ML020870156

Final - Section C Operating (RO & SRO)

ML020870156
Person / Time
Site:	Ginna
Issue date:	02/11/2002
From:	Watts R Rochester Gas & Electric Corp
To:	Conte R NRC/RGN-I/DRS/OSB
References
05000244/2001-301 05000244/2001-301
Download: ML020870156 (25)

Text

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

Laughlin (Conte)

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 /> ago for condenser tube leakage and is ready to go back to full power.

BAST C, - 11,000 ppm. "B" MDAFW pumo and "C" charging pump are OOS.

Turnover: Plant is at -48% reactor power, MOL. C8=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 Dom. "C" charaina oumo is OOS for excessive leakaae. "B" MDAFW oumo is OOS for check valve repair.

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

R(HCO 2 NIS07A I(CRF, PR channel N41 fails high, rods insert. (Enter ER-NIS.3, TS HCO) entry) 3 ROD2A C(CRF, Dropped control rod C7. (Enter AP-RCC.2 for RCC HCO) malfunction, AP-RCC.3 Dropped Rod Recovery) 4 CND07 C(AII) Loss of condenser vacuum-east 1B, results in turbine/Rx A trip. (Enter AP-TURB.4 and EO) 5 EDS01 M(AIl) Loss of offsite power. "A" EDG runs on bus 14.

A&B 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 1 (r

• (N)ormal, I I (RJUeactvity, I

(~instrument, (C)omponent, (M)ajor 39 of 40 NUREG-1021, Revision 8, Supplement I

Armendix D Operator Actions Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 01 Event No.: 1 Page I of 6 Event

Description:

Raise reactor power to 100% lAW O-1.2 Time Position Applicant's Actions or Behavior CRF Direct start of "B" MFW pump per Step 5.8.12.

Go to "MFW Pumo B Attachment" Steps 7.0- 13.0

_O Lineuo Service Water to MFW oumo B oil cooler Take B MFW out of Pull Stop Verify MFW oumo recirculation valve opens (AOV-4148)

Start "B"MFW p2ump Verify MFW oumo discharge pressure and open discharge valve MOV-3976 ICRF Direct AO to close B MFW oumo discharge bypass valve MOV-3976A CO Place HDT Level Controler LC-2013A in Auto CRF Direct AO to check MFW oump warmuo valves closed HC.O Check Delta I cumulative time on PPCS Verify QPTR is <1.02 CRF Verify RP has a leak rate determined from the air eiector samole CO Raise valve position limit to 100%

Raise Setter and start load increase HCO Manually ooerate control rods/dilute as necessary to control Tave Rods in "Manual". raise power at 10%/hr L

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

Ann=nHiY I"1 O3namn~r Arfinn_* Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 01 Event No.: 2 Page 2. of 6 Event

Description:

PR Channel N41 Fails High Time Position Applicant's Actions or Behavior All Identify failed PR channel (ANN AR-E-1 9, 21, 26)

HJO Place rod control bank selector switch in manual HO/CO Adiust Tave/ Tref as necessary

_RF Address Technical Soecifications (ITS3.2.3)

Direct NIS channel 41 to be defeated oer "Attachment N-41 Defeatr HO Verifv rod control bank selector switch in manual HCO/CO Place DROPPED ROD MODE switch to byoass and verify following alarms - DROPPED ROD BYPASS light is lit:

POWER RANGE ROD DROP BYPASS (MCB status light) is lit:

Annunciator E-7 NIS TRIP BYPASS is lit Place TI405E DELTA T DEFEAT switch to LOOP A UNIT I Place OVERTEMP TRIP bistable switch to DEFEAT and verifv 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 & verifv f ft**II,,,in" th___*ll_

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

Ann*ndiY 1"3 Onerator Action* Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 01 Event No.: 2 (con't) Page 3 of 6 Event

Description:

PRN41 Failure Time Position Applicant's Actions or Behavior HCOICO Remove 11 8V 5A AC INSTR POWER fuses & verify the following E-18 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 NC41 R HI POW RANGE P-9 NC41S Verifv various status lights on PR N41A drawer are lit Verify following status lights on PRN41 B drawer are extinguished:

INSTRUMENT POWER ON CHANNEL ON TEST ERF Notify I&C to install iumpers HCO/CO Restore ROD CONTROL back to AUTO Reset dropped rod rod stop signals at PR NIS drawers ERF Check Tech Soecs GNotify ORerationss I&C Suervision: Reactor EnSineer NUREG-1021, Revision 8, Supplement 1 40 of 40

Appendix D Operator Actions Form ES-D-2 Appendix D Operator Actions Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 01 Event No.: _3 Page 4 of 6 Event

Description:

Dropped Control Rod C7 (Enter AP-RCC.2 for RCC malfunction, 0-5.1 for load reduction) Annunciator C-5 Rod Deviation liaht lit, Annunciator F-29 PPCS or QUADRANT POWER TILT lit.

Time Position Applicant's Actions or Behavior HCO/CO Place Rod Control Bank Selector Switch to MANUAL Check Droooed Rod Indication - Pwr and Tave decreasing Go to AP-RCC.2(RCC Malfl. then RCC.3 (Dropged Rod Recoverv)

Check dropped rod indication - ANN E-28 and C-14 lit CO Place EH control in MANUAL (Tayg not stable)

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 Check QPTR<1.02 (verify computer value 0-6.4. ITS 3.2.4)

CRF Evaluate Control Rod Operability Direct I&C to locally investigate rod failure (Will not try to retrieve rod)

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Appendix D Operator Actions Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 01 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 ANN H-7 (Cond HI Press), 1-18 (Cond Exp Joint Lo LvI)

CRF Directs entry into AP-TURB,4 LOSS OF CONDENSER VACUUM Dispatches AO to perform local actions, directs turbine trip CRFDirects Rx Trip and entry into E-0 HCO/COj') Performs Immediate Actions of E-0 Verify Rx Trio 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 Trio Resoonse Monitor RCS Tave-stable or trending to 547 deg Check S/G Feed Flow Status Verify all rods on bottom CUE: Needed for LOOP 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 oump per RNO step 5 Verify IAAvailable Check PZR Level Control - start chargina pumg(s) per RNO steo 7 I E"A" DIG trips - Loss of all AC CRF Directs transition to ECA-0.0 Loss of all AC

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Appendix D Operator Actions Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 01 Event No.: 5_,_7 Page 6 of 6 Event

Description:

Loss of all AC Time Position 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 D/G CRF Direct AO to locally restart a D/G HCO/CO Pull Stop AC emergency bus loads. SW switches to STOP-AUTO Isolate RCP seal injection Try to restore offsite power - NO Restore IAusing D/G A/C CRF Initiate local actions to isolate RCS. provide cooling to vital equip.

Place hotwell level control in manual at 50%

--Check S/G status - secondary side and tubes intact Monitor intact S/G levels Check DC bus loads ("B" EDG restored at this point)

SCRF Direct manual start of "B" D/G (pick up busses 16&17)

CO Manually control S/G ARVs to stabilize S/G pressures er" Restore SW pumps (refer to AP-SW.2 start "D" SW pumDp Verify equipment loaded on available AC emergency buses CRF Direct AO to check battery chargers

-Direct transition to ECA-0, 1. END at transition ICRF Site Area Classification I I I I

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

Lauahlin (Conte)

Silk Initial Conditions: Plant is at 100% power, BOL, C, 1329 ppm, equilibrium xenon.

PORV-430 isolated due to hiah leakaae MOV-516 closed. BAST C - 11.000 oDm.

Turnover: Plant is at 100% power, equil. xenon, C.=1329 ppm. BASTC =11,000 ppm. "A" and "D"SW oumos are selected on Safeauard Selector Switches. PORV-430 is isolated due In AVA fn ayCp-mQiVP 1pnkneum Event Malf. Event Event No. No. Type* Description PZR01 C(CRF, PZR spray valve PCV-431A fails open approx 50%. (Enter A HCO) AP-PRZR.1) 2 PZR03 I (CRF, PZR level instrument LT428 fails low (Enter ER.INST.1)

C HCO) 3 TUR05 C(CRF, Turbine vibration increases. (Enter AP-TURB.3, requires C CO) load reduction to stabilize vibration)

R(HCO 4 SGN04 C(AII) S/G tube leak on S/G 1A at 400 gpm. (Enter AP-SG.1, E-0)

A 5 TUR02 C(CRF, Turbine fails to trip. (Manually trip turbine per E-0)

TUR11 CO)

D 6 C(HCO Instrument air to CNMT fails.

CO) 7 SIS03B C(CRF, 1B SI pump fails to start.

HCO) 8 SGN04 M(AII) SGTR on S/G 1A. (Enter E-3)

A 9 PZR05 C(CRF, PORV 431 fails open, resulting in SBLOCA. (Enter ECA-3.1)

B HCO) Terminate when RCS cool-down is underway.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 02 Event No.: I 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 - 4 chan equal. <2235 and >2000 osig Check Rx Power stable Check Pzr heater status - control group and backup Verify spray valves closed - NO

-Place controllers in manual (ahO% demand Check Pzr Pressure

--controller 431K. 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 I +

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Ap)pendix D Operator Actions Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 02 Event No.: -2 Page 2 of 7 Event

Description:

PZR level LT428 fails low Time Position Applicant's Actions or Behavior HCO Identifies LT428 failed low ANN F-11 PZR low level. F-14 Chg oump sod HI HCO Enter AR-F-11. 14 Check Chg pump speed, control in Auto or Manual Check PZR level and pressure

-Check Tava channels & recorder for normal indication

-Perform channel check PZR level channels CRF Directs entry into ER-INST, I to defeat channel NUREG-1021, Revision 8, Supplement 1 40 of 40

Appendix D Operator Actions Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 02 Event No.: 3 Page 3 of 7 Event

Description:

Turbine vibration increase resulting in a load reduction Time Position Applicant's Actions or Behavior CRF Recognize hi turbine vibration, enter AP-TURB.3 (ANN 1-27)

Verify turbine vibration all brgs <14 mils CRF/CO Check turbine vibration:

- Bras 1-8 <7 mils - NO

- Brg 9 <8.5 mils Attempt to stab vibration - begin reducing load (Maybe AP-TURB.5 Check vibrations-stable or decreasing, stop load reduction HCO Stabilize drimary systems - Tave. Press. Level. RIL alarms ext.

CRF/CO Evaluate turbine operation:

CRF No unusual noises. conditions stable - NO. Notify Maint Mar Notify higher suoervision I 4 I 4.

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Appendix D Oo~erator Actions Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 02 Event No.: 4 Page 4 of 7 Event

Description:

SIG tube leak on S/G A at 400 .qpm, enter AP-SG. 1 S/G Tube Leak Time Position Applicant's Actions or Behavior HCO Identifies PZR level and pressure decrease CRF Directs entry into AP-SG.I S/G Tube Leak HCO Charging pump speed alarm/flow increase Increasina radiation levels on R-15. R-19 and R-31 HCO Start additional charging pumos Close IooQ B cold lea to regen Hx AOV-427 CRF Direct Rx Trip if charaing pumos running at max soeed with L/D isol YES - Enter E-0 1

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

Aooendix D Form ES-D-2 Aooendix D Oroerator ActionsFomED-Op-Test No.: 02-01 Scenario No.: 02 Event No.: 5.,7_ Page 5 of 7 Event

Description:

Rx Trip, turbine fails to trip. 1B SI pump fails to start, IAto CNMT fails Time Position Applicant's Actions or Behavior CRF Direct actions of E-0 HCO/CO Verify Rx Trip SLVerifv turbine stop valves closed- NO- MANUALLY TRIP TURBINE Verify both AC Emergency Busses Energized Check if !SActuated Verifv SI/RHR pumps running -NO-MANUALLY START B SI PUMP Verify CNMT RECIRC FANS running Verify CNMT Spray NOT reauired Check if Main Steamlines should be isolated Verify MFW Isolation Verify AFW Pumps Running Verify at least Two SW Pumrps running Verify CI and CVI Check CCW System Status Verifv SI and RHR Pump Flow Verify AFW Flow > 200 GPM Verify AFW Valve Alignment Verifv SI Purnm and RHR Pump Emergency Alignment Check CCW Flow to RCP Ther Barr, (ANN A-7.15 ext)

Check if TDAFW can be stoped. Tav stable or trending to 547 Check PZR PORVs and Spray Valves - closed, oress<2260 Monitor RCP Trip Criteria Check if S/G Secondary Side is Intact Check if S/G Tubes are Intact - NO- Transition to E-3 HCO Identifies loss IAto CNMT NUREG-1021, Revision 8, Supplement 1 40 of 40

Aonendix D On*mtnr Ar.tinn* Form ES-D-2 Aor~ndi D n~rnor e~tnnsForm ES-D-2 Op-Test No.: 02-01 Scenario No.: 02 Event No.: 8 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- JA S/G (incr level. R-31 alarm)

Isolate Flow From Rugtured 1A S/G (ARV. TDAFW supp. B/D)

_ _ _ Comolete Ruotured S/G Isolation (MSIV. AO to isol)

Check Ruptured S/G Level Verify Ruptured S/G Isolated Establish Condenser Steam Dumo Pressure Control Reset SI Initiate RCS Cooldown - dump steam from S/G B Monitor Intact S/G Level - maintain 17-50%

Check PZR PORVs and Block Valves - PORVs closed. 1 BIk open Reset Cl Monitor AC Busses - Energized by Offsite Power Verify adequate SW Flow - 2 pumps running Establish IAto CTMT - AOV 5392 FAILS to OPEN Check if RHR Pumps should be stopped (place to OFF. AUTO)

Establish Charging Flow - start oump Check if RCS Cooldown Should be Stopped Check ruptured S/G pressure Check RCS subcooling Depressurize RCS to minimize break Flow and Refill PZR IAto CNMT available - NO, depress using PORV (Aft N2 PORVs)

Close PORV - NO. Block valve - NO Check RCS Pressure INCR - NO - TRANSITION TO ECA-3.1 NUREG-1021, Revision 8, Supplement 1 40 of 40

Appendix D Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 02 Event No.: 9 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 - 2 pumos running Establish IAto CTMT - NO AC Busses eneri;zed by offsite power Monitor CTMT Spray Pumps - STOPPED Check Ruptured 1A S/G Level - verify feed flow stoPoed Check if RHR Pumps should be stopped - are stopped Evaluate Plant Status -AB rad normal. RCS/CNMT samples Establish 75 GPM Charging Flow Check SIG Secondary Side and Intact S/G Levels Initiate RCS Cooldown to Cold Shutdown

___ _ Monitor conditions for subcooled recovery EClassify RF_ as Alert t

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

Appendix D Scenario Outline Form ES-D-1 Facility: Ginna Scenario No.: 03 Op-Test No.: 02-01 Examiners: Bissett Operators:

Laughlin (Conte)_

Silk 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 Ii% mn~fnr f~il, r*

fe%mefrr fnil"ra Turnover: Plant is at 100% power, BOL xenon equilibrium. Boron=1329 pDm.

BAST=1 1.000 Dom. Ckt 751 r-is OOS due to auto accident. "D" SW pump OOS due to motor fih

= im . flnntinijA normI ooArntinn f2il"ra nntinue normal onerations Event Malt. 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-RCP.1)

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

I HCO) (Enter AP-RCS. 1) (Cue to start shutdown) 4 N/A N(CRF) Perform plant shutdown in response to RCS leak. (Enter 0 R(HCO 2.1 orAP-TURB.5, 100% to 95%)

5 CND8 C(CRF, Condensate header break 20K gpm, complete loss of main CO) feedwater. (Enter E-0, AP-FW. 1) 6 RPS5A M(AII) ATWS (Enter FR-S.1)

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

CO) 8 N/A N(AII) Loss of reactor or secondary coolant (Enter E-1), due to RCS leak 9 N/A C(AII) Low CST level <5 feet (Enter ER-AFW. 1 if needed)

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

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 03 Event No.: 1 Page 1 of 9 Event

Description:

PZR pressure channel PT-449 fails HI Time Position Applicant's Actions or Behavior CRF PT-449 fails HI, directs entry into AP-PZR.lAbnormal PZR PRESS HCO/CO Acknowledges ANN F-2 PZR HI Press Checks PZR Press -Place cont. 431K in MANUAL. restore Dress, Refer to ER-INST.1 RPS Bistable Defeat (Sect. 4.4)

--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 (ANN F-23, F-27) 408 LOOP B OVER TEMP TRIP (light on MCB) 449 CHANNEL 4 - LOW PRESS TRIP (light on MCB)

Place PZR pressure recorder to Dosition 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 Ooerations Supervision NUREG-1021, Revision 8, Supplement 1 40 of 40

Appendix D Operator Actions Form ES-D-2 Op-Test No.: 02-01 Scenario No 03 Event No.: 2 Page 2 of 9 Event

Description:

"B" RCP #3 seal failure Time Position Applicant's Actions or Behavior HCO Acknowledges ANN B-12 RCP STAND PIPE LO LEVEL 4FT Refer to AR-B-12, refill the stand pipe CRF

_ Directs actions of AP-RRP. 1 RCP SEAL MALFUNCTION HCO/CO Check Total #1 Seal Flow < 8.0 GPM Check RCP Seal Return valve Alignment MOV313 Open. AOV270B Open Check Total #1 Seal Flow Between .8 - 6.0 GPM Check RCP cooling (ANN A-7. A-15 exting.)

Check RCP #2 Seal Indications (ANN B-4 exting.)

Check RCP Labyrinth Seal DIPs > 15" Check RCP #3 Seal Indications (ANN B-12 not exting.)

RNO Check CTMT rad monitors R-11.12 - C y-- "

1. 3 seal leakage probable. monitor RCP Seal Conditions NUREG-1021, Revision 8, Supplement 1 40 of 40

Appendix D Operator Actions Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 03 Event No.: 3 Page 3 of 9 Event

Description:

RCS leak inside CNTMT from A loop hot leg 15 .qpm Time Position I Applicant's Actions or Behavior CRF Directs actions of AP-RCS. 1 REACTOR COOLANT LEAK HCO/CO --Acknowledaes ANN F-14 (CHV pp sod), A-2 UCT level). F-4(PZR)

E-16 (R-2&IOA high activity). C-18 (sumo pump auto start)

Check PZR level (Decreasing) RNO actions Start additional charging Dumos (stab. PZR level)

_Check VCT M/U System (level>20% or stable)

Check if RCS leakage in CTMT R-2.IOA not normal. direct RP samole CNTMT Disoatch AO to Aux Bldg investigate leak Check for leak to CCW System-normal

__Check CVCS Conditions -normal Check AUX Bldg radiation levels-normal Check PRT Indications-normal Check S/Gs for Leakage-rad monitors normal Check SI Accumulator levels Check RCP Seal Leakoff Flows Check RCDT Leak Rate normal Check Valve Leakoff Temos Establish Stable Plant Conditions-PZR level, pressure Evaluate RCS Leakage -not within limits (12-15 aom)

NOTE: Cue S/D 0 1%/min RNO - C.ommence Plant Shutdown at 1%/min (AP-TURB.5.

CRF Notify higher supervision

.9 I NUREG-1021, Revision 8, Supplement 1 40 of 40

Appendix D Operator Actions Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 03 Event No.: 4 Page 4 of 9 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-Rod Cont in Auto Monitor RCS Tave (545-566 deg)

Borate as necessary (-2gal/% load reduction)

Check IA available to CNTMT Monitor plant parameters (PZR press/level. S/G level)

NOTE: Condensate Hdr break @) 95% (AP-FW. 1)

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 03 Event No.: ,5 Page 5 of 9 Event

Description:

Condensate header break 20K aqpm, 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-both pos running Verify MFW pump status Check MFW Pumo suction pressure > 185 osig (NO. plant trip)

Total loss of MFW - Transition to E-0 4

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

Aooendix D Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 03 Event No.: 6-7 Page 6 of 9 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 Verifv Turbine Stop Valves closed - NO C Manually trip turbine Verify AFW flow Initiate Emergency Boration - 2 BAT pumps Check PZR PORV status - NO Open PORVs as necessary to control pressure Verify CTMT ventilation isolation (ANN A-25)

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 both trains AC emergency busses Check if SI is actuated Verifv SI and RHR pumps running Verify CTMT recirc fans running Verify CTMT spray not actuated NUREG-1021, Revision 8, Supplement 1 40 of 40

Ann*ndiY FI I'*n*rmtnr A*finn* I*'n rm I::.q.13.9 Op-Test No.: 02-01 Scenario No.: 03 Event No.: 6-7 con't Page ._.7 of 9 Event

Description:

ATWS and Failure of Main Turbine to Trip

[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 at least 2 SW Dumps running Verify Cl and CVI (ANN A-25. 26)

Check CCW system status Verify SI and RHR flow Verify AFW flow > 200 gpm. and valve alignment Verify SI pump and RHR pump emergency alignment Check CCW flow to RCP Thermal barriers Check if TDAFW pump can be stopped-Yes Monitor RCS Tave- stable at or trending to 547 degrees 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 Check if RCS is intact - NO CRF Transition to E-1 NUREG-1021, Revision 8, Supplement 1 40 of 40

Appendix D Operator Actions Form ES-D-2 Appendix D Operator Actions Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 03 Event No.: 8_ Page 8 of 9 Event

Description:

Loss of Reactor or Secondary Coolant (E-1), due to RCS leak 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 SI and Cl Verify adequate SW flow Establish IAto CTMT Check normal power available to charging pumrs Check if charging flow has been established Check if SI 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-No pumps running Verify CTMT sump recirculation capability Evaluate Plant Status NOTE: SHOULD MEET SI TERMINATION CRITERIA PER FOLDOUT PAGE CRITERIA OR STEP 12 OF E-1 CRF Transition to ES-1.1. SI TERMINATION Classifv as a Site Area NUREG-1021, Revision 8, Supplement 1 40 of 40

Appendix D Operator Actions Form ES-D-2 Op-Test No.: 02-01 Scenario No.: 03 Event No.: 9 Page 9 of 9 Event

Description:

Low CST level (< 5 feet) Transition to ER-AFW.1 (If needed)

Time Position Applicant's Actions or Behavior CRF Direct actions of ER-AFW. 1 Sect. 4.1 CO Cond ump in service, reiect water to CST by adjusting LC107 Cond pump not available, use cond transfer pump Perform appropriate valve alignment

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