ML082950432

R. E. Ginna Draft - Section C Operating Exam (Folder 2)

ML082950432
Person / Time
Site:	Ginna
Issue date:	09/01/2008
From:	Ginna
To:	Todd Fish Operations Branch I
Hansell S
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ML080030004	List: IR 05000244/2008301 ML081360258 ML082950349 ML082950384 ML082950389 ML082950422 ML082950425 ML082950432 ML083110590 ML083110619 ML083110659 ML083110665 ML083510111 ML083660253
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TAC U01687
Download: ML082950432 (88)

Text

Appendix D Scenario Outline Form ES-D-1 Facility: R. E. Ginna Scenario No.: 1 Op-Test No.: 1 Examiners: - Operators:

Initial Conditions: 70%. EOL Turnover: SI Pump A 00s to refurbish failed motlx, S/G A LT-461 00s due to failed electronics, MDAFW Pump A 00s for impeller replacement Event Malf. Event No. No. Description 1 TUR16B I- BOP/SRO PT-486 Turbine First Stage Pressure Fails Low.

2 RCS11F I-All, TS-SRO Loop B ThotTE-404A fails high.

C-ATC/SRO, 3 TS-SRO S/G B l u b e Leak of = 10 gpm R-ATC, 4 N/A N-BOP/SRO Plant Power Reduction RCSl5B, 5 RCS15D C-ATC/SRO RCP 1E High Vibration SGN04B, STM03, STM05B, Main Steam Line Break Downstream of MSlVs which causes S/G tube RHRO1A, leak to rise to a 400 GPM tube rupture in S/G B. MSlV B faits to close M-All, RPS07C, automatically or manually from the MCB, SI Pump C fails to Auto Start on k 6 RPSO7D C-BOP SI Signal, RHR Pump A trips on auto start.

' (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Revision 00 Page 1 of 17

Facilty: R. E. Ginna Scenario No.: 1 Op-Test No.: 1 Scenario

Description:

After the crew takes the watch, PT-486, Turbine First Stage Pressure fails low. This results in Steam Dumps being armed, but not open. The crew should 'determine the instrument is failed, verify AR-G-15, and implement ER-INST.l, Reactor Protection Bistable Defeat after Instrumentation Failure, to place the appropriate RPS bistables in the trip condition.

After the crew completes actions for PT-486, Loop B Thot TE-404A fails high. This results in the steam dumps opening. The crew should take action to stabilize the plant, implement ER-INST.l, and close the steam dumps. The ATC should place Rods and Charging pump A in manual. The SRO should refer to and enter TS 3.3.1 Condition D and Action D.l and 3.3.2 Condition F and Action F.l.

After the crew stabilizes the plant but before the failed channel is defeated, a 10 GPM primary-to-secondary leak develops in Steam Generator B. The crew should implement AP-SG.l, Steam Generator Tube Leakage.

The SRO should refer to and enter TS 3.4.13 Condition B and Actions B.l and 8.2.

Due to the steam generator tube leakage, the crew should initiate a plant shutdown with a turbine ramp rate of 3%/min per AP-SG.1.

During the plant shutdown, RCP 1B Vibration rises. The crew should implement AR-AA-18 and/or AR-AA-26.

Vibrations rise to the point of requiring a manual reactor trip to allow securing RCP 1B.

After the crew trips the reactor and secures RCP 1B, a steam leak downstream of the MSlVs occurs, which causes the tube leakage to rise to 400 gpm. MSlV B fails to close automatically or manually from the Control Room requiring local closure. SI Pump C fail:; to auto start and RHR Pump A trips on start after an SI. The crew should manually start SI Pump C. The crew should implement E-0, transition to E-2, and then to E-3.

The crew should send an A 0 to locally close the failed MSlV and secure feeding S/G B when level requirements are met (> 7% NR). The local closure of the MSlV will be successful after entry into E-3. Once in E-3 the crew may need to feed S/G 6 to > NR and then re-isolate feed flow. The scenario may be ended after the crew completes the initial cool down of the RCS in E-3.

Revision 00 Page 2 of 17

Facilty: R. E. Ginna Scenario No.: 1 Op-Test No.: 1 CRITICAL TASKS CT E-0--I Task: Establish flow from at least one train of high pressure SI pumps (two pumps running with flow to opposite trains) before transition out of E-0.

Cues: A SI pump 00s B SI pump running C SI pump not running Indication: C SI pump manually started from MCB Feedback: B and C SI pump indicate running from status lights and SI flow indicated CT E-3--A Task: Isolate feedwater flow into and steam flow from the ruptured steam generator before a transition to ECA-3.1 occurs.

Cues: Indication of SGTR 0 Increasing SG water level Steam generator radiation and SI actuated and Rx trip actuated Indication: Manipulations of controls to isolaie the ruptured SG 0 MSlVclosed 0 Local isolation by attachment Ruptured SG initiated ARV setpoint adjusted to 1050 in Auto SG blowdown and sample valve closed (verify) 0 TDAFW steam supply valve from ruptured SG closed 0 MDAFW and TDAFW dischaige valve to ruptured SG closed 0 Main feed reg and bypass valve to ruptured SG closed, main feedwater pumps tripped (verify)

Feedback: Ruptured SG pressure stable or increasing. No indication of feed flow to ruptured SG.

Revision 00 Page 3 of 17

Facilty: R. E. Ginna Scenario No.: 1

-___ Op-Test No.: 1 Scenario Timeline:

Event Time Delay Ramp Number (Min) Key Event HH:MM:SS HH:MM:SS Final N/A LOAD SGNO1 B N/A oo:oo:oo 00:00:00 0

- S/G LEVEL CHANNEL FAILURE: LT-461(I) 1 2 TUR16B 1 oo:oo:oo oo:oo:oo 0 FIRST STAGE PRESSURE TRANSMITTER FAILURE : PT-486 2 *** (- 11) RCS11F 3 oo:oo:oo oo:oo:oo 980 RTD FAILURE : LP B HOT TE-404A (TT-404)IV 3 *** (-18) SGN04B 5 oo:oo:oo 0O:Ol :oo 10 S/G B TUBE LEAK AT TUBE SHE!ET 4 (-22) N/A NIA oo:oo:oo oo:oo:oo N/A PLANT POWER REDUCTION 5 *** (-28) RCSl5B 7 oo:oo:oo 00:03:00 25 RCP HIGH VIBRATION : RCP-1E SHAFT 5 RCS15D 7 oo:oo:oo 00:03:00 10 RCP HIGH VIBRATION : RCP-1I? SEISMIC 6 *** (-32) STMO3 9 oo:oo:oo oo:oo:oo 200,000 STEAMLINE BREAK OUTSIDE CNMT DOWNSTREAM OF MSIVS 6 *** (-32) SGN04B N/A oo:oo:oo 00:03:00 400 S/G B TUBE LEAK AT TUBE SHEEET 6 LOAD STMO5B NIA oo:oo:oo oo:oo:oo 100 MAIN STEAM ISOLATION VALVE FAILURE : VLV 3516 6 LOAD RPS07C N/A oo:oo:oo oo:oo:oo 1 AUTO FAIL: C SI PUMP ON BUS 14 6 LOAD RPS07D N/A oo:oo:oo oo:oo:oo 1 AUTO FAIL: C SI PUMP ON BUS 16 6 LOAD RHROlA NIA oo:oo:oo oo:oo:oo 1 RHR PUMP 1A TRIP

• • • Events initiated on cue from NRC Lead Examiner Estimated Time: 65 Minutes Revision 00 Page 4 of 17

Amendix D Reauiired ODerator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 1 Event

Description:

(T=2)

PT-486, Turbine First Stage Pressure Fails LCIW Indications:

PI-486 on vertical section of Board 1 failed Lo 0 G-15, Steam Dump Armed lit ASAC Auto Block Lil i t after 205 seconds P

P Position --

BOP Recognizes failure of PT-486 and reports to SRO.

BOP/SRO Refers to Annunciator Response Procedure AR-G-15 and determines that ER-INST.1, Reac:or Protection Bistable Defeat After Instrumentation Failure should be entisred.

SRO Enters ER-IN!sT.l and determines Section 4.12 is the correct section to implement.

SRO Determines that the Steam Dump system should not be reset.

SRO Refers to Attachment FIRST STAGE PRESSURE PI-486, BLUE, to defeat channel AND to restore AUTOMATIC control.

BOP Places the following bistable proving switch to DEFEAT (UP) AND verifies the proving light status is correct in the (BLUE) 6-1 PROTECTION CHANNEL 3 rack:

0 486 CHANNEL 3 TURBINE PWR TRIP Light ON BOP/ATC Verifies the AMSAC TRIPPED status liaht (MCB) is extinauished.

BOP/SRO Requests an A0 verify the TL 400 bistable indicating light (FOX 3-RELAY ROOM) is extinguished.

BOP/SR0 Sends an A 0 to verify AMSAC feedwater flow bistables are reset: (FOX 3 RELAY ROOM)

TU4E16 TRIP STATUS LIGHT EXTINGUISHED TU4E17 TRIP STATUS LIGHT EXTINGUISHED TU476 TRIP STATUS LIGHT EXTINGUISHED TU477 TRIP STATUS LIGHT EXTINGUISHED BOP/SRO Requests A 0 place switch TPS/486 (FOX 3-RELAY ROOM) to the TRIP position AND verify TU486 TRIP STATUS light is lit.

BOP/ATC Verifies the AMSAC AUTO BLOCK status light (MCB) is extinguished.

BOP Deletes the computer point from the PPCS by performing the following on the Sub/Delete/Flestore display:

Select Point ID PO486 0 Turn OFF scan processing 0 Select Chanae

-End of Event R. E. Ginna Nuclear Plant Page 5 of 17 Revision 00

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

Description:

(- T = l l )

Loop 6 Thot TE-404A fails high Indications:

Steam Dumps indicate open F-14, CHARGING PUMP SPEED LIT F-15, RCS TAVG DEV 4'F LIT F-16, TAVG-TREF DEVIATION +/- 5 'F LIT F-23, RCS OTAT CHANNEL ALERT -IT F-24, RCS AVG AT DEVIATION LIT F-32, RCS OPAT CHANNEL ALERT LIT RCS Tavg lowering TI 404 higher thaii TI-401 through TI-403 BOP Take Steam Dump Mode Selector Switch to Manual, places Steam Dump Controller in MANUAL, lowers output to 0, and verifies Steam Dump valves indicate closed. (may enter ER-INST.l first)

SRO Enters ER-IN!;T.l, Reactor Protection Bistable Defeat after Instrumentation Failure, and goes to step for RCS Tavg or AT failures.

ATC Drives rods in manually until operable Tavg channels are at program.

BOP Places steam dump mode selector to MANUAL.

ATC Places chargiiig in MANUAL to stabilize PRZR level.

SRO Refers to ITS LCOs 3.1.5 and 3.1.6 to determine actual insertion limits.

SRO Refers to TAL'G 404/ DELTA T 408 YELLOW CHANNEL attachment for defeat of the associated control functions.

Verifies Rod Control selector switch in MANUAL.

Verifies Charcling Pump speed controllers in MANUAL.

Check the folllswing ITS Sections for LCOs:

Section 3.3.1, Table 3.3.1 -1, Functions 5 and 6 I

Enters Condition D and Action D.l 3.3.2, Table 3.3.2-1, Function 4d Enters Condition F and Action F.l End of Event R. E. Ginna Nuclear Plant Page 6 of 17 Revision 00

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

Description:

(- T=18)

S/G B Tube Leak of = 10 gpm Indications:

0 PRZR Level slowly lowering 0 PRZR Pressure slowly lowering 0 PPCS, computer point SGTL Indicated Position ATC/BOP Recoanizes indications and alarms and reDorts to SRO.

SROIATC Refers to AR-PPCS-1 (SGTL Indicated) 0 Trencls PPCS point R-47G.

0 Notifies RP/Chemistry to IMMEDIATELY obtain and analyze an air ejector grab sample per CH-SAMP-SG-LEAKRATE.

0 Determines the estimated leak rate using PPCS point R47G or the R-47 Local Reading and the Conversion Table (Curve Book #06-004).

IF any condition below is met, THEN go to AP-SG.1, STEAM GENERATOR TUBE LEAK:

o R47G (PPCS) greater than 5 gpd OR o R-47 greater than or equal to 5 gpd (per conversion table)

SRO Enters AP-SG.1, Steam Generator Tube Leakage ATC Monitors PRZR Level and starts additional charging pumps, or raises charging pump speed, as necessary to stabilize PRZR level.

Crew Monitors S/G tube leak rate and estimates S/G tube leak rate:

0 Charging/Letdown mismatch A VCT Levelnime PPCS Point R47G R-47 drawer indication (using conversion table, Curve Book #06-004)

ATC/BOP Determines tctal RCS to secondary leak rate is not less than 1 gallon per minute (1440 GPD)

SRO Moves forward in procedure to step 8 and orders a plant shutdown.

SRO Notifies Higher Supervision.

Crew Performs Dart; A AND B of ATT-16.1. ATTACHMENT SGTL.

SRO Dispatches an A 0 to perform T-35H, Nuclear House Heating Steam To Boiler Steam Supply Change Over R. E. Ginna Nuclear Plant Page 7 of 17 Revision 00

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

Description:

(- T=l8)

S/G B Tube Leak of = 10 gpm Indications:

0 PRZR Level slowly lowering PRZR Pressure slowly lowering PPCS, computer point SGTL Indicated obtain the following samples:

RCS 3oron xtivity (ITS 3.4.16)

R Pressure - TRENDING TO 2235 PSlG IN AUTO or Control pressu?eby one of the following:

0 431K in MANUAL al control of PRZR heaters and sprays sure can NOT be controlled manually, THEN refers to AP-Irma1 Pressurizer Pressure.

J Regulating Valves - RESTORING S/G LEVEL TO 52% IN x m the following:

0 Place affected S/G(s) MFW regulating valve in MANUAL re S/G level to 52%

,an NOT be controlled manually, THEN refer to AP-FW.l, 1N Pump Flow Or NPSH.

R. E. Ginna Nuclear Plant Page 8 of 17 Revision 00

Appendix D Required Operator Actions Form ES-D-2

-- Event No.: 4 1 Event

Description:

(- T=22) down

- Position

_ I_

SRO Provides ATC and BOP with instructions for down power.

ATC Verifies Rods in AUTO or adjusts rods in MANUAL to maintain Tavg to Tref.

BOP Reduces turbine load in Auto as follows:

0 Places Turbine EH Control in OPER PAN., IMP PRESS IN 0 Selects rate of 3%/min on thumbwheel.

0 Reduces the setter to zero.

0 Depresses the GO button.

ATC Initiates boration (-2-4 gal/% load reduction) at flowrate directed by SRO.

ATC Places PRZR backuo heaters switch to ON.

BOP Transfers 4160V Auxiliary loads from #11 Transformer.

0 Places Bus 12A - BUS 11A TIE SYNCHROSCOPE to ON.

0 Closes BUS 12A - BUS 11A TIE 4160V.

0 Places BUS 12A - BUS 11A TIE SYNCHROSCOPE to OFF.

0 Opens BUS 11A NORMAL FEED 4160V.

Places BUS 11B - BUS 128 TIE SYNCHROSCOPE to ON.

Closes BUS 11B - BUS 12B TIE 41 60V.

0 Places BUS 1l B - BUS 128 TIE SYNCHROSCOPE to OFF.

0 Opens BUS 11B NORMAL FEED 4160V.

Requlssts an A 0 reset alarms L-20 AND L-28, locally in the Relay Roorr~Addition.

ATC Monitors Tavg 545-57gQFand verifies proper operation of Rods in Auto or controls rods manually.

ATC Adjusts Boric Acid addition rate as necessary to:

Maintain control rods above insertion limits Match Tavg and Tref Compensate for Xenon End of Event - P R. E. Ginna Nuclear Plant Page 9 of 17 Revision 00

-Appendix D Requiired Operator Actions Form ES-D-2 Op-Test No,: 1 Scenario No.: 1 Event No.: 5 Event

Description:

(- T=28)

RCP B High Vibration Indications 0 AA-18, Reactor Coolant Pump Vibratilm Alert 0 AA-26, Reactor Coolant Pump Vibrati'm Danger

1B Shaft and SE mic Vibration I P

Time - Position ATC Recognizes alarms and reports to SRO.

SRO Enters AR-AA-18 and/or AR-AA-26 based on magnitude of vibration at time of entry.

ATC Performs the lollowing at the RCP VIBRATION panel:

0 Determines which pump is causing the alarm 0 Verifies the reading ATC Checks the CONTAINMENT SOUND MONITOR for abnormal noise from the affected pump ATC/BOP Checks associated pump's instrumentation for abnormal indications.

SRO Notifies the Maintenance Manager, Component Engineer and RCS System Engineer, if the vibration level continues to rise AND is evident on BOTH Pump Shaft and Motor Casing.

SRO/ATC Performs the lollowing if pump shaft vibration level rises to 20 mils or greater OR motor casing vibration rises to 5 mils or greater:

0 Trips the reactor 0 WHEN all E-0 Immediate Actions done, THEN trip the affected RCP(s)

GOto E-0,REACTOR TRIP OR SAFETY INJECTION.

End of Event R. E. Ginna Nuclear Plant Page 10 of 17 Revision 00

-Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Event

Description:

Main Steam Line Break Downstream of MSlVs which causes S/G tube leak to rise to a 400 GPM tube rupture in S/G B. MSlV B fails to close automatically or manually from the MCB, SI Pump C fails to Auto Start on SI Signal, RHR Pump A trips on auto start.

Indications:

PRZR Level lowering 0 PRZR Pressure lowering 0 RCS Tcold, Thot, Tavg lowering 0 S/G pressures lowering Steam flow noise 0 R-32 rising or in alarm Position _s__ -

ATC/BOP Recognizes indications and alarms and reports to SRO.

ATC Verifies Reactor Tripped At least one set of reactor trip breakers open Neutron flux lowering 0 MRPl indicates all rods on bottom BOP Verifies all turlsine stop valves closed BOP Verifies Buses 14, 16, 17, and 18 > 440V ATC Checks if SI has been actuated by verifying SI annunciators and SI sequencing started both trains.

SRO Enters E-0, Reactor Trip or Safety Injection and re-verifies Immediate Actions before continL ing with supplemental actions.

ATC Verifies Containment Spray not required by verifying Containment pressure e 28 psig and annunciator A-27, Containment Spray is not lit.

BOP Performs ATT-27.0, Attachment Automatic Action Verification 0 Manually starts SI Pumps C (Critical Task CT E-0-4))

0 Reports RHR Pump A tripped ATC Verifies MDAFW pump B running with flow to B S/G and running at e 230 gpm.

Verifies TDAFW Pump running by verifying MOV-3505A and MOV-3504A oDen.

ATC Verifies AFW "low to both S/Gs or manually aligns TDAFW Pump to S/G A.

R. E. Ginna Nuclear Plant Page 11 of 17 Revision 00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Event

Description:

Main Steam Line Break Downstream of MSlVs which causes S/G tube leak to rise to a 400 GPM tube rupture in S/G 6. MSlV B fails to close automatically or manually from the MCB, SI Pump C fails to Auto Start on SI Signal, RHR Pump A trips on auto start.

Indications:

0 PRZR Level lowering 0 PRZR Pressure lowering RCS Tcold, Thot, Tavg lowering S/G pressures lowering 0 Steam flow noise 0 R-32 rising or in alarm Position ATC Monitors Heat Sink 0 Verifies S/G NR levels > 7% or verifies total AFW 200 gpm Isolates AFW flow to any S/G >50% NR Controls S/G levels 7-50% NR ATC Determines TDAFW Pump should not be stopped.

ATC Verifies annurciators A-7(A-15), CCW Pump lA(1B) Return HI Temp or Low Flow are not lit.

ATC Monitors RCS Tavg Stops dumping steam (Steam Dumps or ARV)

Ensures Reheater steam supply valves closed Limits feed flow to maintain one S/G > 7% NR Close:; MSlVs (Notes MSlV B failed and reports to SRO may have been done during ATT. 27-0)

ATC Verifies both F'ORVs closed, Auxiliary Spray valve AOV-296 closed, and when RCS pressure e 2260 psig verifies both Spray Valves are closed ATC Verifies RCP Trip Criteria Verifies an RCP running 0 Verifies at least two SI Pumps running Verifies RCS pressure- maximum S/G pressure >210 psid or secures RCP 1A ~ ~ ~~ ~ ~~~ ~~

ATC Verifies S/G Dressures and determines S/G 1B is not intact.

SRO Transitions to If-2, Faulted Steam Generator Isolation BOP Attempts to manually close MSlV B.

SRO Dispatches ACI with locked valve key to locally close faulted S/G B MSlV R. E. Ginna Nuclear Plant Page 12 of 17 Revision 00

Appendix D Required Operator Actions Form ES-D-2

/ Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Event

Description:

Main Steam Line Break Downstream of MSlVj which causes S/G tube leak to rise to a 400 GPM tube rupture in S/G 6. MSlV B fails to close automatically or manually from the MCB, SI Pump C fails to Auto Start on SI Signal, RHR Pump A trips on auto start.

Indications:

0 PRZR Level lowering 0 PRZR Pressure lowering 0 RCS Tcold, Thot, Tavg lowering 0 S/G pressures lowering 0 Steam flow noise 0 R-32 rising or in alarm Checks If Any S/G Secondary Side Is Intact:

0 C h e c k pressure in S/G A - STABLE OR RISING OR 0 Checks pressure in S/G B - STABLE OR RISING Checks Faulted S/G Status:

Faulted S/G pressure - LOWERING IN AN UNCONTROLLED MANNER OR 0 Faultd S/G - COMPLETELY DEPRESSURIZED IF both SIG pressures stable or rising, THEN searches for initiating break and goes to Step E;.

0 Main steam lines 0 Main feed lines 0 S/G biowdown system 0 Sample system R. E. Ginna Nuclear Plant Page 13 of 17 Revision 00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Event

Description:

Main Steam Line Break Downstream of MSIV:; which causes S/G tube leak to rise to a 400 GPM tube rupture in S/G B. MSIV B fails to close automatically cIr manually from the MCB, SI Pump C fails to Auto Start on SI Signal, RHR Pump A trips on auto start.

Indications:

PRZR Level lowering PRZR Pressure lowering RCS Tcold, Thot, Tavg lowering 0 S/G pressures lowering Steam flow noise R-32 rising or in alarm Isolates Feed Flow To Faulted S/G.

0 Closes or verifies closed the following valves:

MDAFW pump B discharge valve, MOV-4008 MFW regulating valve and bypass valve to S/G B, HCV-476 and HCV-481 0 MFW isolation valve to S/G B, AOV-3994 B13TH MDAFW pump crosstie valves - MOV-4000A and MOV-40008 0 SAFW pump discharge valve to S/G B, MOV-9704B Pull stops faulted S/G MDAFW pump B 0 Closes TDAFW flow control valve to S/G B - AOV-4298.

Isolates Steam Flow From Faulted S/G:

Verifies faulted S/G ARV CLOSED - S/G B, AOV-3410 0 Closes faulted S/G TDAFW pump steam supply valve and place in PULL STOP S/G B, MOV-3504A 0 Verifies faulted S/G blowdown and sample valves CLOSED - S/G B, AOV-!1737 and AOV-5736 Dispatches A 0 to complete faulted S/G isolation (Refer to ATT-10.0, ATTACHMENT FAULTED S/G)

Monitors Intact S/G Levels:

Maintains total feed flow greater than 200 gpm until narrow range level greater than 7% in S/G A. Controls feed flow to maintain narrow range level i iS/G A between 17% and 50%

0 IF narrow range level in any S/G continues to rise in an uncontrolled manner THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step - .

R. E. Ginna Nuclear Plant Page 14 of 17 Revision 00

Appendix D Required Operator Actions Form ES-D-2 lp-Test No.: 1 Scenario No.: 1 Event No.: 6 Event

Description:

dain Steam Line Break Downstream of MSIV, which causes S/G tube leak to rise to a 400 GPM tube rupture n S/G B. MSIV B fails to close automatically c'r manually from the MCB, SI Pump C fails to Auto Start on SI signal, RHR Pump A trips on auto start.

ndications:

0 PRZR Level lowering 0 PRZR Pressure lowering 0 RCS Tcold, Thot, Tavg lowering 0 S/G pressures lowering 0 Steam flow noise R-32 rising or in alarm Time Position 4TC Checks Secoridary Radiation Levels - NORMAL 0 Steam line radiation monitors (R-31 and R-32) 0 Air ejector radiation monitor (R-15)

S/G b owdown radiation monitor (R-19)

Requests RP sample S/Gs for activity SRO Transitions to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

ATC Monitors RCP Trip Criteria 0 Stops RCP 1A IF AT LEAST TWO SI pumps RUNNING and RCS pressure minus maximum S/G pressure is LESS THAN 210 psid.

SRO/BOP Identifies Ruplured S/G is S/G B by:

Unexpected rise in S/G narrow range level 0 High radiation indication on main steam line B radiation monitor R-32 BOP Isolates Flow From S/G 6 (Critical Task CT E-3-A)

Adjusts ruptured S/G ARV controller to 1050 psig in AUTO and checks ruptured S/G ARV CLOSED when ruptured S/G pressure less than 1050 psig Closes TDAFW pump steam supply valve MOV-3504A and places in PULL STOP Ensures S/G B blowdown valve, AOV-5737 - CLOSED BOP Completes Ruptured S/G B Isolation: (Critical Task CT E-3-A)

Ensures MSlV B, AOV-3516 Closed Dispatches A 0 to complete ruptured S/G isolation for S/G B (Refer to ATT-16.0, ATTACHMENT RUPTURED S/G part A)

R. E. Ginna Nuclear Plant Page 15 of 17 Revision 00

Appendix D Required Operator Actions Form ES-D-2

-- Event No.: 6 Event

Description:

Main Steam Line Break Downstream of MSlVs which causes S/G tube leak to rise to a 400 GPM tube rupture in S/G 6. MSlV 6 fails to close automatically or manually from the MCB, SI Pump C fails to Auto Start on SI Signal, RHR Pump A trips on auto start.

0 PRZR Level lowering 0 PRZR Pressure lowering 0 RCS Tcold, Thot, Tavg lowering 0 S/G pressures lowering 0 Steam flow noise 0 R-32 rising or in alarm Position BOP Checks Ruptured S/G Level: (Critical Task CT E-3-A) 0 Ensures S/G B Narrow range level - GREATER THAN 7%

o IF ruptured S/G NOT faulted and Narrow Range level is c 7%,

THEN performs the following:

. Maintains feed flow to ruptured S/G until level greater than 7%

. Continues with Step 6. WHEN ruptured S/G level greater than 7%, THEN does Steps 5b through e.

0 Ensures MDAFW pump discharge valve to S/G B, MOV-4008 closed.

0 Ensures MDAFW pump B in Pull Stop 0 Ensures TDAFW pump flow control valve to S/G B, AOV-4298 closed.

Ensures MDAFW pump crosstie valves closed o MOV-4000A o MOV-40006 BOP Verifies Ruptured S/G Isolated:

0 Checks MSlV 6, AOV-3516 closed 0 Checks TDAFW pump steam supply from S/G B MOV-3504A isolated Verifies S/G B Dressure - GREATER THAN 300 PSlG BOP Establishes Condenser Steam Dump Pressure Control:

Determines Intact MSlV A is closed and adjusts S/G ARV controllers to maintain S/G A pressure in AUTO and goes to Step 8.

ATC/BOP Resets SI R. E. Ginna Nuclear Plant Page 16 of 17 Revision 00

Amendix D Reauired ODerator Actions Form ES-D-2 3p-Test No.: 1 Scenario No.: 1 Event No.: 6 Event

Description:

Vlain Steam Line Break Downstream of MSILs which causes S/G tube leak to rise to a 400 GPM tube rupture n S/G B. MSiV B fails to close automatically lor manually from the MCB, SI Pump C fails to Auto Start on SI Signal, RHR Pump A trips on auto start.

ndications:

0 PRZR Level lowering 0 PRZR Pressure lowering 0 RCS Tcold, Thot, Tavg lowering S/G pressures lowering 0 Steam flow noise 0 R-32 rising or in alarm 0 1 15 risi-Time - Position Crew Initiates RCS Cooldown:

Determines required core exit temperature for S/G B pressure 0 ManLally initiates dumping steam from intact S/G at maximum rate using S/G A ARV.

0 WHEN core exit T/Cs temperatures less than required, THEN stops RCS cooldown and stabilizes core exit T/Cs less than required tem pc?rature End of Scenario SRO Perform EmelagencyPlan Classification for final event Expected EAL.: Alert, 3.1.2, RCS Leakage > 46 gpm Start Time: -

Stop Time:

EAL:

R. E. Ginna Nuclear Plant Page 17 of 17 Revision 00

Aooendix D Scenario Outline Form ES-D-1

_ i _ _ _ _ P Facility: R. E. Ginna Scenario N I ~ . : 2 Op-Test No.: 1 Examiners: - Operators:

Initial Conditions: 1OO%, BOL Turnover: SI Pump A 00s to refurbish failed motor, S/G A LT-461 00s due to failed electronics, MDAFW Pump A 00s for impeller replacement Event Malf. Event Event No.

p _ - P No. Type* -

1 HTR02A C-BOP/SRO Heater Drain Tank Pump 1A Trips R-ATC, 2 N/A N- BOP/SRO Pomer Reduction to 70%

I-ATC/SRO, 3 PZRO4 TS-SRO Pressurizer Pressure Master Controller PC-431K output fails high C-ATC/S RO, 4 RCS02C TS-SRO RCS Leak Hot Leg B I-BOP/SRO, 5 SGNO1D TS-SRO S/G A Level LT-463 fails high RCS03C, RPSO7E, RPS07F, RPS07L, Large Break LOCA Hot Leg B, RHR Pumps A and B, fail to auto start RPS07M, M-ALL, on SI Signal, MDAFW Pump B and the TDAFW Pump fail to auto 6 RPS07N C-BOP start

• (N)orrnal, (R)eactivity, (I)nstrument, (C)ornponent, (M)ajor Revision 00 Page 1 of 20

Facilty: R. E. Ginna Scenario No.: -~ 2 Op-Test No.: 1 Scenario DescriDtion:

Shortly after the crew takes the watch, Heater Drain Tank Pump 1A trips on overload. The crew should implement AP-FW.1, Abnormal MFW Pump Flow or NPSH.

The crew should perform a down power to 70% due to the trip of Heater Drain Tank Pump 1A to ensure sufficient NPSH for the Main Feedwater Pump.

After the crew satisfies the reactivity manipulation requirements, Pressurizer Master Pressure Controller PC-431 K output fails high. This causes the PRZFl Spray Valves to open and Pressurizer heater to de-energize.

The crew should take manual control of the Spray valve controller and close the Spray Valves and implement AP-PRZR.1. The SRO should refer to TS 3.4 1 and COLR Section 2.lO.and enter TS 3.4.1 if Pressurizer Pressure drops below 2205 psig. SRO refers to TR 3.4.3 with PC-431K in Manual. PORV-431C is still OPERABLE but the ATWS mitigating system is not.

After the crew addresses the Pressurizer Pressure Controller failure and restores RCS pressure, a 20 gpm RCS leak occurs in Cold Leg 1A. The crew should implement AP-RCS.1, Reactor Coolant Leak. The SRO should review TS 3.4.1 3 and enter Condition A and Action A.l.

While implementing AP-RCS.l, LT-463 fails high forcing the S/G 1A MFW Reg Vlv controller HCV-466 to manual requiring manual control of S/G 1A level and implement AP-FW.l. The SRO should review Technical Specifications 3.3.1 and 3.3.2 and determine ihere are no actions for 2 instruments 00s on the same S/G and enters TS 3.0.3. The SRO should review TS :3.3.3 and enter Condition D and Action D.l.

After the crew restores S/G 1A level to = 52% NR, the RCS leak rises requiring a reactor trip and entry into E-0, Reactor Trip or Safety Injection. The RHR Pumps, MDAFW Pump B, and the TDAFW Pump fail to start automatically, requiring the crew to start the pumps manually when SI occurs. The crew should transition to E-l,Loss of Reactor or Secondary Coolant. The scenario may be secured when the crew reaches the decision point to transition to ES-1.3, Transfer to Cold Leg Recirculation or return to step 17 of E-1 based on RWST level.

Revision 00 Page 2 of 20

Facilty: R. E. Ginna Scenario No.: 2 Op-Test No.: 1 CRITICAL TASKS CT E-0--H Task: Manually start at least one RHR pumy) before transition out of E-0.

Cues: SI Actuated RCS press c RHR pump shutoff head No RHR pump running Indication: Manipulation of controls to start a: least one RHR pump.

Feedback: Indication that a RHR Pump(s) ar? running Breaker Status Lights 9 RHR Flow CT E-0--F Task: Establish 200 GPM of AFW flow to the S/G before transitioning out of E-0.

Cues: Indication that SI is actuated AND Indication that AFW flow rate is less than the minimum required Total AFW flow c 200 gpm 9 AFW pumps not running Indication: "A" and/or "B" MDAFW pump staited from the MCB Feedback: Indication of AFW flow > 200 gprri S/G levels increasing Revision 00 Page 3 of 20

Facilty: R. E. Ginna Scenario No.: -~2 Op-Test No.: 1 Scenario Timeline:

Event Time Delay Ramp Number (Min) Key Event HH:MM:SS HH:MM:SS Final N/A LOAD SGNO1B NIA oo:oo:oo 00:00:00 0

- S/G LEVEL CHANNEL FAILURE: LT-461(I) 1 2 HTR02A 1 oo:oo:oo oo:oo:oo 1 HEATER DRAIN TANK 1A TRIP 2 ***(- 8) N/A N!A N/A N/A N/A POWER REDUCTION TO 70%

3 ***(- 17) PZR04 3 oo:oo:oo oo:oo:oo 100 PRESSURIZER MASTER PRESSURE CONTROLLER FAILURE 4 ***(- 27) RCS02C 5 oo:oo:oo oo:oo:oo 20 RCS LEAK INTO CNMT: LOOP f3 HOT LEG (UNREC) 5 ***(- 34) SGNO1D 7 oo:oo:oo 00:03:00 70 S/G LEVEL CHANNEL FAILURE: LT-463 (IV) 6 ***(- 40) RCS03C 9 00:00:00 0O:Ol :oo 1 RCS DBA BREAK IN CNMT : LOOP B HOT LEG (UNREC) 6 LOAD RPS07E N/A oo:oo:oo oo:oo:oo 1 AUTO FAIL: A RHR PUMP 6 LOAD RPS07F N/A oo:oo:oo oo:oo:oo 1 AUTO FAIL: B RHR PUMP 6 AT LOAD RPSO7L NJA oo:oo:oo oo:oo:oo 1 AUTO FAIL: B MDAFW PUMP 6 AT LOAD RPS07M N/A oo:oo:oo oo:oo:oo 1

- AUTO FAIL: TDAFW STM SUP FAOV-3504A 6 AT LOAD RPS07N N/A oo:oo:oo oo:oo:oo 1 AUTO FAIL: TDAFW STM SUP FAOV-3505A

• • • Events initiated on cue from NRC Lead Examiner Estimated Time: 65 Minutes Revision 00 Page 4 of 20

Appendix D Requiired Operator Actions Form ES-D-2 3p-Test No.: 1 Scenario No.: 2 Event No.: 1 Event

Description:

(T=2 minutes) ieater Drain Tank Pump 1A Trips ndications:

G-8, 4 KV Breaker Overload G-25, Motor Off Ctr Sect Pumps Except Main & Aux Feed Pumps H-14, Condensate Hdr Lo Pressure 245 psi H-17, Feed Pump Net Positive Suctioi Head H-29, Fdwtr Htr and Drain Tank Level Hi-Lo or Presep Tk Hi Level H-30, Condensate Bypass Valve Open Condensate B Auto Starts (Green Flag on pump C/S w/Red Run indication)

Condensate Bypass Valve AOV-3959 indicates open Feed Pump 1A and 1B Suction Pressure indicators lower and then recover after Condensate pump starts and Condensate Bypass Valve opens

> 100%

Recognizes indications and alarms and reports to SRO BOP/ATC Determines reactor power > 100%

SRO SRO orders BOP to lower turbine load to reduce reactor Dower c 100°/o BOP Commences turbine load reduction SRO Enters AP-FVV.1, Abnormal MFW Pump Flow or NPSH BOP Checks MFW Requirements 0 Verifies Power =. 50%

Verifies two MFW Pumps Running BOP Check S/G Status

+

Checks MFW Flow greater than Steam Flow Checks levels in both S/Gs stabilizing or trending back to 52% NR Verifies at least two Condensate Pumps running Verifies and reports only one Heater Drain Pump running.

SRO Determines a power reduction to 70% is required (May determine to use AP-TURB.5, Rapid Load Reduction.

End of Event

_=_ P P -

R. E. Ginna Nuclear Plant Page 5 of 20 Revision 00

-Appendix D Required Operator Actions Form ES-D-2 Event N0.: 2 Event

Description:

(- T=8 minutes) eduction to 70%

Position I Amlicants Actions or Behavior SRO Provides ATC and BOP with instructions for down power.

ATC Verifies Rods in AUTO or adjusts rods in MANUAL to maintain Tavg to Tref.

BOP Reduces turbine load in Auto as follows:

0 Places Turbine EH Control in OPER PAN., IMP PRESS IN I 0 Selects rate on thumbwheel per SRO instructions.

I 0 0

Reduces the load setter to 70% load value.

Depresses the GO button.

ATC Initiates boration per SRO instructions.

ATCBOP Adjusts Turbine load rate, Boric Acid flowrate, Rods to maintain Tavg to Tref.

BOP I Verifies Turbine Load reduction stops when Load = Setter I

R. E. Ginna Nuclear Plant Page 6 of 20 Revision 00

Amendix D ReauiiLedODerator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Event

Description:

(- T=17 minutes)

Pressurizer Pressure Master Controller PC-43 1 K output fails high 0 Maximum output on PRZR PRES COVTROLLER 431 K 0 Maximum output on PRESSURIZER !SPRAY CONTROLLER PCV-431A and PCV-431B 0 Heater output at minimum 0 Both Spray Valves PCV-431A and B indicate open dications and alarms and reports to SRO.

control of Pressurizer Pressure Control in one of the following Places PRZR PRES CONTROLLER 431 K in manual and lowers output using the Manual potentiometer to close PCV-431A and PCV-431 B (5: 50%).

Places both PRESSURIZER SPRAY CONTROLLER PCV-431A and the Manual potentiometer on each controller.

ZR.1, Abnormal Pressurizer Pressure Checks PRZFl Pressure Channels ts PRZR 1A-1 through 4, (PI-429, PI-430, PI-431, and PI-449) ading approximately equal and trending down or Power Stable Reports that POWER RANGE 1 through 4 FLUX (NI-41B through NI-I PROPORTIONAL HEATERS Breaker closed (Red Light On)

PRZR BACKUP HEATERS by taking C/S to ON.

I PRESS CONTROLLER 431 K demand is less than 50% and d to restore PRZR pressure to 2235 psig.

R. E. Ginna Nuclear Plant Page 7 of 20 Revision 00

Appendix D Requiired Operator Actions Form ES-D-2 Event No.: 4 Event

Description:

(- T=27 minutes)

RCS Leak Cold Leg A Slowly lowering PRZR level 0 Slowly lowering RCS Pressure 0 Annunciator F-14, Charging Pump Speed 0 Rising indications or alarms on R-1OA, R-11, or R-12

)CS alarm, R-11 Rate of Change - -

a Time Position ATC qecognizes irdications and alarms and reports to SRO.

SRO Enters AP-RCS.1, Reactor Coolant Leak ATC Monitors PRZR Level and starts additional charging pumps, or raises charging pump speed as necessary to stabilize PRZR level.

ATC Check VCT Makeup System 0 Monitlxs VCT Level on LI-112 0 Ensures RMW Mode Selector in AUTO 0 Verifies RMW Armed red light lit 0 Verifies Makeup occurring between 20% and 30% on LI-112 ATC Determines Leakage is in Containment By:

0 Rising readings on any of the following Rad Monitors: R-2, R-7, R-10A, 13-11, R-12 0 CNMT Sump A pump run frequency rises SRO Directs RP to sample Containment for entry and informs A 0 to be prepared to enter CNMT t13 search for leaks SRO Continues to eliminate other sources of leakage by dispatching A 0 to AUX BLDG for CVCS leaks with RP support.

ATC Checks CCW System for leaks by:

0 Monitors CCW Surge Tank Level on LI-618 - - 50% and stable 0 Monitor CCW Radiation Monitor R-17 reading not rising and not in alarm ATC Checks Letdown indications Normal:

0 Letdown Line Flow on LI-134 - 40 gpm Low Press Ltdn Pressure on PI-135 or PCV-135 250 psig 0 -

Low Press Ltdn Pressure PCV-135 35% open (- 65% controller output)

R. E. Ginna Nuclear Plant Page 8 of 20 Revision 00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event

Description:

(- T=27 minutes)

RCS Leak Cold Leg A Indications:

0 Slowly lowering PRZR level 0 Slowly lowering RCS Pressure 0 Annunciator F-14, Charging Pump Splsei 0 Rising indications or alarms on R-1OA, R-11, or R-12 0 )CS alarm, R-11 R i P

Time__li - Position 1 ATC/BOP Checks Charging indications Normal 0 Seal Injection Flows > 6 gpm and stable on FI 115A and FI-ll6A Labyrinth Seal D/Ps PI-131 and PI-124 > 15 inches and approximately equal Charging Pump Discharge pressure PI-128 7 RCS pressure PI-429, PI-430, PI-431, PI-449 ATC Checks AUX E3LDG rad levels Normal by verifying no rise indication or alarms on R-4. R-9. R-IOB. R-13. or R-14 ATC/BOP Checks PRT indications Normal 0 PRT Level 61%-84% on Ll-442 0 PRT Pressure -1.5 psig and stable on PI-440A and PI-440B PRT Temperature at CNMT Ambient Temperature and Stable on TI-439 SROIATC Check S/Gs for leakage 0 Air Ejector rad monitors no rise or alarms on R-15, R-47, and R-48 0 S/G Blowdown rad monitor R no rise or alarms 0 Stear line rad monitors R-31 and R-32 no rise or alarms 0 No rise in S/G samDle activities ATC Checks SI Accumulator levels stable (not rising) on Ll-938 and Ll-934 ATC Checks RCP Seal Leakoff flows stable and within normal operating range of Fig-4.0, Figure RCP Seal Leakoff on F-175 to F-178 (Seal Leakoff Recorders)

Crew Checks leak is not into RCDT by checking PPCS PID L1003 and RCS Daily Leakage Log ATC Verifies Normal Letdown in service ATC Verifies RCS pressure and PRZR level are trending back to normal steady state values 2235 psig and 56%

R. E. Ginna Nuclear Plant Page 9 of 20 Revision 00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 cenario No.: 2 Event No. : 4 Event

Description:

(- T=27 minutes)

RCS Leak Cold Leg A 0 Slowly lowering PRZR level Slowly lowering RCS Pressure 0 Annunciator F-14, Charging Pump Speed 0 Rising indications or alarms on R-lOA, R-11, or R-12 PPCS alarm, R-11 R i 1 ATC Verifies Control Systems in AUTO Determines Pressurizer Press Controller 431 K needs to stay in MANUAL Pressurizer Spray Valve Controllers PCV-431A and PCV-431B in AUTO (may be in manual from 431K failure)

PRZR Proportional Heater Breaker Closed 0 PRZR Backup Heater C/S in AUTO (may be ON after 431 K failure) 0 One Charging Pump Controller in AUTO B Annunciators - Refers to AR procedures 12sleak rate and determines TS 3.4.13 is not being met enters i d Action A.l.

R. E. Ginna Nuclear Plant Page 10 of 20 Revision 00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5 Event

Description:

(- T=34 minutes)

S/G A Level LT-463 fails high 0 Ll-463 rising G A FRV controller I in manual Position BOP Recognizes indications and alarms and reports to SRO.

BOP Takes action to stabilize S/G A level by adjusting S/G A FRV controller in manual to resiore SJG Level to 52% on Ll-462.

SRO Enters ER-INST.1 and goes to step 4.8 SRO Implements ATachment Steam Gen A-3 Level Ll-463 Yellow Channel BOP/ATC In the (YELLCW) Y-2 PROTECTION CHANNEL 4 rack Place:; 463 LOOP A-3 LO LO LEVEL TRIP Switch in DEFEAT(UP) 0 Verifies 463 LOOP A-3 LO LO LEVEL TRIP Bistable Proving Light ON 0 Place:; HIGH LEVEL OVER RIDE Switch in DEFEAT(UP) 0 Verifies 463 LOOP A-3 HIGH LEVEL OVER RIDE Bistable Proving Liaht OFF BOP/ATC Verifies the following bistable status lights and annunciators are lit.

LC463C Lo Lo Level LC463D Hi Level Is01 0 G-28, S/G A LO-LO Level Channel Alert 17%

G-4, S/G A HI Level Channel Alert 85%

BOP/ATC Deletes the point from the PPCS, by performing the following:

On the Sub/Delete/Restore display Seleci Point ID LO463 Turn OFF scan processing Selecl Change SRO Checks ITS Reviews Technical Specifications 3.3.1 and 3.3.2 and determines there are no actions for 2 instruments inoperable on the same S/G and enters TS 3.0.3.

The SRO should review TS 3.3.3 and enter Condition D and Action D.l.

End of Event A. E. Ginna Nuclear Plant Page 11 of 20 Revision 00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event

Description:

(- T=40 minutes)

Large Break LOCA Cold Leg A Indications:

0 PRZR and RCS Pressures dropping Iqapidly 0 PRZR level dropping rapidly 0 Reactor trip on Low PRZR Pressure 0 Low RCS Pressure SI 0 R-11 rising and in alarm 0 R-29 and R-30, Containment Hi Range Rad Monitors rising 0 Containment Pressure rising rapidly

'GPressures relativl I stable

- Position -

ATC/BOP Recognizes alarms and indications and reports to SRO ATC Verifies Reactor Tripped 0 One set of reactor trip breakers open Neutron flux lowering 0 MRPl indicates all rods on bottom BOP Verifies all turbine stop valves closed BOP Verifies Buses 14, 16, 17, and 18 > 440V ATC Checks if SI has been actuated by verifying SI annunciators and SI sequencing slarted both trains.

SRO Enters E-0, Rsactor Trip or Safety Injection and re-verifies Immediate Actions before continuing with supplemental actions.

ATC Verifies Containment Spray required by verifying Containment pressure > 28 psig and annunciator A-27, Containment Spray is lit and verifies Containment Spray is initialed.

BOP Perform ATT-27.0, Attachment Automatic Action Verification Manually starts RHR Pumps A and B (Critical Task CT E-0-H) 0 Manually starts TDAFW Pump and MDAFW Pump B (Critical Task CT E-O-F)

ATC Verifies MDAF'W pump B running with flow to B S/G at < 230 gpm. Verifies TDAFW Pump running by verifying MOV-3505A and MOV-3504A open.

ATC Verifies AFW flow to both S/Gs or manually aligns TDAFW Pump to S/G A.

R. E. Ginna Nuclear Plant Page 12 of 20 Revision 00

Amendix D Reauiired h e r a t o r Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event

Description:

(- T=40 minutes)

Large Break LOCA Cold Leg A Indications:

0 PRZR and RCS Pressures dropping 3apidly 0 PRZR level dropping rapidly 0 Reactor trip on Low PRZR Pressure Low RCS Pressure SI 0 R-11 rising and in alarm 0 R-29 and R-30, Containment Hi Range Rad Monitors rising 0 Containment Pressure rising rapidly G Pressures relativl Position Amlicants Actions or Behavior ATC Monitors Heat Sink 0 Verifies S/G NR levels > 25% or verifies total AFW 200 gpm 0 Isolates AFW flow to any S/G > 50% NR Controls S/G levels 25-50% NR SRO Determines TDAFW Pump should not be stopped.

ATC Verifies annuriciators A-7(A-15), CCW Pump lA(1B) Return HI Temp or Low Flow are not It.

ATC Monitors RCS Tavg 0 Stops dumping steam (Steam Dumps or ARVs)

Ensures Reheater steam supply valves closed Maintains total Feed flow at 200-230 gpm until one S/G is >25% NR Limits feed flow to maintain one S/G > 25% NR 0 Closes MSlVs if cooldown continues ATC Verifies both FORVs closed, Auxiliary Spray valve AOV-296 closed, and when RCS pressure e 2260 psig both Spray Valves are closed ATC Verifies RCP Trip Criteria Verifies both RCPs running 0 Verifies at least two SI Pimps running Verifies RCS pressure- maximum S/G pressure <240 psid and secures RCP 1A and RCP 16 by taking C/S to STOP BOP Determines both S/Gs are intact Both S/G Pressures stable or rising and > 110 psig R. E. Ginna Nuclear Plant Page 13 of 20 Revision 00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event

Description:

(- T=40 minutes)

Large Break LOCA Cold Leg A Indications:

0 PRZR and RCS Pressures dropping Rapidly 0 PRZR level dropping rapidly 0 Reactor trip on Low PRZR Pressure 0 Low RCS Pressure SI 0 R-11 rising and in alarm 0 R-29 and R-30, Containment Hi Range Rad Monitors rising 1 0 Containment Pressure rising rapidly G Pressures relativ stable Position ATC Checks that S/G Tubes Are Intact:

0 Verifies air ejector radiation monitors (R-15, R-47, or R-48) are not rising or in alarm 0 Verifies S/G blowdown radiation monitor (R-19) are not rising or in alarm 0 Verifies steam line radiation monitors (R-31 and R-32) are not rising or in alatm ATC Checks If RCS Is Intact:

0 Reports CNMT area radiation monitors R-2, R-7, R-29, R-30 are rising and in alarm Reports CNMT pressure is rising and > 0.5 PSlG 0 Reports CNMT sump 6 level is rising and > 8 inches Reports CNMT sump A level rising Reports Annunciator C-19, CONTAINMENTSUMP A HI LEVEL is tit SRO Transitions to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

SRO Instructs Clem review foldout page criteria and to monitor Critical Safety Functions. Review Red Path Summaries, determines RCS Integrity red path criteria is met and transitions to FR-P.l, Response To Imminent Pressurized Thermal Shocc Condition.

ATC Verifies RCS pressure is < 465 psig and RHR flow is > 475 gpm SRO Returns to ste:, in effect in E-1, Loss Of Reactor Or Secondary Coolant.

SRO Determines RCPs secured and goes to Step 2 SRO Re-verifies S/Gs are intact and goes to step 3 R. E. Ginna Nuclear Plant Page 14 of 20 Revision 00

Appendix D Requii?edOperator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event

Description:

(- T=40 minutes)

Large Break LOCA Cold Leg A Indications:

0 PRZR and RCS Pressures dropping Flapidly 0 PRZR level dropping rapidly Reactor trip on Low PRZR Pressure Low RCS Pressure SI 0 R-11 rising and in alarm 0 R-29 and R-30, Containment Hi Range Rad Monitors rising Containment Pressure rising rapidly G Pressures relatiw I stable Position BOP Monitors S/G and B levels:

Maintains total AFW flow greater that 200 gpm until at one S/G level is

> 25OL, NR 0 Controls AFW flow to maintain S/G A and B NR levels between 25%-

50%

SRO/ATC Monitors Secondary Rad Levels are not rising on steam line rad monitors R-31 and R-32 and requests RP sample S/Gs for activity ATC/BOP Verifies PORV block valves are energized, both PORVs are closed and at least one P O W block valve is open ATC Resets SI by depressing SI Reset Pushbutton ATC Resets CI by depressing CI Reset Pushbutton and verifies A-26, CNMT Isolation is not lit BOP Verifies at lea:st 2 SW pumps are running SRO Dispatches A 0 to establish normal shutdown alignment per ATT-17.0, ATTACHMENT SD-1 BOP Establishes IP, to CNMT 0 Verifies Busses 13 and 15 powered through normal feeder breakers from offsite. Should also check bus voltage > 440 V.

0 Verifies Turbine Building SW isolation valves MOV-4613/MOV-4670 and FVlOV-4614/MOV-4664are open Verifies adequate air compressors are operating or starts additional air compfessors 0 Verifies IA pressure > 60 psig and stable or rising Resets both train XY relays for AOV-5392 and verifies AOV-5392 open BOP Checks Bus 14 and 16 normal feeder breakers closed R. E. Ginna Nuclear Plant Page 15 of 20 Revision 00

Appendix D Requiired Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event

Description:

(- T=40 minutes)

Large Break LOCA Cold Leg A PRZR and RCS Pressures dropping \Rapidly 0 PRZR level dropping rapidly 0 Reactor trip on Low PRZR Pressure 0 Low RCS Pressure SI 0 R-11 rising and in alarm 0 R-29 and R-30, Containment Hi Range Rad Monitors rising 0 Checl<sCCW Flow has not been lost to either RCP thermal barrier (MOL'-817, AOV-814, AOV-815, AOV-754A, and AOV-754B open with a CC\N Pump running) and verifies #1 seal and verifies RCP 1A and 1B #1 Seal Outlet Temperature (TI-181 and TI-182) are 5 23!j8F Ensures HCV-142, Charging Flow to Regen HX is open, controller demand is 0%

0 Verifies Charging Pump suction is aligned to the RWST o Verifies LCV-1128, Emerg Makeup RWST to Charging Pump is open and LCV-1128, VCT Outlet Vlv is closed I

ecures one 1 BOP I Checks if Emergency D/Gs should be stopped 1

Verifks EDG A and B output breakers open Verifies Bus 14, Bus 16, Bus 17, and Bus 18 Voltages > 440 V and ual bus normal feeder breakers are closed R. E. Ginna Nuclear Plant Page 16 of 20 Revision 00

Appendix D Required Operator Actions Form ES-D-2 3p-Test No.: 1 Scenario No.: 2 Event No.: 6 Event

Description:

(- T=40 minutes)

-arge Break LOCA Cold Leg A ndications:

0 PRZR and RCS Pressures dropping Rapidly 0 PRZR level dropping rapidly 0 Reactor trip on Low PRZR Pressure 0 Low RCS Pressure SI R-11 rising and in alarm 0 R-29 and R-30, Containment Hi Rangle Rad Monitors rising 0 Containment Pressure rising rapidly

~~

0 S/G Pressures relativg Time I Position 1 BOP Stops D/G A using ATT 8.1, Attachment D/G Stop Verify D/G A Bus 14 supply breaker is OPEN.

Verify D/G A Bus 18 supply breaker is OPEN.

Using D/G A GOVERNOR, adjust D/G A speed to return frequency to 60 Hz.

Using D/G A AUTO VOLTAGE CONTROL rheostat adjust D/G A voltage to 480 volts.

Place D/G A CONTROL switch to STOP AND immediately depress D/G P, VOLTAGE SHUTDOWN button until voltage decays to zero.

After -60 seconds, perform the following:

o Depress D/G A FIELD RESET o Depress D/G A RESET o Verify D/G A AIR START SOLENOID lights - LIT o Verify D/G A START RELAY lights - LIT R. E. Ginna Nuclear Plant Page 17 of 20 Revision 00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event

Description:

(- T=40 minutes)

Large Break LOCA Cold Leg A Indications:

PRZR and RCS Pressures dropping F3apidly PRZR level dropping rapidly Reactor trip on Low PRZR Pressure Low RCS Pressure SI R-11 rising and in alarm R-29 and R-30, Containment Hi Range Rad Monitors rising Containment Pressure rising rapidly I stable Stops D/G B using ATT 8.1, Attachment D/G Stop 0 Verify D/G B Bus 16 supply breaker is OPEN.

0 Verify D/G B Bus 17 supply breaker is OPEN.

0 Using D/G B GOVERNOR, adjust D/G B speed to return frequency to 60 Hz.

Using D/G B AUTO VOLTAGE CONTROL rheostat adjust D/G B voltage to 480 volts.

0 Place D/G B CONTROL switch to STOP AND immediately depress D/G El VOLTAGE SHUTDOWN button until voltage decays to zero.

After -60 seconds, perform the following:

o Depress D/G B FIELD RESET o Depress D/G B RESET o Verify D/G B AIR START SOLENOID lights - LIT o Verify D/G B START RELAY lights - LIT ATC/BOP Verifies CNMT Sump Recirculation Capability:

0 Checks RHR and Support systems:

o At least one recirculation flow path, including required power supplies, from Sump B and back to RCS available per ATT-14.5, ATTACHMENT RHR SYSTEM o At least one SW pump available.

o At least one CCW pump available.

o At least one CCW Hx available.

Checks at least 2 SW pumps available Dispaches A 0 to check AUX BLDG sub-basement for RHR system leakage (AUX BLDG sub-basement key may be required)

R. E. Ginna Nuclear Plant Page 18 of 20 Revision 00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event

Description:

(- T=40 minutes)

Large Break LOCA Cold Leg A Indications:

0 PRZR and RCS Pressures dropping Iqapidly 0 PRZR level dropping rapidly 0 Reactor trip on Low PRZR Pressure 0 Low RCS Pressure SI 0 R-11 rising and in alarm 0 R-29 and R-30, Containment Hi Rancie Rad Monitors rising 0 Containment Pressure rising rapidly

-stable f

Evaluates Plant Status:

0 Checks auxiliary building radiation - NORMAL o Plant vent iodine (R-1OB) o Plant vent particulate (R-13) o Plant vent gas (R-14) o CCW liquid monitor (R-17) o LTDN line monitor (R-9) o CHG pump room (R-4) 0 WHEN TSC is manned, THEN request evaluation of sampling requirements.

o RCS boron o RCS activity o CNMT hydrogen o CNMT sump boron o CNMTSumppH 0 Verifies adequate Rx head cooling:

o Verifies at least one control rod shroud fan - RUNNING o Verifies one Rx compartment cooling fan - RUNNING SRO Verifies that RCS cooldown is not required RCS Pressure 5 465 psig 0 RHR Pump flow > 475 gpm R. E. Ginna Nuclear Plant Page 19 of 20 Revision 00

Amendix D Reauired ODerator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: i! Event No.: 6 Event

Description:

(- T=40 minutes)

Large Break LOCA Cold Leg A Indications:

0 PRZR and RCS Pressures dropping Rapidly 0 PRZR level dropping rapidly 0 Reactor trip on Low PRZR Pressure 0 Low RCS Pressure SI 0 R-11 rising and in alarm R-29 and R-30, Containment Hi Range Rad Monitors rising Containment Pressure rising rapidly G Pressures relativl

- PositionP BOP Establishes Adequate SW Flow Verififesat least 2 SW pumps running 0 Verifies MOV-4615/MOV-4734 Open 0 Verifies MOV-4616/MOV-4735 open 0 Verifies 5000-6000 gpm SW flow equally divided between CCW HX A and E; or Dispatches SO to adjust flow to required value ATC Establishes flow to RHR HXs Starts Backup CCW Pump Opens CCW Valves to RHR HX A and B (MOV-738A and B)

SRO Checks If Transfer To Cold Leg Recirculation Is Required:

If RWST level > 28% returns to Step 17 If RWST level c 28%, transitions to ES-1.3, TRANSFER TO COLD LEG f3ECIRCULATION, Step 1 End of Scenai-io SRO Perform Emergency Plan Classification for final event Expected EAL.: Site Area Emergency, 3.1.3, RVLIS can not be maintained c 77% with ncl RCPs running Start Time: -

StopTime: -

R. E. Ginna Nuclear Plant Page 20 of 20 Revision 00

Appendix D Scenario Outline Form ES-D-1 1 Facility: R. E. Ginna Scenario No.: 3 Op-Test No.: 1 I Examiners: - Operators:

Initial Conditions: 70%, BOL Turnover: SI Pump A 00s to refurbish failed motor, S/G A LT-461 00s due to failed electronics P

Event Malf. Event Event No. Type* Description R-ATC, N/A N-BOP/SRO Power Ascension RCSl 1C, I-ALL, ROD12 TS-SRO Loop A TcoldTE-401B Fails Low, Rod Block failed OVR-MISOGB, OVR-MISOGD, C-SRO, A-EDS16 TS-SRO Containment Recirculation Fan Cooler A Trips CVC 1OA I-ATC/SRO VCT Level Transmitter LT-112 Fails High Feedwater Control Valve B, FCV-476, Auto Controller Fails FDW07C I-BOP/SRO High, w/Manual Control available STM03, STM05A, STM05B, Main Steam line break downstream of MSIVs, both MSlVs fail to SIS02A, M-ALL, I- close automatically or from the MCB, SI fails to actuate when SISO2B ATC setpoint reached Revision 00 Page 1 of 16

Facilty: R. E. Ginna Scenario No.: 3 Op-Test No.: 1 Scenario

Description:

After the crew takes the watch they will initiate a power ascension to 100% power using 0-5.2, Load Ascension.

When the crew has met reactivity manipulatioi requirements, or at the lead examiners discretion, Loop A Tcold TE-401B Fails Low with Rod Block failed. The crew should take manual control of RODS, stabilize the plant, and implement AP-RCC.l, Continuous Rod Withdrawal/lnsertion and ER-INST.1, Reactor Protection Bistable Defeat after Instrumentation Loop Failure. The SRO should apply TS 3.3.1 Condition D, Action D.l and 3.3.2 Condition F, Action F.l.

After the affected bistables have been tripped, Containment Recirc Fan A will trip. The crew should start the standby Containment Recirc Fan. The SRO should apply TS 3.6.6 Condition D, Action D.l.

After addressing the Containment Recirc Fan failure, LT-112, VCT Level instrument will fail. The crew should realign LCV-112A to the VCT and refer to ERXVCS.1, Reactor Makeup Control Malfunction for guidance on manual makeup.

After the VCT level failure has been addressed, Feedwater Control Valve B, FCV-476, controller fails high The crew should take manual control of FCV-476 and restore S/G B level to 52% NR. The crew should implement AP-FW.1, Abnormal MFW Pump Flow or NPSH.

After the crew restores S/G B level, a Main Steam Line Break occurs downstream of the MSIVs. SI fails to actuate automatically and the MSlVs can not lbe closed from the control room or locally. The crew should manually initiate SI, attempt to close the MSIVs and implement the following procedures:

E-0, Reactor Trip or Safety Injection, E-2, Faulted Steam Generator Isolation, ECA-2.1, Uncontrolled Depressurization of Both Steam Generators and FR-P.l, Response to Imminent Pressurized Thermal Shock Condition The scenario will end after the crew has taken action to minimize the RCS cooldown and stops SI and RHR pumps.

Revision 00 Page 2 of 16

Facilty: R. E. Ginna Scenario No.: 3 Op-Test No.: 1 CRITICAL TASKS CT E-0--D Task: Manually initiate at least one train of SI before transition to E-1 Cues: RCS pressure c SI setpoint or CNMT pressure > SI setpoint and SI component failed to start Indication: Manipulation of control to activate,at least one train of SI Feedback: SI components start, SI flow delivery to RCS CT FR-P.1-B Task: Control the AFW flow rate in order to minimize RCS cooldown rate before an extreme (red path) challenge develops to the Integrity CSF.

Cues: RCS cold leg cooldown rate > 100°F in last 60 minutes.

and Cold leg temperature on either cold leg is c 285°F and AFW flow rate to faulted S/G is > 50 cipm Indication: Manipulation of control to throttle AFW flow to both faulted S/G to 50 gpm (within the ability to control the AFW control valves)

Feedback: RCS cooldown slow and eventually stops.

CT FR-P.1--A Task: Terminate SI flow so that if the challenge to integrity CSF is:

0 Severe, an extreme challenge is prevented 0 Extreme, SI is terminated by the end of the scenario.

Cues: Indication of a red or orange challenge to the integrity CSFST and Indication that SI termination criteria a.re met and AFW flow rate to faulted S/G is > 50 gpm Indication: Manipulation of control to terminate SI flow (SI and RHR pumps secured)

Feedback: SI and RHR flow rate zero.

Revision 00 Page 3 of 16

I Facilty: R. E. Ginna Scenariio No.: 3 Op-Test No.: 1 Scenario Timeline:

Event Time Delay Ramp

- Number (Min) Key Event HH:MM:SS HH:MM:SS Final 1 0 NIA MIA oo:oo:oo oo:oo:oo NIA Power Ascension 2 -

• • • ( 15) RCSl 1C 1 oo:oo:oo oo:oo:oo 0 RTD Failure: LP A Cold TE-401I3 (TT-401)I AUTO 2 At Load ROD12 NIA oo:oo:oo oo:oo:oo ONLY (0)

Rod Stop Failure 3 ***(- 22) OVR-MISO6D 3 oo:oo:oo 0O:OO:OO True (NULL)

CP-HS-CR1A Stop Signal Containment Recirculation Fan No. 1A 3 OVR-MISO6B 3 oo:oo:oo oo:oo:oo ON CP-HS-CR1A White Lamp CONTAINMENT RECIRCULATION FAN NO 1A 3 A-EDSl6 3 oo:oo:oo oo:oo:oo ON (1)

J-9: Safeguard Breaker Trip 4 ***( -27) CVC 1OA 5 oo:oo:oo 00:00:30 100 VCT Level Transmitter Failure: LT-112 5 ***(-32) FDW07C 7 oo:oo:oo oo:oo:oo 101 6 FRV FCV-476 - Manual Available 6 ***( -37) STM03 9 oo:oo:oo 0O:Ol :oo 4000000 Steamline Break Outside CNMT Downstream of MSlVs 6 At Load STM05A NIA oo:oo:oo oo:oo:oo 100 Main Steam Isolation Valve Failure: VLV 3517 6 At Load STM05B NIA oo:oo:oo oo:oo:oo 100 Main Steam Isolation Valve Failure: VLV 3516 MANUAL 6 At Load SIS02A NIA oo:oo:oo oo:oo:oo AVAIL (0)

SIS Train A Failure to Actuate MANUAL 6 At Load SIS02B NIA oo:oo:oo oo:oo:oo AVAIL (0)

- SIS Train B Failure to Actuate NIA At Load SGNOl B NIA oo:oo:oo oo:oo:oo 0

- SIG Level Channel Failure: LT-461(1)

• • • Events initiated on cue from NRC Lead Examiner Estimated Time: 65 Minutes Revision 00 Page 4 of 16

Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 1 Event

Description:

(T=O min)

Power Ascension Provides instriictions to ATC and BOP to continue raising power.

Initiates Dilution per SRO instructions using 0-3.1 BOP Raises turbine load in Auto as follows:

0 Place:; Turbine EH Control in OPER PAN., IMP PRESS IN 0 Selec:s rate on thumbwheel per SRO instructions.

0 Raises the load setter SRO instructions.

0 Depresses the GO button.

Directs the BOP to Start Condensate Booster Pumps.

Adjusts TRIM VLV CONTROL, AOV 9508D AOV-9508G, controller output in AUTO UNTIL the first Trim Valve starts to open.

I Places HOTNELL L.EVEL LC-107, Controller in the MAN position Places the standby Condensate Pump control switch in the PULL STOP position.

Places one CONDENSATE BOOSTER PUMP switch to the RUN position and observes CONDENSATE BOOSTER PUMP selected to RUN starts.

Raises TRIM VLV CONTROL, AOV 9508D AOV-9508G controller setpoint to approximately 375 psig.

BOP Places a second CONDENSATE BOOSTER PUMP switch to the RUN position WHEN CONDENSATE TRIM CONTROL AOV, valve 95086, is less than 20%

OPEN.

Places the thir'd CONDENSATE BOOSTER PUMP switch to the AUTO Dosition.

Adjusts TRIM VLV CONTROL, AOV 9508D AOV-9508G, as necessary during power ascension to maximize the MFWP available NPSH.

Monitors PPCS Point NPAVMFPA and NPAVMFPB Places HOTN ELL LEVEL, LC-107, controller in AUTO with controller setpoint at amroximatelv 24 inches.

~

I BOP BOP/ATC Places the standby Condensate Pump control switch in AUTO.

Adjusts dilution flow rate and/ or Turbine Load rate as necessary to maintain Tavg at Tref.

I End of Event R. E. Ginna Nuclear Plant Page 5 of 16 Revision 00

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

__I - I _ _

Op-Test No.: 1 Scenario No.: 3 Event No.: 2 Event

Description:

(- T=15 min)

Loop A TcoldTE-401B Fails Low, Rod Block failed Indications:

F-4, PRESSURIZER LEVEL DEVIAT ON -5 NORMAL +5 F-7, RCS LOOP A LO TAVG F-14, CHARGING PUMP SPEED F-15, RCS TAVG DEV 4°F F-16, TAVG-TREF DEVIATION +/- 5°F F-24, RCS AVG AT DEVIATION 3°F 0 LOOP 1A-1 DTEMP, TI-4058 reads significantly higher than TI-4066, TI-4078, and TI-408B 0 LOOP A-1 TAVG, TI-401 reads significantly lower than TI-402, TI-403, and TI-404 0 Charging Pump A speed signal goes 0 minimum and charging flow lowers 0 PRZR Backup Heaters energized (Red light on) (PRZR Level setpoint lowers) dications and alarms and reports to SRO.

C.1, Continuous Rod Withdrawal/lnsertion B load - STABLE mtrol in Manual and verifies rod motion stops.

setween 547and 57g8F to Tref using Rod insertion in Manual or Boration ing Pump A Speed Controller in MANUAL and adjusts charging to stabilize PRZR level.

LCOs 3.1.5 and 3.1.6 to determine actual rod insertion limits.

at hot leg streaming does not apply.

perform Tavg 401/Delta T 405 Attachment.

ontrol selector switch in MANUAL, ing Pump speed controllers in MANUAL..

ERTION LIMIT rack, Places T/405E DELTA T DEFEAT switch to R. E. Ginna Nuclear Plant Page 6 of 16 Revision 00

-Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event N0.: 2 Event

Description:

(- T=15 min)

Loop A TcoldTE-401B Fails Low, Rod Block failed Indications:

F-4, PRESSURIZER LEVEL DEVIATION -5 NORMAL +5 F-7, RCS LOOP A LO TAVG F-14. CHARGING PUMP SPEED F-15, RCS TAVG DEV 4°F F-16, TAVG-TREF DEVIATION +/- 5'F F-24, RCS AVG AT DEVIATION 3°F 0 LOOP 1A-1 DTEMP, TI-405B reads significantly higher than TI-406B, TI-407B, and TI-408B 0 LOOP A-1 TAVG, TI-401 reads significantly lower than TI-402, TI-403, and TI-404 0 Charging Pump A speed signal goes to minimum and charging flow lowers 0 PRZR Backup Heaters energized (Red light on) (PRZR Level setpoint lowers) utward Rod Motion Position BOP In the (RED) F3-1 PROTECTION CHANNEL 1 rack 0 Places 401 LOOP A-1 HIGH T'AVG Bistable Proving Switch in DEFEAT (UP) 0 Verificts 401 LOOP A-1 HIGH T'AVG Bistable Proving Light ON 0 Places 401 LOOP A-1 LOW T'AVG Bistable Proving Switch in DEFEAT (UP) 0 Verifies 401 LOOP A-lLOW T'AVG Bistable Proving Light OFF 0 Place:; 405 LOOP A-1 OVERTEMP TRIP Bistable Proving Switch in DEFEAT (UP)

Verifies 405 LOOP A-1 OVERTEMP TRIP Bistable Proving Light OFF Place:; 405 LOOP A-1 OVERPOWER TRIP Bistable Proving Switch in DEFEAT (UP)

Verifies 405 LOOP A-1 OVERPOWER TRIP Bistable Proving Light OFF BOP/ATC Verifies proper bistable status lights and associated annunciators lit.

G-9, FICS LOOP A HI TAVG 57gQ TC40'1A Lo Tavg F-7, RCS LOOP A LO TAVG 545'F TC40!jA OPAT F-32, RCS OPAT CHANNEL ALERT TC40tjC OTAT F-23, RCS OTAT CHANNEL ALERT R. E. Ginna Nuclear Plant Page 7 of 16 Revision 00

Appendix D Required O E a t o r Actions

_ . Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 2 Event

Description:

(- T=15 min)

Loop A TcoldTE-401B Fails Low, Rod Block failed Indications:

F-4, PRESSURIZER LEVEL DEVIAT13N -5 NORMAL +5 F-7, RCS LOOP A LO TAVG F-14, CHARGING PUMP SPEED F-15, RCS TAVG DEV 4°F F-16, TAVG-TREF DEVIATION +/- 5 F-24, RCS AVG AT DEVIATION 3°F 0 LOOP 1A-1 DTEMP, TI-405B reads significantly higher than TI-406B, TI-407B, and TI-408B 0 LOOP A-1 TAVG, TI-401 reads significantly lower than TI-402, TI-403, and TI-404 Charging Pump A speed signal goes to minimum and charging flow lowers PRZR Backup Heaters energized (Red light on) (PRZR Level setpoint lowers)

- Award Rod Motion ,od Block circu Time Position BOP Deletes 401/435 from the PPCS by performing the following:

Selecis Group Update display Selecis List Server Groups 0 Selecis 401-405 from the pick list Turns OFF scan processing, then clicks the Set Scan Processing buttor 0 Answers prompts ATC Restores folloNing systems to automatic operation as necessary:

PRZR level control 0 Rod control SRO Checks the fo lowing ITS Sections for LCOs:

Secticln 3.3.1, Table 3.3.1-1, Functions 5 and 6 Secticln 3.3.2, Table 3.3.2-1, Function 4d Determines the following LCO Actions are applicable 3.3.1 Condition D Action D.l - Place associated channel in trip within 6 hrs 3.3.2, Condition F, Action F.l - Place associated channel in trip within 6 hrs End of Event R. E. Ginna Nuclear Plant Page 8 of 16 Revision 00

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

Description:

(- T=22 min)

Containment Recirculation Fan Cooler A Trips Indications:

Red status light for Containment Recii*cFan A OFF Green and White status lights for Containment Recirc Fan ON arms and indications and reports to SRO.

1-9, Safeguard Breaker Trip investigate and report findings to the Control Room.

set or reclosure of a breaker should not be attempted.

icians or Work Control Center CO 3.6.6 and determines Condition D, Action D.l should be R. E. Ginna Nuclear Plant Page 9 of 16 Revision 00

Amendix D Reauired Oberator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Event

Description:

(- T=27 min)

VCT Level Transmitter LT-112 Fails High LI-112, VCT Level indicates 100°/o VCT OR HOLDUP TK DIVERT VALVE LCV-112A indicates diverted to Holdup Tanks i s when actual level reaches 14%.

idications and alarms and reports to SRO.

ionitor LI-139 in valve alley, and report reading.

12A in the VCT position.

notify Control Room for manual makeup requirement when LI-approximately 20%.

eup as required per ER-CVCS.l R. E. Ginna Nuclear Plant Page 10 of 16 Revision 00

Amendix D Reauired ODerator Actions Form ES-D-2 Dp-Test No.: 1 Scenario No.: 3 Event No.: 5 Event

Description:

(- T=32 min)

Feedwater Control Valve B, FCV-476, Auto Controller Fails High, w/Manual Control available Indications:

0 FCV-476 Controller output at 100%

0 S/G B NR and WR Levels rising Feedwater Flow > Steam Flow 1.1, Abnormal MFW Pump Flow or NPSH.

I I BOP Checks S/G status and continues to monitor S/G B level and adjust FCV-476 to restore levctl to 52%

R. E. Ginna Nuclear Plant Page 11 of 16 Revision 00

Appendix D Required Operator Actions Form ES-D-2 3p-Test No.: 1 Scenario No.: 2 Event No.: 6 Event

Description:

(- T=37 min)

Main Steam line break downstream of MSIVs, both MSlVs fail to close automatically or from the MCB, SI fails o actuate when setpoint reached ndications:

0 Gross Generator Load lowering 0 RCS Tcold, Thot, and Tavg lowering Reactor Power rising 0 RCS and PRZR Pressure lowering 0 PRZR level lowering 0 S/G Pressures lowering 0 Steam Flow rising 0 Steam Flow Noise Recognizes indications and alarms and reports to SRO.

Verifies Reactor Tripped 0 At lezst one set of reactor trip breakers open 0 Neutron flux lowering 0 MRPl indicates all rods on bottom BOP Verifies all turbine stop valves closed BOP Verifies Buses 14, 16, 17, and 18 > 440V ATC Checks if SI Pas been actuated by verifying SI annunciators and SI sequencing slarted both trains. Determines SI is not actuated and Manually actuates SI by depressing SI Manual Pushbutton. (Critical Task CT E-0-D)

SRO Enters E-0, Rzactor Trip or Safety Injection and re-verifies Immediate Actions before continuing with supplemental actions.

ATC Verifies Contzinment Spray not required by verifying Containment pressure e 28 psig and ainunciator A-27, Containment Spray is not lit.

Perform ATT-27.0. Attachment Automatic Action Verification Verifies MDAFW pump A and 6 running with flow to S/Gs and running at < 230 gpm.

ATC Monitors Heal Sink Verifies S/G NR levels > 7% or verifies total AFW 200 gpm Isolates AFW flow to any S/G > 50% NR Controls S/G levels 7-50% NR 1 ATC Secures TDAIW Pump by placing switches in Pull Stop for TDAFW Pump steam isolation valves MOV-3504A and MOV 3505A.

R. E. Ginna Nuclear Plant Page 12 of 16 Revision 00

-Appendix D Required Operator Actions Form ES-D-2 lp-Test No.: 1 Scenario No.: 3 Event No.: 6

!vent

Description:

(- T=37 min) dain Steam line break downstream of MSlVs both MSlVs fail to close automatically or from the MCB, SI fails o actuate when setpoint reached ndications:

0 Gross Generator Load lowering 0 RCS Tcold, Thot, and Tavg lowering 0 Reactor Power rising 0 RCS and PRZR Pressure lowering 0 PRZR level lowering 0 S/G Pressures lowering 0 Steam Flow rising P

0 t eam Flow Noise Time Monitors RCS Tavg and determines RCS temperatures is lowering 0 Stops dumping steam (Steam Dumps or ARVs) 0 Ensures Reheater steam supply valves closed 0 Limits feed flow to 200-230 gpm (- 100 gpm per S/G)

Verifies an RCP running 0 Verifies at least two SI Pumps running 0 Verifies RCS pressure-maximum S/G pressure >210 psid or secures RCP 1Aand 1B ATC Verifies S/G pressures and determines neither S/G is intact.

I SRO Transitions to E-2, Faulted Steam Generator Isolation BOP Attempts to miinually close MSlV A and B.

SRO Dispatches AC) with locked valve key to locally closed faulted S/G A and B MSlVs if not done previously R. E. Ginna Nuclear Plant Page 13 of 16 Revision 00

-Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 6 Event

Description:

(- T=37 min)

Main Steam line break downstream of MSlVs both MSlVs fail to close automatically or from the MCB, SI fails to actuate when setpoint reached Indications:

0 Gross Generator Load lowering 0 RCS Tcold, Thot, and Tavg lowering 0 Reactor Power rising RCS and PRZR Pressure lowering 0 PRZR level lowering 0 S/G Pressures lowering Flow rising eam Flow Noise Position SRO/BO P Check If Any !3G Secondary Side Is Intact:

0 Check pressure in S/G A - STABLE OR RISING OR 0 Check pressure in S/G B - STABLE OR RISING IF both S/G pressures lowering in an uncontrolled manner, THEN go to ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATOFS SRO Determines Orange or Red path criteria for Integrity (PTS) are met and transitions to I-R-P.l (May occur directly from E-2)

SRO/ATC Determines RCS Pressure is > 250 psig SRO/BOP Determines cold Leg temperatures are lowering and attempts to stop RCS Cooldown Verifies ARVs AOV-3411 and AOV-3410 are closed by verifying Green status light only 0 May attempt to close MSlVs again from MCB (valves will not close, A 0 c m not access valves due to location of steam break)

Verifies 0% valve position indicated on HCV-466, HCV-480, HCV-476, and HCV-481 Ensures MFW Pumps A and B C/Ss in PULL STOP Ensures only green status lights for Reheater Steam Supply valves AOV-3425, 3426, 3427 and 3428 lit. If not positions cam on REHEATER STEAM SUPPLY CONTROLLER, TC-3040 to allow arm to go lo center of cam.

Verifies S/G Pressure is c Condensate Pressure and Places Condensate Pump A, B, and C C/Ss in PULL STOP Verifies Total AFW flow > 200 gpm (- 100 gpm per S/G)

R. E. Ginna Nuclear Plant Page 14 of 16 Revision 00

- Appendix D Requiired Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event N0.: 6 Event

Description:

(- T=37 min)

Main Steam line break downstream of MSIVs, both MSlVs fail to close automatically or from the MCB, SI fails to actuate when setpoint reached Indications:

0 Gross Generator Load lowering 0 RCS Tcold, Thot, and Tavg lowering 0 Reactor Power rising 0 RCS and PRZR Pressure lowering 0 PRZR level lowering S/G Pressures lowering I 0 Steam FIOW rising Determines both S/Gs faulted BOP Minimizes Colddown from faulted S/Gs Verifies TDAFW Pump Steam Supply Valves MOV-3504A and MOV-350514 are in PULL STOP and closed Adjusts AFW flow to S/G A and B to 50 gpm each. (Critical Task CT-FR-P.1-6)

ATC Checks PRZFl PORV block valves have power available and at least one is oDen ATC Ensures one PORV open if RCS pressure is z 2335 psig and closes when less

--I---

than 2335 psig.

Determines Si Pumps B and C running SRO/ATC Checks if SI can be reset Determines RCS subcooling > 508F using core exit T/Cs and Fig. 1.O -

Figure Min Subcooling Verifies RVLIS Fluid Fracture > 84%

ATC Verifies SI Reset ATC Stops SI pumps B and C and RHR pumps A and B by placing C/Ss in STOP and returning ':o AUTO. (Critical Task CT FR-P.1-A)

End of Scenario R. E. Ginna Nuclear Plant Page 15 Of 16 Revision 00

Appendix D Requiired Operator Actions Form ES-D-2 3p-Test No.: 1 Scenario No.: 3 Event No.: 6 Event

Description:

(- T=37 min) blain Steam line break downstream of MSIVs, both MSlVs fail to close automatically or from the MCB, SI fails

o actuate when setpoint reached Indications:

Gross Generator Load lowering RCS Tcold, Thot, and Tavg lowering Reactor Power rising RCS and PRZR Pressure lowering PRZR level lowering S/G Pressures lowering Steam Flow rising Steam Flow Noise SRO Perform Emergency Plan Classification for final event Expected EAL.: Alert, 1.4.1, Red Path on F-0.4 Integrity Start Time: -

Stop Time: -

EAL:

R. E. Ginna Nuclear Plant Page 16 Of 16 Revision 00

Amendix D Scenario Outline Form ES-D-1 Facility: R. E. Ginna Scenario N3.: 4 Op-Test No.: 1 Examiners: - Operators:

Initial Conditions: 70%, MOL Turnover: SI Pump A 00s to refurbish failed motor, S/G A LT-461 00s due to failed Electronics, MDAFW Pump A 00s for impeller replacement Event Malf. Event Event No. No. Type* - Description C-ATC/SR0, 1 RCSl6 TS-SRO High RCS Activity I-BOP/SRO, 2 SGN03B TS-SRO Steam Generator A Pressure Transmitter PT-469 Fails Low Letdown Non-Regenerative Heat Exchanger Outlet Temperature TT-3 cvco5 I-ATC/SRO 130 Fails Low 4 FDW04B C-BOP/SRO Feedwater Pump B Lube Oil System Leak N-BOP/SRO, 5 N/A R-ATC Down Power to 50%

CND08, RPS05A, RPS05B, FDW12, Condensate Line Break, Bus 16 Fault, Loss of Feedwater 8, 6 EDS04B M-All Prefl?rredAFW Revision 00 Page 1 of 16

Facilty: R. E. Ginna Scenario No.: 4 Op-Test No.: 1 Scenario Descrbtion:

Shortly after taking the watch, a fuel failure will occur. The crew should enter AP-RCS.3, High Reactor Coolant Activity and EPlP 1-13, Local radiation Emergency and place the 60 GPM letdown orifice in service, in accordance with S-3.2P, Swapping Letdown Orifice. The SRO should refer to TS 3.4.16 and enter appropriate actions after sample results are obtained.

After the 60 gpm letdown orifice is in service, Steam Generator A Pressure Transmitter PT-469 fails low. The crew should implement ER-INST.1, Reactor F'rotection Bistable Defeat After Instrumentation Loop Failure, and place appropriate bistables in the tripped condition. The SRO should refer to TS 3.3.1, 3.3.2, and 3.3.3 and enter the appropriate actions.

After ER-INST.l has been addressed, TT-13C1, Letdown non-regenerative heat exchanger outlet temperature instrument fails low resulting in TCV-130 closing and letdown temperature rising. TCV-145 will bypass the ion exchangers due to high letdown temperature. The crew should implement AR-A-12, NON-REGEN HX LETDOWN OUT HI TEMP 145", take manual control of TCV-130, return letdown temperature to normal, and ensure ion exchangers are placed in service.

After letdown temperature is returned to normal, MFW Pump B develops an oil leak requiring a down power to 50% power. The crew should enter AP-FW.l Abnormal MFW Pump Flow or NPSH and perform the down power per AP-TURB.5, Rapid Load Reduction.

After the reactivity manipulation is satisfied, The Condensate header ruptures resulting in a loss of normal feedwater. The crew should perform a manual trip. The manual trip pushbutton fails and the crew should trip the reactor by opening the Bus 13 and Bus 15 normal feeder breakers. The crew should note at some point that auto failure has occurred as evidenced by S/G levels e 17% trip setpoint and reactor trip breakers still closed. The TDAFW pump fails to start as required and Bus 16 trips resulting in loss of the only operable Motor Driven AFW pump. The crew should perform the immediate actions of E-0, Reactor Trip or Safety injection, and transition to ES-0.1, Reactor Trip Response. After transition to ES-0.1, the crew should note a red path condition on the Heat Sink Critical Safety Function and transition to FR-H.l. The crew should start the Standby AFW Pumps and restore level in at least one S/G to > 7% Narrow Range. After performing the required actions of FR-H.l, the crew should transition back to ES-0.1. The scenario can be terminated after this transition.

Revision 00 Page 2 of 16

Facilty: R. E. Ginna Scenario No.: 4 Op-Test No.: 1 CRITICAL TASKS CT E-0--A - Manually ..ip the reactor from the control room b fo both SG levels lower to 50 inches wide range level.

Cues: Dpanel alarm annunciates and no reactor trip occurs Indication: Reactor trip and bypass breakers open OR Rod drive MG set breakers open Feedback: MRPl indicates rod 011bottom Neutron flux lowering CT FR-H.l--E - Establish 200 gpm feed flow before both SG wide range levels lower below 50 inches.

Cues: Indication of Rx trip and Indication that RCS pressure is > SG pressure and Total FW flow to SG is c 200 gpm Indication: Align and start the C SBAFW pump and establish > 200 gpm flow as indicated on flow indicator FI-4084,B.

Feedback: C SBAFW indicates running Flow is indicated to the SG(s) at > 200 gpm Steam generator leveI(s) rises Revision 00 Page 3 of 16

Facilty: R. E. Ginna Scenario No.: -~4 Op-Test No.: 1 Scenario Timeline:

Event Time Delay Ramp

- Number (Min) Key Event HH:MM:SS HH:MM:SS Final 1 1 RCS16 1 oo:oo:oo oo:oo:oo 60

- FUEL CLADDING FAILURE 2 ***(- 11) SGN03B 3 oo:oo:oo oo:oo:oo 0

- S/G PRESSURE CHANNEL FAILURE: PT-469 (11) 3 ***( -20) cvco5 5 oo:oo:oo oo:oo:oo 0 LOSS OF CCW TO NON-REGENERATIVE LETDOWN HX 4 ***(-28) FDW04B 7 oo:oo:oo 00:10:00 100

- FEEDWATER PUMP 1B LUBE OIL SYSTEM FAILURE 5 (-30) NIA NIA oo:oo:oo oo:oo:oo NIA DOWN POWER TO 50%

6 ***(- 35) CND08 9 oo:oo:oo 0O:Ol :oo 20000 CONDENSATE PIPE BREAK 6 Load FDW12 NIA oo:oo:oo oo:oo:oo 0

- AFW TURBINE DRIVEN PUMP SPEED CONTROL FAILURE 6 Load RPS05A NIA oo:oo:oo 0O:OO:OO NO MAN (1)

REACTOR TRIP BREAKER A FAILURE 6 Load RPS05B NIA oo:oo:oo 0O:OO:OO NO MAN (1)

REACTOR TRIP BREAKER B FAILURE 6 ***( -37) EDS04B 9 oo:oo:oo 00:02:00 1 LOSS OF EMERGENCY BUS: 4130V BUS 16 NIA NIA SGNO1 B NIA oo:oo:oo oo:oo:oo 0

- SIG LEVEL CHANNEL FAILURE: LT-461(1)

• • • Events initiated on cue from NRC Lead Examiner Estimated Time: 60 Minutes Revision 00 Page 4 of 16

Amendix D Reauired Onerator Actions Form ES-D-2 Op-Test No.:, 1 Scenario No.: 4 Event No.: 1 Event

Description:

(T=l min)

High RCS Activity Indications:

0 R-9. Letdown Line Monitor indication k i n g and in alarm 0

-1 24, RMS Area Moni Time Position ATC Recognizes a arms and indications and reports to SRO.

ATC/BOP Refers to AR-E-24 and AR-RMS-9 SRO Enters AP-RCS.3, High Reactor Coolant Activity SRO Directs RP to sample RCS for activity ATC Places 60 GPM orifice in service per S-3.2P, Swapping CVCS Letdown Orifice Valves 0 Verifies AOV-244 is in the BYPASS position.

0 Place; PCV-135 to MANUAL AND adjusts as necessary to control Low Pressure Letdown pressure at approximately 200 psig.

0 Closes on-line 40 gpm orifice valve and verifies standby 40 gpm orifice valve is closed (AOV-200A and AOV-200B), THEN immediately open 60 gpn orifice valve, AOV-202 0 Adjusts PCV-135 to achieve Letdown pressure of - 250 psig on PI-135.

0 Ensures PCV-135 controller signal is nulled/balanced and then places PCV-'I35 to AUTO.

0 Ensures TCV-130 is in AUTO.

0 Monitors Charging/Letdown mismatch and verifies Charging pump A respoiids in AUTO or adjusts charging flow manually.

0 Requests an A 0 locally adjust Reactor Coolant Pump Seal Injection Flow to maintain labyrinth seal D/P between 30 and 40 inches.

0 Monitors Letdown temperature controller TCV-35 is controlling at desired value.

0 Requests an A 0 verify local demin DIP c25 psid (DPI-100, DPI-101).

0 Notifies Shift Chemistry Technician.

SRO Determines R-9 reading > 200 mR/hr and implements EPlP 1-13, Local Radiation Emergency concurrently with AP-RCS.3.

SRO Directs RP to (determineDI decontamination factor.

SRO Directs RP to iperform surveys in the AUX BLDG SRO Evaluates MCB annunciators.

SRO Consults with dant staff to determine if shutdown is required SRO Notifies higher supervision.

SRO Refers to TS 54.16 and enters Condition A, Action A . l R. E. Ginna Nuclear Plant Page 5 of 16 Revision 00

ADDendix D Reauired ODerator Actions form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 1 Event

Description:

(T=l min)

High RCS Activity Indications:

0 R-9, Letdown Line Monitor indication rising and in alarm R. E. Ginna Nuclear Plant Page 6 of 16 Revision 00

-Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 2 Event

Description:

(- T = l l min)

Steam Generator A Pressure Transmitter PT-469 Fails Low Indications:

0 Fl-465, STEAM GEN A-2 STEAM FLOW reads lower than Fl-464, STEAM GEN A-1 STEAM FLOW and Fl-493, STEAM GEN A-3 STEAM FLOW PI-469, STEAM GEN A-2 PRESSURE failed low G-22, ADFCS SYSTEM TROUBLE lit G-11, LO STEAM PRESSURE LOOP A 600 PSI 27, STM LINE A LO-LO PRESS CHANNEL ALERT 514 PSI Position BOP Recognizes alarms and indications and reports to SRO.

SRO Enters ER-1N:ST.l and goes to Section 4.9 and implements Attachment S/G Pressure Channel PI-469 White Channel BOP In the (WHITE!) W2 PROTECTION CHANNEL 2 rack:

0 Places the 469 LOOP A-2 LO LO PRESS SI bistable proving switch to DEFEAT (UP) 0 Verifies the 469 LOOP A-2 LO LO PRESS SI bistable proving light OFF 0 Places the 469 LOOP A-2 LOW PRESS bistable proving switch to DEFEAT (UP) 0 Verifies the 469 LOOP A-2 LOW PRESS bistable proving light OFF 0 Places the 465 LOOP A-2 HIGH TRIP bistable proving switch to DEFEAT (UP) 0 Verifies the 465 LOOP A-2 HIGH TRIP bistable proving light OFF Places the 465 LOOP A-2 HI HI TRIP bistable proving switch to DEFEAT (UP) 0 Verifies the 465 LOOP A-2 HI HI TRIP bistable proving light ON BOP/ATC Verifies the bistable status lights listed above are lit.

0 FC465A Hi Steam Flow 0 FC465B Hi Hi Steam Flow 0 PC469A Lo Press SI G-11, LO STEAM PRESSURE LOOP A 600 PSI G-26, S/G A HI STEAM FLOW G-27, STM LINE A LO-LO PRESS CHANNEL ALERT 514 PSI R. E. Ginna Nuclear Plant Page 7 of 16 Revision 00

-Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 2 Event

Description:

(- T = l l min)

Steam Generator A Pressure Transmitter PT-469 Fails Low Indications:

0 Fl-465, STEAM GEN A-2 STEAM FLOW reads lower than Fl-464, STEAM GEN A-1 STEAM FLOW and Fl-493, STEAM GEN A-3 STEAM FLOW 0 PI-469, STEAM GEN A-2 PRESSURE failed low G-22, ADFCS SYSTEM TROUBLE lit G-11, LO STEAM PRESSURE LOOF A 600 PSI 0 .27, STM LINE A LC LO PRESS CHANNEL ALERT 514 PSI Time Position BOP Deletes the channel from the PPCS by performing the following:

On the Sub/Delete/Restore display o Selects Point ID PO469 o Turns OFF scan processing o Selects Change On the Sub/Delete/Restore display o Selects Point ID F0465 o Turns OFF scan processing o Selects Change SRO Checks the fcllowing ITS Sections for LCOs:

Section 3.3.2, Table 3.3.2-1, Function 1e o Enters Condition L, Action L.l Section 3.3.2, Table 3.3.2-1, Functions 4d and 4e o Enters Condition F, Action F . l Section 3.3.3, Table 3.3.3-1, Functions 24 and 25 o Determines requirements are still being met with one channel out of service, No further action required R. E. Ginna Nuclear Plant Page 8 of 16 Revision 00

~~

-Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 3 Event

Description:

(- T=20 min)

Letdown Non-Regenerative Heat Exchanger Outlet Temperature TT-130 Fails Low Indications:

A-12, NON-REGEN HX LETDOWN ClUT HI TEMP 145'F 0 TI-130, NON-REGEN HX LTDN OUT TEMP failed low 0 LTDN DIVERT TO DI OR VCT, TCV- 145 positioned to VCT in AUTO NRHX LTDN OUTLET TEMP (TI-130'1TCV-130 controller output 100%

.I Divert to DI or VCT, TCV-145 is diverting to VCT.

!activity changes and RCP seal performance.

I ATC/BOP 1 Checks for proper charging and letdown flows, and temperatures.

Charging Line Flow (FI-l28B or C) = 25 gpm.

LTDN Line Flow (FI-134) = 40 gpm

LTDN Outlet Temp PPCS Point TO145 at the normal value.

i,COMPONENT COOLING WATER SYSTEM STARTUP AND

!RATION VALVE ALIGNMENT.

tion Report for Technical Evaluation.

R. E. Ginna Nuclear Plant Page 9 of 16 Revision 00

-Appendix D Required Operator Actions Form ES-D-2 3p-Test No.: 1 Scenario No.: 4 Event No.: 4

vent

Description:

(- T=28 min)

Ieedwater Pump B Lube Oil System Leak ndications:

0 H-12, Feed Pump DC Oil Pump Auto Start O-se tm Reports Annunciator H-12 to SRO.

0 Verifies DC Oil Pump started.

SRO/BOP Notifies A 0 to perform the following:

0 VERIFY Oil in the sump by LG-2764(2773) OR dipstick.

0 CHECK DC Oil Pump.

0 IF required, THEN START the other AC Oil Pump.

Reports Annulxiator H-4 to SRO.

I SRO/BOP Notifies A 0 to perform the following:

0 Check. for leaks.

Check. filter DP.

1 I 0 SRO When MFW Pump trips, goes to AP-FW.l, Abnormal MFW Pump Flow or NPSH.

Verifies Reactor Power > 50%.

SRO/BOP Determines only one MFW Pump running.

Verifies Reactor Power c 75%.

BOP Starts all 3 AFW pumps and verifies flow.

Initiates powei reduction per AP-TURB.5, RAPID LOAD REDUCTION.

If S/G levels drop to 20% NR performs a manual reactor trip and goes to E-0, Reactor Trip cr Safety Injection.

P End of Event R. E. Ginna Nuclear Plant Page 10 of 16 Revision 00

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

Description:

(-T=30)

-Down Pc fer to 50%

P Time -- Position P 3__

Applicants Actions or Behavior P SRO Provides ATC and BOP with instructions for down power.

ATC Verifies Rods in AUTO or adjusts rods in MANUAL to maintain Tavg to Tref.

BOP Reduces turbirle load in Auto as follows:

Place:; Turbine EH Control in OPER PAN., IMP PRESS IN Selecis rate on thumbwheel per SRO instructions.

Reduces the load setter to 50% load value.

Depresses the GO button.

ATC Initiates boration at 4 gal/% load reduction (-40-80 gals) per SRO instructions.

ATC

- Places PRZR backup heater switch to ON.

ATC/BOP Adjusts Turbire load rate, Boric Acid flowrate, Rods to maintain Tavg to Tref.

BOP Verifies Turbine Load reduction stops when Load = Setter End of Event R. E. Ginna Nuclear Plant Page 11 of 16 Revision 00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:, 1 Scenario No.: 4 Event No.: 6 Event

Description:

(-T=35 min)

Condensate Line Break, Bus 16 Fault, Loss 0':all Feedwater Indications:

H-1, Feedwater Pump Lo Suct Press 185 PSI H-11, Feed Pump Seal Water Lo Diff Press 15 PSI H-14, Condensate Header Press Lo H-17, Feed Pump Net Positive Suction Head 0 H-30, Condensate Bypass Valve Open 0 AA-9, Cond Bstr Pump Press Trip 100 PSI 425 0 AA-25, Cond Sys Lo Press 325 PSI 0 AA-30, Cond Bstr Pmp Lo Suct Press 100 PSI 0 Feed Flow e Steam Flow 0 S/G NR and WR levels lowering arms and indications and reports to SRO.

)r Trip per AP-FW.l with no MFW Pumps running and goes to E-I or Safety Injection.

Verifies Reactor Tripped (Critical Task CT-E-O--A) 0 Open:; Bus 13 And 15 normal feeder breakers Verifies Rod Drive MG sets tripped 0 Close:; Bus 13 and Bus 15 normal feeder breakers 0 Resets lighting breakers 0 Verifies neutron flux lowering - Power range indicators NI-41 through NI-44 < 5%

0 Verifies MRPl indicates all rods on bottom '

BOP Verifies all turbine stoD valves closed BOP Verifies Buses 14, 16, 17, and 18 2 440V ATC Determines SI is not actuated or required.

0 No SI Annunciators 0 RCS Pressure > 1750 psig 0 Steam line Pressure > 514 psig 0 CNMT' Pressure < 4 psig 0 SI not sequencing SRO Re-verifies Immediate Actions R. E. Ginna Nuclear Plant Page 12 of 16 Revision 00

-Appendix 0 Required Operator Actions Form ES-0-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 6 Event

Description:

(-T=35 min)

Condensate Line Break, Bus 16 Fault, Loss of all Feedwater Indications:

0 H-1, Feedwater Pump Lo Suct Press 185 PSI 0 H-11, Feed Pump Seal Water Lo Diff Press 15 PSI 0 H-14, Condensate Header Press Lo 0 H-17, Feed Pump Net Positive Suction Head 0 H-30, Condensate Bypass Valve Open 0 AA-9, Cond Bstr Pump Press Trip 100 PSI 425 0 AA-25, Cond Sys Lo Press 325 PSI 0 AA-30, Cond Bstr Pmp Lo Suct Press 100 PSI 0 Feed Flow < Steam Flow 0 S/G NR and WR levels lowering itwell Level lowerin!

- Position

____I SRO Transitions to ES-0.1, Reactor Trip Response SRO/ATC/BOP Commences CSFST and Foldout Page monitoring.

ATC Monitors Tavg at or trending to 547".

ATC Checks PRZFl level control 0 Verifies at least one charging pump running 0 Verifies letdown in service 0 Verifies PRZR level > 13% and trending to 20%

0 Verifies PRZR Proportional and Backup Heaters ON ATC/BOP Checks S/G feed Flow Status 0 Verifies RCS Tavg< 554°F 0 Verifies MFW regulating and bypass valves closed 0 Reports 0 gpm AFW flow and no AFW pumps or MFW available 0 Closes MFW Pump Discharge Valves MOV-3977 and MOV-3976 0 Places both MFW Pump C/Ss to PULL STOP 0 Places MFW Regulating valve controllers in MANUAL and lowers output to 0.

ATC Verifies all rocls fully inserted using MRPl display SRO When Narrow Range level in both S/Gs is < 7% with < 200 gpm total feedwater flow to the S/Gs, transitions to FR-H.l, Response to Loss of Secondary Heat Sink.

R. E. Ginna Nuclear Plant Page 13 of 16 Revision 00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event N0.: 6 Event

Description:

(-T=35 min)

Condensate Line Break, Bus 16 Fault, Loss of all Feedwater Indications:

0 H-1, Feedwater Pump Lo Suct Press 185 PSI 0 H-11, Feed Pump Seal Water Lo Diff Press 15 PSI 0 H-14, Condensate Header Press Lo 0 H-17, Feed Pump Net Positive Suction Head 0 H-30, Condensate Bypass Valve Open 0 AA-9, Cond Bstr Pump Press Trip 100 PSI 425 0 AA-25, Cond Sys Lo Press 325 PSI 0 AA-30, Cond Bstr Pmp Lo Suct Press 100 PSI 0 Feed Flow e Steam Flow 0 S/G NR and WR levels lowering jtwell Level lowerinc vith Hotwell LI

=___ P

_Ip__

Position P p 4TC Verifies secor dary heat sink required 0 RCS pressure is S/G A and S/G B pressure 0 RCS Cold Leg temperature >350QF BOP/ATC Monitors Secondary Heat Sink (Continuous Action) 0 Verifies at least one S/G Wide Range level > 50 inches 0 Verifies PRZR pressure < 2335 psig SRO/BOP Verifies no AFW pumps available and goes to next step ATC Stops RCP 1A and 1B SRO/ATC Verifies SI not actuated and goes to next step BOP Establishes SAFW flow to at least one S/G (CT FR-H.1-E) 0 Using ATT. 5.1, Attachment SAFW, Aligns SAFW Pump C to selected S/G as follows:

o Ensures SI Reset o Ensures the following valves open:

MOV-9701A, SAFW PUMP C DISCHARGE VLV MOV-4616, AUX BLDG SW ISOL VLV 9 MOV-9704A, SAFW PUMP C ISOL VLV I o Opens MOV-9629A, SAFW PUMP C SUCTION VLV.

o Verifies at least 1 SW DumD runnina.

R. E. Ginna Nuclear Plant Page 14 of 16 Revision 00

-Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:, 1 Scenario No.: 4 Event No.: 6 Event

Description:

(-T=35 min)

Condensate Line Break, Bus 16 Fault, Loss of all Feedwater Indications:

0 H-1, Feedwater Pump Lo Suct Press 185 PSI H-11, Feed Pump Seal Water Lo Diff Press 15 PSI 0 H-14, Condensate Header Press Lo 0 H-17, Feed Pump Net Positive Suction Head 0 H-30, Condensate Bypass Valve Open 0 AA-9, Cond Bstr Pump Press Trip 100 PSI 425 0 AA-25, Cond Sys Lo Press 325 PSI 0 AA-30, Cond Bstr Pmp Lo Suct Press 100 PSI 0 Feed Flow e Steam Flow 0 S/G NR and WR levels lowering

)twell Level lowerin! Nith Hotwell Lc

-Position -

BOP o To feed selected S/G: (CT FR-H.1-E cont.)

S/G A - restores SAFW flow as directed by procedure in effect.

OR

. S/G B, performs the following:

0 Ensures MOV-9746, SAFW PMP D EMERG DISCH VLV, open 0 Closes MOV-9704A, SAFW PUMP C ISOL VLV Opens either SAFW CROSSOVER VLV:

o MOV-9703A OR o MOV-9703B 0 Verifies open MOV-9704B, SAFW PUMP D ISOL VLV 0 Restores SAFW flow as directed by procedure in effect.

0 Verifies selected S/G Wide Range level is > 50 inches and determines from ATT-22.0, Attachment Restoring Feed Flow that flow can be started at > 235 gpm 0 Starts SAFW Pump C by taking C/S to START When intact S/G level GREATER THAN 50 inches (100 inches adverse CNMT), THEN verify SAFW flow GREATER THAN 235 GPM R. E. Ginna Nuclear Plant Page 15 of 16 Revision 00

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

Description:

(-T=35 min)

Condensate Line Break, Bus 16 Fault, Loss of all Feedwater Indications:

0 H-1, Feedwater Pump Lo Suct Press 185 PSI 0 H-11, Feed Pump Seal Water Lo Diff Press 15 PSI 0 H-14, Condensate Header Press Lo H-17, Feed Pump Net Positive Suction Head H-30, Condensate Bypass Valve Open AA-9, Cond Bstr Pump Press Trip 100 PSI 425

, 0 AA-25, Cond Sys Lo Press 325 PSI 0 AA-30, Cond Bstr Pmp Lo Suct Press 100 PSI 0 Feed Flow c Steam Flow 0 S/G NR and WR levels lowering

)twell Level lowerinc Nith Hotwell Lc Position ___i SRO Goes to step 1 1 SRO/BOP Checks Narrow Range Level in selected S/G > 7% or SAFW flow is > 235 gpm

- to selected S/S and selected S/G level WR and/or NR rising.

SRO Returns to step in effect in ES-0.1, Reactor Trip Response End of Scenario SRO Perform Emergency Plan Classification for final event Expected EAL: Site Area Emergency, 1.3.1, Red Path in F-0.3 Heat Sink Start Time:

Stop Time: -

EAL:

R. E. Ginna Nuclear Plant Page 16 of 16 Revision 00

-Appendix D Scenario Outline Form ES-D-1 Facility: R. E. Ginna Scenario No.: 5 Op-Test No.: 1 Examiners: - Operators:

Initial Conditions: 1OO%, EOL Turnover: SI Pump A 00s to refurbish failed motor, S/G A LT-461 00s due to failed Electronics, MDAFW Pump A 00s for impeller replacement Event Malf. Event Event No. No. TvDe* DescriDtion 1 N/A TS-SRO EDG A Fuel Oil High Particulates

~~ -

2 TUR11B C-BOP/SRO TLrbine Control Valve V3463 Fails Closed N-BOP/SRO, 3 N/A R-ATC Plilnt Down Power C-ATC/SRO, 4 ROD02-G7 TS-SRO Dropped Rod G7 5 RCS12A C-ATC/SRO RCP 1A #1 Seal Failure ROD03-C5, 6 ROD03-K9 C-ATC/SRO Rods C5 and K9 fail to insert on trip RCS02D, RPSO6, RPS07B, RPSO7C, M-All, Small Break LOCA, CI fails to occur automatically or manually, SI 7 RPS07D I/C BOP Pumps B and C fail to start automatically

' (N)orrnal, (R)eactivity, (I)nstrurnent, (C)ornponerit, (M)ajor Revision 00 Page 1 of 19

Facilty: R. E. Ginna Scenario No.: 5 Op-Test No.: 1 Scenario Descrbtion:

Shortly after taking the watch, the Shift Chem st will call the Control Room and report that two independent samples have been taken and analyzed indicating high out of spec total particulate content in the D/G A Fuel Oil Tank. The SRO should refer to TS 3.8.3 and enter Condition B and Action 6.1 Turbine Control Valve V3463 (Control Valve #4) fails closed. The crew should enter AP-TURB.2, Turbine Load Rejection. The SRO should determine that a Yoad reduction to 50% power is required in accordance with AP-TURB.5, Rapid Load Reduction.

After the reactivity manipulation requirements are satisfied, Rod G7 drops into the core. The crew should stabilize the plant and enter AP-RCC.3, Dropped Rod Recovery. The SRO may refer to AP-RCC.2 initially and then go to AP-RCC.3 from AP-RCC.2 step 2 depending on which annunciator responses are referred to.

The SRO should evaluate the operability of the dropped rod and refer to TS 3.1.4, 3.2.3, and 3.2.4. The SRO should enter TS 3.1.4 Condition B and determine Actions B . l . l through B.6 apply. The SRO should verify Axial Flux Distribution and QPTR are within limits or enters 3.2.3 Condition A and Action A.l and/or 3.2.4 Condition A and Action A.l through A.6 as applicable. G7 is the center rod. AFD and QPTR should not be adversely affected.

After the plant has been stabilized and the crew implements AP-RCC.3 up to the point of referring to ER-RCC.1, Retrieval of a Dropped RCC, RCP 1A #1 Seal fails. The crew should implement AP-RCP.l, RCP Seal Malfunction. The crew should determine that the # I RCP seal is failed and a reactor trip should be performed to secure the 1A Reactor Coolant Pump.

The crew trips the reactor and goes to E-0, Reactor Trip or Safety Injection. After immediate actions are performed the 1A RCP should be secured. The crew should note that two Rods C5 and K9 did not insert on the trip. The crew should determine no SI is required and transition to ES-0.1, Reactor Trip Response.

After the crew commences boration in ES-0.1 to compensate for the reactivity of the stuck rods, A small break LOCA occurs and the crew transitions back tc, E-0, step 1. The crew should take action to manually start SI Pumps B and C which fail to start on SI actua':ion. CI fails to occur automatically or manually and the crew should perform manual actions to close containment isolation valves. The crew will transition to E-1, Loss of Reactor or Secondary Coolant. The scenario ends when the crew transitions to ES-1.2, Post LOCA Cooldown and Depressurization.

Revision 00 Page 2 of 19

Facilty: R. E. Ginna Scenario No.: 5 Op-Test No.: 1 CRITICAL TASKS CT E-O--0 Task: Initiate CNMT isolation such that at least one valve is closed in each flow path which is passing fluid out of containment.

Cues: LOCA in CNMT and SI actuated and CNMT isolation not actuated Alarm not actuated Status lights indicate valve(s) idare open in flow paths Indication: Manipulation of controls to isolate all flow paths by at least one closed CNMT isolation valve before the end of the scenario.

Feedback: Valve status lights indicate valves are closed.

CT E-0--I Task: Establish flow from at least one train of high pressure SI pumps (two pumps running with flow to opposite trains) before transition out of E-0.

Cues: A SI pump 00s B SI pump not running C SI pump not running Indication: B and C SI pump manually startemd from MCB Feedback: B and C SI pump indicates it is running from status lights and SI flow indicated Revision 00 Page 3 of 19

Facilty: R . E. Ginna Scenario No.: 5 Op-Test No.: 1 CT E-1--C Task: Trip the reactor coolant pump 1B within 5 minutes of the time RCP trip criteria met and step reached in E-1 Cues: Two SI pumps running and RCS pressure minus maximum SG pressure is less than 210 psig (240 psig adverse)

Indication: RCP 1 B manually tripped Feedback: RCPs indicate tripped from status lights No flow indicated on loop flow instruments Revision 00 Page 4 of 19

Facilty: R. E. Ginna Scenario No.: 5 Op-Test No.: 1 Scenario Timeline:

Event Time Delay Ramp Number (Min) Key Event HH:MM:SS HH:MM:SS Final N/A Load SGNO1B N/A oo:oo:oo oo:oo:oo 0 S/G LEVEL CHANNEL FAILURE: LT-461(I) 1 1 N/A N/A oo:oo:oo oo:oo:oo N/A EDG A FUEL OIL HIGH PARTlClJLATES 2 ***(- 6) TUR11 B 1 oo:oo:oo oo:oo:oo 0 TURBINE CNTRL VLV FAILURE: CVL-4 (V3463) 3 (- 10) N/A N/A oo:oo:oo oo:oo:oo N/A PLANT DOWN POWER --

4 ***(- 15) ROD02-G7 3 oo:oo:oo 0O:OO:OO STATIONARY (1)

DROPPED ROD G7 5 ***(-- 22) RCS12A 5 oo:oo:oo oo:oo:oo 20

- RCP 1A NO.l SEAL FAILURE (UNREC) 6 Load (- 27) ROD03-C5 N/A oo:oo:oo 0O:OO:OO UNTRIPPABLE (1)

STUCK ROD C5 6 Load ROD03-K9 N/A oo:oo:oo 0O:OO:OO UNTRIPPABLE (1)

STUCK ROD K9 7 ***(- 35) RCS02C 7 00:00:00 00:00:00 1200 RCS LEAK INTO CNMT: LOOP E3 HOT LEG (UNREC) 7 Load RPSOG N/A oo:oo:oo oo:oo:oo 1 CONTAINMENT FAILS TO ISOLATE 7 Load RPSO7B N/A oo:oo:oo oo:oo:oo 1 AUTO FAIL: B SI PUMP 7 Load RPS07C N/A 00:00:00 oo:oo:oo 1 AUTO FAIL: C SI PUMP ON BUS 14 7 Load RPS07D N/A oo:oo:oo oo:oo:oo 1 AUTO FAIL: C SI PUMP ON BUS 16

• • • Events initiated on cue from NRC Lead Examiner Estimated Time: 60 Minutes Revision 00 Page 5 of 19

Appendix D Reauired ODerator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 5 Event No.: 1 Event

Description:

(T=l min)

D/G A Fuel oil High Particulates Indications:

Shift Chemist calls the Control Room and reports that two independent samples have been taken and i report from Shift Chemist concerning D/G A Fuel Oil at TS 3.8.3 Candition 6 and Action 6.1 should be entered (7 day R. E. Ginna Nuclear Plant Page 6 of 19 Revision 00

-Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 5 Event No. : 2 Event

Description:

(-T=6 min)

Turbine Control Valve V3463 Fails Closed Indications:

e F-4, Pressurizer Level Deviation -5 Normal +5 a F-14, Charging Pump Speed e G-15, Steam Dump Armed e Steam dump valves operating e Bank D Rods inserting e Reactor Power lowering e PRZR Pressure rising e PRZR level rising e Tavg-Tref Deviation e CVL-4 Closed light lit on EH Valve Status Panel e

dications and alarms and reports to SRO.

i-15, AR-F-4, and AR-F-14 RB.2, Turbine Load Rejection and verifies Rods responding in AUTO at Turbine Control Valve 4, V3463 indicates closed BOP Verifies Stearri Dump operating properly in AUTO End of Event R. E. Ginna Nuclear Plant Page 7 of 19 Revision 00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 5 Event No. : 3 Event

Description:

(- T=10 min)

Plant Down Power and BOP with instructions for down power.

in AUTO or adjusts rods in MANUAL to maintain Tavg to Tref.

ne load in Auto as follows:

Places Turbine EH Control in OPER PAN., IMP PRESS IN or OUT per SRO instructions Selects rate on thumbwheel per SRO instructions.

Reduces the load setter to per SRO instructions.

DeDresses the GO button.

ATC Initiates boration at 4 gal/% power (-100-200 gals) per SRO instructions.

ATC Places PRZR backup heater switch to ON.

Adjusts Turbine load rate, Boric Acid flowrate, Rods to maintain Tavg to Tref.

Stops Conder sate Booster Pumps B and C at - 70% power.

Verifies Trim valve controller set at 375 psig Verifies Trim valve, AOV-9508G - GREATER THAN 80% open Verifies Annunciator AA-17, COND BSTR PMP DISCH HI PRESS -

LIT Place!; condensate booster pump A switch to the trip position Stops condensate booster pump B or C by placing switch in the trip position.

Verifies Condensate pressure - STABLE or RISING Verifies Trim valve 9508G - GREATER THAN 20% OPEN Stops the remaining condensate booster pump by placing switch in the triD tmsition.

BOP Verifies Turbine Load reduction stops when Load = Setter

=

End of Event R. E. Ginna Nuclear Plant Page 8 of 19 Revision 00

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

Description:

(- T=15 min)

Dropped Rod G7 Indications:

0 C-14, Rod Bottom Rod Stop 0 E-28, Power Range Rod Stop 0 F-10, Pressurizer Lo Press 2205 PSI F-14 Charging Pump Speed 0 MRPl display indicates Rod G7 fully inserted 0 PRZR Pressure lowering Level lowering

!actor Power lowerir L L Position ATC Recognizes indications and alarms and reports to SRO.

SRO/ATC Reviews AR crocedures SRO Enters AP-RCC.3, Dropped Rod Recovery. (May go to AP-RCC.2 initially and have rods placed in manual and then go to AP-RCC.3)

ATC Verifies only cne rod has dropped by checking MRPl Display.

ATC Places Rods irl MANUAL BOP Stabilizes RC!3 Tavg to Tref by adjusting turbine load.

BOP Verifies steam dump valves closed BOP Checks Main Generator Load > 15 MW ATC/BOP Establishes stable plant conditions Tavg :rending to Tref 0 PRZR pressure trending to 2235 psig PRZR level trending to program in AUTO 0 S/G NR levels trending to 52% w/MFW regulating valves in AUTO ATC/BOP Checks QPTFl c 1.02 by PPCS indication NIS and lncore Tilts display SRO/ATC Evaluates Coritrol Rod Operability:

Verifies MRPl indicates rod on bottom Directs I&C to locally investigate rod failure Refer:; to ER-RCC.1, RETRIEVAL OF A DROPPED RCC R. E. Ginna Nuclear Plant Page 9 of 19 Revision 00

-Appendix D Required Operator Actions Form ES-D-2 3p-Test No.: 1 Scenario No.: 5 Event No.: 4 Event

Description:

(- T=15 min) lropped Rod G7 ndications:

0 C-14, Rod Bottom Rod Stop 0 E-28,Power Range Rod Stop 0 F-10, Pressurizer Lo Press 2205 PSI 0 F-14 Charging Pump Speed 0 MRPl display indicates Rod G7 fully inserted 0 PRZR Pressure lowering 0 PRZR Level lowering

-Time p e h a v i o r 0 Operations Manager (or other senior Plant Management) 0 RG&EI Energy Control Center 0 CPS Generation Dispatcher 0 3.1.4 .. Condition B and Actions B.l.l-B.6 0 3.2.3 '. Rod on Bottom Axial Flux Distribution should not be outside

' G7 is the center CEA. Quadrant Power Tilt should still be <

determine cause of dropped rod and to e dropped RCCA rod group.

rod retrieval. (Should continue down power ted if not complete)

R. E. Ginna Nuclear Plant Page 10 of 19 Revision 00

Amendix D Reauired Onerator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 5 Event No.: 5 Event

Description:

(- T=22 min)

RCP A Seal #1 Failure Indications:

B-9, RCP 1A Labyr Seal Lo Diff Press 15" H 2 0 8-17, RCP 1A No. 1 1 Seal Hi-Lo Flow 5.0 GPM 1.0 8-3,RCP 1A Standpipe Hi Level +1 Ft A-8, RCP A Seal Water Inlet Hi Temp 150QF RCP 1A Labyr Seal Diff Press PI-131 indicates 0 RCP 1A Seal Water Inlet Temp, TI-lS2 rising RCP 1A Seal 1 Outlet Temp TI-181 ri:sing

)tal #1 Seal flow > 8.0 GPM for RCP 1A after all E-0 Immediate Actions done.

inutes for pump coast down, then closes RCP 1A seal disch valve, R. E. Ginna Nuclear Plant Page 11 of 19 Revision 00

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

.nd K9 fail to insert on -

Position ATC derifies Reac1:or Tripped 0 Verifies Reactor Trip breakers open 0 Verifies neutron flux lowering - Power range indicators NI-41 through NI-44 c 5%

0 Verifies MRPl indication and reports rods C5 and K9 are stuck out BOP Verifies all turbine stop valves closed BOP Verifies Buse:; 14, 16, 17, and 18 > 440V ATC Determines SI is not actuated or required.

0 No SI Annunciators 0 RCS IRessure > 1750 psig 0 Steam line Pressure > 514 psig 0 CNM-r Pressure c 4 psig 0 SI not sequencing SRO Re-verifies Immediate Actions SRO Transitions to ES-0.1, Reactor Trip Response ATC Monitors Tavsi at or trending to 547".

ATC Checks PRZF' level control 0 Verifies at least one charging pump running 0 Verifies letdown in service 0 Verifies PRZR level > 13% and trending to 20%

0 Verifies PRZR Proportional and Backup Heaters ON ATC/BOP Checks S/G fced Flow Status 0 Verifies RCS Tavgc 554QF 0 Verifies MFW regulating and bypass valves closed 0 Verifies MDAFW pump B running and Total AFW flow is > 200 gpm to S/G B 0 Close:; MFW Pump Discharge Valves MOV-3977 and MOV-3976 0 Place!; both MFW Pump C/Ss to PULL STOP 0 Places MFW Regulating valve controllers in MANUAL and lowers output to 0 0 Verifies MFW bypass controllers are in MANUAL and 0% output.

ATC Verifies MRPl indication and reports C5 and K9 are still not inserted R. E. Ginna Nuclear Plant Page 12 of 19 Revision 00

-Appendix D Required Operator Actions Form ES-D Op-Test No.:, 1 Scenario No.: 5 Event No.: 6 Event

Description:

(- T=27 min) initiate a 1300 gal boration to the RCS Places RMW mode selector switch to BORATE.

0 Adjusts boric acid flow control valve, FCV-110A, for desired flowrate.

0 Sets boric acid integrator to desired amount (650 gallons for each control rod not fully inserted).

0 Places RMW control to START and verifies flow.

Verifies PRZFl Pressure and transitions to E-0, Reactor Trip or Safety R. E. Ginna Nuclear Plant Page 13 of 19 Revision 00

- Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 5 Event No.: 7 Event

Description:

(-T=35 min)

Small Break LOCA, CI fails to occur automatic-,ally or manually, SI Pumps B and C fail to start automatically Indications:

PRZR Level lowering PRZR and RCS Pressures lowering Containment Radiation Monitors rising or in alarm (R-11,R-2, R-7, R-29, R-30)

SI occurs on low PRZR Pressure 1750 psig CI valves remain open after SI SI Pump B and C pump status lights remain green mediate action steps (Steps 1-4)

Notes Contairiment Isolation did not actuate and attempts to manually actuate IANUAL CI pushbutton. Reports CI did not occur.

ps B and C did not start Verifies CNMT Spray is not required I I e A-27, CNMT SPRAY not lit CNMT Pressure c 28 psig on Pl-945, Pl-947, and Pl-949 SRO Directs BOP t13perform ATT-27.0, Attachment Automatic Action Verification.

R. E. Ginna Nuclear Plant Page 14 of 19 Revision 00

Amendix D Reauired ODerator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 5 Event No.: 7 Event

Description:

(-T=35 min)

Small Break LOCA, CI fails to occur automatically or manually, SI Pumps B and C fail to start automatically Indications:

0 PRZR Level lowering 0 PRZR and RCS Pressures lowering Containment Radiation Monitors rising or in alarm (R-11, R-2, R-7, R-29, R-30)

SI occurs on low PRZR Pressure 1750 psig 0 CI valves remain open after SI SI Pump B and C pump status lights remain green 1

Performs AT7'-27.0. Attachment Automatic Action Verification Manually starts SI Pumps B and C by momentarily taking C/S to I STAFlT (CRITICAL CT E-0-4)

Closes or verifies closed Containment lsol Vtvs from MCB (White Statu:; Lights bright) (CRITICAL CT E-0--0 0 PRT/RCDT lsol to Vent HDR lsol Vlvs, AOV-1786 and AOV-1787 0 PRT/RCDT lsol to Gas Analyzer lsol Vlvs, AOV-539 and AOV-1789 0 RCDT Outlet lsol Vlvs, AOV-l003A, AOV-10038, and AOV-1721 0 Steam Gene Blowdown Vlvs, AOV-5735, AOV-5736, AOV-5737, and AOV-5738 0 RCS Sample Vlvs, AOV-966A, AOV-966B, AOV-966C, AOV-951, AOV-953, AOV-955, and AOV-959 0 CCW to Rx Supp Clrs Is01 Vlv, MOV-813 0 CCW from R x Supp Clrs lsol Vlv, MOV-814 0 Seal or Excess LTDN Return lsol Vlv, MOV-313 0 LTDN Is01 VIV RHX to NRHX, AOV-371 0 lnst Air to CNMT lsol Vlv, AOV-5392 Place; CNMT Sump Pump A in PULL-STOP Places CNMT Sump Pump B in PULL-STOP Directs an A 0 to close the following valves at the Waste Panel:

o CNMT Sump Pump A Disch Is01 Vlv, AOV-1723 o CNMT Sump Pump B Disch lsol Vlv, AOV-1728 Determines TDAFW Pump running by verifying MOV-3505A and MOV-3504A open R. E. Ginna Nuclear Plant Page 15 of 19 Revision 00

Appendix D Required Operator Actions Form ES-D-2

-- Event No.: 7 Event

Description:

(-T=35 min)

Small Break LOCA, CI fails to occur automatically or manually, SI Pumps B and C fail to start automatically PRZR Level lowering PRZR and RCS Pressures lowering Containment Radiation Monitors rising or in alarm (R-11, R-2, R-7, R-29, R-30)

SI occurs on low PRZR Pressure 1750 psig CI valves remain open after SI SI Pump B and C pump status lights remain green Position ATC Verifies AFW flow indicated to both S/Gs and MDAFW Pump B flow < 230 aDm.

ATC/BOP Verifies at least one S/G Narrow Range Level > 25% or verifies Total AFW flow is > 200 gpm AT C/BOP Verifies both S/G Narrow Range Levels c 50%. Secures AFW flow to any S/G

> 50% Narrow Range.

ATC/BOP Controls AFW flow to maintain S/G levels between 25 and 50% Narrow Range.

SRO Determines T3AFW Pump should not be stopped.

ATC Verifies annuriciators A-7(A-15), RCPlA(1B) CCW Return HI Temp or Lo Flow are not lit. ,,

ATC Monitor RCS 'ravg - STABLE AT OR TRENDING TO 547°F BOP IF teniperature less than 547°F and lowering, THEN perform the following:

o Stop dumping steam.

o Ensure reheater steam supply valves are closed.

o IF cooldown continues, THEN control total feed flow between 200 gpm to 230 gpm until narrow range level greater than 25% in at least one S/G.

o WHEN S/G level greater than 25% in one S/G, THEN limit feed flow to that required to maintain level in at least one S/G.

o IF cooldown continues, THEN close both MSIVs.

IF temperature greater than 547°F and rising, THEN dump steam to stabilize and slowly lou,er temperature to 547°F.

R. E. Ginna Nuclear Plant Page 16 of 19 Revision 00

-Appendix D Required Operator Actions Form ES-D-2 3p-Test No.: 1 Scenario No.: 5 Event No.: 7

!vent

Description:

(-T=35 min)

Small Break LOCA, CI fails to occur automatically or manually, SI Pumps B and C fail to start automatically ndications:

PRZR Level lowering PRZR and RCS Pressures lowering Containment Radiation Monitors rising or in alarm (R-11, R-2, R-7, R-29, R-30)

SI occurs on low PRZR Pressure 1750 psig CI valves remain open after SI SI Pump B and C pump status lights remain green

_I 0  :

I flow 0 gpm with R( i pressure < S Time -- --

Position ATC Checks PRZF PORVs And Spray Valves:

0 Verifies both PORVs (PCV-430 and PCV-431C) closed or closes associated PORV Block Valve (MOV-516 or MOV-515) 0 Verifies Auxiliary Spray Valve AOV-296 closed 0 Verifies PRZR Pressure < 2260 psig 0 Verifies Normal Spray Valves PCV-431A(B) closed ATC Secures both RCPs if RCS pressure vs. maximum S/G pressure D/P becomes c 240 psig witli 2 SI Pumps running (CRITICAL CT-E-14)

BOP Verifies both W G pressures stable or rising and > 110 psig ATC Verifies S/G tLibes intact by verifying the following Rad Monitors are providing normal stable readings and are not in alarm 0 Air Ejector Rad Monitors R-47/48 0 S/G Blowdown Rad Monitor R-19 0 Stearr line Rad Monitors R-31 and R-32 SRO/ATC Determines RCS is not intact and transitions to E-1, Loss of Reactor or Secondary Coolant, Step 1.

0 CNMl' area radiation monitors are rising or in alarm o R-2 o R-7 o R-29 o R-30 0 CNMT pressure rising and > 0.5 PSlG CNMT sump A level rising Annunciator C-19, CONTAINMENT SUMP A HI LEVEL ATC Secures both f X P s if RCS pressure vs. maximum S/G pressure D/P becomes

< 240 psig with 2 SI Pumps running R. E. Ginna Nuclear Plant Page 17 of 19 Revision 00

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

-- Event No.: 7 Event

Description:

(-T=35 min)

Small Break LOCA, CI fails to occur automatil:ally or manually, SI Pumps B and C fail to start automatically 0 PRZR Level lowering 0 PRZR and RCS Pressures lowering 0 Containment Radiation Monitors rising or in alarm (R-11, R-2, R-7, R-29, R-30) 0 SI occurs on low PRZR Pressure 1750 psig 0 CI valves remain open after SI SI Pump B and C pump status lights remain green Amlicants Actions or Behavior or rising and 7 110 psig until at least one S/G Narrow Range flow to maintain S/G levels between 25 SRO I Requests RP sample both S/Gs for activity.

I ATC Verifies Steam line rad monitors R-31 and R-32 are not rising or in alarm ATC Monitors P0F;V Status 0 Verifies power available to both PORV Block Valves MOV-515 and MOV-516 I 0 Verifies both PORVs (PCV-430 and PCV-431C are closed Verifies at least one PORV Block Valve is open.

I ATC/BOP I Resets SI CI Reset Pushbutton or determines CI not initiated SRO Dispatches ar A 0 to establish normal shutdown alignment per ATT-17.0, Attachment SD-1 Establishes IP to CNMT Verifies normal power available to Charging Pumps Establishes Charging Flow from RWST SRO/ATC Determines SI should not be terminated.

SRO Determines CIVMT Spray secured and Containment Cooling satisfied.

SRO Determines that RHR pumps should be stopped.

ATC Stops both RHR Pumps and places C/Ss in AUTO SRO Dispatches A 0 to perform ATT-14.6, Attachment RHR Press Reduction Part A.

BOP Verifies S/G piessures stable or rising and > 110 psig.

R. E. Ginna Nuclear Plant Page 18 of 19 Revision 00

- Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 5 Event No.: 7 Event

Description:

(-T=35 min)

Small Break LOCA, CI fails to occur automatically or manually, SI Pumps B and C fail to start automatically Indications:

0 PRZR Level lowering 0 PRZR and RCS Pressures lowering 0 Containment Radiation Monitors rising or in alarm (R-11, R-2, R-7, R-29, R-30)

SI occurs on low PRZR Pressure 1750 psig CI valves remain open after SI SI Pump B and C pump status lights remain green Verifies RCS pressure stable or lowering Determines both Emergency D/Gs can be stopped.

Stops both Emergency D/Gs per ATT-8.1, Attachment D/G Stop.

Verifies at least one recirculation flow path is available per Att-14.5, Attachment RIiR Svstem BOP Verifies at least 2 SW pumps running SRO Dispatches an A 0 to Aux Bldg sub-basement to check for RHR system leakage.

ATC Verifies Aux Bldg radiation normal I BOP Verifies at least one Control Rod Shroud Fan and one Rx Compartment I Cooling Fan running

---+---

I 1 SRO SRO Determines R C S Cooldown And Depressurization Is required and transitions to ES-1.2, Post LOCA Cooldown and Depressurization, Step 1.

End of Scenario Perform EmertJency Plan Classification for final event Expected EAL: Alert, 3.1.2, RCS Leakage > 46 gpm Start Time: -

Stop Time:

R. E. Ginna Nuclear Plant Page 19 of 19 Revision 00