than 1 psig

• Actual Containment breach is determined 13 2.6.6 Line 5 - Perform one of the following:

A. IF there is NO emergency release occurring as a result of the declared event as defined above and as determined by the Shift Manager, mark "NONE".

B. IF there is an ongoing emergency release in accordance with the definition above as determined by the Shift Manager, mark "IS OCCURRING".

C. IF an emergency release as defined above and as determined by the Shift Manager has occurred previously during the declared emergency and is no longer occurring, mark "HAS OCCURRED".

STANDARD: Candidate determines NO release is occurring and marks NONE.

Continues to step 2.6.7.

COMMENTS:

ADM-S405 4S Page 11 of 15 Line 6 - IF Imminent Failure exists for Jocassee OR Keowee Hydro dam/dike, ensure following:

A. Check "OTHER".

B. Write: Move residents living downstream of the Keowee Hydro Project dams to higher ground. Prohibit traffic flow across bridges identified on your inundation maps until the danger has ___ SAT passed.

STANDARD: Candidate determines imminent failure does NOT exist for ___ UNSAT 14 2.6.7 Jocassee or Keowee Hydro dam/dike.

Candidate may mark NONE or leave step blank. Either is acceptable.

Continues to step 2.6.8.

COMMENTS:

ADM-S405 4S Page 12 of 15 NOTE: LINE 12 should be used to provide information important to offsite agencies. The following are examples of information which should be provided:

• Emergency Response Actions Underway (for example, site evacuation)

• Requests for offsite assistance (for example, ambulance or fire support)

• Facility Activation Status ___ SAT

• Injured/contaminated individuals

• Any reason causing/requiring a PAR change

• Estimate of any surface contamination in the plant, onsite or offsite

___ UNSAT

• If EAL description includes an "or". (example -Hostile action based EALs that include both a Hostile action "or" an airliner attack, provide more specific information in remarks section).

15 2.6.8 Line 12 - IF the SM has no remarks, write "None" STANDARD: Candidate may include information related to the event or write None in line 12. Either is acceptable.

Continues to step 2.6.9.

COMMENTS:

ADM-S405 4S Page 13 of 15 CRITICAL Line 13 - SM signature, CURRENT Time/Date (MUST SIGN)

STEP STANDARD: Candidate signs and enters current time/date in line 13. ___ SAT STOP TIME #2: Time for Notification __________

___ UNSAT (Actual time) (SAT is < Stop Time #1 + 15 minutes) 16 2.6.9 COMMENTS:

END TASK TIME STOP: ________

ADM-S405 4S Page 14 of 15 CRITICAL STEP EXPLANATIONS SEQ Explanation STEP #

1 The candidate needs to be able to utilize the procedure and determine the conditions meet a Site Area Emergency classification. This is a time critical step. The candidate needs to declare the SAE within 15 minutes of beginning the JPM. (The start of the JPM is the beginning of the assessment period) 7 The correct form that matches the EAL # is selected.

10 The correct message number is input on the ENF.

12 Declaration time and date are input on the ENF.

13 None is marked on line 5 of the ENF to indicate no release in progress.

16 The candidate signs and enters time and date on line 13 of the ENF. This is a time critical step. The time entered must be within 15 minutes of the declaration time in step 1.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Time: 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago:

• The Oconee County Sheriff reported that a large group of anti-nukes had assembled at the Visitor Center CURRENT CONDITIONS

• ALL three Units at 100% power

• Oconee County Sheriff reports that an explosion has occurred at the Keowee Hydro Dam, however the dam shows only minor damage with no breach

• Keowee personnel report no visible damage to the KHUs

• Security Shift Supervisor notifies the SM that security is responding to armed adversaries in the vicinity of the Unit 1 Main Transformer INITIATING CUE You are to perform the required actions of the Emergency Coordinator by referring to RP/0/A/1000/01, Emergency Classification:

1. Determine Emergency Classification at present time.

2. Complete appropriate Emergency Notification Form (ENF) for the current conditions.

Inform the examiner when you have made the classification.

THIS IS A TIME CRITICAL JPM Note: Do not use Emergency Coordinators judgment as the basis for classifying the event. When required, an operator will maintain the Emergency Coordinators Log and assume the duties of the Control Room Offsite Communicator.