ML20225A024

4B D-5 DCS ABNORMAL

6A C-5 PS-68-340A PRESSURIZER HIGH PRESSURE Indications

1-PI-68-340A RCS PZR PRESS reading full scale.

1-AR-M4-B D-5 ATC 5

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:2 Page 6 of 55 Event

Description:

Pzr Pressure Transmitter Fails High Time Position Applicant's Actions or Behavior BOP Refers to 1-AR-M6-A C-5 Examiner Note: Some steps, notes, and cautions in the Annunciator response procedure may have been omitted. Only those that are applicable are listed in this event guide.

6

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:2 Page 7 of 55 Event

Description:

Pzr Pressure Transmitter Fails High Time Position Applicant's Actions or Behavior ATC SRO Transitions AOP-I.04, Pressurizer Instrument Malfunction.

AOP-I.04 Step 1 thru Section 2.3 Step 1 thru 11 SRO ATC ATC 7

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:2 Page 8 of 55 Event

Description:

Pzr Pressure Transmitter Fails High Time Position Applicant's Actions or Behavior ATC PLACES PM-68-340A in MAINT BYP ATC PLACES PM-68-340A2 in MAINT BYP ATC ATC 8

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:2 Page 9 of 55 Event

Description:

Pzr Pressure Transmitter Fails High Time Position Applicant's Actions or Behavior Determines the following LCOs are applicable:

3.3.1 Condition A (for functions listed below) 3.3.1 Condition E (functions 6, 8.b) 3.3.2 Condition A (for functions listed below)

SRO 3.3.2 Condition D (function 1.d) 3.3.2 Condition Q.1 (function 8.b(2))

NOTE 3.3.1 Condition K (function 8 ) is not applicable below P-7 ATC ATC 9

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:2 Page 10 of 55 Event

Description:

Pzr Pressure Transmitter Fails High Time Position Applicant's Actions or Behavior ATC SRO SRO SRO 10

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:2 Page 11 of 55 Event

Description:

Pzr Pressure Transmitter Fails High Time Position Applicant's Actions or Behavior LCO 3.3.1 Condition A, E 11

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:2 Page 12 of 55 Event

Description:

Pzr Pressure Transmitter Fails High Time Position Applicant's Actions or Behavior 12

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:2 Page 13 of 55 Event

Description:

Pzr Pressure Transmitter Fails High Time Position Applicant's Actions or Behavior LCO 3.3.2 Condition A, D, Q 13

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:2 Page 14 of 55 Event

Description:

Pzr Pressure Transmitter Fails High Time Position Applicant's Actions or Behavior 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:3 Page 15 of 55 Event

Description:

Pzr Pressure Transmitter Fails High Time Position Applicant's Actions or Behavior EVENT 3- Feed Reg Bypass Valve fails 50% OPEN Direct simulator operator to insert Event 3 (KEY 3)

Indications available:

1-M4-B D-5DCS ABNORMAL Indications

Loop 3 SG Level rising 1-AR-M4-B D-5 ATC 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:3 Page 16 of 55 Event

Description:

Pzr Pressure Transmitter Fails High Time Position Applicant's Actions or Behavior BOP Refers to AOP-S.01 Step 1 thru Section 2.1 Step Examiners Note: It is expected that the crew will transition directly to AOP-S.01 BOP BOP 16

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:3 Page 17 of 55 Event

Description:

Pzr Pressure Transmitter Fails High Time Position Applicant's Actions or Behavior CT-FW CRITICAL PLACES 1-LIC-3-90 in MANUAL and uses <<, RAMP, and >> pushbuttons to BOP TASK establish manual control of FW flow BOP CT-FW CRITICAL BOP Manually controls FW flow to restore #3 SG level TASK BOP BOP 17

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:3 Page 18 of 55 Event

Description:

Pzr Pressure Transmitter Fails High Time Position Applicant's Actions or Behavior 18

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:4 Page 19 of 55 Event

Description:

IR CHANNEL FAILURE IR CHNL 2 fails to 22%

Time Position Applicant's Actions or Behavior EVENT 4- IR CHANNEL FAILURE IR CHNL 2 fails to 22%

Direct simulator operator to insert Event 4, (KEY 4)

Indications available:

4B B-2: IRS INTERMED RANGE HI FLUX LVL ROD WITHDRAWAL STOP Indications

1-XI-92-5004A slowly increasing to 22%

1-AR-M4-B B-2 Examiners Note: Some steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.

Examiners Note: Crew is expected to directly enter AOP-I.01 ATC SRO Enters AOP-I.01, Nuclear Instrument Malfunction 19

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:4 Page 20 of 55 Event

Description:

IR CHANNEL FAILURE IR CHNL 2 fails to 22%

Time Position Applicant's Actions or Behavior AOP-I.01 Step 1 thru Section 2.2 Step 10 SRO SRO SRO 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:4 Page 21 of 55 Event

Description:

IR CHANNEL FAILURE IR CHNL 2 fails to 22%

Time Position Applicant's Actions or Behavior Determines the following LCOs are applicable LCO 3.3.1 Conditions A, F (Function 4)

SRO LCO 3.3.3 Condition A (Function17.b)

SRO ATC ATC ATC ATC PLACES LEVEL TRIP switch in BYPASS 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:4 Page 22 of 55 Event

Description:

IR CHANNEL FAILURE IR CHNL 2 fails to 22%

Time Position Applicant's Actions or Behavior ATC SRO SRO 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:4 Page 23 of 55 Event

Description:

IR CHANNEL FAILURE IR CHNL 2 fails to 22%

Time Position Applicant's Actions or Behavior LCO 3.3.1 23

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:4 Page 24 of 55 Event

Description:

IR CHANNEL FAILURE IR CHNL 2 fails to 22%

Time Position Applicant's Actions or Behavior LCO 3.3.3 24

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:5 Page 25 of 55 Event

Description:

2 RCP #1 Seal Failure Time Position Applicant's Actions or Behavior EVENT 5- #2 RCP #1 Seal Failure Direct simulator operator to insert Event 5, (KEY 5)

Indications available:

5B B-3: FS-62-11 REAC COOL PMPS SEAL LEAKOFF HIGH FLOW Indications

1-FR-62-24 increasing to ~7.5 gpm 1-AR-M5-B 3 SRO Enters AOP-R.04, Reactor Coolant Pump Malfunctions.

25

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:5 Page 26 of 55 Event

Description:

2 RCP #1 Seal Failure Time Position Applicant's Actions or Behavior AOPR.04 Step 1 thru Section 2.2 Step 11 SRO SRO Directs actions from Section 2.2 26

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:5 Page 27 of 55 Event

Description:

2 RCP #1 Seal Failure Time Position Applicant's Actions or Behavior Examiners Note: Expected leakage is 7.5 gpm ATC ATC ATC 27

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:5 Page 28 of 55 Event

Description:

2 RCP #1 Seal Failure Time Position Applicant's Actions or Behavior RAISES #2 RCP Seal Injection flow by ADJUSTING 1-HIC-62-93A and/or 1-HIC-ATC 62-89A to raise seal injection flow above 9 gpm as indicated on1-FI-62-14A (RCP 2 SEAL WATER SUPPLY FLOW)

CREW Communications: IF contacted as Engineering, report that, Well will consult with the vendor and get back to you promptly.

ATC ATC ATC 28

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:5 Page 29 of 55 Event

Description:

2 RCP #1 Seal Failure Time Position Applicant's Actions or Behavior Examiners Note: Discuss the following step as necessary. Plant condition may prevent maintaining all RCPs within the specified 6-10 gpm range.

ATC CREW SRO Examiners Note: No LCOs are applicable SRO ATC 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:5 Page 30 of 55 Event

Description:

2 RCP #1 Seal Failure Time Position Applicant's Actions or Behavior ATC ATC SRO 30

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:6 Page 31 of 55 Event

Description:

Gland Seal Steam Regulator Fails Closed Time Position Applicant's Actions or Behavior EVENT 6- Gland Seal Steam Regulator Fails Closed Direct simulator operator to insert Event 6, (KEY 6)

Indications available:

*2A A-5: PIS-47-196 TURBINE SEAL STEAM PRESS ABNORMAL Indications

1-PI-47-187 LP TURB STEAM SEAL SUP PRESS lowers to zero 1-AR-M2-A Step 1 thru 2 Communications: If contacted to perform local inspection of gland steam report, Nothing abnormal.

BOP Momentarily PLACES HS-87-181 to OPEN and controlling pressure indicated on BOP PI-47-187 to approximately 120-130 psig. Continues to adjust as necessary to maintain pressure.

31

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:7 Page 32 of 55 Event

Description:

SBLOCA - COLD LEG LOOP 1 Time Position Applicant's Actions or Behavior EVENT 7 - SBLOCA - COLD LEG LOOP 1 Direct simulator operator to insert Event 7, (KEY 7)

Indications/Alarms:

Indications 1-M-4:

RCS PZR LVL, decreasing level value 1-M-5:

RCS PR PRESS (Chs 1-4), 1-PI-68-340A, 334, 323, 322: RCS (Pzr) pressure decreasing Annunciators 1-M-5C:

B-1: TS-30-31 LOWER COMPT TEMP HIGH

B-3: TS-30-241 LOWER COMPT MOISTURE HI

B-4: TS-30-240 LOWER COMPT MOISTURE HI 1-M-6E:

C-6: ZS-61-186 ICE CONDENSER LOWER INLET DOOR OPEN Examiners Note: RCPs automatically trip at 10 minutes to preserve critical task.

Examiners Note: Log time of Phase B (Containment pressure 2.8 psig) __________________

E-0 Steps 1 thru 12 CREW Performs the first four steps of E-0 unprompted.

SRO Directs performance of E-0 32

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:7 Page 33 of 55 Event

Description:

SBLOCA - COLD LEG LOOP 1 Time Position Applicant's Actions or Behavior ATC BOP BOP ATC Examiners Note: It is likely that the crew will identify The failure of Containment Spray at this point and take Prudent Actions for the failed actuation Examiners Note: Ensure time of Phase B (Containment pressure 2.8 psig) has been logged on previous page.

CRITICAL TASK (3) BOP Momentarily PLACES 1-HS-72-39A CNTMT SPRAY HDR 1A ISOL to OPEN.

CRITICAL Momentarily PLACES 1-HS-72-34A CNTMT PUMP 1A RECIRC to CLOSE (Not TASK (3) BOP critical if Containment Spray Flow is >4750 gpm)

BOP May place CSP-1B in PTL due to sheared shaft.

Examiners Note: FOLDOUT Page actions including RCP Trip Criteria (shown below) become applicable upon verification of Immediate Actions ATC 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:7 Page 34 of 55 Event

Description:

SBLOCA - COLD LEG LOOP 1 Time Position Applicant's Actions or Behavior PLACES the following handswitches in OFF (PTL acceptable):

1-HS-68-8A CRITICAL TASK (16) ATC 1-HS-68-31A 1-HS-68-50A 1-HS-68-73A ATC ATC ATC IF not already done, PLACES the following handswitches in OFF (PTL acceptable):

CRITICAL 1-HS-68-8A TASK (16) ATC 1-HS-68-31A 1-HS-68-50A 1-HS-68-73A Examiners Note: ES-0.5 Actions are shown on page 45 BOP ATC 34

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:7 Page 35 of 55 Event

Description:

SBLOCA - COLD LEG LOOP 1 Time Position Applicant's Actions or Behavior ATC Manually controls AFW flow to maintain total AFW flow greater than 440 gpm until ATC S/G are greater than 25% NR.

ATC ATC Manually controls AFW flow to maintain SG levels 25%-50% NR level.

ATC ATC Manually controls AFW flow between 440 and 600 gpm until > 25%.

ATC 35

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:7 Page 36 of 55 Event

Description:

SBLOCA - COLD LEG LOOP 1 Time Position Applicant's Actions or Behavior ATC ATC ATC 36

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:7 Page 37 of 55 Event

Description:

SBLOCA - COLD LEG LOOP 1 Time Position Applicant's Actions or Behavior E-1 Steps 1 thru 7 ATC ATC STOPS all RCP , if not already performed.

ATC ATC

/BOP BOP 37

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:7 Page 38 of 55 Event

Description:

SBLOCA - COLD LEG LOOP 1 Time Position Applicant's Actions or Behavior ATC ATC 38

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:8 Page 39 of 55 Event

Description:

A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Time Position Applicant's Actions or Behavior EVENT 8 - A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Event 8 is automatically inserted E-1 Steps 8 thru 12 Examiners Note:ATC may take prudent actions here or earlier in the event to Manually initiate Containment Spray. In the following step a Containment Spray pump is running with a sheared shaft and the other is running with the header discharge valve closed. The procedurally driven path is via ES-0.5 (see page 45)and FR-Z.1 (see page 41)

ATC ATC ATC ATC Momentarily DEPRESSES 1-HS-63-134A and 1-HS-63-134B ATC 39

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:8 Page 40 of 55 Event

Description:

A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Time Position Applicant's Actions or Behavior ATC ATC Momentarily PLACES 1-HS-74-10A and 1-HS-74-20A to STOP then to A AUTO ATC ATC Examiners Note: Scenario may be terminated when SI termination criteria are determined to be not met BOP 40

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:8 Page 41 of 55 Event

Description:

A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Time Position Applicant's Actions or Behavior BOP FR-Z.1 Steps 1 thru 11 ATC ATC ATC If not already done, Stops all RCPs 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:8 Page 42 of 55 Event

Description:

A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Time Position Applicant's Actions or Behavior ATC ATC ATC ATC ATC CRITICAL If not already done, Momentarily PLACES 1-HS-72-39A CNTMT SPRAY HDR 1A TASK (3) ATC ISOL to OPEN.atc ATC IF not already done, Momentarily PLACES 1-HS-72-34A CNTMT PUMP 1A ATC RECIRC to CLOSE ATC 42

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:8 Page 43 of 55 Event

Description:

A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Time Position Applicant's Actions or Behavior Examiners Note: Containment Air Return Fans will not AUTO START and cannot be started Manually ATC ATC 43

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:8 Page 44 of 55 Event

Description:

A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Time Position Applicant's Actions or Behavior ATC 44

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:8 Page 45 of 55 Event

Description:

A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Time Position Applicant's Actions or Behavior ES-0.5 Steps 1 thru 17 BOP Communications: When directed to perform ES-0.5 Attachment 7, acknowledge direction. No further action required.

BOP BOP BOP 45

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:8 Page 46 of 55 Event

Description:

A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Time Position Applicant's Actions or Behavior BOP 46

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:8 Page 47 of 55 Event

Description:

A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Time Position Applicant's Actions or Behavior BOP BOP 47

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:8 Page 48 of 55 Event

Description:

A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Time Position Applicant's Actions or Behavior 48

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:8 Page 49 of 55 Event

Description:

A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Time Position Applicant's Actions or Behavior BOP 49

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:8 Page 50 of 55 Event

Description:

A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Time Position Applicant's Actions or Behavior BOP BOP 50

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:8 Page 51 of 55 Event

Description:

A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Time Position Applicant's Actions or Behavior BOP If not already done, Momentarily PLACES 1-HS-72-39A CNTMT SPRAY HDR 1A BOP ISOL to OPEN.

CRITICAL IF not already done, Momentarily PLACES 1-HS-72-34A CNTMT PUMP 1A TASK (3) BOP RECIRC to CLOSE (Not critical if Containment Spray Flow is >4750 gpm)

CRITICA L TASK BOP If not already done, May place CSP-1B in PTL due to sheared shaft.

(3)

BOP 51

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:8 Page 52 of 55 Event

Description:

A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Time Position Applicant's Actions or Behavior Examiners Note: Containment Air Return Fans will not AUTO START and cannot be started Manually BOP BOP BOP 52

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:8 Page 53 of 55 Event

Description:

A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Time Position Applicant's Actions or Behavior ES-0.5 Appendix A Examiner Note: Appendix A and B step 2 is Unit 2 only 53

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:8 Page 54 of 55 Event

Description:

A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Time Position Applicant's Actions or Behavior ES-0.5 Appendix B ES-0.5 Step 18 thru end BOP Communications: When requested as Unit 2 RO, acknowledge direction to perform EA-0-1 BOP 54

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 1 Event No.:8 Page 55 of 55 Event

Description:

A Cont Spray Valve Failure With B Cont Spray Pump Shaft Shear Time Position Applicant's Actions or Behavior Communications: When requested as Unit 2, acknowledge request to perform EA-65-1 BOP BOP BOP Communications: When requested as available AUO, acknowledge direction to perform appendix F BOP 55

Today Mode 2 2% 0 MWe Train Week: B RCS Boron: 1571 ppm BAT A RCS Leakage:

EOOS: Green Last Shift: Dilution: Rx Plan Total: Rx plan Identified: 0.01 GPM Grid Status: Qualified This Shift: Boration: Rx plan Total: Rx plan Unidentified: 0.04 GPM Site Aggregate Risk: Low Shutdown LCO Conditions Equipment INOP Next Action Due Other LCO Actions Equipment INOP Next Action Due Info Only Tech Specs Equipment INOP Abnormal Equipment Lineup / Conditions (including significant Radiological changes)

Severe Thunderstorm warning is in effect for Hamilton County FT-1-3A Failed. In MAINT BYPASS Shift Priorities (Surveillances/Testing and Major Activities in Progress or Scheduled)

Maintain current power level while engineering completes evaluation for Part 21 issue For each MCR deficiency, a numbered square will be applied to the MCR Board near the associated indication/alarm. (US maintains magnets)

The CR/WO number and description of the issue will be listed below Main Control Room (7690)

Auxiliary Building (7671)

Turbine Building (7771)

TB Sump: LVWT Pond RCW: Unit 2 Aux Steam: Unit 1 Outside (7666) (423-710-4777)

Miscellaneous

2003 NRC SCN 1 Booth Instructions BOOTH OPERATOR INSTRUCTIONS Sim. Setup Reset IC-9 2% power BOL Perform switch check.

Verify control rod step counters reset.

Place simulator in RUN.

Place Mode 2 placard on panels.

Place B Train Week sign on the simulator.

Load SCN file: - ILT2003 NRC SCN 1 Make the following adjustments to establish RCP#2 Seal Injection at approximately 8.5 gpm Adjust FCV-62-93 to 65% OPEN Adjust FCV 62-89 to 45% OPEN For each SG place the associated Feedwater Valve Control in Force 1 Element SG#1 SG#2 SG#3 SG#4 Place FT-1-3A in MAINT BYP Acknowledge any alarms, allow the plant to stabilize, and freeze the simulator.

Perform the SIMULATOR OPERATOR CHECKLIST Place simulator in RUN before crew enters the simulator.

Start Data Capture

1. REMOVE ORANGE DOTS WHEN SCENARIO COMPLETE Page 1 of 4

2003 NRC SCN 1 Booth Instructions EVENT IC/MF/RF/OR # DESCRIPTION/EXPECTED ACTIONS/BOOTH FEEDBACK This is manually

FT-1-3A in Maintenance Bypass MAIN STEAM FLOW TRANSMITTER inserted during

IMF RX10A f:1 FAILS LOW FT-1-3A setup These controllers are

Set FCV-62-93 to 65% In order to establish Seal injection flow at manually

Set FCV-62-89 to 45% 8.5 gpm for RCP#2 adjusted during setup Throughout this scenario routine communications directing administrative actions, reports, or notifications may be answered by acknowledging the report or direction. Communications requiring reports back to the examinees will be scripted. Unexpected communications requiring report back will be approved by the Lead examiner prior to contacting the Control Room. .

When directed by the Lead ;---Lowering of condenser vacuum.

IMF CN09 f:0.15 k:1 Examiner, use ;---B condenser vacuum pump Auto start KEY 1 to insert IMF CN11B f:1 k:1 failure.

malfunction

---Auto delete malfunction when 1B

{zdihs2176a[2]} dmf CN09 condenser vacuum pump started A vacuum leak was found on the Following starting of standby Communication vacuum breaker flange. The leaking area condenser vacuum pump the field for Event 1 has been covered with plastic and operator will report that, maintenance has been contacted.

When directed by the Lead

---PZR PRESSURE TRANSMITTER FAILS Examiner, use IMF RX07A f: 1 k:2 TO VALUE CH 1 68-340 KEY 2 to insert malfunction All Pzr Pressure instruments are Communication IF directed to check Pzr Pressure reading normal in the Aux Control for Event 2 instrument in ACR then report Room.

When directed by the Lead IMF FW24C f:100 k:3 ;---#3SG Feed Reg Bypass Valve Fails Examiner, use OPEN KEY 3 to insert malfunction.

---Delete malfunction when valve taken to

{zdi1lic0030090h} DMF FW24C Manual If requested to investigate FRBV There is nothing abnormal with #3 Feed Communication locally Reg Bypass Valve.

for Event 3 Page 2 of 4

2003 NRC SCN 1 Booth Instructions EVENT IC/MF/RF/OR # DESCRIPTION/EXPECTED ACTIONS/BOOTH FEEDBACK When directed by the Lead

---IR CHANNEL FAILURE IR CHNL 1 fails Examiner, use IMF NI04A f: 91 r:60 k:4 to 22% over one minute KEY 4 to insert malfunction When directed by the Lead Examiner, use IMF CV17B f:0.11 r:90 k:5 ;---RCP 2 SEAL #1 FAILURE KEY 5 to insert malfunction.

Communication Well will consult with the vendor and IF contacted as Engineering for Event 5 get back to you promptly.

When directed by the Lead

---GLAND SEAL STEAM REGULATOR Examiner, use IMF MS09 f: 1 k:6 FAILS CLOSED KEY 6 to insert malfunction Communication If contacted to perform local inspection for Event 6 of gland steam Nothing abnormal.

When directed by the Lead Examiner, use IMF TH02A f:1.19 k:7 ;---SBLOCA - COLD LEG LOOP 1 KEY 7 to insert malfunction

---A SI PUMP 1A has a shaft shear IMF SI08A f: 1 k:7 (preserves CT)

IMF RC02A f:1 d:600 e:1 Automatically IMF RC02B f:1 d:600 e:1 ;---RCPs trip at 10 minutes to support inserted after IMF RC02C f:1 d:600 e:1 critical task Rx trip IMF RC02D f:1 d:600 e:1 Communication for Event 7

---SLAVE RELAY K644 FAILS - CONT EVENT 8 IMF RP16K644A f: 1 SPRAY ACT A Inserted from IMF CS02B f:1 ;---CNT SPRAY PUMP 1B-B SHEARED beginning SHAFT Page 3 of 4

2003 NRC SCN 1 Booth Instructions EVENT IC/MF/RF/OR # DESCRIPTION/EXPECTED ACTIONS/BOOTH FEEDBACK

---CONTAINMENT AIR RETURN FAN A Inserted from IMF CH08A f: 1 and B OVERCURRENT TRIP beginning IMF CH08B f:1

---To preserve Critical Task (CT-3)

Communication When directed to perform ES-0.5 Acknowledge direction. No further action for Event 8 Attachment 7 required.

Page 4 of 4

Appendix D Scenario Outline Form ES-D-1 Facility: Sequoyah Scenario No.: 2 Op Test No.: 2020-301 Examiners: Operators: SRO ATC BOP Initial Conditions: 100% BOL Turnover: Unit 1 is in MODE 1 100%, BOL FT-1-3A is in Maintenance Bypass Containment Spray Pump 1B OOS Severe Thunderstorm watch is in effect for Hamilton County Critical Tasks CT-36 Transfer the suction of the RHR pumps to the Containment Sump prior to RWST level reaching 8% during a LOCA inside Containment.

CT-29 Minimize RWST outflow by:

reducing Containment Spray flow .

reducing to one CCP and one SIP AND Establish RWST makeup, before reaching 8% RWST level.

CT-PRA Turn off all ECCS pumps taking suction from the RWST within 1.5 minutes of reaching 8% RWST level.

Event Malf. Event Event Description No. No. Type powerdow (R) ATC 1 Lower power from 100% to 94%.

n (N)BOP The 1A CCS Pump trip, failure of 1B CCS pump auto start. BOP will CC09B (C) BOP 2 manually start the 1B CCS pump using AOP-M.03. SRO addresses CC10A TS-SRO LCO

3 Heater Drain Tank level control fails resulting in a runback signal TCRLY2 3 (C)BOP with a failure of the Main Turbine Runback. BOP initiates Main HD06A Turbine runback using valve position limiter per AOP-S.04 Following runback, control rods continue to insert. ATC places (C) ATC control rods in manual per AOP-C.01 and may initiate boration to 4 RD17 TS-SRO restore rods above the insertion limit. The SRO enters the Rod Insertion Limit LCO as required.

(C) ATC A Small RCS Leak develops. The ATC will raise charging flow using 5 TH01C TS-SRO AOP-R.05. SRO addresses LCO LOCA_lb 6 (M) ALL LBLOCA. The B RHR pump trips at 35% RWST level.

TH01C Crew transitions from E-0 to E-1, then ES-1.3. Auto swapover to the 7 RH02 (C) ATC Containment Sump fails. ATC manually aligns ECCS suction to the sump.

The A RHR pump trips after sump swapover. Crew transitions to 8 RH01 (C) ATC ECA-1.1.

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

Appendix D Scenario Outline Form ES-D-1 2020-301 Scenario 2 Summary Event 1 - Crew lowers power from 100% to 94%%

Verifiable actions: (ATC) inserts control rods. BOP reduces Main Turbine load.

Event 2 - 1A CCS Pump trips with a failure of the 1B-B CCS pump to auto start. BOP manually starts the 1B CCS pump per AOP-M.03, Loss of Component Cooling Water. The SRO addresses LCO.

Verifiable actions: (BOP) starts 1B CCS pump.

Event 3 - # 3 Heater Drain Tank level control fails resulting in a runback signal with failure of Main Turbine Runback. BOP initiates Main Turbine runback using the valve position limiter per AOP-S.04, Condensate or Heater Drains Malfunction.

Verifiable actions: (BOP) runs back Main Turbine using valve position limiter.

Event 4 - Following the manual Main turbine runback, a malfunction causes the control rods to continue to insert beyond the expected position. ATC places control rods in manual using AOP-C.01, Rod Control Malfunctions, and may initiate emergency boration. SRO addresses LCO for Rod Insertion Limits, as required.

Verifiable actions: (ATC) places Rod Control switch in manual.

Event 5 - A Small RCS Leak develops. The ATC will raise charging flow using AOP-R.05. SRO addresses LCO Verifiable actions: (ATC) places charging and seal injection controllers in Manual and raises charging flow.

Event 6 - A Large Break LOCA occurs. B RHR pump trips at 35% RWST level.

Verifiable actions: (ATC) stops RCPs.

Event 7 - Crew enters E-0, Reactor Trip or Safety Injection, transitions to E-1, Loss of Reactor or Secondary Coolant, and ultimately to ES-1.3 Transfer to RHR Containment Sump. B RHR pump trips at 35% RWST level. Failure of sump AUTO swapover occurs. ATC manually aligns the suction of the ECCS pumps to the Containment Sump. (CT-36)

Verifiable actions: (ATC) manually aligns ECCS pumps to sump.

Event 8 - The A RHR pump trips after sump swapover. Crew transitions to ECA-1.1, Loss of ECCS Sump Recirculation. BOP takes actions to refill RWST. ATC stops ECCS pumps when RWST low level is reached. (CT-29) (CT-PRA)

Verifiable actions: ((BOP) refills RWST. (ATC) stops ECCS pumps upon low RWST level.

Terminate in ECA-1.1 when ECCS pumps have been stopped.

GO-5 / AOP-M.03 / AOP-S.04 / AOP-C.01 / AOP-R.05 / E-0 / E-1 / ES-1.3 / ECA-1.1

Appendix D Scenario Outline Form ES-D-1 Similarities vs. two most recent exams (1603 was 2016-301) (1712 was 2017-301)

Except as noted, events were not included in the last two exams Audit exam is based on 1712 exam so no events are duplicated from that exam.

3 of 8 events were not used on the previous two exams*

Event 1 - reactivity manipulation exempt from overlap requirements Event 2 - last used in 1603

Event 3 - TCRLY2 HD06A Not used in last two exams. Similar to Scenario 5 event but in that event a runback occurs and rods fail to move automatically.

Event 4 - RD17 Not used in last two exams Event 5 - last used in 1603 Event 6- Major - TH02A (LBLOCA) - last used in 1603 Event 7 - last used in 1603

Event 8 - Not used in last two exams

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:1 Page 1 of 87 Event

Description:

Power reduction Time Position Applicant's Actions or Behavior EVENT LIST 1 Power reduction 2 Component Cooling System Pump Trip 3 #3 Heater Drain Tank Control Failure with No Auto Runback 4 Control Rods Continue to Insert After Runback 5 Small RCS Leak 6 Large Break LOCA 7 Sump Auto Swapover Failure 8 Last RHR Pump Trips EVENT 1 - Power reduction Event 1 is directed via turnover sheet Indications/Alarms Annunciators:

Various indications for Power Range NIs, Electrical Megawatts, feed flow, steam flow, etc.

0-GO-5 Section 5.3 Step 6 Communications: see below Examiner Note: Throughout this scenario routine communications directing administrative actions, reports, or notifications may be answered by acknowledging the report or direction.

Communications requiring reports back to the examinees will be scripted. Unexpected communications requiring report back will be approved by the Lead examiner prior to contacting the Control Room. .

Examiner Note: Steps, notes, and cautions in the procedure that have already been completed or that do not apply to this evolution have been omitted.

SRO Refers to 0-GO-5 section 5.3 1

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:1 Page 2 of 87 Event

Description:

Power reduction Time Position Applicant's Actions or Behavior BOP BOP Adjusts Main Generator Voltage as required.

Examiner Note: Actions are expected per Note 4 above.

0-SO-62-7 Section 6.4 Steps 1 thru 20 Examiner Note: Steps 1 thru 4 are provided to examinee as completed Examiner Note: Crew may elect to divide the 80 gallon add into smaller batches. (Ex, 40+20+20 )

ATC ATC PLACES HS-62-140A in STOP 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:1 Page 3 of 87 Event

Description:

Power reduction Time Position Applicant's Actions or Behavior ATC BOP PLACES HS-62-140B to BORATE ATC ATC This setting is not critical ans is based on judgement of the operator ATC ATC SETS FQ-62-139 to Value from Step 2 of procedureXXX ATC ATC PLACES HS-62-140A to START ATC ATC 3

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:1 Page 4 of 87 Event

Description:

Power reduction Time Position Applicant's Actions or Behavior ATC ATC ATC ATC Examiner Note: step 16 is used to make multiple batch additions.

ATC ATC PLACES HS-62-140A to STOP ATC ATC 4

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:1 Page 5 of 87 Event

Description:

Power reduction Time Position Applicant's Actions or Behavior ATC ADJUSTS FC-62-139 to 985 ATC ATC BOP PLACES HS-62-140B to AUTO ATC ATC PLACES HS-62-140A to START ATC ATC ATC ATC 5

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:1 Page 6 of 87 Event

Description:

Power reduction Time Position Applicant's Actions or Behavior 0-SO-85-1 Examiners Note: The following sections are used as necessary ATC 6

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:1 Page 7 of 87 Event

Description:

Power reduction Time Position Applicant's Actions or Behavior 0-GO-5 Section 5.3 Steps 7 thru 12 BOP BOP uses Up or Down pushbuttons to lower SETTER, and DEPRESSES GO pushbutton BOP OR Places Turbine control to TURB MAN and momentarily GV UP and DOWN pushbuttons to lower load 7

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:1 Page 8 of 87 Event

Description:

Power reduction Time Position Applicant's Actions or Behavior BOP BOP ATC 8

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:1 Page 9 of 87 Event

Description:

Power reduction Time Position Applicant's Actions or Behavior 9

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:2 Page 10 of 87 Event

Description:

Component Cooling System Pump Trip Time Position Applicant's Actions or Behavior EVENT 2 - Component Cooling System Pump Trip Direct simulator operator to insert Event 2 (KEY 2)

Indications available:XXX Annunciator

27B-A E-4: ERCW/CCS PUMP MOTOR TRIP

Numerous A Train CCS cooled component flow alarms Indications

Numerous A Train CCS cooled component flow indicators reading 0.

M27-B-A E-4 Examiner Note: Some steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.

Examiner Note: Examinee may place 1A CCS Pump Handswitch in PTL to silence disagreement alarm and START 1B CCS Pump as a Prudent Action for a failed automatic actuation, prior to entering AOP-M.03.

Communications: If requested as AUO, acknowledge direction to inspect/investigate alarm.

10

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:2 Page 11 of 87 Event

Description:

Component Cooling System Pump Trip Time Position Applicant's Actions or Behavior BOP SRO Transitions AOP-M.03, LOSS OF ESSENTIAL RAW COOLING WATER.

AOP-M.03 Step 1 thru 17 SRO 11

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:2 Page 12 of 87 Event

Description:

Component Cooling System Pump Trip Time Position Applicant's Actions or Behavior SRO Directs actions from AOP-M.03, LOSS OF COMPONENT COOLING WATER BOP BOP Places 0-HS-70-46A CCS PUMP 1A-A in PTL.

BOP BOP BOP Momentarily PLACES 0-HS-70-38A CCS PUMP 1B-B in START BOP Examiners Note: SRO Examinee may defer TS Evaluation until completion of remaining steps of procedure.

SRO 12

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:2 Page 13 of 87 Event

Description:

Component Cooling System Pump Trip Time Position Applicant's Actions or Behavior BOP Restores B Thermal Barrier Booster Pump to Standby by momentarily placing 1-BOP HS-70-130A in STOP and then to P-AUTO .

It is acceptable to instead place the A TBBP in Standby using 1-HS-70-131A SRO SRO SRO SRO 13

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:2 Page 14 of 87 Event

Description:

Component Cooling System Pump Trip Time Position Applicant's Actions or Behavior AOP-M.03 Appendix J 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:2 Page 15 of 87 Event

Description:

Component Cooling System Pump Trip Time Position Applicant's Actions or Behavior Determines LCO applicability as follows:

3.7.7 Condition A is applicable.

And one of the following options:

SRO Option #1: 3.5.2 Condition A and 3.6.6 Condition A OR Option #2 LCO 3.0.6 and SFDP in lieu of 3.5.2 and 3.6.6 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:2 Page 16 of 87 Event

Description:

Component Cooling System Pump Trip Time Position Applicant's Actions or Behavior LCO 3.7.7 Condition A SRO Determines LCO 3.7.7 condition A is applicable (Also see above) 16

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:3 Page 17 of 87 Event

Description:

3 Heater Drain Tank Control Failure with No Auto Runback Time Position Applicant's Actions or Behavior EVENT 3 - #3 Heater Drain Tank Control Failure with No Auto Runback Direct simulator operator to insert Event 3 (KEY 3)

Indications available:

M2-C B-7: ZS-6-105A & B NO 3 HTR DR TK BYPASS TO COND

M3-A E-1: PS-2-129 LOW NPSH AT MFPs (if action is not taken)

Indications

1-FR-6-107 HTR DR SYSTEM FLOW: shows lowering trend

HEATER DRAIN BYPASS TO CONDENSER open light lit

1-PI-2-129 MFP INLET PRESS: shows lowering trend 1-AR-M2-C B-7 Examiners Note: Some steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.

BOP 17

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:3 Page 18 of 87 Event

Description:

3 Heater Drain Tank Control Failure with No Auto Runback Time Position Applicant's Actions or Behavior Examiners Note: Crew should identify that runback conditions exists and that automatic runback has not occurred. BOP may take action based on ARP step below or as directed from AOP-S.04, Condensate or Heater Drains Malfunction.

BOP Reduces Main Turbine Load using Valve Position Limit lower pushbutton BOP OR Enters AOP-S.04 1-AR-M3-A E-1 Examiners Note: Some steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.

BOP BOP Enters AOP-S.04 18

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:3 Page 19 of 87 Event

Description:

3 Heater Drain Tank Control Failure with No Auto Runback Time Position Applicant's Actions or Behavior BOP BOP BOP BOP 19

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:3 Page 20 of 87 Event

Description:

3 Heater Drain Tank Control Failure with No Auto Runback Time Position Applicant's Actions or Behavior AOP-S.04 Step 1 thru Section 2.6 Step 17 SRO SRO Transitions to Section 2.6 BOP BOP 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:3 Page 21 of 87 Event

Description:

3 Heater Drain Tank Control Failure with No Auto Runback Time Position Applicant's Actions or Behavior BOP Reduces turbine load to approximately 940 MWe (~77% turbine Impulse BOP Pressure) using the VPL lower pushbutton.

ATC CREW ATC 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:3 Page 22 of 87 Event

Description:

3 Heater Drain Tank Control Failure with No Auto Runback Time Position Applicant's Actions or Behavior Examiners Note: Alarm is expected. This the ARP for this is shown on Page 26 BOP BOP 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:3 Page 23 of 87 Event

Description:

3 Heater Drain Tank Control Failure with No Auto Runback Time Position Applicant's Actions or Behavior Examiners Note: CREW may defer this step pending determination of potential turbine control problem 23

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:3 Page 24 of 87 Event

Description:

3 Heater Drain Tank Control Failure with No Auto Runback Time Position Applicant's Actions or Behavior SRO BOP SRO SRO 24

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:3 Page 25 of 87 Event

Description:

3 Heater Drain Tank Control Failure with No Auto Runback Time Position Applicant's Actions or Behavior AOP-S.04 Appendix B 25

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:3 Page 26 of 87 Event

Description:

3 Heater Drain Tank Control Failure with No Auto Runback Time Position Applicant's Actions or Behavior 1-AR-M4-B B-7 26

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:3 Page 27 of 87 Event

Description:

3 Heater Drain Tank Control Failure with No Auto Runback Time Position Applicant's Actions or Behavior 27

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:4 Page 28 of 87 Event

Description:

Control Rods Continue to Insert After Runback Time Position Applicant's Actions or Behavior EVENT 4 - Control Rods Continue to Insert After Runback EVENT 4 is automatically initiated during manual turbine runback Indications available:

M4-B A-7: ZS-085-5071A ROD CONTROL BANKS LIMIT LOW

M4-B B-7: ZS-085-5071B ROD CONTROL BANKS LIMIT LOW-LOW Indications

Continued Control Rod clicking with Tave-Tref within limits Examiners Note: This malfunction simulates a failure of the of the rod control system such that all automatic rod commands cause inward rod motion. The associated rod control DCS screen will show OUTWARD rod motion demanded but rods will insert. Eventually, the insertion rate will increase as Tave-Tref deviation increases calling for faster outward rod motion.

AOP-C.01 Step 1 thru Section 2.1 Step 12 SRO SRO Enters AOP-C.01 Rod Control Malfunctions and transitions to Section 2.1 ATC 28

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:4 Page 29 of 87 Event

Description:

Control Rods Continue to Insert After Runback Time Position Applicant's Actions or Behavior Places 1-HS-85-5110 ROD CONTROL MODE SELECTOR switch to MAN and ATC determines that rods have stopped moving ATC ATC ATC 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:4 Page 30 of 87 Event

Description:

Control Rods Continue to Insert After Runback Time Position Applicant's Actions or Behavior ATC ATC ATC Incrementally withdraws control rods to restore Tave, or lowers turbine load, as ATC required.

30

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:4 Page 31 of 87 Event

Description:

Control Rods Continue to Insert After Runback Time Position Applicant's Actions or Behavior SRO IF annunciator ZS-085-5071B ROD CONTROL BANKS LIMIT LOW-LOW is lit SRO then SRO determines that LCO 3.1.6 Condition B is applicable ATC 31

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:4 Page 32 of 87 Event

Description:

Control Rods Continue to Insert After Runback Time Position Applicant's Actions or Behavior LCO 3.1.6 Condition A 32

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:5 Page 33 of 87 Event

Description:

Small RCS Leak Time Position Applicant's Actions or Behavior EVENT 5- Small RCS Leak Direct simulator operator to insert Event 5, (KEY 5)

Indications available:

Alarms:

1-M5A

5A C-5, LS-77-410A REACTOR BLDG AUX FL & EQ DRAIN SUMP HI 1-M5C

5C B-3, MS-30-241 LOWER COMPT MOISTURE HI Indications:

1-M-5

1-LR-68-339, RCS PZR LEVEL actual level deviating low from program level indication

1-FI-62-93A, CHARGING HDR FLOW increasing flow 1-M-6

1-LI-62-129, VCT LEVEL decreasing

1-PDIR-30-133, CNTMT increasing trend 0-M-12

1-RR-90-106A, CNTMT LOWER COMPT PARTICULATE RADMON recorder shows increasing trend

1-RI-90-106B, CNTMT LOWER COMPT RADMON-TOTAL GAS increasing counts

1-RM-90-112B, CNTMT UPPER COMPT RADMON- TOTAL GAS increasing counts 1-AR-M5-C B-3 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:5 Page 34 of 87 Event

Description:

Small RCS Leak Time Position Applicant's Actions or Behavior Examiners Note: Only steps, notes, and cautions associated with this event are included here Examiners Note: Leak size is approx. 35 gpm.

ATC SRO Transitions to AOP-R.05 AOP-R.05 Step 1 thru 8 SRO 34

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:5 Page 35 of 87 Event

Description:

Small RCS Leak Time Position Applicant's Actions or Behavior CREW ATC Places HIC-62-93A Charging Flow Control, in MANUAL and raises FCV-62-93 ATC and while adjusting FCV-62-89 as necessary to maintain Pressurizer level on program.

35

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:5 Page 36 of 87 Event

Description:

Small RCS Leak Time Position Applicant's Actions or Behavior ATC Places HS-62-73A Letdown Orifice B Isol 75 gpm and HS-62-69A Letdown Isol ATC Loop 3 and HS-62-70A Letdown Isol Loop 4 to CLOSE when Pressurizer Level cannot be maintained.

ATC 36

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:5 Page 37 of 87 Event

Description:

Small RCS Leak Time Position Applicant's Actions or Behavior ATC SRO SRO ATC 37

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:5 Page 38 of 87 Event

Description:

Small RCS Leak Time Position Applicant's Actions or Behavior BOP SRO 38

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:5 Page 39 of 87 Event

Description:

Small RCS Leak Time Position Applicant's Actions or Behavior AOP-R.05 Appendix D Examiners Note: Depending on timing and plant response, LCOs 3.6.4 and 3.6.5 may become applicable. SRO may defer evaluation of TS LCOs based on plant conditions.

Determines LOC 3.4.13 Condition A is applicable (and/or 3.6.4, 3.6.5 as SRO applicable)

LCO 3.6.13 Condition B is applicable 39

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:5 Page 40 of 87 Event

Description:

Small RCS Leak Time Position Applicant's Actions or Behavior LCO 3.4.13 Condition A SRO Determines LCO 3.4.13. Condition A is applicable 40

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:5 Page 41 of 87 Event

Description:

Small RCS Leak Time Position Applicant's Actions or Behavior LCO 3.6.13 Condition B SRO Enters LCO 3.6.13. Condition B AOP-R.05 Step 9 thru 14 Examiners Note: When technical specifications have been identified or at discretion of the Lead Examiner, proceed to the next event.

BOP SRO 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:5 Page 42 of 87 Event

Description:

Small RCS Leak Time Position Applicant's Actions or Behavior ATC Examiners Note: Letdown is expected to be isolated at this point ATC ATC ATC 42

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:5 Page 43 of 87 Event

Description:

Small RCS Leak Time Position Applicant's Actions or Behavior ATC ATC PLACES 1-HS-62-90, 91, and 85 in CLOSE BOP ATC ATC 43

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:5 Page 44 of 87 Event

Description:

Small RCS Leak Time Position Applicant's Actions or Behavior BOP BOP ATC ATC ATC ATC BOP BOP 44

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:6 Page 45 of 87 Event

Description:

Large Break LOCA Time Position Applicant's Actions or Behavior EVENT 6 - Large Break LOCA Direct simulator operator to insert Event 6, (KEY 6)

Indications available:

Alarms:

1-M5A

5A C-5, LS-77-410A REACTOR BLDG AUX FL & EQ DRAIN SUMP HI 1-M5C

5C B-3, MS-30-241 LOWER COMPT MOISTURE HI Indications:

1-M-5

1-LR-68-339, RCS PZR LEVEL actual level deviating low from program level indication

1-FI-62-93A, CHARGING HDR FLOW increasing flow 1-M-6

1-LI-62-129, VCT LEVEL decreasing

1-PDIR-30-133, CNTMT increasing trend 0-M-12

1-RR-90-106A, CNTMT LOWER COMPT PARTICULATE RADMON recorder shows increasing trend

1-RI-90-106B, CNTMT LOWER COMPT RADMON-TOTAL GAS increasing counts

1-RM-90-112B, CNTMT UPPER COMPT RADMON- TOTAL GAS increasing counts E-0 Steps 1 thru 12 CREW Performs the first four steps of E-0 unprompted.

SRO Directs performance of E-0 ATC 45

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:6 Page 46 of 87 Event

Description:

Large Break LOCA Time Position Applicant's Actions or Behavior BOP BOP ATC Examiners Note: FOLDOUT Page actions including RCP Trip Criteria (shown below) become applicable upon verification of Immediate Actions ATC PLACES the following handswitches in OFF (PTL acceptable):

1-HS-68-8A ATC 1-HS-68-31A 1-HS-68-50A 1-HS-68-73A ATC ATC ATC 46

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:6 Page 47 of 87 Event

Description:

Large Break LOCA Time Position Applicant's Actions or Behavior IF not already done, PLACES the following handswitches in OFF (PTL acceptable):

1-HS-68-8A ATC 1-HS-68-31A 1-HS-68-50A 1-HS-68-73A Examiners Note: ES-0.5 Actions are shown on page 76 BOP ATC ATC Manually controls AFW flow to maintain total AFW flow greater than 440 gpm until ATC S/G are greater than 25% NR.

ATC ATC Manually controls AFW flow to maintain SG levels 25%-50% NR level.

47

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:6 Page 48 of 87 Event

Description:

Large Break LOCA Time Position Applicant's Actions or Behavior ATC ATC Manually controls AFW flow between 440 and 600 gpm.

ATC ATC 48

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:6 Page 49 of 87 Event

Description:

Large Break LOCA Time Position Applicant's Actions or Behavior ATC ATC FR-P.1 Step 1 ATC SRO Transitions back to E-1 49

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:7 Page 50 of 87 Event

Description:

Sump Auto Swapover Failure Time Position Applicant's Actions or Behavior EVENT 7 - Sump Auto Swapover Failure EVENT 7 is automatically initiated.

E-1 Steps 1 thru 7 Examiners Note: Foldout Page Guidance for Sump Swapover is shown below.

ATC ATC STOPS all RCP , if not already performed.

ATC 50

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:7 Page 51 of 87 Event

Description:

Sump Auto Swapover Failure Time Position Applicant's Actions or Behavior BOP ATC

/BOP BOP ATC 51

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:7 Page 52 of 87 Event

Description:

Sump Auto Swapover Failure Time Position Applicant's Actions or Behavior ATC 52

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:7 Page 53 of 87 Event

Description:

Sump Auto Swapover Failure Time Position Applicant's Actions or Behavior E-1 Steps 8 thru 12 53

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:7 Page 54 of 87 Event

Description:

Sump Auto Swapover Failure Time Position Applicant's Actions or Behavior ATC BOP BOP 54

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:7 Page 55 of 87 Event

Description:

Sump Auto Swapover Failure Time Position Applicant's Actions or Behavior BOP BOP BOP BOP E-1 Appendix D 55

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:7 Page 56 of 87 Event

Description:

Sump Auto Swapover Failure Time Position Applicant's Actions or Behavior BOP PLACES HS-43-200A in ANALYZE BOP PLACES HS-43-210A in ANALYZE PLACES HS-268-73 in ON BOP PLACES HS-268-74 in ON BOP 56

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:7 Page 57 of 87 Event

Description:

Sump Auto Swapover Failure Time Position Applicant's Actions or Behavior SRO BOP ATC BOP BOP 57

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:7 Page 58 of 87 Event

Description:

Sump Auto Swapover Failure Time Position Applicant's Actions or Behavior ATC ATC 58

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 59 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior EVENT 8 - Last RHR Pump Trips EVENT 8 is automatically initiated as RWST level lowers Examiners Note: Second RHR Pump trips 110 seconds after RHR Pump A suction valve (63-72) is selected open ES-1.3 Steps 1 thru 5 CREW ATC ATC PLACES either HS-72-27A or HS-72-10A in PTL (But not both)

ATC ATC ATC Momentarily DEPRESSES both HS-72-43 pushbutton and HS-72-42 pushbutton ATC PLACES both HS-72-27A and HS-72-10A in A-AUTO 59

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 60 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior ATC Momentarily both PLACES HS-72-39 and HS-72-2 to the CLOSE position 60

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 61 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior Communications: When directed to restore power to FCV-63-1, acknowledge, wait 2 minutes and use KEY 33 to restore power. Report, Power has been restored to FCV-63-1.

BOP BOP NOTIFIES AUO to to restore power to FCV-63-1 using EA-201-1 61

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 62 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior BOP BOP Momentarily PLACES both 1-HS-70-156A and 1-HS-70-153A to OPEN BOP ATC ATC Momentarily PLACES HS-63-72A to OPEN ATC ATC Identifies RHR Pump 1A NOT Running ATC 62

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 63 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior ATC CRITICAL ATC Momentarily PLACES HS-63-73A to OPEN TASK(36)

ATC ATC Identifies RHR Pump 1B NOT Running ATC ATC Identifies No RHR Pums running and recognizes that CCPs and SIPs have not lost ATC suction SRO Transitions to ECA-1.1, Loss of ECCS Sump Recirculation 63

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 64 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior Examiners Note: FR-P.1 may become applicable when ES-1.3 is exitied for ECA-1.1. However, it may be immediately exited as shown in the step below ECA-1.1 Steps 1 thru 20 ATC 64

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 65 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior Examiners Note: It is expected that Containment pressure will be < 9.5 psig ATC ATC 65

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 66 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior ATC BOP ATC ATC Momentarily DEPRESSES HS-63-134A and HS-63-134B pushbuttons ATC Momentarily PLACES th HS-63-72D and HS-63-73D switches to RESET Examiners Note: Record time of LS-63-50B RWST LVL LO-LO (M6-F E-4) annunciator alarm TIME: __________________

66

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 67 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior ATC IF RWST level reaches 8%:

PLACES CCP-1A (HS-62-108A) in PTL CRITICAL PLACES CCP-1B (HS-62-104A) in PTL ATC T A S K PLACES SIP-1A in (HS-63-10A) PTL (CT-PRA) PLACES SIP-1B in (HS-63-15A) PTL 67

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 68 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior Examiners Note: It is expected that Containment pressure will be < 9.5 psig 68

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 69 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior PLACES CSP-1A (HS-72-27A) in PTL ATC PLACES CSP-1B (HS-72-10A) in PTL, as necessary ATC Momemtarily PLACES both HS-72-39A and HS-72-2A in CLOSE ATC Communications: When directed to perform EA-63-2 Attachment 1, acknowledge and use KEY:30 to OPEN FCV62-936 and 938, and report, FCV-948 is CLOSED and FCVs 62-936 and 938 are OPEN.

BOP/SR O

69

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 70 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior BOP NOTIFIES available AUO to Initiate RWST Fill using EA-63-2 BOP CONTROLS AFW LCVs to maintain SG NR levels between 25% and 50%

70

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 71 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior BOP Momentarily both PLACES HS-63-135A and HS-63-135B to BLOCK BOP PLACES both HS-1-103A and HS-1-103B in OFF RESET BOP PLACES both HS-1-103A and HS-1-103B in ON PLACES PIC-1-33 in MAN and adjusts steam dump position to establsih BOP cooldown approaching but not exceeding 100 F/Hr 71

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 72 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior CRITICAL ATC PLACES either but not both HS-62-108A or HS-62-104A in Normal After Stop TASK(29) 72

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 73 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior CRITICAL ATC PLACES either but not both HS-63-18A or HS-6-15A in Normal After Stop TASK(29) 73

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 74 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior 74

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 75 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior 75

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 76 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior ES-0.5 Steps 1 thru 17 BOP Communications: When directed to perform ES-0.5 Attachment 7, acknowledge direction. No further action required.

76

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 77 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior BOP BOP BOP 77

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 78 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior BOP 78

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 79 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior BOP BOP 79

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 80 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior 80

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 81 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior BOP 81

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 82 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior BOP BOP 82

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 83 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior BOP BOP Examiners Note: Containment Air Return Fans will not AUTO START and cannot be started Manually BOP 83

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 84 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior BOP BOP 84

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 85 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior ES-0.5 Appendix A Examiner Note: Appendix A and B step 2 is Unit 2 only 85

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 86 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior ES-0.5 Appendix B ES-0.5 Step 18 thru end BOP BOP Communications: When requested as Unit 2, acknowledge request to perform EA-65-1 86

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 2 Event No.:8 Page 87 of 87 Event

Description:

Last RHR Pump Trips Time Position Applicant's Actions or Behavior BOP Communications: When requested as Unit 2 RO, acknowledge direction to perform EA-0-1 BOP BOP Communications: When requested as available AUO, acknowledge direction to perform Appendix F BOP 87

2003 NRC SCN 2 Booth Instructions BOOTH OPERATOR INSTRUCTIONS Sim. Setup Reset IC-16 100% power BOL Perform switch check.

Verify control rod step counters reset.

Place simulator in RUN.

Place Mode 1 placard on panels.

Place B Train Week sign on the simulator.

Place FT-1-3A in MAINT BYP Place CSP-1B in PTL Hang Red Tag Load SCN file: - ILT2003 NRC SCN 2 Acknowledge any alarms, allow the plant to stabilize, and freeze the simulator.

Perform the SIMULATOR OPERATOR CHECKLIST Place simulator in RUN before crew enters the simulator.

Start Data Capture

1. REMOVE ORANGE DOTS WHEN SCENARIO COMPLETE Page 1 of 4

2003 NRC SCN 2 Booth Instructions EVENT IC/MF/RF/OR # DESCRIPTION/EXPECTED ACTIONS/BOOTH FEEDBACK This is manually FT-1-3A in Maintenance Bypass ;MAIN STEAM FLOW TRANSMITTER inserted during IMF RX10A f:1 FAILS LOW FT-1-3A setup Active from IOR CSR04 f:0 ;CONTAINMENT SPRAY PUMP B POWER beginning Throughout this scenario routine communications directing administrative actions, reports, or notifications may be answered by acknowledging the report or direction. Communications requiring reports back to the examinees will be scripted. Unexpected communications requiring report back will be approved by the Lead examiner prior to contacting the Control Room. .

Downpower to 94 % per turnover EVENT 1 None sheet Communication Acknowledge reports as needed.

for Event 1 When directed by the Lead IMF CC09B f:1 ;---1B CCS Defeat Pump Auto-Start Examiner, use KEY 2 to insert IMF CC10A f:1 k:2 ;---1A CCS Trip malfunction Communication If requested as AUO then report Nothing abnormal.

for Event 2

---PIS-47-13 RELAY 2 FAILS LOW IMF TC10RLY2 f: 1 preventing turbine runback When directed ;---LCV-6-106A FAILS TO 40% OVER 1 by the Lead IMF HD01A f:40 r:60 k:3 MINUTE Examiner, use IMF HD01B f:0 r:60 k:3 KEY 3 to insert ;---LCV-6-106B FAILS TO 0% OVER 1 malfunction. {egpmgen<1e9} dmf HD01A MINUTE

{egpmgen<1e9} dmf HD01B ;---Automatically deleted as power is reduced below 1000MWe If requested to investigate #3HDT Communication #3 Heater Drain Tank level control LCVs, delay until runback has for Event 3 valves appear to be operating normally.

occurred and report EVENT 4 is automatically ;---CONTROL ROD AUTO INSERTION inserted as RELAY FAILS CLOSED

{egpmgen<1e9} IMF RD17 f:1 power drops below 1000 ;---Auto inserted at 1000MWe MWe Page 2 of 4

2003 NRC SCN 2 Booth Instructions EVENT IC/MF/RF/OR # DESCRIPTION/EXPECTED ACTIONS/BOOTH FEEDBACK When directed by the Lead Examiner, use IMF TH01C f:0.0035 k:5 ;---RCS Leak - HOT LEG LOOP 3 KEY 5 to insert malfunction.

Communication for Event 5 When directed by the Lead Examiner, use {Key[6]}IMF TH01C f:25 r:300 ;---LBLOCA LOOP 3 KEY 6 to insert malfunction Occurs ;--1B-B RHR Pump Trips at 35% RWST

{silrwst1<.35} IMF RH01B f:1 automatically level Communication When directed to perform ES-0.5 No further action required.

for Event 6 Attachment 7, acknowledge direction EVENT 7

---FAILURE OF AUTO TRANSFER TO inserted from IMF RH02 f: 1 CONTAINMENT SUMP beginning Communication for Event 7 EVENT 8 ;---RHR PUMP A TRIP 110 seconds after Inserted from {zlohs6372a[1]} IMF RH01A f:1 d:110 sump suction valves sump valve switch is beginning taken to open IRF RHR14 f:1 k:33 When directed to restore power to Communication FCV-63-1, acknowledge, wait 2 Power has been restored to FCV-63-1.

for Event 8 minutes and use KEY 33 to restore power

---OPEN RWST fill valves from BORIC IRF CVR05 f: 1 k:30 ACID BLENDER TO RWST (62-936,62-938)

When directed to perform EA-63-2 Communication Attachment 1, acknowledge and use FCV-948 is CLOSED and FCVs 62-936 for Event 8 KEY:30 to OPEN FCV62-936 and and 938 are OPEN.

938, and report, Page 3 of 4

2003 NRC SCN 2 Booth Instructions EVENT IC/MF/RF/OR # DESCRIPTION/EXPECTED ACTIONS/BOOTH FEEDBACK Communication When directed to perform ES-0.5 Acknowledge direction. No further action for Event 8 Attachment 7 required.

Communication Acknowledge request to perform EA When requested as Unit 2 for Event 8 1 Communication Acknowledge direction to perform When requested as available AUO for Event 8 Appendix F Page 4 of 4

Today Mode 1 100% 1206 MWe Train Week: B RCS Boron: 985 ppm BAT A RCS Leakage:

EOOS: Green Last Shift: Dilution: Rx Plan Total: Rx plan Identified: 0.01 GPM Grid Status: Qualified This Shift: Boration: Rx plan Total: Rx plan Unidentified: 0.04 GPM Site Aggregate Risk: Low Shutdown LCO Conditions Equipment INOP Next Action Due LCO 3.6.6 Condition A CSP-1B 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months Other LCO Actions Equipment INOP Next Action Due Info Only Tech Specs Equipment INOP Abnormal Equipment Lineup / Conditions (including significant Radiological changes)

Severe Thunderstorm warning is in effect for Hamilton County FT-1-3A Failed. In MAINT BYPASS Shift Priorities (Surveillances/Testing and Major Activities in Progress or Scheduled)

Reduce power to 94% for governor valve testing Restore CSP-1B when work is complete For each MCR deficiency, a numbered square will be applied to the MCR Board near the associated indication/alarm. (US maintains magnets)

The CR/WO number and description of the issue will be listed below Main Control Room (7690)

Auxiliary Building (7671)

Turbine Building (7771)

TB Sump: LVWT Pond RCW: Unit 2 Aux Steam: Unit 1 Outside (7666) (423-710-4777)

Miscellaneous

Appendix D Scenario Outline Form ES-D-1 Facility: Sequoyah Scenario No.: 3 Op Test No.: 2020-301 Examiners: Operators: SRO ATC BOP Initial Conditions: 76% BOL Turnover: Unit 1 is in MODE 1 76%, BOL FT-1-3A is in Maintenance Bypass Severe Thunderstorm warning is in effect for Hamilton County Critical Tasks CT-18 Manually isolate feed water flow into and steam flow from the ruptured S/G before a transition to ECA-3.1 is required.

CT-19 Manually establish/maintain an RCS temperature so that transition from E-3 is not required because the RCS temperature is in any of the following conditions:

Too high to maintain > 60 degrees CET subcooling.

RED path on PTS Status Tree OR

ORANGE path on Subcriticality Status Tree CT-20 Manually depressurize RCS to meet and maintain SI termination criteria while in E-3 prior to exceeding 100% S/G dome level on the simulator during a SGTR of 430 gpm or less (TH05 9.15%).

Event Malf. Event Event Description No. No. Type Primary water isolation valve to CCP suction seat leak causes 1 CVR18 (C) ATC uncontrolled dilution. ATC stops Primary Water pumps per AOP-C.02 Failure of Containment Narrow Range Pressure transmitter. Crew 2 CH01C TS-SRO takes action per AOP-I.05.SRO addresses LCO (C) BOP ERCW Pump R-A sheared shaft. BOP starts standby pump (K-A) 3 RW18H TS-SRO per AOP-M.01. SRO addresses LCO CCW Traveling Screen 1A develops clogging along with a failure of 4 CW03A (C) BOP the Screen Wash pumps to AUTO-START. The BOP will manually start the Screen Wash pumps using the ARP.

(R) ATC Slowly lowering EHC pressure leads to power reduction per AOP-5 AN_OV_85 (N) BOP C.03 ZDIHS62140D Failure of initial boration flowpath. ATC uses alternate boration 6 ZDIHS62138A (C) ATC flowpath per AOP-C.03 SGTR_base Steam Generator Tube Rupture. Crew may enter AOP-R.01 initially.

7 (M) ALL TH05A Crew enters E-0 and transitions to E-3 1A Shutdown Board is de-energized due to spurious UV signal 30 ED09A 8 (C) BOP seconds after Rx trip. EDG-A does not start on SI actuation. BOP EG08A starts EDG-A.

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

Appendix D Scenario Outline Form ES-D-1 2020-301 Scenario 3 Summary Event 1 - Primary water isolation valve to CCP suction seat leak causes uncontrolled dilution. ATC stops Primary Water pumps per AOP-C.02 Verifiable actions: (ATC) stops PW pumps.

Event 2 - Failure of Containment Narrow Range Pressure transmitter. Crew enters per AOP-I.05, Containment Instrument Malfunction. SRO addresses LCO Verifiable actions: Not applicable.

Event 3 - ERCW Pump R-A sheared shaft. BOP starts standby pump (K-A) per AOP-M.01. SRO addresses LCO Verifiable actions: (BOP) starts alternate ERCW pump and selects alternate pump for autostart.

Event 4 - CCW Traveling Screen 1A develops clogging along with a failure of the Screen Wash pumps to AUTO-START. BOP will manually start the Screen Wash pumps using the ARP.

Verifiable actions: (BOP) starts Screen Wash pumps Event 5 - Slowly lowering EHC pressure leads to power reduction per AOP-C.03, Rapid Shutdown or Load Reduction Verifiable actions: (ATC) performs boration. (BOP) lowers Main Turbine load.

Event 6 - Failure of initial boration method. ATC uses alternate boration flowpath per AOP-C.03, Rapid Shutdown or Load Reduction Verifiable actions: (ATC) uses alternate boration method Event 7 - Steam Generator Tube Rupture. Crew enters E-0 and transitions to E-3 to cooldown and depressurize the RCS (CT-18)(CT-19)(CT-20)

Verifiable actions: (BOP) controls AFW (ATC) reduces RCS pressure Event 8 - 1A Shutdown Board is de-energized due to spurious UV signal 30 seconds after Rx trip. EDG-A does not start on SI actuation. BOP starts EDG-A.

Verifiable actions: (BOP) starts EDG-A Terminate in E-3 when RCS pressure has been reduced to allow for ECCS termination.

AOP-C.02 / AOP-I.05 / AOP-M.01 / ARP / AOP-C.03 / AOP-R.01 / E-0 / E-3

Appendix D Scenario Outline Form ES-D-1 Similarities vs. two most recent exams (1603 was 2016-301) (1712 was 2017-301)

Except as noted, events were not included in the last two exams Audit exam is based on 1712 exam so no events are duplicated from that exam.

3 of 8 events were not used on the previous two exams*

Event 1 - CVR18 Not used in last two exams Event 2 - TS only. Not used in last two exams

Event 3 - RW18H Not used in last two exams Event 4 - last used in 1603 Event 5 - last used in 1603 Event 6 - last used in 1603 Event 7 - Major - TH05A (SGTR) - last used in 1603

Event 8 - similar to 1603 but failure is combined with loss of SDBD during SGTR resulting in potential transition to ECA-3.1 if EDG is not restored

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:1 Page 1 of 85 Event

Description:

Uncontrolled Dilution Time Position Applicant's Actions or Behavior EVENT LIST 1 Uncontrolled Dilution 2 Containment Pressure Transmitter Failure 3 ERCW Pump Shaft Shear 4 Condenser Circ Water Travelling Screen Failure 5 Lowering EHC Pressure 6 Failure of Boration Flowpath 7 SGTR #1 8 SDBD UV with EDG Auto Start Failure EVENT 1- Uncontrolled Dilution Direct simulator operator to insert Event 1 (KEY 1)

Indications/Alarms Annunciators:

Significant Resultant Alarms/Indications:

1-M-6

1-FQ-62-142 (PRIMARY WATER BATCH COUNTER) begins clicking and counting upwards

VCT level slowly rising

Slowly rising thermal power/Tave

1-PI-62-93A, CHARGING HDR FLOW drops to 0

1-TI-62-71, REGEN HX OUTLET TEMP-LETDOWN trending up above 397F

1-TI-62-131, VCT OUTLET TEMP trending down No Annunciators initially Communications: see below Examiner Note: Throughout this scenario routine communications directing administrative actions, reports, or notifications may be answered by acknowledging the report or direction.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:1 Page 2 of 85 Event

Description:

Uncontrolled Dilution Time Position Applicant's Actions or Behavior Communications requiring reports back to the examinees will be scripted. Unexpected communications requiring report back will be approved by the Lead examiner prior to contacting the Control Room. .

Examiner Note: Throughout this scenario, steps not applicable to the event may be omitted.

AOP-C.02 Step 1 thru Section 2.2 Step 8 SRO ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:1 Page 3 of 85 Event

Description:

Uncontrolled Dilution Time Position Applicant's Actions or Behavior ATC ATC ATC MAY SELECT 1-HS-62-143 to CLOSE ATC ATC ATC ATC PLACES 1-HS-81-3A IN PTL ATC PLACES 1-HS-81-7A in PTL

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:1 Page 4 of 85 Event

Description:

Uncontrolled Dilution Time Position Applicant's Actions or Behavior Communications: When requested as Unit 2, acknowledge direction to PLACE BOTH Primary Water Pumps in PULL TO LOCK. (No action required).

ATC ATC Notifies Unit 2 to PLACE BOTH Primary Water Pumps in PULL TO LOCK.

Communications: When Requested as AUO, acknowledge direction to PLACE Waste Gas Compressors in STOP/PULL position (No action required)

ATC ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:1 Page 5 of 85 Event

Description:

Uncontrolled Dilution Time Position Applicant's Actions or Behavior Communications: When requested, acknowledge direction to perform Appendix A.

ATC BOP NOTIFIES AUO to perform APPENDIX A AOP-C.02 Appendix A Examiners Note: These actions are performed outside the Main Control Room.

Communications: When directed by Lead Examiner, Use KEY 11 to close FCV-62-932. Report, FCV-62-932 was found partially OPEN and it is now CLOSED..

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:1 Page 6 of 85 Event

Description:

Uncontrolled Dilution Time Position Applicant's Actions or Behavior AOP-C.02 Section 2.2 Step 9 thru 19 ATC ATC ATC NOTIFIES Chem Lab to sample RCS and PZR boron.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:1 Page 7 of 85 Event

Description:

Uncontrolled Dilution Time Position Applicant's Actions or Behavior BOP ATC ATC ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:1 Page 8 of 85 Event

Description:

Uncontrolled Dilution Time Position Applicant's Actions or Behavior ATC ATC Restores Primary Water Pumps to one RUNNING (NORMAL AFTER START)

ATC and one in STANDBY (NORMAL AFTER STOP and PULLED OUT)

ATC SELECTS 1-HS-62-143 to AUTO, as required.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:2 Page 9 of 85 Event

Description:

Containment Pressure Transmitter Failure Time Position Applicant's Actions or Behavior EVENT 2- Containment Pressure Transmitter Failure Direct simulator operator to insert Event 2 (KEY 2)

Indications available:

3-C E-2 STM GEN LEVEL ADVERSE SETPOINT

6-B A-6 PDS-30-42B CONTAINMENT HIGH PRESSURE S.I. ACTUATE

6-B B-6 PDS-30-42 A CONTAINMENT HI-HI PRESSURE STEAMLINE ISOL Indications

1-PDI-30-44 (CNTMT PRESSURE WIDE RANGE) pegged high

1-XI-3-204 (SG LEVEL ADVERSE SP) Blue Light lit

FS-3-35B SG1 FW<STM status light lit

FS-3-103B FW SG4<STM status light lit 1-AR-M6-B- A-6 BOP SRO Transitions AOP-I-0.5, Containment Instrument Malfunction.

1-AR-M6-B- B-6

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:2 Page 10 of 85 Event

Description:

Containment Pressure Transmitter Failure Time Position Applicant's Actions or Behavior ATC SRO Transitions AOP-I-0.5, Containment Instrument Malfunction.

1-AR-M3-C E-2 ATC SRO Transitions AOP-I-0.5, Containment Instrument Malfunction.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:2 Page 11 of 85 Event

Description:

Containment Pressure Transmitter Failure Time Position Applicant's Actions or Behavior AOP-I.05 Steps 1 thru Section 2.1 step 2 SRO Directs actions from AOP-I-0.5, Containment Instrument Malfunction..

ATC ATC SRO Determines the following LCOs are Applicable 3.3.1 Conditions A and S (Function 13.a)

SRO 3.3.2 Conditions A, D (Function 1.c), E (Function 2.c,3.b.3,4.c) and J (Function 6.b.1 3.3.3 Condition A (Function 4)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:2 Page 12 of 85 Event

Description:

Containment Pressure Transmitter Failure Time Position Applicant's Actions or Behavior LCO 3.3.1

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:2 Page 13 of 85 Event

Description:

Containment Pressure Transmitter Failure Time Position Applicant's Actions or Behavior

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:2 Page 14 of 85 Event

Description:

Containment Pressure Transmitter Failure Time Position Applicant's Actions or Behavior LCO 3.3.2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:2 Page 15 of 85 Event

Description:

Containment Pressure Transmitter Failure Time Position Applicant's Actions or Behavior

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:2 Page 16 of 85 Event

Description:

Containment Pressure Transmitter Failure Time Position Applicant's Actions or Behavior

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:2 Page 17 of 85 Event

Description:

Containment Pressure Transmitter Failure Time Position Applicant's Actions or Behavior LCO 3.3.3 AOP-I.05 Section 2.1 Steps 3 thru 4 Communications: When notified to perform Appendix C Report that I & C will be in the control room in

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:2 Page 18 of 85 Event

Description:

Containment Pressure Transmitter Failure Time Position Applicant's Actions or Behavior about 45 minutes following a shop briefing.

BOP SRO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:3 Page 19 of 85 Event

Description:

ERCW Pump Shaft Shear Time Position Applicant's Actions or Behavior EVENT 3- ERCW Pump Shaft Shear Direct simulator operator to insert Event 3, (KEY 3)

Indications available:

27-A B-2: PUMP R-A DISCH PRESS LOW Indications

0-PI-67-465A (ERCW PUMP R-A DISCH PRESS) lowers to zero 0-AR-M27-A B-2 Examiners Note: Some steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.

BOP SRO Enters AOP-M.01, Loss of Essential Raw Cooling Water.

AOP-M.01 Step 1 thru 7 19

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:3 Page 20 of 85 Event

Description:

ERCW Pump Shaft Shear Time Position Applicant's Actions or Behavior BOP BOP SRO BOP PLACES 0-HS-67-464A ERCW PUMP R-A in PTL BOP BOP PLACES 0-HS-67-436A (ERCW PUMP K-A) momentarily to START BOP 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:3 Page 21 of 85 Event

Description:

ERCW Pump Shaft Shear Time Position Applicant's Actions or Behavior BOP BOP Communications: When requested to inspect ERCW pumps, acknowledge, wait 5 minutes and report There is nothing abnormal at the ERCW pumps.

BOP Examiners Note: Tech Spec evaluation may be defered until higher priority steps are completed.

SRO Determines LCO 3.7.8 Action B is applicable from the time of the R-A ERCW pump trip until the Power Selector Switch is re-positioned to K-A position. Also SRO determines LCO 3.8.1 Condition B is applicable for 1A-A EDG and 2A-A EDG during the same time.

21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:3 Page 22 of 85 Event

Description:

ERCW Pump Shaft Shear Time Position Applicant's Actions or Behavior LCO 3.7.8 Condition B Examiners Note: Site expectation is to perform SR 3.8.1.1 even if EDG is returned to service. If desired Unit 2 can assume responsibility for performing that procedure.

AOP-M.01 Step 8 thru 11 BOP BOP PLACES 0-XS 288 to K-A position 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:3 Page 23 of 85 Event

Description:

ERCW Pump Shaft Shear Time Position Applicant's Actions or Behavior BOP Communications: When requested, report no significant leakage from ERCW pump R-A BOP ATC 23

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:4 Page 24 of 85 Event

Description:

Condenser Circ Water Travelling Screen Failure Time Position Applicant's Actions or Behavior EVENT 4- Condenser Circ Water Travelling Screen Failure Direct simulator operator to insert Event 4, (KEY 4)

Indications available:

15-A A-4: PdS-27-13B TRAV SCREEN 1B DIFF PRESS HI Indications

1-PDI-27-13A (TRAVELING SCREEN DP) rises above 5 inches of water 1-AR-M15-A A-4 Examiners Note: Some steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.

BOP BOP PLACES the following switches momentarily in the START position 1-HS-27-4A BOP 1-HS-27-14A 1-HS-27-24A BOP 24

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:4 Page 25 of 85 Event

Description:

Condenser Circ Water Travelling Screen Failure Time Position Applicant's Actions or Behavior BOP 25

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:5 Page 26 of 85 Event

Description:

Lowering EHC Pressure Time Position Applicant's Actions or Behavior EVENT 5- Lowering EHC Pressure Direct simulator operator to insert Event 5, (KEY 5)

Indications available:

2-A B-3: PS-47-23 ELECTRO-HYD FLUID PRESS LOW (First Out)

2-A C-3: PS-47-21 RESERVE E-H FLUID PUMP RUNNING

2-A C-1: PS-47-20 ELEC-HYD FLUID SYSTEM PRESSURE LOW-LOW Indications 1-AR-M2-A B-3 Examiners Note: Some steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.

Communications: When requested, report you are on your way to inspect the affected equipment.

After Reserve Pump Running alarm report, The standby EHC pump is running and there are not apparent leaks or other abnormalities except low pressure.

BOP 26

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:5 Page 27 of 85 Event

Description:

Lowering EHC Pressure Time Position Applicant's Actions or Behavior BOP 1-AR-M2-A C-3 Examiners Note: Some steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.

27

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:5 Page 28 of 85 Event

Description:

Lowering EHC Pressure Time Position Applicant's Actions or Behavior BOP 1-AR-M2-A C-1 Examiners Note: Some steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.

Communications: When system Pressure Low-Low annunciator is in report, EHC Pressure is 1340 psig and stable. Shift Manager directs and AOP-C.03 Emergency Shutdown to 20%

power.

28

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:5 Page 29 of 85 Event

Description:

Lowering EHC Pressure Time Position Applicant's Actions or Behavior BOP SRO Transitions to AOP-C.03 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:5 Page 30 of 85 Event

Description:

Lowering EHC Pressure Time Position Applicant's Actions or Behavior AOP-C.03 Step 1 SRO AOP-C.03 Appendix A 30

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:5 Page 31 of 85 Event

Description:

Lowering EHC Pressure Time Position Applicant's Actions or Behavior AOP-C.03 Step 2 CREW Examiner Note: Appendix B consists of three copies of this page. Only page 1 is included here.

AOP-C.03 Appendix B 31

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:5 Page 32 of 85 Event

Description:

Lowering EHC Pressure Time Position Applicant's Actions or Behavior AOP-C.03 Step 3 thru 5i BOP Communications: If requested as WCC SRO or Unit 2 Operator, acknowledge direction to make notifications per the step below.

BOP ATC ATC 32

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:5 Page 33 of 85 Event

Description:

Lowering EHC Pressure Time Position Applicant's Actions or Behavior Examiner Note: Expected boration volume is expected to be approximately 560 gallons (per second bullet) for power reduction from 76% to 20%

ATC Examiner Note: Initial boration method selected will malfunction requiring using the other method.

Verifiable Actions are listed in each appendix. Actions associated with the failed method are not applicable. SEE EVENT 6 Examiner Note: Expected boration flow rate is expected to be 2% per minute. Other values are acceptable if they support reduction to Mode 3 with 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . At the discretion of the Chief Examiner a load reduction rate up to 4 % may be specified.

SRO SRO Directs load reduction rate of 2% (~30 gpm) 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:5 Page 34 of 85 Event

Description:

Lowering EHC Pressure Time Position Applicant's Actions or Behavior Examiner Note: IF necessary, provide confirmation that the STA concurs with the boration volume and flowrate.

SRO ATC SRO BOP 34

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 35 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior EVENT 6 - Failure of Boration Flowpath Event 6 occurs automatically AOP-C.03 Appendix I Examiner Note: In the following steps, boration will be by either emergency or normal method. The first method selected will fail.

If Normal method is selected first use KEY 10 to cause valve 62-140D to fail CLOSED.

If Emergency method is selected use KEY 11 to cause the emergency boration flow control valve 62-138 tol fail closed after 30 seconds.

EMERGENCY BORATION (APPENDIX I)

NORMAL BORATION APPENDIX H.

(Appendix H is provided following Appendix I below)

Also Appendix F for Boration from RWST is included on page 41 ATC ATC Records values determined earlier 35

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 36 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior ATC ATC a) Momentarily PLACES 1-HS-62-230A, BA TRANSFER PUMP 1A in STOP; b) SELECTS 1-HS-62-230D BA TRANSFER PUMP 1A SPEED SEL to FAST; c) Momentarily PLACES 1-HS-62-230A, BA TRANSFER PUMP 1A in START (May perform the same actions for the B BA TRANSFER pump but this is not required.)

It is acceptable to perform detail b) prior to detail a)

ATC ATC THROTTLES OPEN 1-HS-62-138A until flowrate on 1-HS-62-137A indicates flowrate from step 1 ATC ATC Records values for boration flow rate and time started.

ATC 36

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 37 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior ATC ATC SELECTS 1-HS-62-138A to CLOSE until flowrate on 1-HS-62-137A indicates ATC zero and GREEN light is LIT.

ATC a) Momentarily PLACES 1-HS-62-230A, BA TRANSFER PUMP 1A in STOP; b) SELECTS 1-HS-62-230D BA TRANSFER PUMP 1A SPEED SEL to SLOW; c) Momentarily PLACES 1-HS-62-230A, BA TRANSFER PUMP 1A in ATC START (Performs the same actions for the B BA TRANSFER pump if it was shifted to fast earlier)

It is acceptable to perform detail b) prior to detail a) 37

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 38 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior AOP-C.03 Appendix H ATC ATC Records values determined earlier ATC ATC Places 1-HS-62-140A, BA SUPPLY TO BLENDER in STOP ATC ATC Places 1-HS-62-140B, MAKEUP MODE SELECTOR in BORATE ATC ATC ADJUSTS 1-FC-62-139 BORIC ACID TO BLENDER setpoint to the desired flowrate as determined earlier (30 expected)

ATC ATC ADJUSTS FQ-62-139, BORIC ACID BATCH COUNTER to desired boric acid volume. (560 expected)

ATC Places 1-HS-62-140A, BA SUPPLY TO BLENDER in START ATC 38

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 39 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior ATC ATC Observes about 30 gpm flow indicated on 1-FI-62-139 (for 2% rate other values ATC acceptable.)

ATC ATC Records time flow is established Examiner Note: The completion of this Appendix may be delayed due to higher priority tasks from upcoming events.

ATC ATC Places 1-HS-62-140A, BA SUPPLY TO BLENDER in STOP ATC ATC ATC Restores 1-FC-62-139 setpoint to original value 39

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 40 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior ATC ATC Places 1-HS-62-140B, MAKEUP MODE SELECTOR in AUTO ATC ATC Places 1-HS-62-140A, BA SUPPLY TO BLENDER in START ATC 40

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 41 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior AOP-C.03 Appendix F ATC 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 42 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior ATC 42

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 43 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior 43

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 44 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior AOP-C.03 Step 5j thru 9 ATC BOP 44

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 45 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior BOP BOP PLACES LOAD RATE thumbwheel to 2% per minute (expected)

Examiner Note: Expected SETTER setpoint is 15 BOP BOP ADJUSTS SETTER to about 15 BOP BOP BOP DEPRESSES GO pushbutton 45

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 46 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior Examiner Note: BOP may stop and restart turbine load reduction based on plant response. This is done by depressing the HOLD pushbutton to stop the reduction then depressing the GO pushbutton to reinitiate the reduction. They may also reduce the LOAD RATE via the thumbwheel.

BOP BOP CREW BOP May ADJUST LOAD RATE thumbwheel or stop and start the load reduction via the HOLD and GO pushbuttons.

46

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 47 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior CREW BOP BOP Examiner Note: At chief Examiners discretion proceed to Next Event 47

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 48 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior AOP-C.03 Appendix C (first 3 pages) 48

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 49 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior 49

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 50 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior 50

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 51 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior AOP-C.03 Step 10 thru 15e ATC SRO SRO BOP 51

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:6 Page 52 of 85 Event

Description:

Failure of Boration Flowpath Time Position Applicant's Actions or Behavior BOP Communications: When requested, as Chemistry, acknowledge direction to initiate sampling.

CREW Lead Examiner may cue the next event when desired.

52

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 53 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior EVENT 7- SGTR #1 Direct simulator operator to insert Event 7, (KEY 7)

Event 8 automatically deenergizes the 1A 6.9KV SDBD 30 seconds after Rx Trip Indications available:

12-A D-3: 1-RA-90-99A CNDS VAC PMP LO RNG AIR EXH MON HIGH RAD Indications

Rising level in #1 SG with lowering pressurizer level 0-AR-M12-A D-3 Examiners Note: Some steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.

BOP Communications: When requested as Chemistry, acknowledge direction to perform 1-SI-CEM-068-137.5 Primary to Secondary Leakage via Steam Generators.

BOP BOP Notifies Chemistry to perform procedure1-SI-CEM-068-137.5 53

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 54 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior SRO SRO Enters AOP-R.01, Steam Generator Tube Leak AOP-R.01 Step 1 thru Section 2.1 Step 2b Examiners Note: Crew may initially enter Section 2.2 if they do not determine that Pzr level is changing based on plant response from previous events. Step 1 of Section 2.2 establishes MONITORING of Pzr level and charging flow and directs transition to Section 2.1 when charging flow is determined to be rising or Pzr level is determined to be lowering due to S/G tube leak. Section 2.2 Actions are similar and not included here SRO Transitions to Section 2.1 (expected) or 2.2 (possible based on existing plant SRO response.

ATC PLACES FCV-62-93 in manual and control charging flow, may adjust HIC-62-89A ATC to maintain RCP Seal Flow 54

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 55 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior ATC ATC PLACES HS-FCV-62-72, FCV-62-73 CLOSED, and FCV-62-74 to CLOSE.

SRO ATC PLACES 1-HS 108A momentarily to START ATC SRO DIRECTS Rx Trip ATC TRIPS Rx by momentarily PLACING 1-RT-1 in TRIP position Examiners Note: There is a time delay before SI signal actuates.

VERIFIES that RX is tripped and ACTUATES SI by Momentarily PLACING 1-HS-ATC 63-133B to ACTUATE position SRO TRANSITIONS to E-0, Reactor Trip or Safety Injection 55

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 56 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior E-0 Step 1 thru 4 Examiner Note: Following IOA performance, prior to Steps 1-4 immediate action verification, ATC/BOP surveys MCBs for any expected automatic system response that failed to occur.

Upon discovery, they may take manual action(s) to align plant systems as expected for the event in progress. (Ref. EPM-4, Prudent Operator Actions). This may include closing the TDAFW LCVs to preclude S/G overfill.

CREW Performs the first four steps of E-0 unprompted.

SRO Directs performance of E-0 REACTOR TRIP OR SAFETY INJECTION.

ATC BOP BOP Examiners Note: It is likely that the BOP will take prudent action (for a failed automatic actuation) to start EDG-1A at this point.

ATC 56

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 57 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior E-0 Step 5 thru 7b ATC ATC Examiners Note: ES-0.5 see EVENT 8 page 77 BOP BOP Performs ES-0.5 57

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 58 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior E-0 Steps 7c thru 11 ATC ATC Takes MANUAL CONTROL of MD AFW LCVs, CLOSES TD aFW LCVs as BOP necessary, and CONTROLS AFW flow between 440 and 600 gpm until one or more sGs are >10% level.

58

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 59 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior ATC SRO TRANSITIONS to E-3, Steam Generator Tube Rupture 59

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 60 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior E-3 Step 1 thru 5b ATC ATC CREW CREW Determines #1 S/G is RUPTURED 60

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 61 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior ATC BOP ADJUSTS PIC-1-6A setpoint to 87%

BOP SRO SRO Determines #1 S/G is ruptured BOP CRITICAL TASK(18) BOP Places FCV-1-15 in CLOSE, if not already done.

ATC BOP CRITICAL TASK(18) BOP Places 1-HS-1-4A in CLOSE.

61

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 62 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior BOP BOP CRITICAL Places HS-3-164A AFW Pump 1A-A to LCV to SG 1 to ACC RESET and RAMP TASK(18) BOP CLOSE.

BOP CRITICAL TASK(18) BOP Places HS-3-174A in CLOSE.

BOP 62

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 63 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior E-3 Step 6 thru 26 BOP BOP BOP BOP 63

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 64 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior CRE SRO Determines target temperature BOP BOP Places HS-63-135A and 135B momentarily in BLOCK position BOP 64

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 65 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior BOP BOP BOP Places HS-1-103A and 103B OFF RESET position BOP Places 1-HS-1-103D in STEAM DUMP MODE SELECTOR in STEAM PRESS BOP position. Observes 1-XI-1-33 STEAM DUMP DEMAND reading less then 25%.

BOP BOP Places HS-1-103A and 103B in ON position Examiners Note: In the following step it is acceptable for more than 3 steam dump valves to momentarily come open as as examinee fine tunes controller to obtain 3 fully open cooldown valves.

Examiners Note: The critical task associated with RCS temperature is met cooling down to target temperature and not overcooling or heating back up (see page 69)

CT-19 Manually establish/maintain an RCS temperature so that transition from E-3 does not occur because the RCS temperature is in any of the following conditions:

Too high to maintain > 60 degrees CET subcooling.

RED path on PTS Status Tree OR

ORANGE path on Subcriticality Status Tree 65

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 66 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior BOP Places 1-PIC 33 STEAM DUMP PRESSURE CONTROL in MANUAL selecting BOP toggle switch to the OPEN (right) direction until FCV-1-130, 107, and 111 indicate OPEN the 9 other steam dump valves should indicate CLOSED BOP BOP Places HS-1-103A and 103B momentarily in the BYPASS INTLK position BOP OPENS TDAFW LCVs (except for HS-3-174A) and raises flow through MDAFW BOP LCVs (except for HS-3-176A) to support cooldown Examiners Note: In the following step after closing steam dumps, examinee may adjust automatic setpoint to match existing steam pressure (in non ruptured SGs) and place controller back in AUTO to assist in maintaining temperature.

BOP On 1-PIC 33 STEAM DUMP PRESSURE CONTROL depresses << pushbutton BOP until FCV-1-130, 107, and 111 indicate CLOSED BOP 66

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 67 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior Throttles TD and MD AFW LCVs to reduce total AFW flow <600 gpm. If all SGs are BOP less than 10% then AFW flow is maintained between 440 and 600 gpm.

BOP BOP Throttles steam dumps (in AUTO or MANUAL) to maintain CETs below target temp BOP ATC ATC Momentarily DEPRESSES 1-HS-63-134A SIS RESET TRAIN 1A and 1-HS-63-134B ATC SIS RESET TRAIN 1B pushbuttons BOP ATC DEPRESSES 1-HS-30-63D PHASE A ISOL RESET - TR A and 1-HS-30-63E ATC PHASE A ISOL RESET - TR B pushbuttons 67

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 68 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior BOP ATC PLACES 1-HS-74-10A RHR PUMP 1A and 1-HS-74-20A RHR PUMP 1B ATC momentarily in the STOP position.and return to A-AUTO position.

ATC BOP 68

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 69 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior On 1-PIC 33 STEAM DUMP PRESSURE CONTROL depresses << pushbutton BOP until FCV-1-130, 107, and 111 indicate CLOSED BOP Throttles TD and MD AFW LCVs to reduce total AFW flow <600 gpm. If all SGs are BOP less than 10% then AFW flow is maintained between 440 and 600 gpm.

BOP CRITICAL Throttles steam dumps (in AUTO or MANUAL) to maintain CETs below target temp TASK(19) BOP (See Critical Task details on page 65)

BOP ATC ATC 69

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 70 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior Examiners Note: IF SG level s >84% This step will not be performed and a PORV will be used for depressurization.

OPENS one or both Normal Pzr Spray Valves by momentarily DEPRESSING CRITICAL TASK(20) ATC MANUAL pushbutton and DEPRESSING >> (May also use RAMP pushbutton) for 1-PIC-68-340D and/or 1-PIC-68-334B.

ATC ATC 70

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 71 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior ATC ATC ATC ATC ATC 71

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 72 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior Examiners Note: This step will not be performed if Normal spray is used for depressurization CRITICAL TASK(20) ATC OPENS one PORV (68-334 or 68-340)

ATC ATC CLOSE PORV opened in revious step.

ATC At the discretion of the Chief Examiner the scenario may be terminated when SI termination criteria have been met.

72

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 73 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior ATC ATC 73

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 74 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior ATC ATC 74

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 75 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior ATC 75

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:7 Page 76 of 85 Event

Description:

SGTR #1 Time Position Applicant's Actions or Behavior 76

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:8 Page 77 of 85 Event

Description:

SDBD UV with EDG Auto Start Failure Time Position Applicant's Actions or Behavior EVENT 8- SDBD UV with EDG Auto Start Failure Examiners Note: Event 8 automatically deenergizes the 1A 6.9KV SDBD 30 seconds after Rx Trip. With failure of 1A EDG to AUTO Start it is expected that the BOP will manually start the EDG as an immediate action of AOP-P.01 or Prudent Action for a Failed Automatic Actuation or as directed by ES-0.5 below ES-0.5 Steps 1 thru 17 BOP Manually STARTS EDG-1A by :

DEPRESSING 1-HS-82-16A pushbutton (DG 1A-A EMERGENCY START) on the EDG (M26) Panel BOP OR Momentarily PLACES 1-HS-82-15 (DG EMERGENCY START 1A-A, 2A-A, 1B-B, 2B-B) to EMERG START BOP Communications: When directed to perform Attachment 7 Acknowledge direction. (No Further Action Required)

BOP BOP 77

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:8 Page 78 of 85 Event

Description:

SDBD UV with EDG Auto Start Failure Time Position Applicant's Actions or Behavior BOP BOP BOP BOP Makes plant announcement BOP BOP 78

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:8 Page 79 of 85 Event

Description:

SDBD UV with EDG Auto Start Failure Time Position Applicant's Actions or Behavior BOP BOP BOP 79

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:8 Page 80 of 85 Event

Description:

SDBD UV with EDG Auto Start Failure Time Position Applicant's Actions or Behavior BOP BOP 80

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:8 Page 81 of 85 Event

Description:

SDBD UV with EDG Auto Start Failure Time Position Applicant's Actions or Behavior BOP 81

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:8 Page 82 of 85 Event

Description:

SDBD UV with EDG Auto Start Failure Time Position Applicant's Actions or Behavior BOP BOP BOP 82

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:8 Page 83 of 85 Event

Description:

SDBD UV with EDG Auto Start Failure Time Position Applicant's Actions or Behavior BOP ES-0.5 Appendix A Examiner Note: Appendix A and B step 2 is Unit 2 only 83

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:8 Page 84 of 85 Event

Description:

SDBD UV with EDG Auto Start Failure Time Position Applicant's Actions or Behavior ES-0.5 Appendix B ES-0.5 Step 18 thru end BOP BOP Communications: IF requested as Unit 2 RO acknowledge direction to perform EA-65-1 84

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 3 Event No.:8 Page 85 of 85 Event

Description:

SDBD UV with EDG Auto Start Failure Time Position Applicant's Actions or Behavior BOP Communications: When requested as Unit 2 RO, acknowledge direction to perform EA-0-1 BOP BOP Communications: If requested as available AUO, acknowledge direction to perform appendix E BOP 85

Today Mode 1 76% 910 MWe Train Week: B RCS Boron: 1071 ppm BAT A RCS Leakage:

EOOS: Green Last Shift: Dilution: Rx Plan Total: Rx plan Identified: 0.01 GPM Grid Status: Qualified This Shift: Boration: Rx plan Total: Rx plan Unidentified: 0.04 GPM Site Aggregate Risk: Low Shutdown LCO Conditions Equipment INOP Next Action Due LCO 3.6.6 Condition A CSP-1B 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months Other LCO Actions Equipment INOP Next Action Due Info Only Tech Specs Equipment INOP Abnormal Equipment Lineup / Conditions (including significant Radiological changes)

Severe Thunderstorm warning is in effect for Hamilton County FT-1-3A Failed. In MAINT BYPASS Shift Priorities (Surveillances/Testing and Major Activities in Progress or Scheduled)

Maintain current power level Restore CSP-1B when work is complete For each MCR deficiency, a numbered square will be applied to the MCR Board near the associated indication/alarm. (US maintains magnets)

The CR/WO number and description of the issue will be listed below Main Control Room (7690)

Auxiliary Building (7671)

Turbine Building (7771)

TB Sump: LVWT Pond RCW: Unit 2 Aux Steam: Unit 1 Outside (7666) (423-710-4777)

Miscellaneous

2003 NRC SCN 3 Booth Instructions BOOTH OPERATOR INSTRUCTIONS Sim. Setup Reset IC-14 76% 1071ppmb BOL Perform switch check.

Verify control rod step counters reset.

Place simulator in RUN.

Place Mode 1 placard on panels.

Place B Train Week sign on the simulator.

Place FT-1-3A in MAINT BYP Place CSP-1B in PTL Hang Red Tag Load SCN file: - ILT2003 NRC SCN 3 Acknowledge any alarms, allow the plant to stabilize, and freeze the simulator.

Perform the SIMULATOR OPERATOR CHECKLIST Place simulator in RUN before crew enters the simulator.

Start Data Capture

1. REMOVE ORANGE DOTS WHEN SCENARIO COMPLETE Page 1 of 4

2003 NRC SCN 3 Booth Instructions EVENT IC/MF/RF/OR # DESCRIPTION/EXPECTED ACTIONS/BOOTH FEEDBACK FT-1-3A in Maintenance Bypass MAIN STEAM FLOW This is manually inserted during TRANSMITTER FAILS LOW FT-setup IMF RX10A f:1 1-3A

CONTAINMENT SPRAY PUMP Active from beginning IOR CSR04 f: 0 B POWER Throughout this scenario routine communications directing administrative actions, reports, or notifications may be answered by acknowledging the report or direction. Communications requiring reports back to the examinees will be scripted. Unexpected communications requiring report back will be approved by the Lead examiner prior to contacting the Control Room. .

When directed by the Lead

---DILUTION TO CHARGING Examiner, use KEY 1 to insert IRF CVR18 f: 40 k:1 PMP SUCTION 62-932 malfunction Acknowledge direction to PLACE BOTH Primary Water Communication for Event 1 When requested as Unit 2 Pumps in PULL TO LOCK.

(No action required).

Acknowledge direction to PLACE Waste Gas Communication for Event 1 When requested as AUO Compressors in STOP/PULL position (No action required)

Acknowledge direction to Communication for Event 1 When requested as AUO perform Appendix A

---Auto delete malfunction when 1B condenser vacuum pump {Key[11]} ior CVR18 f: 0 ;---Close leaking valve started When directed by Lead FCV-62-932 was found Communication for Event 1 Examiner, Use KEY 11 to close partially OPEN and it is now FCV-62-932. CLOSED..

When directed by the Lead ;---CONTAINMENT PRESSURE Examiner, use KEY 2 to insert IMF CH01C f:100 k:2 TRANSMITTER FAILURE PDT malfunction 30-44 When notified to perform Report that, I & C will be in the Appendix C Report that I & C will control room in about 45 Communication for Event 2 be in the control room in about minutes following a shop 45 minutes following a shop briefing briefing When directed by the Lead

---ERCW PUMP R-A SHEARED Examiner, use KEY 3 to insert IMF RW18H f: 1 k:3 SHAFT malfunction.

Page 2 of 4

2003 NRC SCN 3 Booth Instructions EVENT IC/MF/RF/OR # DESCRIPTION/EXPECTED ACTIONS/BOOTH FEEDBACK When requested to inspect There is nothing abnormal at Communication for Event 3 ERCW pumps, acknowledge, the ERCW pumps.

wait 5 minutes and report No significant leakage from Communication for Event 3 When requested, report ERCW pump R-A IMF CW03A f:14 r:120 k:4 ;---CCW TRAVELING SCREEN IOR ZDIHS2704A f:3 1A CLOGGING EVENT 4 IOR ZDIHS2714A f:3 ;---Auto Start Failure 1A, 1B, 1C IOR ZDIHS2724A f:3 Screen Wash Pumps

{zdihs2704a_real[0]} dmf ZDIHS2704A ;---Delete Auto Start Failure

{zdihs2714a_real[0]} dmf Screen Wash Pumps when ZDIHS2714A switches taken to start

{zdihs2724a_real[0]} dmf ;---deletes clogging CCW ZDIHS2724A screens and reading returns to

{zdihs2704a_real[0]} normal over 2 minutes imf CW03A f:1 r:120 Communication for Event 4 IMF AN_OV_85 f:2 k:5 ;---EHC Low Pressure Alarm When directed by the Lead IMF AN_OV_92 d:90 f:2 k:5 ;--- PS-47-21 RESERVE EHC Examiner, use KEY 5 to insert FLUID PUMP RUNNING malfunction. IMF AN_OV_1303 d:180 f:2 k:5 ;--- PS-47-20 ELEC-HYD FLUID PRESS LOW TURB TRIP; When requested, report you are Communication for Event 5 on your way to inspect the affected equipment.

The standby EHC pump is running and there are not After Reserve Pump Running apparent leaks or other alarm report abnormalities except low pressure.

EHC Pressure is 1340 psig and stable. Shift Manager When system Pressure Low-Low directs and AOP-C.03 annunciator is in Report Emergency Shutdown to 20%

power.

Page 3 of 4

2003 NRC SCN 3 Booth Instructions EVENT IC/MF/RF/OR # DESCRIPTION/EXPECTED ACTIONS/BOOTH FEEDBACK For EVENT 6

---Initial method for boration fails after 30 seconds

---second boration method works If Normal method is selected first use KEY 10 to cause valve 62-140D to fail CLOSED.

If Emergency method is selected use KEY 11 to cause the emergency boration flow control valve 62-138 to fail closed after 30 seconds.

Acknowledge direction to If requested as WCC SRO or make notifications to Unit 2 Operator, acknowledge Balancing Authority, direction to make notifications Chemistry, Radiation per the step below. Protection, Plant Management..

acknowledge direction to, When requested, as Chemistry, initiate sampling.

---normal Boration fails 30 If Normal method is selected first IOR ZDIHS62140D f: 0 d:30 k:10 seconds after inserting KEY 10

---valve 62-140D fails closed

---emergency boration fails after If Emergency method is selected IOR ZDIHS62138A f: 0 d:30 k:11 30 seconds first

---valve 62-138 goes closed When directed by the Lead Examiner, use KEY 7 to insert ;---SGTR ramps in over 5 IMF TH05A f: 9.15 r:300 k:7 malfunction minutes When directed to perform Communication for Event 7 No Further Action Required Attachment 7 Acknowledge

---A SDBD De-ENERGIZES 30 EVENT 8 IMF ED09A f: 1 d:30 e:1 seconds after Rx trip Inserted automatically after Rx IMF EG08A f:1 ;---DG 1A-A AUTO-START trip FAILURE Acknowledge direction to When requested as Unit 2 RO, perform EA-0-1 Acknowledge direction to IF requested as Unit 2 RO perform EA-65-1 Acknowledge direction to If requested as available AUO, perform appendix E Page 4 of 4

Appendix D Scenario Outline Form ES-D-1 Facility: Sequoyah Scenario No.: 4 Op Test No.: 2020-301 Examiners: Operators: SRO ATC BOP Initial Conditions: 100% BOL Turnover: Unit 1 is in MODE 1 100%, BOL FT-1-3A is in Maintenance Bypass Containment Spray Pump 1B OOS Severe Thunderstorm watch is in effect for Hamilton County Critical Tasks CT-18 Manually isolate feed water flow into and steam flow from the ruptured S/G before a transition to ECA-3.1 is required.

CT-19 Manually establish/maintain an RCS temperature so that transition from E-3 is not required because the RCS temperature is in any of the following conditions:

Too high to maintain > 60 degrees CET subcooling.

RED path on PTS Status Tree OR

ORANGE path on Subcriticality Status Tree CT-20 Manually depressurize RCS to meet and maintain SI termination criteria while in E-3 prior to exceeding 100% S/G dome level on the simulator during a SGTR of 430 gpm or less (TH05 9.15%).

CT-FRV Take manual control of FRV and restore SG level prior to RX trip.

Event Malf. Event Event Description No. No. Type 120 V vital power breaker to lower Containment radiation monitor 1-ED120B1B 1

007 TS-SRO RM-90-106 trips. The SRO declares the Radiation Monitor INOPERABLE and SRO addresses LCO.

(C) ATC Charging Pump 1B Trips. ATC starts A CCP per AOP-M.09. SRO 2 CV01B TS-SRO addresses LCO VCT level transmitter fails high, resulting in letdown diverting to 3 CV11 (I) ATC HUT. ATC selects divert valve back to VCT per ARP.

An Exciter Insulation Resistance Low alarm occurs along with rising (R) ATC 4 AN_OV_59 vibration on Generator Bearing. The crew will reduce power per (N) BOP AOP-C.03.

During the reduction in power, Feed Regulating valve fails to control 5 FW16B (C) BOP in AUTO. BOP places FRV in MANUAL per AOP-S.01 A leak develops in the Condenser Cooling water Crew will trip the 6 AN_OV_699 (C) BOP Reactor and enter E-0. BOP will stop all Unit 1 CCW pumps and isolate all Unit 1 Main Condenser Waterboxes to stop the leak.

A large SGTR develops in #1S/G. The crew will initiate Safety SGTR_arv 7

TH05A (M) ALL Injection and restart E-0. Crew will transition to E-3 with Condenser unavailable and cooldown and depressurize RCS via ARVs Spray Valve fails open while depressurizing RCS. Crew will stop 8 RC06B (C) ATC RCPs

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

Appendix D Scenario Outline Form ES-D-1 2020-301 Scenario 4 Summary Event 1 - 120 V vital power breaker to Lower Containment radiation monitor 1-RM-90-106 trips. The SRO declares the radiation Monitor INOPERABLE. SRO addresses LCO Verifiable actions: TS only.

Event 2- Charging Pump 1B Trips. ATC starts CCP-1A and recovers letdown per AOP-M.09, Loss of Charging. SRO addresses LCO Verifiable actions: (ATC) starts CCP-1A and recovers letdown.

Event 3- VCT level transmitter fails high, resulting in letdown diverting to HUT. ATC selects divert valve back to VCT per ARP.

Verifiable actions: ATC selects divert valve back to VCT Event 4- An Exciter Insulation Resistance Low alarm occurs. The crew will reduce power per ARP and AOP-C.03, Rapid Shutdown or Load Reduction Verifiable actions: (ATC) performs boration (BOP) performs turbine load reduction.

Event 5 - During the reduction in power, Feed Regulating valve FCV-3-48 fails to control in AUTO, the BOP places FIC-3-48 in MANUAL to control SG level on program per AOP-S.01, Main Feedwater Malfunctions prior to Rx Trip (CT-FRV)

Verifiable actions: (BOP) places FRV in MANUAL and controls SG level.

Event 6 - A leak develops in the Condenser Cooling water. Crew will enter AOP-M.08 to locate and isolate the leak. Crew will trip the Reactor and enter E-0. BOP will stop all Unit 1 CCW pumps and isolate all Unit 1 Main Condenser Waterboxes to stop the leak.

Verifiable actions: (BOP) stops CCW pumps and isolates waterboxes Event 7 - A large SGTR develops in #1S/G. The crew will initiate Safety Injection and restart E-0. Crew will transition to E-3 with Condenser unavailable and cooldown and depressurize RCS via ARVs (CT-18)

(CT-19)

Verifiable actions: (BOP) isolates AFW to ruptured SG. (ATC) will depressurize RCS with normal spray Event 8 - Spray Valve fails open while depressurizing RCS. Crew will stop RCPs to terminate depressurization (CT-19) (CT-20)

Verifiable actions: (ATC) stops RCPs.

Terminate in E-3 when RCS pressure has been reduced to allow for ECCS termination.

ARP / AOP-M.09 / ARP / AOP-C.03 / AOP-S.01 / AOP-M.08 / E-0 / E-3

Appendix D Scenario Outline Form ES-D-1 Similarities vs. two most recent exams (1603 was 2016-301) (1712 was 2017-301)

Except as noted, events were not included in the last two exams Audit exam is based on 1712 exam so no events are duplicated from that exam.

6 of 8 events were not used on the previous two exams*

Event 1 - ED120B1B007 Not used in last two exams Event 2 - last used in 1603. Similar to 1712 but in that case it was used only to drive FR-H.1 F&B Event 3 - CV11 Not used in last two exams. Similar to 1712 but different instrument and different actions.

Event 4 - AN_OV_59 (Exciter Ground) not used in last two exams. Drives power reduction

Event 5 - FW16B (FRV failure) Not used in last two exams

Event 6 - AN_OV_699 (CCW Rupture) Not used in last two exams

Event 7 - Major - TH05A (SGTR_arv) Not used in last two exams

Event 8 - RC06B (Spray Valve) Not used in last two exams

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:1 Page 1 of 87 Event

Description:

Vital Power Breaker Trips (Containment Rad Monitor)

Time Position Applicant's Actions or Behavior EVENT LIST 1 Vital Power Breaker Trips (Containment Rad Monitor) 2 Charging Pump Trips 3 VCT Level Transmitter Fails High LT-62-129 4 Exciter Ground Alarm/Power Reduction 5 Feed Reg Valve Control Failure 6 Condenser Circ Water Rupture 7SGTR 8 Spray Valve Fails OPEN During Depressurization EVENT 1 - Vital Power Breaker Trips (Containment Rad Monitor)

Direct simulator operator to insert Event 1 (KEY 1)

Indications available:

Annunciators:

1-M1

1C, A-7 120V AC VITAL PWR BD 1-I UV OR BKR TRIP 1-M12

12A, A-4 1-RA-90-106A CNTMT BLDG LWR COMPT AIR MON HIGH RAD

12A, A-5 1-RA-90-106B CNTMT BLDG LWR COMPT AIR MON GAS INSTR MALF

12A, A-6 1-RA-90-106C CNTMT BLDG LWR COMPT AIR MON PART INSTR MALF Significant Resultant Alarms/Indications:

Flow light Dark on RI-90-106A (M-12)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:1 Page 2 of 87 Event

Description:

Vital Power Breaker Trips (Containment Rad Monitor)

Time Position Applicant's Actions or Behavior 1-AR-M1-C A-7 Communications: see below Examiner Note: Throughout this scenario routine communications directing administrative actions, reports, or notifications may be answered by acknowledging the report or direction.

Communications requiring reports back to the examinees will be scripted. Unexpected communications requiring report back will be approved by the Lead examiner prior to contacting the Control Room. .

Examiner Note: Steps, notes, and cautions in this Annunciator response procedure that are not applicable to this failure may have been omitted.

BOP Refers to 1-AR-M1C A-7 Communications: When Requested to investigate, report, Vital Instrument Power Board 1-I Breaker 7 is tripped.

Communications: If requested ,the noun name for the affected breaker is 1-BKRA-250-NC/7-D CNTMNT RAD MONITOR 1-RE-90-106.

BOP BOP Dispatches operator to investigate alarm BOP Examiners Note: If attempted, reclosure of breaker is unsuccessful BOP SRO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:1 Page 3 of 87 Event

Description:

Vital Power Breaker Trips (Containment Rad Monitor)

Time Position Applicant's Actions or Behavior SRO Determines LCO 3.0.6, 3.8.9, and 3.8.10 are not applicable 0-AR-M12-A A-4 Examiner Note: The actions specified for this annunciator are related to an actual high alarm condition. Other annunciators will direct actions for a power failure 0-AR-M12-A A-5 Examiner Note: Steps, notes, and cautions in this Annunciator response procedure that are not applicable to this failure may have been omitted.

BOP BOP BOP SRO NOTE: The following are considered TRACKING LCOs or INFO Only as they are applicable when PURGE is in progress.

SRO Determines ODCM 1.1,2 Nonconformance J, and L are applicable for Function 6a ODCM 1.1.2 Nonconformance K, and L are applicable for Function 7a BOP 0-AR-M12-A A-6 Examiner Note: Steps, notes, and cautions in this Annunciator response procedure that are not

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:1 Page 4 of 87 Event

Description:

Vital Power Breaker Trips (Containment Rad Monitor)

Time Position Applicant's Actions or Behavior applicable to this failure may have been omitted.

BOP BOP BOP SRO Determines SRO LCO 3.4.13 is NOT applicable LCO 3.4.15 Condition B is applicable BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:1 Page 5 of 87 Event

Description:

Vital Power Breaker Trips (Containment Rad Monitor)

Time Position Applicant's Actions or Behavior ODCM 1.1.1 Nonconformance J, L

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:1 Page 6 of 87 Event

Description:

Vital Power Breaker Trips (Containment Rad Monitor)

Time Position Applicant's Actions or Behavior

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:1 Page 7 of 87 Event

Description:

Vital Power Breaker Trips (Containment Rad Monitor)

Time Position Applicant's Actions or Behavior LCO 3.4.15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:2 Page 8 of 87 Event

Description:

Charging Pump Trips Time Position Applicant's Actions or Behavior EVENT 2 - Charging Pump Trips Direct simulator operator to insert Event 2 (KEY 2)

Indications/ Annunciators available:

Annunciators:

1-M-1

1B, E-3, MOTOR TRIPOUT PNL 1-M-1 THRU 1-M-6 1-M-5

5B, C-3, FS-62-1, REAC COOL PMPS SEAL WATER FLOW LO 1-M-6

6C, D-3, FS-62-93A/B CHARGING LINE FLOW ABNORMAL 1-M27

27B-B A-5, LETDOWN HX OUTLET FLOW/TEMP ABNORMAL Indications:

Breaker Disagreement alarm 1-AR-M1-B E-3 Examiner Note: Steps, notes, and cautions in this Annunciator response procedure that are not applicable to this failure may have been omitted.

ATC ATC PLACES HS-62-108A in PTL BOP BOP Dispatches operators to inspect CCP-1B locally and inspect 1A 6.9 KV SDBD

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:2 Page 9 of 87 Event

Description:

Charging Pump Trips Time Position Applicant's Actions or Behavior SRO ENTERS AOP-M.09 1-AR-M6-C D-3 Examiner Note: Steps, notes, and cautions in this Annunciator response procedure that are not applicable to this failure may have been omitted.

ATC ATC PLACES HS-62-108A in PTL, if not already done.

SRO SRO Enters AOP-M.09

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:2 Page 10 of 87 Event

Description:

Charging Pump Trips Time Position Applicant's Actions or Behavior 1-AR-M5-B C-3 ATC SRO Enters AOP-M.09 AOP-M.09 Step 1 thru 14 Communications: When requested as AB AUO, acknowledge direction to perform local inspections for 1B-B CCP and checking out 1A-A CCP for starting. After 3 minutes report, 1B-B CCP motor is not running and feels very hot and 1A-A CCP is ready for start.

Communications: When requested as MCR AUO, acknowledge direction to perform local inspections for 1B-B CCP breaker. After 2 minutes report, The 1B CCP breaker tripped on instantaneous overcurrent.

SRO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:2 Page 11 of 87 Event

Description:

Charging Pump Trips Time Position Applicant's Actions or Behavior ATC ATC ATC ATC ATC ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:2 Page 12 of 87 Event

Description:

Charging Pump Trips Time Position Applicant's Actions or Behavior ATC Communications: When requested as AB AUO, after 3 minutes report, 1A CCP is ready to start.

ATC ATC PLACES 1-HS-62-108A, 1A-A CCP, Momentarily to START ATC ATC ATC EA-62-5 Section 4.1 and 4.3 Examiners Note: Steps not applicable to restoring letdown have been omitted.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:2 Page 13 of 87 Event

Description:

Charging Pump Trips Time Position Applicant's Actions or Behavior ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:2 Page 14 of 87 Event

Description:

Charging Pump Trips Time Position Applicant's Actions or Behavior Examiners Note: In the following step valves are already OPEN ATC Examiners Note: In the following step FCV-62-86 is already OPEN ATC ATC Places 1-HIC-62-78A in MANUAL and manually adjusts output meter approx 50%

ATC ATC ATC Places 1-HIC-62-81A in MANUAL and manually adjusts output meter to 50-60%.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:2 Page 15 of 87 Event

Description:

Charging Pump Trips Time Position Applicant's Actions or Behavior open ATC ATC Establishes at least 55 gpm flow using FCV-62-89 and FCV-62-93 as necessary ATC ATC Selects FCV-62-73 (expected) or FCV-62-74 (alternate) momentarily to OPEN ATC ADJUSTS manual setpoint on 1-HIC-62-81A to establish letdown pressure at ATC approx. 325 psig on 1-PI-62-81 ATC ADJUSTS 1-HIC-62-81A auto setpoint to zero out setpoint indicator ATC PLACES 1-HIC-62-81 AUTO/MANUAL selector to AUTO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:2 Page 16 of 87 Event

Description:

Charging Pump Trips Time Position Applicant's Actions or Behavior ATC ADJUSTS manual setpoint on 1-HIC-62-78A to establish letdown temperature to ATC approx 100 F on 1-TI-62-78A ADJUSTS 1-HIC-62-78A auto setpoint to zero out setpoint indicator ATC ATC DEPRESSES 1-HIC-62-78 AUTO/MANUAL pushbutton to select AUTO ATC ATC ATC ATC ADJUSTS FCV-62-89 and FCV-62-93 as necessary to control Pzr level and RCP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:2 Page 17 of 87 Event

Description:

Charging Pump Trips Time Position Applicant's Actions or Behavior seal flow ATC ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:2 Page 18 of 87 Event

Description:

Charging Pump Trips Time Position Applicant's Actions or Behavior ATC AOP-M.09 step 15 SRO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:2 Page 19 of 87 Event

Description:

Charging Pump Trips Time Position Applicant's Actions or Behavior AOP-M.09 Appendix A SRO SRO Determines LCO 3.5.2 Condition A, and TRM 8.1.1 Condition A are applicable.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:2 Page 20 of 87 Event

Description:

Charging Pump Trips Time Position Applicant's Actions or Behavior LCO 3.5.2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:2 Page 21 of 87 Event

Description:

Charging Pump Trips Time Position Applicant's Actions or Behavior TRM 8.1.1

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:2 Page 22 of 87 Event

Description:

Charging Pump Trips Time Position Applicant's Actions or Behavior AOP-M.09 step 16 thru End SRO SRO Examiners Note: When desired continue to next event

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:3 Page 23 of 87 Event

Description:

VCT Level Transmitter Fails High LT-62-129 Time Position Applicant's Actions or Behavior EVENT 3 - VCT Level Transmitter Fails High LT-62-129 Direct simulator operator to insert Event 3 (KEY 3)

Examiners Note: There is initially no alarm associated with this instrument failure. Prolonged operation will result in auto makeup to the VCT with its associated clicking Examiners Note: It is expected that the crew will refer to the ARP for VCT Level Hi-Lo (AR-M6-C A-3 since it has guidance for VCT level instrument failures.

Indications/ Annunciators available:

Annunciators:

NONE Indications:

1-LI-62-129 VCT LEVEL pegged high 1-FCV-62-118 LETDOWN DIVERT TO HUT repositions to DIVERT 1-AR-M6-C E-1

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:3 Page 24 of 87 Event

Description:

VCT Level Transmitter Fails High LT-62-129 Time Position Applicant's Actions or Behavior 1-AR-M4-B D-5 atc ATC 1-AR-DCS-98 ATC ATC PLACES HS-61-118A in VCT position.

ATC CONTROLS VCT level <63% by repositioning FCV-62-118 as necessary

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:3 Page 25 of 87 Event

Description:

VCT Level Transmitter Fails High LT-62-129 Time Position Applicant's Actions or Behavior ATC ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:3 Page 26 of 87 Event

Description:

VCT Level Transmitter Fails High LT-62-129 Time Position Applicant's Actions or Behavior ATC ATC SELECTS ATC 1-LT-62-129A to MAINT BYP 1-LT-62-129A2 to MAINT BYP ATC ATC ATC ATC may elect to place 1-HIC-62-129A in AUTO by either:

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:3 Page 27 of 87 Event

Description:

VCT Level Transmitter Fails High LT-62-129 Time Position Applicant's Actions or Behavior OR

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:3 Page 28 of 87 Event

Description:

VCT Level Transmitter Fails High LT-62-129 Time Position Applicant's Actions or Behavior ATC 1-AR-M6-C A-3 Examiner Note: Steps, notes, and cautions in this Annunciator response procedure that are not applicable to this failure may have been omitted.

Examiner Note: Crew may refer to this ARP as it contains the guidance for VCT level malfunctions.

However, some level failures do not cause this annunciator to light..

ATC ATC ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:3 Page 29 of 87 Event

Description:

VCT Level Transmitter Fails High LT-62-129 Time Position Applicant's Actions or Behavior ATC PLACES HS-61-118A in VCT position BOP ATC ATC ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 30 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior EVENT 4 - Exciter Ground Alarm/Power Reduction Direct simulator operator to insert Event 4, (KEY 4)

Indications available:

1-A D-3: EXCITER GROUND Indications

Ground relay targets at local AVR cabinet 1-AR-M1-C D-3 Examiner Note: Steps, notes, and cautions in this Annunciator response procedure that are not applicable to this failure may have been omitted.

Examiner Note: Turbine bearing vibration will rise to approximately 13 miles over 10 minutes. At the discretion of the Examiner the level of turbine bearing vibration may be limited to the current value by modifying TU02I and TU02J such that the final value is equal to the existing value.

Communications: When dispatched to check which ground relay has actuated, wait 2 minutes and report, Exciter Field Ground Detection Relay 64F is actuated.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 31 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior BOP Dispatches operator BOP BOP Checks ICS BOP BOP Identifies rising vibrations on #9 and #10 Generator bearings SRO SRO Enters AOP-C.03 BOP 1-AR-M2-A D43 BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 32 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 33 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 34 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior AOP-C.03 Step 1 SRO AOP-C.03 Appendix A

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 35 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior AOP-C.03 Step 2 CREW Examiner Note: Appendix B consists of three copies of this page. Only page 1 is included here.

AOP-C.03 Appendix B

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 36 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior AOP-C.03 Step 3 thru 5i BOP Communications: If requested as WCC SRO, acknowledge direction to make notifications per the step below.

BOP ATC ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 37 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior Examiner Note: Expected boration volume is expected to be approximately 800 gallons (per second bullet) for power reduction from 100% to 20%

ATC Examiner Note: Expected boration flow rate is expected to be 2% per minute. Other values are acceptable if they support reduction to Mode 3 with 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . At the discretion of the Chief Examiner a load reduction rate up to 4 % may be specified.

SRO SRO Directs load reduction rate of 2% (~30 gpm)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 38 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior Examiner Note: IF necessary, provide confirmation that the STA concurs with the boration volume and flowrate.

SRO ATC SRO AOP-C.03 Appendix I ATC ATC Records values determined earlier

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 39 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior ATC ATC a) Momentarily PLACES 1-HS-62-230A, BA TRANSFER PUMP 1A in STOP; b) SELECTS 1-HS-62-230D BA TRANSFER PUMP 1A SPEED SEL to FAST; c) Momentarily PLACES 1-HS-62-230A, BA TRANSFER PUMP 1A in START (May perform the same actions for the B BA TRANSFER pump but this is not required.)

It is acceptable to perform detail b) prior to detail a)

ATC ATC THROTTLES OPEN 1-HS-62-138A until flowrate on 1-HS-62-137A indicates flowrate from step 1 ATC ATC Records values for boration flow rate and time started.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 40 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior ATC ATC SELECTS 1-HS-62-138A to CLOSE until flowrate on 1-HS-62-137A indicates ATC zero and GREEN light is LIT.

ATC a) Momentarily PLACES 1-HS-62-230A, BA TRANSFER PUMP 1A in STOP; b) SELECTS 1-HS-62-230D BA TRANSFER PUMP 1A SPEED SEL to SLOW; c) Momentarily PLACES 1-HS-62-230A, BA TRANSFER PUMP 1A in ATC START (Performs the same actions for the B BA TRANSFER pump if it was shifted to fast earlier)

It is acceptable to perform detail b) prior to detail a)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 41 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior AOP-C.03 Step 5j thru 9 ATC BOP BOP BOP PLACES LOAD RATE thumbwheel to 2% per minute (expected)

Examiner Note: Expected SETTER setpoint is 15 BOP BOP ADJUSTS SETTER to about 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 42 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior BOP BOP BOP DEPRESSES GO pushbutton Examiner Note: BOP may stop and restart turbine load reduction based on plant response. This is done by depressing the HOLD pushbutton to stop the reduction then depressing the GO pushbutton to reinitiate the reduction. They may also reduce the LOAD RATE via the thumbwheel.

BOP BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 43 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior CREW BOP May ADJUST LOAD RATE thumbwheel or stop and start the load reduction via the HOLD and GO pushbuttons.

CREW

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 44 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior BOP BOP Examiner Note: At chief Examiners discretion proceed to Event 6.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 45 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior AOP-C.03 Appendix C (first 3 pages)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 46 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 47 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 48 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior AOP-C.03 Step 10 thru 15e ATC SRO SRO BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:4 Page 49 of 87 Event

Description:

Exciter Ground Alarm/Power Reduction Time Position Applicant's Actions or Behavior BOP Communications: When requested, as Chemistry, acknowledge direction to initiate sampling.

CREW Lead Examiner may cue the next event when desired.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:5 Page 50 of 87 Event

Description:

Feed Reg Valve Control Failure Time Position Applicant's Actions or Behavior EVENT 5 - Feed Reg Valve Control Failure Direct simulator operator to insert Event 5, (KEY 5)

Indications available:

3-C C-4 LS-3-156D STM GEN #2 LEVEL LOW

4-B D-5 ,DCS ABNORMAL Indications

LOOP 2 SG level lowering BOP SRO ENTERS AOP-S.01 1-AR-M4-B D-5

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:5 Page 51 of 87 Event

Description:

Feed Reg Valve Control Failure Time Position Applicant's Actions or Behavior ATC AOP-S.01 Step 1 thru 7 SRO BOP CRITICAL TASK BOP PLACES 1-FIC-3-48 in MAN (CT-FRV)

BOP BOP Uses <<, RAMP, and >> as necessary to restore level.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:5 Page 52 of 87 Event

Description:

Feed Reg Valve Control Failure Time Position Applicant's Actions or Behavior BOP BOP BOP BOP BOP SRO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:6 Page 53 of 87 Event

Description:

Condenser Circ Water Rupture Time Position Applicant's Actions or Behavior EVENT 6 - Condenser Circ Water Rupture Direct simulator operator to insert Event 6, (KEY 6)

Indications available:

15-B D-3: TURB AUX OR REAC BLDG FLOODED Indications

Reports from the field 1-AR-M15-B D-3 Communications: When dispatched to flood alarm panel wait 2 minutes and report, Multiple Turbine Building Flooding alarms.

BOP BOP DISPATCHES operator to to Flood Alarm Panel BOP SRO Enters AOP-M.08

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:6 Page 54 of 87 Event

Description:

Condenser Circ Water Rupture Time Position Applicant's Actions or Behavior AOP-M.08 Step 1 thru 10 SRO Transitions to Section 2.6 Communications: When dispatched to determine the source of flooding wait one minute and report, There is huge amount water coming from Unit 1 CCW piping in the TB on the inlet of the Unit 1 waterbox. I cannot determine where exactly the water is coming from. I cannot get to the area due to the amount of water BOP BOP Dispatches operators to determine source of the flooding BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:6 Page 55 of 87 Event

Description:

Condenser Circ Water Rupture Time Position Applicant's Actions or Behavior BOP PERFORMS Appendix C to isolate Unit 1 CCW See page 57 Examiners Note: Actions for Rx Trip E-0 go to page 60 ATC ATC Trips Rx SRO Examiners Note: RCW is aligned to Unit 2 and is not lost due to this event SRO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:6 Page 56 of 87 Event

Description:

Condenser Circ Water Rupture Time Position Applicant's Actions or Behavior Examiners Note: Leak is on Unit 1 waterbox inlet side. Step 2c deals with a UNIT 2 leak.

BOP BOP BOP BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:6 Page 57 of 87 Event

Description:

Condenser Circ Water Rupture Time Position Applicant's Actions or Behavior BOP AOP-M.08 Appendix C BOP PLACES 1-HS-27-9F momentarily to stop BOP PLACES 1-HS-27-19F momentarily to stop PLACES 1-HS-27-29F momentarily to stop

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:6 Page 58 of 87 Event

Description:

Condenser Circ Water Rupture Time Position Applicant's Actions or Behavior BOP BOP CLOSES all the above valves by momentarily placing the handswitch in CLOSE BOP BOP PLACES each of the above handswitches in the PULL TO CLOSE VLV position

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:6 Page 59 of 87 Event

Description:

Condenser Circ Water Rupture Time Position Applicant's Actions or Behavior Communications: When notified to DOG door A57 wait 2 minutes and report, Door A57 is CLOSED and DOGGED.

BOP BOP Notifies operator to CLOSE and DOG door A57 BOP PLACES 1-HS-1-103A in OFF BOP PLACES 1-HS-1-103B in OFF Examiners Note: Simulator is modeled with UNIT 2 always providing RCW Communications: IF contacted as UNIT 2 to report that, UNIT 2 will perform Appendix N.

BOP BOP PLACES 1-HS-2-171A in PTL BOP PLACES 1-HS-2-176A in PTL PLACES 1-HS-2-181A in PTL

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:6 Page 60 of 87 Event

Description:

Condenser Circ Water Rupture Time Position Applicant's Actions or Behavior BOP BOP PLACES 1-HS-6-330A in OPEN ATC BOP PLACES 1-HS-47-180A to CLOSE BOP BOP PLACES 1-HS-47-181A to CLOSE Communications: When notified to close 1-12-713 wait 5 minutes and report, Valve 1-12-713 is CLOSED. (no action required)

ATC BOP NOTIFIES operator to CLOSE valve 1-12-713 E-0 Step 1 thru 4 Examiner Note: Following IOA performance, prior to Steps 1-4 immediate action verification, ATC/BOP surveys MCBs for any expected automatic system response that failed to occur.

Upon discovery, they may take manual action(s) to align plant systems as expected for the event in progress. (Ref. EPM-4, Prudent Operator Actions).

CREW Performs the first four steps of E-0 unprompted.

SRO Directs performance of E-0 REACTOR TRIP OR SAFETY INJECTION.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:6 Page 61 of 87 Event

Description:

Condenser Circ Water Rupture Time Position Applicant's Actions or Behavior ATC ATC ATC ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:6 Page 62 of 87 Event

Description:

Condenser Circ Water Rupture Time Position Applicant's Actions or Behavior Examiners Note: Event 8 is initiated at the discretion of the Examiner. Recommended point is transition to ES-0.1 E-0 Step 5 thru 7b ATC ATC Examiners Note: ES-0.5 see EVENT 8 page 76 BOP BOP Performs ES-0.5

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:6 Page 63 of 87 Event

Description:

Condenser Circ Water Rupture Time Position Applicant's Actions or Behavior E-0 Steps 7c thru 11 ATC ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:6 Page 64 of 87 Event

Description:

Condenser Circ Water Rupture Time Position Applicant's Actions or Behavior ATC SRO TRANSITIONS to E-3, Steam Generator Tube Rupture

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:7 Page 65 of 87 Event

Description:

SGTR Time Position Applicant's Actions or Behavior EVENT 7 - SGTR Direct simulator operator to insert Event 7, (KEY 7)

Indications available:

Annunciator Indications

Rising level in #1 SG

Lowering RCS pressure

Lowering Pzr level

Identifies lowering RCS pressure, Pzr level and/or rising SG level and ATC/

Initiates SI and SRO

Re-enters E-0 (page 60)

E-3 Step 1 thru 5b ATC ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:7 Page 66 of 87 Event

Description:

SGTR Time Position Applicant's Actions or Behavior CREW CREW Determines #1 S/G is RUPTURED ATC BOP ADJUSTS PIC-1-6A setpoint to 87%

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:7 Page 67 of 87 Event

Description:

SGTR Time Position Applicant's Actions or Behavior SRO SRO Determines #1 S/G is ruptured BOP CRITICAL TASK(18) BOP Places FCV-1-15 in CLOSE, if not already done as a prudent action.

ATC BOP CRITICAL TASK(18) BOP Places 1-HS-1-4A in CLOSE.

BOP BOP CRITICAL Places HS-3-164A AFW Pump 1A-A to LCV to SG 1 to ACC RESET and RAMP TASK(18) BOP CLOSE.

BOP CRITICAL TASK(18) BOP Places HS-3-174A in CLOSE.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:7 Page 68 of 87 Event

Description:

SGTR Time Position Applicant's Actions or Behavior BOP E-3 Step 6 thru 19e BOP BOP BOP BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:7 Page 69 of 87 Event

Description:

SGTR Time Position Applicant's Actions or Behavior CREW SRO Determines target temperature BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:7 Page 70 of 87 Event

Description:

SGTR Time Position Applicant's Actions or Behavior BOP Places HS-63-135A and 135B momentarily in BLOCK position BOP BOP For each of the following ARV controllers PLACES 1-PIC-1-13A in MAN and OPENS ARV PLACES 1-PIC-1-24A in MAN and OPENS ARV BOP PLACES 1-PIC-1-31A in MAN and OPENS ARV NOTE: This can also be accomplished in AUTO by lowering the setpoint.

BOP OPENS TDAFW LCVs (except for HS-3-174A) and raises flow through MDAFW BOP LCVs (except for HS-3-176A) to support cooldown

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:7 Page 71 of 87 Event

Description:

SGTR Time Position Applicant's Actions or Behavior Examiners Note: The critical task associated with RCS temperature is met cooling down to target temperature and not overcooling or heating back up (see page 74)

CT-19 Manually establish/maintain an RCS temperature so that transition from E-3 does not occur because the RCS temperature is in any of the following conditions:

Too high to maintain > 60 degrees CET subcooling.

RED path on PTS Status Tree OR

ORANGE path on Subcriticality Status Tree Examiners Note: In the following step after closing steam dumps, examinee may adjust automatic setpoint to match existing steam pressure (in non ruptured SGs) and place controller back in AUTO to assist in maintaining temperature.

BOP For each of the following ARV controllers PLACES 1-PIC-1-13A in MAN and CLOSES ARV PLACES 1-PIC-1-24A in MAN and CLOSES ARV BOP PLACES 1-PIC-1-31A in MAN and CLOSES ARV NOTE: This can also be accomplished in AUTO by raising the setpoint.

BOP Throttles TD and MD AFW LCVs to reduce total AFW flow <600 gpm. If all SGs are BOP less than 10% then AFW flow is maintained between 440 and 600 gpm.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:7 Page 72 of 87 Event

Description:

SGTR Time Position Applicant's Actions or Behavior BOP BOP Throttles ARVs (in AUTO or MANUAL) to maintain CETs below target temp BOP ATC ATC Momentarily DEPRESSES 1-HS-63-134A SIS RESET TRAIN 1A and 1-HS ATC 134B SIS RESET TRAIN 1B pushbuttons BOP ATC DEPRESSES 1-HS-30-63D PHASE A ISOL RESET - TR A and 1-HS-30-63E PHASE A ISOL RESET - TR B pushbuttons ATC May DEPRESS 1-HS-30-64D PHASE B ISOL RESET- TR A and 1-HS-30-64E PHASE B ISOL RESET- TR B but not required based on alarm status

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:7 Page 73 of 87 Event

Description:

SGTR Time Position Applicant's Actions or Behavior BOP ATC PLACES 1-HS-74-10A RHR PUMP 1A and 1-HS-74-20A RHR PUMP 1B ATC momentarily in the STOP position.and return to A-AUTO position.

ATC BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:7 Page 74 of 87 Event

Description:

SGTR Time Position Applicant's Actions or Behavior For each of the following ARV controllers PLACES 1-PIC-1-13A in MAN and CLOSES ARV PLACES 1-PIC-1-24A in MAN and CLOSES ARV BOP PLACES 1-PIC-1-31A in MAN and CLOSES ARV NOTE: This can also be accomplished in AUTO by raising the setpoint.

BOP Throttles TD and MD AFW LCVs to reduce total AFW flow <600 gpm. If all SGs are BOP less than 10% then AFW flow is maintained between 440 and 600 gpm.

BOP CRITICAL Throttles ARVs (in AUTO or MANUAL) to maintain CETs below target temp (See TASK(19) BOP Critical Task details on page 71)

BOP ATC ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:7 Page 75 of 87 Event

Description:

SGTR Time Position Applicant's Actions or Behavior OPENS one or both Normal Pzr Spray Valves by momentarily DEPRESSING CRITICAL TASK(20) ATC MANUAL pushbutton and concurrently DEPRESSING RAMP and >> for 1-PIC-68-340D and 1-PIC-68-334B.

ATC ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:8 Page 76 of 87 Event

Description:

Spray Valve Fails OPEN During Depressurization Time Position Applicant's Actions or Behavior EVENT 8 - Spray Valve Fails OPEN During Depressurization Event 8 should be inserted when normal spray valves are opened to depressurize the RCS following cooldown to target temperature by using KEY 8 E-3 Step 19f thru 26e ATC PLACES 1-HS-68-8A momentarily in STOP ATC PLACES 1-HS-68-31A momentarily in STOP May places switches in PTL ATC ATC At the discretion of the Chief Examiner the scenario may be terminated when SI termination criteria have been met.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:8 Page 77 of 87 Event

Description:

Spray Valve Fails OPEN During Depressurization Time Position Applicant's Actions or Behavior ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:8 Page 78 of 87 Event

Description:

Spray Valve Fails OPEN During Depressurization Time Position Applicant's Actions or Behavior ATC ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:8 Page 79 of 87 Event

Description:

Spray Valve Fails OPEN During Depressurization Time Position Applicant's Actions or Behavior ES-0.5 Steps 1 thru 17 (R13)

BOP BOP Communications: When directed to perform Attachment 7 Acknowledge direction. (No Further Action Required)

BOP BOP BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:8 Page 80 of 87 Event

Description:

Spray Valve Fails OPEN During Depressurization Time Position Applicant's Actions or Behavior BOP BOP BOP Makes plant announcement BOP BOP BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:8 Page 81 of 87 Event

Description:

Spray Valve Fails OPEN During Depressurization Time Position Applicant's Actions or Behavior BOP BOP BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:8 Page 82 of 87 Event

Description:

Spray Valve Fails OPEN During Depressurization Time Position Applicant's Actions or Behavior BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:8 Page 83 of 87 Event

Description:

Spray Valve Fails OPEN During Depressurization Time Position Applicant's Actions or Behavior BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:8 Page 84 of 87 Event

Description:

Spray Valve Fails OPEN During Depressurization Time Position Applicant's Actions or Behavior BOP BOP BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:8 Page 85 of 87 Event

Description:

Spray Valve Fails OPEN During Depressurization Time Position Applicant's Actions or Behavior BOP ES-0.5 Appendix A Examiner Note: Appendix A and B step 2 is Unit 2 only

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:8 Page 86 of 87 Event

Description:

Spray Valve Fails OPEN During Depressurization Time Position Applicant's Actions or Behavior ES-0.5 Appendix B ES-0.5 Step 18 thru end BOP Communications: When requested as Unit 2 RO, acknowledge direction to perform EA-0-1 BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 4 Event No.:8 Page 87 of 87 Event

Description:

Spray Valve Fails OPEN During Depressurization Time Position Applicant's Actions or Behavior Communications: IF requested as Unit 2 RO acknowledge direction to perform EA-65-1 and EA-0-1 BOP BOP BOP Communications: If requested as available AUO, acknowledge direction to perform appendix E BOP

Today Mode 1 100% 1206 MWe Train Week: B RCS Boron: 985 ppm BAT A RCS Leakage:

EOOS: Green Last Shift: Dilution: Rx Plan Total: Rx plan Identified: 0.01 GPM Grid Status: Qualified This Shift: Boration: Rx plan Total: Rx plan Unidentified: 0.04 GPM Site Aggregate Risk: Low Shutdown LCO Conditions Equipment INOP Next Action Due LCO 3.6.6 Condition A CSP-1B 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months Other LCO Actions Equipment INOP Next Action Due Info Only Tech Specs Equipment INOP Abnormal Equipment Lineup / Conditions (including significant Radiological changes)

Severe Thunderstorm warning is in effect for Hamilton County FT-1-3A Failed. In MAINT BYPASS Shift Priorities (Surveillances/Testing and Major Activities in Progress or Scheduled)

Maintain current power level.

Restore CSP-1B when work is complete For each MCR deficiency, a numbered square will be applied to the MCR Board near the associated indication/alarm. (US maintains magnets)

The CR/WO number and description of the issue will be listed below Main Control Room (7690)

Auxiliary Building (7671)

Turbine Building (7771)

TB Sump: LVWT Pond RCW: Unit 2 Aux Steam: Unit 1 Outside (7666) (423-710-4777)

Miscellaneous

2003 NRC SCN 4 Booth Instructions BOOTH OPERATOR INSTRUCTIONS Sim. Setup Reset IC-16 100% 985ppmb BOL Perform switch check.

Verify control rod step counters reset.

Place simulator in RUN.

Place Mode 1 placard on panels.

Place B Train Week sign on the simulator.

Place FT-1-3A in MAINT BYP Place RED TAG on CSP-1B Hand Switch and place in PTL Load SCN file: - ILT2003 NRC SCN 4 Acknowledge any alarms, allow the plant to stabilize, and freeze the simulator.

Perform the SIMULATOR OPERATOR CHECKLIST Place simulator in RUN before crew enters the simulator.

Start Data Capture

1. REMOVE ORANGE DOTS WHEN SCENARIO COMPLETE Page 1 of 4

2003 NRC SCN 4 Booth Instructions EVENT IC/MF/RF/OR # DESCRIPTION/EXPECTED ACTIONS/BOOTH FEEDBACK This is manually FT-1-3A in Maintenance Bypass MAIN STEAM FLOW TRANSMITTER inserted during IMF RX10A f:1 FAILS LOW FT-1-3A setup This is manually IOR CSR04 f:0 ;CONTAINMENT SPRAY PUMP B POWER inserted during setup Throughout this scenario routine communications directing administrative actions, reports, or notifications may be answered by acknowledging the report or direction. Communications requiring reports back to the examinees will be scripted. Unexpected communications requiring report back will be approved by the Lead examiner prior to contacting the Control Room. .

When directed by the Lead

---120VAC BD 1-I BREAKER 7, Examiner, use IMF ED120B1B007 f: 0 k:1 CONTAINMENT RAD MAN 1-RE-9O-106 KEY 1 to insert malfunction Communication When Requested to investigate, Vital Instrument Power Board 1-I for Event 1 report, Breaker 7 is tripped.

The noun name for the affected breaker is If requested 1-BKRA-250-NC/7-D CNTMNT RAD MONITOR 1-RE-90-106.

When directed by the Lead Examiner, use IMF CV01B f:1 k:2 ;---CHARGING PUMP B TRIP KEY 2 to insert malfunction When requested as MCR AUO, Communication acknowledge direction to perform local The 1B CCP breaker tripped on for Event 2 inspections for 1B-B CCP breaker. instantaneous overcurrent.

After 2 minutes report, When requested as AB AUO, acknowledge direction to perform local 1B-B CCP motor is not running and Communication inspections for 1B-B CCP and feels very hot and 1A-A CCP is ready for for Event 2 checking out 1A-A CCP for starting. start.

After 3 minutes report When directed by the Lead

---VCT LEVEL TRANSMITTER FAILS Examiner, use IMF CV11 f: 1 k:3 HIGH; 129-A KEY 3 to insert malfunction.

Communication for Event 3 Page 2 of 4

2003 NRC SCN 4 Booth Instructions EVENT IC/MF/RF/OR # DESCRIPTION/EXPECTED ACTIONS/BOOTH FEEDBACK

--- EXCITER GROUND IMF AN_OV_59 f: 2 k:4

---MAIN TURBINE HIGH VIBES GEN. BRG EVENT 4 IMF TU02I f: 34 r:600 k:4

9 and #10 ramps up to 11 mils over 10 IMF TU02J f:34 r:600 k:4 minutes When dispatched to check which Exciter Field Ground Detection Relay ground relay has actuated, wait 2 64F is actuated.

minutes and report, When directed by the Lead IMF FW16B f:30 r:120 k:5 ;---FAIL FW REG VALVE FCV-3-48 TO Examiner, use 40%

KEY 5 to insert malfunction.

---Malfunction clears when taken to

{zdi1fic0030048h} DMF FW16B MANUAL acknowledge direction to make notifications Communication to: Balancing Authority, Chemistry, If requested as WCC SRO, Radiation Protection Plant Management for Event 5 When directed by the Lead Examiner, use IMF AN_OV_699 f:2 k:6 ;--- TURB AUX OR REAC BLDG FLOODED KEY 6 to insert malfunction Communication When dispatched to flood alarm panel Multiple Turbine Building Flooding for Event 6 wait 2 minutes and report, alarms.

There is huge amount water coming from Unit 1 CCW piping in the TB on the When dispatched to determine the inlet of the Unit 1 waterbox. I cannot source of flooding wait one minute and determine where exactly the water is report, coming from. I cannot get to the area due to the amount of water When notified to DOG door A57 wait 2 Door A57 is CLOSED and DOGGED.

minutes and report, IF contacted as UNIT 2 to report that, UNIT 2 will perform Appendix N.

When notified to close 1-12-713 wait 5 Valve 1-12-713 is CLOSED. (no action minutes and report, required)

Page 3 of 4

2003 NRC SCN 4 Booth Instructions EVENT IC/MF/RF/OR # DESCRIPTION/EXPECTED ACTIONS/BOOTH FEEDBACK When directed by the Lead Examiner, use IMF TH05A f:9.15 r:300 k:7 ;---SGTR ramps in over five minutes KEY 7 to insert malfunction IMF SI08A f:1 k:7 ;---A SI PUMP 1A has a shaft shear Communication When directed to perform Attachment (No Further Action Required for Event 7 7 Acknowledge direction.)

EVENT 8 ;---PRZ SPRAY VALVE PCV-68-340D Inserted from IMF RC06B f:100 k:8 FAILS TO 100% 30 seconds after spray beginning valve Page 4 of 4

Appendix D Scenario Outline Form ES-D-1 Facility: Sequoyah Scenario No.: 5 Op Test No.: 2020-301 Examiners: Operators: SRO ATC BOP Initial Conditions: 100% EOL Turnover: Unit 1 is in MODE 1 100%, EOL FT-1-3A is in Maintenance Bypass Containment Spray Pump 1B OOS Severe Thunderstorm watch is in effect for Hamilton County Critical Tasks CT-24 Manually energize at least one 6.9 kv Shutdown Board before placing safeguards equipment hand switches in the pull to lock position during ECA-0.0 (Step 10) and within 15 minutes of LOOP (REP upgrade)

CT-PORV Manually close PORV or block valve for any open PZR PORV before Rx trip occurs.

Event Malf. Event Event Description No. No. Type MFW Seal water low DP alarm occurs. BOP starts B Injection Water 1 AN_OV_289 (C) BOP pump per ARP (C) ATC PORV fails open mechanically. ATC closes block valve per AOP-2 RC05 TS-SRO I.04. SRO addresses LCO (I) BOP Turbine Impulse Pressure transmitter PT-1-73 fails low. BOP places 3 RX11B TS-SRO channel in MAINT BYPASS. SRO addresses LCO Letdown press transmitter fails low. ATC places Letdown pressure 4 CV25A (I) ATC controller in Manual and controls per ARP A grid disturbance occurs resulting in excessive VAR loading on the 5 ED05 (C) BOP main generator. BOP adjusts the main generator voltage regulator to bring reactive load within limits per AOP-P.07.

3 Heater Drain Tank level control fails resulting in a Main Turbine HD01A (C) ATC 6 Runback. ATC manually inserts control rods per AOP-S.01 due to a HD01B (N) BOP failure of the Rod Control system ED01 Loss of Offsite Power occurs. Normal feeder bkr to A SDBD fails to 7 (M) ALL LOOP open. A EDG breaker is prevented from closing. Crew enters E-0.

EG02B B EDG trips after 1 minute. Crew transitions to ECA-0.0 and BOP 8 (C) BOP EG03A recovers the A EDG .

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

Appendix D Scenario Outline Form ES-D-1 2020-301 Scenario 5 Summary Event 1 - MFW Seal water low DP alarm occurs. BOP starts B Injection Water pump per ARP.

Verifiable actions: (BOP) starts B Injection Water pump.

Event 2 - PORV fails open mechanically. ATC closes block valve per AOP-I.04. SRO addresses LCO Verifiable actions: (ATC) close PORV block valve prior to Rx Trip. (CT-PORV)

Event 3- Turbine Impulse Pressure transmitter PT-1-73 fails low. BOP places channel in MAINT BYPASS per AOP-I.08, Turbine Impulse Pressure Instrument Malfunction. SRO addresses LCO Verifiable actions: (BOP) places channel in MAINT BYPASS.

Event 4 - Letdown press transmitter fails low. ATC places Letdown pressure controller in Manual and controls per ARP Verifiable actions: (ATC) places Letdown pressure controller in Manual Event 5- A grid disturbance occurs resulting in excessive VAR loading on the main generator. BOP adjusts the main generator voltage regulator to bring reactive load within limits per AOP-P.07, Degraded Grid or Abnormal Voltage Conditions.

Verifiable actions: (BOP) adjusts Automatic Voltage Regulator.

Event 6 - #3 Heater Drain Tank level control fails resulting in a Main Turbine Runback. ATC manually inserts control rods due to a failure of the Rod Control system per AOP-S.01, Main Feedwater Malfunctions Verifiable actions: (ATC) manually inserts control rods Event 7 - Major - Loss of Offsite Power occurs. Normal feeder breaker to A SDBD fails to open. A EDG breaker is prevented from closing. Crew enters E-0, Reactor Trip or Safety Injection Verifiable actions: BOP emergency stops A EDG due to loss of cooling with bus de-energized/

Event 8 - B EDG trips after 1 minute. Crew transitions to ECA-0.0, Loss of All AC Power and BOP recovers the A EDG. (CT-24)

Verifiable actions: (BOP) opens normal feeder breaker allowing EDG to re-energize A SDBD ARP / AOP-I.04 / AOP-I.08 / ARP / AOP-P.07 / E-0 / ECA-0.0

Appendix D Scenario Outline Form ES-D-1 Similarities vs. two most recent exams (1603 was 2016-301) (1712 was 2017-301)

Except as noted, events were not included in the last two exams Audit exam is based on 1712 exam so no events are duplicated from that exam.

3 of 8 events were not used on the previous two exams*

Event 1 - AN_OV_289 Not used in last two exams Event 2 - last used in 1603 Event 3 - last used in 1603

Event 4 - CV25A Not used in last two exams Event 5 - last used in 1603

Event 6 - HD03A HD03B RD09 Not used in last two exams Event 7- last used in 1603 Event 8 - Major - ED01 (LOOP) - last used in 1603. Similar to 1712 but different path to EDG recovery

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:1 Page 1 of 36 Event

Description:

MFW Seal Water Low DP Time Position Applicant's Actions or Behavior EVENT LIST 1 MFW Seal Water Low DP 2 PORV Fails OPEN 3 Turbine Impulse Pressure Transmitter Fails Low 4 Letdown Pressure Transmitter Fails Low 5 Grid Disturbance 6 Heater Drain Tank Level Control Failure with No Auto Rod Control 7 LOOP A SDBD Remains Deenergized 8 B EDG Trips / SBO EVENT 1 MFW Seal Water Low DP Direct simulator operator to insert Event 1 (KEY 1)

Indications/Alarms Annunciators:

1-M-3

M3-B E-1 PDIS-54-8C LOW DIFF PRESS MFP 1B SEAL WATER Significant Resultant Alarms/Indications:

1-AR-M3-C E-1 Communications: see below Examiner Note: Throughout this scenario routine communications directing administrative actions, reports, or notifications may be answered by acknowledging the report or direction.

Communications requiring reports back to the examinees will be scripted. Unexpected communications requiring report back will be approved by the Lead examiner prior to contacting

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:1 Page 2 of 36 Event

Description:

MFW Seal Water Low DP Time Position Applicant's Actions or Behavior the Control Room. .

Examiners Note: Only steps, notes, and cautions associated with this event are included here ATC Refers to 1-AR-M3-C E-1 ATC BOP STARTS INJECTION WATER PUMP 1B (HS-54-9B1)

BOP Communications: When dispatched as AUO to investigate this issue report, There is no external leakage, pressure on 1-PIS-54-10C is 385 psig, DP is 31 psid on 1-PDIS-54-8A and 8B.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:2 Page 3 of 36 Event

Description:

PORV Fails OPEN Time Position Applicant's Actions or Behavior EVENT 2 - PORV Fails OPEN Direct simulator operator to insert Event 2 (KEY 2)

Indications/Alarms Annunciators:

1-M-5

M5-C B-6 XS-68-363 PRESSURIZER RELIEF VALVE OPEN

M5-A D TS-68-328 PRESSURIZER SAFETY VALVE LINES TEMP HIGH Indications:

Lowering RCS pressure

PORV Acoustic Monitor upscale 1-AR-M5-C B-6 Examiner Note: Throughout this scenario routine communications directing administrative actions, reports, or notifications may be answered by acknowledging the report or direction.

Communications requiring reports back to the examinees will be scripted. Unexpected communications requiring report back will be approved by the Lead examiner prior to contacting the Control Room. .

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:2 Page 4 of 36 Event

Description:

PORV Fails OPEN Time Position Applicant's Actions or Behavior Examiner Note: Steps, notes, and cautions in this Annunciator response procedure that are not applicable to this failure may have been omitted.

Examiners Note: Closing a spuriously open PORV or PORV Block valve is an Immediate Action in AOP-I.04 and may be performed from memory prior to entering the procedure Examiners Note: This event is a mechanically failed open PORV and the Block Valve must be closed to stop pressure reduction.

ATC ATC SRO ENTERS AOP-I.04 BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:2 Page 5 of 36 Event

Description:

PORV Fails OPEN Time Position Applicant's Actions or Behavior AOP-I.04 Step 1 thru 12 SRO ATC SELECTS 1-HS-68-333A (BLOCK VALVE FOR PORV 334) momentarily to CRITICAL TASK ATC CLOSE. The BLOCK VALVE closes. The PORV remains OPEN (CT-PORV)

ATC ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:2 Page 6 of 36 Event

Description:

PORV Fails OPEN Time Position Applicant's Actions or Behavior ATC ATC Verifies that Pzr BU htrs have energized, as necessary ATC ATC SRO SRO Determines SRO LCO 3.4.1 Condition A is applicable if RCS pressure dropped below 2220 psia LCO 3.4.11 Condition B.1, B.2, B.3 are applicable.

Communications: When contacted as WCC SRO, acknowledge direction to de-energize PORV block valve 68-333. Wait 20 minutes, use KEY 21 to remove power from 68-333, and report, Power has been removed from FCV 68-333.

SRO BOP Directs PORV Block Valve be de-energized per 0-SO-68-3

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:2 Page 7 of 36 Event

Description:

PORV Fails OPEN Time Position Applicant's Actions or Behavior BOP LCO 3.4.11

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:2 Page 8 of 36 Event

Description:

PORV Fails OPEN Time Position Applicant's Actions or Behavior

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:2 Page 9 of 36 Event

Description:

PORV Fails OPEN Time Position Applicant's Actions or Behavior LCO 3.4.1

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:3 Page 10 of 36 Event

Description:

Turbine Impulse Pressure Transmitter Fails Low Time Position Applicant's Actions or Behavior EVENT 3 - Turbine Impulse Pressure Transmitter Fails Low Direct simulator operator to insert Event 3 (KEY 3)

Alarms/Indications Annunciator:

1-M-4

4-B D-5: DCS ABNORMAL

4-A E-3, C-5 LOW TURB IMPULSE PRESS ROD WITHDRAWAL BLOCKED Indications 1-M-4

HP TURBINE IMP PRESS TR A ESF (1-PI-1-73) indicating zero

Various DCS system alarms 1-AR-M4-B D-5 Examiners Note: Only steps, notes, and cautions associated with this event are included here Communications: If directed as AUO to inspect transmitter for PT-1-73, report, Nothing abnormal.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:3 Page 11 of 36 Event

Description:

Turbine Impulse Pressure Transmitter Fails Low Time Position Applicant's Actions or Behavior AOP-I.08 Step 1 thru 9 ATC ATC SELECTS affected channel on on DCS screen and CLICKS on MAINT BYP SIGNAL A button:

ATC PM-1-73A (RC)

PM-1-73A2 (SD)

PM-1-73A3 (C7)

PT-1-73 (FW).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:3 Page 12 of 36 Event

Description:

Turbine Impulse Pressure Transmitter Fails Low Time Position Applicant's Actions or Behavior ATC ATC ATC ATC ATC SRO DETERMINES LCO 3.3.1 Conditions A and P are applicable for function 16.f

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:3 Page 13 of 36 Event

Description:

Turbine Impulse Pressure Transmitter Fails Low Time Position Applicant's Actions or Behavior BOP BOP SRO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:3 Page 14 of 36 Event

Description:

Turbine Impulse Pressure Transmitter Fails Low Time Position Applicant's Actions or Behavior LCO 3.3.1

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:4 Page 15 of 36 Event

Description:

Letdown Pressure Transmitter Fails Low Time Position Applicant's Actions or Behavior EVENT 4 - Letdown Pressure Transmitter Fails Low Direct simulator operator to insert Event 4, (KEY 4)

Indications available:

M6-C C-4: 1 TS-62-75 LOW PRESSURE LETDOWN RELIEF TEMP HIGH Indications

LETDOWN HX OUTLET PRESSURE (1-PI-62-81): drops to zero

LETDOWN PRESSURE PRESSURE CONTROL (1HIC-62-81):output meter shows 100%

1-AR-M6-C C-4 Examiners Note: Only steps, notes, and cautions associated with this event are included here Examiners Note: This malfunction may result in a PRT high pressure alarm which may be corrected per 0-SO-68-5 Section 8.6 by opening valve 68-301 to vent the PRT to the waste gas header ATC SELECTS 1-HIC-62-81 to MANUAL and lowers output to restore letdown flow as ATC indicated on overhead computer point ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:5 Page 16 of 36 Event

Description:

Grid Disturbance Time Position Applicant's Actions or Behavior EVENT 5 - Grid Disturbance Direct simulator operator to insert Event 5, (KEY 5)

Indications available:

Computer alarm at 240 MVAR

M2-A E-2: PNL-1-L-39 GEN AUX ANN OPERATED OR BUS PWR FAILED (eventually due to high hydrogen pressure Indications

MEGAVARS (1-EI-57-8) rising 1-PI-OPS-000-020.1 Communications: If contacted as SELD, report, There has been a grid disturbance. Maintain SWYD voltage per the voltage schedule and attempt to maintain 400 MVARs OUT.

Examiners Note: The ICS computer point for Switchyard Voltage is not available on the simulator BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:5 Page 17 of 36 Event

Description:

Grid Disturbance Time Position Applicant's Actions or Behavior Examiners Note: Contacting WBN control room may be deferred until after voltage adjustment BOP Contacts WBN about planned voltage adjustment PLACES EXCITER VOLTAGE ADJUSTER (1-HS-77-22 in lower until indicated BOP MVARS are <600 MVARS on 1-EI-57-8.

May reduce MVARs further while maintaining above 519KV

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:5 Page 18 of 36 Event

Description:

Grid Disturbance Time Position Applicant's Actions or Behavior AOP-P.07 Appendix C

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:6 Page 19 of 36 Event

Description:

Heater Drain Tank Level Control Failure with No Auto Rod Control Time Position Applicant's Actions or Behavior EVENT 6 - Heater Drain Tank Level Control Failure with No Auto Rod Control Direct simulator operator to insert Event 6, (KEY 6)

Indications available:

2-C B-7: NO 3 HTR DR TK BYPASS to COND

2-A B-1: TURBINE RUNBACK BOP Indications

HTR DR SYSTEM FLOW (1-FR-6-107) lower trend to below 5500 gpm 1-AR-M2-C B-7 Examiners Note: Only steps, notes, and cautions associated with this event are included here Examiners Note: #3 Heater Drain Tank flow will slowly lower, eventually dropping below 5500 gpm.

After 10 seconds this will result in a Turbine Runback. During Runback Control Rods fail to move in AUTO. Malfunction clears at 1000MWe and valves start to control level again CREW

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:6 Page 20 of 36 Event

Description:

Heater Drain Tank Level Control Failure with No Auto Rod Control Time Position Applicant's Actions or Behavior BOP BOP Communications: IF directed to investigate, wait until Runback has completed and report, LCV 105A and 105B appear to be operating normally.

BOP BOP SRO Transitions to AOP-S.04 AOP-S.04 Step 1 thru Section 2.6 Step 10 SRO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:6 Page 21 of 36 Event

Description:

Heater Drain Tank Level Control Failure with No Auto Rod Control Time Position Applicant's Actions or Behavior BOP BOP BOP ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:6 Page 22 of 36 Event

Description:

Heater Drain Tank Level Control Failure with No Auto Rod Control Time Position Applicant's Actions or Behavior PLACES ROD CONTROL MODE SELECTOR switch (1-HS-85-5110) in MAN ATC PLACES ROD CONTROL switch (1-HS-85-5111) to IN and inserts rods until Tave-Tref is within 3 degrees F (various indicators)

BOP ATC If control rods are inserted below the LOW-LOW insertion limit then SRO enters LCO SRO 3.1.6 Condition B

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:6 Page 23 of 36 Event

Description:

Heater Drain Tank Level Control Failure with No Auto Rod Control Time Position Applicant's Actions or Behavior BOP ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:6 Page 24 of 36 Event

Description:

Heater Drain Tank Level Control Failure with No Auto Rod Control Time Position Applicant's Actions or Behavior AOP-S.04 Appendix B BOP BOP DEPRESSES TURB MANUAL pushbutton to allow REFERENCE to stabilize with BOP SETTER BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:6 Page 25 of 36 Event

Description:

Heater Drain Tank Level Control Failure with No Auto Rod Control Time Position Applicant's Actions or Behavior BOP BOP DEPRESSES OPER AUTO pushbutton BOP BOP REDUCES REFERENCE approximately 1% usign REFERENCE CONTROL UP BOP and DOWN pushbuttons. THEN DEPRESSES GO to allow SETTER to run to REFERENCE value.This may be repeated as necessary.

AOP-S.04 Section 2.6 Step 11 thru 14 BOP BOP BOP SELECTS HS-1-103A to OFF BOP SELECTS HS-1-103 to OFF BOP Momentarily PLACES HS-1-103D in RESET

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:6 Page 26 of 36 Event

Description:

Heater Drain Tank Level Control Failure with No Auto Rod Control Time Position Applicant's Actions or Behavior SELECTS HS-1-103A to On BOP SELECTS HS-1-103 to ON BOP BOP BOP NOTIFIES Chemistry ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:6 Page 27 of 36 Event

Description:

Heater Drain Tank Level Control Failure with No Auto Rod Control Time Position Applicant's Actions or Behavior SRO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:7 Page 28 of 36 Event

Description:

LOOP A SDBD Remains Deenergized Time Position Applicant's Actions or Behavior EVENT 7- LOOP A SDBD Remains Deenergized Direct simulator operator to insert Event 7, (KEY 7)

E-0 Step 1 thru 4 Examiners Note: Log the time of the LOOP ___________

Examiners Note: During the next 2 events a LOOP occurs, 1A 6.9 KV SDBD does not reenergize from the 1A EDG because the normal feeder breaker fails to open. After 1 minute the 1B 6.9 KV SDBD is lost resulting in SBO. The crew transitions to ECA-0.0 and recovers the 1A SDBD Examiner Note: Following IOA performance, prior to Steps 1-4 immediate action verification, ATC/BOP surveys MCBs for any expected automatic system response that failed to occur.

Upon discovery, they may take manual action(s) to align plant systems as expected for the event in progress. (Ref. EPM-4, Prudent Operator Actions).

Examiners Note: EDG-1A will be running without cooling water. The BOP may Emergency shutdown the EDG per AOP-P.01 Immediate Action.

CREW Performs the first four steps of E-0 unprompted.

SRO Directs performance of E-0 REACTOR TRIP OR SAFETY INJECTION.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:7 Page 29 of 36 Event

Description:

LOOP A SDBD Remains Deenergized Time Position Applicant's Actions or Behavior BOP BOP ATC ES-0.1 Step 1 thru 7

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:7 Page 30 of 36 Event

Description:

LOOP A SDBD Remains Deenergized Time Position Applicant's Actions or Behavior ATC BOP ATC ATC ATC

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:7 Page 31 of 36 Event

Description:

LOOP A SDBD Remains Deenergized Time Position Applicant's Actions or Behavior BOP BOP ATC ATC BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:7 Page 32 of 36 Event

Description:

LOOP A SDBD Remains Deenergized Time Position Applicant's Actions or Behavior ES-0.1 Appendix A BOP BOP PLACES 1-HS-1-103A and 1-HS-1-103B in OFF BOP PLACES 1-HS-1-103D IN STEAM PRESS BOP PLACES 1-HS-1-103A and 1-HS-1-103B in ON Examiners Note: ES-0.5 see page 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:8 Page 33 of 36 Event

Description:

B EDG Trips / SBO Time Position Applicant's Actions or Behavior EVENT 8- B EDG Trips / SBO Event 8 occurs automatically 1 minute after Rx Trip ECA-0.0 Step 1 thru 8 ATC BOP Crew ATC Communications: When notified to report to MCR, acknowledge and state, We will be standing by in the Shift Managers office BOP BOP NOTIFIES four AUOs to report to MCR

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:8 Page 34 of 36 Event

Description:

B EDG Trips / SBO Time Position Applicant's Actions or Behavior BOP BOP NOTIFIES Security to station officers per SQN-SSI-16.1 ATC ATC SELECTS 1-HS-62-69 to CLOSE ATC SELECTS 1-HS-62-70 to CLOSE BOP BOP

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:8 Page 35 of 36 Event

Description:

B EDG Trips / SBO Time Position Applicant's Actions or Behavior Communications: If requested to investigate status of EDGs, Based on circumstances of scenario, in order to avoid misleading candidates, confer with Examiner to determine desired report back on status of EDG-1A.

BOP BOP IDENTIFIES that EDG-1A is available BOP CRITIC DEPRESSES 0-HS-82-20 DG-1A-A START LOCKOUT RELAY RESET pushbutton AL BOP TASK momentarily (CT-24)

BOP CRITIC DEPRESSES 0-HS-82-16A DG-1A-A EMERGENCY START pushbutton AL BOP TASK momentarily (CT-24)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 5 Event No.:8 Page 36 of 36 Event

Description:

B EDG Trips / SBO Time Position Applicant's Actions or Behavior BOP BOP CRITICA OPENS Breaker 1718 (6.9KV Unit BD 1B ro SD BD 1A-A NOR) which allows the L TASK BOP EDG output breaker 1918 to Automatically close (CT-24)

Today Mode 1 100% 1206 MWe Train Week: B RCS Boron: 9 ppm BAT A RCS Leakage:

EOOS: Green Last Shift: Dilution: Rx Plan Total: Rx plan Identified: 0.01 GPM Grid Status: Qualified This Shift: Boration: Rx plan Total: Rx plan Unidentified: 0.04 GPM Site Aggregate Risk: Low Shutdown LCO Conditions Equipment INOP Next Action Due LCO 3.6.6 Condition A CSP-1B 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months Other LCO Actions Equipment INOP Next Action Due Info Only Tech Specs Equipment INOP Abnormal Equipment Lineup / Conditions (including significant Radiological changes)

Severe Thunderstorm warning is in effect for Hamilton County FT-1-3A Failed. In MAINT BYPASS Shift Priorities (Surveillances/Testing and Major Activities in Progress or Scheduled)

Maintain current power level Restore CSP-1B when work is complete For each MCR deficiency, a numbered square will be applied to the MCR Board near the associated indication/alarm. (US maintains magnets)

The CR/WO number and description of the issue will be listed below Main Control Room (7690)

Auxiliary Building (7671)

Turbine Building (7771)

TB Sump: LVWT Pond RCW: Unit 2 Aux Steam: Unit 1 Outside (7666) (423-710-4777)

Miscellaneous

2003 NRC SCN 5 Booth Instructions BOOTH OPERATOR INSTRUCTIONS Sim. Setup Reset IC-17 100% 9ppmb EOL Perform switch check.

Verify control rod step counters reset.

Place simulator in RUN.

Place Mode 1 placard on panels.

Place B Train Week sign on the simulator.

Place FT-1-3A in MAINT BYP Place RED TAG on CSP-1B Hand Switch and place in PTL Load SCN file: - ILT2003 NRC SCN 5 Acknowledge any alarms, allow the plant to stabilize, and freeze the simulator.

Perform the SIMULATOR OPERATOR CHECKLIST Place simulator in RUN before crew enters the simulator.

Start Data Capture

1. REMOVE ORANGE DOTS WHEN SCENARIO COMPLETE Page 1 of 3

2003 NRC SCN 5 Booth Instructions EVENT IC/MF/RF/OR # DESCRIPTION/EXPECTED ACTIONS/BOOTH FEEDBACK FT-1-3A in Maintenance Bypass MAIN STEAM FLOW This is manually TRANSMITTER FAILS LOW FT-inserted during setup IMF RX10A f:1 1-3A This is manually ;CONTAINMENT SPRAY PUMP IOR CSR04 f:0 inserted during setup B POWER Throughout this scenario routine communications directing administrative actions, reports, or notifications may be answered by acknowledging the report or direction. Communications requiring reports back to the examinees will be scripted. Unexpected communications requiring report back will be approved by the Lead examiner prior to contacting the Control Room. .

When directed by the Lead Examiner, use ;---PDIS-54-8C LOW DIFF IOR AN_OV_289 f:2 k:1 KEY 1 to insert PRESS MFP 1B SEAL WATER malfunction

---deletes malfunction when B

{zdihs549b1[3]} dmf AN_OV_289 INJ PUMP is taken to N-A-START There is no external leakage, Communication for When dispatched as AUO to investigate this pressure on 1-PIS-54-10C is Event 1 issue report, 385 psig, DP is 31 psid on 1-PDIS-54-8A and 8B.

When directed by the Lead Examiner, use ;---FAILURE OF PZR RELIEF IMF RC05 f:100 k:2 KEY 2 to insert VALVE PCV-68-334 malfunction

--- PRZ PORV BLOCK VLV IRF RCR04 f: 0 k:21 FCV-68-333 PWR REMOVAL When contacted as WCC SRO, acknowledge Communication for direction to de-energize PORV block valve Power has been removed Event 2 68-333. Wait 20 minutes, use KEY 21 to from FCV 68-333.

remove power from 68-333, and report, When directed by the

---IMPULSE PRESSURE Lead Examiner, use IMF RX11B f: 0 r:5 k:3 TRANSMITTER FAILS TO KEY 3 to insert VALUE 1-PT-1-73 malfunction.

Communication for If directed as AUO to inspect transmitter for Nothing abnormal with PT Event 3 PT-1-73, report, 73.

---Letdown backpressure EVENT 4 IMF CV25A f: 1 k:4 transmitter PT-62-81 fails low Page 2 of 3

2003 NRC SCN 5 Booth Instructions EVENT IC/MF/RF/OR # DESCRIPTION/EXPECTED ACTIONS/BOOTH FEEDBACK Communication for Event 4 When directed by the Lead Examiner, use ;---ABNORMAL SYSTEM IMF ED05 f:93 k:5 KEY 5 to insert VOLTAGE malfunction.

There has been a grid disturbance. Maintain SWYD Communication for If contacted as SELD, report, voltage per the voltage Event 5 schedule and attempt to maintain 400 MVARs OUT.

---LCV-6-105A FAILS TO 0 over 2 minutes When directed by the IMF HD01B f: 0 r:120 k:6

---LCV-6-105B FAILS TO 0 over Lead Examiner, use IMF HD01A f: 0 r:120 k:6 2 minutes KEY 6 to insert malfunction IMF RD09 f:1 k:6

---RODS FAIL TO MOVE IN AUTO

{egpmgen<1e9} dmf HD01A ;---malfunction clears at

{egpmgen<1e9} dmf HD01B 1000MWe Communication for IF directed to investigate, wait until Runback LCV-6-105A and 105B appear Event 6 has completed and report, to be operating normally.

When directed by the Lead Examiner, use ;---LOOP IMF ED01 f:1 k:7 KEY 7 to insert ;---1A SDBD normal feeder bkr IOR ZDIHS5744A f:0 malfunction stays closed

---When 1718 is manually

{zdihs5744a_real[0]lzdihs5744b_real[0]} IOR opened (M-1 or M-26) the EDG ZDIHS5744A f:3 bkr will auto close Communication for Event 7 EVENT 8 ;---SBO Inserted from IMF EG02B f:1 e:1 d:60 ;---1B EDG trips 60 seconds beginning after Rx Trip If requested to investigate status of EDGs Based on circumstances of scenario, in order Communication for to avoid misleading candidates, confer with Confer with Examiner Event 8 Examiner to determine desired report back on status of EDG-1A.

Page 3 of 3

Appendix D Scenario Outline Form ES-D-1 cility: Sequoyah Scenario No.: 6 Op Test No.: 2020-301 Examiners: Operators: SRO ATC BOP Initial Conditions: 48% BOL Turnover: Unit 1 is in MODE 1 48%, BOL FT-1-3A is in Maintenance Bypass Containment Spray Pump 1B OOS Severe Thunderstorm watch is in effect for Hamilton County Critical Tasks CT-52 Manually insert rods and trip turbine (by closing GVs via VPL) prior to Pzr Safety Valve lifting CT-46 Initiate RCS bleed and feed, including stopping RCPs, so that ECCS injection from at least one charging/SI pump occurs, and the RCS depressurizes sufficiently for SI pump injection flow, prior to incore temperatures exceeding 1200F CT-FRV Take manual control of FRV and restore SG level prior to RX trip.

Event Malf. Event Event Description No. No. Type cd_vac_p 1 (N) BOP Swap condenser vacuum pumps ump 2 ccp_swap (N) ATC Swap Charging Pumps (C) BOP A failure occurs on #1 SG Steam Flow Instrumentation. BOP places 3 RX09VE Feed Reg Valve in manual and controls SG level per AOP-S.01.

ZDIHS465 TD AFW Pump electrical overspeed alarm followed by loss of DC 4 5A TS SRO control power results in unavailable TDAFW Pump. SRO addresses FWR02 LCO THIS EVENT WAS NOT USED (I) ATC PRNI failure. ATC places failed channel in bypass per AOP-I.01.

5 NI07D TS-SRO SRO addresses LCO THIS EVENT WAS NOT USED LOFW_fw A MFWP trips resulting in a loss of MFW. Rx does not automatically 6 (M) ALL FWR13A trip THIS EVENT WAS NOT USED ATWS occurs; Rods fail to auto insert. ATC manually inserts rods 7 RP01C (C) ATC per FR-S.1 immediate actions. Crew enters FR-S.1 NOT USED Turbine fails to trip via Auto or Manual signals. BOP uses Valve 8 TC04 (C) BOP Position Limiter to close Turbine Valves per FR-S.1 NOT USED FW07A Loss of all AFW results in crew entering FR-H.1 and transition to 9 (C) ATC FW07B Feed and Bleed cooling THIS EVENT WAS NOT USED

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor EVENTS 4 - 9 NOT USED BECAUSE SCENARIO WAS RAN TO MEET THE MINIMUM REQUIRED EVENTS FOR ONE RO APPLICANT THAT MISSED AN EARLIER SCENARIO EVENT

Appendix D Scenario Outline Form ES-D-1 2020-301 Scenario 6 Summary Event 1 - BOP swaps condenser vacuum pumps Verifiable actions: (BOP) BOP swaps condenser vacuum pumps Event 2 - ATC swaps Charging pumps.

Verifiable actions: (ATC) swaps CCPs.

Event 3 - A failure occurs on #1 SG Steam Flow Instrumentation. BOP places Feed Reg Valve in manual and controls SG level per AOP-S.01, Main Feedwater Malfunctions prior to Rx Trip (CT-FRV.)

Verifiable actions: (BOP) places Feed Reg Valve in manual and controls SG level.

Event 4 - TD AFW Pump electrical overspeed alarm followed by loss of DC control power results in unavailable TDAFW Pump. SRO addresses LCO. Note: TDAFW pump remains available for manual local operation and recovery with alternate control power iaw EA-3-7 Verifiable actions: TS only Event 5 - PRNI failure. ATC places failed channel in bypass per AOP-I.01, Nuclear Instrument Malfunction. SRO addresses LCO Verifiable actions: (ATC) places failed channel in bypass.

Event 6 - Major - With the B MFP not yet in service, A MFWP trips resulting in a loss of MFW. Rx does not automatically trip.

Verifiable actions: (ATC) manually trips Rx Event 7 -ATWS occurs. Rods fail to auto insert. ATC manually inserts rods per FR-S.1, Nuclear Power Generation/ATWS. Crew enters FR-S.1 (CT-52)

Event 8 - Turbine fails to trip via Auto or Manual signals. BOP uses Valve Position Limiter to close Turbine Valves per FR-S.1, Nuclear Power Generation/ATWS Verifiable actions: (BOP) uses Valve Position Limiter to close Turbine Valves Event 9 - Loss of all AFW results in crew entering FR-H.1, Loss of Secondary Heat Sink. Crew establishes Bleed & Feed based on SG levels.

Verifiable actions: (ATC) Actuates SI and opens PORVs.

Terminate in FR-H.1 when Bleed & Feed has been established (CT-46)

SO-2-9 / SO-62-62-1 / AOP-S.01 / ARP / AOP-I.01 / E-0 / FR-S.1 / FR-H.1

Appendix D Scenario Outline Form ES-D-1 Similarities vs. two most recent exams (1603 was 2016-301) (1712 was 2017-301)

Except as noted, events were not included in the last two exams Audit exam is based on 1712 exam so no events are duplicated from that exam.

6 of 8 events were not used on the previous two exams*

Event 1 - last used in 1603

Event 2 - Not used in last two exams

Event 3 - RX09VE Not used in last two exams

Event 4 - ZDIHS4655A Not used in last two exams

Event 5 - NI07D Not used in last two exams. Similar to 1712 but different instrument different failure

Event 6 - Major - LOFW_afw FWR13A Not used in last two exams Event 7 - last used in 1603

Event 8 - TC04 w/ ATWS Not used in last two exams Event 9 FR-H.1 Feed and Bleed

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:1 Page 1 of 50 Event

Description:

Swap Condenser Vacuum Pumps Time Position Applicant's Actions or Behavior EVENT LIST 1 Swap Condenser Vacuum Pumps 2 Swap Charging Pumps 3 SG Steam Flow Transmitter Fails 4 TDAFW Pump Loss of DC Control Power 5 PRNI Failure 6 MFW Pump Trip 7 ATWS 8 Main Turbine Trip Failure 9 Loss Of All AFW EVENT 1 - Swap Condenser Vacuum Pumps Event 1 is directed by turnover sheet 1-SO-2-9 Examiners Note: A marked up in progress copy of 1-SO-2-9 Section 6.1 is provided. Step 1 indicates that Valve checklists have been completed. Direction is to start the B pump and stop the A Pump ATC BOP NOTIFIES TB AUO to standby.

BOP DIRECTS AUO to obtain required crescent wrench Communications: When directed to CHECK water reservoir level normal for the B Pump report, 1B Condenser Vacuum Pump water reservoir level is normal.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:1 Page 2 of 50 Event

Description:

Swap Condenser Vacuum Pumps Time Position Applicant's Actions or Behavior BOP BOP PLACES 1-HS-2-176A momentarily to the START position Communications: When requested to CHECK OPEN suction valve report, 1-FCV-2-176 is OPEN.

BOP BOP Directs AUO to CHECK OPEN 1-FCV-2-176 Communications: WHEN requested report. Suction Valve 1-FCV-2-171 is CLOSED.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:1 Page 3 of 50 Event

Description:

Swap Condenser Vacuum Pumps Time Position Applicant's Actions or Behavior PLACES 1-HS-2-171A (A pump) momentarily in STOP and then allows it to return BOP to P-AUTO Communications: When directed to CHECK CLOSED 1-FCV-2-171 report, A Condenser Vacuum Pump Suction valve 1-FCV-2-171 is CLOSED.

BOP Examiners Note: Step 9 contains contingency actions if suction valve fails to close or seal water level is lost. These steps are not applicable to this evolution.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:1 Page 4 of 50 Event

Description:

Swap Condenser Vacuum Pumps Time Position Applicant's Actions or Behavior Examiners Note: Step 12 is not expected to be necessary.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:2 Page 5 of 50 Event

Description:

Swap Charging Pumps Time Position Applicant's Actions or Behavior EVENT 2 - Swap Charging Pumps Event 2 is directed by turnover sheet Examiners Note: The ATC is directed to swap from CCP-1B to CCP-1A. An in progress copy of 1-SO-62-1 Section 8.11 is provided 1-SO-62-1 BOP BOP DETERMINES A Train CCS and ERCW are in service Communications: When directed as AB AUO to inspect CCP-1A for start report, CCP-1A is ready for start. Step 2 is complete.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:2 Page 6 of 50 Event

Description:

Swap Charging Pumps Time Position Applicant's Actions or Behavior ATC STEP is NOT APPLICABLE.

Communications: Approximately 1 minute after pump start report, 1A CCP is normal after start.

ATC ATC PLACES 1-HS-62-108A 1A-A CCP momentarily in START ATC PLACES 1-HS-62-108A 1A-A CCP momentarily in STOP and allows it to return to A-ATC AUTO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:2 Page 7 of 50 Event

Description:

Swap Charging Pumps Time Position Applicant's Actions or Behavior ATC ATC ENSURES 1-HS-62-108A 1B-B CCP is in A-AUTO BOP BOP ENSURES 1-HS-62-108A 1A-A CCP is in A-AUTO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:3 Page 8 of 50 Event

Description:

SG Steam Flow Transmitter Fails Time Position Applicant's Actions or Behavior EVENT 3 - SG Steam Flow Transmitter Fails Direct simulator operator to insert Event 3,(KEY 3)

Indications available:

M4-B D-5: DCS ABNORMAL

M5-A A-7: FS-3-35A STEAM GEN FEEDWATER FLOW HIGH Indications

SG-1 STEAM FLOW CH-2 1-FI-1-3B: drops to 0 1-AR-M4-B D-5 Examiners Note: Some steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.

BOP SRO Transitions to AOP-S.01, Main Feedwater Malfunctions 8

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:3 Page 9 of 50 Event

Description:

SG Steam Flow Transmitter Fails Time Position Applicant's Actions or Behavior AOP-S.01 BOP BOP CRITICAL Places FIC-3-35, #1 S/G Feed Regulating Valve to MANUAL and controls output TASK (FRV) BOP to maintain S/G levels on program level based on Immediate Operator Actions.

SRO 9

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:3 Page 10 of 50 Event

Description:

SG Steam Flow Transmitter Fails Time Position Applicant's Actions or Behavior BOP

DETERMINES 1-FT-1-3B has failed low

SELECTS the #1 SG STEAM FLOW Instrument Page

CLICKS MAINT BYPASS SIGNAL B for 1-FT-1-3B BOP

DETERMINES both STEAM FLOW channels have failed

SELECTS the LOOP 1 FEEDWATER VALVE CONTROL screen

ENSURES single element control 10

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:4 Page 11 of 50 Event

Description:

TDAFW Pump Loss of DC Control Power Time Position Applicant's Actions or Behavior EVENT 4 - TDAFW Pump Loss of DC Control Power Direct simulator operator to insert Event 4 (KEY 4)

Examiner Note: Initial annunciator alarm is associated with TDAFWP Electric Overspeed trip. Thirty seconds later DC control power is lost.

Indications available:

M3-C A-3: AUX FWP TURBINE 1A-S ELECTRONIC OVSP TRIP OR TROUBLE Indications:

1-AR-M3-C A-3 Examiner Note: Loss of control power to the TDAFWP will result in:

Closure of SGBD outside CNTMT Isolation valves 1-FCV-1-7, 14, 25, and 32

STM GEN BLDN LIQ SAMP MON ISTR MALFUNC alarm (see page 16)

Loss of GREEN POSITION light for TDAFWP Trip Throttle Valve (FCV-1-51)

Examiner Note: Some steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.

Communications: If requested as AUO, acknowledge direction to inspect/investigate alarm. Wait 3 minutes and report, Panel 1-L-326G appears to be de-energized.

BOP BOP Dispatches AUO to investigate alarm 11

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:4 Page 12 of 50 Event

Description:

TDAFW Pump Loss of DC Control Power Time Position Applicant's Actions or Behavior SRO SRO Determines LCO 3.7.5 Condition B is applicable.

12

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:4 Page 13 of 50 Event

Description:

TDAFW Pump Loss of DC Control Power Time Position Applicant's Actions or Behavior 13

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:4 Page 14 of 50 Event

Description:

TDAFW Pump Loss of DC Control Power Time Position Applicant's Actions or Behavior 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:4 Page 15 of 50 Event

Description:

TDAFW Pump Loss of DC Control Power Time Position Applicant's Actions or Behavior 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:4 Page 16 of 50 Event

Description:

TDAFW Pump Loss of DC Control Power Time Position Applicant's Actions or Behavior 0-AR-M12-A B-6 Examiners Note: Some steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.

Communications: IF dispatched to investigate SGBD Rad Monitor malfunction alarm confer with Examiner to determine desired report back.

BOP SRO Transitions to AOP-S.01, Main Feedwater Malfunctions 16

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:4 Page 17 of 50 Event

Description:

TDAFW Pump Loss of DC Control Power Time Position Applicant's Actions or Behavior LCO 3.7.5 Condition B 17

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:5 Page 18 of 50 Event

Description:

PRNI Failure Time Position Applicant's Actions or Behavior EVENT 5 - PRNI Failure 1-AR-M4-B D-3 Examiners Note: Only steps, notes, and cautions associated with this event are included here BOP SRO Transitions to AOP-I.01, Nuclear Instrument Malfunction 1-AR-M4-B E-3 18

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:5 Page 19 of 50 Event

Description:

PRNI Failure Time Position Applicant's Actions or Behavior Examiners Note: Only steps, notes, and cautions associated with this event are included here ATC SRO Transitions to AOP-I.01, Nuclear Instrument Malfunction 1-AR-M6-A B-1 Examiners Note: Only steps, notes, and cautions associated with this event are included here ATC SRO Transitions to AOP-I.01, Nuclear Instrument Malfunction 19

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:5 Page 20 of 50 Event

Description:

PRNI Failure Time Position Applicant's Actions or Behavior 1-AR-M6-A D-1 Examiners Note: Only steps, notes, and cautions associated with this event are included here ATC SRO Transitions to AOP-I.01, Nuclear Instrument Malfunction AOP-I.01 SRO 20

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:5 Page 21 of 50 Event

Description:

PRNI Failure Time Position Applicant's Actions or Behavior ATC PLACES HS-85-5110 ROD CONTROL MODE SELECTOR in MANUAL.

ATC SRO DETERMINES LCO 3.3.1 Conditions A, D, E, O, P are applicable for functions SRO 2.a, 3.a, 3.b, 6, 7, and 16.c, 16.d, and 16.e ATC ATC ATC 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:5 Page 22 of 50 Event

Description:

PRNI Failure Time Position Applicant's Actions or Behavior ATC ATC PLACES UPPER SECTION switch to N44 ATC ATC PLACES LOWER SECTION switch to N44 ATC ATC PLACES right side ROD STOP BYPASS switch to N44 ATC ATC PLACES the COMPARATOR CHANNEL DEFEAT switch to N44 ATC 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:5 Page 23 of 50 Event

Description:

PRNI Failure Time Position Applicant's Actions or Behavior ATC ATC ATC/SRO ATC PLACES Rod Control switch in AUTO 23

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:5 Page 24 of 50 Event

Description:

PRNI Failure Time Position Applicant's Actions or Behavior Communications: When requested as WCC SRO or I&C Supervisor, acknowledge direction to perform Appendix B. State, I&C personnel will be report to the Control Room in about 45 minutes..

CREW SRO Communications: If requested as WCC SRO, acknowledge direction to write a work order and notify required personnel.

24

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:5 Page 25 of 50 Event

Description:

PRNI Failure Time Position Applicant's Actions or Behavior LCO 3.3.1 Condition A, D, E, O, P 25

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:5 Page 26 of 50 Event

Description:

PRNI Failure Time Position Applicant's Actions or Behavior 26

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:5 Page 27 of 50 Event

Description:

PRNI Failure Time Position Applicant's Actions or Behavior 27

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:5 Page 28 of 50 Event

Description:

PRNI Failure Time Position Applicant's Actions or Behavior 28

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:6 Page 29 of 50 Event

Description:

MFW Pump Trip Time Position Applicant's Actions or Behavior EVENT 6 - MFW Pump Trip Direct simulator operator to insert Event 6 (KEY 6)

Examiners Note: The next 3 events involve a MFW pump trip with a failure of the Rx to automatically trip and failure of Manual trip from the MCR switches ( an ATWS) and failure of the Main Turbine to manually trip.

Examiners Note: The normal practice upon entry into FR-S.1 is to trip the Main Turbine and allow the large power mismatch to drive rods in automatically. This results in a faster rod insertion than in manual control. In this case, the Main Turbine will not trip and VPL is used to close the governor valves. Further, automatic rod control is faulted and Manual insertion of control rods is required.

1-AR-M3-B A-2 ATC Identifies failure of Rx to automatically trip and attempts to trip the Rx using Rx ATC Trip switch (both unsuccessful)

SRO Enters FR-S.1 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:7 Page 30 of 50 Event

Description:

ATWS Time Position Applicant's Actions or Behavior EVENT 7 - ATWS Event 7 is inserted automatically FR-S.1 Step 1 Examiners Note: The normal practice upon entry into FR-S.1 is to trip the Main Turbine and allow the large power mismatch to drive rods in automatically. This results in a faster rod insertion than in manual control. In this case, the Main Turbine will not trip and VPL is used to close the governor valves. Further, automatic rod control is faulted and Manual insertion of control rods is required.

Communications: When contacted to OPEN RX Trip breakers and MG SET Supply breakers, acknowledge and immediately use KEY 16 This will open RX Trip breakers after a built-on 2 minute delay, After 2 minutes report, Rx Trip breakers are OPEN.

ATC CRITICAL PLACES ROD CONTROL MODE SELECTOR Swith to MAN and and PLACES TASK(52) ATC ROD CONTROL swith to IN 30

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:8 Page 31 of 50 Event

Description:

Main Turbine Trip Failure Time Position Applicant's Actions or Behavior EVENT 8 - Main Turbine Trip Failure Event 8 is inserted automatically Examiners Note: TD AFW Pump has previously sufffered a loss of DC Control Power. A and B MD AFW Pumps will not start resulting in a loss of all FW, FR-S.1 Step 2 thru 4b BOP CRITICAL PLACES TURBINE TRIP switch to the TRIP (clockwise) position (unsuccessful)

TASK(52) BOP DEPRESSES the VPL LOWER pushbutton and holds until GVs are fully closed BOP BOP Attempts (unsuccessfully to start A and B MDAFW pumps BOP BOP TDAFW Pump is not available due to previous failure 31

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:8 Page 32 of 50 Event

Description:

Main Turbine Trip Failure Time Position Applicant's Actions or Behavior BOP Examiners Note: With the ATC occupied with continuously driving in control rods in manual, the BOP should get GVs closed before rods are fully inserted and will move over and begin emergency boration ATC BOP BOP INITIATE Emergency Boration EA-68-4 Step 1 BOP 32

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:8 Page 33 of 50 Event

Description:

Main Turbine Trip Failure Time Position Applicant's Actions or Behavior EA-68-4 Attachment 1 ATC a) Momentarily PLACES 1-HS-62-230A, BA TRANSFER PUMP 1A in STOP; b) SELECTS 1-HS-62-230D BA TRANSFER PUMP 1A SPEED SEL to FAST; c) Momentarily PLACES 1-HS-62-230A, BA TRANSFER PUMP 1A in START (May perform the same actions for the B BA TRANSFER pump but this is not required.)

It is acceptable to perform detail b) prior to detail a)

ATC THROTTLES OPEN 1-HS-62-138A until flowrate on 1-HS-62-137A indicates flowrate from step 1 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:8 Page 34 of 50 Event

Description:

Main Turbine Trip Failure Time Position Applicant's Actions or Behavior 34

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:8 Page 35 of 50 Event

Description:

Main Turbine Trip Failure Time Position Applicant's Actions or Behavior FR-S.1 Step 4c thru 21 AT AT AT AT 35

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:8 Page 36 of 50 Event

Description:

Main Turbine Trip Failure Time Position Applicant's Actions or Behavior Communications: IF not already done, When contacted to OPEN RX Trip breakers and MG SET Supply breakers, acknowledge and immediately use KEY 16 This will open RX Trip breakers after a built-on 2 minute delay AT BO DIRECTS AB AUO to OPEN Rx Trip bkrs and MG set output bkrs DIRECTS TB AUO to OPEN MG set supply bkrs Communications: When directed to trip turbine from front standard, acknowledge, wait 2 minutes, insert KEY 30, and report, The Main Turbine is tripped.

Communications: When directed to place the EHC pumps in PTL, acknowledge, wait 2 minutes, insert KEY 31, and report, EHC pumps are in PTL.

DIRECTS TB AUO to TRIP turbine from front stand and PLACE EHC pumps in BOP PTL 36

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:8 Page 37 of 50 Event

Description:

Main Turbine Trip Failure Time Position Applicant's Actions or Behavior 37

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:8 Page 38 of 50 Event

Description:

Main Turbine Trip Failure Time Position Applicant's Actions or Behavior Examiners Note: TD AFW Pump has previously sufffered a loss of DC Control Power. A and B MD AFW Pumps will not start resulting in a loss of all FW, 38

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:8 Page 39 of 50 Event

Description:

Main Turbine Trip Failure Time Position Applicant's Actions or Behavior SRO 39

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:8 Page 40 of 50 Event

Description:

Main Turbine Trip Failure Time Position Applicant's Actions or Behavior SRO Transitions to E-0 E-0 Step 1 thru 4 Examiner Note: Following transition back from FR-S.1 IO Steps 1-4 should be revisited at a high level.

Examiners Note: With no AFW pumps the entry conditions for FR-H.1 are met. The STA should report that a RED PATH exists in HEAT SINK.

CREW Reviews status of the first four steps of E-0.

ATC BOP BOP 40

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:8 Page 41 of 50 Event

Description:

Main Turbine Trip Failure Time Position Applicant's Actions or Behavior ATC ES-0.1 Step 1 thru 5 BOP BOP BOP 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:8 Page 42 of 50 Event

Description:

Main Turbine Trip Failure Time Position Applicant's Actions or Behavior Examiners Note: At this point it should be apparent to the crew that FR-H.1 is applicable 42

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:9 Page 43 of 50 Event

Description:

Loss Of All AFW Time Position Applicant's Actions or Behavior EVENT 9 - Loss Of All AFW Event 9 is inserted automatically FR-H.1 Step 1 thru 3 BOP ATC 43

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:9 Page 44 of 50 Event

Description:

Loss Of All AFW Time Position Applicant's Actions or Behavior Examiners Note: Depending on timing and plant response, criteria may be met to immediately go to feed and bleed. Steps for feed and bleed are shown on page 49 Examiners Note: Attempts to restore any feedwater source are unsuccessful.

BOP 44

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:9 Page 45 of 50 Event

Description:

Loss Of All AFW Time Position Applicant's Actions or Behavior FR-H.1 Step 4 thru 5 (AFW Recovery)

Examiners Note: Attempts to recover MD AFW are unsuccessful 45

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:9 Page 46 of 50 Event

Description:

Loss Of All AFW Time Position Applicant's Actions or Behavior Examiners Note: TD AFW pump not available available due to previous failure BOP 46

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:9 Page 47 of 50 Event

Description:

Loss Of All AFW Time Position Applicant's Actions or Behavior BOP ATC ATC Stops all 4 RCPs BOP 47

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:9 Page 48 of 50 Event

Description:

Loss Of All AFW Time Position Applicant's Actions or Behavior BOP BOP 48

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:9 Page 49 of 50 Event

Description:

Loss Of All AFW Time Position Applicant's Actions or Behavior BOP /

SRO FR-H.1 Step 14 thru 17 (Feed and Bleed)

ATC CRITICAL TASK(46) ATC ACTUATES SI 49

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2020-301 Scenario No.: 6 Event No.:9 Page 50 of 50 Event

Description:

Loss Of All AFW Time Position Applicant's Actions or Behavior ATC ATC ATC CRITICAL TASK(46) ATC SELECTS both PORVs to OPEN Examiners Note: Scenario may be terminate when Feed and Bleed has been established 50

Today Mode 1 48% 570 MWe Train Week: B RCS Boron: 1204 ppm BAT A RCS Leakage:

EOOS: Green Last Shift: Dilution: Rx Plan Total: Rx plan Identified: 0.01 GPM Grid Status: Qualified This Shift: Boration: Rx plan Total: Rx plan Unidentified: 0.04 GPM Site Aggregate Risk: Low Shutdown LCO Conditions Equipment INOP Next Action Due LCO 3.6.6 Condition A CSP-1B 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months Other LCO Actions Equipment INOP Next Action Due Info Only Tech Specs Equipment INOP Abnormal Equipment Lineup / Conditions (including significant Radiological changes)

Severe Thunderstorm warning is in effect for Hamilton County FT-1-3A Failed. In MAINT BYPASS Shift Priorities (Surveillances/Testing and Major Activities in Progress or Scheduled)

Maintain current power level Restore CSP-1B when work is complete For each MCR deficiency, a numbered square will be applied to the MCR Board near the associated indication/alarm. (US maintains magnets)

The CR/WO number and description of the issue will be listed below Main Control Room (7690)

Auxiliary Building (7671)

Turbine Building (7771)

TB Sump: LVWT Pond RCW: Unit 2 Aux Steam: Unit 1 Outside (7666) (423-710-4777)

Miscellaneous

2003 NRC SCN 6 Booth Instructions BOOTH OPERATOR INSTRUCTIONS Sim. Setup Reset IC-13 48% 1204 ppmb Perform switch check.

Verify control rod step counters reset.

Place simulator in RUN.

Place Mode 1 placard on panels.

Place B Train Week sign on the simulator.

Place FT-1-3A in MAINT BYP Place RED TAG on CSP-1B Hand Switch and place in PTL Load SCN file: - ILT2003 NRC SCN 6 Acknowledge any alarms, allow the plant to stabilize, and freeze the simulator.

Perform the SIMULATOR OPERATOR CHECKLIST Place simulator in RUN before crew enters the simulator.

Start Data Capture

1. REMOVE ORANGE DOTS WHEN SCENARIO COMPLETE Page 1 of 4

2003 NRC SCN 6 Booth Instructions EVENT IC/MF/RF/OR # DESCRIPTION/EXPECTED ACTIONS/BOOTH FEEDBACK This is manually FT-1-3A in Maintenance Bypass MAIN STEAM FLOW TRANSMITTER inserted during IMF RX10A f:1 FAILS LOW FT-1-3A setup This is manually IOR CSR04 f:0 ;CONTAINMENT SPRAY PUMP B POWER inserted during setup Throughout this scenario routine communications directing administrative actions, reports, or notifications may be answered by acknowledging the report or direction. Communications requiring reports back to the examinees will be scripted. Unexpected communications requiring report back will be approved by the Lead examiner prior to contacting the Control Room. .

EVENT 1 is a normal ;---BOP Swaps CD vacuum pumps evolution 1B Condenser Vacuum Pump water

{zdihs2176a[2]} dmf CN09 reservoir level is normal.

When directed to CHECK water Communication 1B Condenser Vacuum Pump water reservoir level normal for the B Pump for Event 1 reservoir level is normal.

report, When directed to CHECK OPEN 1-FCV-2-176 is OPEN.

suction valve report, WHEN requested report. Suction Valve 1-FCV-2-171 is CLOSED.

EVENT 2 is a normal ;---ATC SWAP CCPs evolution Communication When directed as AB AUO to inspect CCP-1A is ready for start. Step 2 is for Event 2 CCP-1A for start report, complete.

Approximately 1 minute after pump 1A CCP is normal after start.

start report, When directed by the Lead

---MAIN STEAM FLOW TRANSMITTER Examiner, use IMF RX09VE f: 0 r:0 k:3 FT-1-3B FAILS TO VALUE KEY 3 to insert malfunction.

Communication for Event 3 EVENT 4 IOR ZDIHS4655A f:1 k:4 ;---AFWT A-S MAN ELEC OVSP TRP Page 2 of 4

2003 NRC SCN 6 Booth Instructions EVENT IC/MF/RF/OR # DESCRIPTION/EXPECTED ACTIONS/BOOTH FEEDBACK IOR FWR02 f:2 d:30 k:4 ;---AFPT DC CONTROL POWER Loss If requested as AUO, acknowledge Panel 1-L-326G appears to be de-direction to inspect/investigate alarm.

energized.

Wait 3 minutes and report, IF dispatched to investigate SGBD Confer with Examiner to determine Rad Monitor malfunction alarm desired report back.

When directed by the Lead

---PR CHANNEL OUTPUT SIGNAL Examiner, use IMF NI07D f: 120 k:5 FAILURE PR CHNL 4 KEY 5 to insert malfunction.

When requested as WCC SRO or I&C Communication I&C personnel will be report to the Supervisor, acknowledge direction to for Event 5 Control Room in about 45 minutes..

perform Appendix B. State, When directed

---LOCAL TRIP OF MFP A (NO PWR by the Lead IOR FWR13A f: 1 k:6 REQD)

Examiner, use IMF RD09 f:1 k:6 ;---RODS FAIL TO MOVE IN AUTO KEY 6 to insert (preserves critical task) malfunction Communication for Event 6 EVENT 7 Inserted from ;---BOTH RX TRIP BKRS FAIL TO OPEN IMF RP01C f:1 beginning (ATWS)

---RX TRIP BREAKER A MANUAL TRIP IRF RPR05A f: 1 d:120 k:16 after 2 minute delay IRF RPR05B f:1 d:125 k:16 ;---RX TRIP BREAKER B MANUAL TRIP after 2 minute delay When contacted to OPEN RX Trip breakers and MG SET Supply Communication breakers, acknowledge and Rx Trip breakers are OPEN.

for Event 7 immediately use KEY 16 This will open RX Trip breakers after a built-on 2 minute delay, After 2 minutes report, EVENT 8

---TURBINE FAILS TO TRIP (ALL Inserted from IMF TC04 f: 1 SOLENOIDS & TRIP BAR FAILURES beginning

---TURBINE OVERSPEED REMOTE IOR TCR02 f: 2 k:30 LATCH/NORMAL/TRIP When directed to trip turbine from front Communication standard, acknowledge, wait 2 The Main Turbine is tripped.

for Event 8 minutes, insert KEY 30, and report, When directed to place the EHC pumps in PTL, acknowledge, wait 2 EHC pumps are in PTL.

minutes, insert KEY 31, and report, Page 3 of 4

2003 NRC SCN 6 Booth Instructions EVENT IC/MF/RF/OR # DESCRIPTION/EXPECTED ACTIONS/BOOTH FEEDBACK IOR TCR03 f:0 k:31 ;---LOCAL HS-47-9 FOR EH PUMP A IOR TCR04 f:0 k:31 ;---LOCAL HS-47-14 FOR EH PUMP B EVENT 9 IMF FW07A f:1 Inserted from IMF FW07B f:1 beginning Communication for Event 9 Page 4 of 4

SITE: SQN JPM TITLE Recover a misaligned rod JPM-C.01-JPM NUMBER [01] REVISION: 31 TASK APPLICABILITY: SRO STA UO NAUO TASK NUMBERS / TASK TITLE(S)

K/A RATINGS 001 A2.17 (3.3/3.8)

Ability to (a) predict the impacts of the following malfunction or operations on the CRDS- and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences K/A STATEMENT of those malfunctions or operations: Rod-misalignment alarm RELATED PRA INFORMATION Not required for exam.

SAFETY FUNCTION: 1 EVALUATION LOCATION: In-Plant Simulator Control Room Lab Other - List:

APPLICABLE METHOD OF TESTING: Discussion Simulate/Walkthrough Perform TIME FOR COMPLETION: 10 minutes TIME CRITICAL (Y/N) N ALTERNATE PATH (Y/N) Y Developed by: Aaron Forsha 11/18/19 Developer Date (Ensure validator is briefed on exam security per NPG-SPP-17.8.1)

(See JPM Validation Checklist in NPG-SPP-17.8.2)

Validated by: Ted Doukus 11/18/19 Validator Date Approved by: Aaron Forsha 11/18/19 Site Training Management Date Approved by: Terry Dunny 11/18/19 Site Training Program Owner Date Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 1 of 11 [08-08-2014]

JPM-C.01 [01], Rev 31 SPECIAL INSTRUCTIONS:

1. Ensure Simulator Operator Checklist is complete

2. Reset to IC 273 password: rodfun

{rdprod[44] > 190 IMF RD07D4 f:1

{rdprod[44] > 190 IMF RD07M2 f:1 Automatic RX trips are blocked Place arrow pointing toward misaligned Rod Place Pink tag on Rod Control Select Switch

3. PLACE SIMULATOR IN RUN

4. Place MODE 1 sign on the simulator

5. An extra operator will be required to acknowledge alarms and monitor secondary plant.

6. ACKNOWLEDGE ALARMS

7. FREEZE SIMULATOR

8. After JPM is complete, x IF this JPM is to be ran again ENSURE recorders have been cleared.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 2 of 11 [08-08-2014]

JPM-C.01 [01], Rev 31 JPM Briefing from NPG-SPP-17.8.2 completed? Yes If no, perform briefing prior to continuing.

Initial Conditions As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

(REMEMBER TO VERIFY STUDENT SHEET HAS THIS SAME INFORMATION)

INITIAL CONDITIONS:

1. Unit 1 is in MODE 1

2. 20 minutes ago ROD D-4 became misaligned at 185 steps with Control Bank D during normal rod withdrawal

3. AOP-C.01 Rod Control Malfunctions is complete through section 2.3 step 15

4. The misaligned rod will be recovered by moving the rod to the bank

5. The disconnect panel is unlocked INITIATING CUES (IF APPLICABLE):

1. The US has directed you to Recover Rod D-4 Using AOP-C.01 Section 2.3 starting at step 16 This JPM is a "time critical" JPM.

This JPM is not a "time critical" JPM.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 3 of 11 [08-08-2014]

JPM-C.01 [01], Rev 31 Required Materials: AOP-C.01 Rod Control Malfunctions (marked up)

References:

1. AOP-C.01 Rod Control Malfunctions Operator aligns rod control to withdraw Rod D4, during recovery two rods fall to Task Standards: the bottom over 10 seconds, Negative rate trip generates a RX trip which fails, and the operator must manually trip the reactor.

NOTE:

When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

IMPORTANT:

Critical steps are marked with a Y below the Performance Step number field. Failure to meet the standard for any critical step shall result in failure of this JPM.

Start Time:

Step # 1. Performance step:

Critical Step?

16. PLACE rod control in BANK SELECT for affected bank.

Y Standard: Operator rotates Bank Select switch to Control Bank D Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 4 of 11 [08-08-2014]

JPM-C.01 [01], Rev 31 Step # 2. Performance step:

Critical Step?

17. CHECK affected rod bank is to be moved to misaligned rod position.

N Standard: Operator determines per cue sheet rod is being moved to the bank Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: If asked, provide Refer to cue sheet.

Comments:

Step # 3. Performance step:

Critical Step? 21. RECORD step counter reading(s) for affected rod bank:

Group 1: _________ steps N Group 2:

(if applicable) _________ steps Standard: Applicant records Grp 1 : 198 Grp 2 : 197 Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 5 of 11 [08-08-2014]

JPM-C.01 [01], Rev 31 Step # 4. Performance step:

Critical Step? NOTE 1 Key #81 is needed to open lift coil disconnect switch panel.

NOTE 2 Toggle switch UP is DISCONNECTED position.

22. DISCONNECT all lift coils of rods in affected bank EXCEPT misaligned rod:

CONTROL ROD LOCATION / BANK SDA E-5 E-11 L-11 L-5 B-4 D-14 P-12 M-2 SDB G-3 C-9 J-13 N-7 C-7 G-13 N-9 J-3 Y

SDC E-3 C-11 L-13 N-5 SDD C-5 E-13 N-11 L-3 CBA H-6 H-10 F-8 K-8 CBB F-2 B-10 K-14 P-6 B-6 F-14 P-10 K-2 CBC H-2 B-8 H-14 P-8 F-6 F-10 K-10 K-6 CBD D-4 D-12 M-12 M-4 H-4 D-8 H-12 M-8 H-8 Standard: Bolded switches above are moved upward to the disconnected position Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 6 of 11 [08-08-2014]

JPM-C.01 [01], Rev 31 Step # 5. Performance step:

Critical Step? 23. ADJUST affected group step counter N to misaligned rod position.

Applicant adjusts Group 1 step counter to 185 steps using pen/stylus to toggle Standard:

buttons to the right of the indicator Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 6. Performance step:

Critical Step? 24. RECORD reactor power level:

N %

Standard: Operator records power at ~79%

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 7 of 11 [08-08-2014]

JPM-C.01 [01], Rev 31 Step # 7. Performance step:

Critical Step? BEGIN ALT PATH NOTE ROD CONTROL URGENT FAILURE alarm [M-4B, A-6] will annunciate when rod motion begins (except Shutdown Banks C and D). Other alarms associated with rod control may occur due to errors in P/A converter and ICS. Alarms will reset when rods are aligned and rod position is updated.

Y 25. PERFORM recovery action based on elapsed time since rod misalignment:

a. IF elapsed time since misaligned rod is less than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , THEN:

1) WITHDRAW or INSERT rod/bank to associated bank/rod position at fastest practical rate.

Standard: Operator Withdrawals Rod D4 by moving in/hold/out switch to out Performance:

When the misaligned rod is >190 steps, Rod M2 will fall to the bottom; Rod D4 will fall Examiner Notes: to the bottom.

The RX will receive a Negative rate trip signal; Automatic RX trip is blocked.

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 8 of 11 [08-08-2014]

JPM-C.01 [01], Rev 31 Step # 8. Performance step:

Critical Step? 2.2 Dropped Rod(s)Reactor Initially in Mode 1 or 2 NOTE Steps 1 and 2 are immediate actions.

1. PLACE rod control in MANUAL.

2. CHECK ONLY ONE rod dropped. IF more than one rod has dropped, Y THEN TRIP the reactor and GO TO E-0, Reactor Trip or Safety Injection. [C.5]

Standard: Operator Manually Trips the Reactor Performance: SATISFACTORY UNSATISFACTORY Operator may recognize an auto trip of the reactor is called for and take actions per E-0 Examiner Notes:

immediate operator actions. The critical element of this step is the Reactor Trip Cue:

Comments:

Terminating Cue: Another operator will complete the remaining steps of this procedure.

Stop Time:

Operator Fundamental evaluated:

Historical Record:

Rev 29 New JPM Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 9 of 11 [08-08-2014]

JPM-C.01 [01], Rev 31 JPM DATA SHEET EXAMINEES NAME: EIN:

EVALUATORS NAME: DATE:

JPM Title JPM-C.01 [01], Recover a misaligned rod Start Time Finish Time Performance Time PERFORMANCE RESULTS: SAT UNSAT COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory)

Evaluators Signature:

Date NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

[08-08-2014]

TURNOVER SHEET As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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:

1. Unit 1 is in MODE 1

2. 20 minutes ago ROD D-4 became misaligned at 185 steps with Control Bank D during normal rod withdrawal

3. AOP-C.01 Rod Control Malfunctions is complete through section 2.3 step 15

4. The rod will be recovered by moving the rod to the bank

5. The disconnect panel is unlocked INITIATING CUES (IF APPLICABLE):

1. The US has directed you to Recover Rod D-4 Using AOP-C.01 Section 2.3 starting at step 16 This JPM is a "time critical" JPM.

This JPM is not a "time critical" JPM.

SITE: SQN JPM TITLE Terminate Safety Injection JPM NUMBER JPM-E0 [02] REVISION: 41 TASK APPLICABILITY: SRO STA UO NAUO TASK NUMBERS / TASK TITLE(S) 00001000501 K/A RATINGS 013 A2.06 (3.7/4.0)

Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions K/A STATEMENT or operations; Inadvertent ESFAS actuation RELATED PRA INFORMATION Not required for exam SAFETY FUNCTION: 2 EVALUATION LOCATION: In-Plant Simulator Control Room Lab Other - List:

APPLICABLE METHOD OF TESTING: Discussion Simulate/Walkthrough Perform TIME FOR COMPLETION: 10 minutes TIME CRITICAL (Y/N) N ALTERNATE PATH (Y/N) Y Developed by: Aaron Forsha 8/26/19 Developer Date (Ensure validator is briefed on exam security per NPG-SPP-17.8.1)

(See JPM Validation Checklist in NPG-SPP-17.8.2)

Validated by: Ted Doukas 11/18/19 Validator Date Approved by: Aaron Forsha 11/18/19 Site Training Management Date Approved by: Terry Dunny 11/18/19 Site Training Program Owner Date Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 1 of 12 [08-08-2014]

JPM-E-0 [02], Rev 41 SPECIAL INSTRUCTIONS:

1. Ensure Simulator Operator Checklist is complete

2. Reset to IC 274 password: tdfun IMF RP04B ZDIHS6325A f:1 ZDIHS6339A f:1

3. PLACE SIMULATOR IN RUN

4. Place MODE 1 sign on the simulator

5. An extra operator will be required to acknowledge alarms and monitor secondary plant.

6. ACKNOWLEDGE ALARMS

7. FREEZE SIMULATOR

8. After JPM is complete,

IF this JPM is to be ran again ENSURE recorders have been cleared.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 2 of 12 [08-08-2014]

JPM-E-0 [02], Rev 41 JPM Briefing from NPG-SPP-17.8.2 completed? Yes If no, perform briefing prior to continuing.

Initial Conditions As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

(REMEMBER TO VERIFY STUDENT SHEET HAS THIS SAME INFORMATION)

INITIAL CONDITIONS:

1. Unit 1 is in MODE 3 following a spurious Safety Injection.

2. The crew completed E-0, REACTOR TRIP OR SAFETY INJECTION through step 13.

INITIATING CUES (IF APPLICABLE):

1. The US has directed you perform E-0, REACTOR TRIP OR SAFETY INJECTION starting at step 14.

2. Inform the US when charging flow and seal injection flow have been established.

NOTE: Another operator is available to acknowledge alarms not associated with your task.

This JPM is a "time critical" JPM.

This JPM is not a "time critical" JPM.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 3 of 12 [08-08-2014]

JPM-E-0 [02], Rev 41 Required Materials: Copy of E-0, REACTOR TRIP OR SAFETY INJECTION, marked up to step 14.

References:

E-0, REACTOR TRIP OR SAFETY INJECTION , Rev 41 Operator begins to terminate SI flow and stops one charging pump. Then during isolating the CCPIT, two of four CCPIT valves will not close requiring the operator Task Standards:

to go to Appendix D of E-0. Operator secures all Charging and RCPs per Appendix D.

NOTE:

When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

IMPORTANT:

Critical steps are marked with a Y below the Performance Step number field. Failure to meet the standard for any critical step shall result in failure of this JPM.

Start Time:

Step # 1. Performance step:

Critical Step?

14. RESET SI signal.

Y Standard: Operator depresses SI Reset pushbuttons.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Candidate may elect to address seal flow alarm.

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 4 of 12 [08-08-2014]

JPM-E-0 [02], Rev 41 Step # 2. Performance step:

Critical Step?

15. MONITOR shutdown boards continuously energized.

N Standard: Operator observes Shutdown Boards energized.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 3. Performance step:

Critical Step? 16. ENSURE only one CCP RUNNING:

a. CHECK offsite power supplying shutdown boards.

Y

b. STOP all BUT one CCP and PLACE in A-AUTO.

Standard: Operator places ONE Charging Pump in STOP.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 5 of 12 [08-08-2014]

JPM-E-0 [02], Rev 41 Step # 4. Performance step:

Critical Step?

17. CHECK RCS pressure STABLE or RISING.

N Operator verifies RCS pressure stable or rising by observing installed Standard:

instrumentation.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 5. Performance step:

Critical Step? BEGIN ALT PATH

18. ISOLATE CCPIT:

N a. CLOSE CCPIT inlet valves FCV-63-39 and FCV-63-40.

b. CLOSE CCPIT outlet valves FCV-63-25 and FCV-63-26.

Operator attempts to close CCPIT inlet valves FCV-63-39 AND FCV-63-40 Standard: Operator attempts to close CCPIT outlet valves FCV-63-25 AND FCV-63-26 Performance: SATISFACTORY UNSATISFACTORY BOLDED valves will not close, others valves do close but are not enough to complete Examiner Notes:

the isolation Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 6 of 12 [08-08-2014]

JPM-E-0 [02], Rev 41 Step # 6. Performance step:

Critical Step? 18. ISOLATE CCPIT:

c. CHECK CCPIT flow isolated:

N

FCV-63-39 and -40 CLOSED OR

FCV-63-25 and -26 CLOSED Standard: Operator observes CCPIT is NOT isolated goes to RNO Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 7. Performance step:

Critical Step? RNO

c. PERFORM the following:

1) IF CCPIT flow CANNOT be isolated from MCR, N THEN PERFORM Appendix D, Contingency Actions for Terminating CCPIT Flow.

Standard:

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 7 of 12 [08-08-2014]

JPM-E-0 [02], Rev 41 Step # 8. Performance step:

Critical Step? Appendix D Contingency Actions for Terminating CCPIT Flow 1.0 ACTIONS

1. DISPATCH personnel to close affected CCPIT valves N USING EA-201-3, Operation of Motor-Operated Valves from Outside MCR.

Standard: Contact AUO to close FCV-63-39 and FCV-63-25 locally using EA-201-3 Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Another operator will dispatch AUOs to perform EA-201-3.

Cue:

Time compressed. FCV-63-39 and FCV-63-25 are NOT able to be closed.

Comments:

Step # 9. Performance step:

Critical Step? CAUTION If RCP thermal barrier cooling is lost after CCP is stopped, RCP seals will overheat rapidly. Prompt action is required to restore seal injection flow to avoid damage to RCP seals.

N 2. IF all of the following conditions are met prior to CCPIT isolation:

thermal barrier cooling is in service to RCP seals

pressurizer level is greater than 80%

RCS subcooling greater than 40°F, Operator checks all conditions are met, thermal barrier cooling, PZR level, and Standard:

Sub Cooling Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 8 of 12 [08-08-2014]

JPM-E-0 [02], Rev 41 Step # 10. Performance step:

Critical Step? THEN PERFORM the following:

a. ENSURE CCPs in PULL TO LOCK.

b. IF any CCP CANNOT be stopped from MCR, Y THEN DISPATCH operator to locally stop affected CCP USING EA-202-2, Operating Equipment from 6.9KV Shutdown Board.

Standard: Operator places BOTH Charging pumps in PULL TO LOCK Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 11. Performance step:

Critical Step? c. STOP RCPs.

d. IF any RCP CANNOT be stopped from MCR, Y THEN PERFORM Appendix E, Contingency Actions for RCP Trip Failure.

Standard: All four RCPs are STOPPED Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 9 of 12 [08-08-2014]

JPM-E-0 [02], Rev 41 Terminating Cue: Provide the following cue, Another operator will complete the remaining steps of this procedure.

Stop Time:

Operator Fundamental evaluated:

Historical Record:

Rev 40 Modified JPM from E-0 [01]

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 10 of 12 [08-08-2014]

JPM-E-0 [02], Rev 41 JPM DATA SHEET EXAMINEES NAME: EIN:

EVALUATORS NAME: DATE:

JPM Title JPM-E-0 [02], Terminate Safety Injection Start Time Finish Time Performance Time PERFORMANCE RESULTS: SAT UNSAT COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory)

Evaluators Signature:

Date NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

[08-08-2014]

TURNOVER SHEET As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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:

1. Unit 1 is in MODE 3 following a spurious Safety Injection

2. The crew completed E-0, REACTOR TRIP OR SAFETY INJECTION through step 13.

INITIATING CUES (IF APPLICABLE):

1. The US has directed you perform E-0, REACTOR TRIP OR SAFETY INJECTION starting at step 14.

2. Inform the US when charging flow and seal injection flow have been established.

NOTE: Another operator is available to acknowledge alarms not associated with your task.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

SITE: SQN JPM TITLE Reduce RCS pressure during E-3 SGTR JPM NUMBER JPM-E-3[01] REVISION: 26 TASK APPLICABILITY: SRO STA UO NAUO TASK NUMBERS / TASK TITLE(S)

K/A RATINGS 010 A2.03 (4.1/4.2)

Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, K/A STATEMENT or mitigate the consequences of those malfunctions or operations: PORV failures RELATED PRA INFORMATION Not required SAFETY FUNCTION: 3 EVALUATION LOCATION: In-Plant Simulator Control Room Lab Other - List:

APPLICABLE METHOD OF TESTING: Discussion Simulate/Walkthrough Perform TIME FOR COMPLETION: 5 minutes TIME CRITICAL (Y/N) N ALTERNATE PATH (Y/N) Y Developed by: Aaron Forsha 8/26/19 Developer Date (Ensure validator is briefed on exam security per NPG-SPP-17.8.1)

(See JPM Validation Checklist in NPG-SPP-17.8.2)

Validated by: Ted Doukas 11/18/19 Validator Date Approved by: Aaron Forsha 11/18/19 Site Training Management Date Approved by: Terry Dunny 11/18/19 Site Training Program Owner Date Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 1 of 9 [08-08-2014]

JPM-E-3 [01], Rev 26 SPECIAL INSTRUCTIONS:

1. Ensure Simulator Operator Checklist is complete

2. Reset to IC 279 password: sock

{zdihs68334a[1]} IMF RC05 f:100 When Porv 334a opens, it fails open

{zdihs68340aa[1]} IMF RC14 f:100 When Porv 340aa opens, it fails open

3. PLACE SIMULATOR IN RUN

4. Place MODE 1 sign on the simulator

5. An extra operator will be required to acknowledge alarms and monitor secondary plant.

6. ACKNOWLEDGE ALARMS

7. FREEZE SIMULATOR

8. After JPM is complete,

IF this JPM is to be ran again ENSURE recorders have been cleared.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 2 of 9 [08-08-2014]

JPM-E-3 [01], Rev 26 JPM Briefing from NPG-SPP-17.8.2 completed? Yes If no, perform briefing prior to continuing.

Initial Conditions As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

(REMEMBER TO VERIFY STUDENT SHEET HAS THIS SAME INFORMATION)

INITIAL CONDITIONS:

1. Unit 1 is performing E-3 Steam Generator Tube Rupture.

2. #1 Steam Generator is ruptured.

3. Normal Pressurizer spray is NOT available.

INITIATING CUES (IF APPLICABLE):

1. The US has directed you to reduce RCS pressure per step 20 of E-3 This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 3 of 9 [08-08-2014]

JPM-E-3 [01], Rev 26 Required Materials: Provide Pages 26-36 of E-3

References:

1. E-3 Steam Generator Tube Rupture Operator initiates RCS pressure reduction with one PORV. When reduction is Task Standards: complete, PORV will not close requiring the operator to close the associated BLOCK valve prior to PRT rupture.

NOTE:

When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

IMPORTANT:

Critical steps are marked with a Y below the Performance Step number field. Failure to meet the standard for any critical step shall result in failure of this JPM.

Start Time:

Step # 1. Performance step:

Critical Step? 20. REDUCE RCS pressure USING one pzr PORV to minimize break flow and restore pzr level:

N

a. CHECK at least one pzr PORV AVAILABLE Standard: Operator observes PORV indications Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 4 of 9 [08-08-2014]

JPM-E-3 [01], Rev 26 Step # 2. Performance step:

Critical Step?

b. OPEN one pzr PORV Y

Operator selects one of the PORV valves and rotates control switch to the open Standard:

position Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 3. Performance step:

Critical Step? UNTIL any of the following conditions (listed in Appendix A)

BOTH of the following:

1) RCS pressure less than Ruptured S/G(s) pressure N 2) Pzr level greater than 10% [20% ADV]

Pzr level greater than 65%.

RCS subcooling based on core exit T/Cs less than 40°F.

Standard: Operator monitors parameters until an action to secure is required Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 5 of 9 [08-08-2014]

JPM-E-3 [01], Rev 26 Step # 4. Performance step:

Critical Step? BEGIN ALT PATH N c. CLOSE pressurizer PORV.

Standard: Operator rotates PORV switch from Open to PAuto Performance: SATISFACTORY UNSATISFACTORY Valve should close in PAuto based on plant conditions but it is failed open. Operator Examiner Notes: may elect to take switch to Close but this will not work as the valve is failed mechanically.

Cue:

Comments:

Step # 5. Performance step:

Critical Step?

RNO Y c. CLOSE block valve.

Standard: Operator rotates block valve switch to Close prior to PRT rupture.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Terminating Cue: Another operator will complete the remaining steps of this procedure.

Stop Time:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 6 of 9 [08-08-2014]

JPM-E-3 [01], Rev 26 Operator Fundamental evaluated:

Historical Record:

Rev 26 New JPM Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 7 of 9 [08-08-2014]

JPM-E-3 [01], Rev 26 JPM DATA SHEET EXAMINEES NAME: EIN:

EVALUATORS NAME: DATE:

JPM Title JPM-E-3[01], Reduce RCS pressure during E-3 SGTR Start Time Finish Time Performance Time PERFORMANCE RESULTS: SAT UNSAT COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory)

Evaluators Signature:

Date NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

[08-08-2014]

TURNOVER SHEET As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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:

1. Unit 1 is performing E-3 Steam Generator Tube Rupture.

2. #1 Steam Generator is ruptured.

3. Normal Pressurizer spray is NOT available.

INITIATING CUES (IF APPLICABLE):

1. The US has directed you to reduce RCS pressure per step 20 of E-3 This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

SITE: SQN JPM TITLE Start a Reactor Coolant Pump JPM-1-SO-JPM NUMBER 68-2 [01] REVISION: 43 TASK APPLICABILITY: SRO STA UO NAUO TASK NUMBERS / TASK TITLE(S) 0030010101 K/A RATINGS (3.4/3.5) 003.A1.05 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCPS controls including:

K/A STATEMENT RCS flow RELATED PRA INFORMATION Not required for exam.

SAFETY FUNCTION: 4P EVALUATION LOCATION: In-Plant Simulator Control Room Lab Other - List:

APPLICABLE METHOD OF TESTING: Discussion Simulate/Walkthrough Perform TIME FOR COMPLETION: 10 minutes TIME CRITICAL (Y/N) N ALTERNATE PATH (Y/N) N Developed by: Aaron Forsha 9/14/17 Developer Date (Ensure validator is briefed on exam security per NPG-SPP-17.8.1)

(See JPM Validation Checklist in NPG-SPP-17.8.2)

Validated by: Frank Schulte 9/4/17 Validator Date Approved by: Aaron Forsha 9/4/17 Site Training Management Date Approved by: David Neff 9/4/17 Site Training Program Owner Date Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 1 of 11 [08-08-2014]

JPM-1-SO-68-2 [01], Rev 43 SPECIAL INSTRUCTIONS:

1. Ensure Simulator Operator Checklist is complete

2. Initialize to IC 268

3. IF IC 268 is not available Then initialize to IC 7 and perform the following

4. Stop the #1 RCP.

5. Place MODE 3 sign on Panel M-4

6. Insert AN_OV_359 to OFF (Disables Loose Parts Alarm.)

7. Close the Loop 1 Pressurizer Spray valve

8. Set NR-45 to display one SRM and one IRM

9. An extra operator will be required to acknowledge alarms.

10. ACKNOWLEDGE ALARMS

11. FREEZE SIMULATOR.

12. Provide a marked up procedure 1-SO-68-2, Reactor Coolant Pumps Section 5.1 completed through step 10.

13. PLACE SIMULATOR IN RUN Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 2 of 11 [08-08-2014]

JPM-1-SO-68-2 [01], Rev 43 JPM Briefing from NPG-SPP-17.8.2 completed? Yes If no, perform briefing prior to continuing.

Initial Conditions As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

(REMEMBER TO VERIFY STUDENT SHEET HAS THIS SAME INFORMATION)

INITIAL CONDITIONS:

1. Unit 1 is in MODE 3.

2. #1 RCP startup is in progress.

3. All precautions and prerequisites are complete.

4. 1-SO-68-2 Section 5.1, steps 1 through 10 are complete.

5. All other RCPs are in service.

INITIATING CUES:

1. You have been directed to start and monitor the #1 RCP using 1-SO-68-2, Reactor Coolant Pumps starting at step 5.1.11.

2. Notify the US when you are complete.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 3 of 11 [08-08-2014]

JPM-1-SO-68-2 [01], Rev 43 This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 4 of 11 [08-08-2014]

JPM-1-SO-68-2 [01], Rev 43 1-SO-68-2 Reactor Coolant Pumps marked up copy Required Materials:

1-SO-68-2 Attachment 6, RCP Operational Parameters

References:

1-SO-68-2 Reactor Coolant Pumps Task Standards: The Operator manually starts the #1 Reactor Coolant Pump.

NOTE:

When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

IMPORTANT:

Critical steps are marked with a Y below the Performance Step number field. Failure to meet the standard for any critical step shall result in failure of this JPM.

Start Time:

Step # 1. Performance step:

Critical Step? [11] PLACE 1-HS-68-84A, No.1 RCP Lift Oil Pump in the START Y position.

Standard: Examinee places hand switch 1-HS-68-84A #1 RCP Lift Oil Pump to START.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 5 of 11 [08-08-2014]

JPM-1-SO-68-2 [01], Rev 43 Step # 2. Performance step:

Critical Step? [12] WHEN Lift Oil Pump for No.1 RCP has run greater than or equal to 2 minutes, THEN N ANNOUNCE No.1 RCP start on the P/A system.

Standard: Examinee addresses the procedure step.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: Provide the following cue, Another operator will make the PA Announcement.

Comments:

Step # 3. Performance step:

Critical Step? [13] IF NO RCPs are running AND RCP No.1 is the first RCP to be started, THEN N MONITOR the SRMs during startup of the RCP. [C.3]

Standard: Examinee determines other 3 RCPs are running and marks this step as N/A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 6 of 11 [08-08-2014]

JPM-1-SO-68-2 [01], Rev 43 Step # 4. Performance step:

Critical Step?

[14] PLACE 1-HS-68-8A, No.1 RCP in the START position.

Y Standard: Examinee places 1-HS-68-8A #1 RCP to START.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 5. Performance step:

Critical Step?

[15] ENSURE No.1 RCP motor and pump are operating within the N parameters listed in Attachment 6 Standard: Examinee monitors #1 RCP motor and pump to verify all parameters are normal.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 7 of 11 [08-08-2014]

JPM-1-SO-68-2 [01], Rev 43 Step # 6. Performance step:

Critical Step?

[16] ENSURE 1-TCV-67-86, RCP Motor Cooler 1A is OPEN N (1-HS-67-86 red light illuminated).

Examinee verifies 1-TCV-67-86 is open on Panel M-27A by observing the red Standard:

indicating light above handswitch ON.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 7. Performance step:

Critical Step? [17] WHEN Lift Oil Pump has run greater than 1 minute after RCP start, THEN N PLACE 1-HS-68-84A, No.1 RCP Lift Oil Pump in the STOP position.

Standard: Examinee places 1-HS-68-84A #1 RCP Lift Oil Pump handswitch to STOP Performance:

Examiner Notes:

Cue: Time Compressed. Lift Pump has been running for greater than 1 minute.

Comments:

Terminating Cue: Provide the following cue, another operator will complete the remaining steps of this procedure.

Stop Time:

Operator Fundamental evaluated:

Historical Record:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 8 of 11 [08-08-2014]

JPM-1-SO-68-2 [01], Rev 43 Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 9 of 11 [08-08-2014]

JPM-1-SO-68-2 [01], Rev 43 JPM DATA SHEET EXAMINEES NAME: EIN:

EVALUATORS NAME: DATE:

JPM Title Start a RCP Start Time Finish Time Performance Time PERFORMANCE RESULTS: SAT UNSAT COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory)

Evaluators Signature:

Date NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

[08-08-2014]

TURNOVER SHEET As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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:

1. Unit 1 is in MODE 3

2. #1 RCP startup is in progress.

3. All precautions and prerequisites are complete.

4. 1-SO-68-2 Section 5.1, steps 1 through 10 are complete.

5. All other RCPs are in service INITIATING CUES:

1. You have been directed to start and monitor the #1 RCP using 1-SO-68-2, Reactor Coolant Pumps starting at step 5.1.11.

2. Notify the US when you are complete.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

SITE: SQN JPM TITLE Synchronize the Main Generator to the Grid JPM-0-GO-JPM NUMBER 4 [03] REVISION: 103 TASK APPLICABILITY: SRO STA UO NAUO TASK NUMBERS / TASK TITLE(S) 0450970101 K/A RATINGS 045 A4.02 (2.7/2.6)

Ability to manually operate and/or monitor in the control room: T/G controls, K/A STATEMENT including breakers RELATED PRA INFORMATION Not required for exam.

SAFETY FUNCTION: 4S EVALUATION LOCATION: In-Plant Simulator Control Room Lab Other - List:

APPLICABLE METHOD OF TESTING: Discussion Simulate/Walkthrough Perform TIME FOR COMPLETION: 10 minutes TIME CRITICAL (Y/N) N ALTERNATE PATH (Y/N) N Developed by: Max Hime (Signature on file) 11/6/17 Developer Date (Ensure validator is briefed on exam security per NPG-SPP-17.8.1)

(See JPM Validation Checklist in NPG-SPP-17.8.2)

Validated by: J. Alexander 9/3/17 Validator Date Approved by: Jeremy Bailey (Signature on file) 11/29/17 Site Training Management Date Approved by: David Neff (Signature on file) 11/20/17 Site Training Program Owner Date Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 1 of 12 [08-08-2014]

JPM-0-GO-4 [01], Rev 103 SPECIAL INSTRUCTIONS:

1. Ensure Simulator Operator Checklist is complete

2. Reset to IC 272 password: brutus

3. PLACE SIMULATOR IN RUN

4. Place MODE 1 sign on the simulator

5. An extra operator will be required to acknowledge alarms and monitor control board.

6. ACKNOWLEDGE ALARMS

7. FREEZE SIMULATOR

8. After JPM is complete,

IF this JPM is to be ran again ENSURE recorders have been cleared.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 2 of 12 [08-08-2014]

JPM-0-GO-4 [01], Rev 103 JPM Briefing from NPG-SPP-17.8.2 completed? Yes If no, perform briefing prior to continuing.

Initial Conditions As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

(REMEMBER TO VERIFY STUDENT SHEET HAS THIS SAME INFORMATION)

INITIAL CONDITIONS:

1. Unit 1 is in MODE 1.

2. 0-GO-4 POWER ASCENSION FROM LESS THAN 5% REACTOR POWER TO 30%

REACTOR POWER section 5.4 is in progress complete up to step 27.

3. TR-47-1 (pt. #1, IMPULSE CHMBR METAL) from step 5.3[32.1] is 125°F and time to hold is 33 minutes per TI-28 Attachment 15.

INITIATING CUES (IF APPLICABLE):

1. The SRO has directed you to synchronize the Main generator and raise load to 30 to 60 MW using 0-GO-4 POWER ASCENSION FROM LESS THAN 5% REACTOR POWER TO 30%

REACTOR POWER section 5.4 starting at step 27.

2. Auto operation of the generator voltage regulator is desired.

3. Inform the SRO when complete.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 3 of 12 [08-08-2014]

JPM-0-GO-4 [01], Rev 103

- Marked up copy of 0-GO-4 to Section 5.4, step 27 Required Materials:

1. 0-GO-4, POWER ASCENSION FROM LESS THAN 5% REACTOR

References:

POWER TO 30% REACTOR POWER, Rev 100 Task Standards: Operator will Sync the Main Generator to the grid.

NOTE:

When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

IMPORTANT:

Critical steps are marked with a Y below the Performance Step number field. Failure to meet the standard for any critical step shall result in failure of this JPM.

Start Time:

Step # 1. Performance step:

[27] IF AUTO operation of generator voltage regulator is desired, THEN Critical Step?

PERFORM the following:

[27.1] MONITOR EI-57-15, Generator Volts [M-1]

N [27.2] ENSURE AVR in AUTO using HS-57-20, Regulator Transfer Sw, with blue light LIT.

Standard: Operator monitors Volts while energizing the regulator and ensures blue light LIT.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 4 of 12 [08-08-2014]

JPM-0-GO-4 [01], Rev 103 Step # 2. Performance step:

Critical Step?

[27.3] PLACE HS-57-110, Synchronization Switch to the Sync Check Intlk ENABLE position.

Y Standard: Examinee places [HS-57-110] to the ENABLE position.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 3. Performance step:

Critical Step?

[27.4] MOMENTARILY PLACE (spring return) HS-57-19, Excitation Cont Sw, to START AND CHECK red light LIT.

Y Standard: Examinee places [HS-57-19] to START and releases observing the red light lit.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 5 of 12 [08-08-2014]

JPM-0-GO-4 [01], Rev 103 Step # 4. Performance step:

[27.5] CHECK Generator Voltage rises to between 22.8kv and 24.8kv on EI-57-15.

Critical Step?

[27.6] CHECK EI-57-15 generator voltage on all three phases between 22.8kv and 24.8kv using XS-57-15 Generator Volts.

[28] CHECK annunciator XA-55-1A, window A-5: EXCITATION SYSTEM N ABNORMAL is DARK.

[29] CHECK annunciator XA-55-1A, window A-6: EXCITATION SYSTEM MALFUNTION is DARK.

Examinee checks voltage of all three phases between 22.8kv- 24.8kv and Checks A-Standard:

5, A-6 windows dark.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 5. Performance step:

[30] PERFORM the following to synchronize the generator with the grid:

Critical Step?

[30.1] DEPRESS turbine control panel pushbutton OPER AUTO SYNC, AND Y

CHECK pushbutton LIT.

Examinee DEPRESS turbine control panel pushbutton [OPER AUTO SYNC] and Standard:

observes pushbutton LIT.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 6 of 12 [08-08-2014]

JPM-0-GO-4 [01], Rev 103 Step # 6. Performance step:

Critical Step?

[30.2] ADJUST HS-57-21 GEN SPEED CONTROL to obtain desired speed on 1(2)-

XI-57-1 rotating slowly in the fast (clockwise) direction.

Y Examinee adjusts [HS-57-21] GEN SPEED CONTROL to obtain desired speed on Standard:

[XI-57-1] rotating slowly in the fast (clockwise) direction.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 7. Performance step:

Critical Step?

[30.3] ENSURE Generator Circuit Breaker annunciators and alarms are clear on XA-55-1A.

N Standard: Operator checks alarm is clear Performance:

Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 7 of 12 [08-08-2014]

JPM-0-GO-4 [01], Rev 103 Step # 8. Performance step:

Critical Step?

[30.4] ADJUST HS-57-22 Voltage Control Switch, to establish EI-57-2 incoming voltage slightly higher than EI-57-3 running voltage.

Y Operator raises voltage to establish slightly higher voltage using HS-57-22 in raise Standard:

direction Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 9. Performance step:

[30.5] RECORD the first stage metal temperature obtained Critical Step?

from TR-47-1 (pt. #1, IMPULSE CHMBR METAL) from step 5.3[32.1]. ___________ºF

[30.6] DETERMINE time to hold at 5% turbine load on TI-28 N

Attachment 15 and record minutes.

____________ minutes Standard: Operator records data from cue sheet Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 8 of 12 [08-08-2014]

JPM-0-GO-4 [01], Rev 103 Step # 10. Performance step:

[30.7] CLOSE Generator Circuit Breaker by performing the Critical Step?

following steps:

N A. CHECK GCB Disconnect 1(2)-MOD-57-313 (323) is CLOSED.

Standard: Operator checks disconnect is closed Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: 1-MOD-57-313 handswitch and indication are located on 1-M-1 (1-HS-57-111)

Cue:

Comments:

Step # 11. Performance step:

Critical Step?

B. ENSURE HS-57-110, Synchronization Switch is in the SYNC CHK INTLK ENABLE position.

N Standard: Operator checks Sync Check is in Enable Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 9 of 12 [08-08-2014]

JPM-0-GO-4 [01], Rev 103 Step # 12. Performance step:

Critical Step?

C. WHEN synchroscope reaches 5-10 minutes before the 12:00 position (the needle is at the O in the word SLOW), THEN Y

CLOSE Generator Circuit Breaker with HS-57-109.

Operator Closes Breaker at 5-10 min before 12:00 position and observes breaker Standard:

closing Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

If breaker fails to close and applicant requests Maintenance/MEG investigate Cue:

THEN respond The Sync Check Relay is working correctly Comments:

Terminating Cue: Provide the following cue: Another operator will complete the remaining steps of this procedure.

Stop Time:

Operator Fundamental evaluated:

Historical Record:

Rev 96 Converted JPM into current template and verified against latest procedure revisions.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 10 of 12 [08-08-2014]

JPM-0-GO-4 [01], Rev 103 JPM DATA SHEET EXAMINEES NAME: EIN:

EVALUATORS NAME: DATE:

JPM Title JPM-0-GO-4 [01], Synchronize the Main Generator to the Grid Start Time Finish Time Performance Time PERFORMANCE RESULTS: SAT UNSAT COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory)

Evaluators Signature:

Date NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

[08-08-2014]

TURNOVER SHEET As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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:

1. Unit 1 is in MODE 1.

2. 0-GO-4 POWER ASCENSION FROM LESS THAN 5% REACTOR POWER TO 30% REACTOR POWER section 5.4 is in progress complete up to step 27.

3. TR-47-1 (pt. #1, IMPULSE CHMBR METAL) from step 5.3[32.1] is 125°F and time to hold is 33 minutes per TI-28 Attachment 15.

INITIATING CUES (IF APPLICABLE):

1. The SRO has directed you to synchronize the Main generator and raise load to 30 to 60 MW using 0-GO-4 POWER ASCENSION FROM LESS THAN 5% REACTOR POWER TO 30%

REACTOR POWER section 5.4 starting at step 27.

2. Auto operation of the generator voltage regulator is desired.

3. Inform the SRO when complete.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

SITE: SQN JPM TITLE Phase A faulted lineup JPM NUMBER ES-0.5 [01] REVISION: 13 TASK APPLICABILITY: SRO STA UO NAUO TASK NUMBERS / TASK TITLE(S) 0130020101 K/A RATINGS 3.9/4.2 103 A3.01 Ability to monitor automatic operation of the containment K/A STATEMENT system, including: Containment isolation RELATED PRA INFORMATION Not required for exam.

SAFETY FUNCTION: 5 EVALUATION LOCATION: In-Plant Simulator Control Room Lab Other - List:

APPLICABLE METHOD OF TESTING: Discussion Simulate/Walkthrough Perform TIME FOR COMPLETION: 10 minutes TIME CRITICAL (Y/N) N ALTERNATE PATH (Y/N) Y Developed by: Aaron Forsha 11/19/19 Developer Date (Ensure validator is briefed on exam security per NPG-SPP-17.8.1)

(See JPM Validation Checklist in NPG-SPP-17.8.2)

Validated by: Don Boyles 11/21/19 Validator Date Approved by: Aaron Forsha 11/21/19 Site Training Management Date Approved by: Terry Dunny 11/21/19 Site Training Program Owner Date Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 1 of 13 [08-08-2014]

JPM-ES-0.5 [01] Rev 13 SPECIAL INSTRUCTIONS:

1. Ensure Simulator Operator Checklist is complete

2. Reset to IC 293 password: zdihshell

3. PLACE SIMULATOR IN RUN

4. Place MODE 1 sign on the simulator

5. An extra operator will be required to acknowledge alarms and monitor SGWL.

6. ACKNOWLEDGE ALARMS

7. FREEZE SIMULATOR

8. PLACE SIMULATOR IN RUN, when JPM begins

9. After JPM is complete,

IF this JPM is to be ran again ENSURE recorders have been cleared.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 2 of 13 [08-08-2014]

JPM-ES-0.5 [01] Rev 13 JPM Briefing from NPG-SPP-17.8.2 completed? Yes If no, perform briefing prior to continuing.

Initial Conditions As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

(REMEMBER TO VERIFY STUDENT SHEET HAS THIS SAME INFORMATION)

INITIAL CONDITIONS:

1. Unit 1 is performing E-0 Reactor Trip and Safety Injection INITIATING CUES (IF APPLICABLE):

1. The SRO has directed you to continue the in progress ES-0.5, Equipment Checks beginning at Step 13 NOTE: Another operator is available to acknowledge alarms not associated with your task.

This JPM is a "time critical" JPM.

This JPM is not a "time critical" JPM.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 3 of 13 [08-08-2014]

JPM-ES-0.5 [01] Rev 13 Required Materials: Marked up Copy of ES 0.5

References:

1. ES-0.5 Equipment Checks Operator will recognize Phase A isolation is not complete; identify and close the Task Standards:

remaining two components manually to complete Phase A Containment Isolation NOTE:

When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

IMPORTANT:

Critical steps are marked with a Y below the Performance Step number field. Failure to meet the standard for any critical step shall result in failure of this JPM.

Start Time:

Step # 1. Performance step:

Critical Step? 13. CHECK ECCS operation:

a. CHECK ECCS pumps RUNNING:

N

CCPs

RHR pumps

SI pumps.

Standard: Operator Checks pumps running Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 4 of 13 [08-08-2014]

JPM-ES-0.5 [01] Rev 13 Step # 2. Performance step:

Critical Step?

b. CHECK CCPIT flow established.

N Standard: Operator Observes CCPIT valves open Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 3. Performance step:

Critical Step? c. CHECK RCS pressure less than 1650 psig.

N RNO GO TO step 14 Standard: Operator Observes Pressure is greater than 1650 and goes to step 14 Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 5 of 13 [08-08-2014]

JPM-ES-0.5 [01] Rev 13 Step # 4. Performance step:

14. CHECK ESF systems ALIGNED:

Critical Step?

a. Phase A ACTUATED:

PHASE A TRAIN A alarm N LIT [M-6C, window B5]

PHASE A TRAIN B alarm LIT [M-6C, window B6].

Standard: Operator observes alarm windows DARK and goes to RNO Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 5. Performance step:

Step 14 RNO Critical Step?

a. ACTUATE PHASE A AND CNTMT Y

VENT ISOL switches HS-30-63A and HS-30-63B.

Operator rotates HSs30-63B and 30-63A to actuate PHASE A and CNTMT VENT Standard:

isolation. Operator determines valves actuate but NOT all release paths are isolated.

Performance: SATISFACTORY UNSATISFACTORY Begin ALT Path: Phase A Hand switch is ineffective, actions to address this begin at Examiner Notes:

step f.

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 6 of 13 [08-08-2014]

JPM-ES-0.5 [01] Rev 13 Step # 6. Performance step:

Critical Step? b. Cntmt Vent Isolation ACTUATED:

CNTMT VENT ISOLATION TRAIN A alarm LIT N [M-6C, window C5]

CNTMT VENT ISOLATION TRAIN B alarm LIT

[M-6C, window C6].

Standard: Operator observes both windows LIT Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 7 of 13 [08-08-2014]

JPM-ES-0.5 [01] Rev 13 Step # 7. Performance step:

Critical Step? c. Aux Bldg Isolation ACTUATED:

AUX BUILDING ISOLATION TRAIN A alarm LIT N [M-6C, window D5]

AUX BUILDING ISOLATION TRAIN B alarm LIT

[M-6C, window D6].

Standard: Operator observes both windows LIT Performance:

Examiner Notes:

Cue:

Comments:

Step # 8. Performance step:

Critical Step? d. Control Room Isol ACTUATED:

CONTROL RM ISOLATION TRAIN A alarm LIT N [M-6C, window E5]

CONTROL RM ISOLATION TRAIN B alarm LIT

[M-6C, window E6].

Standard: Operator observes both windows LIT Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 8 of 13 [08-08-2014]

JPM-ES-0.5 [01] Rev 13 Step # 9. Performance step:

Critical Step? e. Status monitor panels:

6C DARK

6D DARK N

6E LIT OUTSIDE outlined area

6H DARK

6J LIT.

Operator observes 6C DARK, 6D DARK, 6E LIT OUTSIDE, outlined area 6H Standard:

DARK, 6J LIT Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 10. Performance step:

Critical Step? f. Train A status panel 6K:

N

CNTMT VENT GREEN

PHASE A GREEN Operator observes:

Standard: CNTMT VENT GREEN PHASE A some RED and goes to RNO Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 9 of 13 [08-08-2014]

JPM-ES-0.5 [01] Rev 13 Step # 11. Performance step:

Step f RNO Critical Step?

f. CLOSE affected valves or dampers (may be performed as time permits if Train B valves closed).

REFER TO applicable attachment as necessary:

N

Attachment 1, Train A Containment Vent Isolation OR

Attachment 2, Phase A Cntmt Isolation Valves (Train A).

Standard: Operator goes to Attachment 2 Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 12. Performance step:

Performance Attachment 2 step:

Phase A Cntmt Isolation Valves (Train A)

Y Standard:

Operator locates and closes FCV-1-14 Performance: SATISFACTORY UNSATISFACTORY Examiner Steps 12/13 of JPM can be done in any order Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 10 of 13 [08-08-2014]

JPM-ES-0.5 [01] Rev 13 Step # 13. Performance step:

Critical Step? Attachment 2 Phase A Cntmt Isolation Valves (Train A)

Y Standard:

Operator locates and closes FCV-61-191 Performance: SATISFACTORY UNSATISFACTORY Examiner Steps 12/13 of JPM can be done in any order Notes:

Cue:

Comments:

Terminating Cue: Provide the following cue: Another operator will complete the remaining steps of this procedure.

Stop Time:

Operator Fundamental evaluated:

Historical Record:

Rev 13 New JPM Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 11 of 13 [08-08-2014]

JPM-ES-0.5 [01] Rev 13 JPM DATA SHEET EXAMINEES NAME: EIN:

EVALUATORS NAME: DATE:

JPM Title JPM-ES-0.5 [01] Equipment Checks Start Time Finish Time Performance Time PERFORMANCE RESULTS: SAT UNSAT COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory)

Evaluators Signature:

Date NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

[08-08-2014]

TURNOVER SHEET As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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:

1. Unit 1 is performing E-0 Reactor Trip and Safety Injection INITIATING CUES (IF APPLICABLE):

1. The SRO has directed you to continue the in progress ES-0.5, Equipment Checks beginning at Step 13 NOTE: Another operator is available to acknowledge alarms not associated with your task.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

SITE: SQN JPM TITLE Transfer 1A-A 6.9 KV SD Bd from Alternate to Normal Supply JPM-0-SO-JPM NUMBER 202-4[03] REVISION: 61 TASK APPLICABILITY: SRO STA UO NAUO TASK NUMBERS / TASK TITLE(S) 0620520201 K/A RATINGS 3.2/3.6 062 A4.07 Ability to manually operate and/or monitor in the control room: Synchronizing and paralleling of different ac supplies (3.1/3.1) 062 A2.12 Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those K/A STATEMENT malfunctions or operations: Restoration of power to a system with a fault on it (3.2/3.6)

RELATED PRA INFORMATION Not required for exam.

SAFETY FUNCTION: 6 EVALUATION LOCATION: In-Plant Simulator Control Room Lab Other - List:

APPLICABLE METHOD OF TESTING: Discussion Simulate/Walkthrough Perform TIME FOR COMPLETION: 7 minutes TIME CRITICAL (Y/N) N ALTERNATE PATH (Y/N) Y Developed by: On File Developer Date (Ensure validator is briefed on exam security per NPG-SPP-17.8.1)

(See JPM Validation Checklist in NPG-SPP-17.8.2)

Validated by: John Alexander 9/13/17 Validator Date Approved by: On File Site Training Management Date Approved by: On File Site Training Program Owner Date Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 1 of 10 [08-08-2014]

JPM-0-SO-202-4[03], Rev 61 SPECIAL INSTRUCTIONS:

1. Ensure Simulator Operator Checklist is complete

2. Reset to IC 266. pw: zlono

3. An extra operator will be required to acknowledge alarms.

4. Place simulator in RUN.

5. Insert AN_OV_325 to ASIS

6. ACKNOWLEDGE ALARMS

7. FREEZE SIMULATOR.

8. Provide a copy of 0-SO-202-4, 6900V Shutdown Boards completed through 8.1.6 step 4.

9. PLACE SIMULATOR IN RUN

10. Recommend placing a chair near the work area to allow for a place to rest procedure.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 2 of 10 [08-08-2014]

JPM-0-SO-202-4[03], Rev 61 JPM Briefing from NPG-SPP-17.8.2 completed? Yes If no, perform briefing prior to continuing.

Initial Conditions As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

(REMEMBER TO VERIFY STUDENT SHEET HAS THIS SAME INFORMATION)

INITIAL CONDITIONS:

1. Units 1 and 2 are in MODE 1.

2. Relay testing has been completed on normal feeder to 1A-A 6.9 Kv Shutdown Board.

3. 1B-B, 2A-A, and 2B-B 6.9kV Shutdown Boards are aligned to Normal Power supply.

4. Loads have been evaluated and aligned as desired for the transfer INITIATING CUES:

1. You have been directed to transfer 1A-A 6.9kV Shutdown Board to Normal Feeder at 0-M-26 using 0-SO-202-4, 6900V Shutdown Boards, Section 8.1.6, starting at step 5.

2. 0-SO-202-4, 6900V Shutdown Boards, Section 4.0 and Section 8.1.1 has been completed.

3. Inform the SRO when complete.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 3 of 10 [08-08-2014]

JPM-0-SO-202-4[03], Rev 61 Required Materials: 0-SO-202-4, 6900V Shutdown Boards marked up copy

References:

0-SO-202-4, 6900V Shutdown Boards Operator will attempt to transfer SDBD 1-A from an alternate to normal supply, during the transfer a fault causes SDBD 1-A to lose power, the DG starts but the output Task Standards: breaker does not close. The operator must recognize BKR 1718 must be opened to allow the DG to align to the SDBD.

NOTE:

When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

IMPORTANT:

Critical steps are marked with a Y below the Performance Step number field. Failure to meet the standard for any critical step shall result in failure of this JPM.

Start Time:

Step # 1. Performance step:

Critical Step? [5] ENSURE [0-XS-82-6A], voltmeter selector switch, in SD Bd.

N 1A position.

Standard: Examinee observes 0-XS-82-6A voltmeter selector switch in the SDBD 1A position.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 4 of 10 [08-08-2014]

JPM-0-SO-202-4[03], Rev 61 Step # 2. Performance step:

Critical Step?

[6] PLACE [1-HS-57-45], 6.9 kV SD Bd. Synchronize Switch, in SYN position for the normal supply breaker 1718.

Y Standard: Examinee places Sync Switch to the SYN position Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Respond to the examinee when asked to provide a concurrent verification, Cue:

Operator concurs.

Comments:

Step # 3. Performance step:

Critical Step?

[7] PLACE AND HOLD 1-HS-57-44B, control switch for 1718, in CLOSE position.

Y Standard: Examinee places 1-HS-57-44B control switch for 1718 to CLOSE and HOLD.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

If mentioned The SRO will address the Tech Specs Cue: Respond to the examinee when asked to provide a concurrent verification, Operator concurs.

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 5 of 10 [08-08-2014]

JPM-0-SO-202-4[03], Rev 61 Step # 4. Performance step:

Critical Step?

[8] PLACE 1-HS-57-41B, control switch for 1716, in TRIP position Y Momentarily.

Examinee places 1-HS-57-41B control switch for 1716 to TRIP.

Standard:

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Begin ALT path Respond to the examinee when asked to provide a concurrent verification, Cue:

Operator concurs.

Comments:

Step # 5. Performance step:

Critical Step? NOTE: Steps 8.1.6[9] & 8.1.6[10] may be marked N/A if breaker does not close.

[9] CHECK breaker 1716 OPEN and breaker 1718 CLOSED.

N [10] CHECK 0-EI-82-6A, SHTDN BD 1A-A voltage, INDICATES normal (6560-7260).

Standard: Examinee observes transfer did not occur Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 6 of 10 [08-08-2014]

JPM-0-SO-202-4[03], Rev 61 Step # 6. Performance step:

Critical Step?

[11] RELEASE 1-HS-57-44B to MID position.

N Standard: Examinee releases 1-HS-57-44B control switch for [1718] to MID position Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 7. Performance step:

Critical Step?

[12] IF transfer does NOT occur OR 6.9KV Shutdown Board 1A-A is de-energized, THEN N PERFORM the following:

[12.1] ENSURE all four diesel Generators have started.

Standard: Examinee Observes DGs running Performance:

Examiner Notes: BEGIN ALT PATH Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 7 of 10 [08-08-2014]

JPM-0-SO-202-4[03], Rev 61 Step # 8. Performance step:

Critical Step?

[12.2] ENSURE breakers 1718 and 1716 OPEN.

Y Standard: Examinee Opens Breaker 1718 Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 9. Performance step:

Critical Step?

[12.3] ENSURE D/G breaker closes on the de-energized shutdown board.

N Standard: Observes D/G breaker closed Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Terminating Cue: Provide the following cue, another operator will complete the remaining steps of this procedure.

Stop Time:

Operator Fundamental evaluated:

Historical Record:

Rev 1 Converted JPM into current template and verified against latest procedure revisions.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 8 of 10 [08-08-2014]

JPM-0-SO-202-4[03], Rev 61 JPM DATA SHEET EXAMINEES NAME: EIN:

EVALUATORS NAME: DATE:

JPM Title JPM-0-SO-202-4[03], Transfer 1A-A 6.9 KV SD Bd from Alternate to Normal Supply Start Time Finish Time Performance Time PERFORMANCE RESULTS: SAT UNSAT COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory)

Evaluators Signature:

Date NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

[08-08-2014]

TURNOVER SHEET As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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:

1. Units 1 and 2 are in MODE 1.

2. Relay testing has been completed on normal feeder to 1A-A 6.9 KV Shutdown Board.

3. 1B-B, 2A-A, and 2B-B 6.9kV Shutdown Boards are aligned to Normal Power supply.

4. Loads have been evaluated and aligned as desired for the transfer INITIATING CUES:

1. You have been directed to transfer 1A-A 6.9KV Shutdown Board to Normal Feeder at 0-M-26 using 0-SO-202-4, 6900V Shutdown Boards, Section 8.1.6, starting at step 5.

2. 0-SO-202-4, 6900V Shutdown Boards, Section 4.0 and Section 8.1.1 has been completed.

3. Inform the SRO when complete.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

SITE: SQN JPM TITLE Operate the Feedwater Regulating Valves JPM-1-SO-JPM NUMBER 98-1 [01] REVISION: 13 TASK APPLICABILITY: SRO STA UO NAUO TASK NUMBERS / TASK TITLE(S) 0590050101 K/A RATINGS (3.0/3.1) 016A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the NNIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or K/A STATEMENT operations: Detector failure RELATED PRA INFORMATION Not required for exam.

SAFETY FUNCTION: 7 EVALUATION LOCATION: In-Plant Simulator Control Room Lab Other - List:

APPLICABLE METHOD OF TESTING: Discussion Simulate/Walkthrough Perform TIME FOR COMPLETION: 5 minutes TIME CRITICAL (Y/N) N ALTERNATE PATH (Y/N) N Developed by: Aaron Forsha 9/14/17 Developer Date (Ensure validator is briefed on exam security per NPG-SPP-17.8.1)

(See JPM Validation Checklist in NPG-SPP-17.8.2)

Validated by: Frank Shulte 9/14/17 Validator Date Approved by: Aaron Forsha 9/14/17 Site Training Management Date Approved by: David Neff 9/14/17 Site Training Program Owner Date Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 1 of 13 [08-08-2014]

JPM-1-SO-98-1 [01], Rev 13 SPECIAL INSTRUCTIONS:

1. Ensure Simulator Operator Checklist is complete

2. Any UNSAT requires comments

3. Reset the simulator to IC 333 and place in RUN.

4. Bypass PT-3-1A of MFW pressure control using 1-SO-98-1, Distributed Control System (DCS).

5. Return DCS screen to normal.

6. Acknowledge and clear alarms then FREEZE the simulator until the operator is ready to begin task.

7. An extra operator will be required to acknowledge alarms.

8. A copy of 1-SO-98-1 Section 8.3, Restoring a Channel In Bypass Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 2 of 13 [08-08-2014]

JPM-1-SO-98-1 [01], Rev 13 JPM Briefing from NPG-SPP-17.8.2 completed? Yes If no, perform briefing prior to continuing.

Initial Conditions As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

(REMEMBER TO VERIFY STUDENT SHEET HAS THIS SAME INFORMATION)

INITIAL CONDITIONS:

1. PT-3-1B MFW Pressure is bypassed due to instrument failure

2. PT-3-1A MFW pressure is bypassed for I&C inspection.

3. Inspection complete on PT-3-1A and the channel is ready to be restored.

INITIATING CUES:

1. The US/SRO has directed you to restore PT-3-1A to service using 1-SO-98-1 Section 8.3

2. When the channel has been restored, inform the US.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 3 of 13 [08-08-2014]

JPM-1-SO-98-1 [01], Rev 13 Required Materials: 1-SO-98-1Distributed Control System (DCS)

References:

1. 1-SO-98-1Distributed Control System (DCS)

Task Standards: The directed bypassed channel of MFW pressure input to DCS is restored NOTE:

When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

IMPORTANT:

Critical steps are marked with a Y below the Performance Step number field. Failure to meet the standard for any critical step shall result in failure of this JPM.

Start Time:

Step # 1. Performance step:

Critical Step? 8.3 Restoring a Channel In Bypass N [1] RECORD instrument(s) to be restored.

Standard: Operator records instrument from Cue sheet PT-3-1A Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 4 of 13 [08-08-2014]

JPM-1-SO-98-1 [01], Rev 13 Step # 2. Performance step:

Critical Step?

[2] NOTIFY SRO of instrument(s) to be restored.

N Standard: Operator notifies SRO of restoration Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Cue Acknowledge the report Cue:

Comments:

Step # 3. Performance step:

Critical Step?

N Standard: Operator evaluates this step is NA Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 5 of 13 [08-08-2014]

JPM-1-SO-98-1 [01], Rev 13 Step # 4. Performance step:

Critical Step? [4] IF both channels of steam OR feed flow on one loop are out of service AND N a large percent change in flow has occurred, THEN Standard: Operator evaluates this step is NA Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 5. Performance step:

Critical Step?

[5] SELECT display screen for instrument channel to be restored.

N Standard: Operator using mouse selects screen for PT-3-1 Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 6 of 13 [08-08-2014]

JPM-1-SO-98-1 [01], Rev 13 Step # 6. Performance step:

Critical Step?

[6] SELECT data point for instrument recorded in step 8.3[1].

Y Standard: Operator using mouse selects point for PT-3-1A Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 7 of 13 [08-08-2014]

JPM-1-SO-98-1 [01], Rev 13 Step # 7. Performance step:

Critical Step?

N Standard: Operator compares signals and determines they are not different, PT-3-1(A) and (C)

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 8. Performance step:

Critical Step?

[8] IF redundant instrument loop inputs have differences, THEN N

Operator compares signals and determines they are not different, PT-3-1(A) and (C)

Standard:

and determines this step is NA Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 8 of 13 [08-08-2014]

JPM-1-SO-98-1 [01], Rev 13 Step # 9. Performance step:

Critical Step? [9] IF instrument is displayed with its MAINT BYP SIGNAL button indicating BYPASSED (red), THEN Y [9.1] SELECT MAINT BYP SIGNAL button for instrument loop.

Standard: Using Mouse Operator clicks on MAINT BYP SIGNAL for PT-3-1(A)

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 10. Performance step:

Critical Step?

[9.2] CHECK status color changes from red to gray.

N Standard: Operator checks color changes to grey Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Annunciator 1-XA-55-3B, window D-1 DCS TRANSFER TO MANUAL will clear Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 9 of 13 [08-08-2014]

JPM-1-SO-98-1 [01], Rev 13 Step # 11. Performance step:

Critical Step?

[10] SELECT RESTORE SIGNAL button.

Y Standard: Using mouse Operator clicks on RESTORE SIGNAL for PT-3-1(A)

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 12. Performance step:

Critical Step?

[11] CHECK yellow BYP is NOT displayed above associated instrument N column.

Standard: Operator sees BYP is no longer displayed Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 10 of 13 [08-08-2014]

JPM-1-SO-98-1 [01], Rev 13 Step # 13. Performance step:

Critical Step?

N Standard: Operator determines PT-3-1A is no longer bypassed Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Terminating Cue: Provide the following cue, another operator will complete the remaining steps of this procedure.

Stop Time:

Operator Fundamental evaluated:

Historical Record:

Rev 13 Converted JPM into current template and verified against latest procedure revisions.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 11 of 13 [08-08-2014]

JPM-1-SO-98-1 [01], Rev 13 JPM DATA SHEET EXAMINEES NAME: EIN:

EVALUATORS NAME: DATE:

JPM Title JPM-1-SO-98-1 [01], Operate the Feedwater Regulating Valves Start Time Finish Time Performance Time PERFORMANCE RESULTS: SAT UNSAT COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory)

Evaluators Signature:

Date NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

[08-08-2014]

TURNOVER SHEET As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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:

1. PT-3-1B MFW Pressure is bypassed due to instrument failure

2. PT-3-1A MFW pressure is bypassed for I&C inspection.

3. Inspection complete on PT-3-1A and the channel is ready to be restored.

INITIATING CUES:

1. The US/SRO has directed you to restore PT-3-1(A) to service using 1-SO-98-1 Section 8.3

2. When the channel has been restored, inform the US.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

Uncontrolled Boron Dilution Flowpath Isolation SITE: SQN JPM TITLE (O-SI-OPS-062-214.0)

JPM-0-SI-OPS-062-JPM NUMBER 214.0 [01] REVISION: 5 TASK APPLICABILITY: SRO STA UO NAUO TASK NUMBERS / TASK TITLE(S) 0000220501 Respond to uncontrolled boration / dilution K/A RATINGS 4.2/4.3 K/A STATEMENT 004 A2.06 Inadvertent boration/dilution RELATED PRA INFORMATION Not required for exam.

SAFETY FUNCTION: Not required for exam.

EVALUATION LOCATION: In-Plant Simulator Control Room Lab Other - List:

APPLICABLE METHOD OF TESTING: Discussion Simulate/Walkthrough Perform TIME FOR COMPLETION: 11 minutes TIME CRITICAL (Y/N) N ALTERNATE PATH (Y/N) N Developed by: On File Developer Date (Ensure validator is briefed on exam security per NPG-SPP-17.8.1)

(See JPM Validation Checklist in NPG-SPP-17.8.2)

Validated by: On File Validator Date Approved by: On File Site Training Management Date Approved by: On File Site Training Program Owner Date Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Revision 5 Page 1 of 9 [08-08-2014]

JPM-0-SI-OPS-062-214.0 [01]

JPM Briefing from NPG-SPP-17.8.2 completed? Yes If no, perform briefing prior to continuing.

Initial Conditions As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

(REMEMBER TO VERIFY STUDENT SHEET HAS THIS SAME INFORMATION)

INITIAL CONDITIONS:

1. Unit 1 has been shut down for refueling and is currently in Mode 5.

2. In one hour the reactor vessel head bolts will be detensioned in preparation for pulling the head.

3. All systems required for Mode 6 are operable.

4. 0-SI-OPS-062-214.0, Uncontrolled Boron Dilution Appendix C is in progress and 1-VLV-81-536 has been closed and tagged.

INITIATING CUES (IF APPLICABLE):

1. You are the Unit 1 Auxiliary Bldg AUO and you are to continue the initial performance of 0-SI-OPS-062-214.0, Appendix C.

2. Inform the U1 CRO when Appendix C has been completed.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Revision 5 Page 2 of 9 [08-08-2014]

JPM-0-SI-OPS-062-214.0 [01]

Required Materials: 0-SI-OPS-062-214.0, Uncontrolled Boron Dilution, Rev 5, Appendix C

References:

0-SI-OPS-062-214.0, Uncontrolled Boron Dilution, Rev 5 Operator isolates uncontrolled boron dilution path valves 1-VLV-62-921, Task Standards: 1-VLV-62-914, 1-VLV-62-907, 1-VLV-62-933 and places under administrative controls NOTE:

When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

IMPORTANT:

Critical steps are marked with a Y below the Performance Step number field. Failure to meet the standard for any critical step shall result in failure of this JPM.

Step # 1. Performance step:

Critical Step?

Obtain clearance and cards.

N Standard: Trainee obtains clearance and tags required for the task.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: (Simulate clearance and cards)

Cue: The other operator has provided you with the approved clearance and tags.

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Revision 5 Page 3 of 9 [08-08-2014]

JPM-0-SI-OPS-062-214.0 [01]

Step # 2. Performance step:

Critical Step?

CLOSE and TAG valve 81-536, primary water to containment.

N Standard: Operator reviews completed step.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: At the time of development this valve was in a Contaminated area.

Cue:

Comments:

Step # 3. Performance step:

Critical Step?

CLOSE and TAG VALVE 62-921, primary water to cation bed.

Y Operator locates62-921 (CVCS demin reach rod area), attempts to turn handwheel Standard:

clockwise until snug and hangs tag.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: HW will not turn in the CW direction. Indicator indicates closed. HO is in place.

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Revision 5 Page 4 of 9 [08-08-2014]

JPM-0-SI-OPS-062-214.0 [01]

Step # 4. Performance step:

Critical Step?

CLOSE and TAG valve 62-914, primary water to Mixed Bed Demin B.

Y Operator locates valve 62-914 (CVCS demin reach rod area), attempts to turn Standard:

handwheel clockwise until snug and hangs tag.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: HW will not turn in the CW direction. Indicator indicates closed. HO is in place.

Comments:

Step # 5. Performance step:

Critical Step?

CLOSE and TAG valve 62-907, Primary Water to Mixed Bed Demin A.

Y Operator locates valve 62-907 (CVCS demin reach rod area), attempts to turn Standard:

handwheel clockwise until snug and hangs tag.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: HW turned several times in the CW direction and is now snug. HO is in place.

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Revision 5 Page 5 of 9 [08-08-2014]

JPM-0-SI-OPS-062-214.0 [01]

Step # 6. Performance step:

Critical Step?

CLOSE and TAG valve 62-933, Primary Water to Blender.

Y Operator locates valve 62-933 (690 blender area), turns handwheel clockwise until Standard:

snug and hangs tag.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: HW turned several times in the CW direction and is now snug. HO is in place.

Comments:

Step # 7. Performance step:

Critical Step?

Inform Unit 1 CRO that Appendix C of O-SI-OPS-062-214.0 is complete.

N Standard: Operator informs Unit 1 CRO that Appendix C of 0-SI-OPS-062-214.0 is complete.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: Unit 1 CRO acknowledges communication.

Comments:

Terminating Cue: Unless specified otherwise below, the JPM is terminated when the_____

examinee returns the JPM Briefing sheet to the examiner.________________

Stop Time:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Revision 5 Page 6 of 9 [08-08-2014]

JPM-0-SI-OPS-062-214.0 [01]

Operator Fundamental evaluated:

Historical Record:

Rev 5 Updated to latest procedure revision and converted to the current template.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Revision 5 Page 7 of 9 [08-08-2014]

JPM DATA SHEET EXAMINEES NAME: EIN:

EVALUATORS NAME: DATE:

JPM-0-SI-OPS-062-214.0 [01],Uncontrolled Boron Dilution Flowpath Isolation JPM Title (O-SI-OPS-062-214.0)

Start Time Finish Time Performance Time PERFORMANCE RESULTS: SAT UNSAT COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory)

Evaluators Signature:

Date NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Revision 5 Page 8 of 9 [08-08-2014]

TURNOVER SHEET As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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:

1. Unit 1 has been shutdown for refueling and is currently in Mode 5.

2. In one hour the reactor vessel head bolts will be detensioned in preparation for pulling the head.

3. All systems required for Mode 6 are operable.

4. 0-SI-OPS-062-214.0, Uncontrolled Boron Dilution Appendix C is in progress and 1-VLV-81-536 has been closed and tagged.

INITIATING CUES (IF APPLICABLE):

1. You are the Unit 1 Auxiliary Bldg AUO and you are to continue the initial performance of 0-SI-OPS-062-214.0, Appendix C.

2. Inform the U1 CRO when Appendix C has been completed.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

SQN UNCONTROLLED BORON DILUTION 0-SI-OPS-062-214.0 Unit 1 & 2 Rev. 0005 Page 14 of 15 Appendix C (Page 1 of 1)

DATA SHEET HOLD ORDER NO. 1-62-100 DESCRIPTION LOCATION VALVE NO. POSITION INITIALS Primary Water 690 pipe chase 81-536 Closed &

Valve to in corner behind tagged RO containment CCPIT CAT Bed Demin 690 CVCS62-921 Closed &

Flush demin reach rod tagged ________

area Mix Bed 690 CVCS62-914 Closed &

Demin B Flush demin reach rod tagged ________

area Mix Bed 690 CVCS62-907 Closed &

Demin A Flush demin reach rod tagged ________

area BA Blend PW 690 blender 62-933 Closed &

Supply area near 1-L-43 tagged ________

panel Acceptance Criteria: At least one set of valves listed on Appendix A, B, C, or D Closed and under Administrative hold (SPP-10.2, Clearance Program).

JPM-EA-250-3 [01]

Restore a 125 V Vital Battery Charger I During a Station SITE: SQN JPM TITLE Blackout.

JPM NUMBER JPM-EA-250-3[01] REVISION: 10 TASK APPLICABILITY: SRO STA UO NAUO TASK NUMBERS / TASK TITLE(S) 0630030104 EPE 055 EA1.06 (4.1/4.5)

K/A REF and Ability to operate and monitor the following as they apply to a RATINGS Station Blackout: Restoration of power with one ED/G RELATED PRA INFORMATION Not required for annual exam SAFETY FUNCTION: 6 EVALUATION LOCATION: In-Plant Simulator Control Room Lab Other - List: Classroom APPLICABLE METHOD OF TESTING: Discussion Simulate/Walkthrough Perform Validation Time: 10 minutes TIME CRITICAL (Y/N) N ALTERNATE PATH (Y/N) N Developed by: On File Developer Date (Ensure validator is briefed on exam security per NPG-SPP-17.8.1)

(See JPM Validation Checklist in NPG-SPP-17.8.2)

Validated by: On File Validator Date Approved by: On File Site Training Management Date Approved by: On File Site Training Program Owner Date

JPM-EA-250-3 [01]

Page 2 of 10 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.

2. Any UNSAT requires comments.

Standard : Operator restores Vital Battery Charger I during a Loss of All AC event.

Tools/Equipment/Procedures Needed:

References:

Reference Title Rev No.

1. EA-250-3 RESTORING BATTERY CHARGERS 10

========================================================================

JPM Briefing from NPG-SPP-17.8.2 completed? Yes If no, perform briefing prior to continuing.

READ TO EXAMINEE HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

DIRECTIONS TO OPERATOR:

I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I will provide initiating cues and indicate any steps to be discussed.

When you complete the task successfully, the objective for this job performance measure will be satisfied. 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:

1. Units 1 and 2 are in MODE 3.

2. ECA-0.0 LOSS OF ALL AC POWER is in progress.

INITIATING CUES:

1. You have been directed to energize Vital Battery Charger I from the Normal (Train A) supply using EA-250-3, RESTORING BATTERY CHARGERS, Section 4.2, Restoring 125 V Vital Battery Charger I.

2. Inform the Examiner when complete.

JPM-EA-250-3 [01]

Page 3 of 10 Start Time STEP 1 : SAT Obtain a copy of EA-250-3, RESTORING BATTERY CHARGERS.

UNSAT Standard: The examinee obtains a copy of EA-250-3, RESTORING BATTERY CHARGERS.

Cue Provide a copy of EA-250-3, RESTORING BATTERY CHARGERS Section 4.2, Restoring 125 V Vital Battery Charger I.

Comment STEP 2 : SAT UNSAT Standard: The examinee determines red potential light LIT below NORMAL breaker.

Cue Point to the red potential light LIT below NORMAL breaker and state, Light is ON.

Comment

JPM-EA-250-3 [01]

Page 4 of 10 STEP 3 : SAT UNSAT Standard: The examinee determines ALTERNATE (Train B) breaker in OFF position.

Cue If asked provide the following cue, point at the ALTERNATE (Train B) breaker OFF and state the ALT breaker is in this position.

Comment STEP 4 : SAT UNSAT Standard: The examinee simulates placing NORMAL (Train A) breaker in ON CRITICAL position.

Before the examinee simulates performing the step point at the NORMAL Cue (Train A) breaker in the OFF position, state the breaker is in this position.

After the examinee simulates performing the step point at the NORMAL Cue (Train A) breaker in the ON position, state the breaker is in this position.

Comment

JPM-EA-250-3 [01]

Page 5 of 10 STEP 5 : SAT UNSAT Standard: The examinee addresses the step as N/A.

Comment STEP 6 : SAT UNSAT Standard: The examinee determines equalizing voltage timer at ZERO.

Cue Point to the voltage timer and state The timer is in the as found position.

Comment

JPM-EA-250-3 [01]

Page 6 of 10 STEP 7 : SAT UNSAT Standard: The examinee simulates placing the DC POWER breaker in the ON CRITICAL position.

Before the examinee simulates performing the step point at the DC Cue Power breaker in the OFF position, state the breaker is in this position.

Cue After the examinee simulates performing the step point at the DC Power breaker in the ON position, state the breaker is in this position.

Comment STEP 8 : SAT UNSAT Standard: The examinee simulates placing the AC POWER breaker in the ON CRITICAL position.

Before the examinee simulates performing the step point at the AC Cue Power breaker in the OFF position, state the breaker is in this position.

Cue After the examinee simulates performing the step point at the AC Power breaker in the ON position, state the breaker is in this position.

Comment

JPM-EA-250-3 [01]

Page 7 of 10 STEP 9 : SAT UNSAT Standard: The examinee simulates placing mechanical slide interlock positioned over breaker [0-SW-250-KE/227-D]. [Vital Battery Bd. I, Breaker 227]

Cue Point above mechanical slide interlock and state The slide interlock is in the as found position.

Comment STEP 10 : SAT UNSAT The examinee simulates placing .charger to battery board breaker [0-Standard: SW-250-KE/226-D] placed in ON position. [Vital Battery Bd. I, Breaker CRITICAL 226]

Before the examinee simulates performing the step point at the charger Cue to battery board breaker [0-SW-250-KE/226-D] breaker in the OFF position, state the breaker is in this position.

After the examinee simulates performing the step point at the charger to Cue battery board breaker [0-SW-250-KE/226-D] breaker in the ON position, state the breaker is in this position.

Comment

JPM-EA-250-3 [01]

Page 8 of 10 STEP 11 : SAT UNSAT Standard: The examinee determines charger ammeter current INDICATED Cue Point to the charger ammeter and state The ammeter is in the as found position.

Comment Terminating Provide the following cue Another operator will perform the Cue: STOP remaining steps of this procedure.

Stop Time

JPM-EA-250-3 [01]

Page 9 of 10 JPM DATA SHEET EXAMINEES NAME: EIN:

EVALUATORS NAME: DATE:

JPM Title JPM-EA-250-3[01]

Restore a 125 V Vital Battery Charger I During a Station Blackout.

Start Time Finish Time Performance Time minutes PERFORMANCE RESULTS: SAT UNSAT COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory)

Evaluators Signature:

Date NOTE: If completed satisfactorily only this page needs to be retained in examinees record. If unsatisfactory performance is demonstrated, the entire JPM, including procedures, is retained.

JPM BRIEFING SHEET DIRECTIONS TO OPERATOR:

All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. You will be provided initiating cues and indicate any steps to be discussed. When you complete the task successfully, the objective for this job performance measure will be satisfied. 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:

1. Units 1 and 2 are in MODE 3.

2. ECA-0.0 LOSS OF ALL AC POWER is in progress.

INITIATING CUES:

1. You have been directed to energize Vital Battery Charger I from the Normal (Train A) supply using EA-250-3, RESTORING BATTERY CHARGERS, Section 4.2, Restoring 125 V Vital Battery Charger I.

2. Inform the Examiner when complete.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

SITE: SQN JPM TITLE Respond to Loss of Control Air System JPM-EA-JPM NUMBER 32-2 [01] REVISION: 5 TASK APPLICABILITY: SRO STA UO NAUO TASK NUMBERS / TASK TITLE(S) 0000900501 K/A RATINGS APE 065 AA1.04 (3.5/3.4)

K/A STATEMENT Respond to Loss of Control Air System RELATED PRA INFORMATION Not required for exam.

SAFETY FUNCTION: 8 EVALUATION LOCATION: In-Plant Simulator Control Room Lab Other - List:

APPLICABLE METHOD OF TESTING: Discussion Simulate/Walkthrough Perform TIME FOR COMPLETION: 10 minutes TIME CRITICAL (Y/N) N ALTERNATE PATH (Y/N) N Developed by: On File 7-25-18 Developer Date (Ensure validator is briefed on exam security per NPG-SPP-17.8.1)

(See JPM Validation Checklist in NPG-SPP-17.8.2)

Validated by: On File 8-23-18 Validator Date Approved by: On File 9-24-18 Site Training Management Date Approved by: On File 9-24-18 Site Training Program Owner Date Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Revision 5 Page 1 of 9 [08-08-2014]

JPM-EA-32-2 [01], Rev 5 JPM Briefing from NPG-SPP-17.8.2 completed? Yes If no, perform briefing prior to continuing.

Initial Conditions As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

(REMEMBER TO VERIFY STUDENT SHEET HAS THIS SAME INFORMATION)

INITIAL CONDITIONS:

1. Units 1 and 2 are in MODE 3 following a Loss of Offsite Power.

2. The Aux. Air Compressors are not in service.

3. EA-32-2, Establishing Control and Service Air is in progress, completed through section 4.3 step 3.

4. Station Air Compressor A is available INITIATING CUES (IF APPLICABLE):

1. You have been directed to start and manually load the Station Air Compressor A using EA-32-2, Establishing Control and Service Air section 4.3 starting at step 4.

2. Inform the SRO when complete.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Revision 5 Page 2 of 9 [08-08-2014]

JPM-EA-32-2 [01], Rev 5 Marked up copy of EA-32-2, Establishing Control and Service Air complete Required Materials:

through Section 4.3 step 3.

References:

EA-32-2, Establishing Control and Service, Rev 5 The operator will reset and start Control & Service Air Compressor A using EA-32-2, Task Standards: Establishing Control and Service Air.

NOTE:

When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

IMPORTANT:

Critical steps are marked with a Y below the Performance Step number field. Failure to meet the standard for any critical step shall result in failure of this JPM.

Start Time:

Step # 1. Performance step:

Critical Step?

4. DEPRESS 0-HS-32-25B to reset air compressor trip signals.

Y Standard: Examinee simulates depressing 0-HS-32-25B to reset air comp trip signals.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Following simulated operation provide the following cue, 0-HS-32 25B went in and Cue:

returned to out..

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Revision 5 Page 3 of 9 [08-08-2014]

JPM-EA-32-2 [01], Rev 5 Step # 2. Performance step:

Critical Step?

IF Station Air Compressor A is available, THEN PERFORM the following:

[5.1] CHECK Air Compressor A trip lights DARK:

N - Low OIL PRESSURE

- High OIL TEMPERATURE

- High DISCHARGE AIR PRESSURE Standard: Examinee observes Compressor A Trip lights DARK.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: When asked provide the following cue, All Compressor A trip lights are DARK.

Comments:

Step # 3. Performance step:

Critical Step?

[5.2] PLACE 0-HS-32-25D Air Compressor A AUTO/HAND switch in HAND.

Y Standard: Examinee simulates placing 0-HS-32-25D to HAND.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

When asked provide the following cue, 0-HS-32-25D is positioned counter-Cue:

clockwise to HAND.

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Revision 5 Page 4 of 9 [08-08-2014]

JPM-EA-32-2 [01], Rev 5 Step # 4. Performance step:

Critical Step?

[5.3] PLACE HS-32-25A, Control Air Compressor Selector N Switch in Position 1 (AB).

Standard: Examinee simulates placing HS-32-25A in Position 1.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

When asked provide the following cue, HS-32-25A is positioned counter-clockwise Cue:

to Position 1.

Comments:

Step # 5. Performance step:

Critical Step?

Y [5.4] ENSURE 0-HS-32-25F for Air Compressor A in PULL TO START.

Standard: Examinee simulates placing 0-HS-32-25F for comp A in PULL TO START position.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

When asked provide the following cue, HS-32-25F is maintained in the pull out Cue:

position.

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Revision 5 Page 5 of 9 [08-08-2014]

JPM-EA-32-2 [01], Rev 5 Step # 6. Performance step:

Critical Step?

Y [5.5] DEPRESS 0-HS-32-25E to start Air Compressor A.

Standard: Examinee simulates depressing 0-HS-32-25E.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

When asked provide the following cue, You hear a mechanical rotational noise from Cue:

Compressor A.

Comments:

Step # 7. Performance step:

Critical Step?

[5.6] PLACE 0-HS-32-43A and 0-HS-32-43B in ON to fully load Air Y Compressor A.

Examinee simulates placing 0-HS-32-43A and 0-HS-32-43B in ON (clockwise)

Standard:

position to fully load comp A.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

When asked provide the following cue, You hear the rotational sound lowering Cue:

then recovering from Compressor A.

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Revision 5 Page 6 of 9 [08-08-2014]

JPM-EA-32-2 [01], Rev 5 Step # 8. Performance step:

Critical Step?

[5.7] CHECK operation of Air Compressor A:

- Air Compressor A oil pressure between 15 and 40 psig on 0-PI-32-40 N

- Air Compressor A cooling water flow INDICATED on 0-FG-32-44B Standard: Examinee checks oil pressure and cooling water indications Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

When asked provide the following cues, Cue: point to an oil pressure of 25 psig indicate flow mid scale of meter 0-FG-32-44B Comments:

Terminating Cue: Provide the following cue, Another operator will perform the remaining steps of this procedure.

Stop Time:

Operator Fundamental evaluated:

Historical Record:

Rev 5 JPM formatted to current template and verified against the latest procedure revision.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Revision 5 Page 7 of 9 [08-08-2014]

JPM DATA SHEET EXAMINEES NAME: EIN:

EVALUATORS NAME: DATE:

JPM Title JPM-EA-32-2 [01], Rev 1, Respond to Loss of Control Air System Start Time Finish Time Performance Time PERFORMANCE RESULTS: SAT UNSAT COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory)

Evaluators Signature:

Date NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Revision 5 Page 8 of 9 [08-08-2014]

TURNOVER SHEET As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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:

1. Units 1 and 2 are in MODE 3 following a Loss of Offsite Power.

2. The Aux. Air Compressors are not in service.

3. EA-32-2, Establishing Control and Service Air is in progress, completed through section 4.3 step 3.

4. Station Air Compressor A is available INITIATING CUES (IF APPLICABLE):

1. You have been directed to start and manually load the Station Air Compressor A using EA-32-2, Establishing Control and Service Air section 4.3 starting at step 4.

2. Inform the SRO when complete.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

SITE: SQN JPM TITLE Manually Determine QPTR JPM-0-SI-NUC-JPM NUMBER 133[01] REVISION: 17 TASK APPLICABILITY: SRO STA UO NAUO TASK NUMBERS / TASK TITLE(S) 0150030201 K/A RATINGS 3.9/4.6 G 2.2.42 Ability to recognize system parameters that are entry-level conditions for l K/A STATEMENT Technical Specifications.

RELATED PRA INFORMATION Not required for exam.

SAFETY FUNCTION: NA EVALUATION LOCATION: In-Plant Simulator Control Room Lab Other - List: Classroom APPLICABLE METHOD OF TESTING: Discussion Simulate/Walkthrough Perform TIME FOR COMPLETION: 25 minutes TIME CRITICAL (Y/N) N ALTERNATE PATH (Y/N) N Developed by: Bank Developer Date (Ensure validator is briefed on exam security per NPG-SPP-17.8.1)

(See JPM Validation Checklist in NPG-SPP-17.8.2)

Validated by: Chris Blackwell 11/22/19 Validator Date Approved by: On File Site Training Management Date Approved by: On File Site Training Program Owner Date Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 1 of 14 [08-08-2014]

JPM-0-SI-NUC-133[01]

SPECIAL INSTRUCTIONS:

1. Ensure Classroom is prepared for admin JPMs Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 2 of 14 [08-08-2014]

JPM-0-SI-NUC-133[01]

JPM Briefing from NPG-SPP-17.8.2 completed? Yes If no, perform briefing prior to continuing.

Initial Conditions As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

(REMEMBER TO VERIFY STUDENT SHEET HAS THIS SAME INFORMATION)

1. Unit 1 is in MODE 1 100% power.

2. The Plant Computer is INOPERABLE.

3. QPTR alarm is OPERABLE.

4. See attached pictures of NI current indications.

INITIATING CUES:

1. The SRO has directed you to perform a manual QPTR calculation in accordance with 0-SI-NUC-000-133.0, Quadrant Power Tilt Ratio, Section 6.2, QPTR Determination with plant computer nonfunctional.

2. Notify the Examiner of your results and the required actions (if any.)

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 3 of 14 [08-08-2014]

JPM-0-SI-NUC-133[01]

Classroom with computer access Copy of 0-SI-NUC-000-133.0QUADRANT POWER TILT RATIO Required Materials: TI-28 Attachment 4 Pictures of NI-41,42,43,44 wide and narrow angles and one blank meter wide angle

1. 0-SI-NUC-000-133.0 QUADRANT POWER TILT RATIO

References:

2. TI-28 Attachment 4 Examinee calculates the correct value (within three decimal places, i.e., 0.000) QPTR values for

41B - 1.016

42A - 0.992

42B - 0.994 Task Standards:

43A - 0.997

43B - 1.008

44A - 0.985

44B - 0.982 Examinee notifies the SM that the acceptance criteria was not satisfied because Channel 41A QPTR is 1.026 and the acceptance criteria is less than or equal to 1.020.

NOTE:

When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

IMPORTANT:

Critical steps are marked with a Y below the Performance Step number field. Failure to meet the standard for any critical step shall result in failure of this JPM.

Start Time:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 4 of 14 [08-08-2014]

JPM-0-SI-NUC-133[01]

Step # 1. Performance step:

Critical Step?

N Examinee records data from the initial conditions.

N-41A I t 530 N-43A I t 530 Standard: N-41B I b 510 N-43B I b 520 N-42A I t 550 N-44A I t 530 N-42B I b 550 N-44B I b 550 Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 5 of 14 [08-08-2014]

JPM-0-SI-NUC-133[01]

Step # 2. Performance step:

Critical Step?

N The Examinee enters the following values from TI-28 Att 4.

NI Rt Rb N-41 0.0174 0.0184 Standard:

N-42 0.0162 0.0167 N-43 0.0169 0.0179 N-44 0.0167 0.0165 Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 6 of 14 [08-08-2014]

JPM-0-SI-NUC-133[01]

Step # 3. Performance step:

Critical Step?

N The Examinee calculates the following values.

N-41A V t 9.222 N-43A V t 8.957 Standard: N-41B V b 9.384 N-43B V b 9.308 N-42A V t 8.910 N-44A V t 8.851 N-42B V b 9.185 N-44B V b 9.075 Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 7 of 14 [08-08-2014]

JPM-0-SI-NUC-133[01]

Step # 4. Performance step:

Critical Step?

N The Examinee calculates the following averages.

Standard: V t 8.985 Vb 9.238 Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 8 of 14 [08-08-2014]

JPM-0-SI-NUC-133[01]

Step # 5. Performance step:

Critical Step?

Y Standard: The Examinee calculates calculate ALL Upper and Lower QPTR values Performance: SATISFACTORY UNSATISFACTORY Critical element : Operator determines 41 A channel is NOT Acceptable, Channel 41A Examiner Notes: QPTR is 1.026 and the acceptance criteria is less than or equal to 1.020 Steps 5 and 6 of the JPM can be done in any order.

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 9 of 14 [08-08-2014]

JPM-0-SI-NUC-133[01]

Step # 6. Performance step:

Critical Step?

Y The Examinee calculates as a minimum, the following worst case QPTR.

41B - 1.016 42A - 0.992 42B - 0.994 Standard:

43A - 0.997 43B - 1.008 44A - 0.985 44B - 0.982 Performance: SATISFACTORY UNSATISFACTORY Critical element : Operator determines remaining channels are Acceptable Examiner Notes:

Steps 5 and 6 of the JPM can be done in any order.

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 10 of 14 [08-08-2014]

JPM-0-SI-NUC-133[01]

Step # 7. Performance step:

Critical Step?

Y Standard: The Examinee determines the acceptance criteria is not met and Checks NO Performance:

Examiner Notes:

Cue:

Comments:

Step # 8. Performance step:

Critical Step?

Y Standard: The Examinee determines notification of an SRO (SM or US) is required Performance:

Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 11 of 14 [08-08-2014]

JPM-0-SI-NUC-133[01]

Terminating Cue: Provide the following cue, another operator will complete the remaining steps of this procedure.

Stop Time:

Operator Fundamental evaluated:

Historical Record:

Rev 17 Converted JPM into current template and updated JPM to new given currents and adjusted answers for new TI-28 constants Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 12 of 14 [08-08-2014]

JPM-0-SI-NUC-133[01]

JPM DATA SHEET EXAMINEES NAME: EIN:

EVALUATORS NAME: DATE:

JPM Title JPM-0-SI-NUC-133[01], Manually Determine QPTR Start Time Finish Time Performance Time PERFORMANCE RESULTS: SAT UNSAT COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory)

Evaluators Signature:

Date NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

[08-08-2014]

TURNOVER SHEET As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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.

1. Unit 1 is in MODE 1 100% power.

2. The Plant Computer is INOPERABLE.

3. QPTR alarm is OPERABLE.

4. See attached pictures of NI current indications.

INITIATING CUES:

1. The SRO has directed you to perform a manual QPTR calculation in accordance with 0-SI-NUC-000-133.0, Quadrant Power Tilt Ratio, Section 6.2, QPTR Determination with plant computer nonfunctional.

2. Notify the Examiner of your results and the required actions (if any.)

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

SQN NIS POWER RANGE CALIBRATION TI-28, ATT. 4 Unit 1 & 2 DATA Effective Date: 10-15-2019 Page 1 of 2 The NIS Power Range calibration data is determined for each unit by an incore/excore cross calibration and/or single point alignment periodically during the operating cycle. The calibration data changes with core burnup and must be periodically updated.

UNIT 1 NOTE This data may be updated during the initial startup following a refueling outage as follows:

Prior to initial criticality; at 35% or 45% or 75% power; and at 100% power. This data will also be updated periodically during the fuel cycle. Because of the frequent updates, this data must be verified before it is used to perform any Tech Spec related work.

NIS N Rt Rb G Channel %/Volts Volts/Amp Volts/Amp %/Pu N-41 16.6095 0.0174 0.0184 1.8 N-42 16.4864 0.0162 0.0167 1.8 N-43 16.3923 0.0169 0.0179 1.8 N-44 16.8590 0.0167 0.0165 1.8 NIS Full Power Currents (A) for Values of 0%, 30%, and -30%

NIS Channel IEt (0%) IEb (0%) IEt (+30%) IEb (+30%) IEt (-30%) IEb (-30%)

N-41 479.2 453.1 574.0 346.3 384.4 559.8 N-42 515.3 499.5 614.1 377.1 416.5 621.8 N-43 491.7 465.2 589.6 353.4 393.9 576.9 N-44 497.9 503.8 593.2 385.0 402.7 622.5 Data taken from 0-SI-NUC-092-002.0 dated 6/25/19.

SQN NIS POWER RANGE CALIBRATION TI-28, ATT. 4 Unit 1 & 2 DATA Effective Date: 10-15-2019 Page 2 of 2 UNIT 2 NOTE This data may be updated during the initial startup following a refueling outage as follows:

Prior to initial criticality; at 35% or 45% or 75% power; and at 100% power. This data will also be updated periodically during the fuel cycle. Because of the frequent updates, this data must be verified before it is used to perform any Tech Spec related work.

NIS N Rt Rb G Channel %/Volts Volts/Amp Volts/Amp %/Pu N-41 17.0333 0.0166 0.0174 1.8 N-42 16.9258 0.0150 0.0150 1.8 N-43 16.9514 0.0142 0.0147 1.8 N-44 16.9532 0.0149 0.0152 1.8 NIS Full Power Currents (A) for Values of 0%, 30%, and -30%

NIS Channel IEt (0%) IEb (0%) IEt (+30%) IEb (+30%) IEt (-30%) IEb (-30%)

N-41 502.4 479.9 587.9 358.7 416.9 601.0 N-42 556.9 554.9 652.0 413.7 461.7 696.1 N-43 588.2 568.2 686.7 422.1 489.6 714.3 N-44 560.0 549.2 657.0 411.1 463.0 687.3 Data taken from 0-SI-NUC-092-002.0 dated 10/08/19.

N-41A N-41B

N-42A N-42B

N-43A N-43B

N-44A N-44B

SITE: SQN JPM TITLE Determine the Functionality of a BAT before use JPM-Tech JPM NUMBER Spec [01] REVISION: 1 TASK APPLICABILITY: SRO STA UO NAUO TASK NUMBERS / TASK TITLE(S) 1190100302 K/A RATINGS 3.9/4.2 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, K/A STATEMENT etc.

RELATED PRA INFORMATION Not required for exam.

SAFETY FUNCTION: na EVALUATION LOCATION: In-Plant Simulator Control Room Lab Other - List: Classroom APPLICABLE METHOD OF TESTING: Discussion Simulate/Walkthrough Perform TIME FOR COMPLETION: 10 minutes TIME CRITICAL (Y/N) N ALTERNATE PATH (Y/N) N Developed by: On File Developer Date (Ensure validator is briefed on exam security per NPG-SPP-17.8.1)

(See JPM Validation Checklist in NPG-SPP-17.8.2)

Validated by: Don Boyles 11/26/19 Validator Date Approved by: On File Site Training Management Date Approved by: On File Site Training Program Owner Date Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 1 of 9 [08-08-2014]

JPM-Tech Spec [01]

SPECIAL INSTRUCTIONS:

1. Ensure classroom is prepared to administer admin JPM Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 2 of 9 [08-08-2014]

JPM-Tech Spec [01]

JPM Briefing from NPG-SPP-17.8.2 completed? Yes If no, perform briefing prior to continuing.

Initial Conditions As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

(REMEMBER TO VERIFY STUDENT SHEET HAS THIS SAME INFORMATION)

INITIAL CONDITIONS:

1. Unit 1 is at 100% power

2. Preparations are in progress to place a clearance on BAT A for Maintenance.

3. BAT C level is indicating 9,600 gallons on 0-LI-62-242.

INITIATING CUES:

1. You have been directed to evaluate the FUNCTIONALITY of the current level in the BAT C, before the clearance is placed on BAT A.

2. Notify the Examiner of results when determination of FUNCTIONALITY has been completed.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 3 of 9 [08-08-2014]

JPM-Tech Spec [01]

1. Computer access with frozen procedures Required Materials: 2. JPM Chemistry Handout

1. TRM

2. TRM Figure 3.1.2.6

References:

3. 1-SI-OPS-000-003.W, Weekly Shift Log page 24

4. JPM Chemistry Handout The examinee notifies the examiner that BAT C is NOT functional because TRV Task Standards: 8.1.1.3 (Figure 8.1.1-1) requires a minimum volume of 9850 gallons and the current level in BAT C is only 9600 gallons.

NOTE:

When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

IMPORTANT:

Critical steps are marked with a Y below the Performance Step number field. Failure to meet the standard for any critical step shall result in failure of this JPM.

Start Time:

Step # 1. Performance step:

Critical Step?

Examinee goes to 1-SI-OPS-000-003.W to review BAT C Level FUNCTIONALITY requirements.

N Examinee reviews 1-SI-OPS-000-003.W, Attachment 1 (page 33 of 36), SR Standard:

requirements for BAT C level FUNCTIONALITY Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 4 of 9 [08-08-2014]

JPM-Tech Spec [01]

Step # 2. Performance step:

Critical Step?

On BATC curve, Operator locates correct vertical axis for BAT PPM concentration Y

Operator using OPS info Handout identifies BAT concentration as 6450 ppm and Standard:

locates corresponding axis on TRM Limits curves Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 3. Performance step:

Critical Step?

Operator moves up the axis to the intersect point matching the given RWST boron concentration Y

Operator identifies RWST concentration for Unit 1 as 2550 ppm and moves up the Standard:

6450 ppm vertical axis to find the intersecting point Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 5 of 9 [08-08-2014]

JPM-Tech Spec [01]

Step # 4. Performance step:

Critical Step?

Operator moves horizontally left from the intersection point identified in the previous JPM step to identify a required volume from the left vertical axis (BAT Volume)

Y Operator determines the required volume is 9850 gallons (+50/-75 for interpolation Standard:

errors)

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 5. Performance step:

Critical Step?

SRO determines tank is NOT FUNCTIONAL by comparison of actual vs required volumes Y

Operator compares actual volume (9600 gallons) to required (9850 gallons) and Standard:

determines BAT C is NOT FUNTIONAL Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 6 of 9 [08-08-2014]

JPM-Tech Spec [01]

Step # 6. Performance step:

Critical Step?

SRO notifies examiner of results Y

Standard: SRO reports BAT C is NOT FUNCTIONAL Performance:

Examiner Notes:

Cue:

Comments:

Terminating Cue: Provide the following cue: That completes the JPM.

Stop Time:

Operator Fundamental evaluated:

Historical Record:

Rev 1 Converted JPM into current template and verified against latest procedure revisions.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 7 of 9 [08-08-2014]

JPM-Tech Spec [01]

JPM DATA SHEET EXAMINEES NAME: EIN:

EVALUATORS NAME: DATE:

JPM Title JPM-Tech Spec [01], Determine the FUNCTIONALITY of a BAT before use Start Time Finish Time Performance Time PERFORMANCE RESULTS: SAT UNSAT COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory)

Evaluators Signature:

Date NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

[08-08-2014]

TURNOVER SHEET As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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:

1. Unit 1 is at 100% power

2. Preparations are in progress to place a clearance on BAT A for Maintenance.

3. BAT C level is indicating 9,600 gallons on 0-LI-62-242.

INITIATING CUES:

1. You have been directed to evaluate the FUNCTIONALITY of the current level in the BAT C, before the clearance is placed on BAT A.

2. Notify the Examiner of results when determination of FUNCTIONALITY has been completed.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

Operations Information Sample Point Units Boron Date / Time Goal Limit U1 RCS ppm 660 Today/XXXX Variable Variable U2 RCS ppm 968 Today/XXXX Variable Variable U1 RWST ppm 2550 Today/XXXX 2550 - 2650 2500 - 2700 U2 RWST ppm 2589 Today/XXXX 2550 - 2650 2500 - 2700 BAT A ppm 6764 Today/XXXX Variable Variable BAT B ppm 6872 Today/XXXX Variable Variable BAT C ppm 6450 Today/XXXX Variable Variable U1 CLA #1 ppm 2532 Two Weeks Ago/XXXX 2470-2630 2400-2700 U1 CLA #2 ppm 2542 Two Weeks Ago/XXXX 2470-2630 2400-2700 U1 CLA #3 ppm 2546 Two Weeks Ago/XXXX 2470-2630 2400-2700 U1 CLA #4 ppm 2515 Two Weeks Ago/XXXX 2470-2630 2400-2700 U2 CLA #1 ppm 2555 Last Week/XXXX 2470-2630 2400-2700 U2 CLA #2 ppm 2502 Last Week/XXXX 2470-2630 2400-2700 U2 CLA #3 ppm 2579 Last Week/XXXX 2470-2630 2400-2700 U2 CLA #4 ppm 2540 Last Week/XXXX 2470-2630 2400-2700 Spent Fuel Pool ppm 2659 Last Week/XXXX > 2050 > 2000 Lithium Results Date / Time Goal Midpoint U1 RCS Lithium ppm 2.44 Today/XXXX 2.26-2.52 2.39 U2 RCS Lithium ppm 3.51 Today/XXXX 3.28-3.54 3.41 Primary to Secondary Leakrate Information (Total CPM RM-90-99/119)

Indicator Units U1 Date / Time U2 Date/Time SI 50 S/G Leakage? Yes/No No Today/XXXX No Today / Now SI 137.5 CVE Leakrate gpd <0.1 Last Week/XXXX <0.1 Today / Now 5 gpd leak equivalent cpm 115 Today / Now 85 Today / Now 30 gpd leak equivalent cpm 490 Today / Now 308 Today / Now 75 gpd leak equivalent cpm 1165 Today / Now 710 Today / Now 100 gpd leak equivalent cpm 1540 Today / Now 933 Today / Now 150 gpd leak equivalent cpm 2290 Today / Now 1380 Today / Now Bkgd on 99 /119 cpm 40 Last Week/XXXX 40 Today / Now Correlation Factor 99/119 cpm/gpd 5.31 Last Week/XXXX 0.854 Today / Now Steady State conditions are necessary for an accurate determination of leak rate using the CVE Rad Monitor

SITE: SQN JPM TITLE Determine Electrical Safety requirements NPG-SPP-JPM NUMBER 18.4.9 [01] REVISION: 0 TASK APPLICABILITY: SRO STA UO NAUO TASK NUMBERS / TASK TITLE(S) 0621060102 K/A RATINGS (4.1/4.0) 2.1.29 Knowledge of how to conduct system lineups, such as valves, K/A STATEMENT breakers, switches, etc.

RELATED PRA INFORMATION Not required for exam.

SAFETY FUNCTION: NA EVALUATION LOCATION: In-Plant Simulator Control Room Lab Other - List: Classroom APPLICABLE METHOD OF TESTING: Discussion Simulate/Walkthrough Perform TIME FOR COMPLETION: 15 minutes TIME CRITICAL (Y/N) N ALTERNATE PATH (Y/N) N Developed by: Aaron Forsha 1/6/20 Developer Date (Ensure validator is briefed on exam security per NPG-SPP-17.8.1)

(See JPM Validation Checklist in NPG-SPP-17.8.2)

Validated by: Don Boyles 1/12/20 Validator Date Approved by:

Site Training Management Date Approved by:

Site Training Program Owner Date Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 1 of 10 [08-08-2014]

NPG-SPP-18.4.9 [01]

SPECIAL INSTRUCTIONS:

1. Ensure Classroom is prepared for Admin JPMs Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 2 of 10 [08-08-2014]

NPG-SPP-18.4.9 [01]

JPM Briefing from NPG-SPP-17.8.2 completed? Yes If no, perform briefing prior to continuing.

Initial Conditions As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

(REMEMBER TO VERIFY STUDENT SHEET HAS THIS SAME INFORMATION)

INITIAL CONDITIONS:

1. Unit 1 is in MODE 1.

2. The 1A SI PUMP breaker is being replaced.

INITIATING CUES (IF APPLICABLE):

1. Determine the Electrical Safety (Arc Flash PPE/Boundary) requirements for manually racking out the 1A SI PUMP Breaker.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 3 of 10 [08-08-2014]

NPG-SPP-18.4.9 [01]

Required Materials: Computer Access with frozen procedures available

References:

1. Frozen Procedures Folder Operator determines:

1. The breaker is located on the 6.9kV Shutdown Bd 1A-A Task Standards: 2. The Hazard Energy (Cal/cm2) is 9.6

3. The Arc Flash Protection Boundary is 25.5 Feet

4. The Arc Flash Personal Protective Equipment (PPE) requirements NOTE:

When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

IMPORTANT:

Critical steps are marked with a Y below the Performance Step number field. Failure to meet the standard for any critical step shall result in failure of this JPM.

Start Time:

Step # 1. Performance step:

Critical Step?

Operator determines the board where the breaker is located.

Y Operator refers to 1-SO-63-5 ATT 1, ECCS System Power Checklist and determines Standard:

the breaker is located on the 6.9kV Shutdown Bd 1A-A Performance: SATISFACTORY UNSATISFACTORY Critical element is the correct board Identification, there are several other sources that Examiner Notes:

could be utilized to determine the breaker location.

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 4 of 10 [08-08-2014]

NPG-SPP-18.4.9 [01]

Step # 2. Performance step:

Critical Step?

Operator refers to NPG-SPP-18.4.9 Electrical Safe Work Practices and Protective Boundary Matrices Attachment 7 for SQN N

Standard:

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 3. Performance step:

Critical Step?

Operator identifies the Hazard Energy and Arc Flash Boundary requirements for the 6.9KV SDBD 1A-A Y

Standard: Hazard Energy @36 (Cal/cm2) = 9.6 and Arc Flash Boundary = 25.5 Feet Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 5 of 10 [08-08-2014]

NPG-SPP-18.4.9 [01]

Step # 4. Performance step:

Critical Step?

Operator identifies if AR Clothing Protection is/is not required.

Y Operator determines that AR Clothing Protection is required.

Standard:

Performance: SATISFACTORY UNSATISFACTORY Requirements per NPG-SPP-18.4.9 Electrical Safe Work Practices and Protective Examiner Notes:

Boundary Matrices Attachment 5.

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 6 of 10 [08-08-2014]

NPG-SPP-18.4.9 [01]

Step # 5. Performance step:

Critical Step?

Operator identifies the Arc Flash PPE and Arc Flash Boundary requirements for the 6.9KV SDBD 1A-A Y

Standard:

Operator determines PPE and Boundary requirements. Either Manual racking or Remote racking tool PPE requirements is acceptable.

Performance: SATISFACTORY UNSATISFACTORY Examiner Requirements per NPG-SPP-18.4.9 Electrical Safe Work Practices and Protective Notes: Boundary Matrices Attachment 3.

Cue:

Comments:

Terminating Cue: That completes the JPM.

Stop Time:

Operator Fundamental evaluated:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 7 of 10 [08-08-2014]

NPG-SPP-18.4.9 [01]

Historical Record:

Rev 0 New Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 8 of 10 [08-08-2014]

NPG-SPP-18.4.9 [01]

JPM DATA SHEET EXAMINEES NAME: EIN:

EVALUATORS NAME: DATE:

JPM Title NPG-SPP-18.4.9 [01] Determine Electrical Safety requirements Start Time Finish Time Performance Time PERFORMANCE RESULTS: SAT UNSAT COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory)

Evaluators Signature:

Date NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

[08-08-2014]

TURNOVER SHEET As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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:

1. Unit 1 is in MODE 1.

2. The 1A SI PUMP breaker is being replaced.

INITIATING CUES (IF APPLICABLE):

2. Determine the Electrical Safety (Arc Flash PPE/Boundary) requirements for manually racking out the 1A SI PUMP Breaker.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

SITE: SQN JPM TITLE Determine MODE Change Requirements Tech Spes JPM NUMBER [02] REVISION: 1 TASK APPLICABILITY: SRO STA UO NAUO TASK NUMBERS / TASK TITLE(S) 1190150301 K/A RATINGS 4.5 K/A STATEMENT 2.2.35 Ability to determine Technical Specification Mode of Operation.

RELATED PRA INFORMATION Not required for exam.

SAFETY FUNCTION: na EVALUATION LOCATION: In-Plant Simulator Control Room Lab Other - List: Classroom APPLICABLE METHOD OF TESTING: Discussion Simulate/Walkthrough Perform TIME FOR COMPLETION: 15 minutes TIME CRITICAL (Y/N) N ALTERNATE PATH (Y/N) N Developed by: Aaron Forsha 11/25/19 Developer Date (Ensure validator is briefed on exam security per NPG-SPP-17.8.1)

(See JPM Validation Checklist in NPG-SPP-17.8.2)

Validated by: Don Boyles 11/26/19 Validator Date Approved by: Aaron Forsha 11/26/19 Site Training Management Date Approved by: Terry Dunny 11/26/19 Site Training Program Owner Date Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 1 of 9 [08-08-2014]

Tech Spec [02], Rev 01 SPECIAL INSTRUCTIONS:

1. Ensure Classroom is prepared for Admin JPMs Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 2 of 9 [08-08-2014]

Tech Spec [02], Rev 01 JPM Briefing from NPG-SPP-17.8.2 completed? Yes If no, perform briefing prior to continuing.

Initial Conditions As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

(REMEMBER TO VERIFY STUDENT SHEET HAS THIS SAME INFORMATION)

INITIAL CONDITIONS:

1. Unit 1 is MODE 4.

2. 0-GO-1 UNIT STARTUP FROM COLD SHUTDOWN TO HOT STANDBY is in progress.

3. Preparations are in progress to perform a mode change to MODE 3 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

4. The following equipment is currently INOPERABLE:

SG 1 SGBD Sample Isolation Valve (1-FSV-43-55) was declared INOPERABLE seven days ago due to failing to meet valve stroke acceptance criteria of 0-SI-SXV-043-266.0. The manual isolation valve (1-VLV-1-820) was tagged CLOSED to comply with the applicable LCO action(s).

Remote Shutdown AFW flow to #1 SG (1-FI-3-163C) was declared INOPERABLE 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ago. The instrument has been removed from service for emergent MIG repairs. Estimated to be returned to service within the next 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

INITIATING CUES:

1. You are directed to assess each plant condition separately and determine if Mode 3 can be entered in the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , including the reason(s) for your determination.

2. Notify the examiner of your results.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 3 of 9 [08-08-2014]

Tech Spec [02], Rev 01

1. Classroom with computer access Required Materials:

2. Access to procedure references

1. Unit 1 Tech Specs

References:

2. NPG-SPP-09.11.2 Risk Assessment Methods for Technical Specifications The examinee determines that SG1 SGBD Sample Isolation Valve (1-FSV-43-55) being inoperable does NOT preclude entering Mode 3 because LCO 3.6.3 allows an unlimited period of time to operate with the valve inoperable.

The examinee determines that Remote Shutdown AFW flow to #1 SG (1-FI 163C) being inoperable requires a risk assessment per LCO 3.0.4.b to be Task Standards: performed before entering Mode 3 because LCO 3.3.4 does NOT allow an unlimited period of time for Function 10 to be inoperable.

The examinee uses NPG-SPP-09.11.2, Attachment 1, Flow Chart for MODE Change Risk Assessment, to determine that Mode 3 is allowed to be entered, in accordance with LCO 3.0.4.b, because the 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months maintenance time is within the 30 day Tech Spec 3.3.4 required action time.

NOTE:

When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

IMPORTANT:

Critical steps are marked with a Y below the Performance Step number field. Failure to meet the standard for any critical step shall result in failure of this JPM.

Start Time:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 4 of 9 [08-08-2014]

Tech Spec [02], Rev 01 Step # 1. Performance step:

Critical Step? SG 1 SGBD Sample Isolation Valve (1-FSV-43-55) is evaluated per Tech Specs Y

SRO determines LCO 3.0.4 a can be invoked and MODE 3 is allowed because the Standard:

time period is unlimited.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Step # 2. Performance step:

Remote Shutdown AFW flow to #1 SG (1-FI-3-163C) is evaluated per Tech Specs Critical Step?

Y The Examinee determines risk assessment is needed because there is not an Standard:

indefinite time period.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

IF Candidate reports not allowed unitl risk assessment is performed You are Cue:

directed to perform the Risk Assessment Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 5 of 9 [08-08-2014]

Tech Spec [02], Rev 01 Step # 3. Performance step:

Remote Shutdown AFW flow to #1 SG (1-FI-3-163C) is evaluated per 3.0.4 b Risk Critical Step?

assessment Y

The Examinee determines LCO 3.0.4 b can be invoked and MODE 3 is allowed Standard: because the 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months maintenance time is within the 30 day Tech Spec 3.3.4 required action time.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Terminating Cue: Provide the following cue, that completes the JPM.

Stop Time:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 6 of 9 [08-08-2014]

Tech Spec [02], Rev 01 Operator Fundamental evaluated:

Historical Record:

Rev 1 Converted JPM into current template and verified against latest procedure revisions.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 7 of 9 [08-08-2014]

Tech Spec [02], Rev 01 JPM DATA SHEET EXAMINEES NAME: EIN:

EVALUATORS NAME: DATE:

JPM Title Tech Spec [02], Determine Mode Change Requirements Start Time Finish Time Performance Time PERFORMANCE RESULTS: SAT UNSAT COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory)

Evaluators Signature:

Date NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

[08-08-2014]

TURNOVER SHEET As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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:

1. Unit 1 is MODE 4.

2. 0-GO-1 UNIT STARTUP FROM COLD SHUTDOWN TO HOT STANDBY is in progress.

3. Preparations are in progress to perform a mode change to MODE 3 within the next six hours.

4. The following equipment is currently INOPERABLE:

SG 1 SGBD Sample Isolation Valve (1-FSV-43-55) was declared INOPERABLE seven days ago due to failing to meet valve stroke acceptance criteria of 0-SI-SXV-043-266.0.

The manual isolation valve (1-VLV-1-820) was tagged CLOSED to comply with the applicable LCO action(s).

Remote Shutdown AFW flow to #1 SG (1-FI-3-163C) was declared INOPERABLE 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ago. The instrument has been removed from service for emergent MIG repairs.

Estimated to be returned to service within the next 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

INITIATING CUES:

1. You are directed to assess each plant condition separately and determine if Mode 3 can be entered in the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , including the reason(s) for your determination.

2. Notify the examiner of your results.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

SITE: SQN JPM TITLE Manual Leakrate calculation JPM-0-SI-OPS-068-JPM NUMBER 137.0 [01] REVISION: 41 TASK APPLICABILITY: SRO STA UO NAUO TASK NUMBERS / TASK TITLE(S) 0020010201 K/A RATINGS 3.9/4.6 2.2.42 Ability to recognize system parameters that are entry-level conditions K/A STATEMENT for Technical Specifications.

RELATED PRA INFORMATION Not required for exam.

SAFETY FUNCTION: NA EVALUATION LOCATION: In-Plant Simulator Control Room Lab Other - List: Classroom APPLICABLE METHOD OF TESTING: Discussion Simulate/Walkthrough Perform TIME FOR COMPLETION: 20 minutes TIME CRITICAL (Y/N) N ALTERNATE PATH (Y/N) N Developed by: On File Developer Date (Ensure validator is briefed on exam security per NPG-SPP-17.8.1)

(See JPM Validation Checklist in NPG-SPP-17.8.2)

Validated by: On File Validator Date Approved by: On File Site Training Management Date Approved by: On File Site Training Program Owner Date Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 1 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

SPECIAL INSTRUCTIONS:

1. Ensure classroom is prepared for admin JPMs Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 2 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

JPM Briefing from NPG-SPP-17.8.2 completed? Yes If no, perform briefing prior to continuing.

Initial Conditions As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

(REMEMBER TO VERIFY STUDENT SHEET HAS THIS SAME INFORMATION)

INITIAL CONDITIONS:

1. Unit-2 is in MODE 1.

2. 0-SI-OPS-068-137.0, Reactor Coolant System Water Inventory is in progress up to step 6.2.2 [1].

3. ICS is not available.

4. 0-SI-CEM-000-050.3 and 2-SI-CEM-068-137.5 were completed last night at 2300 SG # 1 SG # 2 SG # 3 SG # 4 3.2 gpd 3.2 gpd 3.2 gpd 4.8 gpd

5. Chemistry supervisor reported no additions or samples taken from the RCS during the selected performance period.

6. CCPIT/HUT leakage and other leakage is 0 gpm.

7. Current Pressurizer Pressure is 2225 psig INITIATING CUES:

1. You are the Unit 2 CRO and have been directed to complete step 6.2.2[1] of 0-SI-OPS-068-137.0, Reactor Coolant System Water

2. Notify the Examiner if Acceptance Criteria is (met / NOT met) when finished.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 3 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

Classroom with computer access Marked up copy of 0-SI-OPS-068-137.0 Reactor Coolant System Water Required Materials:

Inventory Steam tables based on year 2000 ASME steam tables

References:

1. 0-SI-OPS-068-137.0 Reactor Coolant System Water Inventory The examinee completes Attachment 4 and calculates the following parameter values:

VCT Leakage = 0.80 gpm PZR Leakage = (0.51-0.52) gpm Total RCS Leakage = (1.31-1.32) gpm PRT Leakage= 0.00 gpm Task Standards:

RCDT Leakage = 0.00 gpm SG Leakage = 0.01 gpm Total identified leakage = 0.01 gpm Total unidentified leakage = (1.30-1.31) gpm The examinee notifies the Examiner that the acceptance criteria is NOT met because the unidentified leakage is greater than 1 gpm.

NOTE:

When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

IMPORTANT:

Critical steps are marked with a Y below the Performance Step number field. Failure to meet the standard for any critical step shall result in failure of this JPM.

Start Time:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 4 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

Step # 1. Performance step:

Critical Step?

Y Standard: The Examinee determines VCT Leakage is .80 gpm.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 5 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

Step # 2. Performance step:

Critical Step?

Y The Examinee determines Initial Pressurizer Volume is between (4883.25-4899.38)

Standard:

gallons Performance: SATISFACTORY UNSATISFACTORY Examiner Acceptability band is based on interpolation of Steam tables Derosa Steam tables 2000 Notes: ASME with PZR pressure @2240 psia with a +/- 15 psia allowance Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 6 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

Step # 3. Performance step:

Critical Step?

Y Standard: The Examinee determines Final Pressurizer Volume is (4821.33-4836.69) gallons Performance: SATISFACTORY UNSATISFACTORY Examiner Acceptability band is based on interpolation of Steam tables and previous acceptability Notes: bands Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 7 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

Step # 4. Performance step:

Critical Step?

Y Standard: The Examinee determines Pressurizer Leakage is (0.51-0.52) gpm Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Acceptability band is based previous acceptability bands Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 8 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

Step # 5. Performance step:

Critical Step?

Y Standard: The Examinee determines RCS Temperature Correction is 0 gpm.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 9 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

Step # 6. Performance step:

Critical Step?

Y Standard: The Examinee determines Total RCS leakage is (1.31-1.32) gpm.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Acceptability band is based previous acceptability bands Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 10 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

Step # 7. Performance step:

Critical Step?

Y Standard: The Examinee determines Pressurizer Relief Tank (PRT) leakage is 0.00 Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 11 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

Step # 8. Performance step:

Critical Step?

Y Standard: The Examinee determines Reactor Coolant Drain Tank (RCDT) is 0.00.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 12 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

Step # 9. Performance step:

Critical Step?

Y The examinee determines the Steam Generator Leakage is 0.01 gpm.

Standard: The examinee obtains the date and time of the steam generator leakage surveillance from the initiating cue.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 13 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

Step # 10. Performance step:

Critical Step?

N Standard: The Examinee determines this step is NA Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 14 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

Step # 11. Performance step:

Critical Step?

N Standard: The Examinee determines from cue sheet the Other Identified Leakage is zero.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 15 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

Step # 12. Performance step:

Critical Step?

Y Standard: The Examinee determines Total Identified Leakage is 0.01 gpm.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 16 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

Step # 13. Performance step:

Critical Step?

Y Standard: The Examinee determines Unidentified Leakage is (1.30-1.31) gpm.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Acceptability band is based previous acceptability bands Cue:

Comments:

Step # 14. Performance step:

Acceptance Criteria Determination Critical Step?

Y Operator determines Acceptance Criteria is NOT met because Unidentified leakage Standard:

exceeds 1 gpm Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: If not provided ask Is Acceptance Criteria met or NOT met, explain your answer Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 17 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

Terminating Cue: Provide the following cue, That completes the JPM.

Stop Time:

Operator Fundamental evaluated:

Historical Record:

Rev 41 Converted JPM into current template and verified against latest procedure revisions.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 18 of 20 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [01]

JPM DATA SHEET EXAMINEES NAME: EIN:

EVALUATORS NAME: DATE:

JPM Title JPM-0-SI-OPS-068-137.0 [01], Manual Leakrate Calculation Start Time Finish Time Performance Time PERFORMANCE RESULTS: SAT UNSAT COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory)

Evaluators Signature:

Date NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

[08-08-2014]

TURNOVER SHEET As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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:

1. Unit-2 is in MODE 1.

2. 0-SI-OPS-068-137.0, Reactor Coolant System Water Inventory is in progress up to step 6.2.2 [1].

3. ICS is not available.

4. 0-SI-CEM-000-050.3 and 2-SI-CEM-068-137.5 were completed last night at 2300 SG # 1 SG # 2 SG # 3 SG # 4 3.2 gpd 3.2 gpd 3.2 gpd 4.8 gpd

5. Chemistry supervisor reported no additions or samples taken from the RCS during the selected performance period.

6. CCPIT/HUT leakage and other leakage is 0 gpm.

7. Current Pressurizer Pressure is 2225 psig INITIATING CUES:

1. You are the Unit 2 CRO and have been directed to complete step 6.2.2[1] of 0-SI-OPS-068-137.0, Reactor Coolant System Water

2. Notify the Examiner if Acceptance Criteria is (met / NOT met) when finished.

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

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127(6

1) All calculations must be performed manually. Verification may be performed using the computer.

2) All calculations should be carried out to two places after the decimal. Signs must be carried through all calculations.

3) Calculations in this Attachment may need to be performed more than once. If multiple calculations are required, copies of this Attachment may be used.

Ke Key ey ey

727$/5&6/($.$*(

9ROXPH&RQWURO7DQN

RQWURO7DQN 9&7

[( %) - (

%)] x 19.27 gal/%ga Initial Level vel Final nal Level VCT Leakage eakage =

min.)

in.)

' Time Tim VCT Leakage

eakage _________________GPM

3UHVVXUL]HU 3]U 81,7RQO\

[1] &$/&8/$7( initial PZR volume by using the following equation:

127(6

1) Vf (specific volume of a fluid) and Vg (specific volume of a gas)values for current plant conditions can be found using a copy of the steam tables.

2) In the following equation the multiplier is the Pressurizer Volumetric Constant determined by engineering.

§ PZRLevel 100 % PZRLevel

3 Initial PZR Vol ¨¨ ¸¸

2.02 gal

ft Vf Vg lb * %level

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§ *

¨ ¸ Initial PZR Vol

¨ %

100 %¸

2 . 02 gal

ft 3

¨ 3 ft 3 ¸ lb * %level

¨¨ ft lb lb ¸ ¸ m

Initial PZR Vol ___________ gal Keyy Performed By Reviewed By

[2] &$/&8/$7(

&8

&8/$7( Final P PZR volume by using the following equation:

ation ation:

127(6

127 127(6

1) Vf (specific volume ume of a fluid) and Vg (specific volume of a gas)value gas)values ffor current plant conditions can be found using a copy of the steam tables. t

2) In the followingg equation the multiplier is the Pressurizer VolumetricVolumet Co Constant eng determined by engineering.

§ PZRLevel 100 % PZRLevel

3 Final PZR Vol ¨¨ ¸¸

2.02 gal

ft Vf Vg lb * %level

§ *

¨ ¸ Final PZR Vol

¨ %

100 %¸

2. 02 gal

ft 3

¨ 3 ft 3 ¸ lb * %level

¨¨ ft lb ¸ m lb ¸

BB JDO

)LQDO 3=5 9RO BBBBBBB Performed By Reviewed By

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[3] &$/&8/$7( PZR leakage rate by using the following equation:

,QLWLDO 3=5 9ROXPH )LQDO 3=5 9ROXPH 3=5 /HDNDJH

'WLPH

JDO 4828.9

JDO 3=5 /HDNDJH

BBBBBBBBBB PLQ Key

.519

BB JSP 3=5 /HDNDJH BBBBBBBBBB Performed By Reviewed By

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>@ &$/&8/$7(LQLWLDO3=5YROXPHXVLQJWKHIROORZLQJHTXDWLRQ

127(6

9I VSHFLILFYROXPHRIDIOXLG DQG9J VSHFLILFYROXPHRIDJDV YDOXHVIRUFXUUHQWSODQW FRQGLWLRQVFDQEHIRXQGXVLQJDFRS\RIWKHVWHDPWDEOHV

,QWKHIROORZLQJHTXDWLRQWKHPXOWLSOLHULVWKH3UHVVXUL]HU9ROXPHWULF&RQVWDQW GHWHUPLQHGE\HQJLQHHULQJ

Key Key

§ PZRLevel 100 % PZRLevel

3 Initial PZR Vol ¨¨ ¸¸

2.01 gal

ft Vf Vg lb * %level

§ *

¨ % 00

100 %¸ 3 Initial PZR Vol ¨ ¸

2.01 gal

ft

¨ ft3 ft3 ¸ lb m * %level

¨ lb m lb m ¹¸

____ _ gal 1$

BBBBBBBBBBBB

3HUIRUPHG%\

1$

BBBBBBBBBBBB

5HYLHZHG%\

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[2] &$/&8/$7( Final PZR volume using the following equation:

127(6

1) Vf (specific volume of a fluid) and Vg (specific volume of a gas)values for current plant conditions can be found using a copy of the steam tables.

2) In the following equation the multiplier is the Pressurizer Volumetric Constant determined by engineering.

Key Key

§ 3=5/HYHO 3=5/HYHO *

)LQDO 3=5 9RO ¨¨ ¸¸ JDO IW 9I 9J OE OHYHO

§ *

¨

¸

)LQDO 3=5 9RO ¨ JDO IW

¸

¨ IW IW ¸ OE P OHYHO

¨ OE P OE P ¹ ¸

©

)LQDO 3=5 9RO BBBBBBB B B BB JDO 1$

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Reviewed By

[3] &$/&8/$7( PZR leakage rate using the following equation:

,QLWLDO 3=5 9ROXPH )LQDO 3=5 9ROXPH 3=5 /HDNDJH

'WLPH JDO JDO 3=5 /HDNDJH BBBBBBBBBBPLQ 3=5 /HDNDJH BBBBBBBBBBBB JSP 1$

Performed By 1$

Reviewed By

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The multiplier used in the following equation is the RCS Temperature Correction Volumetric constant as determined by engineering.

A. Initial Conditions:

RCS pressure ________psig 14.7 ________psia RCS temperature ________qF

Key Ke ey

3/lbm Specific volume (vi) ________ft

Density 1/vi ________lbm/ft 3 B. Final Conditions:

_

RCS pressure ________psig

_______

__psig 14.7 ________psia

RCS temperature temperatur ________qF

Specific volum

volume (vi) ________ft 3/lbm

_______ft /

Density 1/vi ________lbm/ft

___lbm 3 C. Temperature Correction:

[(

lbm/ftm/ft3) - ( lbm lbm/ft3)]

1298.19 ga 3 / lbm 1298.1 gal*ft Temp Corr. = Initial Density it Final Density

time

Temperature Correction ___________GPM

7RWDO5&6/HDNDJH

.519

( )+ ( )+ ( )

Total RCS Leakage =

VCT PZR Temp Corr 1.319

Total RCS Leakage ________GPM ________

Performed By Reviewed By

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Leakage into the PRT or CLA tanks will always be a positive value (or zero) when RCS pressure is greater than the specific tanks pressure. If negative leakage is calculated under these conditions, that tanks leakage must be set equal to zero.

3UHVVXUL]HU5HOLHI7DQN 357

Key

[( gal) - ( gal)]

Final Volume Initial Volume PRT Leakage =

( min)

' Time

PRT Leakage __________GPM 127(

127(

RCDT Level (2.2) may be marked N/A if conditions do NOT permit obtaining obt obtainin RCDT level.

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[( gal)

l) - ( gal)]

l)]

Final Volume Initial Volume RCDT Leakage =

( min)

' Time

RCDT Leakage __________GPM Performed By Reviewed By

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1) SG leak rates are obtained by 1, 2SICEM068137.5. 0SICEM000050.3 is performed every 31 days and looks at activity levels which will determine if those leak rates from the last performance of 1, 2SICEM068137.5 have risen.

2) Individual steam generator leakage may be N/Adif activity is too low to be separately identified.

Key ey A.

SG1 Leakage ________GPD B.

SG2 Leakage ________GPD C. __

SG3 Leakage ________GPD D. __GPD

SG4 Leakage ________GPD Totall SG leakage

leakag ___________GPD

___ GPD D

________GPM 1440 min/day Date/Time me 0 0SICEMM000 0SICEM000050.3 00005 50.3 performed: /DVW1LJKW DVW1LJ

Da Date Time Date/Time 1, 2SICEM068137.5 performed: /DVW1LJKW

/DVW

Date Time Recorded by

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CLA leakage calculations may be marked N/A if RCS pressure is greater than 683 psig and quantification of CLA leakage is NOT required.

A. CLA 1 Leakage

§ * § *º

<<¨© Final Volume gal¸¹ - ¨© Initial Volume gal¸¹ >>

¬ 1/4 Key Key

§ *

¨ min¸

§ * § *º

<<¨© Final Volume Vo gall¸ - ¨

¹ © Initial Volum Volume gall¸ >>

¹1/4

¬

§ *

¨ min n¸

__________GP C. CLA 3 Leakage

§ * § *º

<<¨© Final Volume gall¸ l¸ ¨

¹ © Initial Volume gall¸ >>

¹1/4

¬

§ *

¨ min¸

§ * § *º

<<¨© Final Volume gal¸¹ ¨© Initial Volume gal¸¹ >>

¬ 1/4

§ *

¨ min¸

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The following value may be marked N/A if no additional identified leakage sources (i.e.,

Attachment 1) are to be included.

1$

Other identified leakage (Attachment 1) ________GPM Key 127(

If NO CCPIT de-pressurization essurization / pres pressurization activity has occurred during the stabilization period, CCPIT/HUT T leakage may be marked N/A.

7RWDO,GHQWLILHG/HDNDJH

LILHG/HDNDJH LILHG/HDNDJ

________

_________

Total identified ________________________

fied leakage ________

P PRT RCDTDT SG

_______ _

__________

_______________________________

A Total CLA CCPIT/HUT Other

Total identified leakage ________GPM

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Unidentified leakage ________________________________

Total leakage Identified leakage 1.309

Unidentified leakage ________GPM Performed By Reviewed By (QGRI6HFWLRQ

Sequoyah Nuclear Plant Unit 1 & 2 Surveillance Instruction 0-SI-OPS-068-137.0 Reactor Coolant System Water Inventory Revision 0041 Quality Related Level of Use: Continuous Use Effective Date: 06-03-2019 Responsible Organization: OPS, Operations Prepared By: S. A. Meyer Approved By: D. A. Porter

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 2 of 95 Current Revision Description Revised section 3.1, 6.1, and 7.0 for T-MOD 2-2019-063-001, SI System Continuous Pressure Relief Line.

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 3 of 95 Table of Contents

1.0 INTRODUCTION

.......................................................................................................... 5 1.1 Purpose ........................................................................................................................ 5 1.2 Scope............................................................................................................................ 5 1.2.1 Surveillance Test to be Performed .................................................................. 5 1.2.2 Requirements Fulfilled .................................................................................... 5 1.2.3 Modes ............................................................................................................. 6 1.3 Frequency and Conditions ............................................................................................ 6

2.0 REFERENCES

............................................................................................................. 6 2.1 Performance References .............................................................................................. 6 2.2 Developmental References........................................................................................... 7 2.3 Commitments................................................................................................................ 8 3.0 PRECAUTIONS AND LIMITATIONS ........................................................................... 9 3.1 Precautions ................................................................................................................... 9 3.2 Limitations................................................................................................................... 11 3.2.1 Manual Calculations...................................................................................... 11 3.2.2 Plant Computer ............................................................................................. 12 4.0 PREREQUISITE ACTIONS ........................................................................................ 14 4.1 Preliminary Actions ..................................................................................................... 14 4.2 Measuring and Test Equipment, Parts, and Supplies ................................................. 16 4.3 Field Preparations ....................................................................................................... 17 4.4 Approvals and Notifications ........................................................................................ 17 5.0 ACCEPTANCE CRITERIA ......................................................................................... 18 6.0 PERFORMANCE ........................................................................................................ 19 6.1 Preliminary Actions ..................................................................................................... 19 6.2 MANUAL calculation method ...................................................................................... 19 6.2.1 Data Collection for MANUAL calculation method .......................................... 19 6.2.2 Calculation of RCS Leakage using the MANUAL method............................. 26 6.2.3 Restoration using the MANUAL method ....................................................... 30 6.3 RCS LEAKAGE USING THE PLANT COMPUTER .................................................... 32 7.0 POST PERFORMANCE ACTIVITY ............................................................................ 43

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 4 of 95 Table of Contents (continued) 8.0 RECORDS .................................................................................................................. 45 : IDENTIFICATION OF RCS LEAKAGE ...................................................... 46 : REACTOR COOLANT DRAIN TANK LEAKAGE ...................................... 47 : INITIAL / FINAL DATA ............................................................................... 50 : RCS LEAKAGE CALCULATIONS ............................................................ 61 : LEVEL VS. VOLUME TABLES .................................................................. 71 : RCS Leak Source Identification ............................................................... 73 : Leak Search Support Checklist ............................................................... 77 : Leak Search Baseline Data ...................................................................... 79 : Relief Valve Checklist ............................................................................... 80 0: Valves with Stem Leakoffs ....................................................................... 81 1: Process of Isolating Trains and/or Components ................................... 82 2: Leak Detection Via Thermal Imaging ...................................................... 84

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 5 of 95

1.0 INTRODUCTION

1.1 Purpose This Instruction provides detailed steps for performing a water inventory balance on the Reactor Coolant System (RCS).

1.2 Scope 1.2.1 Surveillance Test to be Performed This SI performs a detailed water inventory balance on the RCS to determine the total identified and unidentified RCS leakage. These values are then compared to applicable sections of Technical Specification (TS) Limiting Condition for Operation (LCO) 3.4.13 and to the administrative limits on S/G leakage and unidentified leakage.

1.2.2 Requirements Fulfilled A. Performance of this instruction completely fulfills TS 3.4.13 surveillance requirement (SR) 3.4.13.1 & 3.4.13.2.

B. Performance of this instruction may be utilized to fulfill TS LCO 3.4.15 Required Action A or B on a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months frequency, however is NOT required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

C. This procedure implements, in part, License Renewal Aging Management Program Nickel Alloy Inspection Program UFSAR Section 13, Appendix A, A.1.23. [C.4]

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 6 of 95 1.2.3 Modes Plant operating modes for which the surveillance requirements covered by this Instruction must be satisfied (applicable modes) and during which the test can be performed (performance modes) are:

A. Applicable Modes: 1, 2, 3, and 4 B. Performance Modes: 1 through 5 1.3 Frequency and Conditions A. This SI must be performed at least once every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , however is NOT required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state plant conditions.

B. This SI may be performed at least once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to satisfy LCO 3.4.15 Required Action A.

C. This SI may be performed at least once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to satisfy LCO 3.4.15 Required Action B in lieu of performance of SI-183, Lower Containment Gaseous and Particulate Radioactivity Monitoring During Periods of Radiation Monitor Inoperability.

2.0 REFERENCES

2.1 Performance References A. 0SICEM000050.3, Secondary Coolant Activity Determination.

B. 1, 2SICEM068137.5, PrimaryToSecondary Leakage Via Steam Generators.

C. 0-TI-SXX-068-001.0, RCS Leakage Monitoring and Action Plans.

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 7 of 95 2.2 Developmental References A. SQN Unit 1 & 2 Technical Specifications.

B. SI137.1, Reactor Coolant System Unidentified Leakage Measurement.

C. SQN Updated Final Safety Analysis Report (UFSAR):

1. Section 5.2.7, Table 5.11

2. Section 13, Appendix A, A.1.23, Nickel Alloy Inspection Program.

D. Westinghouse Calculation No. PDC7623, Pressurizer Level Channel Cross Reference, G. Richard, November 15, 1976. (Information Sheet from Westinghouse, S. O. No. TVA 320).

E. Westinghouse Letter TVA88533, Steam Generator Secondary Water Volume, T. A. Lordi to J. B. Hosmer, February 11, 1988.

F. TVA Drawings 47W8012; 47W8091, 2; 47W8131; and 47W8301.

G. Westinghouse Drawing 1099J91.

H. TI41.68, Scaling and Setpoint Document Reactor Coolant System.

I. ONPSTD4.4.7, Attachment 1, Writers Guide for Technical Documents.

J. Safety Evaluation, Reg Guide 1.121 Eval of SQN 1 S/G Circumferential Defect.

K. STA Log.

L. NPG-SPP06.9.1, Conduct of Testing.

M. Westinghouse Safety Evaluation, SECL91431, Circumferential Oriented Primary Water Stress Corrosion Cracking WEXTEX Region.

N. Integrated Computer System, NSSS Critical Design Review, Chapter 9, RCS Leakage Rate.

O. TSC 05-09.

P. WCAP-16423-NP, Pressurized Water Reactor Owners Group Standard Process and Methods for Calculating RCS Leak Rate for Pressurized Water Reactors.

Q. WCAP-16465-NP, Pressurized Water Reactor Owners Group Standard RCS Leakage Action Level and Response Guidelines for Pressurized Water Reactors.

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 8 of 95 2.2 Developmental References (continued)

R. License Renewal Application (LRA) Commitment #42, NCO 115566210.

S. License Renewal Application (LRA) Commitment #42, NCO 115566256.

2.3 Commitments Implementing Requirements Statement Source Document Statement Take RCDT data over same interval as NRC Exit with C. Chung C.1 other data. The test should last at (13088) least two hours. All Tavg changes shall be considered.

Steps to take when negative NRC Inspection Report C.2 unidentified leakage is calculated. 50327,328/8916.

Revised corrective action for NOV 50327, 328/891602 L44 891226 801 Procedures that do NOT contain TROI NCO 970071001 C.3 appropriate verification requirements will be revised. This item is NOT annotated within the procedure, since the entire procedure must meet the verification program requirements Nickel Alloy Inspection Program SQN 1, NCO 115566210 C.4 SQN 2, NCO 115566256 To require the sampling of the Safety NCO970034001 C.5 Injection pump suction piping and TSC-96-01 verify that a sufficient boron concentration exists whenever leakage into the Safety Injection System from the Reactor Coolant System is confirmed.

End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 9 of 95 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions A. A short-term leak rate calculation is available on ICS (NSSS and BOP screen).

This function is intended for use in conjunction with AOP-R.01 (S/G Tube Leak) or AOP-R.05 (RCS Leak) when significant leakage exists. It may be used to estimate the leak rate for REP classification or to help determine if a leak has been successfully isolated. Due to the reduced accuracy of the calculation over short time intervals, this function should NOT be used to verify compliance with Tech Spec RCS leakage limits.

B. Stability of the RCS during performance of this test is of utmost importance. It is essential that the end points for RCS temperature and pressure be as close as possible to the RCS temperature and pressure values used at the beginning of the test.

C. Two hours is the minimum test duration. Use of a longer test duration (3, 4 or 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ) is preferred, but NOT required.

D. The administrative limit for primarytosecondary leakage to an individual SG is 75 GPD. This reduced limit is due to the circumferential cracking of SG tubes at the tube sheet caused by primary water stress corrosion cracking. The limit is obtained from EPRI PWR Primary-To-Secondary Leak Guidelines.

E. All attempts to identify RCS leakage in accordance with Attachment 1 must be completed before proceeding past Section 6.2. This is NOT meant to delay the completion of this test; rather, to identify as many sources of RCS leakage as possible while performing Section 6.2.

F. The Reactor Coolant Drain Tank (RCDT) level data may be marked N/A if conditions do NOT permit obtaining RCDT level. The leakage into the RCDT in this case will be accounted for as unidentified leakage.

G. During the performance of this Instruction, it is expected that the unidentified leakage will occasionally be determined to be less than zero (i.e., negative leakage). If negative leakage is calculated to be more negative than

0.10 gpm, then the following sequence of actions are taken: [C.2]

1. A minimum of one hour of additional data is collected and all calculations are reperformed (at the discretion of the Test Director, any twohour block or longer of data may be used provided all PRECAUTIONS AND LIMITATIONS are satisfied). [C.2]

2. If the unidentified leakage calculated using the additional data is equal to or more positive than 0.10 GPM, this value may be recorded as an acceptable result. [C.2]

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 10 of 95 3.1 Precautions (continued)

3. If the recalculated unidentified leakage calculated using the additional data is more negative than 0.10 GPM, the test must be continued until:

[C.2]

a. The calculated value of unidentified leakage is equal to or more positive than 0.10 GPM, or

b. The total RCS leakage is less than or equal to 1.0 gpm, or

c. A condition occurs which causes the test to be aborted (e.g., makeup to the VCT).

4. If an unidentified leakage equal to or more positive than 0.10 GPM can NOT be obtained but the total RCS leakage is less than or equal to 1.0 GPM, the calculated value of unidentified leakage may be recorded as an acceptable result provided an investigation is initiated by Systems Engineering and Operations to determine the source of the negative calculation. If the total RCS leakage is greater than 1.0 GPM (coincident with an unidentified leakage more negative than 0.1 GPM), then nonRCS inleakage may be masking the true RCS leakage and the validity of the test is questionable. Under these conditions, the test must be continued until the above described criteria are satisfied or a condition occurs which causes the test to be aborted. [C.2]

5. If four consecutive tests result in negative values for unidentified leakage, an investigation into the source of the inleakage must be initiated regardless of whether or NOT the above described criteria are satisfied.

[C.2]

H. Once a suitable window has been established for the test, the first result obtained should be recorded. Any repetition of testing to obtain favorable results within the window creates a bias in the RCS Leakage Monitoring Program and may lead to unnecessary Action Level entries.

I. Following restart from a refueling outage, RCS leak rate results for the first 7-10 days may not be accurate. It takes time for equipment packing and gaskets to swell and for the leak rate to stabilize.

J. Responses to exceeding Action Levels (step 7.0[5]) based solely on statistical deviations from baseline mean (P) while establishing a new baseline should not be made without consultation with Engineering.

K. (Unit 2 Only) T-Mod 2-2019-063-001 installs a temporary vent line from the SI Pump discharge piping to the suction of the Charging Pumps. This vent line must be isolated when measuring RCS leakage.

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 11 of 95 3.2 Limitations 3.2.1 Manual Calculations A. The final RCS temperature must be within r 1qF of the initial RCS temperature or the final data is VOID and must be retaken.

B. The final core power level must be within r 2.0 % of the initial core power level or the final data is VOID and must be retaken.

C. All pumps, coolers, valve alignments, etc. which could affect RCS leakage results must remain constant for 30 minutes before starting and throughout the performance, unless specified by this Instruction or otherwise directed by the Unit Senior Reactor Operator (SRO).

D. The same instrumentation shall be used when recording initial and final values of RCS parameters. Differences between two instruments monitoring the same parameter could be misinterpreted as RCS leakage.

E. No samples shall be taken from, nor chemical additions made to, the RCS during the performance of this instruction. An exception is RCS Zinc Injection, which is NOT detectable within the instrumentation and testing parameters.

F. If any of the following events occur during the performance, the data is VOID and the test must be restarted or the system returned to normal.

1. Emergency boration.

2. Diversion of letdown to the holdup tanks.

3. Makeup from any source.

4. Change in purification demineralizers or filter lineup.

5. Failure of any instrument channel used to obtain initial readings.

6. Failure to use data for at least a two (2) hour time period.

7. VCT level falls below 10% or low VCT level alarm annunciates.

8. Restarting the primary water pumps if they were stopped before the initial data was collected.

9. CCPIT de-pressurization/ pressurization activity.

G. Containment pressure and temperature should remain approximately stable (normal trends acceptable).

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 12 of 95 3.2.2 Plant Computer A. All pumps, coolers, valve alignments, etc. which could affect RCS leakage results remained constant during data collection, except where makeup was accounted for by the plant computer.

B. Preferably no samples shall be taken from, nor chemical additions made to the RCS. However, the Plant Computer program has provisions for accounting for RCS leakage changes. Any samples or additions should be noted in the Remarks section Data Package Cover Sheet. An exception is RCS Zinc Injection, which is NOT detectable within the instrumentation and testing parameters.

C. CVCS and RCS should remain nearly constant (i.e., no diversion of letdown to holdup tanks, no changes in CVCS demineralizer lineup, no changes to filter lineups, no RCS makeup from any source and no CCPIT de-pressurization/

pressurization activity.

D. If any of the following events occur, the data is VOID and the test must be restarted or the system returned to normal.

1. Plant Computer becomes inoperable.

2. Emergency boration.

3. Diversion of letdown to the holdup tanks.

4. Makeup from any source that is NOT accounted for by the Plant Computer program.

5. RCS Dilution

6. Change in purification demineralizers or filter lineup.

7. Failure to use data for at least a two (2) hour time period.

8. CCPIT de-pressurization / pressurization activity.

E. The Plant Computer leakage report shall be attached to the completed SI package to provide documentation in lieu of manually entered data.

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 13 of 95 3.2.2 Plant Computer (continued)

F. The ICS will periodically store data to history for each computer point flagged as an archive point. Depending on the amount of data that is being stored or archived at one time, the computer may take a short period of time to archive the data creating what appears to be a gap in the data. If a selected start or stop time coincides with one of these archive gaps, one of the following alarm messages may appear during the calculation:

START TIME IN ARCHIVE GAP. CALCULATION CANCELLED END TIME IN ARCHIVE GAP. CALCULATION CANCELLED.

If either of these messages is received, move the start and/or stop time a few minutes and repeat the calculation.

G. Performance of any of the following while performing the leakage calculation may result in RCS leak rate uncertainty:

1. RCS Makeup or Dilution (Data will be considered Void.)

2. Changing level in the PRT and / or the RCDT.

3. Removal from service of any of the instruments listed in Step 4.1[2].

4. Procedures or activities that result in Control Rod motion.

H. Containment pressure and temperature should remain approximately stable (normal trends acceptable).

End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 14 of 95 4.0 PREREQUISITE ACTIONS NOTE Throughout this Instruction where an IF/THEN statement exists, the step should be marked N/A if condition does NOT exist.

4.1 Preliminary Actions

[1] ENSURE Instruction to be used is a copy of the effective TJ version. ________

NOTE Attachment 3 can be used to manually collect data for any unavailable computer point(s).

[2] IF ICS Points are to be used for leakage determination, THEN IDENTIFY ICS Points that are in service prior to performing leakage calculation:

Computer Points Needed to Perform RCS Water Inventory at 100% Power Parameter Instrument Computer Point I/S Inputs to Total Leakage RCS Temperature Correction RCL AVG Tavg(1) U0484 Loop 1 Tavg T-68-2 T0400A Loop 2 Tavg T-68-25 T0420A Loop 3 Tavg T-68-44 T0440A Loop 4 Tavg T-68-67 T0460A Pzr. Pressure 1/2/3/4 Avg(2) U0482 Pzr. Pressure Ch. I P-68-340 P0480A Pzr. Pressure Ch. II P-68-334 P0481A Pzr. Pressure Ch.III P-68-323 P0482A Pzr. Pressure Ch.IV P-68-322 P0483A

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 15 of 95 4.1 Preliminary Actions (continued)

Computer Points Needed to Perform RCS Water Inventory at 100% Power Parameter Instrument Computer Point I/S Pressurizer Pzr. Level(3) U0483 Pzr. Level Ch. I L-68-339 L0480A Pzr. Level Ch. II L-68-335 L0481A Pzr. Level Ch. III L-68-320 L0482A Volume Control Tank VCT Level L-62-130 L0112A Inputs to Identified RCS Leakage RCDT Level L-77-1 L2400A PRT Level L-68-300 L0485A (1) RCL AVG Tavg is the average of the four narrow range loop temperatures.

(2) Pzr. Pressure 1/2/3/4 Avg is the average of the four narrow range Pressurizer Pressure Channels.

(3) Pzr. Level is the average of the three Pressurizer Level Channels

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 16 of 95 4.2 Measuring and Test Equipment, Parts, and Supplies NOTE The tables in this section may be completed during the performance of Section 6.2, as necessary.

[1] IF any RCS leak sources will be quantified using a stopwatch and container, THEN RECORD the following information for all stopwatches and containers to be used.

TVA ID Number Calibration Due Date Stopwatch Container

[2] IF any other special test equipment will be used during the performance of this Instruction, THEN RECORD the following information for each additional piece of test equipment to be used.

Test Model Accuracy TVA ID Calibration Equipment Due Date

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 17 of 95 4.3 Field Preparations

[1] ENSURE reactor power and RCS average temperature (Tavg) are stable and have varied less than r 2% and TJ r 1qF, respectively, during the calculation test interval. ________

4.4 Approvals and Notifications NOTE During data collection using the Manual Calculation Method (Sect. 6.2), RCS chemical additions and / or sampling invalidate the data and will require a re-initiation of SI performance. During data collection using the Plant Computer (Sect. 6.3), it is preferred that RCS chemical additions and / or sampling NOT take place. If chemical additions or samples are required, then volume MUST be accounted for, in gallons per minute. RCS dilution is NOT allowed during either method of data collection.

[1] CONTACT Chemistry Lab to verify that performance of this SI and limitations imposed on sampling will NOT interfere with any sampling required by Technical Specifications or TJ Technical Requirements Manual. ________

End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 18 of 95 5.0 ACCEPTANCE CRITERIA A. The Technical Specification acceptance criteria is as follows:

RCS operational leakage shall be limited to:

1. 1 gpm unidentified leakage,

2. 10 gpm identified leakage, and

3. 150 gallons per day primary to secondary leakage through anyone steam generator (SG).

B. If any of the Technical Specification criteria are NOT satisfied, the SM must be notified and Required Actions and Completion Times of 3.4.13 Condition A and B satisfied.

C. The administrative acceptance criteria for total primarytosecondary leakage is less than or equal to 75 GPD through any one steam generator. AOP-R.01, Steam Generator Tube Leak, contains required actions and criteria for plant shutdown.

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 19 of 95 6.0 PERFORMANCE 6.1 Preliminary Actions

[1] (Unit 2 Only) ENSURE SI Pump Discharge Piping Temporary Vent Line is isolated using 2-SO-63-5, Emergency Core TJ Cooling System. (N/A for Unit 1) ________

NOTE Maintaining the pressurizer pressure control and pressurizer level control systems in the automatic mode during data collection will improve RCS stability.

[2] IF using the Plant Computer, THEN GO TO Section 6.3.

[3] IF using MANUAL calculations, THEN GO TO Section 6.2.

6.2 MANUAL calculation method 6.2.1 Data Collection for MANUAL calculation method

[1] ENSURE VCT level is such that makeup is NOT anticipated for TJ the duration of this test. ________

NOTES

1) The applicable section of 1, 2SO771 is dependent upon where the RCDT is to be pumped.

2) The following step may be marked N/A if conditions do NOT permit obtaining RCDT level.

[2] IF reactor coolant drain tank (RCDT) level is greater than 30%

as indicated by 1, 2LI771, THEN GO TO 1, 2SO771.

PERFORM the applicable section, AND RETURN to step 6.2.1[3] of this section. ________

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 20 of 95 6.2.1 Data Collection for MANUAL calculation method (continued)

NOTE The following step may be marked N/A if conditions do NOT permit obtaining RCDT level.

[3] PLACE both RCDT pumps hand switches in the PULLTOLOCK position:

PUMP HANDSWITCH REQUIRED POSITION INITIALS A HS774A PULLTOLOCK TJ B HS776A PULLTOLOCK TJ NOTE Steam generator primary to secondary leak rates required by Section 2.3 of Attachment 4 may be obtained from the Chemistry Lab at the time the following notification is performed.

[4] NOTIFY Chemistry Lab of the following:

[4.1] ENSURE no chemical additions to, nor take samples from, the RCS until further notice. An exception is RCS Zinc Injection, which is NOT detectable within the TJ instrumentation and testing parameters. ________

[4.2] ENSURE 0SICEM000050.3 has been performed TJ within the last 31 days. ________

[5] ENSURE the following system lineup ESTABLISHED:

VALVE DESCRIPTION POSITION INITIALS FCV62118 VCT Isolation Valve To VCT TJ FCV62128 Blender Output to VCT CLOSED TJ FCV62144 Blender Output to CCPs CLOSED TJ FCV62138 Emerg Boration to CCPs CLOSED TJ PCV68301 PRT Vent to RCDT CLOSED TJ FCV68310 PRT Drain to RCDT CLOSED TJ

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 21 of 95 6.2.1 Data Collection for MANUAL calculation method (continued)

NOTE Primary water pumps should be shut off only if primary water in-leakage is suspected, the last performance of this SI resulted in a negative value for unidentified leakage, or if directed by the Unit SRO.

[6] IF primary water pumps will be shut off during data collection, THEN

[6.1] PLACE both primary water pumps hand switches in the PULLTOLOCK position:

PUMP HANDSWITCH POSITION INITIALS A HS813A PULLTOLOCK TJ B HS817A PULLTOLOCK TJ

[6.2] ENSURE 081519, Primary Water Unit Crosstie Valve TJ is LOCKED CLOSED. ________

[7] IF RCS conditions are NOT stable and it is desired to do a calculation from the current time, THEN WAIT approximately 30 minutes to allow RCS parameters to stabilize, AND RECORD any remarks regarding RCS stability in the chronological test log. ________

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 22 of 95 6.2.1 Data Collection for MANUAL calculation method (continued)

NOTE The following step may be marked N/A if conditions do NOT permit obtaining RCDT level.

[8] IF pump down of the RCDT is required during the 30minute waiting period, THEN

[8.1] GO TO 1, 2SO771. ________

[8.2] PERFORM the applicable section, AND RETURN to step 6.2.1[8.3] of this section. ________

[8.3] RETURN both RCDT pumps handswitches to the PULLTOLOCK position:

PUMP HANDSWITCH POSITION INITIALS A HS774A PULLTOLOCK B HS776A PULLTOLOCK

[9] IF additional methods will be used to quantify RCS leakage, THEN INITIATE performance of Attachment 1. ________

NOTES

1) When bench board instruments are used, the first instrument read will initiate the timed duration of this test (minimum of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ).

2) RCS Tavg should be maintained within a r 1.0qF band for at least 5 minutes before data collection is initiated.

[10] RECORD initial RCS data required by Attachment 3.

[11] ENSURE all readings are taken at approximately the same TJ time. [C.1] ________

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 23 of 95 6.2.1 Data Collection for MANUAL calculation method (continued)

[12] IF pump down(s) of the RCDT (level greater than 45%) is required before final RCS data is recorded, THEN COMPLETE RCDT pump down in accordance with Attachment 2 before proceeding to step 6.2.1[13]. ________

NOTES

1) Two hours is the minimum test duration. If desired, the final data may be voided and retaken to lengthen the test. Extending the length of the test will reduce the adverse impact of variations in RCS temperature and reactor power.

2) When using bench board instruments, the last instrument read will determine the finish time of the data collection.

3) RCS Tavg should be maintained within a r 1.0qF band for at least 5 minutes before data collection is initiated.

[13] WHEN a minimum of two hours has elapsed since initial data collection, THEN [C.1]

[13.1] RECORD final RCS data required by Attachment 3.

[13.2] ENSURE all readings are taken at approximately the same time. [C.1]

NOTE Depressurization of RHR discharge piping using 1,2-SO-63-5 is acceptable during the performance of 0-SI-OPS-068-137.0.

[14] IF Attachment 1 is being used to quantify additional RCS leakage sources, THEN ENSURE Attachment 1 has been completed. ________

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 24 of 95 6.2.1 Data Collection for MANUAL calculation method (continued)

[15] WHEN final data collection has been completed, THEN CHECK appropriate boxes to indicate whether initial and final data are acceptable.

[15.1] Were final reactor power and RCS temperature within r 2% and r 1qF, respectively, of their initial readings?

YES NO

[15.2] Have all pumps, coolers, valve alignments, etc. which could affect RCS leakage results remained constant during data collection (except as specified otherwise by this Instruction or the Unit SRO).

YES NO

[15.3] Have the CVCS and RCS remained nearly constant (i.e.,

no VCT makeup, no diversion of letdown to holdup tanks, no changes in CVCS demineralizer lineup, no changes to filter lineups, and no CCPIT de-pressurization/ pressurization activity and no RCS makeup from any source)?

YES NO

[15.4] Were sampling and chemical additions to the RCS (with the exception of RCS Zinc Injection) stopped during data collection?

YES NO

[15.5] Were the same instruments/points used for recording initial and final data?

YES NO

[15.6] Were initial and final RCDT data taken at the same time as the other data?

N/A YES NO

[15.7] Was data collection performed over a minimum of two hours?

YES NO TJ

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 25 of 95 6.2.1 Data Collection for MANUAL calculation method (continued)

[16] IF any box in step 6.2.1[15] is checked NO, THEN

[16.1] TERMINATE this test. ________

[16.2] NOTIFY the Unit SRO that the test was invalid. ________

[16.3] NOTE in Remarks section of chronological test log why test has been aborted. ________

[16.4] OBTAIN a working copy of this procedure to restart test AND MAINTAIN the working copy in this SI package. ________

End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 26 of 95 6.2.2 Calculation of RCS Leakage using the MANUAL method

[1] CALCULATE total RCS leakage, identified leakage and unidentified leakage in accordance with Attachment 4, AND RECORD below:

A. Total RCS leakage ________GPM B. Identified leakage ________GPM C. Unidentified leakage ________GPM ________

NOTE Copies of Attachment 3, or Attachment 4 may be used to perform steps 6.2.2[2] through 6.2.2[9] provided all copies are included in the data package.

[2] IF unidentified leakage is less than zero by more than

0.1 gpm (i.e., negative leakage), THEN [C.2]

[2.1] COLLECT a minimum of one hour of additional data.

[2.2] RECALCULATE all RCS leakage terms in accordance with Attachment 4.

[2.3] RECORD below:

A. Total RCS leakage ________GPM B. Identified leakage ________GPM C. Unidentified leakage ________GPM ________

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 27 of 95 6.2.2 Calculation of RCS Leakage using the MANUAL method (continued)

NOTE An unidentified leakage more negative than 0.10 GPM may be recorded as an acceptable result provided the total RCS leakage is equal to or less than 1.0 GPM and there is an ongoing investigation to determine the source of the in-leakage. [C.2]

[3] IF unidentified leakage is more negative than 0.10 GPM, THEN CONTINUE data collection and calculation of RCS leakage terms in accordance with Attachment 3, or Attachment 4 by changing the time interval or performing a new calculation until an unidentified leakage term more positive than 0.10 GPM is obtained or total RCS leakage is equal to or less than 1.0 GPM (or until test must be aborted), AND [C.2]

RECORD results below (Mark N/A any blanks NOT used).

A. Calculations completed:

Time ________

Total RCS leakage ________GPM

Identified leakage ________GPM

Unidentified leakage ________GPM ________

B. Calculations completed:

Time ________

Total RCS leakage ________GPM

Identified leakage ________GPM

Unidentified leakage ________GPM ________

C. Calculations completed:

Time ________

Total RCS leakage ________GPM

Identified leakage ________GPM

Unidentified leakage ________GPM ________

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 28 of 95 6.2.2 Calculation of RCS Leakage using the MANUAL method (continued)

[4] IF an unidentified leakage more positive than 0.10 GPM could NOT be obtained, OR IF four consecutive performances of this Instruction have resulted in a negative value of unidentified leakage, THEN NOTIFY Unit SRO and/or cognizant Systems Engineer that an investigation to determine the source of in-leakage to the RCS must be initiated. [C.2] ________

NOTE Maximum may be the same as Total if activity/leakage is too low to identify an individual steam generator.

[5] RECORD maximum leak rate from an individual steam generator and total leak rate from all four steam generators from Section 2.3 of Attachment 4.

A. Max. individual SG leakage ________GPD B. Total SG leakage ________GPM ________

[6] CHECK appropriate box to indicate whether the following acceptance criteria were satisfied.

TECHNICAL SPECIFICATION ACCEPTANCE CRITERIA:

Maximum individual SG leakage is less than or equal to 150 GPD.

YES NO The total identified leakage is less than or equal to 10.0 GPM.

YES NO The total unidentified leakage is less than or equal to 1.0 GPM.

YES NO ADMINISTRATIVE ACCEPTANCE CRITERIA:

The maximum individual SG leakage is less than or equal to 75 GPD.

YES NO

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 29 of 95 6.2.2 Calculation of RCS Leakage using the MANUAL method (continued)

[7] IF any of the Technical Specification acceptance criteria stated in step 6.2.2[6] is NOT satisfied, THEN

[7.1] NOTIFY SM that RCS leakage exceeds limit of Condition A and B of LCO 3.4.13 and Required Actions and Completion Times must be satisfied.

[7.2] REFER TO EPIP1 for REP implementation.

[7.3] ENTER AOP-R.01, Steam Generator Tube Leak, or AOP-R.05, RCS Leak and Leak Source Identification, as applicable.

[8] IF leakage is within Tech Spec limits but exceeds administrative acceptance criteria for S/G leakage, THEN

[8.1] NOTIFY SM that primarytosecondary leakage exceeds administrative limit.

[8.2] ENTER AOP-R.01, Steam Generator Tube Leak.

[9] WHEN all data collection has been completed, THEN NOTIFY Chemistry Lab that RCS sampling/chemical additions may be resumed, as necessary. ________

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 30 of 95 6.2.3 Restoration using the MANUAL method

[1] IF the following RCDT handswitch(es) can be returned to their normal alignment, THEN PLACE the applicable handswitch(es) in required position:

PUMP HANDSWITCH POSITION INITIALS A HS774A PAUTO ________ ________

1st IV B HS776A PAUTO ________ ________

1st IV

[2] IF the RCDT pump handswitch(es) cannot be returned to the required position, THEN NOTIFY the US and ENSURE the position is documented and controlled by an approved configuration control process. ________

[3] IF the Primary Water Pump(s) were stopped for data collection, AND

[3.1] IF handswitch(es) are to be returned to the required position, THEN PLACE the pump handswitch(es) to the required position in accordance with the applicable SO:

PUMP HANDSWITCH POSITION INITIALS A HS813A START/MAN ________ ________

PAUTO 1st IV B HS817A START/MAN ________ ________

PAUTO 1st IV

[3.2] IF handswitch(es) cannot be returned to the required position, THEN NOTIFY the US and ENSURE the position is documented and controlled by an approved configuration control process. ________

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 31 of 95 6.2.3 Restoration using the MANUAL method (continued)

[4] ENSURE the following valves are in their required position:

VALVE REQUIRED FIRST PERSON INDEPENDENT POSITION VERIFICATION FCV779 A AUTO/OPEN ________ ________

FCV7710 AP AUTO/OPEN ________ ________

FCV62128 PAUTO ________ ________

FCV62144 PAUTO ________ ________

FCV62118 PAUTO ________ ________

FCV62138 CLOSED ________ ________

PCV68301 CLOSED ________ ________

FCV68310 CLOSED ________ ________

End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 32 of 95 6.3 RCS LEAKAGE USING THE PLANT COMPUTER NOTES

1) VCT level should be in a range between Auto make-up and Auto divert to the HUT before starting the test. Desired range 25 to 60%.

2) Dilution of the RCS will void data collected.

3) Up to twenty minutes may be needed to stabilize and provide good data if VCT levels are adjusted in step 6.3[1].

[1] CHECK VCT level in desired range:

[1.1] IF VCT level approaching Auto make-up, THEN ADJUST VCT level using 0-SO-62-7 (manual make-up). ________

[1.2] IF VCT level approaching divert to HUT,THEN DIVERT letdown flow to the HUT by turning HS-62-118A to the DIVERT position. ________

[2] WHEN VCT level in desired range, THEN PLACE HS-62-118A in VCT position. ________

[3] ENSURE containment will not require venting for the duration of test. ________

[4] ENSURE containment ventilation will not be required to be realigned for the duration of test. ________

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 33 of 95 6.3 RCS LEAKAGE USING THE PLANT COMPUTER (continued)

NOTES

1) Plant computer uses historical data for calculations. The minimum test duration is two hours. Use of a longer test duration (3, 4 or 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ) is preferred, but NOT required.

2) Stable conditions result in reactor power and RCS average temperature (Tavg) having NOT varied more than r 2% and r 1qF, respectively, and pressurizer, PRT, VCT, and RCDT levels NOT changing excessively over the calculation period.

3) Once a suitable window has been established for the test, the first result obtained should be recorded. Any auctioneering of possible results within the window creates a bias in the RCS Leakage Monitoring Program and may lead to unnecessary Action Level entries.

[5] IF any computer point is inoperable OR the value is suspect, THEN INITIATE Attachment 3 to collect data manually as required. ________

[6] MAINTAIN plant conditions as stable as possible (minimum of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ).

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 34 of 95 6.3 RCS LEAKAGE USING THE PLANT COMPUTER (continued)

NOTES

1) SG leak rates are obtained by 1, 2SICEM068137.5. 0SICEM000050.3 is performed every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months at activity levels which will determine if those leak rates from the last performance of 1, 2SICEM068137.5 have risen.

2) Individual steam generator leakage may be marked N/A if activity is too low to be separately identified.

[7] REQUEST from Chemistry Lab the following:

A. SG 1 Leakage ________GPD B. SG 2 Leakage ________GPD C. SG 3 Leakage ________GPD D. SG 4 Leakage ________GPD Total SG leakage ___________GPD ________GPM 1440 min/day Date/Time 0SICEM000050.3 performed:

Date Time Date/Time 1, 2SICEM068137.5 performed:

Date Time NOTE Selected performance period (time interval) is that period chosen by the operator to perform this instruction. Water additions or samples taken from RCS must be converted to gallons per minute.

[7.1] DETERMINE the amount of any chemical additions made to or samples taken from the RCS during the selected performance period, with the exception of RCS Zinc Injection, which is NOT detectable within the instrumentation and testing parameters.

(to be recorded in computer as Other Sources in gpm):

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 35 of 95 6.3 RCS LEAKAGE USING THE PLANT COMPUTER (continued)

[8] IF volume from any source (chemical addition, sampling, or makeup) cannot be determined from the selected performance period, THEN PERFORM one of the following (N/A other):

[8.1] CHANGE the selected performance period (time interval) so known volume changes can be used AND REPEAT the instruction.

[8.2] PERFORM Section 6.2, step 6.2.1[1] through 6.2.1[14],

THEN GO TO step 6.3[9].

[9] IF pump down of the RCDT is a frequent occurrence, THEN PERFORM one of the following (N/A other):

[9.1] WAIT for computer to build a file history (greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) after the RCDT is initially pumped down AND REPEAT the instruction.

[9.2] COMPLETE RCDT pump down in accordance with Attachment 2. ________

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 36 of 95 6.3 RCS LEAKAGE USING THE PLANT COMPUTER (continued)

[10] IF inleakage to the CLA, THEN

[10.1] RECORD initial CLA levels in Attachment 3 and wait at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

[10.2] WHEN greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months has elapsed, THEN RECORD final CLA levels in Attachment 3.

NOTES

1) Plant Computer cannot look ahead and determine leakage rates. All leakage rates must be determined from past points.

2) The ICS will periodically store data to history for each computer point flagged as an archive point. Depending on the amount of data that is being stored or archived at one time, the computer may take a short period of time to archive the data creating what appears to be a gap in the data. If a selected start or stop time coincides with one of these archive gaps, one of the following alarm messages may appear during the calculation:

START TIME IN ARCHIVE GAP. CALCULATION CANCELLED END TIME IN ARCHIVE GAP. CALCULATION CANCELLED.

If either of these messages is received, move the start and/or stop time a few minutes and repeat the calculation.

[11] INITIATE RCS Leakage Program using the Plant Computer by performing the following:

[11.1] SELECT NSSS & BOP menu on monitor.

[11.2] SELECT SI137.0, RCS leakage screen on monitor.

[11.3] ENSURE correct START date and time entered in Plant Computer.

[11.4] ENSURE correct STOP date and time entered in Plant Computer.

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 37 of 95 6.3 RCS LEAKAGE USING THE PLANT COMPUTER (continued)

NOTE If initial and final volume data is to be manually inserted into the computer, then the start/stop times to be entered into the computer must coincide with the time interval the data was taken.

[12] MANUALLY enter the following:

[12.1] SG leakages from Chemistry.

NOTE CLA leakage calculations may be marked N/A if the RCS pressure is greater than 683 psig and quantification of the CLA leakage is NOT required.

[12.2] CLA initial and final volumes from Attachment 3 (if required).

NOTE If NO CCPIT de-pressurization / pressurization activity has occurred during the stabilization period, CCPIT/HUT leakage may be marked N/A.

[12.3] CCPIT/HUT leakage (Mark N/A if NOT required).

[12.4] Other leakage sources documented on Attachment 1 or 2 (Mark N/A if NOT required).

NOTE Manual entry for individual parameters will require depressing F1 on normal ICS entry display for calculation.

[12.5] Initial and final values from Attachment 3 for inoperable or suspect computer points. (N/A if NOT required) ________

[13] INITIATE execute for calculation results.

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 38 of 95 6.3 RCS LEAKAGE USING THE PLANT COMPUTER (continued)

NOTE Depressurization of RHR discharge piping using 1,2-SO-63-5 is acceptable during the performance of 0-SI-OPS-068-137.0.

[14] WHEN data collection has been completed, THEN CHECK the following to indicate whether data is acceptable:

[14.1] CHECK dates and times entered for the leak rate performance period are correct and data collection performed over a minimum of two hours. ________

[14.2] CHECK all sampling and chemical additions to the RCS were stopped during data collection or have been accounted for.

(with the exception of RCS Zinc Injection). ________

[14.3] CHECK all pumps, coolers, valve alignments, etc. which could affect RCS leakage results remained constant during data collection, except where makeup was accounted for by the plant computer. ________

[14.4] CHECK the CVCS and RCS remained nearly constant (i.e., no diversion of letdown to holdup tanks, no changes in CVCS demineralizer lineup, no changes to filter lineups, no CCPIT de-pressurization/ pressurization activity and no RCS makeup from any source, except where makeup was accounted for by the plant computer. ________

[14.5] CHECK NO RCS dilution occurred during data taking period. ________

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 39 of 95 6.3 RCS LEAKAGE USING THE PLANT COMPUTER (continued)

[14.6] RECORD the ICS Points that were available during performance of leakage calculation:

Computer Points Needed to Perform RCS Water Inventory at 100% Power Parameter Instrument Computer Point Inputs to Total Leakage RCS Temperature Correction RCL AVG Tavg(1) U0484 Loop 1 Tavg T-68-2 T0400A Loop 2 Tavg T-68-25 T0420A Loop 3 Tavg T-68-44 T0440A Loop 4 Tavg T-68-67 T0460A Pzr. Pressure 1/2/3/4 Avg(2) U0482 Pzr. Pressure Ch. I P-68-340 P0480A Pzr. Pressure Ch. II P-68-334 P0481A Pzr. Pressure Ch.III P-68-323 P0482A Pzr. Pressure Ch.IV P-68-322 P0483A Pressurizer Pzr. Level(3) U0483 Pzr. Level Ch. I L-68-339 L0480A Pzr. Level Ch. II L-68-335 L0481A Pzr. Level Ch. III L-68-320 L0482A Volume Control Tank VCT Level L-62-130 L0112A Inputs to Identified RCS Leakage RCDT Level L-77-1 L2400A PRT Level L-68-300 L0485A (1) RCL AVG Tavg is the average of the four narrow range loop temperatures.

(2) Pzr. Pressure 1/2/3/4 Avg is the average of the four narrow range Pressurizer Pressure Channels.

(3) Pzr. Level is the average of the three Pressurizer Level Channels

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 40 of 95 6.3 RCS LEAKAGE USING THE PLANT COMPUTER (continued)

[14.7] IF ICS Points recorded in Section 4.1[2] do NOT match those recorded in Step 6.3[14.6], THEN ENSURE evaluation of the validity of the data is performed by engineering. ________

[15] IF any substep in step 6.3[14] cannot be completed, THEN

[15.1] TERMINATE this test. ________

[15.2] NOTIFY the Unit SRO that the test was invalid. ________

[15.3] NOTE in chronological test log why test has been aborted. ________

[15.4] OBTAIN a working copy of this procedure to restart test AND MAINTAIN the working copy in this SI package. ________

[15.5] ENSURE HS-62-118A in P-AUTO. ________

1st IV

[16] IF calculation inputs are invalid, THEN

[16.1] INITIATE MANUAL function to correct inputs.

[16.2] INITIATE execute function for calculated results.

[17] PRINT a hard copy of the results.

[18] ATTACH hard copy program output (printout) to surveillance procedure package.

[19] WHEN all data collection has been completed, THEN NOTIFY Chemistry Lab that RCS sampling/chemical additions may be resumed, as necessary.

[20] IF Step 6.3[8.2] was performed for manual data collection, THEN PERFORM Section 6.2.3 for restoration of equipment. ________

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 41 of 95 6.3 RCS LEAKAGE USING THE PLANT COMPUTER (continued)

NOTES

1) Due to the calculation methodology of rounding off numbers, Unidentified Leakage and Identified Leakage may NOT add up to computer generated total RCS leakage when leakage is small.

2) An unidentified leakage more negative than 0.10 GPM may be recorded as an acceptable result provided the total RCS leakage is equal to or less than 1.0 GPM and there is an ongoing investigation to determine the source of the in-leakage. [C.2]

[21] IF unidentified leakage is more negative than 0.10 GPM, THEN REPEAT data collection by changing and/or lengthening the time interval until an unidentified leakage term more positive than 0.10 GPM is obtained or total RCS leakage is equal to or less than 1.0 GPM (or until test must be aborted), AND [C.2]

RECORD results below (Mark N/A any blanks NOT used).

A. Calculations completed:

Time Interval ________

Total RCS leakage ________GPM

Identified leakage ________GPM

Unidentified leakage ________GPM B. Calculations completed:

Time Interval ________

Total RCS leakage ________GPM

Identified leakage ________GPM

Unidentified leakage ________GPM

[22] IF an unidentified leakage more positive than 0.10 GPM could NOT be obtained, OR IF four consecutive performances of this Instruction have resulted in a negative value of unidentified leakage, THEN NOTIFY Unit SRO and/or cognizant Systems Engineer that an investigation to determine the source of in-leakage to the RCS must be initiated. [C.2] ________

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 42 of 95 6.3 RCS LEAKAGE USING THE PLANT COMPUTER (continued)

[23] CHECK appropriate box to indicate whether the following acceptance criteria were satisfied.

TECHNICAL SPECIFICATION ACCEPTANCE CRITERIA:

The maximum individual SG leakage is less than or equal to 150 GPD.

YES NO The total identified leakage is less than or equal to 10.0 GPM.

YES NO The total unidentified leakage is less than or equal to 1.0 GPM.

YES NO ADMINISTRATIVE ACCEPTANCE CRITERIA:

The maximum individual SG leakage is less than or equal to 75 GPD.

YES NO

[24] IF any of the Technical Specification acceptance criteria stated in step 6.3[23] is NOT satisfied, THEN

[24.1] NOTIFY SM that RCS leakage exceeds limit of Condition A and B of LCO 3.4.13 and Required Actions and Completion Times must be satisfied.

[24.2] REFER TO EPIP1 for REP implementation.

[24.3] ENTER AOP-R.01, Steam Generator Tube Leak, or AOP-R.05, RCS Leak, as applicable.

[25] IF leakage is within Tech Spec limits but exceeds administrative acceptance criteria for S/G leakage, THEN

[25.1] NOTIFY SM that primarytosecondary leakage exceeds administrative limit.

[25.2] ENTER AOP-R.01, Steam Generator Tube Leak.

[26] WHEN leakage test is complete, THEN ENSURE HS-62-118A in P-AUTO. ________

1st IV End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 43 of 95 7.0 POST PERFORMANCE ACTIVITY

[1] NOTIFY Unit SRO that test has been completed. ________

[2] (Unit 2 Only) EVALUATE restoring SI Pump Discharge Piping Temporary Vent using 2-SO-63-5, Emergency Core Cooling System. (N/A for Unit 1) ________

NOTES

1) Baseline Mean (P), Standard Deviation (), and graphs of RCS leakage trends are available on S:\Engineering\Systems\Systems Notebook\068 - Reactor Coolant System\Trending and Walkdowns\Trending\SI-137 (RCS Leakage)\Current data.

2) Following restart from a refueling outage, RCS leak rate results for the first 7-10 days may not be accurate. After this time, the Baseline Mean and Standard Deviation from the quarter just prior to the outage should be used during the next 7 days for Action Level purposes until a new baseline can be established.

3) Action Level are defined in 0-TI-SXX-068-001.0 RCS Leakage Monitoring and Action Plans:

x Action Level I is entered when Unidentified RCS leak rates are greater than 0.1 gpm for a seven day rolling average OR if nine consecutive daily Unidentified RCS leak rates are greater than the baseline P.

x Action Level II is entered when two consecutive daily Unidentified RCS leak rates are greater than 0.15 gpm OR if two of three consecutive daily Unidentified RCS leak rates are greater than P + 2.

x Action Level III is entered when one Unidentified RCS leak rate value is greater than 0.30 gpm OR one Unidentified RCS leak rate is greater than P + 3.

[3] COMPARE unidentified leakage results to Baseline Mean (P) and Standard Deviation () values from RCS leakage trends on this unit.

[4] EVALUATE entry into Action Levels defined above.

[5] IF entry into Action Level is confirmed, THEN INITIATE associated actions per 0-TI-SXX-068-001.0 RCS Leakage Monitoring and Action Plans. ________

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 44 of 95 7.0 POST PERFORMANCE ACTIVITY (continued)

[6] IF the result is between 2 and 3 Standard Deviations above the Baseline Mean (P + 2 < unidentified leakage < P + 3),

THEN PERFORM an additional official leak rate calculation later (in the same shift if possible) using different time interval with no overlap. ________

[7] IF the result is 3 or more Standard Deviations above the Baseline Mean (P + 3),

THEN PERFORM the following:

[7.1] PERFORM an additional official leak rate calculation later (in the same shift if possible) using different time interval with no overlap. ________

[7.2] IF rise in leak rate is confirmed by additional calculation(s), THEN PERFORM the following:

[7.2.1] IF leakage exceeds Tech Spec limit, THEN ENSURE AOP-R.05, RCS Leak has been entered.

[7.2.2] EVALUATE recent activities to determine possible causes of rise in leak rate.

[7.2.3] IF leak source has NOT been positively identified THEN PERFORM the following:

x INITIATE leak search USING Attachment 6, RCS Leak Source Identification x REQUEST assistance from Systems Engineering as required.

[7.2.4] INITIATE performance of this SI at least shiftly to monitor leakage trend UNTIL SM determines leak rate is stable (NOT rising).

[7.2.5] ENSURE CR initiated.

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 45 of 95 7.0 POST PERFORMANCE ACTIVITY (continued)

[7.3] IF rise in leak rate is NOT confirmed by additional calculation(s), THEN LOG results in narrative log.

[7.4] INITIATE performance of NPG-SPP-01.12 Nuclear Event Response Process. ________

End of Section 8.0 RECORDS All records are maintained per NPG-SPP-31.2.

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 46 of 95 Attachment 1 (Page 1 of 1)

IDENTIFICATION OF RCS LEAKAGE 1.0 PERFORMANCE NOTES

1) Any attempts to isolate RCS leakage before completing the appropriate section of this Instruction will make the initial and final data VOID.

2) An acceptable method for calculating leakage is to collect leakage in a container of known volume and time the fill with a stopwatch. Leakage calculated in the following step must be a positive number or zero.

3) All test equipment used in the following step must be listed in Section 4.2.

[1] MEASURE and RECORD any other RCS leakage, source of the leakage, and method used to calculate leakage below (Mark N/A any blanks NOT used).

LEAKAGE METHOD APPLICABLE DATA LEAK RATE SOURCE USED (GPM)

[2] SUM all leak rates identified in step 1.0[1], AND RECORD below:

Total leak rate _______GPM ________

End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 47 of 95 Attachment 2 (Page 1 of 3)

REACTOR COOLANT DRAIN TANK LEAKAGE 1.0 PERFORMANCE NOTE The following steps provide instructions for pumping down the RCDT after the initial RCDT pump down has been completed. These instructions may be performed as many times as necessary or marked N/A if they are NOT required.

[1] ENSURE initial time and RCDT level/volume from Attachment 3 have been recorded on Data Sheet B1. ________

[2] WHEN RCDT approaches 50% level, THEN RECORD final time and RCDT level on Data Sheet B1. ________

NOTE The applicable section of 1,2SO771 is dependent upon where the RCDT is to be pumped.

[3] GO TO 1,2SO771 PERFORM the applicable section, AND RETURN to step 1.0[4] of this Attachment. ________

[4] RETURN both RCDT pumps handswitches to the PULLTOLOCK position:

PUMP HANDSWITCH POSITION INITIALS A HS774A PULLTOLOCK B HS776A PULLTOLOCK

[5] RECORD new initial time and RCDT level on Data Sheet B1. ________

[6] CONVERT initial and final RCDT levels to gallons using Table E2 of Attachment 5, AND RECORD on Data Sheet B1.

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 48 of 95 Attachment 2 (Page 2 of 3) 1.0 PERFORMANCE (continued)

[7] CALCULATE RCDT leakage using the following equation, AND

( Gal) - ( Gal)

Initial Volume Final Volume RCDT Leak Rate =

( min.)

' Time RECORD on Data Sheet B1.

[8] WHEN final RCS leakage data has been collected, THEN CALCULATE total of all calculated RCDT leakages, AND RECORD on Data Sheet B1.

[9] CALCULATE average RCDT leakage using the following equation, AND

( GPM)

Total of All Calculated Leakage Avg. RCDT Leak Rate =

( )

Number of Data Points Taken RECORD on Data Sheet B1.

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 49 of 95 Attachment 2 (Page 3 of 3) 1.0 PERFORMANCE (continued)

DATA SHEET B 1 Data Initial Initial Initial Final Final Final Calculated Points Time Level Volume Time Level Volume Leak Rate Taken (%) (Gal) (%) (Gal) (GPM) 1 2

3 4

5 6

7 8

9 10 TOTAL OF ALL CALCULATED RCDT LEAK RATES Average RCDT leak rate ________GPM Data Recorded By Date Data Reviewed By Date End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 50 of 95 Attachment 3 (Page 1 of 11)

INITIAL / FINAL DATA NOTES

1) Copies of this Attachment may be used if more than one data set is required provided all copies are included in the data package.

2) If ICS computer points are inoperable or value is suspect, OR Section 8.0 is being performed, then appropriate section should be used to collect the data. (Steps NOT used should be marked N/A).

1.0 VOLUME CONTROL TANK (VCT) LEVEL

[1] RECORD initial data start time and date:

TJ 2100 Yesterday Initial Data Start Time Date

[2] RECORD initial and final level for chosen instrument (Mark N/A instrument not chosen):

INSTRUMENT INITIAL INITIALS FINAL INITIALS LEVEL LEVEL N/A N/A N/A N/A L0112MA (%) (%)

LI-62-129 50.1 (%) TJ 45.1 (%) TJ

[3] RECORD final data end time and date:

TJ 2300 Yesterday Final Data End Time Date

[4] RECORD total time for data collection:

Initial Data _ Final Data 120 2100 2300 Start Time: End Time = min

' Time PBJ Yesterday Data Reviewed By Date End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 51 of 95 Attachment 3 (Page 2 of 11) 2.0 PRESSURIZER (PZR) LEVEL

[1] RECORD initial data start time and date:

TJ 2100 Yesterday Initial Data Start Time Date

[2] RECORD initial and final level for chosen instrument (Mark N/A instruments not chosen):

INSTRUMENT INITIAL INITIALS FINAL INITIALS LEVEL LEVEL U0483MA N/A (%) N/A N/A (%) N/A 58 TJ 57 TJ LI68320 (%) (%)

N/A N/A N/A N/A LI68335A (%) (%)

N/A (%) N/A N/A (%) N/A LI68339A

[3] RECORD final data end time and date:

TJ 2300

____________________ Yesterday Final Data End Time Date

[4] RECORD total time for data collection:

Initial Data _ Final Data 2100 2300 120 Start Time: End Time = min

' Time PBJ Yesterday Data Reviewed By Date End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 52 of 95 Attachment 3 (Page 3 of 11) 3.0 PRESSURIZER PRESSURE

[1] RECORD initial data start time and date:

TJ 2100 Yesterday Initial Data Start Time Date

[2] IF P greater than or equal to 1700 psig, THEN RECORD initial and final level for chosen instrument (Mark N/A instruments not chosen):

INSTRUMENT INITIAL INITIALS FINAL INITIALS PRESSURE PRESSURE U0482MA N/A (psig) N/A N/A (psig) N/A 2225 (psig) TJ 2225 (psig) TJ PR68340 N/A (psig) N/A N/A (psig) N/A PI68334 N/A (psig) N/A N/A (psig) N/A PI68342A

[3] IF P less than 1700 psig, THEN RECORD initial and final level for chosen instrument (Mark N/A instruments not chosen):

INSTRUMENT INITIAL INITIALS FINAL INITIALS PRESSURE PRESSURE P0499MA N/A (psig) N/A N/A (psig) N/A PI68342A N/A (psig) N/A N/A (psig) N/A PI6866 N/A (psig) N/A N/A (psig) N/A

[4] RECORD final data end time and date:

TJ 2300 Yesterday Final Data End Time Date

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 53 of 95 Attachment 3 (Page 4 of 11) 3.0 PRESSURIZER PRESSURE (continued)

[5] RECORD total time for data collection:

Initial Data _ Final Data 2100 2300 120 Start Time: End Time = min

' Time PBJ Yesterday Data Reviewed By Date End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 54 of 95 Attachment 3 (Page 5 of 11) 4.0 RCS TEMPERATURE (T AVG)

[1] RECORD initial data start time and date:

TJ 2100 Yesterday Initial Data Start Time Date

[2] IF T greater than or equal to 530 qF, THEN RECORD initial and final temperature for chosen instrument (NA instrument not chosen):

INSTRUMENT INITIAL INITIALS FINAL INITIALS TEMP. TEMP.

N/A N/A N/A N/A U0484MA (qF) (qF) 578 TJ 578 TJ TI682E (qF) (qF)

[3] IF T less than 530 qF, THENN/A RECORD initial and final temperature for chosen instrument (NA instruments not chosen):

INSTRUMENT INITIAL INITIALS FINAL INITIALS TEMP. TEMP.

U0486MA N/A N/A N/A N/A (qF) (qF)

N/A N/A N/A N/A U0489MA (qF) (qF)

N/A N/A N/A N/A TR681 (qF) (qF)

[4] RECORD final data end time and date:

TJ 2300 Yesterday Final Data End Time Date

[5] RECORD total time for data collection:

Initial Data 2100 _ Final Data 2300 120 Start Time: End Time = min

' Time PBJ Yesterday Data Reviewed By Date End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 55 of 95 Attachment 3 (Page 6 of 11) 5.0 REACTOR POWER

[1] RECORD initial data start time and date:

TJ 2100 Yesterday Initial Data Start Time Date

[2] RECORD initial and final Reactor Power for chosen instruments (Mark N/A instruments not chosen):

INSTRUMENT INITIAL INITIALS FINAL INITIALS PWR. PWR.

U1127 Percent Rated N/A N/A N/A N/A Core Thermal Power XI925005C Power 100 TJ 100 TJ Range NIS XI925006C Power N/A N/A N/A N/A Range NIS U0485 Average Delta T (use when reactor power N/A is less than 15% OR less N/A N/A N/A than 40% with LEFM unavailable)

[3] RECORD final data end time and date: Yesterday TJ 2300 Final Data End Time Date

[4] RECORD total time for data collection:

Initial Data _ Final Data 2300 2100 120 Start Time: End Time = min

' Time PBJ Yesterday Data Reviewed By Date End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 56 of 95 Attachment 3 (Page 7 of 11) 6.0 PRESSURIZER RELIEF TANK (PRT) LEVEL

[1] RECORD initial data start time and date:

TJ 2100 Yesterday Initial Data Start Time Date

[2] RECORD readings for the chosen instrument (Mark N/A instruments not chosen):

INSTRUMENT INITIAL INITIALS FINAL INITIALS LEVEL LEVEL L0485MA N/A (%) N/A N/A (%) N/A LI-68-300 70 (%) TJ 70 (%) TJ LI-68-312C N/A (%) N/A N/A (%) N/A (Unit 2 only)

[3] RECORD final data end time and date:

TJ 2300

____________________ Yesterday Final Data End Time Date

[4] RECORD total time for data collection:

Initial Data _ Final Data 2100 2300 120 Start Time: End Time = min

' Time PBJ Yesterday Data Reviewed By Date End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 57 of 95 Attachment 3 (Page 8 of 11) 7.0 REACTOR COOLANT DRAIN TANK (RCDT) LEVEL NOTES

1) RCDT Level (7.0) may be marked N/A if conditions do NOT permit obtaining RCDT level.

2) Final RCDT data may be marked N/A if Attachment 4 will be used to calculate average RCDT leakage; however, initial data must be recorded. Table E2 of Attachment 5 is used to convert RCDT level (%) to gallons.

[1] RECORD initial data start time and date:

TJ 2100

____________________ Yesterday Initial Data Start Time Date

[2] RECORD initial readings for the chosen instrument (Mark N/A instrument not chosen):

INSTRUMENT INITIAL INITIAL INITIALS USED LEVEL VOLUME L2400MA N/A (%) N/A (gal) N/A 29 100.4 TJ LI771 (%) (gal)

[3] RECORD final readings for the chosen instrument (Mark N/A instrument not chosen):

INSTRUMENT FINAL FINAL INITIALS USED LEVEL VOLUME L2400MA N/A (%) N/A (gal) N/A LI771 29 (%) 100.4 (gal) TJ

[4] RECORD final data end time and date:

TJ 2300

____________________ Yesterday Final Data End Time Date

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 58 of 95 Attachment 3 (Page 9 of 11) 7.0 REACTOR COOLANT DRAIN TANK (RCDT) LEVEL (continued)

[5] RECORD total time for data collection:

Initial Data _ Final Data 120 2100 2300 Start Time: End Time = min

' Time PBJ Yesterday Data Reviewed By Date End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 59 of 95 Attachment 3 (Page 10 of 11) 8.0 COLD LEG ACCUMULATOR (CLA) LEVEL NOTE CLA data may be marked N/A if RCS pressure is greater than 683 psig and quantification of CLA leakage is NOT required.

[1] RECORD initial data start time and date:

N/A N/A Initial Data Start Time Date

[2] CLA 1 INSTRUMENT INITIAL INITIALS FINAL INITIALS USED VOLUME VOLUME LI63129 N/A (gal) N/A N/A (gal) N/A N/A (gal) N/A N/A (gal) N/A LI63119

[3] CLA 2 INSTRUMENT INITIAL INITIALS FINAL INITIALS USED VOLUME VOLUME N/A (gal) N/A N/A (gal) N/A LI63109 LI6399 N/A (gal) N/A N/A (gal) N/A

[4] CLA 3 INSTRUMENT INITIAL INITIALS FINAL INITIALS USED VOLUME VOLUME N/A (gal) N/A N/A (gal) N/A LI6389 LI6381 N/A (gal) N/A N/A (gal) N/A

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 60 of 95 Attachment 3 (Page 11 of 11) 8.0 COLD LEG ACCUMULATOR (CLA) LEVEL (continued)

[5] CLA 4 INSTRUMENT INITIAL INITIALS FINAL INITIALS USED VOLUME VOLUME LI6382 N/A (gal) N/A N/A (gal) N/A N/A (gal) N/A N/A (gal) N/A LI6360 N/A N/A Final Data End Time Date Initial Data N/A _ Final Data N/A N/A Start Time: End Time = min.

' Time N/A N/A Data Reviewed By Date End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 61 of 95 Attachment 4 (Page 1 of 10)

RCS LEAKAGE CALCULATIONS NOTES

1) All calculations must be performed manually. Verification may be performed using the computer.

2) All calculations should be carried out to two places after the decimal. Signs must be carried through all calculations.

3) Calculations in this Attachment may need to be performed more than once. If multiple calculations are required, copies of this Attachment may be used.

1.0 TOTAL RCS LEAKAGE 1.1 Volume Control Tank (VCT)

[( %) - ( %)] x 19.27 gal/%

Initial Level Final Level VCT Leakage =

min.)

' Time VCT Leakage _________________GPM 1.2 Pressurizer (Pzr) UNIT 2 only

[1] CALCULATE initial PZR volume by using the following equation:

NOTES

1) Vf (specific volume of a fluid) and Vg (specific volume of a gas)values for current plant conditions can be found using a copy of the steam tables.

2) In the following equation the multiplier is the Pressurizer Volumetric Constant determined by engineering.

§ PZRLevel 100 % PZRLevel

3 Initial PZR Vol ¨¨ ¸¸

2.02 gal

ft Vf Vg lb * %level

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 62 of 95 Attachment 4 (Page 2 of 10) 1.2 Pressurizer (Pzr) UNIT 2 only (continued)

§ *

¨ ¸ Initial PZR Vol

¨ %

100 %¸

2 . 02 gal

ft 3

¨ ¸ lb * %level

¨¨ ft 3 ft 3 ¸ m lb lb ¸

[2] CALCULATE Final PZR volume by using the following equation:

NOTES

1) Vf (specific volume of a fluid) and Vg (specific volume of a gas)values for current plant conditions can be found using a copy of the steam tables.

2) In the following equation the multiplier is the Pressurizer Volumetric Constant determined by engineering.

§ PZRLevel 100 % PZRLevel

3 Final PZR Vol ¨¨ ¸¸

2.02 gal

ft Vf Vg lb * %level

§ *

¨ ¸ Final PZR Vol

¨ %

100 %¸

2. 02 gal

ft 3

¨ ¸ lb * %level

¨¨ ft 3 ft 3 ¸ m lb lb ¸

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 63 of 95 Attachment 4 (Page 3 of 10) 1.2 Pressurizer (Pzr) UNIT 2 only (continued)

[3] CALCULATE PZR leakage rate by using the following equation:

Initial PZR Volume Final PZR Volume PZR Leakage

'time gal gal PZR Leakage

__________min PZR Leakage ____________ gpm Performed By Reviewed By

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 64 of 95 Attachment 4 (Page 4 of 10) 1.3 Pressurizer (Pzr) UNIT 1 only

[1] CALCULATE initial PZR volume using the following equation:

NOTES

1) Vf (specific volume of a fluid) and Vg (specific volume of a gas)values for current plant conditions can be found using a copy of the steam tables.

2) In the following equation the multiplier is the Pressurizer Volumetric Constant determined by engineering.

§ PZRLevel 100 % PZRLevel

3 Initial PZR Vol ¨¨ ¸¸

2.01 gal

ft Vf Vg lb * %level

§ *

¨ % 100 %¸ 3 Initial PZR Vol ¨ ¸

2.01 gal

ft

¨ ft3 ft3 ¸ lb m * %level

¨ lb m lb m ¹¸

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 65 of 95 Attachment 4 (Page 5 of 10) 1.3 Pressurizer (Pzr) UNIT 1 only (continued)

[2] CALCULATE Final PZR volume using the following equation:

NOTES

1) Vf (specific volume of a fluid) and Vg (specific volume of a gas)values for current plant conditions can be found using a copy of the steam tables.

2) In the following equation the multiplier is the Pressurizer Volumetric Constant determined by engineering.

§ PZRLevel 100 % PZRLevel

3 Final PZR Vol ¨¨ ¸¸

2.01 gal

ft Vf Vg lb * %level

§ *

¨ % 100 %¸ 3 Final PZR Vol ¨ ¸

2.01 gal

ft

¨ ft3 ft3 ¸ lb m * %level

¨ lb m lb m ¹ ¸

[3] CALCULATE PZR leakage rate using the following equation:

Initial PZR Volume Final PZR Volume PZR Leakage

'time gal gal PZR Leakage

__________min PZR Leakage ____________ gpm Performed By Reviewed By

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 66 of 95 Attachment 4 (Page 6 of 10) 1.4 RCS Temperature Correction [C.1]

NOTE The multiplier used in the following equation is the RCS Temperature Correction Volumetric constant as determined by engineering.

A. Initial Conditions:

RCS pressure ________psig 14.7 ________psia RCS temperature ________qF Specific volume (vi) ________ft3/lbm Density 1/vi ________lbm/ft3 B. Final Conditions:

RCS pressure ________psig 14.7 ________psia RCS temperature ________qF Specific volume (vi) ________ft3/lbm Density 1/vi ________lbm/ft3 C. Temperature Correction:

[( lbm/ft3) - ( lbm/ft3)]

1298.19 gal*ft3 / lbm Temp Corr. = Initial Density Final Density time Temperature Correction ___________GPM 1.5 Total RCS Leakage

( )+ ( )+ ( )

Total RCS Leakage =

VCT PZR Temp Corr Total RCS Leakage ________GPM ________

Performed By Reviewed By

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 67 of 95 Attachment 4 (Page 7 of 10) 2.0 IDENTIFIED LEAKAGE NOTE Leakage into the PRT or CLA tanks will always be a positive value (or zero) when RCS pressure is greater than the specific tanks pressure. If negative leakage is calculated under these conditions, that tanks leakage must be set equal to zero.

2.1 Pressurizer Relief Tank (PRT)

[( gal) - ( gal)]

Final Volume Initial Volume PRT Leakage =

( min)

' Time PRT Leakage __________GPM NOTE RCDT Level (2.2) may be marked N/A if conditions do NOT permit obtaining RCDT level.

2.2 Reactor Coolant Drain Tank (RCDT)

[( gal) - ( gal)]

Final Volume Initial Volume RCDT Leakage =

( min)

' Time RCDT Leakage __________GPM Performed By Reviewed By

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 68 of 95 Attachment 4 (Page 8 of 10) 2.3 Steam Generator (SG)

NOTES

1) SG leak rates are obtained by 1, 2SICEM068137.5. 0SICEM000050.3 is performed every 31 days and looks at activity levels which will determine if those leak rates from the last performance of 1, 2SICEM068137.5 have risen.

2) Individual steam generator leakage may be N/Ad if activity is too low to be separately identified.

A. SG1 Leakage ________GPD B. SG2 Leakage ________GPD C. SG3 Leakage ________GPD D. SG4 Leakage ________GPD Total SG leakage ___________GPD ________GPM 1440 min/day Date/Time 0SICEM000050.3 performed:

Date Time Date/Time 1, 2SICEM068137.5 performed:

Date Time Recorded by

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 69 of 95 Attachment 4 (Page 9 of 10) 2.4 Cold Leg Accumulators (CLA)

NOTE CLA leakage calculations may be marked N/A if RCS pressure is greater than 683 psig and quantification of CLA leakage is NOT required.

A. CLA 1 Leakage

§ * § *º

¬ 1/4

§ *

¨ min¸

§ * § *º

¬ 1/4

§ *

¨ min¸

§ * § *º

¬ 1/4

§ *

¨ min¸

§ * § *º

¬ 1/4

§ *

¨ min¸

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 70 of 95 Attachment 4 (Page 10 of 10) 2.5 Other Identified Leakage NOTE The following value may be marked N/A if no additional identified leakage sources (i.e.,

Attachment 1) are to be included.

Other identified leakage (Attachment 1) ________GPM NOTE If NO CCPIT de-pressurization / pressurization activity has occurred during the stabilization period, CCPIT/HUT leakage may be marked N/A.

2.6 Total Identified Leakage Total identified leakage ________________________

PRT RCDT SG

______________________________

Total CLA CCPIT/HUT Other Total identified leakage ________GPM 3.0 UNIDENTIFIED LEAKAGE Unidentified leakage ________________________________

Total leakage Identified leakage Unidentified leakage ________GPM Performed By Reviewed By End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 71 of 95 Attachment 5 (Page 1 of 2)

LEVEL VS. VOLUME TABLES TABLE E 1 PRESSURIZER RELIEF TANK (PRT)

LEVEL VS. VOLUME Level Volume Level Volume Level Volume Level Volume

(%) (Gal) (%) (Gal) (%) (Gal) (%) (Gal) 0.0 317.0 25.0 3033.7 50.0 6732.9 75.0 10432.0 1.0 387.7 26.0 3170.6 51.0 6886.6 76.0 10567.5 2.0 462.9 27.0 3308.8 52.0 7040.2 77.0 10701.3 3.0 542.4 28.0 3448.4 53.0 7193.8 78.0 10833.6 4.0 626.0 29.0 3589.3 54.0 7347.2 79.0 10964.1 5.0 713.3 30.0 3731.4 55.0 7500.4 80.0 11093.0 6.0 804.1 31.0 3874.6 56.0 7653.3 81.0 11219.9 7.0 898.4 32.0 4018.8 57.0 7805.9 82.0 11345.0 8.0 996.0 33.0 4164.1 58.0 7958.1 83.0 11468.0 9.0 1096.6 34.0 4310.4 59.0 8109.9 84.0 11589.0 10.0 1200.1 35.0 4457.5 60.0 8261.2 85.0 11707.8 11.0 1306.5 36.0 4605.5 61.0 8411.9 86.0 11824.3 12.0 1415.6 37.0 4754.2 62.0 8562.0 87.0 11938.5 13.0 1527.3 38.0 4903.7 63.0 8711.5 88.0 12050.1 14.0 1641.4 39.0 5053.8 64.0 8860.2 89.0 12159.2 15.0 1757.9 40.0 5204.6 65.0 9008.2 90.0 12265.6 16.0 1876.7 41.0 5355.9 66.0 9155.4 91.0 12369.2 17.0 1997.7 42.0 5507.6 67.0 9301.6 92.0 12469.8 18.0 2120.7 43.0 5659.8 68.0 9446.9 93.0 12567.3 19.0 2245.8 44.0 5812.4 69.0 9591.2 94.0 12661.6 20.0 2372.8 45.0 5965.3 70.0 9734.4 95.0 12752.5 21.0 2501.6 46.0 6118.5 71.0 9876.4 96.0 12839.8 22.0 2632.2 47.0 6271.9 72.0 10017.3 97.0 12923.3 23.0 2764.4 48.0 6425.3 73.0 10156.9 98.0 13002.8 24.0 2898.3 49.0 6579.2 74.0 10295.2 99.0 13078.0 100.0 13148.7

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 72 of 95 Attachment 5 (Page 2 of 2)

TABLE E 2 REACTOR COOLANT DRAIN TANK (RCDT)

LEVEL VS. VOLUME Level Volume Level Volume Level Volume Level Volume

(%) (Gal) (%) (Gal) (%) (Gal) (%) (Gal) 0.0 17.4 25.0 86.4 50.0 179.1 75.0 271.8 1.0 19.4 26.0 89.8 51.0 182.9 76.0 275.2 2.0 21.6 27.0 93.3 52.0 186.8 77.0 278.5 3.0 23.8 28.0 96.8 53.0 190.6 78.0 281.7 4.0 26.1 29.0 100.4 54.0 194.5 79.0 285.0 5.0 28.4 30.0 103.9 55.0 198.3 80.0 288.2 6.0 30.8 31.0 107.5 56.0 202.2 81.0 291.3 7.0 33.3 32.0 111.2 57.0 206.0 82.0 294.4 8.0 35.8 33.0 114.8 58.0 209.9 83.0 297.5 9.0 38.4 34.0 118.5 59.0 213.7 84.0 300.5 10.0 41.1 35.0 122.2 60.0 217.4 85.0 303.4 11.0 43.7 36.0 125.3 61.0 221.2 86.0 306.2 12.0 46.4 37.0 129.5 62.0 224.9 87.0 309.1 13.0 49.2 38.0 133.3 63.0 228.7 88.0 311.8 14.0 52.0 39.0 137.1 64.0 232.4 89.0 314.5 15.0 54.9 40.0 140.9 65.0 236.1 90.0 317.2 16.0 57.7 41.0 144.6 66.0 239.8 91.0 319.9 17.0 60.8 42.0 148.4 67.0 243.5 92.0 322.4 18.0 63.8 43.0 152.2 68.0 247.2 93.0 324.9 19.0 66.8 44.0 156.0 69.0 250.8 94.0 327.4 20.0 69.9 45.0 159.8 70.0 254.4 95.0 329.8 21.0 73.2 46.0 163.7 71.0 257.9 96.0 332.1 22.0 76.4 47.0 167.5 72.0 261.5 97.0 334.4 23.0 79.6 48.0 171.4 73.0 265.0 98.0 336.7 24.0 83.0 49.0 175.2 74.0 268.4 99.0 338.7 100.0 340.8

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 73 of 95 Attachment 6 (Page 1 of 4)

RCS Leak Source Identification 1.0 ACTIONS

[1] IF leak rate rises above Acceptance Criteria in Section 5.0, THEN REFER TO AOP-R.05, RCS Leak.

NOTES

1) Three AUOs may be required for performance of this procedure; one on each of two search teams and one to provide continuous communications between the Leak Search Coordinator (LSC) and each of the two search teams. The search communicator is required only when a team searches inside containment.

2) Leak search may be coordinated from MCR, WCC, or TSC, as determined by Shift Manager.

3) Steps 1.0[2] through 1.0[12] may be performed out of sequence.

[2] DESIGNATE a Leak Search Team consisting of the following:

x Leak Search Coordinator (LSC) x AUO support as needed.

[3] NOTIFY LSC to perform Attachment 8.

[4] ENSURE Attachment 7, Leak Search Support Checklist, completed by WCC.

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 74 of 95 Attachment 6 (Page 2 of 4) 1.0 ACTIONS (continued)

[5] DEVELOP action plan using all available data and following guidelines:

x MAINTAIN configuration control.

x EVALUATE LCOs prior to isolating components and/or swapping trains.

x USE placekeeping boxes on attachments as valves are checked to prevent repetition.

x IF at midloop or reduced inventory, THEN PERFORM physical inspection of items on appropriate attachments prior to swapping RHR trains or CCPs.

x USE available data to determine most probable leak location.

x USE noise/flow detecting instruments in conjunction with temperature detecting instruments (e.g., Thermal Imaging Camera, see Attachment 12, Leak Detection Via Thermal Imaging) where applicable.

x REVIEW eSOMS Clearance Module to assist in identifying items to be inspected.

x REVIEW maintenance history provided by WCC.

[6] NOTIFY Chemistry Shift Supervisor to ensure all primary side sample points CLOSED.

[Aux Bldg, el. 690, Hot Sample Room].

[7] DESIGNATE search teams consisting of personnel from:

x Operations (team leader) x Rad Protection (surveyor) x Engineering

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 75 of 95 Attachment 6 (Page 3 of 4) 1.0 ACTIONS (continued)

[8] WHEN searching inside containment, THEN DESIGNATE AUO Search Communicator to work with each search team.

[9] PROVIDE search team members with appropriate appendixes and prints from list below:

x Attachment 7, Leak Search Support Checklist x Attachment 8, Leak Search Baseline Data x Attachment 9, Relief Valve Checklist x Attachment 10, Valves with Stem Leakoffs x Attachment 11, Process of Isolating Trains and/or Components x Attachment 12, Leak Detection Via Thermal Imaging

[10] NOTIFY Rad Protection to establish entry coverage USING 0-PI-OPS-000-011.0, Containment Access Control During Modes 1-4.

[11] NOTIFY SM to obtain management approval for entry into containment and polar crane wall.

[12] MONITOR plant parameters on ICS.

[13] ENSURE record of leak search actions is maintained in Unit Narrative Log.

[14] CONSULT Unit SRO and UOs periodically to provide current status and progress.

[15] DISPATCH search teams to designated areas.

[16] WHEN leak source IDENTIFIED, THEN NOTIFY SM and Unit SRO to develop action plan to mitigate the leak.

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 76 of 95 Attachment 6 (Page 4 of 4) 1.0 ACTIONS (continued)

[17] IF leakage is past primary check valves into Safety Injection System discharge headers, THEN PERFORM the following:

[17.1] OBTAIN a boron sample from both Safety Injection Pump Casing Vents.

[17.2] PERFORM one the following (N/A option not used):

x CHECK the boron concentration of the samples greater than 1950 ppm. [C.1]

x IF either boron sample is verified less than 1950 ppm, THEN CONTACT Engineering for an operability evaluation.

End of Section

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 77 of 95 Attachment 7 (Page 1 of 2)

Leak Search Support Checklist 1.0 ACTIONS NOTES

1) This attachment provides Maintenance with a list of personnel and material recommended for leak search. Leak search may be coordinated from MCR, WCC, or TSC, as determined by Shift Manager.

2) Rad Protection RWPs are necessary to cover action plan.

3) Additional Rad Protection personnel may be needed for containment entry.

4) Heat stress evaluations are required for search team members prior to containment entry.

A. Personnel:

1. Rad Protection Surveyors (two recommended).

2. Engineers (two recommended).

3. Instrument Mechanics (two recommended).

B. Materials

1. Copy of these attachments.

2. Maintenance history including:

a. Work performed on identified items in a time frame consistent when time leak was first suspected including recent outage, maintenance, etc.

b. RCS, RHR, and CVCS drains, vents, and test connection valves that have had flanges or caps removed in a time frame consistent when time leak was first suspected.

C. Appropriate field instruments for search team engineers.

D. Phone with jack and run of extension line.

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 78 of 95 Attachment 7 (Page 2 of 2) 1.0 ACTIONS (continued)

E. Copy of the latest as-constructed prints as follows (preferably 100 percent size):

MECHANICAL PIPING PRINTS FLOW PRINTS 47W465-2 47W809-1 47W465-3 47W810-1 47W465-4 47W811-1 47W465-7 47W813-1 47W465-52 47W852-2 47W465-53

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 79 of 95 Attachment 8 (Page 1 of 1)

Leak Search Baseline Data Mode ________ PRT Condition Temp ________

PZR Level ________ Press ________

Level ________

Reactor Power ________

VCT Level ________ CLA 1 Level ________

CLA 2 Level ________

RCS Temperature ________ CLA 3 Level ________

CLA 4 Level ________

VCT Press ________

RCS Pressure ________ RCDT Condition Temp ________

RHR In Service: Press ________

x Train A Level ________

x Train B Midloop ARBF&E Drain Sump:

Level ________

CVCS Cleanup Rate Of Rise (U0967 Or U0968) ________

Reduced Inventory RBF&E Drain Sump:

CCP In Service: Rate Of Rise x Train A (U0969) ________

x Train B Wafer Valve: Known/Estimated RCS Leak Rate:

x Closed gpm ________

x Open Time ________

RCS Prepared For Fill & Vent Other Information:

Fill & Vent In Progress SFP Gate To Xfer Canal:

Installed Removed

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 80 of 95 Attachment 9 (Page 1 of 1)

Relief Valve Checklist NOTE This attachment identifies relief valves and should be used in conjunction with other appropriate attachments that identify specific leak flow destination points.

EL 690 PIPE CHASE 63-534 A SIS pump disch. RV upstream of FCV-63-152 approx. 7 overhead above A train controls.63-536 B SIS pump disch. RV upstream of FCV-63-153 approx. 11 overhead above B train controls.63-535 RV SI disch. to cold legs el. 698 63-626 RV RHR to 2 3 cold legs 4 from 63-93 and 6 from ceiling.63-627 RV RHR to 1 4 cold legs 6 from 63-94 and 6 from ceiling.63-577 CCPIT RV in front of CCPIT 4-1/2 above floor.

INSIDE CONTAINMENT 62-636 Seal Return RV 62-662 CVCS Letdown RV 63-637 RV on RHR to loops 1 3 hot legs No. 4 Accum. Rm at hatch end and partially up the ladder.74-505 RV RHR pump suction from loop 4 hot leg No. 4 Accum. Rm 4-1/2 from P.C. wall on RHR suction line.

AUXILIARY BUILDING 72-512 A CS pump suction RV in A CS pump rm.

72-513 B CS pump suction RV in A CS pump rm.

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 81 of 95 Attachment 10 (Page 1 of 1)

Valves with Stem Leakoffs 1.0 WHEN ON RHR VALVE DESTINATION OF LEAK OFF FCV-68-332 (PRT)

FCV-68-333 (PRT)

PCV-68-340B (PRT)

PCV-68-340D (PRT)74-520 (Aux Bldg FEDS)74-521 (Aux Bldg FEDS)

HCV-74-36 (Aux Bldg FEDS)

HCV-74-37 (Aux Bldg FEDS)74-524 (Aux Bldg FEDS)74-525 (Aux Bldg FEDS)

FCV-74-16 (Aux Bldg FEDS)

FCV-74-28 (Aux Bldg FEDS)

FCV-74-32 (Aux Bldg FEDS)

FCV-74-34 (Aux Bldg FEDS)

FCV-63-94 (TDCT)

FCV-63-172 (PRT) 2.0 WHEN RCS IS ISOLATED FROM RHR, LETDOWN AND CHARGING VALVE DESTINATION OF LEAK OFF FCV-68-332 (PRT)

FCV-68-333 (PRT)

PCV-68-340B (PRT)

PCV-68-340D (PRT)

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 82 of 95 Attachment 11 (Page 1 of 2)

Process of Isolating Trains and/or Components NOTES

1) The process to identify the leakage may also involve isolating trains and/or components provided that one train of one system is affected at a time. Should this be necessary, appropriate Technical Specification LCOs shall be strictly adhered to.

1(2)-SO-62-1, Chemical And Volume Control System; 0-SO-74-1, Residual Heat Removal System; NPG-SPP-10.2, Clearance Procedure may be utilized to remove components from service.

2) For the process of isolating trains and/or components, configuration control shall be stressed and maintained. The LSC will ensure that all trains, components, and sections of the system that are isolated have been identified and documented on the appropriate prints and logged in the LSC journal. This will help to ensure that work is not unnecessarily duplicated.

1.0 MODES 1-4 (LETDOWN AND CHARGING ISOLATED)

NOTE This section assumes that the leak has been determined to be located within that section of the CVCS system that was isolated during the performance of AOP-R.05, RCS Leak.

[1] Evaluate the following leak locations:

x Letdown heat exchanger x Reactor Coolant Filter x CCPs x Mixed Beds x Cation Beds x Chemical Mix Tank x Regenerative Heat Exchanger x Excess Letdown Heat Exchanger

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 83 of 95 Attachment 11 (Page 2 of 2) 2.0 MODES 1-4 (LETDOWN AND CHARGING IN SERVICE)

NOTE This section assumes that letdown and charging have:

x previously been isolated, x been determined not to be the source of the leak, x been returned to service.

[1] Evaluate the following leak locations:

x Seal Return Line x Seal Water Return Filter x Seal Water Heat Exchanger x Seal Water Injection Filters 3.0 RHR IN SERVICE NOTE Physical inspection of items on appropriate attachments should be performed prior to swapping RHR trains.

[1] Coordinate an effort with the unit SRO to swap RHR pumps in accordance with 0-SO-74-1, Residual Heat Removal System.

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 84 of 95 Attachment 12 (Page 1 of 12)

Leak Detection Via Thermal Imaging A Thermal Imaging Camera may be used to locate leaking valves on lines that drain to the Tritiated Drain Collector Tank (TDCT). This appendix contains a representation of the TDCT, Unit 1 Collection Header, Unit 2 Collection Header, and the Common Collection Header. The collection headers should be the starting point for leak searches when the thermal imaging camera is used.

The following pages list the drains that enter the TDCT. An example of how to use this attachment is as follows: If leakage is suspected from Unit 1, then a thermal image may be taken of drain lines in to the Unit 1 Collection Header. If the image shows elevated temperature on the #7 line entering the collection header, then the leakage can be traced to an instrument drain at coordinates A6-W on elev. 714.

Attachment 12 contains a listing of all equipment that drains into the TDCT. When searching for RCS leaks some equipment drains may be eliminated because they are obviously not the source of RCS leaks, e.g., caustic batching tank drains).

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 85 of 95 Attachment 12 (Page 2 of 12) 1.0 UNIT 1 DRAIN HEADER (NORTH HEADER)

NOTE

(#1 is the most eastern pipe); ED = equip dr.; (O) = open; (C) = closed DRAIN PIPE / ELEVATION EQUIPMENT DRAINS Line SIZE SERVICED Checked

1 (4 in.) elev. 690 2 Sample Sink Dr. Sample Rm 1 2 ED Spare Sample Room 1 (O)

2 (3 in.) elev. 714 3 ED Spare A5-W

3 (4 in.) elev. 714 4 ED Spare A5-W

4 (4 in.) elev. 714 4 ED Spare A5-W

5 (3 in.) elev. 714 2 ED Spent Fuel Hx Dr (O) elev. 714 2 ED Spent Fuel Hx Dr (O)

6 (4 in.) elev. 714 2 Clear Out Letdown Hx Rm elev. 714 2 ED Letdown Hx Rm (O)

7 (3 in.) elev. 714 2 Instrument Dr A6-W (O) elev. 714 2 Instrument Dr A6-U (O)

8 (4 in.) elev. 706 2 ED Spare A2-U (O) 2 ED Caustic Batching elev. 690 Tk Dr (O) 2 ED Caustic Batching Tk elev. 690 Pmp Dr (O) 3 ED Caustic Batching Tk elev. 690 Overflow (O) elev. 690 2 RadioChem Lab Sink Dr elev. 690 2 Clear out A2-U (capped) elev. 690 2 ED Spare A5-U (O) elev. 690 2 ED Seal Water Hx Dr (O) elev. 690 2 ED VCT Dr (O) 2 ED Chemical Mixing elev. 690 Tk Dr (O) elev. 690 2 Clear Out A5-W elev. 690 2 2B CCPIT Funnel Dr (O) elev. 690 2 ED Spare A5-W (O)

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 86 of 95 Attachment 12 (Page 3 of 12) 1.0 UNIT 1 DRAIN HEADER (NORTH HEADER) (continued)

DRAIN PIPE / ELEVATION EQUIPMENT DRAINS Line SIZE SERVICED Checked

9 (4 in.) elev. 706 2 ED Spare Demin Vaults (C) elev. 706 2 ED Spare Demin Vaults (C) elev. 706 2 ED Spare Demin Vaults (C) elev. 706 2 ED Spare Demin Vaults (C) elev. 706 2 ED Spare Demin Vaults (C) elev. 706 2 ED Spare Demin Vaults (C) 3 Evaporator Condensate elev. 690 Filter Dr (C) elev. 690 2 ED Spares Filter Vaults (C) elev. 690 2 ED Spares Filter Vaults (C) elev. 690 2 ED Spares Filter Vaults (C) elev. 690 2 ED Spares Filter Vaults (C) elev. 690 2 ED Spares Filter Vaults (C) elev. 690 2 ED Spares Filter Vaults (C) elev. 690 2 ED Spares Filter Vaults (C) elev. 690 2 ED Spares Filter Vaults (C) elev. 690 2 Instrument Dr A4-R (C) elev. 690 2 Waste Gas Compressor Dr (C) elev. 690 2 Waste Gas Compressor Dr (C) elev. 690 Clear Out A11-R (capped) elev. 690 2 Instrument Dr A11-R (C) elev. 690 2 Instrument Dr A11-R (C) elev. 690 3 Evaporate Feed Filter Dr (C) elev. 690 3 Evaporate Feed Filter Dr (C) elev. 690 3 Spent Fuel Pit Filter Dr (C) elev. 690 2 Instrument Dr A8-R (C) elev. 690 Clear Out A6-R (capped) elev. 690 2 CVCS Dr. A6-A10-S elev. 690 2 CVCS Dr. A6-A10-S elev. 690 Instrument Dr A4-T (C) 2 ED Reactor Coolant elev. 690 Fltr Dr (C)

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 87 of 95 Attachment 12 (Page 4 of 12) 1.0 UNIT 1 DRAIN HEADER (NORTH HEADER) (continued)

DRAIN PIPE / ELEVATION EQUIPMENT DRAINS Line SIZE SERVICED Checked elev. 690 2 ED Seal Water Inj Fltr Dr (C) elev. 690 2 Instrument Dr A5-T (C) 2 ED Seal Water Injection elev. 690 Fltr Dr (C) elev. 690 Clear Out A6-T (capped) elev. 690 2 Instrument Dr A6-T elev. 690 2 ED Seal Water Fltr Dr (C) elev. 690 3 ED VCT Dr (C) elev. 690 Clear Out A4-V (capped) elev. 690 2 ED VCT Dr (C) 3 ED Cation Mixed Bed elev. 690 Demin Dr (C) elev. 690 2 ED Seal Water Hx Dr (C) elev. 690 2 ED Seal Water Hx Dr (C) elev. 690 2 ED Seal Water Hx Dr (C) elev. 690 2 ED A5-U (C) 2 ED Containment Spray elev. 690 Hx Dr (C) elev. 690 2 Instrument Dr A9-V (C) elev. 690 2 Instrument Dr A8-U (C) elev. 690 2 Instrument Dr A7-V (C) elev. 690 2 Instrument Dr A7-V (C) elev. 690 2 ED RHR Hx Dr (C) elev. 690 2 Clear Out A5-V (capped) elev. 690 2 ED Containment Spray Hx Dr elev. 690 2 ED RHR Hx Dr (C) elev. 690 2 ED Spare A2-U (C) elev. 690 2 Instrument Dr A3-V (C) elev. 690 2 Instrument Dr A4-W (C) 2 Instrument Dr A5-W (C) elev. 690 see detail A2 or 1,2-47W852-2 elev. 690 2 ED Abandoned (blocked) (C)

10 Plant Vent 1 North Header Vent

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 88 of 95 Attachment 12 (Page 5 of 12) 1.0 UNIT 1 DRAIN HEADER (NORTH HEADER) (continued)

DRAIN PIPE / ELEVATION EQUIPMENT DRAINS Line SIZE SERVICED Checked

11 (2 in.) 2 ED Refueling Water Purification elev. 669 Pump Dr. (O)

12 (2 in.) elev. 669 2 Clear Out A5-W (capped) elev. 669 2 Clear Out A3-U (capped) 2 ED Primary Water elev. 669 Makeup Dr A2-T (O) 2 ED Primary Water elev. 669 Makeup Dr A2-T (O) 2 ED Aux Feedwater Pump Dr elev. 669 Room 1A (O)

13 (3 in.) elev. 669 2 Instrument Dr. A6-T (C) elev. 669 2 Clear Out A5-U 2 ED Charging Pump Dr elev. 669 Room 1C (C) elev. 669 2 ED Dr. A5-U (C) elev. 669 2 Instrument Drain A3-T (C) elev. 669 2 ED CVCS Dr. A3-U (C) elev. 669 2 Clear Out A3-U (capped) elev. 669 2 Instrument Dr (C) A3-U elev. 669 2 ED A4-U elev. 669 2 Clear Out A4-T (capped) 2 ED Charging Pump Dr elev. 669 Room 1A (C) elev. 669 2 Instrument Dr A4-T (C) 2 ED CVCS Low Point Drain elev. 669 Pipe Gallery (C) elev. 669 2 ED Drain A5-U (C) elev. 669 Clear Out A4-T (capped) 2 ED Charging Pump Dr elev. 669 Rm 1B (C) elev. 669 2 Instrument Dr A5-U (C) 2 Purge Air Filter Unit 1 Pipe elev. 669 Chase (C) elev. 669 1 Clear Out A6-U

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 89 of 95 Attachment 12 (Page 6 of 12) 1.0 UNIT 1 DRAIN HEADER (NORTH HEADER) (continued)

DRAIN PIPE / ELEVATION EQUIPMENT DRAINS Line SIZE SERVICED Checked 2 ED Safety Injection Pump Dr elev. 669 Rm 1B (C) elev. 669 2 Instrument Dr A7-U (C) elev. 669 1 Clear Out A6-V 2 ED Safety Injection Pump Dr elev. 669 Rm 1A (C) 2 ED Refueling Water Purification elev. 669 Filter Dr (C) elev. 669 2 Instrument Dr A7-V (C) 2 ED Refueling Water Purification elev. 669 Filter Dr. (C) elev. 669 2 Instrument Dr. A5-V (C) 2 ED Charging Pump

14 (4 in.) elev. 669 Room 1C (O) 2 ED Charging Pump elev. 669 Room 1A (O) 2 ED CVCS Low Point Dr Pipe elev. 669 Gallery (O) 2 ED Charging Pump elev. 669 Room 1B Dr (O) 2 ED Safety Injection Pump elev. 669 Room 1B Dr (O) elev. 669 2 Trench Drain Pipe Chase (O) 2 ED Safety Injection Pump Dr elev. 669 Room 1A (O)

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 90 of 95 Attachment 12 (Page 7 of 12) 2.0 UNIT 2 DRAIN HEADER (SOUTH HEADER)

NOTE

(#1 is the most eastern pipe); ED = equip dr.; (O) = open; (C) = closed DRAIN PIPE / ELEVATION EQUIPMENT DRAINS Line SIZE SERVICED Checked

1 (4 in.) elev. 706 2 ED Spare A13-U (O) elev. 690 2 ED Volume Control Drain 2 ED Chemical Mixing Tank Dr elev. 690 and Overflow (O) 2 ED Instrument Drain elev. 690 A11-W (C) 2 ED Boron Injection Tank elev. 690 Funnel Drain (O) 2 ED Sampling Sink elev. 690 Room 2 (O)

2 (4 in.) elev. 690 2 ED RHR Hx Dr. Rm 2A (C) 2 ED Containment Spray Hx Dr elev. 690 Rm 2A (C) elev. 690 2 ED RHR Hx Dr Rm 2B (C) 2 ED Containment Spray elev. 690 Hx Dr Rm 2B (C) elev. 690 2 ED Seal Water Hx Dr (C) elev. 690 2 ED Seal Water Hx Dr (C) elev. 690 2 ED Seal Water Hx Dr (C) elev. 690 2 ED A11-U (C)

3 (4 in.) elev. 714 2 Instrument Dr A10-U elev. 714 2 Instrument Dr A10-W 2 ED Spent Fuel Cooling elev. 714 Pump Drain (O) 2 ED Spent Fuel Cooling elev. 714 Pump Drain (O) elev. 714 2 ED Skimmer Pump Dr (O)

4 (4 in.) elev. 734 3 ED Spare A11-V (C)

5 (4 in.) elev. 734 3 ED Spare A5-V (C) elev. 734 2 ED A5-W (C) elev. 734 2 ED A4-V (C) elev. 734 2 ED A4-V (C)

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 91 of 95 Attachment 12 (Page 8 of 12) 2.0 UNIT 2 DRAIN HEADER (SOUTH HEADER) (continued)

DRAIN PIPE / ELEVATION EQUIPMENT DRAINS Line SIZE SERVICED Checked 2 Clear Out CO Aux Waste

6 (2 in.) elev. 669 Evaporator Room (capped) 2 ED (C) Aux Waste Evaporator elev. 669 Room elev. 669 2 ED (C) Waste Evaporator Rm

7 (1 in.) Plant Vent 1 South Header Vent

8 (2 in.) elev. 669 2 Instrument Dr A7-W (C)

9 (4 in.) 2 ED Boron Injection elev. 690 Tank Dr (C) elev. 690 2 Instrument Dr A11-W elev. 690 2 Instrument Dr A12-W elev. 690 2 ED Volume Control Tk Dr (C) 2 Clear Out Volume elev. 690 Control Tk Dr (capped) 2 ED Reactor Coolant elev. 690 Filter Dr (C) elev. 690 2 Instrument Drain A11-T 2 ED Seal/Water elev. 690 Filter Dr (C) 2 ED Seal/Water Injection elev. 690 Filter Dr (C) 2 ED Seal/Water Injection elev. 690 Filter Dr (C) elev. 690 2 Instrument Drain A10-T elev. 690 2 Instrument Drain A12-T elev. 690 2 ED Volume Control Drain elev. 690 2 ED Mixed Bed Demin Dr (C) elev. 690 2 Instrument Drain A13-V (C) elev. 690 2 Instrument Drain A14-T (C) elev. 690 2 Clear Out A14-T (capped) elev. 690 2 Instrument Dr A13-S (C) elev. 690 2 Clear Out A14-Q (capped) elev. 690 2 Instrument Dr A14-Q (C) elev. 690 2 Boric Acid Filter Dr (C)

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 92 of 95 Attachment 12 (Page 9 of 12) 2.0 UNIT 2 DRAIN HEADER (SOUTH HEADER) (continued)

DRAIN PIPE / ELEVATION EQUIPMENT DRAINS Line SIZE SERVICED Checked elev. 690 2 Boric Acid Filter Dr (C) 2 Instrument Dr A-10 reactor

10 (4 in.) elev. 714 centerline (C) 2 Clear Out A10 reactor center elev. 714 line (C) elev. 714 2 Skimmer Filter Dr (C) elev. 714 2 Letdown Hx Dr (C) 2 Clear Out Letdown Hx Rm elev. 714 (capped)

11 (3 in.) elev. 690 3 ED Monitor Tank Dr (O) 3 ED Monitor Tank elev. 690 Overflow (O) 3 ED Boric Acid Tank elev. 690 Overflow (O) 2 ED Boric Acid Tank elev. 690 Transfer Pump Dr (O) 2 ED Boric Acid Tank elev. 690 Transfer Pump Dr (O) 2 ED Boric Acid Tank elev. 690 Transfer Pump Dr (O) 2 ED Boric Acid Tank elev. 690 Transfer Pump Dr (O) elev. 690 2 ED Boric Acid Tank Dr (O) 3 ED Boric Acid Tank elev. 690 Overflow (O) elev. 690 2 ED Boric Acid Tank Dr (O) 3 ED Boric Acid Batching Tank elev. 690 Overflow (O) 3 ED Boric Acid Tank elev. 690 Overflow (O) elev. 690 2 ED Boric Acid Tank Dr (O) 2 ED Boric Acid Batching elev. 690 Tank (O) elev. 690 2 Clear Out A11-V (capped) elev. 690 2 Spare A11-U (O) elev. 690 2 Seal Water Hx Dr (O)

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 93 of 95 Attachment 12 (Page 10 of 12) 2.0 UNIT 2 DRAIN HEADER (SOUTH HEADER) (continued)

DRAIN PIPE / ELEVATION EQUIPMENT DRAINS Line SIZE SERVICED Checked

12 (3 in.) elev. 669 2 Clear Out A13-U 2 CVCS Monitor Tank elev. 669 Pump Dr (O) 2 CVCS Monitor Tank elev. 669 Pump Dr (O) 2 Primary Water Makeup elev. 669 Pump Dr (O) 2 Primary Water Makeup elev. 669 Pump Dr (O) 2 ED Aux Feedwater elev. 669 Pump Dr (O) elev. 669 2 Clear Out A12-V (capped)

13 (3 in.) elev. 669 2 Instrument Dr A10-U (C) 2 ED Spare Charging Pump Dr elev. 669 Room 2A (C) 2 Clear Out Charging Pump elev. 669 Room 2A 2 ED Charging Pump Dr elev. 669 Room 2A (C) elev. 669 2 Instrument Dr (C) A14-T elev. 669 2 Clear Out A14-T (capped) elev. 669 2 Instrument Dr A13-T (C) elev. 669 2 CVCS Dr A13-U (C) 2 ED Spare Charging Pump Dr elev. 669 Room 2C (C) 2 Clear Out Charging Pump elev. 669 Room 2C (capped) 2 ED Charging Pump Dr elev. 669 Room 2C (C) elev. 669 2 Instrument Dr A12-T (C) 2 ED CVCS Low Point Dr Pipe elev. 669 Gallery (C) 2 ED Charging Pump Drain elev. 669 Room 2B (C) 2 Clear Out Charging elev. 669 Pump Room 2B (capped)

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 94 of 95 Attachment 12 (Page 11 of 12) 2.0 UNIT 2 DRAIN HEADER (SOUTH HEADER) (continued)

DRAIN PIPE / ELEVATION EQUIPMENT DRAINS Line SIZE SERVICED Checked 2 ED Charging Pump Drain elev. 669 Room 2B (C) elev. 669 2 Instrument Drain A12-U (C) 2 Purge Air Filter Unit 2 Pipe elev. 669 Chase (C) 2 Clear Out Safety Injection elev. 669 Pump Room (capped) 2 ED Safety Injection Pump Dr elev. 669 Room 2B (C) elev. 669 2 Instrument Drain A9-U (C) 2 Clear Out Safety Injection elev. 669 Pump Room 2A elev. 669 2 Instrument Drain A10-V (C) elev. 669 2 Clear Out A11-W (capped) elev. 669 2 Instrument Drain A9-W (C) elev. 669 2 Instrument Drain A11-V (C) 2 ED Charging Pump Room 2C

14 (3 in.) elev. 669 Drain (O) 2 ED Charging Pump Room 2A elev. 669 Drain (O) 2 CVCS Low Point Drain Pipe elev. 669 Gallery (O) 2 ED Charging Pump Room 2B elev. 669 Drain (O) 2 ED Safety Injection Pump elev. 669 Room 2B Drain (O) (capped) elev. 669 2 Trench Drain Pipe Chase (O) 2 ED Safety Injection Pump elev. 669 Drain Room 2A (O)

SQN Reactor Coolant System 0-SI-OPS-068-137.0 Unit 1 & 2 Water Inventory Rev. 0041 Page 95 of 95 Attachment 12 (Page 12 of 12) 3.0 UNIT 0 DRAIN HEADER (EASTERN HEADER)

NOTE

(#1 is the most eastern pipe); ED = equip dr.; (O) = open; (C) = closed DRAIN PIPE / ELEVATION EQUIPMENT DRAINS Line SIZE SERVICED Checked 3 ED Spare Waste Packaging

1 (3 in.) elev. 706 Area (C) 3 ED Spare Waste Packaging elev. 706 Area (C) elev. 669 2 ED Valve Gallery (C) elev. 669 3 ED A8 (C) 2 Fuel Transfer Canal Leakage

2 (2 in.) elev. 683 Drain (O) 2 Fuel Transfer Canal Leakage elev. 683 Drain (O) elev. 683 2 HUT to Transfer Canal Tell Tale

3 (3 in.) elev. 734 2 Crane Rail Drain elev. 734 2 Crane Rail Drain elev. 734 2 Instrument Drain A11 (O)

4 (4 in.) elev. 706 4 ED Spare A8 and SFP Wall

5 Plant Vent 1 East Header Vent

6 (4 in.) elev. 714 ED Spare A8 and reactor centerline

7 (4 in.) elev. 714 ED Spare A8 and reactor centerline 2 Spent Fuel Pit Leakage

8 (2 in.) elev. 683 Drain (O) 2 Spent Fuel Pit Leakage elev. 683 Drain (O) 2 Spent Fuel Pit Leakage elev. 683 Drain (O) 2 Spent Fuel Pit Leakage elev. 683 Drain (O) 2 Cask Loading Area elev. 683 Leakage Drain (O) 4 ED Spare A8 and reactor

9 (4 in.) elev. 714 centerline (C)

10 (3 in.) elev. 734 2 Crane Rail Drain (O)

SITE: SQN JPM TITLE Manual Leakrate calculation JPM-0-SI-OPS-068-JPM NUMBER 137.0 [02] REVISION: 41 TASK APPLICABILITY: SRO STA UO NAUO TASK NUMBERS / TASK TITLE(S) 0020010201 K/A RATINGS 3.9/4.6 2.2.42 Ability to recognize system parameters that are entry-level conditions K/A STATEMENT for Technical Specifications.

RELATED PRA INFORMATION Not required for exam.

SAFETY FUNCTION: NA EVALUATION LOCATION: In-Plant Simulator Control Room Lab Other - List: Classroom APPLICABLE METHOD OF TESTING: Discussion Simulate/Walkthrough Perform TIME FOR COMPLETION: 20 minutes TIME CRITICAL (Y/N) N ALTERNATE PATH (Y/N) N Developed by: On File Developer Date (Ensure validator is briefed on exam security per NPG-SPP-17.8.1)

(See JPM Validation Checklist in NPG-SPP-17.8.2)

Validated by: On File Validator Date Approved by: On File Site Training Management Date Approved by: On File Site Training Program Owner Date Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 1 of 21 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [02]

SPECIAL INSTRUCTIONS:

1. Ensure classroom is prepared for admin JPMs Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 2 of 21 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [02]

JPM Briefing from NPG-SPP-17.8.2 completed? Yes If no, perform briefing prior to continuing.

Initial Conditions As a reminder:

You may use any approved reference materials normally available including logs.

Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS (N/A simulator).

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

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.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

(REMEMBER TO VERIFY STUDENT SHEET HAS THIS SAME INFORMATION)

INITIAL CONDITIONS:

1. Unit-2 is in MODE 1.

2. 0-SI-OPS-068-137.0, Reactor Coolant System Water Inventory is in progress up to step 6.2.2 [1].

3. ICS is not available.

4. 0-SI-CEM-000-050.3 and 2-SI-CEM-068-137.5 were completed last night at 2300 SG # 1 SG # 2 SG # 3 SG # 4 3.2 gpd 3.2 gpd 3.2 gpd 4.8 gpd

5. Chemistry supervisor reported no additions or samples taken from the RCS during the selected performance period.

6. CCPIT/HUT leakage and other leakage is 0 gpm.

7. Current Pressurizer Pressure is 2225 psig INITIATING CUES:

1. You are the Unit 2 CRO and have been directed to complete step 6.2.2[1] of 0-SI-OPS-068-137.0, Reactor Coolant System Water

2. Notify the Examiner if Acceptance Criteria is (met / NOT met) and what actions are required (if any).

This JPM is a "time critical" JPM This JPM is not a "time critical" JPM.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

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JPM-0-SI-OPS-068-137.0 [02]

Classroom with computer access Marked up copy of 0-SI-OPS-068-137.0 Reactor Coolant System Water Required Materials:

Inventory Steam tables based on year 2000 ASME steam tables

References:

1. 0-SI-OPS-068-137.0 Reactor Coolant System Water Inventory The examinee completes Attachment 4 and calculates the following parameter values:

VCT Leakage = 0.80 gpm PZR Leakage = (0.51-0.52) gpm Total RCS Leakage = (1.31-1.32) gpm PRT Leakage= 0.00 gpm Task Standards: RCDT Leakage = 0.00 gpm SG Leakage = 0.01 gpm Total identified leakage = 0.01 gpm Total unidentified leakage = (1.30-1.31) gpm The examinee notifies the Examiner that the acceptance criteria is NOT met because the unidentified leakage is greater than 1 gpm.

- Tech Spec 3.4.13, 1 GPM unidentified leakage, Condition A NOTE:

When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

IMPORTANT:

Critical steps are marked with a Y below the Performance Step number field. Failure to meet the standard for any critical step shall result in failure of this JPM.

Start Time:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

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JPM-0-SI-OPS-068-137.0 [02]

Step # 1. Performance step:

Critical Step?

Y Standard: The Examinee determines VCT Leakage is .80 gpm.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

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JPM-0-SI-OPS-068-137.0 [02]

Step # 2. Performance step:

Critical Step?

Y The Examinee determines Initial Pressurizer Volume is between (4883.25-4899.38)

Standard:

gallons Performance: SATISFACTORY UNSATISFACTORY Examiner Acceptability band is based on interpolation of Steam tables Derosa Steam tables 2000 Notes: ASME with PZR pressure @2240 psia with a +/- 15 psia allowance Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

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JPM-0-SI-OPS-068-137.0 [02]

Step # 3. Performance step:

Critical Step?

Y Standard: The Examinee determines Final Pressurizer Volume is (4821.33-4836.69) gallons Performance: SATISFACTORY UNSATISFACTORY Examiner Acceptability band is based on interpolation of Steam tables and previous acceptability Notes: bands Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 7 of 21 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [02]

Step # 4. Performance step:

Critical Step?

Y Standard: The Examinee determines Pressurizer Leakage is (0.51-0.52) gpm Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Acceptability band is based previous acceptability bands Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

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JPM-0-SI-OPS-068-137.0 [02]

Step # 5. Performance step:

Critical Step?

Y Standard: The Examinee determines RCS Temperature Correction is 0 gpm.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

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JPM-0-SI-OPS-068-137.0 [02]

Step # 6. Performance step:

Critical Step?

Y Standard: The Examinee determines Total RCS leakage is (1.31-1.32) gpm.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Acceptability band is based previous acceptability bands Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

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JPM-0-SI-OPS-068-137.0 [02]

Step # 7. Performance step:

Critical Step?

Y Standard: The Examinee determines Pressurizer Relief Tank (PRT) leakage is 0.00 Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

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JPM-0-SI-OPS-068-137.0 [02]

Step # 8. Performance step:

Critical Step?

Y Standard: The Examinee determines Reactor Coolant Drain Tank (RCDT) is 0.00.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

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JPM-0-SI-OPS-068-137.0 [02]

Step # 9. Performance step:

Critical Step?

Y The examinee determines the Steam Generator Leakage is 0.01 gpm.

Standard: The examinee obtains the date and time of the steam generator leakage surveillance from the initiating cue.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

Page 13 of 21 [08-08-2014]

JPM-0-SI-OPS-068-137.0 [02]

Step # 10. Performance step:

Critical Step?

N Standard: The Examinee determines this step is NA Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

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Step # 11. Performance step:

Critical Step?

N Standard: The Examinee determines from cue sheet the Other Identified Leakage is zero.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

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JPM-0-SI-OPS-068-137.0 [02]

Step # 12. Performance step:

Critical Step?

Y Standard: The Examinee determines Total Identified Leakage is 0.01 gpm.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

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JPM-0-SI-OPS-068-137.0 [02]

Step # 13. Performance step:

Critical Step?

Y Standard: The Examinee determines Unidentified Leakage is (1.30-1.31) gpm.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes: Acceptability band is based previous acceptability bands Cue:

Comments:

Step # 14. Performance step:

Acceptance Criteria Determination Critical Step?

Y Operator determines Acceptance Criteria is NOT met because Unidentified leakage Standard:

exceeds 1 gpm.

Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue: If not provided ask Is Acceptance Criteria met or NOT met, explain your answer Comments:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

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JPM-0-SI-OPS-068-137.0 [02]

Step # 15. Performance step:

SRO Evaluates Tech Specs Critical Step?

Y SRO Determines Condition A, 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to reduce leakage Standard:

May also report, if not corrected in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Condition B is applicable Performance: SATISFACTORY UNSATISFACTORY Examiner Notes:

Cue:

Comments:

Terminating Cue: Provide the following cue, That completes the JPM.

Stop Time:

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

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JPM-0-SI-OPS-068-137.0 [02]

Operator Fundamental evaluated:

Historical Record:

Rev 41 Converted JPM into current template and verified against latest procedure revisions.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

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JPM-0-SI-OPS-068-137.0 [02]

JPM DATA SHEET EXAMINEES NAME: EIN:

EVALUATORS NAME: DATE:

JPM Title JPM-0-SI-OPS-068-137.0 [02], Manual Leakrate Calculation Start Time Finish Time Performance Time PERFORMANCE RESULTS: SAT UNSAT COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory)

Evaluators Signature:

Date NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

Retain in accordance with NPG-SPP-17.1, Appendix B, TPRM.

[08-08-2014]