Latest revision as of 19:57, 11 March 2020

Text

Initial Exam 2010-301 Draft Simulator Scenarios
	ML102520123
Person / Time
Site:	Browns Ferry
Issue date:	08/16/2010
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	50-259/10-301, 50-260/10-301, 50-296/10-301 50-259/10-301, 50-260/10-301, 50-296/10-301
	Download: ML102520123 (166)
	v • d • e

Appendix D Scenario Outline Form ES-D-1 Facility: Browns Ferry NPP Scenario No.: 3-24 Op-Test No.: ILT 1006 SRO:

Examiners: Operators: ATC:

BOP:

Initial Unit 3 is at 5 to 6% power with IRM E out of service. Unit 1 and 2 are at 100% power.

Conditions: Unit startup is in progress per 3-GOI-100-1A. At step 67 to raise reactor power with rods to 8%. Continue unit startup to Mode 1.

Turnover: A Severe Thunder Storm Warning has been issued for Limestone County for the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Event Event No. Malf. No. Type* Event Description N-BOP 1 Perform step 71 of 3-GOI-100-1A and other steps as directed N-SRO R-ATC 2 Raise power with rods to 8%

R-SRO TS-SRO 3 rd05 Uncoupled Control Rod C-ATC C-BOP 4 ms01 Steam Seal Regulator failure C-SRO TS-SRO 5 hp08 HPCI Steam leak w/ auto isolation failure C-BOP C-ATC 6 rfpt c RFPT C trips C-SRO 7 vacuum loss M-All Loss of vacuum causes a loss of feedwater and pressure control 8 loca M-All Loss of High pressure injection with a LOCA, ATWS, and TAF

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

Appendix D Scenario Outline Form ES-D-1 Critical Tasks

1. ADS inhibited before ADS actuates

2. With a reactor scram required and the reactor not shutdown:

Inserts control rods, to prevent exceeding the primary containment design limits

Inject boron (prior to exceeding 110°F SP temperature)

3. During an ATWS with emergency depressurization required, injection has been stopped and prevented, with the exception of RCIC, SLC, and CRD, into the RPV until reactor pressure is below Minimum Alternate RPV Flooding Pressure(MARFP)

4. ATWS with power >5%, injection has been stopped and prevented, with the exception of RCIC, SLC, and CRD, into the RPV until RPV level is below -50 to establish a lower limit

5. Emergency depressurizes when RPV level cannot be restore and maintained above -180". Emergency depressurization is initiated before level reaches -200"

6. When RPV pressure is below MARFP, injection reestablished to maintain RPV level above -180

7. Manually isolates HPCI before Max Safe Operating Value is exceeded.

3-24 Rev 0 Page 3 of 52 With the unit at 5 to 6% power, the ATC will continue power ascension with rods to 8% and the BOP operator will perform actions in 3-GOI-100-1A as directed by the Unit Supervisor.

The first rod to 48 will fail the coupling check. When actions are taken to couple the rod per 3-AOI-85-2, the rod will couple and power ascension may continue. SRO should refer to Tech Spec 3.1.3 for uncoupled rod. Follow up question after scenario for Tech Spec call if rod failed to couple. Tech Spec 3.1.3 Condition C.

The Steam Seal Regulator will fail causing a loss of sealing steam. Off gas flow will increase and vacuum will slowly degrade. The BOP operator can restore seal steam by taking manual control of the steam seal regulator bypass valve. Off gas flow will slowly return to normal and vacuum will quickly recover.

HPCI steam leak will develop and HPCI will fail to auto isolate. The BOP operator will isolate HPCI and stop the steam leak. EOI-3 will be entered on HPCI room temperature. With HPCI Inoperable, the SRO will evaluate Tech Spec 3.5.1 and enter condition C and Tech Spec 3.6.1.3 Condition B. With HPCI Inoperable, mode change can not be made.

After failure of HPCI, RFPT C will trip. The ATC will take control of RFPT B and raise discharge pressure in order to restore level to the normal operating band or he will need to insert a manual reactor scram if unable to recover level. RFPT B is idling at 600 RPM at the start of the scenario; speed will need to be raised to about 3400 RPM for injection to the reactor.

Once the level is stable on RFPT B or if the reactor is scrammed, a lighting strike at the CCW Capacitor Banks will trip all running Circ Water Pumps and create a loss of condenser vacuum. The vacuum loss will trip the RFPT and isolate bypass valves. The crew will attempt to scram the reactor but an electrical ATWS will exist and no rod motion will occur. Pressure control will be on SRVs and rods can be inserted manually per appendix 1D. When RCIC is started it will trip and will be unavailable. Level will lower to TAF, the SRO will determine that Reactor Level can not be restored and maintained above -180 inches. Once this determination is made the crew will transition to ED. Injection sources will be terminated and prevented and 6 ADS valves will be opened. Once Reactor Pressure lowers to the MARFP pressure of 190 psig, injection can commence with low pressure systems to restore Reactor level to the prescribed level band.

3-24 Rev 0 Page 4 of 52 VIII. Console Operator Instructions A. Scenario File Summary

1. File: batch and trigger files for scenario 3-24 Batch NRC201024

steam seal failure imf ms01 (e1 0) imf mc04 (e1 0) 100

uncoupled control rod imf rd05r0235

rfpt c trip ior zdihs03176[1] (e10 0) trip

hpci steam leak ior xa554c[10] alarm_off imf hp09 imf hp08 (e5 0) 10 120

loss of vacuum imf mc02a (e30 0) imf mc02b (e30 0) imf mc02c (e30 0) imf rp07 (e30 0) imf rp14a (e30 0) imf rp14b (e30 0) ior zdihs661a[3] (e30 0) open ior zlohs661a[2] (e30 0) off imf hp04 ior zdihs7316a[2] auto ior zdihs719a[1] (e29 0) trip trg e29 nrc2010718open imf th22 (e30 30) 100 imf th21 (e30 150) 0.8 600 imf rc08

rps fuses out and in trg 20 = bat nrc201024rpsout trg 21 = bat nrc201024rpsin

3-24 Rev 0 Page 5 of 52 Batch NRC201024rpsout mrf rp05a (none 60) out mrf rp05c (none 120) out mrf rp05e (none 180) out mrf rp05g (none 240) out mrf rp05b (none 300) out mrf rp05d (none 360) out mrf rp05f (none 420) out mrf rp05h (none 480) out Batch NRC201024rpsout mrf rp05a (none 0) in mrf rp05c (none 30) in mrf rp05e (none 60) in mrf rp05g (none 90) in mrf rp05b (none 120) in mrf rp05d (none 150) in mrf rp05f (none 180) in mrf rp05h (none 210) in RCIC Start Trigger zdihs718a[2].ne.1 IX. Console Operators Instructions Scenario 3-24 DESCRIPTION/ACTION Simulator Setup manual Reset to IC 183 Simulator Setup Load Batch Bat nrc201024 Simulator Setup manual Bypass IRM E Simulator Setup Verify Batch file loaded RCP required (Start up) - Provide marked up copy of 3-GOI-100-1A

3-24 Rev 0 Page 6 of 52 X. Scenario Summary:

With the unit at 5 to 6% power, the ATC will continue power ascension with rods to 8%

and the BOP operator will perform actions in 3-GOI-100-1A as directed by the Unit Supervisor.

The first rod to 48 will fail the coupling check. When actions are taken to couple the rod per 3-AOI-85-2, the rod will couple and power ascension may continue. SRO should refer to Tech Spec 3.1.3 for uncoupled rod. Follow up question after scenario for Tech Spec call if rod failed to couple. Tech Spec 3.1.3 Condition C.

The Steam Seal Regulator will fail causing a loss of sealing steam. Off gas flow will increase and vacuum will slowly degrade. The BOP operator can restore seal steam by taking manual control of the steam seal regulator bypass valve. Off gas flow will slowly return to normal and vacuum will quickly recover.

HPCI steam leak will develop and HPCI will fail to auto isolate. The BOP operator will isolate HPCI and stop the steam leak. EOI-3 will be entered on HPCI room temperature.

With HPCI Inoperable, the SRO will evaluate Tech Spec 3.5.1 and enter condition C and Tech Spec 3.6.1.3 Condition B. With HPCI Inoperable, mode change can not be made.

After failure of HPCI, RFPT C will trip. The ATC will take control of RFPT B and raise discharge pressure in order to restore level to the normal operating band or he will need to insert a manual reactor scram if unable to recover level. RFPT B is idling at 600 RPM at the start of the scenario; speed will need to be raised to about 3400 RPM for injection to the reactor.

Once the level is stable on RFPT B or if the reactor is scrammed, a lighting strike at the CCW Capacitor Banks will trip all running Circ Water Pumps and create a loss of condenser vacuum.

The vacuum loss will trip the RFPT and isolate bypass valves. The crew will attempt to scram the reactor but an electrical ATWS will exist and no rod motion will occur. Pressure control will be on SRVs and rods can be inserted manually per appendix 1D. When RCIC is started it will trip and will be unavailable. Level will lower to TAF, the SRO will determine that Reactor Level can not be restored and maintained above -180 inches. Once this determination is made the crew will transition to ED. Injection sources will be terminated and prevented and 6 ADS valves will be opened. Once Reactor Pressure lowers to the MARFP pressure of 190 psig, injection can commence with low pressure systems to restore Reactor level to the prescribed level band.

3-24 Rev 0 Page 7 of 52 Terminate the scenario when the following conditions are satisfied or upon request of Lead Examiner.

Control Rod insertion in progress Emergency Depressurization Reactor Water Level restored after ED

3-24 Rev 0 Page 8 of 52 XII. Simulator Event Guide:

Event 1 and 2: Unit Startup SRO 3-GOI-100-1A Section 5.0 Instruction Steps

[67] CONTINUE to withdraw control rods to raise Reactor power to approximately 8%. (REFER TO 3-OI-85 and 3-SR-3.1.3.5(A))

Directs ATC to continue power ascension with rods ATC 3-OI-85 6.6 Control Rod Withdrawal 6.6.1 Initial Conditions Prior to Withdrawing Control Rods

[2] VERIFY the following prior to control rod movement:

CRD POWER, 3-HS-85-46 in ON.

Rod Worth Minimizer is operable and LATCHED into the correct ROD GROUP when Rod Worth Minimizer is enforcing (not required with no fuel in RPV).

6.6.2 Actions Required During and Following Control Rod Withdrawal

[4] OBSERVE the following during control rod repositioning:

Control rod reed switch position indicators (four rod display) agree with the indication on the Full Core Display.

Nuclear Instrumentation responds as control rods move through the core (This ensures control rod is following drive during Control Rod movement.)

[5] ATTEMPT to minimize automatic RBM Rod Block as follows:

STOP Control Rod withdrawal (if possible) prior to reaching any RBM Rod Block using the RBM displays on Panel 3-9-5 and PERFORM Step 6.6.2[6].

[6] IF Control Rod movement was stopped to keep from exceeding a RBM setpoint or was caused by a RBM Rod Block, THEN PERFORM the following at the Unit Supervisors discretion to REINITIALIZE the RBM:

[6.1] PLACE CRD POWER, 3-HS-85-46 in the OFF position to deselect the Control Rod.

[6.2] PLACE CRD POWER, 3-HS-85-46, in the ON position.

3-24 Rev 0 Page 9 of 52 XII. Simulator Event Guide:

Event 1 and 2: Unit Startup ATC 6.6.3 Control Rod Notch Withdrawal

[1] SELECT the desired control rod by depressing the appropriate CRD ROD SELECT pushbutton, 3-XS-85-40.

[2] OBSERVE the following for the selected control rod:

CRD ROD SELECT pushbutton is brightly ILLUMINATED

White light on the Full Core Display ILLUMINATED

Rod Out Permit light ILLUMINATED

[3] VERIFY Rod Worth Minimizer is operable and LATCHED into the correct ROD GROUP when the Rod Worth Minimizer is enforcing.

[4] PLACE CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH, and RELEASE.

[5] OBSERVE the control rod settles into the desired position and the ROD SETTLE light extinguishes.

[6] IF control rod is notch withdrawn to rod notch Position 48, THEN PERFORM control rod coupling integrity check as follows:

[6.1] PLACE CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH, and RELEASE.

[6.2] CHECK control rod coupled by observing the following:

Four rod display digital readout and the full core display digital readout and background light remain illuminated.

CONTROL ROD OVERTRAVEL annunciator, 3-XA-55-5A, Window 14, does not alarm.

[6.3] CHECK the control rod settles into Position 48 and the ROD SETTLE light extinguishes.

[6.4] IF Control Rod Coupling Integrity Check fails, THEN REFER TO 3-AOI-85-2.

3-24 Rev 0 Page 10 of 52 XII. Simulator Event Guide:

Event 1 and 2: Unit Startup ATC 6.6.4 Continuous Rod Withdrawal

[1] SELECT the desired control rod by depressing the appropriate CRD ROD SELECT pushbutton, 3-XS-85-40.

[2] OBSERVE the following for the selected control rod:

CRD ROD SELECT pushbutton is brightly ILLUMINATED

White light on the Full Core Display ILLUMINATED

Rod Out Permit light ILLUMINATED

[3] VERIFY Rod Worth Minimizer is operable and LATCHED into the correct ROD GROUP when the Rod Worth Minimizer is enforcing.

[4] VERIFY Control Rod is being withdrawn to a position greater than three notches.

[5] IF withdrawing the control rod to a position other than 48, THEN PERFORM the following: (Otherwise N/A)

[5.1] PLACE AND HOLD CRD NOTCH OVERRIDE, 3-HS-85-47, in NOTCH OVERRRIDE.

[5.2] PLACE AND HOLD CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH.

[5.3] WHEN control rod reaches two notches prior to the intended notch, THEN RELEASE CRD NOTCH OVERRIDE, 3-HS-85-47 and CRD CONTROL SWITCH, 3-HS-85-48.

[5.4] IF control rod settles at notch before intended notch, THEN PLACE CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH and RELEASE.

[5.5] WHEN control rod settles into the intended notch, THEN CHECK the following.

Four rod display digital readout and the full core display digital readout and background light remain illuminated.

CONTROL ROD OVERTRAVEL annunciator, 3-XA-55-5A, Window 14, does NOT alarm.

[5.6] CHECK the control rod settles at intended position and ROD SETTLE light extinguishes.

3-24 Rev 0 Page 11 of 52 XII. Simulator Event Guide:

Event 1 and 2: Unit Startup ATC 6.6.4 Continuous Rod Withdrawal (continued)

[6] IF continuously withdrawing the control rod to position 48 and performing the control rod coupling integrity check in conjunction with withdrawal, THEN PERFORM the following: (Otherwise N/A)

[6.1] PLACE and HOLD CRD NOTCH OVERRIDE, 3-HS-85-47, in NOTCH OVERRRIDE.

[6.2] PLACE and HOLD CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH.

[6.3] MAINTAIN the CRD Notch Override Switch in the Override position and the CRD Control Switch in the Rod Out Notch position with the control rod at position 48.

[6.4] CHECK control rod coupled by observing the following:

Four rod display digital readout and the full core display digital readout and background light remain illuminated.

CONTROL ROD OVERTRAVEL annunciator, 3-XA-55-5A, Window 14, does not alarm.

[6.5] RELEASE both CRD NOTCH OVERRIDE, 3-HS-85-47, and CRD CONTROL SWITCH, 3-HS-85-48.

[6.6] CHECK control rod settles into position 48 and ROD SETTLE light extinguishes.

[6.7] IF control rod coupling integrity check fails, THEN REFER TO 3-AOI-85-2.

3-24 Rev 0 Page 12 of 52 XII. Simulator Event Guide:

Event 1 and 2: Unit Startup ATC 6.6.4 Continuous Rod Withdrawal (continued)

[7] IF continuously withdrawing the control rod to position 48 and the control rod coupling integrity check will be performed after the CRD NOTCH OVERRIDE, 3-HS-85-47, and CRD CONTROL SWITCH, 3-HS-85-48 are to be released, THEN PERFORM control rod coupling integrity check as follows (otherwise N/A):

[7.1] PLACE AND HOLD CRD NOTCH OVERRIDE, 3-HS-85-47, in NOTCH OVERRRIDE.

[7.2] PLACE AND HOLD CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH.

[7.3] WHEN position 48 is reached, THEN RELEASE CRD NOTCH OVERRIDE, 3-HS-85-47, and CRD CONTROL SWITCH, 3-HS-85-48.

[7.4] VERIFY control rod settles into position 48.

[7.5] PLACE CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH and RELEASE.

[7.6] CHECK control rod coupled by observing the following:

Four rod display digital readout AND full core display digital readout AND background light will remain illuminated.

CONTROL ROD OVERTRAVEL annunciator (3-XA-55-5A, Window 14) does NOT alarm.

[7.7] CHECK control rod settles into position 48 and ROD SETTLE light extinguishes.

[7.8] IF control rod coupling integrity check fails, THEN REFER TO 3-AOI-85-2.

6.6.5 Return to Normal After Completion of Control Rod Withdrawal

[1] WHEN control rod movement is no longer desired AND deselecting control rods is desired, THEN:

[1.1] PLACE CRD POWER, 3-HS-85-46, in OFF.

[1.2] PLACE CRD POWER, 3-HS-85-46, in ON.

3-24 Rev 0 Page 13 of 52 XII. Simulator Event Guide:

Event 1 and 2: Unit Startup SRO 3-GOI-100-1A Section 5.0 Instruction Steps

[68] VERIFY all operable APRM downscale alarms are reset and no rod blocks exist.

[69] VERIFY the following:

Hotwell Pressure is below -24" Hg.

CONDENSER A, B OR C VACUUM LOW annunciator, (3-XA-55-7B, window 17) is reset on Panel 3-9-7.

[70] VERIFY all operable MSIVs are open on Panel 3-9-3.

[71] IF primary containment purge and/or Primary Containment Ventilation is in service, THEN PLACE the following switches in the BYPASS position (Panel 3 3):

PC PURGE DIV I RUN MODE BYPASS, 3-HS-64-24.

PC PURGE DIV II RUN MODE BYPASS, 3-HS-64-25.

[72] IF Recirculation System is in Single Loop Operation, THEN (Otherwise N/A)

VERIFY that 3-SR-3.4.1(SLO) is completed to satisfy Tech Specs and SR-3.0.4.

Initials Date Time SRO Directs BOP to perform step 71 BOP [71] IF primary containment purge and/or Primary Containment Ventilation is in service, THEN PLACE the following switches in the BYPASS position (Panel 3 3):

PC PURGE DIV I RUN MODE BYPASS, 3-HS-64-24.

PC PURGE DIV II RUN MODE BYPASS, 3-HS-64-25.

3-24 Rev 0 Page 14 of 52 XII. Simulator Event Guide:

Event 3: Uncoupled Control Rod ATC Respond to Annunciator CONTROL ROD OVERTRAVEL and CONTROL ROD DRIFT A. VALIDATE alarm as follows:

1. Full Core Display will have no digital readout.

2. Background light extinguished.

3. Rod DRIFT light on.

B. IF alarm valid, THEN REFER TO 2-AOI-85-2.

C. NOTIFY Reactor Engineer.

D. REFER TO Tech Spec 3.1.3, 3.10.8.5, 3.3.2.1, and TRM TABLE 3.3.5-1.

Reports Control Rod 02-35 is Uncoupled or over traveled SRO Enter 2-AOI-85-2 Uncoupled Control Rod ATC 3-AOI-85-2 4.1 Immediate Actions

[1] STOP all control rod withdrawal.

SRO 4.2 Subsequent Actions

[1] NOTIFY Reactor Engineer to evaluate the suspect uncoupled control rod for its impact on core thermal limits and rod worth.

[2] ADJUST the rod pattern as directed by the Reactor Engineer throughout the performance of this procedure.

Driver Driver Acknowledge uncoupled control rod, concur with coupling attempt per 3-AOI-85-2

3-24 Rev 0 Page 15 of 52 XII. Simulator Event Guide:

Event 3: Uncoupled Control Rod SRO [3] IF the control rod drive is at position 48 AND with Reactor Engineer concurrence, THEN PERFORM the following:

Direct ATC to attempt to couple Control Rod 02-35 PERFORM the following:

ATC [3.1] NOTCH INSERT the control rod drive to position 46 to attempt to couple the control rod.

[3.2] RESET associated annunciators.

[3.3] NOTCH WITHDRAW the control rod drive to position 48.

[3.4] PERFORM a coupling check.

[3.5] IF coupling integrity check fails, THEN CONTINUOUSLY INSERT control rod drive to position 00 to attempt to latch control rod with control rod drive mechanism.

[3.5.1] RESET associated annunciators.

[3.5.2] NOTCH WITHDRAW control rod to position 48.

[3.5.3] PERFORM a coupling check.

Report Control Rod 02-35 is Coupled Driver Driver When control rod 02-35 is inserted to position 46 delete the failure rd05r0235 SRO Makes notifications that Control Rod 02-35 is Coupled SRO Exits 3-AOI-85-2 and directs power ascension to continue NRC NRC At completion of scenario if SRO does not address Tech Spec 3.1.3 Follow up for Tech Spec call if rod failed to couple TS 3.1.3 Condition C Driver Driver Upon Lead examiner direction, initiate Trigger 1 for Steam Seal Regulator Failure

3-24 Rev 0 Page 16 of 52 XII. Simulator Event Guide:

Event 4: Steam Seal Regulator Failure BOP Respond to Annunciator STEAM TO STEAM SEAL REG PRESS LOW A. CHECK steam seal header pressure, 3-PI-1-148, Panel 3-9-7.

B. VERIFY proper valve alignment on Panel 3-9-7.

C. IF pressure is low, THEN OPEN steam seal bypass valve 3-FCV-1-145.

D. DISPATCH personnel to check 3-PIC-1-147 (El 617' Turb Bldg).

E. CHECK condenser vacuum on 3-P/TR-2-2 (Panel 3-9-6) and turbine vibration on 3-XR-47-15 (Panel 3-9-7) normal.

BOP Responds to Annunciators STEAM PACKING EXHAUSTER VACUUM LOW OG HOLDUP LINE INLET FLOW HIGH BOP Recommends opening steam seal bypass valve 3-FCV-1-145 to restore steam pressure SRO Concurs with actions to restore steam seal pressure BOP Dispatches personnel and checks condenser vacuum Reports Condenser Vacuum stable or slowly degrading Driver Driver 3 minutes after dispatch report No noticeable problems at 3-PIC-1-147, once steam seal pressure is restored delete mc04 (e1 0) 100 condenser air in leakage SRO Evaluate entry to 3-AOI-47-3 Loss of Condenser Vacuum BOP Once steam seal pressure is restored resets annunciators and verifies condenser vacuum is improving.

SRO Direct Power Ascension to continue and contacts personnel to investigate Steam Seal Regulator Driver Driver If I&C is dispatched acknowledge communication Driver Driver Upon Lead examiner direction, initiate Trigger 5 for HPCI Steam Leak

3-24 Rev 0 Page 17 of 52 XII. Simulator Event Guide:

Event 5: HPCI Steam Leak BOP Respond to Annunciator RX BLDG AREA RADIATION HIGH A. DETERMINE area with high radiation level on Panel 3-9-11. (Alarm on Panel 3-9-11 will automatically reset if radiation level lowers below setpoint.)

C. NOTIFY RADCON.

D. IF the TSC is NOT manned and a VALID radiological condition exists., THEN USE public address system to evacuate area where high airborne conditions exist Determine HPCI Area Radiation Monitor is in Alarm and report, Evacuate affected area and notify radiation protection.

BOP Respond to annunciator HPCI LEAK DETECTION TEMP HIGH Continued rise will cause the following valves to isolate (at Steamline Space Temperature of 165°F Torus Area or 185°F HPCI Pump Room):

HPCI STEAM LINE INBD ISOL VALVE, 3-FCV-73-2 HPCI STEAM LINE OUTBD ISOL VALVE, 3-FCV-73-3 HPCI STEAM LINE WARM-UP VALVE, 3-FCV-73-81.

A. CHECK HPCI temperature switches on LEAK DETECTION SYSTEM TEMPERATURE, 3-TI-69-29 on Panel 3-9-21.

B. IF high temperature is confirmed, THEN ENTER 3-EOI-3 Flowchart.

C. CHECK following on Panel 3-9-11 and NOTIFY RADCON if rising radiation levels are observed:

1. HPCI ROOM EL 519 RX BLDG radiation indicator, 3-RI-90-24A.

2. RHR WEST ROOM EL 519 RX BLDG radiation indicator, 3-RI-90-25A.

D. DISPATCH personnel to investigate for leaks consistent with ALARA considerations in HPCI Turbine Area (El 519) and HPCI Steam Supply Area (El 550).

BOP Reports rising temperature in HPCI, reports HPCI failed to isolate and isolates HPCI Steam Line SRO Enter EOI-3 on Secondary Containment Area Radiation Driver Driver If dispatched to HPCI area report after 5 minutes that can not access area at this time.

3-24 Rev 0 Page 18 of 52 XII. Simulator Event Guide:

Event 5: HPCI Steam Leak SRO If Reactor Zone or Refuel Zone Exhaust Radiation Level is above 72 mr/hr Then verify isolation of Reactor Zone or Refuel Zone and verify SGTS initiates If above 72 mr/hr direct Operator to verify isolation of ventilation system ATC/BO Verifies Reactor Zone and Refuel Zone Ventilation Systems isolated P

SRO If Reactor Zone or Refuel Zone Exhaust Ventilation isolated and ventilation radiation levels are below 72 mr/hr Then Restart Reactor Zone and Refuel Zone Ventilation per Appendix 8F If ventilation isolated and below 72 mr/hr directs Operator to perform Appendix 8F SRO EOI-3 Secondary Containment Temperature Monitor and Control Secondary Containment Temperature Operate available ventilation per Appendix 8F Answers Yes to Is Any Area Temp Above Max Normal CT#7 Isolate all systems that are discharging into the area except systems required to:

Be operated by EOIs OR

Suppress a Fire CT#7 BOP Isolates HPCI Steam Lines and reports Temperatures and Radiation Levels lowering SRO EOI-3 Secondary Containment Radiation Monitor and Control Secondary Containment Radiation Levels Answers Yes to Is Any Area Radiation Level Max Normal Isolate all systems that are discharging into the area except systems required to:

Be operated by EOIs OR

Suppress a Fire SRO Ensures no systems are still discharging to Secondary Containment, remains in EOI-3 until entry conditions are cleared.

3-24 Rev 0 Page 19 of 52 XII. Simulator Event Guide:

Event 5: HPCI Steam Leak ATC/BO 3-EOI Appendix 8F P

1. VERIFY PCIS Reset.

2. PLACE Refuel Zone Ventilation in service as follows (Panel 3-9-25):

a. VERIFY 3-HS-64-3A, REFUEL ZONE FANS AND DAMPERS, control switch is in OFF.

b. PLACE 3-HS-64-3A, REFUEL ZONE FANS AND DAMPERS, control switch to SLOW A (SLOW B).

c. CHECK two SPLY/EXH A(B) green lights above 3-HS-64-3A, REFUEL ZONE FANS AND DAMPERS, control switch extinguish and two SPLY/EXH A(B) red lights illuminate.

d. VERIFY OPEN the following dampers:

3-FCO-64-5, REFUEL ZONE SPLY OUTBD ISOL DMPR

3-FCO-64-6, REFUEL ZONE SPLY INBD ISOL DMPR

3-FCO-64-9, REFUEL ZONE EXH OUTBD ISOL DMPR

3-FCO-64-10, REFUEL ZONE EXH INBD ISOL DMPR.

3. PLACE Reactor Zone Ventilation in service as follows (Panel 3-9-25):

a. VERIFY 3-HS-64-11A, REACTOR ZONE FANS AND DAMPERS, control switch is in OFF.

b. PLACE 3-HS-64-11A, REACTOR ZONE FANS AND DAMPERS, control switch in SLOW A ( SLOW B).

c. CHECK two SPLY/EXH A(B) green lights above 3-HS-64-11A, REACTOR ZONE FANS AND DAMPERS, control switch extinguish and two SPLY/EXH A(B) red lights illuminate.

d. VERIFY OPEN the following dampers:

3-FCO-64-13, REACTOR ZONE SPLY OUTBD ISOL DMPR

3-FCO-64-14, REACTOR ZONE SPLY INBD ISOL DMPR

3-FCO-64-42, REACTOR ZONE EXH INBD ISOL DMPR

3-FCO-64-43, REACTOR ZONE EXH OUTBD ISOL DMPR.

Driver Driver Upon Lead examiner direction, initiate Trigger 10 for RFPT C Trip

3-24 Rev 0 Page 20 of 52 XII. Simulator Event Guide:

Event 5: HPCI Steam Leak SRO EOI-3 Secondary Containment Level Monitor and Control Secondary Containment Water Levels Answers No to Is Any Floor Drain Sump Above 66 inches and Answer No to Is Any Area Water Level Above 2 inches SRO Directs Power Ascension stopped Evaluates Tech Spec 3.5.1 and 3.6.1.3 Tech Spec 3.5.1 enter Condition C and Tech Spec 3.6.1.3 and Enter Condition A and B Notifies Operations management that Mode Change can not be completed Driver Driver Upon Lead examiner direction, initiate Trigger 10 for RFPT C Trip

3-24 Rev 0 Page 21 of 52 XII. Simulator Event Guide:

Event 6: RFPT C Trip ATC Report RFPT C Trip SRO Enters 3-AOI-3-1 Loss of Reactor Feedwater ATC Actions for Low Reactor Water Level or Loss of Feedwater

[10] IF RFPs are in manual control, THEN RAISE speed of operating RFPs.

[14] IF unit remains on-line, THEN RETURN Reactor water level to normal operating level of 33 (normal range).

SRO Direct RFPT B used to restore level or directs a Reactor Scram if level cannot be restored ATC Raises speed of RFPT B to restore Reactor Level BOP Dispatches personnel to RFPT C area SRO Establishes a Reactor Level at which a scram will be inserted, automatic scram is plus 2 inches.

Driver Driver 4 minutes after dispatched report workers in area accidentally tripped RFPT C ATC Reports that level is recovering when RFPT B is feeding the vessel Report Power level and SRM alarms as level is restored ATC Control speed of RFPT B to maintain Reactor Level Driver Driver If the crew inserts a scram or level reaches level 3 then initiate trigger 30 for lighting strike at CCW Capacitor Banks, Call control room as security and report lighting strike at CCW Capacitor Banks Driver Driver Upon Lead examiner direction, initiate Trigger 30 for lighting strike at CCW Capacitor Banks, Call control room as security and report lighting strike at CCW Capacitor Banks

3-24 Rev 0 Page 22 of 52 XII. Simulator Event Guide:

Event 7: Loss of Condenser Vacuum / ATWS Crew Responds to trip of operating Circ Water Pumps and Degrading Vacuum SRO Enters 3-AOI-47-3 Loss of Vacuum SRO [6] CHECK CCW pumps for proper operation. If available, START additional CCW PUMPS.

[7] VERIFY CLOSED CONDENSER VAC BREAKERS 1A AND 1B, 3-HS-66-1A, Panel 9-8.

Directs BOP to start CCW Pump A and verify vacuum breakers closed BOP Attempts start of CCW Pump A and reports trip SRO Directs Reactor Scram ATC Manually scrams Reactor ATC Reports no control rods movement, initiates one channel of ARI ATC Places mode switch in shutdown and reports power above 5%

SRO Enters EOI-1 RPV Control, Power Directs second channel of ARI Answers Yes to is Power Above 5%

Directs ATC to Trip Recirc Pumps ATC Initiates second channel of ARI and trips Recirc Pumps and reports power CT#2 SRO Directs Appendix 1A, 1D and 2 ATC Contacts AUO to perform field actions of appendix 1A, 1D and 2 Driver Driver When Notified to perform appendix 1A and 2, wait 2 minutes initiate trigger 20 and verify batch file for removing fuses is active. If requested to open/close 3-shv-085-0586 wait 3 minutes to close or open and use remote function rd06.

Driver Driver When requested to install fuses initiate trigger 21 and verify batch file goes active

3-24 Rev 0 Page 23 of 52 XII. Simulator Event Guide:

Event 7: ATWS ATC Appendix 1D to manually insert rods

1. VERIFY at least one CRD pump in service.

2. IF Reactor Scram or ARI CANNOT be reset, THEN DISPATCH personnel to CLOSE 3-SHV-085-0586, CHARGING WATER SOV (RB NE, El 565 ft).

3. VERIFY REACTOR MODE SWITCH in SHUTDOWN.

4. BYPASS Rod Worth Minimizer.

5. REFER to Attachment 2 and INSERT control rods in the area of highest power as follows:

a. SELECT control rod.

b. PLACE CRD NOTCH OVERRIDE switch in EMERG ROD IN position UNTIL control rod is NOT moving inward.

CT#2 ATC Inserts Control Rods SRO Stops at Stop sign Before Suppression Pool Temperature Rises to 110°F Continue

3-24 Rev 0 Page 24 of 52 XII. Simulator Event Guide:

Event 7: ATWS SRO EOI-1 Pressure Monitor and Control RPV Pressure Answer No to is any MSRV cycling Directs RPV pressure band of 800 to 1000 psig, initially on bypass valves then on MSRVs BOP Maintains RPV pressure band of 800 to 1000 psig SRO EOI-1 Level Monitor and Control RPV Water Level Directs Verification of PCIS isolations ATC/BO Verifies PCIS isolations P

SRO Exits RC/L and Enters C5 Level Power Control CT#1 SRO Directs ADS Inhibited CT#1 BOP/AT Inhibits ADS C

SRO Answers Yes to Is Any Main Steam Line Open Bypass the following isolation interlocks

MSIV Low Low Low RPV Water Level (Appendix 8A)

RB Ventilation Low RPV Water Level (Appendix 8E)

ATC/BO Contacts AUO to perform Appendix 8A and 8E P

Answer Yes to Is Reactor Power Above 5%

Driver Driver If requested to perform Appendix 8A and 8E wait 5 minutes insert Bat app08ae and report field actions for appendix 8A are complete and appendix 8E is complete ATC/BOP Complete Appendix 8A

3. NOTIFY Unit Operator to verify closed the following valves (Unit 3 Control Room, Panel 9-3):

3-FCV-43-13, RX RECIRC SAMPLE INBD ISOLATION VLV 3-FCV-43-14, RX RECIRC SAMPLE OUTBD ISOLATION VLV CT#4 SRO Directs Stop and Prevent All Injection Into RPV Except From RCIC, CRD and SLC (Appendix 4)

3-24 Rev 0 Page 25 of 52 XII. Simulator Event Guide:

Event 7: ATWS

3-24 Rev 0 Page 26 of 52 CS#4 BOP/AT Terminate and Prevent per Appendix 4 C

1. PREVENT injection to RPV from the following systems in any order as required:

a. HPCI

1) IF HPCI Turbine is NOT at zero speed, THEN PRESS and HOLD 3-HS-73-18A, HPCI TURBINE TRIP push-button.

2) WHEN HPCI Turbine is at zero speed, THEN PLACE 3-HS-73-47A, HPCI AUXILIARY OIL PUMP control switch in PULL TO LOCK and RELEASE 3-HS 18A, HPCI TURBINE TRIP push-button.

c. CORE SPRAY NOTE: After receipt of an automatic initiation signal, it is NOT necessary to wait until the pump actually starts before performing the next step.

Following an initiation signal, PLACE ALL Core Spray pump control switches in STOP.

d. LPCI SYSTEM I PREVENT injection by EITHER of the following methods:

Following automatic pump start, PLACE RHR SYSTEM I pump control switches in STOP.

BOP/AT OR C

BEFORE RPV pressure drops below 450 psig,

1) PLACE 3-HS-74-155A, LPCI SYS I OUTBD INJ VLV BYPASS SEL, in BYPASS.

AND

2) VERIFY CLOSED 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE.

e. LPCI SYSTEM II PREVENT injection by EITHER of the following methods:

Following automatic pump start, PLACE RHR SYSTEM II pump control switches in STOP.

OR

BEFORE RPV pressure drops below 450 psig,

1) PLACE 3-HS-74-155B, LPCI SYS II OUTBD INJ VLV BYPASS SEL, in BYPASS.

AND

2) VERIFY CLOSED 3-FCV-74-66, RHR SYS II LPCI OUTBD INJECT VALVE.

3-24 Rev 0 Page 27 of 52 XII. Simulator Event Guide:

Event 7: EOI-3 CT#4 BOP/AT Terminate and Prevent per Appendix 4 C

f. CONDENSATE and FEEDWATER

1) LOWER RFPT 3A(3B)(3C) speed to minimum setting (approximately 600 rpm) using ANY of the following methods on Panel 3-9-5:

Using 3-LIC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL AND individual 3-SIC-46-8(9)(10), RFPT 3A(3B)(3C) SPEED CONTROL PDS in AUTO, OR

Using individual 3-SIC-46-8(9)(10), RFPT 3A(3B)(3C) SPEED CONTROL PDS in MANUAL, OR

Using individual 3-HS-46-8A(9A)(10A), RFPT 3A(3B)(3C) SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR.

2) CLOSE the following valves BEFORE RPV pressure drops below 450 psig:

3-FCV-3-19, RFP 3A DISCHARGE VALVE

3-FCV-3-12, RFP 3B DISCHARGE VALVE

3-FCV-3-5, RFP 3C DISCHARGE VALVE

3-LCV-3-53, RFW START-UP LEVEL CONTROL.

3) TRIP RFPTs as necessary to prevent injection by DEPRESSING the following push-buttons:

3-HS-3-125A, RFPT 3A TRIP

3-HS-3-151A, RFPT 3B TRIP

3-HS-3-176A, RFPT 3C TRIP.

CT#4 SRO When RPV Water Level Drops Below -50 inches Then Continue Directs a RPV Level Band of -50 to -100 inches using RCIC and CRD ATC/BO Reports RCIC failed to auto start and attempts to start RCIC Report failure of RCIC and dispatch personnel P

Driver Driver When dispatched to RCIC wait 5 minutes and report Turbine is tripped and tripped linkage can not be reset

3-24 Rev 0 Page 28 of 52 XII. Simulator Event Guide:

Event 8: Loss of High Pressure Injection

3-24 Rev 0 Page 29 of 52 Crew Monitor Reactor Water Level CT#2 SRO Before Suppression Pool Temperature rises to 110°F directs Boron Injection CT#2 ATC Initiates SLC per Appendix 3A

1. UNLOCK and PLACE 3-HS-63-6A, SLC PUMP 3A/3B, control switch in START PUMP 3A or START PUMP 3B position.

2. CHECK SLC System for injection by observing the following:

Selected pump starts, as indicated by red light illuminated above pump control switch.

Squib valves fire, as indicated by SQUIB VALVE A and B CONTINUITY blue lights extinguished,

SLC SQUIB VALVE CONTINUITY LOST Annunciator in alarm on Panel 3-9-5 (3-XA-55-5B, Window 20).

3-PI-63-7A, SLC PUMP DISCH PRESS, indicates above RPV pressure.

System flow, as indicated by 3-IL-63-11, SLC FLOW, red light illuminated on Panel 3-9-5,

SLC INJECTION FLOW TO REACTOR Annunciator in alarm on Panel 3-9-5 (3-XA-55-5B, Window 14).

SRO Direct Verification of RWCU Isolation ATC/BO Verifies RWCU isolated P

SRO If RPV Water Level Cannot Be Restored And Maintained Above -180 inches Then Continue at Step C5-19 CT#5 Prior to -180 inches transitions to Emergency Depressurization CT#3 Directs Stop and Prevent All Injection Into RPV Except From RCIC, CRD and SLC (Appendix 4)

CT#3 BOP/AT Confirms Appendix 4 Injection Systems are stopped and prevented C

SRO Answers Yes to Is Suppression Pool Level Above 5.5 feet CT#5 Directs All ADS Valves Open CT#5 ATC/BO Opens 6 ADS Valves P

SRO Answers Yes to Can 6 ADS Valves Be Opened

3-24 Rev 0 Page 30 of 52 XII. Simulator Event Guide:

Event 8: Loss of High Pressure Injection CS#6 SRO When Reactor Pressure is below 190 psig (MARFP Pressure) Then Continue Direct Start and Slowly Raise RPV Injection with the following injection sources to restore and maintain RPVwater level above -180 inches Condensate and Feedwater, CRD, LPCI CT#6 ATC/BO Restore Level using Condensate and/or LPCI to the prescribed level band P

SRO Answers Yes to Can RPV Water Level Be Restored And Maintained Above -180 inches Answers Yes to Was Water Level Lowered For Step C5-12 Directs the same level band that was in use prior to ED ATC/BOP Restore Level using Condensate and/or LPCI to the prescribed level band

3-24 Rev 0 Page 31 of 52 XII. Simulator Event Guide:

Event 8: EOI-2 SRO Enters EOI-2 Primary Containment Control EOI-2 Drywell Temperature SRO Monitor and Control DW Temp Below 160°F using available DW Cooling Answers No to Can Drywell Temp Be Maintained Below 160°F Operate All Available Drywell Cooling Stops at Stop sign Before Drywell Temperature Rises to 280°F Then Continue SRO EOI-2 Primary Containment Pressure Monitor and Control PC Pressure Below 2.4 psig Using the Vent System As Necessary (Appendix 12)

Directs venting of Primary Containment per Appendix 12 Answers No to Can PC Pressure Be Maintained Below 2.4 psig Evaluates stop sign Before Suppression Chamber Pressure Rises To 12 psig Continue Initiates Suppression Chamber Sprays Using Only Pumps Not Required to Assure Adequate Core Cooling By Continuous Injection (Appendix 17C)

SRO Should not initiate sprays or terminates sprays prior to ED SRO EOI-2 Suppression Pool Level Monitor and Control Suppression Pool Level Between -1 inch and -6 inches (Appendix 18)

Answers Yes to Can Suppression Pool Level Be Maintained Above -6 inches Answers Yes to Can Suppression Pool Level Be Maintained Below -1 inches

3-24 Rev 0 Page 32 of 52 XII. Simulator Event Guide:

Event 8: EOI-2 SRO EOI-2 Suppression Pool Temperature Monitor and Control Suppression Pool Temperature Below 95°F Using Available Suppression Pool Cooling As Necessary (Appendix 17A)

Answers No to Can Suppression Pool Temperature Be Maintained Below 95°F Operate all available Suppression Pool Cooling using only RHR Pumps not required to assure adequate core cooling by continuous injection (Appendix 17A)

SRO Should not initiate Pool Cooling or terminates pool cooling prior to ED SRO EOI-2 Directs H2O2 Analyzers placed in service BOP Places H2O2 analyzers in service:

1.Place Analyzer Isolation Bypass Switch to Bypass

2. Select DW or SUPPR CHMBR and pulls out select switch handle to start pumps.

SRO Emergency Plan Classification is 1.2-S

3-24 Rev 0 Page 33 of 52 XII. Simulator Event Guide:

Event 8: EOI-2 BOP Vents the suppression chamber per Appendix 12

1. VERIFY at least one SGTS train in service.

2. VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):

3-FCV-64-31, DRYWELL INBOARD ISOLATION VLV, 3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE, 3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV, 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE.

NOTE: Venting may be accomplished using EITHER:

3-FIC-84-19, PATH B VENT FLOW CONT, OR 3-FIC-84-20, PATH A VENT FLOW CONT.

Driver Driver If requested to start a Standby Gas Train After 1 minute, Remote function PC01A or B or C

7. CONTINUE in this procedure at:

Step 8 to vent the Suppression Chamber through 3-FCV-84-19, OR Step 9 to vent the Suppression Chamber through 3-FCV-84-20.

8. VENT the Suppression Chamber using 3-FIC-84-19, PATH B VENT FLOW CONT, as follows:

a. PLACE keylock switch 3-HS-84-35, DW/SUPPR CHBR VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).

b. VERIFY OPEN 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE (Panel 3-9-54).

c. PLACE 3-FIC-84-19, PATH B VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

d. PLACE keylock switch 3-HS-84-19, 3-FCV-84-19 CONTROL, in OPEN (Panel 3-9-55).

e. VERIFY 3-FIC-84-19, PATH B VENT FLOW CONT, is indicating approximately 100 scfm.

f. CONTINUE in this procedure at step 12.

3-24 Rev 0 Page 34 of 52 XII. Simulator Event Guide:

Event 8: EOI-2 BOP Vents the suppression chamber per Appendix 12

1. VERIFY at least one SGTS train in service.

2. VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):

3-FCV-64-31, DRYWELL INBOARD ISOLATION VLV, 3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE, 3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV, 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE.

NOTE: Venting may be accomplished using EITHER:

3-FIC-84-19, PATH B VENT FLOW CONT, OR 3-FIC-84-20, PATH A VENT FLOW CONT.

Driver Driver If requested to start a Standby Gas Train After 1 minute, Remote function PC01A or B or C

7. CONTINUE in this procedure at:

Step 8 to vent the Suppression Chamber through 3-FCV-84-19, OR Step 9 to vent the Suppression Chamber through 3-FCV-84-20.

8. VENT the Suppression Chamber using 3-FIC-84-19, PATH B VENT FLOW CONT, as follows:

a. PLACE keylock switch 3-HS-84-35, DW/SUPPR CHBR VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).

b. VERIFY OPEN 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE (Panel 3-9-54).

c. PLACE 3-FIC-84-19, PATH B VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

d. PLACE keylock switch 3-HS-84-19, 3-FCV-84-19 CONTROL, in OPEN (Panel 3-9-55).

e. VERIFY 3-FIC-84-19, PATH B VENT FLOW CONT, is indicating approximately 100 scfm.

f. CONTINUE in this procedure at step 12.

3-24 Rev 0 Page 35 of 52 XII. Simulator Event Guide:

Event 8: EOI-2 BOP Vents the suppression chamber per Appendix 12

9. VENT the Suppression Chamber using 3-FIC-84-20, PATH A VENT FLOW CONT, as follows:

a. VERIFY OPEN 3-FCV-64-141, DRYWELL DP COMP BYPASS VALVE (Panel 3-9-3).

b. PLACE keylock switch 3-HS-84-36, SUPPR CHBR/DW VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).

c. VERIFY OPEN 3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV (Panel 3-9-54).

d. VERIFY 3-FIC-84-20, PATH A VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

e. PLACE keylock switch 3-HS-84-20, 3-FCV-84-20 ISOLATION BYPASS, in BYPASS (Panel 3-9-55).

f. VERIFY 3-FIC-84-20, PATH A VENT FLOW CONT, is indicating approximately 100 scfm.

g. CONTINUE in this procedure at step 12.

12. ADJUST 3-FIC-84-19, PATH B VENT FLOW CONT, or 3-FIC-84-20, PATH A VENT FLOW CONT, as applicable, to maintain ALL of the following:

Stable flow as indicated on controller, AND 3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND Release rates as determined below:

i. IF PRIMARY CONTAINMENT FLOODING per C-1, Alternate Level Control, is in progress, THEN MAINTAIN release rates below those specified in Attachment 2.

ii. IF Severe Accident Management Guidelines are being executed, THEN MAINTAIN release rates below those specified by the TSC SAM Team.

iii. IF Venting for ANY other reason than items i or ii above, THEN MAINTAIN release rates below Stack release rate of 1.4 x 107 µCi/s AND 0-SI-4.8.B.1.a.1 release fraction of 1.

BOP Call AUO to Monitor Release Rates Driver Driver Acknowledge Notification

3-24 Rev 0 Page 36 of 52

3-24 Rev 0 Page 37 of 52 XII. Simulator Event Guide:

Event 8: EOI-2 ATC/BO Initiate Suppression Chamber Sprays per Appendix 17C P

1. BEFORE Suppression Chamber pressure drops below 0 psig, CONTINUE in this procedure at Step 6.

2. IF Adequate core cooling is assured, OR Directed to spray the Suppression Chamber irrespective of adequate core cooling, THEN BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS-74-155A(B), LPCI SYS I(II) OUTBD INJ VLV BYPASS SEL in BYPASS.

5. INITIATE Suppression Chamber Sprays as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. IF ............. EITHER of the following exists:

LPCI Initiation signal is NOT present, OR

Directed by SRO, THEN PLACE keylock switch 3-XS-74-122(130), RHR SYS I(II) LPCI 2/3 CORE HEIGHT OVRD, in MANUAL OVERRIDE.

c. MOMENTARILY PLACE 3-XS-74-121(129), RHR SYS I(II) CTMT SPRAY/CLG VLV SELECT, switch in SELECT.

d. IF 3-FCV-74-53(67), RHR SYS I(II) INBD INJECT VALVE, is OPEN, THEN VERIFY CLOSED 3-FCV-74-52(66), RHR SYS I(II) OUTBD INJECT VALVE.

e. VERIFY OPERATING the desired RHR System I(II) pump(s) for Suppression Chamber Spray.

3-24 Rev 0 Page 38 of 52 XII. Simulator Event Guide:

Event 8: EOI-2

f. VERIFY OPEN 3-FCV-74-57(71), RHR SYS I(II) SUPPR CHBR/POOL ISOL VLV.

ATC/BO P g. OPEN 3-FCV-74-58(72), RHR SYS I(II) SUPPR CHBR SPRAY VALVE.

h. IF RHR System I(II) is operating ONLY in Suppression Chamber Spray mode, THEN CONTINUE in this procedure at Step 5.k.

i. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM I(II) MIN FLOW VALVE.

j. RAISE system flow by placing the second RHR System I(II) pump in service as necessary.

k. MONITOR RHR Pump NPSH using Attachment 2.

l. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

m. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm flow:

3-FCV-23-34, RHR HX 3A RHRSW OUTLET VLV

3-FCV-23-46, RHR HX 3B RHRSW OUTLET VLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLET VLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLET VLV.

3-24 Rev 0 Page 39 of 52 XIII. Crew Critical Tasks:

8. ADS inhibited before ADS actuates

9. With a reactor scram required and the reactor not shutdown:

Inserts control rods, to prevent exceeding the primary containment design limits

Inject boron (prior to exceeding 110°F SP temperature)

10. During an ATWS with emergency depressurization required, injection has been stopped and prevented, with the exception of RCIC, SLC, and CRD, into the RPV until reactor pressure is below Minimum Alternate RPV Flooding Pressure(MARFP)

11. ATWS with power >5%, injection has been stopped and prevented, with the exception of RCIC, SLC, and CRD, into the RPV until RPV level is below -50 to establish a lower limit

12. Emergency depressurizes when RPV level cannot be restored and maintained above -180". Emergency depressurization is initiated before level reaches -200"

13. When RPV pressure is below MARFP, injection reestablished to maintain RPV level above -180

14. Manually isolates HPCI before Max Safe Operating Value is exceeded.

3-24 Rev 0 Page 40 of 52 XIV. Scenario Verification Data EVENT TASK NUMBER K/A RO SRO 1 and 2 Reactor Startup RO U-000-NO-03 201002A4.01 3.5 3.4 SRO S-000-NO-001 2.1.7 4.4 4.7 3 Uncoupled Control Rod RO U-085-AB-02 201003A2.02 3.7 3.8 SRO S-085-AB-02 4 Steam Seal Regulator Fail RO U-001-AL-01 239001 K3.06 2.6 2.7 5 HPCI Steam Leak RO U-073-AL-06 295032EA2.03 3.8 4.0 SRO S-000-EM-10 6 RFPT Trip RO U-003-AL-16 259001A2.01 3.7 3.7 SRO S-003-AB-01 7 Loss of Condenser Vacuum RO U-047-AB-03 295002AA1.06 3.0 3.1 SRO S-047-AB-03 295037EA2.02 4.1 4.2 SRO S-000-EM-18

3-24 Rev 0 Page 41 of 52 XV. SCENARIO REVIEW CHECKLIST SCENARIO NUMBER: HLTS-3-24 8 Total Malfunctions Inserted: List (4-8) 3 Malfunctions that occur after EOI entry: List (1-4) 4 Abnormal Events: List (1-3) 2 Major Transients: List (1-2) 3 EOIs used: List (1-3) 2 EOI Contingencies used: List (0-3) 90 Run Time (minutes) 7 Crew Critical Tasks: (2-5)

YES Technical Specifications Exercised (Yes/No)

1. Appendix D Scenario Outline Form ES-D-1 SHIFT TURNOVER SHEET Equipment Out of Service/LCOs:

IRM E is out of service and bypassed Operations/Maintenance for the Shift:

Continue plant startup IAW 3-GOI-100-1A section 5.4, mode change from Mode 2 to Mode 1.

Unit 1 and 2 are 100% power Unusual Conditions/Problem Areas:

Severe Thunderstorm warning is affect for Limestone, Morgan, and Madison Counties for the next two hours.

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

2. Appendix D Scenario Outline Form ES-D-1 Facility: Browns Ferry NPP Scenario No.: 3-22 Op-Test No.: ILT 1006 SRO:

Examiners: Operators: ATC:

BOP:

Initial Unit 3 is at 93% power. Unit 1 and 2 are at 100% power. RHR Pump A is out of service.

Conditions: RBCCW Pump A work is complete and ready to be returned to service. Spare RBCCW Pump is aligned to Unit 3.

Turnover: Rotate Raw Cooling Water Pumps C on and A off and then raise Reactor Power to 100%.

Event Event No. Malf. No. Type* Event Description N-BOP 1 Rotate Raw Cooling Water Pumps C on and A off N-SRO R-ATC 2 Raise Power with Recirc R-SRO C-SRO 3 pc014 Suppression Pool leak on RHR A Loop, isolation available C-BOP C-BOP B Shutdown Board Supply Breaker trips DG B fails to start 4 ed16b TS-SRO C-ATC 5 sw02b RBCCW Pump B trips C-SRO C-ATC 6 rd04 Rod 30-47 drifts out TS-SRO 7 th23 M-ALL Fuel Failure: scram on increasing Radiation and close MSIVs 8 rc09 M-ALL RCIC Steam leak no isolation ED on High Radiation C-ATC 9 ad03c/f Two ADS SRVs will fail to open for emergency depressurization C-SRO

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

2. Appendix D Scenario Outline Form ES-D-1 Critical Tasks 1 Emergency depressurization initiated within 5minutes with a primary system discharging into the secondary containment and area radiation/water/temperature levels exceed maximum safe operating levels in two or more areas.

2 Maintains RPV water level above TAF (-162")

3 Manually isolate systems discharging into secondary containment before Max Safe Operating Value is exceeded. Isolates RHR Loop A

3-22 Rev 0 Page 3 of 52 With the unit at 93% power the BOP operator will rotate Raw Cooling Water Pumps C on and A off per 3-OI-24 section 6.1.1. Upon completion the ATC will commence power increase to 100%.

When the NRC is satisfied with power maneuver, a suppression pool leak will develop on RHR A suction due to maintenance in the area. After field personnel are dispatched, field reports will indicate that the leak is isolable. The BOP operator will close RHR A Suppression Pool Suction Valve and the leak will stop. Depending on the timeliness of the crews actions EOI-2 may be entered on low Suppression Pool level. The SRO will evaluate EOI-2 entry conditions and Tech Specs.

Once the plant is stable Shutdown Board B supply breaker will trip and DG B will fail to auto start to energize the board. In addition, RBCCW Pump B will trip shortly after the DG failure.

The BOP operator will start DG B to restore Shutdown Board B safety related loads. The ATC will start RBCCW Pump A and restore RBCCW to a normal cooling lineup. The SRO will declare DG B Inoperable and refer to Tech Spec 3.8.1 for one DG out of service, condition B will be entered.

After the above transient Control Rod 30-47 will drift out. The ATC will select and insert Control Rod 30-47 per 3-AOI-85-6. The SRO will refer to Tech Spec 3.1.3 and enter Condition A.

The rod drift and insertion will cause a fuel element defect. Plant radiation levels will begin to rise. The SRO will establish power reduction strategies and determine the point at which to scram the reactor. Shortly after the reactor is scrammed, a triple high radiation alarm on MSIVs will come in forcing the crew to isolate the MSIVs. The crew will transition level control to RCIC and pressure control to SRVs. A steam leak on RCIC will develop and with no isolation the crew will have to emergency depressurize due to secondary containment radiation levels.

HPCI can be used for level control but the automatic operation of the controller will fail, Two ADS SRVs will fail to open requiring two additional SRVs opened. The crew will maintain level above TAF and after ED restore level to a band of 2 to 51 inches.

3-22 Rev 0 Page 4 of 52 VIII. Console Operator Instructions A. Scenario File Summary

1. File: batch and trigger files for scenario 3-24 Batch NRC201024

steam seal failure imf ms01 (e1 0) imf mc04 (e1 0) 100

uncoupled control rod imf rd05r0235

rfpt c trip ior zdihs03176[1] (e10 0) trip

hpci steam leak ior xa554c[10] alarm_off imf hp09 imf hp08 (e5 0) 10 120

loss of vacuum imf mc02a (e30 0) imf mc02b (e30 0) imf mc02c (e30 0) imf rp07 (e30 0) imf rp14a (e30 0) imf rp14b (e30 0) ior zdihs661a[3] (e30 0) open ior zlohs661a[2] (e30 0) off imf hp04 ior zdihs7316a[2] auto ior zdihs719a[1] (e29 0) trip trg e29 nrc2010718open imf th22 (e30 30) 100 imf th21 (e30 150) 0.8 600 imf rc08

rps fuses out and in trg 20 = bat nrc201024rpsout trg 21 = bat nrc201024rpsin

3-22 Rev 0 Page 5 of 52 Batch NRC201024rpsout mrf rp05a (none 60) out mrf rp05c (none 120) out mrf rp05e (none 180) out mrf rp05g (none 240) out mrf rp05b (none 300) out mrf rp05d (none 360) out mrf rp05f (none 420) out mrf rp05h (none 480) out Batch NRC201024rpsout mrf rp05a (none 0) in mrf rp05c (none 30) in mrf rp05e (none 60) in mrf rp05g (none 90) in mrf rp05b (none 120) in mrf rp05d (none 150) in mrf rp05f (none 180) in mrf rp05h (none 210) in RCIC Start Trigger zdihs718a[2].ne.1 IX. Console Operators Instructions Scenario 3-24 DESCRIPTION/ACTION Simulator Setup manual Reset to IC 183 Simulator Setup Load Batch Bat nrc201024 Simulator Setup manual Bypass IRM E Simulator Setup Verify Batch file loaded RCP required (Start up) - Provide marked up copy of 3-GOI-100-1A

3-22 Rev 0 Page 6 of 52 X. Scenario Summary:

With the unit at 5 to 6% power, the ATC will continue power ascension with rods to 8%

and the BOP operator will perform actions in 3-GOI-100-1A as directed by the Unit Supervisor.

The first rod to 48 will fail the coupling check. When actions are taken to couple the rod per 3-AOI-85-2, the rod will couple and power ascension may continue. SRO should refer to Tech Spec 3.1.3 for uncoupled rod. Follow up question after scenario for Tech Spec call if rod failed to couple. Tech Spec 3.1.3 Condition C.

The Steam Seal Regulator will fail causing a loss of sealing steam. Off gas flow will increase and vacuum will slowly degrade. The BOP operator can restore seal steam by taking manual control of the steam seal regulator bypass valve. Off gas flow will slowly return to normal and vacuum will quickly recover.

HPCI steam leak will develop and HPCI will fail to auto isolate. The BOP operator will isolate HPCI and stop the steam leak. EOI-3 will be entered on HPCI room temperature.

With HPCI Inoperable, the SRO will evaluate Tech Spec 3.5.1 and enter condition C and Tech Spec 3.6.1.3 Condition B. With HPCI Inoperable, mode change can not be made.

After failure of HPCI, RFPT C will trip. The ATC will take control of RFPT B and raise discharge pressure in order to restore level to the normal operating band or he will need to insert a manual reactor scram if unable to recover level. RFPT B is idling at 600 RPM at the start of the scenario; speed will need to be raised to about 3400 RPM for injection to the reactor.

Once the level is stable on RFPT B or if the reactor is scrammed, a lighting strike at the CCW Capacitor Banks will trip all running Circ Water Pumps and create a loss of condenser vacuum.

The vacuum loss will trip the RFPT and isolate bypass valves. The crew will attempt to scram the reactor but an electrical ATWS will exist and no rod motion will occur. Pressure control will be on SRVs and rods can be inserted manually per appendix 1D. When RCIC is started it will trip and will be unavailable. Level will lower to TAF, the SRO will determine that Reactor Level can not be restored and maintained above -180 inches. Once this determination is made the crew will transition to ED. Injection sources will be terminated and prevented and 6 ADS valves will be opened. Once Reactor Pressure lowers to the MARFP pressure of 190 psig, injection can commence with low pressure systems to restore Reactor level to the prescribed level band.

3-22 Rev 0 Page 7 of 52 Terminate the scenario when the following conditions are satisfied or upon request of Lead Examiner.

Control Rod insertion in progress Emergency Depressurization Reactor Water Level restored after ED

3-22 Rev 0 Page 8 of 52 XII. Simulator Event Guide:

Event 1 and 2: Unit Startup SRO 3-GOI-100-1A Section 5.0 Instruction Steps

[67] CONTINUE to withdraw control rods to raise Reactor power to approximately 8%. (REFER TO 3-OI-85 and 3-SR-3.1.3.5(A))

Directs ATC to continue power ascension with rods ATC 3-OI-85 6.6 Control Rod Withdrawal 6.6.1 Initial Conditions Prior to Withdrawing Control Rods

[2] VERIFY the following prior to control rod movement:

CRD POWER, 3-HS-85-46 in ON.

Rod Worth Minimizer is operable and LATCHED into the correct ROD GROUP when Rod Worth Minimizer is enforcing (not required with no fuel in RPV).

6.6.2 Actions Required During and Following Control Rod Withdrawal

[4] OBSERVE the following during control rod repositioning:

Control rod reed switch position indicators (four rod display) agree with the indication on the Full Core Display.

Nuclear Instrumentation responds as control rods move through the core (This ensures control rod is following drive during Control Rod movement.)

[5] ATTEMPT to minimize automatic RBM Rod Block as follows:

STOP Control Rod withdrawal (if possible) prior to reaching any RBM Rod Block using the RBM displays on Panel 3-9-5 and PERFORM Step 6.6.2[6].

[6] IF Control Rod movement was stopped to keep from exceeding a RBM setpoint or was caused by a RBM Rod Block, THEN PERFORM the following at the Unit Supervisors discretion to REINITIALIZE the RBM:

[6.1] PLACE CRD POWER, 3-HS-85-46 in the OFF position to deselect the Control Rod.

[6.2] PLACE CRD POWER, 3-HS-85-46, in the ON position.

3-22 Rev 0 Page 9 of 52 XII. Simulator Event Guide:

Event 1 and 2: Unit Startup ATC 6.6.3 Control Rod Notch Withdrawal

[1] SELECT the desired control rod by depressing the appropriate CRD ROD SELECT pushbutton, 3-XS-85-40.

[2] OBSERVE the following for the selected control rod:

CRD ROD SELECT pushbutton is brightly ILLUMINATED

White light on the Full Core Display ILLUMINATED

Rod Out Permit light ILLUMINATED

[3] VERIFY Rod Worth Minimizer is operable and LATCHED into the correct ROD GROUP when the Rod Worth Minimizer is enforcing.

[4] PLACE CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH, and RELEASE.

[5] OBSERVE the control rod settles into the desired position and the ROD SETTLE light extinguishes.

[6] IF control rod is notch withdrawn to rod notch Position 48, THEN PERFORM control rod coupling integrity check as follows:

[6.1] PLACE CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH, and RELEASE.

[6.2] CHECK control rod coupled by observing the following:

Four rod display digital readout and the full core display digital readout and background light remain illuminated.

CONTROL ROD OVERTRAVEL annunciator, 3-XA-55-5A, Window 14, does not alarm.

[6.3] CHECK the control rod settles into Position 48 and the ROD SETTLE light extinguishes.

[6.4] IF Control Rod Coupling Integrity Check fails, THEN REFER TO 3-AOI-85-2.

3-22 Rev 0 Page 10 of 52 XII. Simulator Event Guide:

Event 1 and 2: Unit Startup ATC 6.6.4 Continuous Rod Withdrawal

[1] SELECT the desired control rod by depressing the appropriate CRD ROD SELECT pushbutton, 3-XS-85-40.

[2] OBSERVE the following for the selected control rod:

CRD ROD SELECT pushbutton is brightly ILLUMINATED

White light on the Full Core Display ILLUMINATED

Rod Out Permit light ILLUMINATED

[3] VERIFY Rod Worth Minimizer is operable and LATCHED into the correct ROD GROUP when the Rod Worth Minimizer is enforcing.

[4] VERIFY Control Rod is being withdrawn to a position greater than three notches.

[5] IF withdrawing the control rod to a position other than 48, THEN PERFORM the following: (Otherwise N/A)

[5.1] PLACE AND HOLD CRD NOTCH OVERRIDE, 3-HS-85-47, in NOTCH OVERRRIDE.

[5.2] PLACE AND HOLD CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH.

[5.3] WHEN control rod reaches two notches prior to the intended notch, THEN RELEASE CRD NOTCH OVERRIDE, 3-HS-85-47 and CRD CONTROL SWITCH, 3-HS-85-48.

[5.4] IF control rod settles at notch before intended notch, THEN PLACE CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH and RELEASE.

[5.5] WHEN control rod settles into the intended notch, THEN CHECK the following.

Four rod display digital readout and the full core display digital readout and background light remain illuminated.

CONTROL ROD OVERTRAVEL annunciator, 3-XA-55-5A, Window 14, does NOT alarm.

[5.6] CHECK the control rod settles at intended position and ROD SETTLE light extinguishes.

3-22 Rev 0 Page 11 of 52 XII. Simulator Event Guide:

Event 1 and 2: Unit Startup ATC 6.6.4 Continuous Rod Withdrawal (continued)

[6] IF continuously withdrawing the control rod to position 48 and performing the control rod coupling integrity check in conjunction with withdrawal, THEN PERFORM the following: (Otherwise N/A)

[6.1] PLACE and HOLD CRD NOTCH OVERRIDE, 3-HS-85-47, in NOTCH OVERRRIDE.

[6.2] PLACE and HOLD CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH.

[6.3] MAINTAIN the CRD Notch Override Switch in the Override position and the CRD Control Switch in the Rod Out Notch position with the control rod at position 48.

[6.4] CHECK control rod coupled by observing the following:

Four rod display digital readout and the full core display digital readout and background light remain illuminated.

CONTROL ROD OVERTRAVEL annunciator, 3-XA-55-5A, Window 14, does not alarm.

[6.5] RELEASE both CRD NOTCH OVERRIDE, 3-HS-85-47, and CRD CONTROL SWITCH, 3-HS-85-48.

[6.6] CHECK control rod settles into position 48 and ROD SETTLE light extinguishes.

[6.7] IF control rod coupling integrity check fails, THEN REFER TO 3-AOI-85-2.

3-22 Rev 0 Page 12 of 52 XII. Simulator Event Guide:

Event 1 and 2: Unit Startup ATC 6.6.4 Continuous Rod Withdrawal (continued)

[7] IF continuously withdrawing the control rod to position 48 and the control rod coupling integrity check will be performed after the CRD NOTCH OVERRIDE, 3-HS-85-47, and CRD CONTROL SWITCH, 3-HS-85-48 are to be released, THEN PERFORM control rod coupling integrity check as follows (otherwise N/A):

[7.1] PLACE AND HOLD CRD NOTCH OVERRIDE, 3-HS-85-47, in NOTCH OVERRRIDE.

[7.2] PLACE AND HOLD CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH.

[7.3] WHEN position 48 is reached, THEN RELEASE CRD NOTCH OVERRIDE, 3-HS-85-47, and CRD CONTROL SWITCH, 3-HS-85-48.

[7.4] VERIFY control rod settles into position 48.

[7.5] PLACE CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH and RELEASE.

[7.6] CHECK control rod coupled by observing the following:

Four rod display digital readout AND full core display digital readout AND background light will remain illuminated.

CONTROL ROD OVERTRAVEL annunciator (3-XA-55-5A, Window 14) does NOT alarm.

[7.7] CHECK control rod settles into position 48 and ROD SETTLE light extinguishes.

[7.8] IF control rod coupling integrity check fails, THEN REFER TO 3-AOI-85-2.

6.6.5 Return to Normal After Completion of Control Rod Withdrawal

[1] WHEN control rod movement is no longer desired AND deselecting control rods is desired, THEN:

[1.1] PLACE CRD POWER, 3-HS-85-46, in OFF.

[1.2] PLACE CRD POWER, 3-HS-85-46, in ON.

3-22 Rev 0 Page 13 of 52 XII. Simulator Event Guide:

Event 1 and 2: Unit Startup SRO 3-GOI-100-1A Section 5.0 Instruction Steps

[68] VERIFY all operable APRM downscale alarms are reset and no rod blocks exist.

[69] VERIFY the following:

Hotwell Pressure is below -24" Hg.

CONDENSER A, B OR C VACUUM LOW annunciator, (3-XA-55-7B, window 17) is reset on Panel 3-9-7.

[70] VERIFY all operable MSIVs are open on Panel 3-9-3.

[71] IF primary containment purge and/or Primary Containment Ventilation is in service, THEN PLACE the following switches in the BYPASS position (Panel 3 3):

PC PURGE DIV I RUN MODE BYPASS, 3-HS-64-24.

PC PURGE DIV II RUN MODE BYPASS, 3-HS-64-25.

[72] IF Recirculation System is in Single Loop Operation, THEN (Otherwise N/A)

VERIFY that 3-SR-3.4.1(SLO) is completed to satisfy Tech Specs and SR-3.0.4.

Initials Date Time SRO Directs BOP to perform step 71 BOP [71] IF primary containment purge and/or Primary Containment Ventilation is in service, THEN PLACE the following switches in the BYPASS position (Panel 3 3):

PC PURGE DIV I RUN MODE BYPASS, 3-HS-64-24.

PC PURGE DIV II RUN MODE BYPASS, 3-HS-64-25.

3-22 Rev 0 Page 14 of 52 XII. Simulator Event Guide:

Event 3: Uncoupled Control Rod ATC Respond to Annunciator CONTROL ROD OVERTRAVEL and CONTROL ROD DRIFT A. VALIDATE alarm as follows:

1. Full Core Display will have no digital readout.

2. Background light extinguished.

3. Rod DRIFT light on.

B. IF alarm valid, THEN REFER TO 2-AOI-85-2.

C. NOTIFY Reactor Engineer.

D. REFER TO Tech Spec 3.1.3, 3.10.8.5, 3.3.2.1, and TRM TABLE 3.3.5-1.

Reports Control Rod 02-35 is Uncoupled or over traveled SRO Enter 2-AOI-85-2 Uncoupled Control Rod ATC 3-AOI-85-2 4.1 Immediate Actions

[1] STOP all control rod withdrawal.

SRO 4.2 Subsequent Actions

[1] NOTIFY Reactor Engineer to evaluate the suspect uncoupled control rod for its impact on core thermal limits and rod worth.

[2] ADJUST the rod pattern as directed by the Reactor Engineer throughout the performance of this procedure.

Driver Driver Acknowledge uncoupled control rod, concur with coupling attempt per 3-AOI-85-2

3-22 Rev 0 Page 15 of 52 XII. Simulator Event Guide:

Event 3: Uncoupled Control Rod SRO [3] IF the control rod drive is at position 48 AND with Reactor Engineer concurrence, THEN PERFORM the following:

Direct ATC to attempt to couple Control Rod 02-35 PERFORM the following:

ATC [3.1] NOTCH INSERT the control rod drive to position 46 to attempt to couple the control rod.

[3.2] RESET associated annunciators.

[3.3] NOTCH WITHDRAW the control rod drive to position 48.

[3.4] PERFORM a coupling check.

[3.5] IF coupling integrity check fails, THEN CONTINUOUSLY INSERT control rod drive to position 00 to attempt to latch control rod with control rod drive mechanism.

[3.5.1] RESET associated annunciators.

[3.5.2] NOTCH WITHDRAW control rod to position 48.

[3.5.3] PERFORM a coupling check.

Report Control Rod 02-35 is Coupled Driver Driver When control rod 02-35 is inserted to position 46 delete the failure rd05r0235 SRO Makes notifications that Control Rod 02-35 is Coupled SRO Exits 3-AOI-85-2 and directs power ascension to continue NRC NRC At completion of scenario if SRO does not address Tech Spec 3.1.3 Follow up for Tech Spec call if rod failed to couple TS 3.1.3 Condition C Driver Driver Upon Lead examiner direction, initiate Trigger 1 for Steam Seal Regulator Failure

3-22 Rev 0 Page 16 of 52 XII. Simulator Event Guide:

Event 4: Steam Seal Regulator Failure BOP Respond to Annunciator STEAM TO STEAM SEAL REG PRESS LOW A. CHECK steam seal header pressure, 3-PI-1-148, Panel 3-9-7.

B. VERIFY proper valve alignment on Panel 3-9-7.

C. IF pressure is low, THEN OPEN steam seal bypass valve 3-FCV-1-145.

D. DISPATCH personnel to check 3-PIC-1-147 (El 617' Turb Bldg).

E. CHECK condenser vacuum on 3-P/TR-2-2 (Panel 3-9-6) and turbine vibration on 3-XR-47-15 (Panel 3-9-7) normal.

BOP Responds to Annunciators STEAM PACKING EXHAUSTER VACUUM LOW OG HOLDUP LINE INLET FLOW HIGH BOP Recommends opening steam seal bypass valve 3-FCV-1-145 to restore steam pressure SRO Concurs with actions to restore steam seal pressure BOP Dispatches personnel and checks condenser vacuum Reports Condenser Vacuum stable or slowly degrading Driver Driver 3 minutes after dispatch report No noticeable problems at 3-PIC-1-147, once steam seal pressure is restored delete mc04 (e1 0) 100 condenser air in leakage SRO Evaluate entry to 3-AOI-47-3 Loss of Condenser Vacuum BOP Once steam seal pressure is restored resets annunciators and verifies condenser vacuum is improving.

SRO Direct Power Ascension to continue and contacts personnel to investigate Steam Seal Regulator Driver Driver If I&C is dispatched acknowledge communication Driver Driver Upon Lead examiner direction, initiate Trigger 5 for HPCI Steam Leak

3-22 Rev 0 Page 17 of 52 XII. Simulator Event Guide: