Text

Initial Exam 2010-301 Final Simulator Scenarios
	ML102520171
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: ML102520171 (170)
	v • d • e

Appendix D Scenario Outline Form ES-D-1 Facility:

Browns Ferry NPP Scenario No.:

3-24 Op-Test No.:

ILT 1006 Examiners:

Operators:

SRO:

ATC:

BOP:

Initial Conditions:

Unit 3 is at 5 to 6% power with startup is in progress per 3-GOI-100-1A. IRM E is out of service. Maintenance has identified that EHC Pump A motor is operating hotter than normal. Unit 1 and 2 are at 100% power. 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 .

Turnover:

Complete EHC Auto Pump Start Test and Weekly Pump Alternation per 3-OI-47A. At step 67 to raise reactor power with rods to 8%. Continue unit startup to Mode 1.

Event No.

Malf. No.

Event Type*

Event Description 1

N-BOP N-SRO Weekly EHC Pump Test 2

R-ATC R-SRO Raise power with rods to 8%

3 rd05 TS-SRO C-ATC Uncoupled Control Rod 4

ms01 C-BOP C-SRO Steam Seal Regulator failure 5

hp08 TS-SRO C-BOP HPCI Steam leak w/ auto isolation failure 6

rfpt c C-ATC C-SRO RFPT C trips 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. Emergency depressurizes when RPV level cannot be restored and maintained above -180". Emergency depressurization is initiated before level reaches -200"

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

3-24 Rev 0 Page 3 of 53 With the unit at 5 to 6% power, the BOP operator will complete the weekly EHC Pump Test per 3-OI-47A section 6.2. Upon completion the ATC will commence power increase.

The second 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 53 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 rd05r2659

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 53 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 Delete the ATWS from trigger 30 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 53 X. Scenario Summary:

With the unit at 5 to 6% power, the BOP operator will complete the weekly EHC Pump Test per 3-OI-47A section 6.2. Upon completion the ATC will commence power increase.

The second 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 53 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 53 Event 1:

EHC Pump Test SRO Direct BOP to perform EHC Auto Pump Start Test & Weekly Pump Alternation BOP Perform EHC Auto Pump Start Test & Weekly Pump Alternation

[1] VERIFY the EHC System is in service. REFER TO Section 5.1.

[2] REVIEW Precautions and Limitations listed in Section 3.0.

[3] DEPRESS the EHC PUMP 3A(3B) TEST, 3-HS-47-4A(5A), and CHECK the following actions occur:

EHC Hydraulic Fluid Pump 3A(3B) starts.

Annunciator STANDBY EHC PUMP RUNNING, 3-XA-47-108 (3-XA-55-7B Window 8), ANNUNCIATES.

Red light above test switch is ILLUMINATED (PS-47-1B(2B)) (positive indication of pump discharge pressure).

[4] CHECK the started EHC HYD PUMP A(B) DISCH PRESS, 3-PI-047-0001(0002), indicates between 1550 psig and 1750 psig, locally at the EHC skid.

Driver Driver Pre start walk down complete Pump ready for start Local Pressure is 1600 psig Volts are 0 Volts BOP

[5] IF the started EHC pump discharge pressure is NOT between 1550 psig and 1750 psig, THEN

[6] CHECK locally on Junction Box 3-JBOX-047-10166 that the following voltmeters indicate approximately 0 volts:

TURBINE EHC HDR PRESS 3-PS-47-63A TRIP IND, 3-EI-047-0063A

TURBINE EHC HDR PRESS 3-PS-47-63B TRIP IND, 3-EI-047-0063B

TURBINE EHC HDR PRESS 3-PS-47-63C TRIP IND, 3-EI-047-0063C

[7] IF alternating operating EHC pumps, THEN STOP EHC pump 3B(3A) using EHC HYD FLUID PUMP 3B(3A), 3-HS-47-2A(1A).

[8] IF NOT alternating EHC pumps, THEN

3-24 Rev 0 Page 9 of 53 XII.

Simulator Event Guide:

Event 1:

EHC Pump Test BOP

[9] IF the pump stopped in Step 6.2[7] or 6.2[8] fails to stop or remain stopped, THEN

[10] CHECK EHC HEADER PRESSURE, 3-PI-47-7, indicates between 1550 psig and 1650 psig.

[11] IF EHC header pressure is NOT between 1550 psig and 1650 psig, THEN

[12] IF pumps were alternated, THEN RESET any disagreement flags by placing the operating EHC pump handswitch, 3-HS-47-1A(2A), to START.

[13] CHECK EHC PMP 3A(3B) MTR AMPS, 3-EI-47-1(2), indicates less than 140 amps for the operating pump.

[14] VERIFY EHC Pump 3A(3B), 3A(3B) EHC PMP SUCT FLT, 3-FLT-047-0229(0230) and 3A(3B) EHC PMP AUX FLT, 3-FLT-047-0217(0218), indicate CLEAN, locally at the EHC skid.

[15] VERIFY MANUAL FLOW CONTROL VALVE, 3-SHV-047-0588, is set at 2.0 turns clockwise.

Driver Driver Filter indicates Clean, Flow control valve is 2 turns open Volts are 0 Volts

[16] CHECK locally on Junction Box 3-JBOX-047-10166 that the following voltmeters indicate approximately 0 volts:

TURBINE EHC HDR PRESS 3-PS-47-63A TRIP IND, 3-EI-047-0063A

TURBINE EHC HDR PRESS 3-PS-47-63B TRIP IND, 3-EI-047-0063B

TURBINE EHC HDR PRESS 3-PS-47-63C TRIP IND, 3-EI-047-0063C Driver Driver Post Start Walk down complete, No Leaks Pump running normally

3-24 Rev 0 Page 10 of 53 XII.

Simulator Event Guide:

Event 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 11 of 53 XII.

Simulator Event Guide:

Event 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 12 of 53 XII.

Simulator Event Guide:

Event 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 13 of 53 XII.

Simulator Event Guide:

Event 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 14 of 53 XII.

Simulator Event Guide:

Event 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 15 of 53 XII.

Simulator Event Guide:

Event 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

3-24 Rev 0 Page 16 of 53 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 26-59 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 17 of 53 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 26-59 ATC PERFORM the following:

[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 26-59 is Coupled Driver Driver When control rod 26-59 is inserted to position 46 delete the failure rd05r2659 SRO Makes notifications that Control Rod 26-59 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, C.1 Fully insert inoperable control rod in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months AND disarm the associated CRD within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Driver Driver Upon Lead examiner direction, initiate Trigger 1 for Steam Seal Regulator Failure

3-24 Rev 0 Page 18 of 53 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 19 of 53 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 20 of 53 XII.

Simulator Event Guide:

Event 5:

HPCI Steam Leak 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 Isolate all systems that are discharging into the area except systems required to:

Be operated by EOIs OR

Suppress a Fire 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 21 of 53 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, C.1 Verify by administrative means RCIC is OPERABLE Immediately and C.2 Restore HPCI System to operable status in 14 Days.

Tech Spec 3.6.1.3 and Enter Condition A and B, B Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve or blind flange 1 Hour.

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 22 of 53 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 23 of 53 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 24 of 53 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 25 of 53 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 P

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

Inhibits ADS 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 P

Contacts AUO to perform Appendix 8A and 8E 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 SRO Directs Stop and Prevent All Injection Into RPV Except From RCIC, CRD and SLC (Appendix 4)

3-24 Rev 0 Page 26 of 53 XII. Simulator Event Guide:

Event 7:

ATWS

3-24 Rev 0 Page 27 of 53 BOP/AT C

Terminate and Prevent per Appendix 4

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.

BOP/AT C

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.

OR

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 28 of 53 XII.

Simulator Event Guide:

Event 7:

EOI-3 BOP/AT C

Terminate and Prevent per Appendix 4

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.

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 P

Reports RCIC failed to auto start and attempts to start RCIC Report failure of RCIC and dispatch personnel 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 29 of 53 XII.

Simulator Event Guide:

Event 8:

Loss of High Pressure Injection

3-24 Rev 0 Page 30 of 53 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 P

Verifies RWCU isolated SRO If RPV Water Level Cannot Be Restored And Maintained Above -180 inches Then Continue at Step C5-19 CT#4 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 C

Confirms Appendix 4 Injection Systems are stopped and prevented SRO Answers Yes to Is Suppression Pool Level Above 5.5 feet CT#4 Directs All ADS Valves Open CT#4 ATC/BO P

Opens 6 ADS Valves SRO Answers Yes to Can 6 ADS Valves Be Opened

3-24 Rev 0 Page 31 of 53 XII.

Simulator Event Guide:

Event 8:

Loss of High Pressure Injection CS#5 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 RPV water level above -180 inches Condensate and Feedwater, CRD, LPCI CT#5 ATC/BO P

Restore Level using Condensate and/or LPCI to the prescribed level band 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 32 of 53 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 33 of 53 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 34 of 53 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 53 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 36 of 53 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 37 of 53

3-24 Rev 0 Page 38 of 53 XII.

Simulator Event Guide:

Event 8:

EOI-2 ATC/BO P

Initiate Suppression Chamber Sprays per Appendix 17C

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 39 of 53 XII.

Simulator Event Guide:

Event 8:

EOI-2 ATC/BO P

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

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 40 of 53 XIII.

Crew Critical Tasks:

6.

ADS inhibited before ADS actuates

7.

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)

8.

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)

9.

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

10.

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

3-24 Rev 0 Page 41 of 53 XIV.

Scenario Verification Data EVENT TASK NUMBER K/A RO SRO 1

EHC Pump Shift RO U-074-AL-16 241000 A4.10 2.9 2.9 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 42 of 53 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) 5 Crew Critical Tasks: (2-5)

YES Technical Specifications Exercised (Yes/No)

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:

Maintenance has identified that EHC Pump A motor is operating hotter than normal. The Shift Manager in discussion with plant management has decided to remove EHC Pump A from service but for it to remain in standby. Complete EHC Auto Pump Start Test & Weekly Pump Alternation per 3-OI-47A and then 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.

Appendix D Scenario Outline Form ES-D-1

Appendix D Scenario Outline Form ES-D-1 Facility:

Browns Ferry NPP Scenario No.:

3-22 Op-Test No.:

ILT 1006 Examiners:

Operators:

SRO:

ATC:

BOP:

Initial Conditions:

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

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 No.

Malf. No.

Event Type*

Event Description 1

N-BOP N-SRO Rotate Raw Cooling Water Pumps C on and A off 2

R-ATC R-SRO Raise Power with Recirc 3

pc014 C-SRO C-BOP Suppression Pool leak on RHR A Loop, isolation available 4

ed16b C-BOP TS-SRO B Shutdown Board Supply Breaker trips DG B fails to start 5

sw02b C-ATC C-SRO RBCCW Pump B trips 6

rd04 C-ATC TS-SRO Rod 30-47 drifts out 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 9

ad03c/f C-ATC C-SRO Two ADS SRVs will fail to open for emergency depressurization

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

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 55 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. In addition with RHR A out of service evaluate Tech Spec 3.6.2.3, 3.6.2.4 and 3.6.2.5 and enter condition B for each one.

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 55 VIII.

Console Operator Instructions A.

Scenario File Summary

1.

File:

batch and trigger files for scenario 3-22 Batch NRC201022

spare rbccw pump aligned irf sw02 align

rhr a pump out of service ior ypobkrpmparh fail_power

rcic no isolation/ steam leak imf rc10 imf rc09 (e10 600) 25 180 ior zdihs712a[2] auto ior zdihs713a[2] auto trg e10 modesw

hpci controller failure in auto/ ads valve failure imf hp03 (e10 0) 0 imf ad03c imf ad03f

suppression pool leak imf pc14 (e1 0) 10 ior xa554c[3] alarm_off mor xa554c[3] (e1 270) alarm_on ior xa554c[17] (e1 30) alarm_on ior xa554c[24] alarm_off ior xa554c[30] alarm_off ior xa554c[31] alarm_off

loss of shutdown board b/ dg fails to auto start imf dg01b (e5 0) imf ed16b (e5 0) trg 6 nrc2010dgb trg 6 = dmf ed16b

rbccw trips imf sw02b (e8 0)

rod drift/fuel failure imf rd04r3047 (e15 0) imf rd23 imf th23 (e15 180) 20 1200

3-22 Rev 0 Page 5 of 55 DG B Start Trigger zdi3hs823b1a(4).eq. 1 IX. Console Operators Instructions Scenario 3-22 DESCRIPTION/ACTION Simulator Setup manual Reset to IC 28, Lower Power to 93%, Verify 60 RPM difference if between 1200 and 1300 RPM on Recirc Pumps Simulator Setup Load Batch Bat nrc201022 Place RBCCW Pump 3A in STBY Simulator Setup manual Tag RHR A Pump Switch Simulator Setup Verify Batch file loaded RCP required (w/Recirc flow) - Provide marked up copy of 3-GOI-100-12 RCP for Urgent Load Reduction

3-22 Rev 0 Page 6 of 55 X. Scenario Summary:

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 C.

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 high-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 7 of 55 Terminate the scenario when the following conditions are satisfied or upon request of Lead Examiner.

All Control Rods are inserted Emergency Depressurization Reactor Water Level restored after ED

3-22 Rev 0 Page 8 of 55 XII.

Simulator Event Guide:

Event 1: Alternate Raw Cooling Water Pumps BOP 6.1.1 Alternating RCW Pumps

[1] REVIEW all Precautions and Limitations in Section 3.0.

[2] NOTIFY Chemistry prior to alternating a RCW pump.

[3] For the pump to be placed in continuous operation, START the RCW PUMP using the appropriate hand-switch. (Refer to Step 3.2F for pump alteration.)

RCW PUMP 3A, 3-HS-24-7A

RCW PUMP 3B, 3-HS-24-10A

RCW PUMP 3C, 3-HS-24-13A

RCW PUMP 3D, 3-HS-24-16A

RCW PUMP 3E, 3-HS-24-232A

[4] For the pump to be removed from continuous operation, STOP the RCW PUMP using the appropriate hand-switch. (Refer to Step 3.2F for pump alteration.)

RCW PUMP 3A, 3-HS-24-7A

RCW PUMP 3B, 3-HS-24-10A

RCW PUMP 3C, 3-HS-24-13A

RCW PUMP 3D, 3-HS-24-16A

RCW PUMP 3E, 3-HS-24-232A

[5] For the pump to be placed in automatic operation, PLACE the applicable RCW PUMP hand-switch to the mid position and PULL to AUTO. (Refer to Step 3.2F for pump alteration.)

RCW PUMP 3A, 3-HS-24-7A

RCW PUMP 3B, 3-HS-24-10A

RCW PUMP 3C, 3-HS-24-13A

RCW PUMP 3D, 3-HS-24-16A

RCW PUMP 3E, 3-HS-24-232A

[6] VERIFY RCW Header Pressure are within the following:

RCW header pressure >61 psig with only 3 pumps operating in parallel.

RCW header pressure >59 psig with only 4 pumps operating in parallel.

RCW header pressure >58 psig with only 5 pumps operating in parallel.

RCW header pressure >57 psig with 6 or more pumps operating in parallel.

BOP Starts Raw Cooling Water Pump C, Stops A and places D or E in Standby Driver Driver If dispatched to Raw Cooling Water Pumps report Oil levels are normal pump ready for start, after start report no abnormal leaks, pump operating normally.

3-22 Rev 0 Page 9 of 55 XII.

Simulator Event Guide:

Event 2: Raise Power with Recirc flow SRO Notify ODS of power increase Direct Power increase using Recirc Flow per 3-GOI-100-12

[20] WHEN desired to restore Reactor power to 100%, THEN PERFORM the following as directed by Unit Supervisor and recommended by the Reactor Engineer:

RAISE power using control rods or core flow changes. REFER TO 3-SR-3.3.5(A) and 3-OI-68.

MONITOR Core thermal limits using Illustration 1, ICS, and/or 0-TI-248 ATC Raises Power w/Recirc using 3-GOI-100-12 and 3-OI-68, section 6.2

[1] IF NOT in single loop operation, THEN ADJUST Recirc Pump speeds 3A using, RAISE SLOW (MEDIUM), 3-HS-96-15A(15B)

AND/OR ADJUST Recirc Pump speed 3B using, RAISE SLOW (MEDIUM), 3-HS 16A(16B)

[2] WHEN desired to control Recirc Pumps 3A and/or 3B speed with the RECIRC MASTER CONTROL, THEN ADJUST Recirc Pump speed 3A & 3B using the following push buttons as required:

RAISE SLOW, 3-HS-96-31 RAISE MEDIUM, 3-HS-96-32 NRC When satisfied with Reactivity Manipulation; an additional reactivity manipulation will be required when Control Rod 30-47 drifts out and for the fuel failure.

SRO Notify ODS of power increase Driver Driver When directed by lead examiner insert trigger 1, to start suppression pool leak

3-22 Rev 0 Page 10 of 55 XII.

Simulator Event Guide:

Event 3:

RHR A Suppression Pool Leak BOP/AT C

Respond to Annunciator RHR LOOP I PUMP ROOM FLOOD LEVEL HIGH, A. DISPATCH personnel to visually check the RHR pump room.

B. IF alarm is valid, THEN PERFORM the following

VERIFY the floor drain sump pumps running.

VERIFY the floor drains for proper drainage.

IF possible, THEN DETERMINE the source of the leak and the leak rate.

ENTER 3-EOI-3 FLOWCHART.

BOP/AT C

Respond to Annunciator DRYWELL TO SUPPR CHAMBER. DIFF PRESS ABNORMAL A. CHECK alarm by checking Drywell to Suppression Chamber DP.

B. REFER TO 1-AOI-64-1.

C. REFER TO Tech Spec Section 3.6.2.6.

BOP/AT C

Dispatch personnel to RHR Loop 1 area SRO Evaluates Tech Spec 3.6.2.6 and Enters EOI-3 Driver Driver 3 minutes after dispatched report leak is between 3-FCV-74-1 RHR Pump 3A Suppression Pool Suction Valve and RHR Pump 3A, appears leak was caused by maintenance work in the area. When the crew closes 74-1 report leak has slowed; some minor leakage or residual leakage remains. Change PC14 to.01 In addition report water level is about 3 to 5 inches in this quad and there is a few inches in the suppression chamber area.

BOP/AT C

Respond to Annunciator SUPPR CHMB RM FLOOD LEVEL HIGH A. DISPATCH personnel to VISUALLY CHECK the suppression chamber room.

B. IF alarm is valid, THEN PERFORM the following:

CHECK the floor drain sump pumps running.

CHECK the floor drains for proper drainage.

IF possible, THEN DETERMINE the source of the leak and the leak rate.

ENTER 3-EOI-3 FLOWCHART.

CT #3 SRO When report of leak source is reported direct BOP to close 74-1 RHR Pump 3A Suppression Pool Suction Valve CT #3 BOP Close 74-1 RHR Pump 3A Suppression Pool Suction Valve

3-22 Rev 0 Page 11 of 55 XII.

Simulator Event Guide:

Event 3:

RHR A Suppression Pool Leak SRO EOI-3 Secondary Containment Water Level Monitor and Control Secondary CNTMT Water Levels Answers Yes to Is Any Area Water Level Above 2 inches Answers Yes to Is Any Floor Drain Sump Water Level Above 66 inches.

Restores and Maintains floor drain sump levels and area water levels using all available sump pumps When source of leak is determined and isolated answers yes to can all floor drain and area water levels be restored and maintained.

BOP/AT C

Contact Radwaste to determine status of sump Pumps Driver Driver Report sump pumps in area of alarm are operating normally, after 74-1 is isolated delete overrides on alarms xa554c[3] alarm_on and ior xa554c[17] alarm_on SRO EOI-3 Temperature Monitor and Control Secondary Containment Temperatures Operate all available ventilation (Appendix 8F)

Defeat isolation interlocks as necessary (Appendix 8E)

Answers No to Is Any Area Temperature Above Max Normal SRO EOI-3 Radiation Monitor and Control Secondary CNTMT Radiation Levels Answers No to Is Any Area Radiation Level Above Max Normal Driver Driver Upon Lead examiner direction, initiate Trigger 5 for Shutdown Board B Supply Breaker Trip

3-22 Rev 0 Page 12 of 55 XII.

Simulator Event Guide:

Event 4:

Shutdown Board B Supply Breaker Trip Crew Respond to numerous Annunciators the key ones being 4KV SHUTDOWN BD 3EB DEGRADED VOLTAGE, A. VERIFY Diesel starts and ties to board, if required.

B. REFER TO 0-OI-57A and Tech Spec Section 3.8.1.

4160V SD BD 3EB DEGRADED VOLTAGE A. VERIFY unit in stable condition by checking:

1. Auto actions has occurred and diesel at rated frequency and voltage.

2. Diesel connects properly to assigned 4160V Shutdown Bd.

3. Diesel reaches proper loading when supplying equipment feed from board.

BOP/SR O

Recognize loss of Shutdown Board 3EB with a failure of the 3B Diesel Generator to start BOP Recommend or start DG 3B SRO Concur with start of DG 3B or have BOP start DG 3B BOP Report DG 3B started and energized Shutdown Board 3EB Driver Driver Once crew energizes the bus report trip of supply breaker due to staging of equipment by contractor personnel, inadvertently bumped breaker with hand truck.

BOP Responds to remaining annunciators which will reset and clear once DG 3B is started.

BOP Reports other annunciators are clear and were 480 volt alarms due to loss of 4 KV Shutdown Board 3EB ATC/BO P

Determine what equipment tripped on the loss of Shutdown Board 3EB Driver Driver While the SRO and BOP are addressing the loss of Shutdown Board B insert trigger 8 for trip of RBCCW Pump 3B, after the RBCCW Pump Trips delete the malfunction sw02.

3-22 Rev 0 Page 13 of 55 XII.

Simulator Event Guide:

Event 4:

Shutdown Board B Supply Breaker Trip SRO Evaluates Technical Specification 3.8.1 Condition B, B.1 Verify power availability from the offsite transmission network. 1 Hour AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND B.2 Declare required feature(s), supported by the inoperable Unit 3 DG, inoperable when the required feature(s) are inoperable. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from the discovery of Condition B concurrent with inoperability of redundant required feature(s) AND B.3.1 Determine OPERABLE Unit 3 DG(s) are not inoperable due to common cause failure. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR Perform SR 3.8.1.1 for OPERABLE DG(S). 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND B.4 Restore Unit 3 DG to OPERABLE status 7 days.

SRO Evaluate Technical Specification 3.6.2.3, 3.6.2.4, 3.6.2.5 3.6.2.3 Condition B, B.1 Restore one RHR suppression pool cooling subsystem to OPERABLE status. 7 days.

3.6.2.4 Condition B, B.1 Restore one RHR suppression pool spray subsystem to OPERABLE status. 7 days.

3.6.2.5 Condition B, B.1 Restore one drywell spray subsystem to OPERABLE status. 7 days.

Driver Driver While the SRO and BOP are addressing the loss of Shutdown Board B insert trigger 8 for trip of RBCCW Pump 3B, after the RBCCW Pump Trips delete the malfunction sw02.

3-22 Rev 0 Page 14 of 55 XII.

Simulator Event Guide:

Event 5:

RBCCW Pump 3B Trip ATC Respond to RBCCW Pump Trip Annunciators, RBCCW PUMP DISCH. HDR PRESS LOW and RBCCW 3-FCV-70-48 CLOSED, report trip of RBCCW Pump 3B ATC RBCCW PUMP DISCH. HDR PRESS LOW A. VERIFY 3-FCV-70-48 CLOSING/CLOSED.

B. VERIFY RBCCW pumps A and B in service.

C. VERIFY RBCCW surge tank low level alarm is reset.

D. DISPATCH personnel to check the following:

RBCCW surge tank level locally.

RBCCW pumps for proper operation.

E. REFER TO 3-AOI-70-1 for RBCCW System failure and 3-OI-70 for starting spare pump.

SRO Enter 3-AOI-70-1 Loss of Reactor Building Closed Cooling Water ATC Immediate Actions

[1] IF RBCCW Pump(s) has tripped, THEN Perform the following (Otherwise N/A):

SECURE RWCU Pumps.

VERIFY RBCCW SECTIONALIZING VLV, 3-FCV-70-48 CLOSED.

ATC Secures RWCU Pumps and verifies 3-FCV-70-48 closes

3-22 Rev 0 Page 15 of 55 XII.

Simulator Event Guide:

Event 5:

RBCCW Pump 3B Trip ATC Respond to RBCCW Pump Trip Annunciators, RBCCW PUMP DISCH. HDR PRESS LOW and RBCCW 3-FCV-70-48 CLOSED, report trip of RBCCW Pump 3B SRO 4.2 Subsequent Actions

[1] IF Reactor is at power AND Drywell Cooling cannot be immediately restored, AND core flow is above 60%,THEN: (Otherwise N/A):

[1.1] REDUCE core flow to between 50-60%.

[1.2] MANUALLY SCRAM the Reactor and PLACE Mode Switch to SHUTDOWN.

REFER TO 3-AOI-100-1.

[1.3] SHUT DOWN both Recirc Pumps.

DEPRESS RECIRC DRIVE 3A SHUTDOWN, 3-HS-96-19.

DEPRESS RECIRC DRIVE 3B SHUTDOWN, 3-HS-96-20.

[1.4] INITIATE a 90°F/HR cooldown rate. REFER TO 3-AOI-100-1.

[2] IF any EOI entry condition is met, THEN ENTER appropriate EOI(s) (otherwise N/A).

ATC Subsequent Actions

[3] IF RBCCW Pump(s) has tripped and it is desired to restart the tripped RBCCW pump, THEN PERFORM the following:

[3.1] INSPECT the tripped RBCCW pump and its associated breaker for any damage or abnormal conditions.

[3.2] IF no damage or abnormal conditions are found, THEN ATTEMPT to restart tripped RBCCW pump(s).

[4] IF unable to restart a tripped pump, THEN: PLACE Spare RBCCW Pump in service. REFER TO 3-OI-70.

[5] IF RBCCW flow was restored to two pump operation by placing the Spare RBCCW pump in service in the preceding step, THEN PERFORM the following:

[5.1] REOPEN RBCCW SECTIONALIZING VLV, 3-HS-70-48A

[5.2] RESTORE the RWCU system to operation. (REFER TO 3-OI-69)

3-22 Rev 0 Page 16 of 55 XII.

Simulator Event Guide:

Event 5:

RBCCW Pump 3B Trip ATC Starts RBCCW Pump 3A or 3B, opens 3-FCV-70-48 and dispatches personnel to RBCCW Pumps / Breaker Driver Driver If requested wait 2 minutes report surge tank level normal and stable in middle of band.

If requested to verify position of RBCCW Pump 3A discharge valve wait 2 minutes and report valve is open.

If requested, wait 2 minutes and report RBCCW Pump 3B breaker (480 volt SD BD 3B) is tripped if Pump was not started; if 3B RBCCW Pump was started, report nothing abnormal.

If requested wait 2 minutes and report prior to a pump start nothing abnormal at pump or breaker for RBCCW 3B SRO Concurs with start of RBCCW Pump 3A or 3B and prioritizes recovery plan for RWCU SRO 3.4.1 Notifies Chemistry that continuous monitoring is no longer available and to commence sampling per TRM Surveillance 3.4.1.1, Monitor reactor coolant activity 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months when the continuous conductivity monitor is inoperable and the reactor is not in MODE 4 or 5

[6] IF RBCCW loss is partial, THEN CONTROL OR REDUCE Drywell and Recirc Pump Temperatures.(Otherwise N/A) REFER TO 3-GOI-100-12A

[6.1] REDUCE Recirculation flow as necessary until 50-60% core flow is reached.

[6.2] INSERT control rods per 3-SR-3.1.3.5(a) as directed by Reactor Engineer until below 66.7% rod line.

[6.3] REDUCE Recirculation flow as necessary until minimum core flow is reached.

[6.4] INSERT control rods per 3-SR-3.1.3.5(a) as directed by Reactor Engineer.

[7] IF RBCCW Surge Tank level is low, THEN: (Otherwise N/A):

[8] VERIFY all available Drywell Coolers in service. REFER TO 3-OI-64.

[9] IF RBCCW PUMP SUCTION HDR TEMP, 3-TIS-70-3 (Panel 3-9-4), cannot be maintained below 105°F, THEN: (Otherwise N/A):

[11] MONITOR Drywell Temperature on 3-XR-64-50 (Panel 3-9-3).

[12] MONITOR the following Recirc Pump and Motor 3A(3B) Winding and Bearing Temperatures on 3-TR-68-71 (Panel 3-9-21):

Driver Driver Upon Lead examiner direction, initiate Trigger 15 for Control Rod 30-47 drift out

3-22 Rev 0 Page 17 of 55 XII.

Simulator Event Guide:

Event 6:

Control Rod 30-47 Drift Out

3-22 Rev 0 Page 18 of 55 ATC Report CONTROL ROD DRIFT on Control Rod 30-47 A. DETERMINE which rod is drifting from Full Core Display.

B. IF no control rod motion is observed, THEN RESET rod drift as follows:

1. PLACE ROD DRIFT ALARM TEST switch, 3-HS-85-3A-S7, in RESET and RELEASE.

C. IF rod drifting in, THEN REFER TO 3-AOI-85-5.

D. IF rod drifting out, THEN REFER TO 3-AOI-85-6.

E. REFER TO Tech Spec Section 3.1.3, 3.10.8.

SRO Enter 3-AOI-85-6 Rod Drift Out ATC 4.1 Immediate Actions

[1] IF multiple control rod drifts are identified, THEN MANUALLY SCRAM the reactor and enter 3-AOI-100-1.

Subsequent Actions

[1] IF a Control Rod is moving from its intended position without operator actions, THEN SELECT the drifting control rod and INSERT to the FULL IN (00) position.

[2] IF control rod drive does NOT respond to INSERT signal, THEN PERFORM the following:

SRO

[3] NOTIFY the Reactor Engineer to Evaluate Core Thermal Limits and Preconditioning Limits for the current Control Rod pattern.

Driver Driver Acknowledge Reactor Engineer communication, when control rod 30-47 is being driven in to 00 deletes the malfunction rd04r3047 and rd23 ATC

[4] IF another Control Rod Drift occurs before Reactor Engineering completes the evaluation, THEN

[5] IF the control rod will not latch into position 00 and continues to demonstrate occurrences of inadvertent withdrawal, THEN INSERT and MAINTAIN control rod at position 00. (Otherwise N/A)

SRO

[6] REMOVE associated HCU from service per 3-OI-85.

BOP/ATC Dispatch personnel to remove HCU 30-47 from service Driver Driver When dispatched to remove HCU from service wait 4 minutes and report HCU 30-47 removed from service

3-22 Rev 0 Page 19 of 55 XII.

Simulator Event Guide:

Event 6:

Control Rod 30-47 Drift Out SRO

[7] EVALUATE Tech Spec 3.1.3.

[8] INITIATE Service Request/Work Order.

SRO Evaluate Technical Specification 3.1.3 Condition C, C.1 Fully insert inoperable control rod 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months AND C.2 Disarm the associated CRD 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

[9] NOTIFY Reactor Engineer to perform the following for current condition:

EVALUATE condition of core to assure no resultant fuel damage has occurred.

EVALUATION of impact on thermal limits and PCIOMOR restraints.

DETERMINE if other control rods need to be repositioned in order to safely restore core symmetry to prevent local fuel damage.

[10] NOTIFY System Engineering to PERFORM 0-TI-20, Control Rod Drive System Testing and Troubleshooting to determine problem with faulty control rod.

[11] IF a manual scram was not inserted and Reactor Startup or Shutdown is not in progress, THEN VERIFY 3-GOI-100-12, Power Maneuvering, has been entered if a power change occurred.

SRO Enters 3-GOI-100-12 Power Maneuvering SRO No Actions in Power Maneuvering

3-22 Rev 0 Page 20 of 55 XII.

Simulator Event Guide:

Event 7:

Fuel Failure Crew Respond to Fuel Failure annunciators TURBINE BLDG AREA RADIATION HIGH, OG AVG ANNUAL RELEASE LIMIT EXCEEDED, OG PRETREATMENT RADIATION HIGH, MAIN STEAM LINE RADIATION HIGH BOP TURBINE 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.)

B. IF the TSC is NOT manned, THEN USE public address system to evacuate area where high airborne conditions exist.

D. NOTIFY RADCON.

E. MONITOR other parameters providing input to this annunciator frequently as these parameters will be masked from alarming while this alarm is sealed in.

BOP Determines monitors in alarm, evacuates affected areas SRO OG PRETREATMENT RADIATION HIGH A. VERIFY high radiation on following:

1. OFFGAS PRETREATMENT RADIATION recorder, 3-RR-90-157 on Panel 3-9-2.

2. OFFGAS RADIATION recorder, 3-RR-90-160 on Panel 3-9-2.

3. OG PRETREATMENT RAD MON RTMR, 3-RM-90-157 on Panel 3-9-10.

4. OFFGAS RAD MON RTMR, 3-RM-90-160 on Panel 3-9-10.

B. CHECK off-gas flow normal.

C. CHECK following radiation recorders and associated radiation monitors:

1. MAIN STEAM LINE RADIATION, 3-RR-90-135 on Panel 3-9-2.

2. OFFGAS POST-TREATMENT RADIATION, 3-RR-90-265 on Panel 3-9-2.

3. STACK GAS/CONT RM RADIATION FROM STACK GAS, 0-RR-90-147 on Panel 1-9-2.

SRO Has BOP Operator report Off Gas readings

3-22 Rev 0 Page 21 of 55 XII.

Simulator Event Guide:

Event 7:

Fuel Failure SRO OG PRETREATMENT RADIATION HIGH D. NOTIFY RADCON.

E. REQUEST Chemistry perform radiochemical analysis to determine source.

F. IF Offgas System Isolation Valve, 3-FCV-66-28 is manually restrained in the OPEN position and it has been determined that this is a valid alarm, THEN UNRESTRAIN Offgas System Isolation Valve, 3-FCV-66-28.

G. REFER TO 0-SI-4.8.B.1.a.1 and 1(2)(3)-SR-3.4.6.1(A) for ODCM compliance and to determine if power level reduction is required.

H. IF directed by Unit Supervisor, THEN REDUCE reactor power to maintain off-gas radiation within ODCM limits.

SRO Directs a Urgent Load Reduction per Reactivity Control Plan and notifies Chemistry and Radcon ATC Urgent Load Reduction:

1A. Lower power by reducing core flow until either the desired operating power level is reached or core flow is 60% of rated core flow.

ATC If additional power reduction is directed then 2A. Insert control rods by groups per Emergency Shove Sheet till either the desired power level is reached or 3 rod groups are inserted.

SRO Determine a point when a Reactor Scram will be directed SRO MAIN STEAM LINE RADIATION HIGH-HIGH A. VERIFY alarm on 3-RM-90-136 thru 137 on Panel 3-9-10.

B. CONFIRM main steam line radiation level on recorder 3-RR-90-135, Panel 3 2.

C. IF alarm is VALID and scram has NOT occurred, THEN PERFORM the following:

IF core flow is above 60%, THEN

1. LOWER core flow to between 50-60%.

2. MANUALLY SCRAM the Reactor.

3. REFER TO 3-AOI-100-1.

Crew Once MSL Radiation High High is received if the reactor is not scrammed it will be required to scram.

3-22 Rev 0 Page 22 of 55 XII.

Simulator Event Guide:

Event 7:

Reactor Scram SRO MAIN STEAM LINE RADIATION HIGH-HIGH D. IF plant conditions DO NOT require the execution of 3-C-5, Power/Level Control, THEN VERIFY the MSIVs CLOSED.

ATC Scrams the Reactor and places the Mode Switch in Shutdown Reports all Rods inserted SRO Enters EOI-1 RPV Control on the scram SRO Directs BOP Operator to close MSIVs BOP Closes MSIVs SRO EOI-1 Level Directs PCIS Isolations Verified ATC/BO P

Verifies PCIS isolations CT#2 SRO Directs a Level Band of +2 to +51 inches using RCIC or HPCI CT#2 ATC/BO P

Starts RCIC or HPCI and maintains reactor level in prescribed band ATC If HPCI is started the Controller will fail and the Operator will have to take manual control too maintain Reactor Level.

SRO EOI-1 Pressure SRO Directs a Pressure Band between 500 to 1000 psig on SRVs (expect 800 to 1000 psig)

ATC/BO P

Maintain prescribed pressure band with SRVs

3-22 Rev 0 Page 23 of 55 XII. Simulator Event Guide:

Event 7:

EOI-3 Crew Recognize increasing radiation levels in Secondary Containment due to the start of RCIC or HPCI, Enter EOI-3 Secondary Containment Control SRO Enter EOI-3 on Secondary Containment Area Radiation 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 P

Verifies Reactor Zone and Refuel Zone Ventilation Systems isolated 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. Defeat isolation interlocks if necessary Appendix 8E.

If ventilation isolated and below 72 mr/hr directs Operator to perform Appendix 8F ATC/BO P

3-EOI Appendix-8F

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.

Driver Driver If requested wait 3 minutes and report Appendix 8E complete, enter bat app08e

3-22 Rev 0 Page 24 of 55 XII.

Simulator Event Guide:

Event 7:

EOI-3 ATC/BO P

3-EOI Appendix-8F

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.

SRO EOI-3 Secondary Containment Temperature Monitor and Control Secondary Containment Temperature Operate available ventilation per Appendix 8F Answers No to Is Any Area Temp Above Max Normal 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

3-22 Rev 0 Page 25 of 55 XII.

Simulator Event Guide:

Event 7:

EOI-3 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 Directs Operator to determine if a System is discharging to the affected areas ATC/BO P

Reports no indication of a system discharging to the area SRO Answers No to Will Emergency Depressurization Reduce Discharge Into Secondary Containment Answers No to Are Radiation Levels in 2 or more Areas Above Max Safe

3-22 Rev 0 Page 26 of 55 XII.

Simulator Event Guide:

Event 7:

EOI-2 SRO Enters EOI-2 on Suppression Pool Level or Temperature due to SRV Operation and RCIC EOI-2 Drywell Temperature SRO Monitor and Control DW Temp Below 160°F using available DW Cooling Answers Yes to Can Drywell Temp Be Maintained Below 160°F 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 Yes to Can PC Pressure Be Maintained Below 2.4 psig 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 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 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 Directs Suppression Pool Cooling per Appendix 17A

3-22 Rev 0 Page 27 of 55 XII.

Simulator Event Guide:

Event 7:

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.

3-22 Rev 0 Page 28 of 55 XII.

Simulator Event Guide:

Event 7:

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

3-22 Rev 0 Page 29 of 55 XII.

Simulator Event Guide:

Event 7:

EOI-2 ATC/BO P

Initiates Suppression Pool Cooling per Appendix 17A

1. IF Adequate core cooling is assured, OR Directed to cool the Suppression Pool 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.

2. PLACE RHR SYSTEM I(II) in Suppression Pool Cooling as follows:

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

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

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

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

e. IF LPCI INITIATION Signal exists, THEN MOMENTARILY PLACE 3-XS-74-121(129), RHR SYS I(II) CTMT SPRAY/CLG VLV SELECT in SELECT.

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

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

h. VERIFY desired RHR pump(s) for Suppression Pool Cooling are operating.

3-22 Rev 0 Page 30 of 55 XII.

Simulator Event Guide:

Event 8:

RCIC Steam Leak with out Isolation Crew Recognize rising RCIC Room Temperatures and Radiation Levels RCIC STEAM LINE LEAK DETECTION TEMP HIGH A. CHECK RCIC temperature switches on LEAK DETECTION SYSTEM TEMPERATURE indicator, 3-TI-69-29 on Panel 3-9-21.

B. IF RCIC is NOT in service AND 3-FI-71-1A(B), RCIC STEAM FLOW indicates flow, THEN ISOLATE RCIC and VERIFY temperatures lowering.

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

D. CHECK CS/RCIC ROOM El 519 RX BLDG radiation indicator, 3-RI-90-26A on Panel 3-9-11 and NOTIFY RADCON if rising radiation levels are observed.

ATC/BO P

Verifies RCIC STEAM LINE INBD ISOLATION VLV, 3-FCV-71-2 and RCIC STEAM LINE OUTBD ISOLATION VLV, 3-FCV-71-3 close Attempt to isolate RCIC Steam Supply Valves Report RCIC fails to isolate SRO EOI-3 Answers Yes to Will Emergency Depressurization Reduce Discharge Into Secondary Containment Proceeds to the STOP sign for When Radiation Levels In 2 or More Areas are Above Max Safe Then Continue OR Proceeds to the STOP sign for When Temperatures In 2 or More Areas are Above Max Safe Then Continue Crew Monitor for Max Safe Radiation and Temperature CT#1 ATC/BO P

Report Two Areas above Max Safe Radiation Levels CT#1 SRO Determines Emergency Depressurization is Required Transitions to 3-C-2 Emergency Depressurization

3-22 Rev 0 Page 31 of 55 XII.

Simulator Event Guide:

Event 8:

Emergency Depressurization SRO Enter 3-C-2 Emergency Depressurization Answers Yes to Will the Reactor Remain Subcritical Without Boron Under All Conditions Answers No to Is Drywell Pressure Above 2.4 psig Answers Yes to Is Suppression Pool Level Above 5.5 feet Directs All ADS Valves Open ATC/BO P

Opens 6 ADS Valves Reports 2 ADS Valves failed to Open SRO Answers No to Can 6 ADS Valves Be Opened Directs Opening of Additional MSRVs as necessary to establish 6 MSRVs Open ATC/BO P

Opens 2 MSRVs SRO Answers Yes to Are At Least 4 MSRVs Open CT#2 SRO Direct Reactor Level Restored to +2 to +51 inches with Condensate or Core Spray or RHR CT#2 ATC/BO P

Restore Reactor Level to prescribed level band SRO Emergency Plan Classification is 3.1-S or 3.2-S

3-22 Rev 0 Page 32 of 55 XIII.

Crew 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 33 of 55 XIV.

Scenario Verification Data EVENT TASK NUMBER K/A RO SRO 1

Rotate Raw Cooling Water Pumps RO U-024-NO-03 400000 A4.01 3.1 3.0 2

Raise Power with Recirc Flow RO U-000-NO-06 202002 A4.07 3.3 3.3 SRO S-000-AD-31 3

Suppression Pool Leak RO U-77A-AL-01 223001A2.11 3.6 3.8 SRO S-000-EM-07 4

B Shutdown Board Failure RO U-082-AL-19 264000A3.01 3.0 3.1 SRO S-57C-AB-01 5

RBCCW Trip RO U-070-AB-01 295018AA1.01 3.3 3.4 SRO S-070-AB-01 6

Control Drift Out RO U-085-AB-06 201003A2.03 3.4 3.7 SRO S-085-AB-06 7

Fuel Failure RO U-090-AL-04 272000A2.01 3.7 4.1 SRO S-066-AB-02 8

RCIC Steam Leak RO U-000-EM-10 295033EA2.01 3.8 3.9 SRO S-000-EM-10

3-22 Rev 0 Page 34 of 55 XV.

SCENARIO REVIEW CHECKLIST SCENARIO NUMBER:

HLTS-3-22 7

Total Malfunctions Inserted:

List (4-8) 2 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) 1 EOI Contingencies used: List (0-3) 60 Run Time (minutes) 3 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:

RHR A is out of service and has been for 2 days and is expected to be returned to service tomorrow. All Tech Specs and Appendix R actions have been addressed.

RBCCW Pump 3A work is complete. RBCCW Pump 3A is aligned in preparation for return to service and the casing has been vented. Spare RBCCW Pump is currently aligned to Unit

3.

Operations/Maintenance for the Shift:

Alternate Raw Cooling Water Pumps per 3-OI-24 Raw Cooling Water System start Raw Cooling Water Pump C and secure Raw Cooling Water Pump A. Once completed then raise Reactor Power to 100% using flow IAW 3-GOI-100-12 section 5.0 step 20 and the Reactivity Control Plan. Units 1 and 2 are at 100% power.

Unusual Conditions/Problem Areas:

None

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

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

Browns Ferry NPP Scenario No.:

3-21 Op-Test No.:

ILT 1006 Examiners:

Operators:

SRO:

ATC:

BOP:

Initial Conditions:

Unit 3 is at 75% power. Unit 1 and 2 are at 100% power. Condensate Pump B and Condensate Booster Pump B are ready to be returned to service. RFPT C is out of service and preparations are underway to return it to service. Unit 3 DG A is out of service and clearanced out.

Turnover:

Return Condensate Pump B and Condensate Booster Pump B to service and then raise Reactor Power to 80% with Recirc and hold until RFPT C is returned to service.

Event No.

Malf. No.

Event Type*

Event Description 1

N-BOP N-SRO Start Condensate Pump B and Condensate Booster Pump B 2

R-ATC R-SRO Raise Power with Recirc 3

pc12d C-SRO C-BOP Belt shear on operating Reactor Zone Exhaust Fan 4

th03a C-ATC TS-SRO RWCU Leak / No Auto Isolation / Failure of Inboard Valve 5

eg13a C-BOP C-SRO Bus Duct cooling fan trip/ start standby fan 6

th03a C-ATC R-ATC TS-SRO Recirc Pump A Trip w/ power oscillations 7

th33a M-ALL Main Steam Line Break in Drywell with MSIV isolation 8

trg-21/22 C-BOP C-SRO Failure of Drywell Spray Valves to close 9

rc08 C-ATC C-SRO Failure of RCIC to Auto Start

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

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

Drywell sprays are initiated when suppression chamber pressure exceeds 12 psig, while in the safe region of the DSIL, prior to exceeding PSP, and RHR not required for adequate core cooling.

OR Drywell sprays are initiated while in the safe region of the DSIL, prior to exceeding 280°F, and RHR not required for adequate core cooling.

2 Drywell / suppression chamber sprays are secured before drywell / suppression chamber pressure drops below 0 psig.

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

3-21 Rev 0 Page 3 of 48 With the unit at 75% power the BOP operator will start Condensate Pump B and Condensate Booster Pump B. Upon completion the ATC will commence power increase to 80%.

When the NRC is satisfied with power maneuver, belt shear will occur on the Reactor Zone Exhaust Fan A. EOI-3 will be entered on Secondary Containment D/P. Once the other train of Reactor Zone Ventilation is started and Secondary Containment D/P is restored EOI-3 can be exited.

RWCU will experience a leak in RWCU HX Room with a failure of the inboard valve 69-1 to isolate, the outboard valve 69-2 will start to stroke close but will lose power in mid position. The ATC will have to close the 69-1 to isolate the penetration. SRO again will have to enter EOI-3 on high temperature in RWCU areas. Once isolated, temperatures will decrease and EOI-3 can be exited. SRO will need to evaluate Tech Specs for the failed penetration 3.6.1.3 Condition A and will need to deactivate the inboard isolation valve 69-1.

Once the plant is stable, Bus Duct Cooling Fan A will trip and the standby fan will fail to start in Auto. The BOP operator will start Bus Duct Cooling Fan B per 3-ARP-9-7A window 31 Gen Bus Duct Fan Failure.

Reactor Recirc Pump A will trip and small power oscillations will be observed. ATC will respond per 3-AOI-68-1A and close the tripped pumps discharge valve and insert control rods to exit region 2 of the power to flow map. Once control rod insertion is commenced power oscillations will be suppressed. The SRO will refer to Tech Spec 3.4.1 and enter Condition A.

A main steam line break in the drywell will raise drywell pressure. The crew will scram the reactor, all rods will insert and MSIVs will isolate. Pressure control will be on the SRVs and level control will be RCIC, which will fail to auto start but can be manually started. When Suppression Chamber pressure exceeds 12 psig the crew will spray the drywell. Drywell sprays will be secured prior to Drywell pressure lowering to 0 psig. The Drywell Spray valves will fail to close and the crew will have to secure the RHR Pumps to stop Drywell Sprays.

3-21 Rev 0 Page 4 of 48 VIII.

Console Operator Instructions A.

Scenario File Summary

1.

File:

batch and trigger files for scenario 3-21 Batch NRC201021

dg a out of service irf dg01a open imf dg01a ior zlo3hs2113ea9a[1] off

reactor zone exhaust fan a belt shear 2 to 3 minutes prior to alarm imf pc12d (e1 0) ior xa553d[32] (e1 30) alarm_on trg 2 nrc2010rxzone trg 2 = mor xa553d[32] alarm_off

rwcu leak imf cu04 (e5 0) 50 imf cu06 ior ypovfcv692 (e5 15) fail_now

reactor recirc pump a trip, power oscillations imf th03a (e10 0) imf cr02a (e10 30) 10 120 imf cr02b (e10 30) 10 120

bus duct cooling fan failure imf eg13a (e15 0)

3-21 Rev 0 Page 5 of 48

msiv isolation, scram imf rc08 ior ypomtroilpmp (e20 0) fail_cn_pow imf th33a (e20 0).8 15 imf th27e (e20 0) imf th27g (e20 40) ior zdihs7460a[2] (e21 0) open ior zdihs7461a[2] (e21 0) open ior zdihs7474a[2] (e22 0) open ior zdihs7475a[2] (e22 0) open ior zdihs7037a[4] (e25 0) start ior zdihs7038a[4] (e25 0) start ior zdihs7039a[4] (e25 0) start ior zdihs7040a[4] (e25 0) start ior zdihs7041a[4] (e25 0) start ior zdihs7042a[4] (e25 0) start ior zdihs7043a[4] (e25 0) start ior zdihs7044a[4] (e25 0) start ior zdihs7045a[4] (e25 0) start ior zdihs7046a[4] (e25 0) start imf pc17a (e25 0) 5 Reactor Zone Exhaust Fan Trigger zdihs6411a(5).eq. 1 IX. Console Operators Instructions Scenario 3-21 DESCRIPTION/ACTION Simulator Setup manual Reset to IC 182 Simulator Setup Load Batch Bat nrc201021 Simulator Setup manual Clearance out DG A Simulator Setup Verify Batch file loaded RCP required (75% - 80% w/Recirc flow) - Provide marked up copy of 3-GOI-100-12 RCP for Urgent Load Reduction

3-21 Rev 0 Page 6 of 48 X. Scenario Summary:

With the unit at 75% power the, BOP operator will start Condensate Pump B and Condensate Booster pump B. Upon completion, the ATC will commence power increase to 80%.

When the NRC is satisfied with power maneuver, belt shear will occur on the Reactor Zone Exhaust Fan A. EOI-3 will be entered on Secondary Containment D/P. Once the other train of Reactor Zone Ventilation is started and Secondary Containment D/P is restored, EOI-3 can be exited.

RWCU will experience a leak in RWCU HX Room with a failure of the inboard valve 69-1 to isolate; the outboard valve 69-2 will start to stroke close but will lose power in mid position. The ATC will have to close the 69-1 to isolate the penetration. SRO again will have to enter EOI-3 on high temperature in RWCU areas. Once isolated temperatures will decrease and EOI-3 can be exited. SRO will need to evaluate Tech Specs for the failed penetration 3.6.1.3 Condition A and will need to deactivate the inboard isolation valve 69-1.

Once the plant is stable Bus Duct Cooling Fan A will trip and the standby fan will fail to start in Auto, the BOP operator will start Bus Duct Cooling Fan B per 3-ARP-9-7A window 31 Gen Bus Duct Fan Failure.

Reactor Recirc Pump A will trip and small power oscillations will be observed. ATC will respond per 3-AOI-68-1A and close the tripped pumps discharge valve and insert control rods to exit region 2 of the power to flow map. Once control rod insertion is commenced power oscillations will be suppressed. The SRO will refer to Tech Spec 3.4.1 and enter Condition A.

A main steam line break in the drywell will raise drywell pressure. The crew will scram the reactor, all rods will insert and due to the steam leak, MSIVs will isolate. Pressure control will be on the SRVs and level control will be RCIC which will fail to auto start but can be manually started. When Suppression Chamber pressure exceeds 12 psig the crew will spray the drywell. Drywell sprays will be secured prior to Drywell pressure lowering to 0 psig. The Drywell Spray valves will fail to close and the crew will have to secure the RHR Pumps to stop Drywell Sprays.

3-21 Rev 0 Page 7 of 48 Terminate the scenario when the following conditions are satisfied or upon request of Lead Examiner.

All Control Rods are inserted Drywell has been sprayed Drywell Sprays have been terminated Reactor Level is being maintained

3-21 Rev 0 Page 8 of 48 XII.

Simulator Event Guide:

Event 1:

Start of Condensate Pump B SRO Directs Start of Condensate Pump B BOP 5.3.1 Start a Condensate Pump as follows:

[1] CHECK the following initial conditions are satisfied:

Condensate system in operation in accordance with this instruction.

Sufficient number of Demineralizers in service to accommodate the raised flow.

[2] REVIEW the precautions and limitations in Section 3.0.

[3] CHECK Condensate Pump Motor 3B oil level.

[4] START CONDENSATE PUMP 3B, using 3-HS-2-21A.

[5] PLACE additional Condensate Demins in service to maintain system D/P less than 40 psid, and individual Condensate Demin flow less than 3150 gpm. REFER TO 3-OI-2A.

Driver Driver Report Condensate Pump 3B oil level in middle of sight glass, no obstructions and personnel are standing clear for pump start.

BOP Determines additional condensate demins are not needed Driver Driver If called for Demin status report all demins in service

3-21 Rev 0 Page 9 of 48 XII.

Simulator Event Guide:

Event 1:

Start of Condensate Booster Pump B SRO Directs Start of Condensate Booster Pump B BOP 5.3.2 Start a Condensate Booster Pump as follows:

[1] CHECK the following initial conditions are satisfied:

Condensate system in operation in accordance with this instruction.

Three Demineralizers in service with their E valves full open, to accommodate system flow and to prevent the Demineralizer Bypass Valve from opening.

IF the Condensate Demin E Valves are pinned open, THEN EVALUATE if sufficient margin is available to prevent the Demineralizer Bypass Valve from opening.

[2] REVIEW the precautions and limitations in Section 3.0.

[4] IF starting Condensate Booster Pump 3B, THEN PERFORM the following:

[4.1] ENSURE adequate number of Condensate Pumps in-service prior to starting Condensate Booster Pump.

[4.2] VERIFY OPEN CNDS BSTR PUMP 3B SUCTION VLV, 3-SHV-002-0554.

[4.3] VERIFY oil tank level is greater than 3/4.

[4.4] At Junction Box 2069 TB El 557', START CONDENSATE BOOSTER PUMP 3B AUX OIL PUMP using 3-HS-002-0140.

[4.5] OPEN CNDS BSTR PMP B SEAL WTR DRAIN VLV, 3-DRV-002-1702B.

[4.6] WHEN a steady stream of water is observed flowing from the vent, THEN CLOSE CNDS BSTR PMP B SEAL WTR DRAIN VLV, 3-DRV-002-1702B.

[4.7] VERIFY OPEN CNDS BSTR PUMP 3B DISCH VLV, 3-SHV-002-0559.

[4.8] START CONDENSATE BOOSTER PUMP 3B, using 3-HS-2-62A.

Driver Driver Report Condensate Booster Pump 3B Suction Valve Open, Condensate Booster Pump 3B Discharge Valve Open, Condensate Booster Pump B oil levels in middle of sight glass and oil tank level is 7/8, Aux oil pump started and venting is complete.

3-21 Rev 0 Page 10 of 48 XII.

Simulator Event Guide:

Event 1:

Start of Condensate Booster Pump B BOP

[6] WHEN Condensate flow and pressure stabilizes, THEN RETURN the E valves for in-service Demineralizers to normal configuration for plant conditions.

[7] PLACE additional Condensate Demins in service to maintain system D/P less than 40 psid, and individual Condensate Demin flow less than 3150 gpm. REFER TO 3-OI-2A.

[8] VERIFY Condensate Booster Pump aux oil pumps shutdown, on the Condensate Booster Pumps which were started in Step 5.3.2[4.8].

[9] IF desired, THEN ALIGN Hydrogen Water Chemistry System to the Condensate System. REFER TO 3-OI-4, Hydrogen Water Chemistry System.

BOP Determines additional Demins are not required Contacts AUO to place Hydrogen Water Chemistry System Driver Driver Acknowledge notification for Hydrogen Water Chemistry

3-21 Rev 0 Page 11 of 48 XII.

Simulator Event Guide:

Event 2:

Raise Power with Recirc flow SRO Notify ODS of power increase Direct Power increase using Recirc Flow per 3-GOI-100-12

[19] IF desired to raise power with only two(2) Reactor feed pumps in service, THEN RAISE Reactor power, as desired, maintaining each Reactor Feedpump less than 5050 RPM.

ATC Raises Power w/Recirc using 3-GOI-100-12 and 3-OI-68, section 6.2

[1] IF NOT in single loop operation, THEN ADJUST Recirc Pump speeds 3A using, RAISE SLOW (MEDIUM), 3-HS-96-15A(15B)

AND/OR ADJUST Recirc Pump speed 3B using, RAISE SLOW (MEDIUM), 3-HS 16A(16B)

[2] WHEN desired to control Recirc Pumps 3A and/or 3B speed with the RECIRC MASTER CONTROL, THEN ADJUST Recirc Pump speed 3A & 3B using the following push buttons as required:

RAISE SLOW, 3-HS-96-31 RAISE MEDIUM, 3-HS-96-32 NRC When satisfied with Reactivity Manipulation; an additional reactivity manipulation will be required when the Reactor Recirc Pump trips Driver Driver Upon Lead examiner direction, initiate Trigger 1 for belt shear on Reactor Zone Exhaust Fan

3-21 Rev 0 Page 12 of 48 XII.

Simulator Event Guide:

Event 3:

Belt Shear on Reactor Building Zone Exhaust Fan A BOP Respond to annunciator REACTOR ZONE DIFFERENTIAL PRESSURE LOW A. IF the alarm is intermittent, THEN CHECK for high wind conditions (ex., >20 mph) on ICS.

B. IF high wind conditions CANNOT be confirmed, THEN REQUEST personnel to check local Reactor Building differential pressure.

C. IF alarm is due to high wind conditions, THEN EOI-3 entry is NOT required.

D. IF alarm is valid, THEN NOTIFY Unit Supervisor of 3-EOI-3 entry condition.

E. REQUEST personnel to check fans locally for any apparent problems.

F. REFER TO 3-OI-30B and PLACE standby fan in service to restore normal differential pressure.

BOP Determines high wind condition does not exist Proceeds to check conditions for Reactor Zone Ventilation on Panel 3-9-25 On Panel 3-9-25 determines that Reactor Zone Exhaust Flow indicates 0 SCFM Driver Driver When dispatched wait 2 minutes and report +4 inches on DP gauge, if asked to investigate fans 2 minutes later report belt shear on Exhaust Fan A SRO Direct placing standby train in service and Enter EOI-3 SRO No actions in EOI-3 but entry condition of above -.17 inches of water exceeded BOP 6.1 Alternating Reactor Zone Supply and Exhaust Fans

[1] VERIFY the Reactor Zone supply and exhaust fans are operating. REFER TO Section 5.1.

[2] REVIEW all Precautions and Limitations in Section 3.0

[3] IF Reactor Zone Supply and Exhaust Fans will NOT be operated in fast speed, THEN SHUT DOWN Steam Vault Exhaust Booster Fan. REFER TO Section 7.4. (N/A if Reactor Building Ventilation has been lost and it desired to run the booster fan to cool the steam tunnel).

3-21 Rev 0 Page 13 of 48 XII.

Simulator Event Guide:

Event 3:

Belt Shear on Reactor Building Zone Exhaust Fan A BOP

[4] PLACE REACTOR ZONE FANS AND DAMPERS Switch, 3-HS-64-11A, in OFF.

[5] VERIFY dampers close and fans stop as indicated by illuminated green lights above the following switches:

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

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

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

REACTOR ZONE EXH OUTBD ISOL DMPR, 3-HS-64-43

REACTOR ZONE FANS AND DAMPERS, 3-HS-64-11A

[6] PLACE REACTOR ZONE FANS AND DAMPERS Switch, 3-HS-64-11A, in SLOW B to start alternate fans.

Driver Driver After fan swap -.3 inches on DP gauge

[7] VERIFY dampers open and fans start as indicated by illuminated red lights above the following switches:

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

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

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

REACTOR ZONE EXH OUTBD ISOL DMPR, 3-HS-64-43

REACTOR ZONE FANS AND DAMPERS, 3-HS-64-11A

[8] IF fast speed Reactor Zone Supply and Exhaust Fan operation is required, five minutes should be allowed after slow start for the discharge dampers to FULLY OPEN, THEN

[8.1] PLACE REACTOR ZONE FANS AND DAMPERS switch, 3-HS-64-11A, in FAST B.

[8.2] VERIFY that the two green lights B remain extinguished and the two red lights B remain illuminated above REACTOR ZONE FANS AND DAMPERS Switch, 3-HS-64-11A.

[9] VERIFY the following conditions:

[9.1] VERIFY REACTOR ZONE PRESS DIFFERENTIAL Indicator, 3-PDIC-064-0002, on 3-LPNL-925-0213, located at R17-P El 639', indicates between -0.25 inches and -0.40 inches H2O.

[9.2] IF REACTOR ZONE PRESS DIFFERENTIAL Indicator, 3-PDIC-64-2, is NOT between -0.25 inches and -0.40 inches H2O, THEN REFER TO 3-AOI-30B-1, Reactor Building Ventilation Failure.

3-21 Rev 0 Page 14 of 48 XII.

Simulator Event Guide:

Event 3:

Belt Shear on Reactor Building Zone Exhaust Fan A SRO May enter 3-AOI-30B-1, Reactor Building Ventilation Failure.

BOP 4.2 Subsequent Actions

[1] IF any EOI entry condition is met, THEN ENTER the appropriate EOI(s).

(Otherwise N/A)

[2] IF building pressure is observed to be outside the normal limits of -0.25 to -0.40 inch H2O.

AND The ventilation systems have not ISOLATED, THEN PERFORM the following at Panel 3-9-25:

[2.1] CHECK the reactor and refuel zone exhaust flow path dampers 3-FCO-64-9, -

10, -43, and -42 open.

[2.2] CHECK Reactor Zone Exhaust Fan A(B) running.

[2.3] CHECK Refuel Zone Exhaust Fan A(B) running.

[2.4] CHECK the reactor and refuel zone supply flow path dampers 3-FCO-64-5, -

13, -6, and -14 open.

[2.5] CHECK Reactor Zone Supply Fan A(B) running.

[2.6] CHECK Refuel Zone Supply Fan A(B) running.

[3] IF a reactor zone ventilation fan is not running OR a damper is CLOSED, THEN START the alternate Reactor Zone supply and exhaust fans at panel 3-9-25 by placing the REACTOR ZONE FANS AND DAMPERS switch, 3-HS-64-11A, to Slow A (Slow B) position. (Otherwise N/A)

[4] IF a refuel zone ventilation fan is not running or a damper is closed, THEN START the alternate Refuel Zone supply and exhaust fans at panel 3-9-25 by placing the REFUELING ZONE FANS AND DAMPERS switch, 3-HS-64-3A, to Slow A (Slow B) position.

(Otherwise N/A)

[5] VERIFY STEAM VAULT EXH BOOSTER FAN running, RB El 565 Top of TIP Room. REFER TO 3-OI-30B.

Driver Driver Upon Lead examiner direction, initiate Trigger 5 for RWCU Leak

3-21 Rev 0 Page 15 of 48 XII.

Simulator Event Guide:

Event 3:

Belt Shear on Reactor Building Zone Exhaust Fan A SRO

[6] MONITOR and RECORD at 15-minute intervals MAIN STEAM LINE TUNNEL TEMP, 3-TIS-1-60A, on Panel 3-9-3.

[7] NOTIFY the Shift Manager if Main Steam Line temperature on 3-TIS-1-60A reaches 150°F and REFER TO 3-EOI-3.

BOP

[8] IF building pressure is more negative than -0.40 inch H2O, THEN CHECK all ventilation supply fan suction dampers open locally.

[9] IF building pressure is more positive than -0.25 inch H2O, THEN CHECK all ventilation exhaust fan discharge dampers open locally.

[10] CHECK locally all reactor and refuel supply and exhaust fans for normal operation:

A. Motors, drive belts, fans are working.

B. Dampers in ventilation flow path are open.

C. Dampers in shutdown flow path are closed.

[11] SHUT DOWN the malfunctioning ventilation equipment. REFER TO the appropriate operating instruction.

[12] START the alternate ventilation equipment. REFER TO the appropriate operating instruction.

[13] IF reactor building pressure CANNOT be maintained negative, THEN START Standby Gas Treatment. REFER TO 0-OI-65. (Otherwise N/A)

[14] WHEN the abnormal condition has been corrected, THEN PERFORM the following as applicable: (Otherwise N/A)

[14.1] RESTORE the Refuel Zone Ventilation System to normal operation. REFER TO 3-OI-30A.

[14.2] RESTORE the Reactor Zone Ventilation System to normal operation.

REFER TO 3-OI-30B.

[14.3] SHUT DOWN and RETURN the SGT System to standby readiness. REFER TO 0-OI-65, SGT System.

Driver Driver Upon Lead examiner direction, initiate Trigger 5 for RWCU Leak

3-21 Rev 0 Page 16 of 48 XII.

Simulator Event Guide:

Event 4:

RWCU Leak ATC Report alarm RWCU LEAK DETECTION TEMP HIGH A. IF this alarm is received in conjunction with RWCU ISOL LOGIC CHANNEL A TEMP HIGH [3-XA-55-5B, window 32] and RWCU ISOL LOGIC CHANNEL B TEMP HIGH [3-XA-55-5B, window 33], THEN EXIT this procedure and GO TO 3-ARP-9-5B.

ATC Report alarms RWCU ISOL LOGIC CHANNEL A TEMP HIGH, RWCU ISOL LOGIC CHANNEL A TEMP HIGH A. VERIFY alarm by checking:

1. ATUs on Panel 3-9-84 and 3-9-86, located in Aux Instrument Room.

2. RWCU LEAK DETECTION TEMP HIGH annunciator in alarm (3-XA-55-3D, Window 17).

3. Area temperature indications on LEAK DETECTION SYSTEM TEMPERATURE, 3-TI-69-29, on Panel 3-9-21.

4. ARMs 3-RR-90-1, 3-CONS-90-50A on Panel 3-9-2 and 0-MON-90-361 on Panel 1-9-2.

5. ICS HPTURB' & RWCU' mimics for the 834 and 835 temperature loops.

B. IF a leak is suspected, THEN MANUALLY ISOLATE RWCU or if RWCU automatically isolates, REFER TO 3-AOI-64-2A.

C. IF TIS-69-835B(D) indicates greater than 131°F, THEN ENTER 3-EOI-3.

D. REFER TO Tech. Spec. Table 3.3.6.1-1.

CT#3 ATC Reports RWCU Valve 69-1 failed to isolate and 69-2 started to close but has lost indication Closes 69-1 to stop RWCU Leak CT#3 SRO Directs Penetration Isolated or concurs with the closure of 69-1 SRO Enter EOI-3 and 3-AOI-64-2A BOP Dispatch Operator to 69-2 Breaker Driver Driver RWCU 69-2 Valve Breaker 250 DC RMOV BD 3B tripped, breaker will not reset, working with RP to gain access to 69-2 Valve.

Driver Driver Upon Lead examiner direction, initiate Trigger 15 for Bus Duct Cooling Fan Trip

3-21 Rev 0 Page 17 of 48 XII.

Simulator Event Guide:

Event 4:

RWCU Leak SRO Enters 3-AOI-64-2A ATC 4.1 Immediate Actions

[1] VERIFY automatic actions occur.

[2] PERFORM any automatic actions which failed to occur.

SRO BOP BOP 4.2 Subsequent Actions

[1] IF any EOI entry condition is met, THEN ENTER appropriate EOI(s).

[2] CHECK the following to confirm high area temperature condition exists:

LEAK DETECTION SYSTEM TEMPERATURE, 3-TI-69-29 (Panel 3-9-21)

ATUs in Auxiliary Instrument Room

[3] IF isolation is caused by high area temperature, THEN DETERMINE if a line break exists by:

RWCU ARMs 3-RI-90-9A, 13A, and 14A

Visual Observation

Rx Zone Exhaust Rad Monitors 3-RE-90-142A, 142B, 143A, and 143B

[4] PERFORM necessary Heat Balance adjustments. REFER TO 3-OI-69.

BOP

[5] CHECK the following monitors for a rise in activity:

AREA RADIATION, 3-RR-90-1, Points 9, 13, and 14 (Panel 3-9-2)

AIR PARTICULATE MONITOR CONSOLE, 3-MON-90-50, 3-RM-90-55 and 57 (Panel 3-9-2)

RB, TB, and Refuel Zone Exhaust Rad on CHEMISTRY CAM, MONITOR CONTROLLER, 0-MON-90-361 (Panel 1-9-2)

[6] IF it has been determined that leakage is the cause of the isolation, THEN NOTIFY RADCON of RWCU status.

Driver Driver Acknowledge Notifications, when dispatched to ATUs report high temperatures in RWCU HX room and temperature lowering.

TE-69-838A(838C) - RWCU Heat Exchanger Room TE-69-839A(839C) - RWCU Heat Exchanger Room TE-69-838B(838D) - RWCU Heat Exchanger Room TE-69-839B(839D) - RWCU Heat Exchanger Room Driver Driver Upon Lead examiner direction, initiate Trigger 15 for Bus Duct Cooling Fan Trip

3-21 Rev 0 Page 18 of 48 XII.

Simulator Event Guide:

Event 4:

RWCU Leak BOP

[7] NOTIFY Chemistry that RWCU has been removed from service for the following evaluations:

The need to begin sampling Reactor Water

The need to remove the Durability Monitor from service SRO

[8] IF the isolation cannot be reset, THEN

[9] EVALUATE Technical Requirements Manual Section 3.4.1, Coolant Chemistry, for limiting conditions for operation.

Driver Driver Acknowledge Notifications SRO Evaluate Technical Specification 3.6.1.3 and TRM 3.4.1 3.6.1.3 Condition A and B, B.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange. 1 Hour 3.4.1 Notifies Chemistry that continuous monitoring is no longer available and to commence sampling per TRM Surveillance 3.4.1.1, Monitor reactor coolant activity 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months when the continuous conductivity monitor is inoperable and the reactor is not in MODE 4 or 5 SRO Enter EOI-3 Monitor and Control Secondary CNTMT Temperatures Operate available ventilation (Appendix 8F)

Defeat Isolation Interlocks if necessary (Appendix 8E)

BOP Verifies Reactor Zone Ventilation in service SRO Answers Yes to Is Any Area Temp Above Max Normal Isolate all systems that are discharging into the area except systems required to Be operated by EOIs Suppress a Fire Driver Driver Upon Lead examiner direction, initiate Trigger 15 for Bus Duct Cooling Fan Trip

3-21 Rev 0 Page 19 of 48 XII.

Simulator Event Guide:

Event 4:

RWCU Leak SRO EOI-3 Monitor and Control Secondary CNTMT Water Levels Answers No to Is Any Floor Drain Sump Water Level Above 66 inches Answers No to Is Any Area Water Level Above 2 inches SRO Monitor and Control Secondary CNTMT Radiation Levels Answers No to Is Any Area Radiation Level Above Max Normal Driver Driver Upon Lead examiner direction, initiate Trigger 15 for Bus Duct Cooling Fan Trip

3-21 Rev 0 Page 20 of 48 XII.

Simulator Event Guide:

Event 5:

Bus Duct cooling Fan Trip BOP Responds to alarm GEN BUS DUCT FAN FAILURE A. VERIFY Main Bus Cooling Fans, 3-HS-262-1A or 1-HS-262-2A, indicates running on Panel 3-9-8 AND START GEN BUS DUCT HX FAN A(B) using 3-HS-262-1A(2A), on panel 3-9-8 to start the standby fan.

B. IF no Fans are operating and the Generator is tied to the grid and loaded to greater than the self cooled bus rating of 16,500 amps THEN, IMMEDIATELY INSERT a manual reactor scram, AND TRIP the Main Generator.

C. IF while executing this procedure, the Bus Duct Temperature is at or above the Temperature Excursion limit of 120°C, THEN IMMEDIATELY INSERT a manual reactor scram, AND TRIP the Main Generator.

D. DISPATCH personnel as necessary to check the following:

1. Main Bus Cooling Fan on elevation 586 to check fan condition.

2. Monitor Bus Duct temperature by available means including using a portable temperature monitor device locally at the 14 in-service thermostats. REFER to Window 32, Figure 1.

3. 480V Unit Board 3A on elevation 586 to check breaker 5C closed.

4. 480V Unit Board 3B on elevation 604 to check breaker 5C closed.

E. VERIFY the system is operating in accordance with 3-OI-47.

BOP Start Standby Bus Duct Cooling Fan B and dispatches personnel SRO Concurs with start or directs start of Bus Duct Cooling Fan B BOP Dispatch personnel to breaker and bus duct cooling fans Driver Driver Breaker for bus duct cooling fan A is tripped, no abnormal indications apparent, if asked to reset breaker, breaker trips again, no problems noted at fans Driver Driver Upon Lead examiner direction, initiate Trigger 10 for Reactor Recirc Pump Trip

3-21 Rev 0 Page 21 of 48 XII.

Simulator Event Guide:

Event 6:

Reactor Recirc Pump A Trip with Power Oscillations

3-21 Rev 0 Page 22 of 48 ATC Respond to numerous alarm and Report Trip of RR Pump A REACTOR WATER LEVEL ABNORMAL VERIFY Reactor water level hi/low using multiple indications OPRM TRIP ENABLED C. IF this area was entered due to a Recirc Pump Trip,

ENTER 3-AOI-68-1A, RECIRC PUMP TRIP/CORE FLOW DECREASE OPRMs OPERABLE or 3-AOI-68-1B RECIRC PUMP TRIP/CORE FLOW DECREASE.

RECIRC DRIVE 3A TRIPPED A. VERIFY Recirc Drive 3A shutdown B. REFER TO 3-AOI-68-1A or 3-AOI-68-1B.

RECIRC LOOP A OUT OF SERVICE A. IF alarm was received due a trip of Recirculation Pump A, THEN REFER TO 3-AOI-68-1A or 3-AOI-68-1B AND 3-OI-68.

B. IF RECIRC Discharge Valve was closed to prevent reverse rotation, THEN WAIT five minutes and open RECIRC Discharge Valve as necessary to maintain RECIRC loop A temperature.

RECIRC DRIVE 3A PROCESS ALARM RECIRC LOOP A DIFF PRESS LOW RECIRC DRIVE 3A DRIVE ALARM RECIRC LOOP A FLOW LIMITER ENFORCING DRYWELL DIV II RAD MONITOR DOWNSCALE/INOP A. VERIFY alarm on Panel 3-9-55 by downscale reading on 3-RR-90-273.

B. COMPARE reading with 3-RR-90-272 on Panel 3-9-54.

4KV RECIRC PMP DRIVE AUTO XFR 4KV RECIRC PMP BD 3 UNDERVOLTAGE A. IF Reactor Recirc Pumps have tripped, THEN REFER TO 3-AOI-68-1A or 1B.

4KV MOTOR OVERLOAD CHECK Control Room for white light illuminated for affected equipment.

MOTOR TRIPOUT

1. CHECK Control Room for white disagreement light illuminated for affected equipment.

2. CLEAR disagreement light.

Driver Driver Upon Lead examiner direction, initiate Trigger 20 for DW MSL Leak and MSIV Isolation

3-21 Rev 0 Page 23 of 48 XII.

Simulator Event Guide:

Event 6:

Reactor Recirc Pump A Trip with Power Oscillations SRO Enter 3-AOI-68-1A Recirc Pump Trip/Core Flow Decrease OPRMs Operable ATC

[1] IF both Recirc Pumps are tripped in modes 1 or 2, THEN

[1.1] SCRAM the Reactor.

[2] IF a single Recirc Pump tripped, THEN CLOSE tripped Recirc Pump discharge valve.

Closes A Recirc Pump Discharge Valve ATC

[3] IF Region I or II of the Power to Flow Map is entered, THEN IMMEDIATELY take actions to INSERT control rods to less than 95.2% loadline.

Report in Region 2 of Power to Flow Map SRO Directs Load Line reduction to <95%

ATC Insert Rods per Emergency shove sheets until <95% power, Inserts rods 14-39, 46-39, 46-23, and 14-23.

Driver Driver When rod insertion begins delete power oscillations cr02a and cr02b SRO Directs RR Flow Increase

[4] RAISE core flow to greater than 45%.

[5] INSERT control rods to exit regions if not already exited. Refer to 0-TI-464, Reactivity Control Plan Development and Implementation.

[6] MAINTAIN operating Recirc pump flow less than 46,600 gpm.

ATC Raises RR Flow on B Pump to >45% but less than 46,600 Driver Driver As Reactor Engineer acknowledge request, any field investigation for pump trip report no obvious causes. Pump Breaker 4KV Recirc BD 3A Driver Driver Upon Lead examiner direction, initiate Trigger 20 for DW MSL Leak and MSIV Isolation

3-21 Rev 0 Page 24 of 48 XII.

Simulator Event Guide:

Event 6:

Reactor Recirc Pump A Trip with Power Oscillations ATC

[7] WHEN plant conditions allow, THEN MAINTAIN operating jet pump loop flow greater than 41 x 106 lbm/hr (3-FI-68-46 or 3-FI-68-48).

[8] IF Recirc Pump was tripped due to dual seal failure, THEN (Otherwise N/A)

[9] NOTIFY Reactor Engineer to PERFORM the following:

Tech Specs 3.4.1.

3-SR-3.4.1(SLO), Reactor Recirculation System Single Loop Operation.

0-TI-248, Core Flow Determination in Single Loop Operation SRO Evaluate Tech Spec for Single Loop Operation TS 3.4.1 Condition A, A.1 Satisfy the requirement of the LCO (Two recirculation loops with matched flows shall be in operation). 24 Hours

[10] WHEN the Recirc Pump discharge valve has been closed for at least five minutes (to prevent reverse rotation of the pump), OPEN Recirc Pump discharge valve as necessary to maintain Recirc Loop in thermal equilibrium.

ATC Opens Recirc Pump A discharge valve BOP

[11] REFER TO the following ICS screens to help determine the cause of recirc pump trip/core flow lowering. VFDPMPA(VFDPMPB), VFDAAL(VFDBAL)

[12] CHECK parameters associated with Recirc Drive and Recirc Pump/Motor 3A(3B) on ICS and 3-TR-68-71 to determine cause of trip.

BOP Dispatch personnel [13] PERFORM visual inspection of tripped Reactor Recirc Drive.

BOP Dispatch personnel [14] PERFORM visual inspection of Reactor Recirc Pump Drive relay boards for relay targets.

Driver Driver As Reactor Engineer acknowledge request, any field investigation for pump trip report no obvious causes. Pump Breaker 4KV Recirc BD 3A Driver Driver Upon Lead examiner direction, initiate Trigger 20 for DW MSL Leak and MSIV Isolation

3-21 Rev 0 Page 25 of 48 XII.

Simulator Event Guide:

Event 7:

Main Steam Line Break in Drywell ATC Reports alarm MAIN STEAM LINE CH A FLOW HIGH and rising Drywell Pressure and Temperature SRO Directs Reactor Scram and enters EOI-1 on Drywell Pressure ATC Scrams the Reactor and places the Mode Switch in Shutdown Reports all Rods in and MSIVs isolated SRO EOI-1 Level Directs PCIS Isolations Verified ATC/BO P

Verifies PCIS isolations SRO Directs a Level Band of +2 to 51 inches using RCIC or HPCI ATC/BO P

Starts RCIC or HPCI and maintains reactor level in prescribed band SRO EOI-1 Pressure SRO Directs a Pressure Band between 500 to 1000 psig on SRVs (expect 800 to 1000 psig)

ATC/BO P

Maintain prescribed pressure band with SRVs

3-21 Rev 0 Page 26 of 48 XII.

Simulator Event Guide:

Event 7:

Main Steam Line Break in Drywell SRO Enters EOI-2 on High Drywell Pressure EOI-2 Drywell Temperature Monitor and Control DW Temp Below 160°F using available DW Cooling SRO Answers No to Can Drywell Temp Be Maintained Below 160°F Directs BOP to operate all available Drywell cooling BOP Verifies all Drywell Blowers operating on panel 9-25 SRO Stops at the STOP sign Before Drywell Temperature rises to 280°F BOP On High Drywell Pressure report failure of HPCI to start, Aux Oil Pump will not start Crew Call for support to repair HPCI 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

3-21 Rev 0 Page 27 of 48 XII. Simulator Event Guide:

Event 7:

Main Steam Line Break in Drywell 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.

3-21 Rev 0 Page 28 of 48 XII.