ML050350345

Draft - Section C Operating (Folder 2)

ML050350345
Person / Time
Site:	Limerick
Issue date:	11/15/2004
From:	Jason White Exelon Generation Co
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-352/05-301, 50-353/05-301
Download: ML050350345 (42)

Text

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3 Appendix D Scenario Outline Form ES-D-1 N/A Override flow controller pot to 0 MED280B FIC46-1 R600 Facility: Limerick Scenario No.: 1 Op-Test No.:

4 5

5 5

Examiners:

Operators:

MRDO16F C (RO/

MRC465 M (ALL)

MRC464A C (PRO/

MRC464B C RS)

MAD141D C (PRO/

CRS)

CRS)

(0-1 00%)

Initial Conditions: 4% power, Reactor Startup in progress, "1 B" EHC pump blocked for maintenance Turnover: A Reactor Startup is in progress with GP-2, Normal Plant Startup completed up to and including step 3.4.1 5. Reactor power is approximately 4%. RClC is operating for ST-6-049-230-1, RClC Pump Valve and Flow Test, and RT-6-049-701-1 (step 4.4.30) should be completed within the next hour. !'I B EHC pump is blocked for maintenance, and will be out of service until a new pressure compensator arrives tomorrow. The bypass valve jack is being used to ensure partial bypass valve opening for feedwater stability per GP-2 step 3.3.20.4. The crew must continue power ascension to achieve 4 bypass valves open in preparation for main turbine startup. Control Rod movement is per the Control Rod Move Sheets, with Sequence Step Number 14, Rod Group 8, Control Rod 26-43 the next rod to withdraw (12-48).

Event Type*

R (RO/

CRS)

I (RO/

CRS)

I (ALL)

Event Description Withdraw control rods until 4 bypass valves open CRD flow controller fails downscale in AUTO Loss of 1 BY160 due to underfrequency trip of a series supply breaker (TS)

Control Rod 22-35 inadvertently scrams (TS)

Steam Leak from RClC piping RClC isolation valves fail to close "1 E" SRV fails to open

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39

Attachment to Form ES-D-2

1. SIMULATOR OPERATOR INSTRUCTIONS A.

INITIAL SIMULATOR SETUP J -

ITEM / MALFUNCTION / REMOTE FUNCTION / CONDITION Prepare Simulator per TQ-AA-106-0301, Simulator Training Practices Job Aid Reset Simulator to IC-51 Take out of FREEZE and ensure the following:

Reactor power is approximately 4%

- I B EHC pump handswitch is in Pull-To-Lock

- An INFO tag is hung on the IB EHC pump handswitch with the following information:

IB EHC PUMP OUT OF SERVICE FOR PRESSURE COMPENSATOR REPLACEMENT GP-2 completed up to and including step 3.4.15 is available at the TRIP table Load Scenario ILT05-1 from floppy disk labeled 2005 ILT Scenario Files using A: drive and ensure the following malfunctions are loaded:

MED280B, active 12 minutes the first time the WITHDRAW pushbutton is depressed (trigger I

)

MRDOI 6F for rod 22-35, active 6 minutes after HS-57-191 B is taken to BYPASS (trigger 2)

MRC464A, active immediately MRC464B, active immediately MRC465, active 12 minutes after trigger 2, with a severity of 100% and a ramp time of 5 minutes MAD141 D, active immediately Override 42-1 2605/CS for 1 B EHC pump indicating lamps is ALLOFF, active immediately Override FIC46-I R600 for CRD flow controller setpoint is O, active I O minutes after trigger 1 Annunciators 006 FIRE E l L, E3U, G3L are overridden OFF, active immediately Reset any annunciators that should not be present

Attachment to Form ES-D-2 B. INSTRUCTIONS FOR SIMULATOR OPERATOR EVENT I

Withdraw control rods until 4 bypass valves open II MALFUNCTION / REMOTE FUNCTION / REPORT I I/ I L 4 Ensure trigger I activates when WITHDRAW pushbutton used for the first time, and timers are running. If trigger I does not activate as expected, then manually activate trigger 1.

EVENT 2: CRD flow controller fails downscale in AUTO 1 4 1 MALFUNCTION / REMOTE FUNCTION / REPORT H If requested to investigate failure of 1 B CRD flow control valve, report that the valve looks like its closed, and theres no indication of anything abnormal at the flow control valve.

EVENT 3: Loss of I BY1 60 L-ir--

MALFUNCTION / REMOTE FUNCTION / REPORT H If Equipment Operator / Floor Supervisor are contacted for investigation, wait 5 minutes then report to the crew that there is an underfrequency trip on one of the series supply breakers in the inverter room.

H When the PRO places HS-57-191 B to BYPASS, ensure trigger 2 activates and timers start for malfunctions as appropriate.

EVENT 4: Control Rod 22-35 inadvertently scrams II I/ I

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~

~

~

~

~~

~

MALFUNCTION / REMOTE FUNCTION / REPORT H If asked to investigate at the HCU for 22-35, wait 4 minutes then report to the crew that the A side fuse for the scram pilot valves has blown.

H If Reactor Engineering contacted for 22-35 scram, respond that a recovery plan and ReMA will be developed and brought to the MCR as soon as its ready.

Attachment to Form ES-D-2 L

EVENT 5: Steam leak from RClC piping v

MALFUNCTION / REMOTE FUNCTION / REPORT

)I I

H If asked to investigate alarm at IAC208, wait 4 minutes then report to the crew RClC room temperature as indicated on the Simulator Instructor Console T-I 03 Temperature screen.

If asked to perform T-290, wait 5 minutes then report to the crew RClC room and 309 room temperatures as indicated on the Simulator Instructor Console T-I 03 Temperature screen. Provide updates of temperatures as requested by the crew.

EVENT 6: RClC isolation valves fail to close 1 4 1 MALFUNCTION / REMOTE FUNCTION / REPORT If asked to attempt to close the RClC isolation valves locally, report that the contactor will not seal in at the breaker for either isolation valve.

If asked to manually close the outboard isolation valve at the actual valve location, report that environmental conditions dont permit access to the actual valve location.

EVENT 7: 1 E SRV fails to open ll J I MALFUNCTION / REMOTE FUNCTION / REPORT II II (I

1 H Respond to request for assistance as appropriate.

Afmendix D Reauired OPerator Action Form ES-D-2 Time Op-Test No.

Position Applicant's Actions or Behavior CRS Direct the RO to withdraw control rods until 4 bypass valves are open Scenario No.

1 RO PRO Event No.: I Withdraw rods in accordance with RWM startup sequence sheets Peer check all control rod movements Event

Description:

Withdraw control rods until 4 bypass valves open Appendix D, Page 39 of 39

Appendix D Required Operator Action Form ES-D-2

~

1 v

Op-Test No.

Scenario No.

Event

Description:

CRD flow controller fails downscale in AUTO

~~~

~

CRS RO RO/PRO Direct RO to place the CRD flow controller to MANUAL and attempt to open the flow control valve.

Place CRD flow controller to MANUAL and open the valve to establish normal CRD parameters.

Contact personnel outside MCR to investigate failure of the CRD Flow Control Valve in AUTO.

Event No.:

2 11 Time I Position I Applicant's Actions or Behavior I Ro Recognize failure of CRD flow controller and report the failure to the I CRS.

Appendix D, Page 39 of 39

Appendix D Required Operator Action Form ES-D-2 RO Op-Test No.

Scenario No.

1 Event No.:

3 Event

Description:

Loss of 1 BY1 60 (TS)

Recognize no actual scram condition exists and DO NOT manually scram the reactor Time RO CRS Position I Applicant's Actions or Behavior Reference ARC for I 1 I RECIRC G-3 and monitor Recirculation pump temperatures on BOP DAS monitor using S43.0.D Direct PRO/RO to contact EO/FSV to investigate the cause of the loss of I BY1 60 PRO PRO PRO Reference ARCS for annunciators 122 D12, F-4 (1B RPS & UPS STATIC INVERTER TROUBLE) and 123 D14, F-5 (IB APRM UPS INVERTER TROUBLE), and recognize loss of 1 BY1 60 bus Bypass and restore DWCW per E-I BY160 step 2.4 Bypass and restore PClG per E-I BY1 60 step 2.5 RO CRS I Enter E-I BY160 Recognize Recirculation pump temperatures are returning to normal after DWCW flow is restored CRS I Enter ON-I 13, Loss of RECW CRS Direct the PRO to bypass and restore RECW, DWCW, and PClG per E-I BY160 steps 2.3 through 2.5. NOTE: The crew may also elect to perform step 2.6 to bypass and restore air-to-gas blocks and vents, even though instrument air is not currently backing up instrument gas.

PRO I Bypass and restore RECW per E-lBY160 step 2.3 CRS Enter T.S. LCO 3.6.3 for inoperable PClVs following performance of isolation bypasses per E-I BY 160 and recognize per ACTION a that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> must either restore inoperable valves to OPERABLE status, or isolate each affected penetration by use of at least one deactivated automatic valve secured in the isolation position, or isolate each affected penetration by use of at least one closed manual valve or blind flange. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

RO I Contact EOlFSV to investigate loss of 1 BY1 60 using S94.9.B.

Appendix D, Page 39 of 39

Appendix D Required Operator Action Form ES-D-2 Op-Test No.

Scenario No.

I Event No.:

4 Event

Description:

Control Rod 22-35 inadvertently scrams (TS) / Manual Reactor Scram Time I Position Applicant's Actions or Behavior Reference ARC for annunciator 108 REACTOR, F-4, (ROD DRIFT)

I Ro Recognize control rod 22-35 has scrammed (Blue light lit on full core display) and the rod is at position 00.

-P-RO/PRO Enter ON-I 04, Control Rod Problems Contact EO/FSV to investigate scram of control rod 22-35.

1 CRS Reference TS 3.1.3.1 for Control Rod Operability and determine appropriate action is b.2 I CRS Recognize reactor power is less than 10% rated thermal power and the RWM is not latched Recognize ON-I 04 Attachment 3 requires a manual reactor scram I CRS I CRS Direct the RO to manually scram the reactor Place Reactor Mode Switch to SHUTDOWN CT I RO I CRS Enter T-I 01 if RPV level drops below 12.5 inches; Enter T-I 00 if RPV level does not drop below 12.5 inches.

Verify all control rods fully inserted Direct manually tripping the main turbine Trip the main turbine and ensure generator lockout Direct the RO to maintain RPV level 12.5 to 54 inches using feedwater Verify feedwater aligns to startup level control Provide directions to maintain RPV pressure within a band Appendix D, Page 39 of 39

Appendix D Required Operator Action Form ES-D-2 PRO PRO Op-Test No.

Scenario No.

1 Event No.:

5 Reference ARC for 004 VENT window A-2, A REAC ENCL HVAC PANEL 1AC208 TROUBLE Dispatch an EO to lAC208 to investigate the trouble alarm Event

Description:

Steam leak from RClC piping / RClC isolation valves fail to close/l E SRV fails to open I Ro Reference ARC for 107 REACTOR window F-5, DIV 1 STEAM LEAK DET SYS HI TEMPTTROUBLE I Ro/PRo I CRS I Enter T-I 03, Secondary Containment Control Use only PAMS, FZ level, and EQ PMS parameters for values when reporting RPV level and pressure to the CRS Direct RO/PRO to read RPV level and pressure only on PAMS, FZ lCRS I level, and EQ PMS parameters CRS RO/PRO PRO PRO Direct RO/PRO to perform T-291 for RPV level effects Use T-291 to determine that RPV level instruments being used are not affected by the high RClC temperatures Attempt to close RClC isolation valves HV-49-I F007 and HV I

F008 Recognize failure of RClC isolation valves to close I CRS I Direct T-290, Instrumentation Available for T-I 03/SAMP-2 CT When report received of RClC room high temperature, direct ICRS I isolation of RClC per T-250 PRO PRO Place all 5 ADS valve handswitches to OPEN Recognize 1 E SRV fails to open and report to CRS I Request assistance from EO/FSV/WWM in closing RClC isolation I Ro valves Recognize approaching MSO in 2nd area per T-I03 Table SCC-2 ICRS I and direct RO to fully open all bypass valves I RO I Use bypass valve jack to open bypass valves Recognize 2 areas in Table SCC-2 exceeding MSO temperature lCRS I and enter T-I 12, Emergency Blowdown I CRS I Direct opening all 5 ADS valves I CRS I Direct PRO to open non-ADS SRVs until a total of 5 SRVs are open Appendix D, Page 39 of 39

Appendix D Required ODerator Action Form ES-D-2 PRO RO/PRO (1 Op-Test No.

Open an additional SRV until a total of 5 SRVs are open Control injection into the RPV and stabilize RPV level Scenario No.

I Event No.:

5 i

Event

Description:

Steam leak from RClC piping / RClC isolation valves fail to close/l E SRV fails to open Termination Point:

The scenario will be terminated when the following criteria are met:

1.

An Emergency Blowdown has been performed per T-I 12, Emergency Blowdown, and RPV level has been stabilized Appendix D, Page 39 of 39

Appendix D Scenario Outline Form ES-D-1 Malf.

No.

N/A MCW483B MCW485A MED263D MRR433B MRR434B Facility: Limerick Scenario No.: 2 Op-Test No.:

Event Event Type*

Description N (ALL)

Perform ST-6-001-761-1 I (ALL)

"1 B RECW pump trips, "1A" RECW pump fails to auto start (TS)

I (PRO/

D14 Bus Lockout relay fails, Loss of D14 Bus C (ALL)

"1 B Reactor Recirculation Pump seal failure CRS)

(TS)

(TS)

Examiners:

Operators:

Initial Conditions: 100% power, #3 APRM is inoperable and bypassed Turnover: Reactor power is 100%. #3 APRM is inoperable and bypassed. 1&C has been contacted to begin troubleshooting. The crew is directed to perform ST-6-001-761-1, Main Turbine Bypass Valve Exercising.

Event No.

I 2

3 4

~

MRH171B

~ C:::)

MRH174C C (PRO/

Leakage past "I B o Reactor Recirculation loop isolation valves

• 'I B" Reactor Recirculation piping break "1 B" RHR pump trip "1 C RHR LPCl injection valve fails to close after it opens

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39

Attachment to Form ES-D-2

1. SIMULATOR OPERATOR INSTRUCTIONS A.

INITIAL SIMULATOR SETUP J -

ITEM / MALFUNCTION / REMOTE FUNCTION / CONDITION Prepare Simulator per TQ-AA-106-0301, Simulator Training Practices Job Aid Reset Simulator to IC-50 W Take out of FREEZE and ensure the following:

Reactor power is 100%

1. 3 APRM is bypassed using the joystick on lOC603 A blue Equipment Status Tag is hung on the APRM bypass joystick with the following information:

Equipment: #3 APRM ETT# (NR): R0286435 SYSTEM: 074 UNIT: 1 DATE: 1/10/04 POSITION/CON DITION: BY PASS AUTHORIZED BY: Art Star HUNGBY: AJS REASON: #3 APRM BYPASSED DUE TO BEING INOPERABLE Load Scenario ILT05-2 from floppy disk labeled 2005 ILT Scenario Files using A: drive and ensure the following malfunctions are loaded:

+

MPROOGB, active immediately

+

MCW485A, active immediately

+

+

+

+

+

MCW483B, active 5 minutes after trigger 1 (depressing bypass valve test pb)

MED263D, active I O minutes after trigger 1 MRR433B, active 18 minutes after trigger I MRR434B, active 22 minutes after trigger I MRR441, active 30 minutes after trigger 1, with a severity of 50 gpm and a ramp time of 4 minutes MRR440B, active 6 minutes after trigger 2 (mode switch to S/D), with a severity of 3% and a ramp time of 25 minutes

+

Attachment to Form ES-D-2 II ITEM / MALFUNCTION / REMOTE FUNCTION / CONDITION II J I MRHI 71 B, active 3 seconds after trigger 3 (RHR pump start)

MRHl74C, active 10 seconds after trigger 4 (HV-51-1 FOI7C starts to open) ll 11 1

Reset any annunciators that should not be present B. INSTRUCTIONS FOR SIMULATOR OPERATOR EVENT 1 : Perform ST-6-001 -761 -1, Main Turbine Bypass Valve Exercising II J I MALFUNCTION / REMOTE FUNCTION / REPORT (I

Ensure trigger 1 activates when Bypass Valve Test pushbutton used for the first time, and timers are running. If trigger 1 does not activate as expected, then manually activate trigger 1.

EVENT 2: 1 B RECW pump trip, and failure of IA RECW pump to auto start II J I MALFUNCTION / REMOTE FUNCTION / REPORT If requested to investigate the trip of the 1 B RECW pump, report that everything looks okay at the pump. The breaker for the 1 B RECW pump has tripped due to thermal overload. If asked to investigate the failure of 1A RECW pump to auto start, report that a TRT will be generated to troubleshoot.

EVENT 3: D14 Bus Lockout relay fails / Loss of D14 Bus II MALFUNCTION I REMOTE FUNCTION / REPORT II I/ I If EO/FSV are contacted for investigation, report to the crew that the Lockout relay is tripped for the D14 bus. NOTE: If the crew attempts to contact personnel outside the MCR using the plant page, do not respond.

Attachment to Form ES-D-2 EVENT 4: I B Reactor Recirculation pump seal failure / Leakage past the closed I B RRP isolation valves 1 4 1 MALFUNCTION / REMOTE FUNCTION / REPORT

((--(.Respond to requests for assistance as appropriate I

EVENT 5: 1 By Reactor Recirculation piping break / 1 By RHR pump trip 1 IC RHR LPCl injection valve fails to close after it opens MALFUNCTION / REMOTE FUNCTION / REPORT ll I 1

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If requested to perform SE-10-1, RHRSW radiation monitor resets, and Area Radiation Monitor resets, then load the appropriate scenario files from Ops Training Scenarios/Remotes folder. When timers time out, report to the MCR that actions are complete.

If EO/FSV are contacted for investigation, report to the crew that I B RHR pump breaker has tripped due to overcurrent on all three phases.

If EO/FSV are contacted to investigate HV51-1 FOI 7C, report to the crew that evewthina at the valve and the breaker for the valve appear normal.

Appendix D Required Operator Action Form ES-D-2 Time Op-Test No.

Scenario No.

2 Event

Description:

Perform ST-6-001 -761 -1 Position Applicant's Actions or Behavior CRS Direct the PRO to perform ST-6-001-761-1 Event No.: I I PRO I Perform ST-6-001 -761 -1 RO During performance of ST-6-001 -761 -1, monitor reactivity transient as each bypass valve is opened, and ensure reactor power and pressure are stable before the next valve is tested.

Appendix D, Page 39 of 39

Appendix D Required Operator Action Form ES-D-2 Position PRO Op-Test No.

Scenario No.

2 Event No.:

2 Applicants Actions or Behavior Recognize trip of the 1 B RECW pump and failure of the I A

RECW pump to auto start Event

Description:

1 B RECW pump trip / I A RECW pump fails to auto start CRS PRO RO Time

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Reference TS SR 4.4.4 and recognize sampling required every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> due to conductivity recorder out of service per SR 4.4.4.c.1 Dispatch EO/FSV to investigate trip of 1 B RECW pump and failure of IA RECW pump to auto start Contact Chemistry for Reactor water sampling to meet TS SR 4.4.4 CRS Enter ON-I 13 and direct the PRO to manually start the I A RECW 1 Pump PRO I Manually start 1A RECW pump RO Reference ARC for annunciator 1 12 CLEANUP, G-2, and recognize I A RWCU pump trip. Inform CRS of required TS entry for SR 4.4.4 RO

~~

I Contact EO to ensure RWCU filteddemins are on the hold pumps Appendix D, Page 39 of 39

Appendix D Required Operator Action Form ES-D-2 Time Op-Test No.

Scenario No.

2 Event No.:

3 Position Event

Description:

D14 Bus Lockout relay fails, Loss of D14 Bus (TS)

I CRS

--E-

+

I PRO CRS I PRO I

Applicants Actions or Behavior Recognize loss of D14 4KV bus Enter E-Dl4 procedure Refer to E-Dl44-R-E, E-Dl44-H, E-D144, and E-D144-C-B Dispatch EO/FSV to investigate loss of D14 bus Dispatch EO to perform running check of D l 4 D/G Recognize trip of the 1 B Drywell Chiller and report to the CRS Direct PRO to place 1A Drywell Chiller in service Start 1A Drywell Chiller Reference TS LCO 3.8.3.1 and recognize that (per ACTION a) all Unit 1 Division 4 buses must be re-energized within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Recognize Div 4 RHR and Div 4 Core Spray inoperable Verify 1A or 1 B FPC pump running Verify I A Instrument Air Compressor running Verify 1A RECW pump running Enter SE-12, Loss of Communications for loss of plant page capability Appendix D, Page 39 of 39

Appendix D Required Operator Action Form ES-D-2 Time Op-Test No.

Scenario No.

2 Event No.:

4 Position Applicants Actions or Behavior Event

Description:

1 B Reactor Recirculation Pump seal failures CRS PRO Refer to TS 3.4.3.2 for Reactor Coolant system leakage Recognize failure of #2 seal on I B Reactor Recirculation Pump I PRO I Recognize failure of # I seal on I B Reactor Recirculation Pump RO CRS PRO CRS I PRO Recognize rising drywell pressure Enter OT-101, High Drywell Pressure Ensure Drywell Cooling is maximized and containment inerting is not in progress Direct PRO to perform OT-I 01 section 3.4 to secure I B Reactor Recirculation Pump Reference ARC for 1 12 CLEANUP A-I, I B RECIRC PUMP SEAL STAGE HVLO FLOW I

Reference ARC for 112 CLEANUP A-2, 1 B RECIRC PUMP SEAL LEAKAGE HI FLOW I PRO I Trip 1 B Reactor Recirculation Pump I

Close HV-43-I F031 B, HV-46-115B, and HV-43-1 F023B to isolate the 1 B Reactor Recirculation Pump RO Peer check handswitch manipulations for securing 1 B Reactor Recirculation Pump to ensure correct pump is being secured and isolated.

I Ro Recognize drywell pressure turns after isolation of the 1 B Reactor Recirculation Pump Appendix D, Page 39 of 39

Appendix D Required Operator Action Form ES-D-2 Op-Test No.

Scenario No.

2 Event No.:

5 Event

Description:

Leakage past the 1 B Reactor Recirculation Pump isolation valves /

Reactor Recirculation system piping break RO/CRS Recognize drywell pressure begins to rise again several minutes after isolation of the Reactor Recirculation pump CRS I Direct RWCU isolation per OT-I 01 section 3.1 0 3 PRO CRS Isolate RWCU per OT-101 section 3.10.3 Direct plant shutdown per GP-4, Rapid Plant Shutdown to Hot Shutdown PRO I Transfer house loads per S91.6.B PRO I Runback 1A Reactor Recirculation Pump to minimum RO RO Manually scram the reactor when core flow less than 50%

Place Reactor Mode Switch to SHUTDOWN CRS

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I Enter T-I 01, RPV Control when RPV level drops below 12.5 inches RO Insert SRMs/lRMs RO Verify all control rods full in and report to the CRS CRS I Direct PRO to trip the Main Turbine PRO CRS PRO Trip the Main Turbine and ensure Generator Lockout Reenter T-I 01 and enter T-I 02, Primary Containment Control when drywell pressure exceeds I

.68 psig Recognize HPCl start at I

.68 psig and report to the CRS CRS I Direct the PRO to minimize HPCl injection PRO Place HPCl flow controller to MANUAL and lower speed until injection to the RPV is stopped, while maintaining HPCl speed above 2200 RPM.

CRS PRO When drywell temperature is above 145 deg. F, direct PRO to maximize drywell cooling, bypassing isolation using GP-8.5 Bypass and restore drywell cooling using GP-8.5 CRS Direct RO to maintain RPV level 12.5 - 54 inches using feedwaterkondensate RO

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I Verify feedwater aligns to startup level control RO Maintain RPV level in band 12.5 - 54 inches, or inform CRS if out of Appendix D, Page 39 of 39

Appendix D Required Operator Action Form ES-D-2 I CRS Op-Test No.

Scenario No.

2 Event No.:

5 Direct PRO to spray the suppression pool per T-225 using RHR before Suppression Pool pressure reaches 7.5 psig Event

Description:

Leakage past the 1 B Reactor Recirculation Pump isolation valves /

Reactor Recirculation system piping break I CRS I

I band Recognize on the unsafe side of the Pressure Suppression Pressure Curve (Curve PC/P-3)

Provide RPV pressure control directions to RO, including a pressure ICRS I control band I Ro I RO I Maintain RPV pressure in band, or inform CRS if out of band

~~~

Contact EO/FSV to perform shunt trip resets, RHRSW rad monitor resets and ARM resets per SE-10-1.

CT I PRO I Spray the suppression pool per T-225

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~~

CRS PRO Provide level control directions to RO or PRO with either condensate or low pressure ECCS Spray the drywell per T-225 Direct drywell spray per T-225 when on safe side of the Drywell lCRS 1 Spray Initiation Limit Curve (Curve PC/P-2)

I CRS I Enter T-I 12, Emergency Blowdown Direct the RO and PRO to prevent uncontrolled condensate and/or ICRS I ECCS injection I CRS I Direct the PRO to open 5 ADS valves CT I PRO I Place handswitches for all 5 ADS valves to OPEN Recognize LOCA signal and reenergize instrument buses per SE-I RoPRo I 1 0 I RO I Ensure uncontrolled condensate injection does not occur Take control of low pressure ECCS systems as required to prevent IPR0 I uncontrolled injection I RO/PRO I Control RPV level in band, or inform CRS if out of band Appendix D, Page 39 of 39

Appendix D Reauired Operator Action Form ES-D-2 Termination Point:

The scenario will be terminated when the following criteria are met:

I.

An Emergency Blowdown has been performed per T-I 12, Emergency Blowdown, and RPV level has been stabilized Appendix D, Page 39 of 39

Appendix D Scenario Outline Form ES-D-I Event No.

1 1

2

~

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Facility: Limerick Scenario No.: 3 Malf.

Event No.

Type*

N/A N (ALL)

MCR414C C (RO/

MRMOl9A I (PRO/

CRS)

CRS)

Op-Test No.:

4 4

4 Examiners:

Operators:

MSL559 C (RO/

MEH104B I (ALL)

MEH108 C (ALL)

CRS Initial Conditions: 100% power, "1 K SRV tailpipe temperature is elevated, and is being monitored using RT-6-041-230-1, MSRV Tailpipe Temperature Data Monitoring.

Turnover: Reactor power is 100%. "1 K SRV tailpipe temperature is elevated, and is being monitored using RT-6-041-230-1. Current temperature is 217 deg. F. The crew SDV Valve Exercise Test.

Event Description Perform ST-6-047-200-1 Scram discharge volume drain valve XV47-1 F181 fails closed/ SDV Hiah Level (TSI U/l RHRSW Radiation Monitor fails inoperable fTS)

Reactor Pressure Instrument fails high ATWS - Control Rods fail to scram (Hydraulic Lock)

SLC piping rupture EHC Turbine Load Set runs back to minimum Main Turbine Bypass Valves fail closed

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39

Attachment to Form ES-D-2 I. SIMULATOR OPERATOR INSTRUCTIONS A.

INITIAL SIMULATOR SETUP J -

ITEM / MALFUNCTION / REMOTE FUNCTION / CONDITION H Prepare Simulator per TQ-AA-106-0301, Simulator Training Practices Job Aid Reset Simulator to IC-50 H Take out of FREEZE and ensure the following:

Reactor power is 100%

1 K SRV tailpipe temperature is approximately 217 deg. F. and stable Ensure two stopwatches (with current cal stickers) are available H Load Scenario ILT05-3 from floppy disk labeled 2005 ILT Scenario Files using A: drive and ensure the following malfunctions are loaded:

+

MCR414C, active immediately when the SDV vent and drain valve test is performed (trigger I)

+

Annunciator 107 REACTOR C-3 to ON, 5 minutes after trigger I

+

MRMOl9A to 0, active I I minutes after trigger 1

+

MV1234A, active 18 minutes after trigger I

+

MRD556, active immediately

+

MSL559, active 3 minutes after Reactor Mode Switch placed in SHUTDOWN (trigger 2)

MEHI 04B, active 15 minutes after trigger 2 MEHI 08, active 20 minutes after trigger 2 with a ramp time of I O minutes

+

+

H Reset any annunciators that should not be present

Attachment to Form ES-D-2 B. INSTRUCTIONS FOR SIMULATOR OPERATOR L

EVENT 1 : Perform ST-6-047-200-1, SDV Valve Exercise Test / Scram discharge volume drain valve XV47-1 F181 fails closed/ SDV High Level MALFUNCTION / REMOTE FUNCTION / REPORT II J I Ensure trigger I activates when SDV test pushbuttons are depressed. If trigger 1 does not activate as expected, then manually activate trigger 1.

If EO/FSV requested to investigate failure of XV47-1 F181, report that the valve operator has an air leak. The FIN team will be contacted to try to repair the air line to the valve. If asked to manually open the valve, report that the handwheel spins freely, but does not operate the valve.

H If EO/FSV requested to report SDV level from the AER, wait 4 minutes, then report that all four SDV level indicators are reading 14% and look like their rising very slowly.

EVENT 2: RHRSW Radiation Monitor fails downscale 1 4 1 MALFUNCTION / REMOTE FUNCTION / REPORT H If EO/FSV are contacted for investigation, report to the crew that the Unit 1 RHRSW radiation monitor indicates downscale in the Aux. Equipment Room.

EVENT 3: Reactor pressure instrument PT42-NO78A fails high II MALFUNCTION / REMOTE FUNCTION / REPORT II I

H If EO/FSV are contacted for investigation, report to the crew that RPV pressure instrument PT42-NO78A indicates upscale in the Aux. Equipment Room.

If asked which AER panel PT42-NO78A is on, report that it is on 1OC609

Attachment to Form ES-D-2 J

EVENT 4: ATWS / SLC piping rupture / EHC Load Set runback to minimum /

Main Turbine Bypass Valves fail closed MALFUNCTION / REMOTE FUNCTION / REPORT H If asked to perform T-221, wait 1 I minutes, then toggle remote function RTRO51 to bypass, then report T-221 complete in the Unit 1 AER.

H If asked to perform T-217:

H Wait 12 minutes, then toggle remote functions RTR181 and RTR 303 to bypass. Call the MCR and report that T-217 steps 4.1.I through 4.1.6 are complete and this notification is being made per step 4.1.7.

If requested to perform draining of SDV per steps 4.1.I I through 4.1.13, toggle remote function RTRI 92, then call the MCR and report that SDV draining is in progress.

H Three minutes after reporting that SDV draining is in progress, call the MCR and report that all four SDV level indicators in the AER are indicating less than 62%.

If requested to stop draining the SDV and pull jumpers to initiate a reactor scram, then perform the following in this sequence:

1. Toggle remote function RTR192 to NORMAL

2. Insert malfunction MRP029D

3. Remove malfunction MRD556

4. Toggle remote function RTRl81 to NORMAL

5. Wait 20 seconds, then remove malfunction MRP029D

6. Call the MCR and report that the jumpers have been removed per steps 4.2.2 through 4.2.5 H If asked to perform T-251, wait 5 minutes, then call the MCR and ask them to confirm that HV-55-1 F006 is closed. After the MCR reports the valve is closed, then toggle remote function RTR309 to OPEN, then notify the MCR that T-251 is complete on Unit 1.

H If asked to perform T-270 in the AER, then load scenario T-270 Terminate and Prevent with seven minute time delay from Ops Training Scenarios/Remotes folder. When timers time out, report to the MCR that T-270 is complete in the Unit I AER.

If asked to perform SE-10-1 shunt trip resets, RHRSW radiation monitor resets, and Area Radiation Monitor resets, then load the appropriate scenario files from Ops Training Scenarios/Remotes folder. When timers time out, report to the MCR that actions are complete.

Respond as appropriate for other requests for assistance.

Appendix D Required ODerator Action Form ES-D-2 RO/PRO Op-Test No.

Scenario No.

3 Event No.:

1 Obtain two stop watches and coordinate the starting of the stop watches with the depressing of both TEST pushbuttons Event

Description:

Perform ST-6-047-200-1 SDV Valve Exercise Test RO/PRO RO/PRO Time Recognize that XV47-1 F181 fails to reopen Notify CRS of failure of XV47-1 F181 Position I Applicant's Actions or Behavior CRS Direct the RO and PRO to Perform ST-6-047-200-1 SDV Valve Exercise Test CRS Enter TS 3.1.3.1 for inoperable SDV drain valve and determine per ACTION d. that the inoperable valve must be restored to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

RO/PRO I Contact EO/FSV to monitor SDV level indicators in the AER RO Reference ARC for 107 REACTOR C-3, SCRAM DISCH VOLUME NOT DRAINED CRS I Enter OT-105, Scram Discharge Volume High Level RO/PRO I Request EO/FSV to investisate XV47-I F181 CRS I Direct EO/FSV to attempt to manually open XV47-I F181 Appendix D, Page 39 of 39

i-Time Appendix D Required Operator Action Form ES-D-2 Position Applicant's Actions or Behavior PRO Recognize failure of Unit 1 RHRSW Radiation Monitor downscale Op-Test No.

Scenario No.

3 Event No.:

2 CRS Event

Description:

RHRSW Radiation Monitor fails downscale Reference ODCM Section 3.2, recognize ACTION 101 is required.

I I

I Ro Reference ARC for 01 1 SERV WTR B, C-4, RHRSW RAD MONITOR HI-HI / INOP / DNSCL Appendix D, Page 39 of 39

Appendix D Reauired ODerator Action Form ES-D-2 Time Op-Test No.

Position Applicants Actions or Behavior RO RO Recognize and report to the CRS that the Reactor Hi Press Trip annunciator has alarmed, and no half scram has been generated Use multiple indications to validate that actual RPV pressure is not above the RPS scram setpoint.

Scenario No.

3 Event No.:

3 RO CRS Recognize that a half-scram was not generated Direct the RO to attempt to insert a half-scram using the A RPS manual pushbutton that was not used for the first attempt I

RO RO Reference ARCS for annunciator 107 G-I REACTOR HI PRESS 1 TRIP Manually arm and depress the A2 or A I RPS manual pushbutton Recognize that a half-scram was not generated I CRS I Enter OT-I 17, RPS Failures I Determine which instrument has caused the Reactor Hi Press Trip I RoPRo alarm I CRS I Direct the RO to attempt to insert a half-scram on the A RPS side I Manually arm and depress the A I or A2 RPS manual pushbutton I CRS I Direct RO to manually scram the reactor I Place the reactor mode switch in SHUTDOWN Appendix D, Page 39 of 39

Appendix D Required Operator Action Form ES-D-2 Time Op-Test No.

Position Applicants Actions or Behavior Scenario No.

3 Event No.:

4 RO CRS RO Event

Description:

ATWS / SLC piping rupture / EHC Load Set runback to minimum / Main Turbine Bypass Valves fail closed Recognize no control rod motion, and report to the CRS Enter T-101, RPV CONTROL due to scram condition with power above 4%

Place reactor mode switch in SHUTDOWN CRS PRO Direct trip of both Reactor Recirculation pumps Trip both Reactor Recirculation pumps I Insert SRM~/IRM~

CT I CRS RO CRS RO Insert control rods manually with RWM bypassed Direct performance of T-217, RPS/ARI Reset and Backup Method of Draining Scram Discharge Volume Perform T-217 with EO to insert all control rods (rod insertion will actually occur later)

I Direct RRCS initiation RO CRS I Manually initiate RRCS After SLC initiation, recognize SLC is not injecting to the RPV Direct the RO to secure all three SLC pumps I CRS RO CRS CRS Direct PRO to runback both Reactor Recirculation pumps to minimum Manually secure all three SLC pumps Direct performance of T-209 to inject SLC Enter T-I 17, LEVEL/POWER CONTROL I PRO I Runback both Reactor Recirculation Dumps to minimum CT PRO Inhibit auto ADS CRS Direct performance of T-221 to maintain MSlVs open I CRS Direct the RO to manually insert control rods and bypass RWM as necessary I CRS I Direct auto ADS inhibited Appendix D, Page 39 of 39

Appendix D Required Operator Action Form ES-D-2 PRO/RO Op-Test No.

Scenario No.

3 Event No.:

4 Perform T-270 to terminate and prevent HPCI, RHR, Core Spray injection (PRO) and Condensate/Feedwater (RO)

Event

Description:

ATWS / SLC piping rupture / EHC Load Set runback to minimum / Main Turbine Bypass Valves fail closed RO Time 1 Position I

Applicant's Actions or Behavior Reinject with condensate/feedwater to maintain RPV level in band as directed by CRS Direct performance of T-270 to terminate and prevent injection to CRS I reduce RPV level to below -50 inches CRS RO RO CT Direct PRO to control pressure using SRVs between 990-1096 psig Recognize Main Turbine trip Recognize Bypass Valves failing closed and notify PRO/CRS PRO CRS Provide direction to the RO to reinject as necessary to maintain CRS I RPV level in a band that is above -129 and at or below -50 inches Recognize suppression pool temperature at or above 110 deg. F.

Direct performance of T-270 to terminate and prevent injection PRO/RO CRS I Direct performance of T-251, Establish a HPCI Injection Flowpath Via Feedwater Only Perform T-270 to terminate and prevent HPCI, RHR, Core Spray injection (PRO) and Condensate/Feedwater (RO)

I RO I Recognize RPV pressure rising and report to CRS RO CRS Recognize control rods inserted following performance of T-217 Exit T-117, LEVEL/POWER CONTROL Enter T-I 02, Primary Containment Control when suppression pool CRS I temperature exceeds 95 deg. F.

CRS RO Give RO a level band above the top of active fuel (>-I61 inches)

Restore RPV level above -1 61 inches CT CRS RO Direct RO to reinject when RPV level is below -161, or SRV is closed and DW pressure is 4. 6 8 psig, or power is <4%, or SP temperature is less than 1 I O deg F.

Reinject with condensate/feedwater to maintain RPV level in band as directed by the CRS I CRS I Re-enter T-1 01, RPV CONTROL, RC/L leg

Appendix D Required Operator Action Form ES-D-2 Termination Point:

The scenario will be terminated when the following criteria are met:

1.

2.

All control rods are fully inserted RPV level is being maintained above the top of active fuel Appendix D, Page 39 of 39

Appendix D Scenario Outline Form ES-D-1 No.

1 1

2 3

3 Facility: Limerick Scenario No.: 4 Op-Test No.:

No.

I Type*

Description MV1231 B MHP452 MHP453 CRS) isolation/trip of HPCl MSW489B Override close MRR507A I (ALL)

C (PRO/

RPV instrument line break, XV42-1 F045B closes causing Division 2 LOCA signal (TS)

HPCl Injection valves will fail to reopen after initial HS05-102C to Examiners:

Operators:

I (PRO/

CRS)

M (ALL)

C (ALL)

Initial Conditions: 83% power, ST-6-052-232-1, B Loop Core Spray Pump, Valve and Flow Test is in progress.

"1A" Reactor Recirculation MG Set fails to runback Feedwater line rupture inside Primary Containment "B" Feedwater line isolation valve fails to close Turnover: Reactor power is 83% following a rod pattern adjustment. Reactor Engineering is completing a ReMA. Power restoration will resume within the next hour.

ST-6-052-232-1, B Loop Core Spray Pump, Valve and Flow Test is in progress and has been completed up to and including step 4.7.21. "1 D" Core Spray pump has been running for 20 minutes of its required 45 minutes for step 4.7.22.

4 4

4 5

Event I Malf.

I Event I Event MFW252B (0-1 00%)

Override HS41-1 F032B to fail "as-is" MAD146B MAD 146E MAD1 51 D C (PRO/

CRS)

"1 E" SRV downcomer leak c (PRO/ I Y K l SRV opens CRS)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39

Attachment to Form ES-D-2

1. SIMULATOR OPERATOR INSTRUCTIONS A.

INITIAL SIMULATOR SETUP J

ITEM / MALFUNCTION / REMOTE FUNCTION / CONDITION W Prepare Simulator per TQ-AA-I 06-0301, Simulator Training Practices Job Aid Reset Simulator to IC-52 Take out of FREEZE and ensure the following:

Reactor power is approximately 83%

I D Core Spray pump is operating in full flow test through HV52-I F015B rn

+

+

+

+

Load Scenario ILTO5-1 from floppy disk labeled 2005 ILT Scenario Files using A: drive and ensure the following malfunctions are loaded:

MV1231 B, active 3 minutes after trigger I (manually activated)

MSW489B active 5 minutes after start of OB ESW pump (trigger 2)

MHP452, active 1 minute after HPCl manual isolation pushbutton depressed (trigger 3)

MHP453, active 1 minute after trigger 3 MRR507A, active immediately MRR506A, active immediately after IC Condensate pump trip (trigger 4)

MFW252B ( I OO%), active 30 minutes after trigger 1 with a ramp time of 4 minutes MRR441 (300 gpm), active 30 minutes after trigger 1 with a ramp time of 3 minutes MAD146B, active 40 minutes after trigger I MAD146E, active 40 minutes after trigger 1 Override HS05-102C (I C Cond pump handswitch) to CLOSE, active 17 minutes after trigger 1 Override HS41-1 F032B (Feedwater Line B Reactor Inlet Valve) to ALLOFF, active immediately Reset any annunciators that should not be present

Attachment to Form ES-D-2 B.

INSTRUCTIONS FOR SIMULATOR OPERATOR EVENT I

RPV instrument line break, closure of XV42-1 F045B / HPCl Injection valves will fail to reopen after initial isolation/trip of HPCl MALFUNCTION / REMOTE FUNCTION / REPORT II I/ I If asked to investigate excess flow check valve panel 10C218, wait 4 minutes, then report that XV42-1 F045B is indicating closed.

W If asked to investigate the failure of the HPCl injection valves to reopen, report that the contactors will not seal in at the breaker for either valve. If asked to open the valves manually, report that the valves are stuck and cannot be opened.

EVENT 2: OB ESW Pump trip 1 4 1 MALFUNCTION I REMOTE FUNCTION / REPORT v

11 I

If requested to investigate failure of OB ESW pump, report that the pump breaker has an overcurrent trip flag up on the C phase EVENT 3: IC Condensate Pump discharge valve strokes closed due to a short in the control switch / IA Reactor Recirculation Pump MG set fails to runback II MALFUNCTION I REMOTE FUNCTION / REPORT II I

II 11 I

Respond as appropriate to requests for assistance

Attachment to Form ES-D-2 EVENT 4: Feedwater line rupture inside Primary Containment / B Feedwater line isolation valve fails to close / 1 K SRV opens II J I MALFUNCTION / REMOTE FUNCTION / REPORT W If requested to support closure of HV41-1 F032B, wait 5 minutes, then report that all attempts to close the valve have been unsuccessful.

Electrical and Mechanical Maintenance personnel have been contacted and are working on the problem.

H If requested to support start of 1 B CRD pump for T-240, report that there is a significant oil leak on the 1 B CRD pump. If the crew decides to start the pump anyway, wait one minute after pump start, then insert malfunction MCR412B and report the pump has tripped W If requested to pull fuses for 1 K SRV per OT-I 14, wait until RPV pressure is 700 psig, then toggle remote function RAD213 to OUT, then remove malfunctions MAD146B and MAD146E. Call the MCR and inform them that the fuses have been removed for the 1 K SRV per OT-I 14.

H Respond as appropriate to requests for assistance EVENT 5: IE SRV downcomer leak ll MALFUNCTION / REMOTE FUNCTION / REPORT II I

L H Respond as appropriate for requests for assistance c

Amendix D Reauired Operator Action Form ES-D-2 RO/PRO Op-Test No.

Scenario No.

4 Event No.:

1 Recognize excess flow check valve actuated and reference ARC for annunciator 112 CLEANUP, E-5 EXCESS FLOW CHECK VALVE OPERATED PANEL C218 Event

Description:

RPV instrument line break, closure of XV42-1 F045B / HPCl Injection valves will fail to reopen after initial isolationltrip of HPCl RO Time Recognize power rise and take immediate operator action to reduce reactor power below initial pre-transient power level Position I Applicants Actions or Behavior PRO PRO Reclose D12 instrument bus breaker 52-20224KS per SE-10 Recognize 1 B RHR pump and 1 B Core Spray pump are running PRO I Recognize HPCl is injecting RO RO Send an EO/FSV to investigate at panel 1 OC218 Send an EO to perform Division 2 shunt trip resets per SE-10-1,

reset RHRSW rad monitor, and reset RE ARMS CRS I Direct PRO to secure HPCl injection PRO Either manually isolate HPCl using manual isolation pushbutton, or minimize HPCl injection by placing HPCl flow controller to MANUAL and reducing HPCl pump speed until injection is stopped, with HPCl speed still above 2200 rpm.

CRS I Direct PRO to secure I B RHR pump and 1 B Core Spray pump RO I Send an EO to reset RDCS inop RO CRS Send an EO to perform running checks of D12 D/G Reference TS LCO 3.6.3 and TRM Table 3.6.3-1 to determine that per LCO 3.6.3 ACTION b.2 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the excess flow check valve line must be isolated (this is met by the valve being closed) and the associated instrument declared inoperable, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Appendix D, Page 39 of 39

Appendix D Required Operator Action Form ES-D-2 Position PRO PRO Op-Test No.

Scenario No.

4 Event No.:

2 Applicants Actions or Behavior Recognize trip of the OB ESW pump Recognize D12 D/G running without cooling water Event

Description:

OB ESW Pump trip CRS PRO Time Direct PRO to start OD ESW pump or secure D12 D/G Start OD ESW pump or secure D12 D/G RO I Contact EO/FSV to investigate trip of the OB ESW pump CRS Reference TS LCO 3.7.1.2 and determine that B loop of ESW is not operable, and per ACTION A.l the OB ESW pump must be restored to OPERABLE status within 45 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Appendix D, Page 39 of 39

Appendix D Required Operator Action Form ES-D-2 II IRO Op-Test No.

Recognize IC Condensate Pump discharge valve is stroking closed and that the pump will trip when the valve is fully closed Scenario No.

4 Event No.:

3 RO PRO CRS Recognize trip of 1 C Condensate Pump Recognize 1A Reactor Recirculation Pump MG set failed to automatically runback following condensate pump trip Direct PRO to manually runback 1 A Reactor Recirculation Pump MG set to match 1 B Reactor Recirculation Pump MG set speed (approximately 42%)

I CRS Enter OT-I 04, Unexpected/Unexplained Positive or Negative Reactivity Insertion RO CRS RO/PRO RO/PRO I CRS I Request the RO to print out a Control Rod Position Report Print out a Control Rod Position Report and determine all control rods are in their expected positions Reference GP-5 Appendix 3, section 3.1, Response to Unintentional Drop in Power Contact WWM/EO/FSV to investigate failure of I A Reactor Recirculation Pump MG set to automatically runback Contact WWM/EO/FSV to investigate inadvertent closure of 1 C Condensate Pump discharge valve Appendix D, Page 39 of 39

Appendix D Required Operator Action Form ES-D-2 Op-Test No.

Scenario No.

4 Event No.:

4 Event

Description:

Feedwater line rupture inside Primary Containment / B Feedwater line isolation valve fails to close / 1 K SRV Opens Position Time Applicants Act ions or Behavior Recognize rising drywell pressure Manually scram the reactor, or recognize reactor scram and place Reactor Mode Switch in SHUTDOWN RO/PRO RO CRS Enter T-I 01, RPV Control when RPV level drops below 12.5 inches or drywell pressure exceeds 1.68 psig RO Insert SRMs/lRMs Verify all control rods full in and report to the CRS RO Direct PRO to trip the Main Turbine Trip the Main Turbine and ensure Generator Lockout Reenter T-101 if appropriate and enter T-102, Primary Containment Control when drywell pressure exceeds 1.68 psia CRS I

I RO Recognize high feedwater flow at pressure below RPV pressure Recognize RClC flow with discharge pressure below RPV pressure

+

RO/PRO Report feedwater line break to the CRS Direct RO to close HV41-I F032B CRS RO

~~

Attempt to close HV41-1 F032B and report to the CRS the failure of the valve to close RO/PRO +

Request assistance from WWM/EO/FSV to close HV41-1 F032B When drywell temperature is above 145 deg. F, direct PRO to maximize drywell cooling, bypassing isolation using GP-8.5 I PRO Bypass and restore drywell cooling using GP-8.5 Direct the PRO to restore HPCl to service I CRS Recognize HPCl injection valves fail to reopen Contact WWM/EO/FSV for assistance in opening HPCI injection valves locally I CRS Direct the PRO to secure HPCl to minimize inventow loss I PRO Isolate HPCI Appendix D, Page 39 of 39

Appendix D Required Operator Action Form ES-D-2 RO/PRO CRS Op-Test No.

Recognize 1 K SRV inadvertently opens Enter OT-114, Inadvertent Opening of a Relief Valve Scenario No.

4 Event No.:

4 PRO CRS Event

Description:

Feedwater line rupture inside Primary Containment / B Feedwater line isolation valve fails to close / 1 K SRV Opens Close the MSlVs when directed by the CRS Direct fuses removed for I K SRV per OT-I14 Time I Position I Applicants Actions or Behavior ROJPRO CRS I CRS I Direct RO to maximize CRD injection per T-240 Recognize 1 K SRV closed and report to the CRS Recognize RPV level cannot be maintained above -1 61 and enter T-111, Level Restoration IRO PRO CRS

~

~ _ _ _ _ _

Eontact EO to support maximizing CRD injection per T-240 Start RHWCS pumps as requested by the CRS Direct all low pressure ECCS subsystems aligned to the reactor before reaching -1 61 inches RPV level I CRS I Direct RO to inject SLC I RO I Manually start all three SLC pumps I CRS Provide RPV pressure control directions to RO, including a pressure control band I R O IMaintain RPV pressure in band, or inform CRS if out of band I CRS 1 Direct closing the MSlVs prior to exceeding 100 deg/hr cooldown

/-cRs

~

~

Direct PRO to spray the suppression pool per T-225 using RHR r

before Suppression Pool pressure reaches 7.5 psig

~~

~~

E O

--Epray the suppression pool per T-225 using RHR I CRS I Direct PRO to place 2 RHR/CS subsystems in service I

Realign all low pressure ECCS subsystems for injection before reaching -1 61 inches RPV level I PRO I Report to the CRS when RPV level is at the top of active fuel (-161)

I CRS I Enter T-I 12, Emergency Blowdown I CRS I Direct the PRO to open 5 ADS valves CT I PRO I Place handswitches for all 5 ADS valves to OPEN Appendix D, Page 39 of 39

Appendix D Required Operator Action Form ES-D-2 PRO CRS Op-Test No.

Scenario No.

4 Event No.:

4 Recognize 1 K SRV did not open due to its fuses being pulled Direct PRO to open non-ADS SRVs until a total of 5 SRVs are open Event

Description:

Feedwater line rupture inside Primary Containment / B Feedwater line isolation valve fails to close / 1 K SRV Opens Time I Position I Applicants Actions or Behavior I PRO I Open an additional SRV until a total of 5 SRVs are open Appendix D, Page 39 of 39

Appendix D Required Operator Action Form ES-D-2 RO/PRO CRS PRO Op-Test No.

Scenario No.

4 Event No.:

5 Recognize rapid rise in drywell pressure Recognize suppression pool pressure is above drywell pressure Ensure ECCS injection and report to the CRS when RPV level is above -1 61 inches.

I Ro Recognize LOCA signal and reenergize instrument buses per SE-I Ro/PRo 110

~~

Contact EO/FSV to perform shunt trip resets, RHRSW rad monitor resets and ARM resets per SE-10-1.

CT Provide level control directions to RO or PRO with low pressure I CRS I ECCS PRO CRS PRO RO/PRO Spray the Suppression Pool per T-225 Direct drywell spray per T-225 when on safe side of the Drywell Spray Initiation Limit Curve (Curve PC/P-2)

Spray the drywell per T-225 Control RPV level in band, or inform CRS if out of band

~~

I CRS I Direct Suppression Pool Spray per T-225 Termination Point:

The scenario will be terminated when the following criteria are met:

1.

An Emergency Blowdown has been performed per T-I 12, Emergency Blowdown, and RPV level has been stabilized Appendix D, Page 39 of 39