ML030240184

Draft - Section C Operating

ML030240184
Person / Time
Site:	Ginna
Issue date:	02/11/2002
From:	Watts R Rochester Gas & Electric Corp
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-244/01-301, ES-D-1, NUREG-1021, Rev 8, Suppl 1 50-244/01-301
Download: ML030240184 (24)

Text

AO Appendix D Scenario Outline Form ES-D-Facility: Ginna Scenario No.: 1 Op-Test No.: 01-01 Examiners: Lauahlin (Bissett) Operators:

Fish Silk Initial Conditions: Plant is at -48% reactor power, MOL. C, = 824 ppm. Power was reduced 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> aao for condenser tube leakage and is ready to go back to full power.

BAST Co - 11.000 rom. "B" MDAFW pump and "C" charqinq pump are OOS.

Turnover: Plant is at -48% reactor power, MOL. CB=824 ppm. Power was reduced 4 hrs ago for condenser tube leakage and is ready to go back to full power. BAST C=1 1,000 ppm. "C" charging pump is OOS for excessive leakage, "B" MDAFW pump is OOS for check valve renair.

Event Malf. Event Event No. No. Type* Description 1 N/A N(CRF) Raise power to 100% lAW 0-1.2.*

a(HCO "; ," ,{

2 NIS07A I(CRF, PR channel N41 fails high, rods insert. (Enter ER-NIS.3, TS HCO) entry) 6 . ,

3 ROD2A C(CRF, Dropped control rod (Enter AP-RCC.2 for RCC HCO) malfunction, 0-5.1 for load reduction) , ,

4 CND07 C(AII) Loss of condenser vacuum-east 1 B, results in turbine/Rx A trip. (Enter AP-TURB.4 and EO) 5 EDS01 M(AII) Loss of offsite power. Er ^,AP- E-.) "A" EDG runs on A&B bus 14.

6 GEN04 C(AII) "A" EDG runs on bus 14, "B" EDG fails to auto-start but can B be started manually.

7 GEN04 M(AII) "A" EDG trips, station blackout. (Enter ECA-0.0) Terminate A when transition to ECA-0.1 I. M i

4. I I I (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 39 of 40 NUREG-1021, Revision 8, Supplement 1

Appendix D Operator Actions Form ES-D-2 Op-Test No.: _ Scenario No.: _1_ Event No.: 1 Page 1 of 6 Event

Description:

-Raise reactor power to 100% lAW )-1.2 Time J Position Applicant's Actions or Behavior CRF Direct start of "B" MFW pump per attachment "MFW Pump B" (Steps 7.0- 13.0) 54 q' 3.. /_

CO Lineup Service Water to MFW pump B oil cooler Take B MFW out of Pull Stop Veriy MFW pump recirculation valve opens (AOV-4148)

Start "B" MFW pump Verify MFW pump discharge pressure and open discharge valve MOV-3976 CRF Direct AO to close B MFW pump discharge bypass valve MOV-3976A CO Place HDT Level Controlerl*j;-2013A in Auto CRF _ Direct AO to check MFW pump warmup valves closed HCO Check Delta I cumulative time on PPCS Verify QPTR is <1.02 CRFO Verify RP has a leak rate determined from the air ejector sample CO Raise valve position limit to 100%

Raise Setter and start load increase HCO Manually operate control rods/dilute as necessary to control Tave I I NUREG-1021, Revision 8, Supplement 1 40 of 40

A nnc:,nrliY ri *n*.r*fnr At.fin n.* Form ES-D-2 Op-Test No.: __ Scenario No.: 1 Event No.: :2 Page _2_ of 6_

Event

Description:

_PR Channel N41 Fails Hiqh

[Time Position Applicant's Actions or Behavior All Identify failed PR channel HCO Place rod control bank selector switch in manual HCO/CO Adjust Tave/ Tref as necessary CRF Address Technical Specifications (ITS3.2.3)

Direct NIS channel 41 to be defeated per "ttachment N-41 Defeat" HCO Verify rod control bank selector switch in manual HCO/CO Place DROPPED ROD MODE switch to bypass and verify following alarms - DROPPED ROD BYPASS is lit:

POWER RANGE ROD DROP BYPASS is lit:

Annunciator E-7 NIS TRIP BYPASS is lit Place T/405E DELTA T DEFEAT switch to LOOP A UNIT 1 Place OVERTEMP TRIP bistable switch to DEFEAT and verify the following - F-23 RCS OTA T CHANNEL ALERT is lit Red bistable status light OTA T LOOP A TC405C is lit Place OVERPOWER TRIP B/S switch to DEFEAT and verify the following: F-32 RCS OPAT CHANNEL ALERT is lit Red B/S status light OPAT LOOP A TC405A is lit Place UPPER SECTION DEFEAT switch to the PRN41 position &

verify the following: Local light for CHANNEL DEFEAT is lit Place LOWER SECTION DEFEAT switch to the PRN41 position &

verify the following: Local ight for CHANNEL DEFEAT is lit Place POWER MISMATCH BYPASS switch to BYPASS PRN41 Place ROD STOP BYPASS switch to BYPASS PRN41 Place COMPARATOR CHANNEL DEFEAT switch to N41 & verify the fll_ alinn CiMPARATCI:P r)[:F=I:AT lirch4 8r lit _

NUREG-1021, Revision 8, Supplement 1 40 of 40

Appendix D Operator Actions Form ES-D-2 Op-Test No.: _ Scenario No.: _1_ Event No.: _2 (con't)_ Page _3_ of 6_

Event

Description:

_PRN41 Failure Time Position Applicant's Actions or Behavior HCO/CO Remove 118V 5A AC INSTR POWER fuses & verify the following E-1 8 POWER RANGE LOSS OF DETECTOR VOLTAGE E-19 POWER RANGE HI RANGE CHANNEL ALERT 108%

E-21 POWER RANGE OVERPOWER ROD STOP 103%

E-27 POWER RANGE LO RANGE CHANNEL ALERT 24%

E-28 POWER RANGE ROD DROP ROD STOP 5%/5 SEC Verify the following red bistable lights (MCB) are lit HI POW RANGE P-10 NC41M HI POW RANGE P-8 NC41N

_LO POW RANGE TRIP NC41P HI POW RANGE TRIP NC41R HI POW RANGE P-9 NC41S Verify various status lighnt on PR N41A drawer are lit Verify following status lights on PRN41 B drawer are extinguished INSTRUMENT POWER ON CHANNEL ON TEST CRF Notify I&C to install jumpers HCO/CO Restore ROD CONTROL back to AUTO Reset dropped rod rod stop signals at RR NIS drawers CRF Check Tech Specs Revision NUREGi0218 Spi Ie-t 2nd R 'r P40n-er-f NUREG-i 021, Reiin8, Supplement 1 40of 40

Appendix D Operator Actions Form ES-D-2 Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 EEyent No.: _3_ Page _4 of 6 Event

Description:

Dropped Control Rod.2(Enter AP-RCC.2 for RCC malfunction, 0-5.1 for load reduction) Annunciator C-5 Rod Deviation light lit, Annunciator F-29 PPCS or QUADRANT POWER TILT lit.

Time Position Applicant's Actions or Behavior HCO/CRO Place Rod Control Bank Selector Switch to MANUAL Check Dropped Rod Indication - Pwr and Tave decreasing Go to AP-RCC.3 (Dropped Rod Recovery)

CO Place EH control in MANUAL Reduce turbine load as necessary to match Tave and Tref Verify Annunciator G-15 STEAM DUMP ARMED- EXTINGUISHED Check Main Generator Load - GREATER THAN 15 MW Establish Stable Plant Conditions Check REGEN HX Letdown Indications CRF Evaluate Control Rod Operability HCO/CO Go toER-RCC.1 RETRIEVAL OF A DROPPED ROD (are we going to try and retrieve?)

4 +

4. +

1- 1-4- 4.

+

4. I.

NUREG-1 021, Revision 8, Supplement 1 40 of 40

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 4 Page -5 of 6 Event

Description:

Loss of condenser vacuum- east 1B resulting in a turbine/Rx trip Time Position Applicant's Actions or Behavior CO Identifies decreasing vacuum, monitors condenser indications CRF Directs entry into AP-TURB.4 LOSS OF CONDENSER VACUUM Dispatches AO to perform local actions I CRF Directs Rx Trip and entry into E-0 HCO/CO Performs Immediate Actions of E-0 Verify Rx Trip Verify Turbine Stop Valves Shut Verify BothTrains of AC Emergency Buses Energized Check if SI is Actuated SI NOT Required - Transition to ES 0.1 Reactor Trip Response Monitor RCS Tave Check S/G Feed Flow Status Verify all rods on bottom Verify All AC Buses ENERGIZED BY OFFSITE POWER - NO Perform RNO actions of step 4 of ES-0,1 Verify at Least Two SW Pumps running - NO Start one SW pump per RNO step 5 Verify IA Available Check PZR Level Control - start charging pump2(s) per RNO step 7 "A"D/G trips - Loss of all AC CRF Directs transition to ECA-0.0 Loss of all AC

.1 1

NUREG-1021, Revision 8, Supplement 1 40 of 40 Appendix D Operator Actions Form ES-D-2 Op-Test No.: _ Scenario No.: 1 Event No.:5,6,7 Page 6 of 6 Event

Description:

Loss of all AC Time Position I Applicant's Actions or Behavior CRF Directs immediate actions of ECA-0.0 CO Close MSIVs HCO Isolate RCS by closing AOV 200A, B, C , AOV 371, 427& AOV 310 CO Verify adequate TDAFW flow >200 gpm Try to restart a DIG CRF Direct AO to locally restart a D/G HCO/CO Pull Stop Equipment Isolate RCP seal injection Place hotwell level control in manual at 50%

Check S/G status - intact (RF Direct manual start of "B" DIG (O Manually control ARV to stabilize RCS temp Restore SW pumps Verify equipment loaded on available AC emergency buses CRF Direct AO to check battery chargers Direct transition to ECA-0. 1 (CRF Site Area Classification

Appendix D Scenario Outline Form ES-D-1 Facility: Ginna Scenario No.: 01-02 Op-Test No.:

Examiners: Bissett Operators:

Fish Lauqhlin Initial Conditions: Plant is at 100% power, BOL, C, 1329, xenon equilibrium. PORV-430 isolated due to hicgh leakage. MOV-516 closed. BAST C, - 11,000 ppm.

Turnover:

Event Malf. Event Event No. No. Type* Description 1 PZR01 C(CRF, PZR spray valve PCV-431A fails open approx 50%. (Enter A HCO) AP-PRZR.1) 2 NIS8A I (CRF, BI ter HCO) &R44+aý) fzL. tO,. 5 -..

3 TUR05 C(CRF) Turbine vibration increases. (Enter AP-TURB.3, requires C R(HCO load reduction to stabilize vibration) 4ý 4 SGN04 M(AII) SGTR on S/G !A at'5Q-.gpm. (Enter E-0, E-3, O-.A6

___A 1WDA?-SGJ 5 TUR02 C(CRF, Turbine fails to trip. (Manually trip turbine per E-0)

TUR11 CO)

D 6 SIS03B C(CRF, 1B SI pump fails to staFr.

HCO) 7 PZR05 C(CRF, PORV 431 fails open, resulting in SBLOCA. (Enter ECA-3.1, B HCO) -AP PRZR 1,AP44CO. 1) Terminate when RCS cool-down is I underway.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 39 of 40 NUREG-1021, Revision 8, Supplement 1

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

Description:

Pzr spray valve PCV-431A fails open (-50%)

Time Position Applicant's Actions or Behavior HCO Identifies stuck open spray valve, RCS pressure decrease CRF Directs entry into AP-PRZR.1 "Abnormal Pressurizer Pressure" HCO Checks Pzr Pressure, Reactor Power, Pzr Heater Status, Pzr Spray valve closed Place controllers in manual (.0% demand Check Pzr Pressure controller 431 K, Demand <50%

Check PORVs closed, Check Pzr safety valves closed Check Aux Spray valve closed Restore Pzr pressure control Check PRT Indications CRF Notify plant supervision and maintenance and reactor Engineering NUREG-1021, Revision 8, Supplement 1 40 of 40

AnDendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2 Event No.: 2 Page 2 of 7 Event

Description:

BIov, fuc" on to.. rani" A ....

Time Position Applicant's Actions or Behavior

.. CO Identifies IR channel 35 failure

• 9R:F * -4*jrects entry into ER-Nl aluction" .. I HCO', De--et eý ýa~ rod stopfunctio2*45*IR5 by placing level Contacts F Refers to TS io 3.1, Table 3.3.1-1, Function and #16a i i L 4 I I i i J .1 I i i i NUREG-1021, Revision 8, Supplement 1 40 of 40

Appendix D Operator Actions Form ES-D-2 Op-Test No.: _ Scenario No.: 2 Event No.: 3 Page 3_ of 7_

Event

Description:

Turbine vibration increase resultingq in a load reduction

[Time Position Applicant's Actions or Behavior CRF Recognize hi turbine vibration, enter AP-TURB.3 Verify turbine trip not required CRF/CO Reduce turbine load to stabilize vibrations Continue load reduction until vibrations stabilize, then stop load decrease HCO Stabilize primary systems CRF Direct walkaround inspection of turbine Notify higher supervision Notify Maintenance Mgr.

NUREG-1021, Revision 8, Supplement 1 40 of 40

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2 Event No.: 4_ Page 4 of 7 Event

Description:

SGTR on S/G A at 400qpm Time Position Applicant's Actions or Behavior HCO Identifies prz level decrease and pressure decrease CO Identifies SF/FF mismatch on A S/G HCO Charging pump speed alarm/flow increase Increasing radiation levels on R-15, R-19 and R-31 Start additional charging pumps Close loop B cold leg to reqen Hx AOV-427 CRF Enter AP-SG.1 Steam Generator Tube Leak I Direct Rx Trig if charging pumps running at max speed with I _Letdown isolated L I L L 4 4

________ I L 4 4 4 4 i i

£ I

-4 4 I i 17!nt "

NUREG-1021, Revision 8, Supplement 1 40 of 40

Appendix D Operator Actions Form ES-D-2 Op-Test No.: _ Scenario No.: _1 Event No.: _5,6- Page _5_ of 7_

Event

Description:

Rx Trip, turbine fails to trip, 1 B SI pump fails to start Time Position Applicant's Actions or Behavior CRF Direct actions of E-0 HCO/CO Verify Rx Trip Verify turbine stop valves closed- NO- MANUALLY TRIP TURBINE Verify AC Emergency Busses Energized Check if SI Actuated Verify SI/RHR pumps running -NO-MANUALLY START B SI PUMP Verify CNMT RECIRC FANS running Verify CNMT Spray NOT required Check if Main Steamlines should be isolated Verify MFW Isolation Verify AFW Pumps Running Verify at least Two SW Pumps running Verify CI and CVI Check CCW System Status Verify SI and RHR Pump Flow Verify AFW Flow > 200 GPM Verify AFW Valve Alignment Verify SI Pump and RHR Pump Emergency Alignment Check CCW Flow to RCP Thermal Barriers Check PZR PORVs and Spray Valves Monitor RCP Trip Criteria Check if S/G Secondary Side is Intact Check if S/G Tubes are Intact - NO- Transition to E-3 NUREG-1021, Revision 8, Supplement 1 40 of 40

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

Description:

-Steam Generator Tube Rupture Time Position Applicant's Actions or Behavior CRF Direct actions of E-3 Steam Generator Tube Rupture HCO/CO Monitor RCP Trip Criteria Identify Ruptured S/G- 1A S/G Isolate Flow From Ruptured 1A S/G Complete Ruptured S/G Isolation Check Ruptured SIG Level Verify Ruptured S/G Isolated Establish Condenser Steam Dump Pressure Control Reset SI Initiate RCS Cooldown Monitor Intact S/G Levels Check PZR PORVs and Block Valves Reset CI Monitor AC Busses - Energized by Offsite Power Verify SW Flow Establish IA to CTMT - AOV 5392 FAILS to OPEN Check if RHR Pumps should be stopped Establish Charging Flow Check if RCS Cooldown Should be Stopped Depressurize RCS to minimize break Flow and Refill Pzr via PORV Check RCS Pressure INCREASING - NO - TRANSITION TO ECA-3.1 NUREG-1021, Revision 8, Supplement 1 40 of 40 Appendix D Operator Actions Form ES-D-2

Op-Test No.: __ Scenario No.: 2 Event No.: 7 Page 7 of 7 Event

Description:

_PORV 431 Fails Open During RCS Depressurization Time Position Applicant's Actions or Behavior CRF Direct actions of ECA-3.1 HCO/CO Reset SI and CI Verify adequate SW Flow Establish IA to CTMT - NO AC Busses energized by offsite power Monitor CTMT Spray Pumps - STOPPED Check Ruptured JA S/G Level Stopped RHR Pumps Evaluate Plant Status Establish 75 GPM Charging Flow Check S/G Secondary Side and Intact S/G Levels Initiate RCS Cooldown to Cold Shutdown CRF Classify as Alert NUREG-1021, Revision 8, Supplement 1 40 of 40

Appendix D Scenario Outline Form ES-D-1 Facility: Ginna Scenario No.: 01-03 Op-Test No.:

Examiners: Bissett Operators:

Fish Laughlin Initial Conditions: The plant is at 100% power BOL xenon equilibrium. Boron=1329ppm, BAST conc. = 11,000. Circuit 751 is OOS due to an auto accident, "D"SW pump is OOS due to motor failure.

Turnover:

Event Malf. Event Event No. No. Type* Description 1 PZR2D I(CRF, PZR pressure channel PT-449 fails high. (Enter AP-PRZR. 1, HCO) ER-INST.1 to defeat channel) 2 RCS14 C(CRF, "B" RCP #3 seal failure.: (Enter AP-FRCP.1)

B HCO) 3 RCS2A C(CRF, RCS leak inside containment from loop A hot leg, 15 gpm.

HCO) (Enter AP-RCS.1) ('j 0 ' c. * .

4 N/A N(CRF) Perform plant shutdown in respgnse to RCS leak. (Enter 0 R(HCO 2.1, 100% to 95%) (,A e-"*,,*)

5 CND8 C(CRF, Condensate header break 20K gpm, complete loss of main CO) feedwater. (Enter E-0, 15< (A.- ! .j,)

6 RPS5A M(AII) ATWS (Enter FR-S.1)

&B 7 TUR2 C(CRF, Main turbine fails to automatically trip.

CO) 8 z. #

Terminate drill when Sl termination criteria met in E-1.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 39 of 40 NUREG-1021, Revision 8, Supplement 1

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

Description:

_PZR pressure channel failure PT-449 fails HI Time Position Applicant's Actions or Behavior CRF PT-449 fails HI, Directs entry into AP-PZR.1Abnormal PZR PRESS HCO/CO Acknowledges ANN F-2 and F-10 Checks PZR Press - Refers to ER-INST.1 Place 431K in MANUAL (@ -50%

Refer to Attachment PZR PRESSURE PI-449 YELLOW CHANNEL to defeat failed channel Place P/429A to DEFEAT-1 (PLP PZR PRESS/LVL RACK)

Place T/405F DELTA T DEFEAT switch to LOOP B UNIT 2 (RIL INSERTION LIMIT Rack)

In Y-1 PROTECTION CHANNEL 4 rack Place B/S switches To DEFEAT 408 LOOP B OVER TEMP TRIP 449 CHANNEL 4- LOW PRESS TRIP Place PZR oressure recorder to position 1-3 (MCB)

Delete 404/408 from the PPCS Restore PZR Pressure Control to automatic CRF Refer to ITS for applicable LCOs Section 3.3.1 Table 3.3.1-1 Functions 5 and 7a Section 3.3.3 Table 3.3.3-1 Functions 1 and 6 Check TRM 3.4.3 ATWS mitigation Notify maintenance and higher supervision NUREG-1021, Revision 8, Supplement 1 40 of 40

Appendix D Operator Actions Form ES-D-2 Op-Test No.: _ Scenario No 3 Event No.: 2 Page 2 of 8 Event

Description:

_"B" RCP #3 seal failure Time Position Applicant's Actions or Behavior HCO Acknowledges ANN B-1 1 RCP STAND PIPE LO LEVEL -4FT CRF Directs actions of AP-RCP.1 RCP SEAL MALFUNCTION HCO/CO Check Total #1 Seal Flow < 8.0 GPM Check RCP Seal Return valve Alignment MOV313 Open, AOV27OA/B Open Check Total #1 Seal Flow Between .8 - 6.0 GPM Check RCP cooling Check RCP #2 Seal Indications Check RCP Labyrinth Seal D/Ps > 15" Check RCP #3 Seal Indications RNO Check CTMT rad monitors Monitor RCP Seal Conditions 4 4-I 4-4 4 NUREG-1021, Revision 8, Supplement 1 40 of 40

Appendix D Form ES-D-2 Op-Test No.: _ Scenario No.: 3 Event No.: 3 Page 53 of 8 Event

Description:

_RCS leak inside CTMT from A loop hot leq Time Position Applicant's Actions or Behavior CRF Directs actions of AP-RCS. 1 REACTOR COOLANT LEAK HCO/CO Acknowledges ANN F-14, A-2, E-16. F-4 Check PZR level (Decreasing) RNO actions Start additional charging pumps Check VCT M/U System Check if RCS leakage in CTMT Dispatch AO to Aux Bidg Check for leak to CCW System Check CVCS Conditions Check AUX Bldg radiation levels Check PRT Indications Check S/Gs for Leakage Check SI Accumulator levels Check RCP Seal Leakoff Flows Check RCDT Leak Rate Check Valve Leakoff Temps Establish Stable Plant Conditions Evaluate RCS Leakage RNO - Commence Plant Shutdown at 1 %/min CRF Notify higher supervision NUREG-1021, Revision 8, Supplement 1 40 of 40

Appendix D Operator Actions Form ES-D-2 Op-Test No.: _ Scenario No.: 3 Event No.: 4 Page 4 of 8 Event

Description:

_Rapid Plant Shutdown due to RCS leak

[Time Position Applicant's Actions or Behavior CRF Direct actions of AP-TURB.5 RAPID LOAD REDUCTION HCO/CO Initiate load reduction Monitor RCS Tave Borate as necessary Check IA to CTMT Monitor plant parameters I- I-

i. i I I

+ +

1- 4

+ i 4- .4-NUREG-1021, Revision 8, Supplement 1 40 of 40

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

Description:

-Condensate header break 20K .qpm, Loss of MFW Time Position Applicant's Actions or Behavior CRF Direct actions -AP-FW.1 Partial or complete loss of MFW HCO/CO Check MFW requirements Verify MFW pump status Check MFW Pump suction pressure Total loss of MFW - Transition to E-0

__ I ___ I ________________

I. f I. t I

4 4 4

t 4 4 NUREG-1021, Revision 8, Supplement 1 40 of 40

Ann*nHiY n *n*.r*tnr A*finns Form ES-D-2 Op-Test No.:_ Scenario No.: 3 Event No.: 6 Page 6 of 8 Event

Description:

_ATWS and Failure of Main Turbine to Trip Time Position Applicant's Actions or Behavior CRF Direct actions of E-0 HCO/CO Verify Rx Trip - NO Manually trip the reactor - NO CRF Transition to FR-S.1 HCO/CO Verify Rx Trip - NO RNO- Manually trip reactor Manually insert rods Verify Turbine Stop Valves closed - NO Manually trip turbine Verify AFW flow Initiate Emergency Boration Check PZR PORV status - NO Open PORVs as necessary to control pressure Verify CTMT ventilation isolation CRF Dispatch AO to locally trip reactor - YES Transition to E-0 Direct actions of E-0 HCO/CO Verify Rx Trip Verify turbine stop valves closed Verify AC emergency busses Check if SI is actuated Verify SI and RHR pumps running Verify CTMT recir fans running Verify CTMT spray not actuated NUREG-1021, Revision 8, Supplement 1 40 of 40 Appendix D Operator Actions Form ES-D-2

Op-Test No.: Scenario No.: _3 Event No.: 6 con't Page 7 of 8 Event

Description:

ATWS and Failure of Main Turbine to Trip F Time Position Applicant's Actions or Behavior HCO/CO Check if any main steamline should be isolated Verify MFW isolation Verify AFW pumps running Verify CI and CVI Check CCW system status Verify Sl and RHR flow Verify AFW flow > 200 gpm Verify SI pump and RHR pump emergency alignment Check CCW flow to RCP Thermal barriers Check if TDAFW pump can be stopped Monitor RCS Tave- stable or trending to 547 degrees Check PZR PORVs and Spray valves Monitor RCP Trip Criteria Check if SIG Secondary side is intact Check if S/G Tubes are intact Check if RCS is intact - NO Transition to E-1 NUREG-1021, Revision 8, Supplement 1 40 of 40

Form ES-D-2 A '*n,*nHiv N VV r,,,./ f r t Actions Onerator Acios.om....

Op-Test No.: Scenario No.: 3 Event No.: Page 8 of 8 Event

Description:

Loss of Reactor or Secondary Coolant (E-1)

Time Position Applicant's Actions or Behavior CRF Direct actions of E-1 HCO/CO Monitor RCP Trip Criteria Check if S/G secondary side intact Monitor intact S/G levels Monitor if secondary radiation levels are normal Monitor PRZ PORV status Reset Sl and Cl Verify adequate SW flow Establish IA to CTMT Check normal power to charging pumps Check if charging flow has been established Check if Sl should be terminated Monitor if CTMT spray should be stopped Monitor if RHR pumps should be stopped Check RCS and S/G pressures Check if EDGs should be stopped Check if RHR should be throttled Verify CTMT sump recirculation capability Evaluate Plant Status NOTE: SHOULD MEET Sl TERMINATION CRITERIA PER FOLDOUT PAGE CRITERIA OR STEP 12 OF E-1 CRF Transition to ES-i.1. Sl TERMINATION I Classify as a Site Area NUREG-1021, Revision 8, Supplement 1 40 of 40