ML102371246: Difference between revisions

[7.2]

EVALUATE starting one Condensate Booster Pump, based on MFP suction pressure or MFP vibration.

[7.3]

IF the Standby MFP is running, THEN SHUTDOWN the Standby MFP, and PLACE in Standby per S01-2 &

3.01.

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

Applicants Actions or Behavior NRC Scenario #

1 Event #

2 Page 4

of 58 Event

Description:

Auctioneered Tavg fails high.

Time 1

Position II Booth Instructor:

When directed, initiate Event 2 (Trigger 1)

Indications available:

Alarm 92A PZR Level Hi/Lo.

Alarm 94B Tavg-Tauct Deviation.

Auctioneered Tavg failed high on 1-TR-68-28.

Charging Flow rising.

Pressurizer Level rising.

C The crew should diagnose that there has been a failure re affecting Auctioneered Tavg.

May take Prudent Operator action lAW Tl-12.04 to place RO Charging (1-FCV-62-93) in manual and lower charging flow to normal.

Evaluator Note (1): The crew may go to either A01-2 MALFUNCTION OF REACTOR CONTROL S YSTEM or A01-20, MALFUNCTION OF PRESSURIZER LEVELCONTROL SYSTEM. (ARI-92A has a step which states: IF Malfunction Of Pressurizer Level Control System, THEN GO TO AOI-20)

Evaluator Note (2):

Following Steps are from A01-20, MALFUNCTION OF PRESSURIZER LEVELCONTROL S YSTEM.

1. CHECK pzr level program signal NORMAL:

LR-68-339 (green pen).

Perform RNO:

RO PERFORM the following:

a.

PLACE charging valve controller 1-HIC-62-93A in MAN, and RESTORE level to normal.

b.

IF letdown in service, THEN GO TO Step 10.

10. INITIATE repairs to failed instrument/circuitry.

I Aooendix D Reciuired Operator Actions Form ESD-2 I

Op Test No.:

Time Position 1 1. RETURN TO instruction in effect.

RO Evaluator Note:

Following Steps are from AOl-2 MALFUNCTION OF REACTOR CONTROL SYSTEM.

SRO Directs actions lAW AOI-2 MALFUNCTION OF REACTOR CONTROL SYSTEM 3.1 Diagnostics Diagnostics Goes to Subsection 3.2 NRC Scenario #

1 Event #

2 Page 5

of 58 Event

Description:

Auctioneered Tavg fails high.

Applicants Actions or Behavior IF GO TO Subsection Continuous Rod Withdrawal/Insertion 3.2 (Page 6)

Instrument failure (e.g. T-avg, NIS, PT-1-73) with Rod Control in MAN 3.2 (Page 6)

Dropped RCCA 3.3 (Page 11)

RCCA Misalignment 3.4 (Page 21)

Rod Position Indicator (RPI) Malfunction 3.5 (Page 39)

Failure of Control Rods to Move on Demand 3.6 (Page 42)

1. PLACE control rods in MAN.

2. CHECK control rod movement STOPPED.

3. MAINTAIN T-avg on PROGRAM. (Reference Attachment 1)

RO USE control rods.

OR ADJUST turbine load.

4. CHECK loop T-avg channels NORMAL.

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

Op Test No.:

NRC Scenario #

1 Event#

2 Page 6

of 58 Event

Description:

Auctioneered Tavg fails high.

Position Applicants Actions or Behavior Time II

5. CHECK Auct Tavg NORMAL on 1-TR-68-2B.

Perform RNO:

CONTROL pzr level in MAN with 1 -FCV-62-93.

(Reference Attachment 1)

RX TAVG-PZR POWER TREF LEVEL RO 2%

557.6 °F 25.7 %

4%

558.2 °F 26.4 %

6%

558.8 °F 27.1 %

8%

559.3 °F 27.8 %

10%

559.9 °F 28.5 %

12%

560.5 °F 29.2 %

14%

561.1 °F 29.9%

6. CHECK NIS power range channels NORMAL.

7. CHECK the following:

Turbine impulse pressure channel 1-Pl-1-73, NORMAL.

Tref and Auct Tavg NORMAL on 1 -TR-68-2B Perform RNO: (No actions required, since plant in Startup Mode)

BOP PLACE steam dumps in pressure mode as follows:

a.

PLACE steam dumps to OFF.

b.

PLACE mode selector HS to STEAM PRESS.

c.

ADJUST steam dump demand to zero.

d.

PLACE steam dumps to ON.

e.

ENSURE controller set at 84% (1092 psig).

f.

WHEN conditions allow, THEN REFER TO SOI-1.02 and PLACE steam dumps in TAVG Mode.

Appendix D Required Operator Actions Form ESD-2 Op Test No.:

NRC Scenario #

1 Event #

2 Page 7

of 58 Event

Description:

Auctioneered Tavg fails high.

Time Position Applicants Actions or Behavior

8. MONITOR core power distribution parameters:

Power range channels.

z\\ Flux Indicators.

T-avg.

RO Loop ET.

Incore TCs.

Feed flow/Steam flow.

Should be no changes SRO

9. INITIATE repairs to failed equipment.

10. REFER TO Tech Specs:

SRO none applicable.

At discretion of the Lead Examiner, proceed to the next event

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

Event

Description:

1 A CCS Pump trips.

1 B CCS pump fails to auto start on low pressure Applicants Actions or Behavior NRC Scenario #

1 Event #

3 Page 8

of 58 Time II Position Booth Instructor:

When directed, initiate Event 3 (Trigger 2)

Indications available:

CCS PMPS lA-A & lB-B DISCH PRESS LO [250C].

LOW FLOW (headers or individual equipment).

Breaker disagreement WHITE light on l-HS-70-46A CCS PMP lA-A Handswitch.

Alarm 226E ERCW/CCS Motor Tripout.

The crew should diagnose that there has been a failure Crew affecting CCS flow.

BOP May take Prudent Operator action lAW Tl-12.04 to start 1 B CCS Pump and place the 1A in PTL.

Evaluator Note: Following Steps are from AOl-15 Loss of Component Cooling Water Directs actions lAW AOl-i 5 Loss of Component Coo/mg Water 3.1 Diagnostics IF GOTO Loss of CCS Flow, Subsection 3.2 OR Surge tank level less than 60%

SRO or dropping uncontrolled.

Surge tank level greater than 72% or Subsection 3.3 rising uncontrolled OR CCS Rad Monitor alarm.

Loss of CCS due to loss of AC power train.

AOl-35 Goes to Subsection 3.2

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

NRC Scenario #

1 Event #

3 Page 9

of 58 Event

Description:

1A CCS Pump trips. lB CCS pump fails to auto start on low pressure Applicants Actions or Behavior Time II Position

1. CHECK CCS pumps status:

a.

CHECK any CCS pump TRIPPED or running pump NOT pumping forward:

ERCW/CCS Motor tripout alarm, Low header pressure (train A or B),

Multiple low flow alarms.

BOP b.

CHECK at least one U-i Train A header supply pump RUNNING AND pumping forward:

iA-A lB-B Should diagnose that 1A CCS Pump is tripped. Should perform RNO to start lB CCS

b. START available U-i Train A CCS Pump.

c. CHECK any Train B header supply pump RUNNING AND pumping forward:

BOP CS 2B-B Determines that B Train is operating properly d.

PLACE any non-operable or tripped CCS pump in BOP STOP/PULL-TO-LOCK.

e.

CHECK TWO U-iTrain A header supply pumps RUNNING:

iA-A lB-B BOP Perform RNO:

ENSURE at least one of the following CLOSED to avoid excessive flow:

RHR htx A, l-FCV-70-156, OR

SFP htx A, O-FCV-70-197.

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

NRC Scenario #

1 Event #

3 Page 10 of 58 Event

Description:

1A CCS Pump trips. lB CCS pump fails to auto start on low pressure Time Position Applicants Actions or Behavior f.

CHECK flows returned to NORMAL.

BOP Determines that flows returned to normal due to absence of alarms.

g.

CHECK A and B side surge tank levels between 57% and BOP 85%.

BOP h.

- GOTOStep15 BOP Evaluator Note:

AOl-15 Appendix A pages are at the end of this section (page_11).

BOP 15.

EVALUATE affected equipment operation_USING_Appendix_A.

16.

WHEN CCS returned normal, THEN CHECK only one CCS pump per Train. CHECK one TBBP running.

Will need to Perform RNO and stop and place one TBBP in P-Auto BOP IF 2 CCS pumps or 2 TBBPs running, THEN:

STOP second running CCS pump and Return HS to A-P AUTO.

STOP second running TBBP pump and Return HS to A-PUTO.

Evaluator Note: Following Steps are from ARI-1 1O-D LTDN TO DEMINS TEMP HI

[1]

IF letdown temperature is greater than 137.5 F on 1-Tl-62-78 [1-M-6], THEN Ij ENSURE CVCS demineralizers bypassed (lights above 1-HS-62-79

[1 -M-6]).

[2]

ENSURE letdown flow is 45 gpm to 120 gpm on 1-FI-62-82 [1-M-6].

[3]

ENSURE charging flow is 57 gpm to 132 gpm on 1-FI-62-93A

[1-M-5J.

I Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

NRC Scenario#

1 Event#

3 Page 11 of 58 Event

Description:

1A CCS Pump trips.

1 B CCS pump fails to auto start on low pressure Applicants Actions or Behavior Time H

Position After CCS is restored RO

[4]

ADJUST 1-HIC-62-78A to maintain letdown temperature less than 127 °F on 1-Tl-62-78.

[7]

WHEN ready to return to normal, THEN RO PLACE 1-HS-62-79A. LTDN HI TEMP DIVERT, in DEMIN position, and HOLD until 1-TCV-62-79 is fully open.

Evaluator Note: Following Steps are SRO Actions in A01-15

17. REFER TO Tech Specs 3.7.7, Component Cooling Water SRO System (CCS).

Enters LCQ 3.7.7 condition A for one train CCS inoperable.

18. INITIATE repairs.

SRO GO TO appropriate plant procedure.

When technical specifications have been identified or at discretion of the Lead Examiner, proceed to the next event

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

NRC Scenario #

1 Event #

3 Page 12 of 58 Event

Description:

1 A CCS Pump trips.

1 B CCS pump fails to auto start on low pressure Time Position Applicants Actions or Behavior AOI-15 WBN LOSS OF COMPONENT COOLING WATER (CCS)

Revision 30 Page27of3l APPENDIX A Page 1 of 2 HEADER CROSS-REFERENCE ESF EQUIPMENT IA COMPONENT NORMAL FLOW FLOW INDICATOR CCP IA Gear & Oil Clr 28 gpm 1-FI-70-146 SIP 1A Oil CIr 15 gpm 1-FI-70-147 CS Pump 1A Oil Clr 2 gpm 1-FI-70-150 RHR Pump 1A Seal Hx 1O gpm 1-FI-70-151 RHR Hx IA 5000 gpm 1-FI-70-158 ESF EQUIPMENT lB COMPONENT NORMAL FLOW FLOW INDICATOR CCP 18 Gear & Oil CIr 28 gpm 1-FI-70-145 SIP 18 Oil CIr 15 gpm 1-FI-70-148 CS Pump 18 Oil Clr 2 gpm 1-FI-70-149 RHR Pump lB Seal Hx 1O gpm 1-Fl-70-152 RHR Hx lB 5000 gpm 1-FI-70-155

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

Op Test No.:

NRC Scenario #

1 Event #

3 Page 13 of 58 Event

Description:

1 A CCS Pump trips.

1 B CCS pump fails to auto start on low pressure Time Position Applicants Actions or Behavior AOl-I 5 WBN LOSS OF COMPONENT COOLING WATER (CCS)

Revision 31 Page 28 of 31 APPENDIX A Page 2 of 2 HEADER CROSS-REFERENCE Equipment Affected by Isolation of the Rx Bldg or Misc Equip Hdr NOTE:

All listed equipment affected by isolation Misc Equip and Rx Bldg Hdrs.

COMPONENT ACTION RX BLDG HDR EQUIPMENT Excess Letdown Hx Remove from service USING SOI-62.01.

Stop RCP(s) if motor bearing rises to 195°F RCP Motor Bearings (alarm @ 185°F).

RCPs must be tripped within 10 minutes of loss of CCS to oil coolers.

Thermal Barrier Booster Pump Stop TB pumps. Check RCP seal temp & flow.

supply Post Accident Sampling Notify Chemistry.

MISC HDR EQUIPMENT Seal Water Hx Check VCT temp. Should be slight rise in seal supply temp (max 130°F).

Letdown Hx Isolate charging and letdown (Excess Letdown is NOT available).

Sample Hxs Notify Chemistry.

Waste Gas Compressor Remove from service USING SOI-77.02

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

Op Test No.:

Applicants Actions or Behavior NRC Scenario #

1 Event #

4 Page 14 of 58 Event

Description:

Dropped Control Rod Time II Position Booth Instructor:

When directed, initiate Event 4 & 5 (Trigger 3)

Indications available:

Alarm 87D Rod at Bottom Rod H-12 indicates fully inserted Reactor Power Nis lowering Cr The crew should diagnose that there has been a dropped ew Control Rod.

SRO The SRO may direct the reactor trip breakers to be opened at any time the crew believes the reactor is subcritical.

Evaluator Note: Following Steps are from AOI-2 MALFUNCTION OF REACTOR CONTROL SYSTEM Directs actions lAW AOI-2 MALFUNCTION OF REACTOR CONTROL SYSTEM 3.1 Diagnostics Diagnostics IF GO TO Subsection Continuous Rod Withdrawal/Insertion 3.2 (Page 6)

SRO Instrument failure (e.g. T-avg, NIS, PT-1-73) with Rod Control in MAN 3.2 (Page 6)

Dropped RCCA 3.3 (Page 11)

RCCA Misalignment 3.4 (Page 21)

Rod Position Indicator (RPI) Malfunction 3.5 (Page 39)

Failure of Control Rods to Move on Demand 3.6 (Page 42)

Goes to Subsection 3.3 1.

PLACE control rods in MAN.

I Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

NRC Scenario #

1 Event #

4 Page 15 of 58 Event

Description:

Dropped Control Rod Applicants Actions or Behavior Time Position

2. CHECK core power distribution parameters normal:

Power Range Channels AFlux Indicators Tavg RD Loop tT IncoreTCs Feed Flow/Steam Flow Continue with Step 4.

EVALUATOR NOTE: The following step will be required when the second rod drops into the core.

LEAD EVALUATOR NOTE:

Cue Console Operator to initiate Trigger 4 (2 rod drop) after Tech Spec evaluation, at your discretion.

4. IF two or more RCCAs have dropped, THEN:

RD

a. TRIP reactor.

b. GO TO E-O, Reactor Trip or Safety Injeclion.

5. ENSURE T-avg and T-ref within 3°F:

RD ADJUST turbine load and/or Boron concentration as necessary.

NO ACTION SHOULD BE PERFORMED

6. MONITOR core power distribution parameters:

Power range channels.

RD L\\Flux Indicators.

T-avg.

Core AT.

lncoreTCs.

Feed flow/Steam flow.

7. RESET any power range monitor POSITIVE RATE TRIP BOP window LIT, [1-M-13].

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

Op Test No.:

NRC Scenario #

1 Event

Description:

Dropped Control Rod Time II Position Event#

4 Page 16 of 58 I

Applicants Actions or Behavior NOTE If the reactor is subcritical, retrieval of a dropped rod is NOT the conservative action. Reactor Engineering evaluation should consider opening the reactor trip breakers.

8. NOTIFY Reactor Engineering to evaluate core anomaly.

9. NOTIFY STA to perform 1-Sl-0-21, Excore QPTR.

SRO Step is N/A.

10. REFER TO Tech Specs:

3.1.5, Rod Group Alignment Limits.

Tech Spec 3.1.5 applies 5.

toe rod not attAin alignment lirsts.

5.

conrinued) 3.1 Restore rod to withio alignment limits.

OR all.! Verify VIM as 3 1.60 616.

OR 1

hour 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 tsar SRO 6.2.1.2 AN) 6.2.2 RID 5.2.3 AND 6.2.1 Ant 1.2.5 003 6.2.6 ititiste horatiOn to restore 1DM to nithio unit Sedate THERMAL POWER 2 Soars ts S 015 RIP.

Verify 120 is o 1.60 h/h Pertorrr 103.2.1.1.

Pnrtorm 10 1.2.2.1.

seeoainate safety OCOIISPO and tsetire results renarn voice.

for duration of operatsor. under these cord i Chess.

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

Applicants Actions or Behavior NRC Scenario #

1 Event #

4 Page 17 of 58 Event

Description:

Dropped Control Rod Time Position II 1 1. RECORD the following information:

Time the RCCA dropped.

SRO Core location of RCCA.

Reactor power prior to dropping.

Affected RCCA height prior to dropping.

At discretion of the Lead Examiner, proceed to the next event

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

NRC Scenario #

1 Event #

5 & 6 Page 18 of 58 Event

Description:

2 Control Rod Drop, E-O, ES-O. 1 and 1 -PT-i -33 failure resulting in Steam Dumps opening Time Position Applicants Actions or Behavior Booth Instructor: When requested by Lead Evaluator, initiate Event 5 (Trigger 4)

Indications:

Rod C-5 drops into the core SRO Directs RO to manual trip the Reactor due to 2 dropped control rods.

Evaluator Note:

The following are steps from E-O.

NOTE 1 Steps 1 thru 4 are IMMEDIATE ACTION STEPS.

NOTE 2 Status Trees I SPDS should be monitored when transitioned to another instruction.

1. ENSURE reactor trip:

Reactor trip and bypass breakers OPEN.

RPIs at bottom of scale.

Neutron flux DROPPING.

2. ENSURE Turbine Trip:

All turbine stop valves CLOSED.

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

NRC Scenario #

1 Event #

5 & 6 Page 19 of 58 Event

Description:

2 d Control Rod Drop, E-O, ES-O.1 and 1-PT-1-33 failure resulting in Steam Dumps opening Time I

Position Applicants Actions or Behavior

3. CHECK 6.9 kV shutdown boards:

a. At least one board energized from:CSST (offsite), OR DIG (blackout).

4. CHECK SI actuated:

a. Any SI annunciator LIT.

Perform RNO:

DETERMINE if SI required:

a. IF ANY of the following exists:

SIG press less than 675 psig, OR

RCS press less than 1870 psig, OR

Cntmt press greater than 1.5 psig IF SI NOT required, THEN GO TO ES-0.1, Reactor Trip Response.

SRO Directs crew to ES-0.1, Reactor Trip Response.

Evaluator Note (1):

The following are steps from ES-O. 1, Reactor Trip Response.

Evaluator Note (2):

SRO should call STA to perform Status Trees MONITOR SI actuation criteria:

IF SI actuation occurs during the performance of this Instruction, THEN ** GO TO E-0, Reactor Trip or Safety Injection.

BOP CHECK Generator PCBs OPEN.

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

NRC Scenario #

1 Event #

5 & 6 Page 20 of 58 Event

Description:

2d Control Rod Drop, E-0, ES-0.i and 1-PT-i -33 failure resulting in Steam Dumps opening Time K

Position Applicants Actions or Behavior Evaluator Note:

The following RNO step will be required when Event 6(1-PT-i-33 high failure) occurs.

LEAD EVALUATOR NOTE:

Cue Console Operator to initiate Event 6 (1-PT-i-33 failure) at your discretion.

Due to the ramping of the malfunction and the initial steam pressure, it may take 2-3 minutes for the first three Steam Dumps to start to open. After they start to open, the MSIVs will automatically close 90 seconds later.

Indications for i-PT-i-33 high failure:

Steam Dumps opening Tave lowering RCS Pressure lowering.

Main Steam flow rising.

Main Steam Pressure lowering MSIV closure (should get an SI, but auto SI actuation is blocked)

MONITOR RCS temperature stable at or trending to 557°F:

IF any RCP running, THEN MONITOR RCS Loop T-avg trending to 557° F.

Perform RNO:

IF temperature is less than 557°F, THEN ENSURE steam dumps, SIG PORVs, and blowdown isolation valves CLOSED. IF cooldown continues, THEN:

ENSURE total feed flow is less than or equal to 500 gpm:

a. REFER TO SOl-302, Auxiliary Feedwater System, for manual control of TDAFWP.

MAINTAIN at least one SIG NR level greater than 29%, or total feed flow between 410 and 500 gpm for heat sink.

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

NRC Scenario #

1 Event #

5 & 6 Page 21 of 58 Event

Description:

2 d Control Rod Drop, E-O, ES-O.1 and 1 -PT-i -33 failure resulting in Steam Dumps opening Time Position Applicants Actions or Behavior IF cooldown continues after AFW flow is controlled, THEN:

CLOSE MSIVs.

ENSURE MSIV bypasses CLOSED.

PLACE steam dump controls OFF.

LEAD EVALUATOR NOTE:

Cue Console Operator to initiate Event 7 (Large Break LOCA, Loss of 1A 6.9 KV Shutdown Board) at your discretion.

4. ENSURE AFW operation:

a. AFW established:

Both MD AFW pumps RUNNING.

TD AFW pump RUNNING.

LCVs in AUTO or controlled in MANUAL.

b. Heat sink available:

Total feed flow greater than 410 gpm, OR

At least one S/G NR level greater than 29%.

5. CHECK MEW status:

a. CHECK RCS T-avg less than 564° F.

b. ENSURE MEW isolation:

MEW isolation and bypass isolation valves CLOSED.

MEW reg and bypass reg valves CLOSED.

MEP A and B TRIPPED.

Standby MEP STOPPED.

Cond demin pumps TRIPPED.

Cond booster pumps TRIPPED.

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

NRC Scenario #

1 Event #

5 & 6 Page 22 of 58 Event

Description:

2 Rod Drop, E-O, ES-O. 1 and 1 -PT-i -33 failure resulting in Steam Dumps opening Time Position

[

Applicants Actions or Behavior

6. ENSURE all control rods fully inserted:

RPIs at bottom scale.

7. ANNOUNCE reactor trip over PA system.

RO Evaluator Note:

No more ES-O. 1 steps are included. When Event 7 is commenced, the SRO should direct the crew back to E-O.

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

NRC Scenario #

1 Event #

7 & 8 Page 23 of 58 Event

Description:

LBLOCA with failure of SI to auto actuate, Loss of 1A 6.9 KV Shutdown Board and failure of RHR Pump to auto swapover to CNTMT sump.

Applicants Actions or Behavior Time Position Booth Instructor:

When directed, initiate Event 7 & 8 (Trigger 6)

Indications PZR Pressure lowering toward 0 psig Cold Leg Accumulators injecting Loss of Sub Cooled Margin Loss of 1 A 6.9 KV Shutdown Board voltage.

Crew Diagnose a Large Break LOCA SRO Direct actions per E-O Evaluator Note (1):

When the LB LOCA occurs, there will also be a failure of auto initiation of both trains of SI Evaluator Note (2):

Adverse Numbers should be utilized Evaluator Note (3):

SRO should direct the crew to GO FR-P. 1 when the STA reports RED path for Pressurized Thermal Shock status tree.

SRO should verify RED path conditions and then go to FR P.1.

There is only one step to perform and then immediately back into E-1.

NOTE 1 Steps 1 thru 4 are IMMEDIATE ACTION STEPS.

NOTE 2 Status Trees I SPDS should be monitored when transitioned to another instruction.

1. ENSURE reactor trip:

Reactor trip and bypass breakers OPEN.

RPIs at bottom of scale.

Neutron flux DROPPING.

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

NRC Scenario #

1 Event #

7 & 8 Page 24 of 58 Event

Description:

LBLOCA with failure of SI to auto actuate, Loss of 1A 6.9 KV Shutdown Board and failure of RHR Pump to auto swapover to CNTMT sump.

Time Position Applicants Actions or Behavior

2. ENSURE Turbine Trip:

All turbine stop valves CLOSED.

3. CHECK 6.9 kV shutdown boards:

a. At least one board energized from:CSST (offsite), OR DIG (blackout).

1A 69 1w Shutdown Board will be powered from EDG lA-A

4. CHECK SI actuated:

a. Any SI annunciator LIT.

Perform RNO:

DETERMINE if SI required:

a. IF ANY of the following exists:

SIG press less than 675 psig, OR RO

RCS press less than 1870 psig, OR

Cntmt press greater than 1.5 psig CRITICAL TASK #1 THEN ACTUATE SI manually.

b. Both trains SI ACTUATED.

1 -XX-55-6C

1-XX-55-6D BOP

5. EVALUATE support systems:

REFER TO Appendixes A and B (E-0), Equipment Verification pages 15-28.

6. ANNOUNCE reactor trip and safety injection over PA system.

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

NRC Scenario #

1 Event #

7 & 8 Page 25 of 58 Event

Description:

LBLOCA with failure of SI to auto actuate, Loss of 1A 6.9 KV Shutdown Board and failure of RHR Pump to auto swapover to CNTMT sump.

Time Position Applicants Actions or Behavior

7. ENSURE secondary heat sink RO available with either:

Total AFW flow greater than 410 gpm, OR

At least one S/G NR level greater than [39% ADV].

8. MONITOR RCS temp stable at or trending to 557° F:

IF any RCP running, THEN MONITOR RCS Loop T-avg RO trending to 557° F.

IF NO RCP running, THEN MONITOR RCS Loop T-cold trending to 557° F.

9. ENSURE excess letdown valves CLOSED:

1-FCV-62-54

1-FCV-62-55

10. CHECK pzr PORVs and block valves:

a. Pzr PORVs CLOSED.

b. At least one block valve OPEN.

11. CHECK pzr safety valves CLOSED:

EVALUATE tailpipe temperatures and acoustic monitors.

12. CHECK pzr sprays CLOSED.

13. CHECK if RCPs should remain in service:

a. Phase B signals DARK [MISSP].

RO RCPs should be secured.

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

NRC Scenario #

1 Event #

7 & 8 Page 26 of 58 Event

Description:

LBLOCA with failure of SI to auto actuate, Loss of 1A 6.9 KV Shutdown Board and failure of RHR Pump to auto swapover to CNTMT sump.

Time Applicants Actions or Behavior Position

14. CHECK S/G pressures:

All S/G pressures controlled or rising.

All SIG pressures greater than 120 psig.

15. CHECK for RUPTURED SIG

All SIGs narrow range levels CONTROLLED or RO DROPPING.

Secondary side radiation NORMAL from Appendix A.

16. CHECK cntmt conditions:

Cntmt pressure NORMAL.

Radiation NORMAL from Appendix A.

Cntmt sump level NORMAL.

Cntmt temp ann window DARK [104-B].

Perform RNO:

GO TO E-1, Loss of Reactor or Secondary Coolant.

Evaluator Note:

SRO should direct the crew to GO TO E-1 at this point. The following steps are from E-1.

1. CHECK if RCPs should remain in service:

RD

a. Phase B DARK [MISS P1.

b. RCS pressure greater than 1500 psig.

2. REFER TO EPIP-1, Emergency Plan Classification SRO Flowchart.

3. RECORD current time to mark initiation of LOCA and SRO determination of time for hot leg recirc.

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

NRC Scenario #

1 Event #

7 & 8 Page 27 of 58 Event

Description:

LBLOCA with failure of SI to auto actuate, Loss of 1A 6.9 KV Shutdown Board and failure of RHR Pump to auto swapover to CNTMT sump.

Applicants Actions or Behavior Time II Position

4. CHECK SIG pressures:

All S/G pressures controlled or rising.

All SIGs pressures greater than 120 psig.

5. MAINTAIN Intact SIG NR levels:

a. MONITOR levels greater than [39% ADV].

b. CONTROL intact SIG levels between [39% and 50%

ADV].

6. CHECK secondary radiation:

S/G discharge monitors NORMAL.

Condenser vacuum exhaust rad monitors NORMAL.

S/G blowdown rad monitor recorders NORMAL trend prior to isolation.

7. ENSURE cntmt hydrogen analyzers in service:

PLACE 1-HS43200A in ANALYZE [M-10].

PLACE 1-HS43-210A in ANALYZE [M-10].

CHECK low flow lights not lit [M-10j.

Locally CHECK low analyzer temp lights NOT lit

[North wall of Train A 480V SD Bd rm].

8. MONITOR pzr PORVs and block valves:

a. Pzr PORVs CLOSED.

b. At least one block valve OPEN.

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

NRC Scenario #

1 Event #

7 & 8 Page 28 of 58 Event

Description:

LBLOCA with failure of SI to auto actuate, Loss of 1A 6.9 KV Shutdown Board and failure of RHR Pump to auto swapover to CNTMT sump.

Applicants Actions or Behavior Time Position Evaluator Note:

Containment Pressure should be less than 2 psig approximately 20 minutes post LOCA. Only B Train operating.

9. DETERMINE if cntmt spray should be stopped:

a. MONITOR cntmt pressure less than 2.0 psig.

b. CHECK at least one cntmt spray pump RUNNING.

c. RESET cntmt spray signal.

d. STOP cntmt spray pumps, and PLACE in A-AUTO.

e. CLOSE cntmt spray discharge valves 1-FCV-72-2 and 1-FCV-72-39.

10. ENSURE both pocket sump pumps STOPPED [M-15]:

1-HS-77-410.

1-HS-77-411.

1 1. CHECK SI termination criteria:

a. CHECK RCS subcooling greater than [85°F ADV].

Perform RNO:

a. GO TO Caution prior to Step 12.

12. RESET SI and CHECK the following:

SI ACTUATED permissive DARK.

AUTO SI BLOCKED permissive LIT.

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

NRC Scenario #

1 Event #

7 & 8 Page 29 of 58 Event

Description:

LBLOCA with failure of SI to auto actuate, Loss of 1A 6.9 KV Shutdown Board and failure of RHR Pump to auto swapover to CNTMT sump.

Time Position Applicants Actions or Behavior

13. DETERMINE if RHR pumps should be stopped:

R0

a. CHECK RCS pressure greater than 150 psig.

Perform RNO:

a. ENSURE B RHR pump RUNNING.GO TO Step 16.

EVALUATOR NOTE:

AOI-43.O1, Loss Of Unit 1 Train A Shutdown Board will be performed as resources allow. Steps are at the end of this document.

16. MONITOR electrical board status:

a. CHECK offsite power available.

b. CHECK all shutdown boards ENERGIZED by offsite power.

c. PLACE any unloaded DIG in standby USING SOI-82 Diesel Generators.

Performs RNO:

BOp ENERGIZE shutdown boards USING:

SOI-211 Shutdown Boards OR A01-43 Loss of Shutdown Boards OR S0I-82 Diesel Generators EVALUATOR NOTE:

AOI-17, Turbine Trip BOP realignment steps are at the end of this document.

17. INITIATE BOP realignment:

REFER TO AOI-17, Turbine Trip.

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

NRC Scenario #

1 Event #

7 & 8 Page 30 of 58 Event

Description:

LBLOCA with failure of SI to auto actuate, Loss of 1A 6.9 KV Shutdown Board and failure of RHR Pump to auto swapover to CNTMT sump.

Time Position Applicants Actions or Behavior EVALUATOR NOTE:

E-1 Foldout page states:

SUMP RECIRC SWITCHOVER CRITERIA IF RWST level less than 34%, THEN GO TO ES-1.3, Transfer to RHR Containment Sump.

The crew should go to ES-1.3 when the RWST level gets to less than 34%.

18. INITIATE 480V board room breaker alignments USING the following:

Appendix A (E-1), CLA Breaker Operation.

Appendix B (E-1), Ice Condenser AHU Breaker Operation.

Appendix C (E-1), 1-FCV-63-1 Breaker Operation.

Appendix D (E-1), 1-FCV-63-22 Breaker Operation.

19. DETERMINE if hydrogen igniters should be energized:

a. CHECK hydrogen analyzers in service.

b. CHECK cntmt hydrogen less than 5% [M-1O].

c. ENERGIZE hydrogen igniters [M.1O]:

1-HS-268-73 ON.

1-HS-268-74 ON.

20. ENSURE RHR available for cntmt sump recirculation:

Power to at least one operable RHR pump AVAILABLE.

Cntmt sump valve 1FCV-63-73 to operable RHR pump AVAI LABLE.

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

NRC Scenario #

1 Event #

7 & 8 Page 31 of 58 Event

Description:

LBLOCA with failure of SI to auto actuate, Loss of 1A 6.9 KV Shutdown Board and failure of RHR Pump to auto swapover to CNTMT sump.

Time I

Position I

Applicants Actions or Behavior EVALUATOR NOTE: Appendix E (E-1), Equipment Evaluation is located at the back of this section.

21. EVALUATE plant equipment status:

REFER TO Appendix E (E-1), Equipment Evaluation.

22. CHECK Aux Bldg radiation for loss of RCS inventory outside cntmt:

a. Area monitor recorders 1-RR-90-1 and 0-RR-90-12 Aux BOP Bldg points NORMAL.

b. Vent monitor recorder 0-RR-90-101 NORMAL trend prior to isolation.

23. NOTIFY Chemistry of event status and plant conditions.

24. DETERMINE if RCS cooldown and depressurization is required:

a. CHECK RCS pressure greater than 150 psig.

RO Perform RNO:

a. IF RHR pump injecting to RCS, THEN GO TO Step 25.

25. PREPARE for switchover to RHR cntmt sump:

a.

ENSURE power restored to 1-FCV-63-1 USING Appendix C (El), 1-FCV-63-1 Breaker Operation.

b. CHECK RWST less than 34%.

Perform RNO:

GO TO Step 20.

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

NRC Scenario #

1 Event #

7 & 8 Page 32 of 58 Event

Description:

LBLOCA with failure of SI to auto actuate, Loss of 1A 6.9 KV Shutdown Board and failure of RHR Pump to auto swapover to CNTMT sump.

Time Position I

Applicants Actions or Behavior EVALUATOR NOTE:

The crew will loop between steps 20 and 25 until RWST is less than 34% and go then to ES-l.a The following step are out of ES-l.3:

LEAD EVALUATOR NOTE: When ES-l.3 is entered, cue console operator to reduce RWST leak to lOOgpm

1. ENSURE both RHR pumps RUNNING.

When Event 9 is implemented the SRO should direct the crew to go to ECA-l.l.

RO RNO:

IF NO RHR pumps can be started, THEN

- GO TO ECA-l. 1, Loss of RHR Sump Recirculation.

2. ESTABLISH CCS to RHR heat exchangers [M-27Bj:

a.

ENSURE RHR heat exchanger outlet valves 1-FCV-70-153 and 1-FCV-70-156 OPEN.

b.

CLOSE SEP heat exchanger A CCS supply 0-ECV-70-197.

BOP c.

ENSURE CCS flow to ESF supply header and greater than 5000 gpm.

Train A: 1-EI-70-159

Train B: 1-EI-70-165 d.

MONITOR level in CCS surge tanks.

3. CHECK RWST level less than 34%.

4. CHECK cntmt sump level greater than or equal to 16.1 %.

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

NRC Scenario #

1 Event #

7 & 8 Page 33 of 58 Event

Description:

LBLOCA with failure of SI to auto actuate, Loss of 1A 6.9 KV Shutdown Board and failure of RHR Pump to auto swapover to CNTMT sump.

Time Applicants Actions or Behavior Position EVALUATOR NOTE:

RO WILL BE REQUIRED TO MANUALLY OPEN CNTMT SUMP VALVE 1-FCV-63-73 using M-6 handswitch. (only one valve due to only having B train power)

CRITICAL TASK #2

5. ENSURE automatic switchover complete:

(5. a & b) a.

ENSURE cntmt sump valve i-FCV-63-73 OPEN.

b.

ENSURE RWST to RHR suction valve i-FCV-74-2i RO CLOSED.

c.

INITIATE power restoration to i-FCV-63-l USING Appendix A (ES-i.3), i-FCV-63-i Breaker Operation.

6. MONITOR RWST level greater than 8%.

Lead Evaluator Note:

Cue console operator to implement EVENT 9 (Trigger 7 loss of 1 B RHR Pump) at your discretion.

Evaluator Note (1):

ES-1.3 steps (up to step 20) are included in this section.

When Event 9 is implemented the SRO should direct the crew to go to ECA-1.1.

Evaluator Note (2):

Actions to secure Containment Spray may have been performed earlier in E-1.

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

NRC Scenario #

1 Event #

7 & 8 Page 34 of 58 Event

Description:

LBLOCA with failure of SI to auto actuate, Loss of 1A 6.9 KV Shutdown Board and failure of RHR Pump to auto swapover to CNTMT sump.

Time Position Applicants Actions or Behavior

7. DETERMINE if cntmt spray should be stopped:

a. MONITOR cntmt press less than 2.0 psig.

RNO:

WHEN cntmt press less than 2.0 psig, THEN PERFORM Substeps 7b thru e. GO TO Step 8.

b. CHECK at least one cntmt spray pump RUNNING.

RO RNO: IF both spray pumps stopped, THEN GO TO Step 9.

c. RESET cntmt spray signal.

d. STOP cntmt spray pumps and PLACE in A-AUTO.

e. CLOSE cntmt spray discharge valves 1-FCV-72-2 and 1 -FCV-72-39.

f. GOTOStep9.

8. DETERMINE if ONE train cntmt spray should be stopped:

a. CHECK BOTH trains cntmt spray delivering flow.

RNO:

GOTOStep9.

b. RESET cntmt spray signal.

c. STOP ONE cntmt spray pump and PLACE in A AUTO.

d. CLOSE spray discharge valve for stopped pump.

9. IF RCS press rises to greater than 1350 psig, THEN STOP both SI pumps.

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

NRC Scenario #

1 Event #

7 & 8 Page 35 of 58 Event

Description:

LBLOCA with failure of SI to auto actuate, Loss of 1A 6.9 KV Shutdown Board and failure of RHR Pump to auto swapover to CNTMT sump.

Time Applicants Actions or Behavior Position Evaluator Note:

The following ES-1.3 steps (10, 11, 12, & 13) will also be critical steps if the Lead Evaluator allows the scenario to continue before Event 9 is implemented.

Potential PART OF

10. (#1) ISOLATE SI pump miniflow:

CLOSE 1-FCV-63-3.

CRITICAL TASK #2 RO

CLOSE 1-FCV-63-175.

CLOSE 1-FCV-63-4.

Potential PART OF

11. (#2) ISOLATE RHR crossties:

CLOSE 1-FCV-74-33.

CRITICAL RO

CLOSE 1-FCV-74-35.

TASK #2 Potential PART OF

12. (#3) ALIGN charging pump and SI pump supply from RHR:

OPEN 1 -FCV-63-6.

CRITICAL TASK #2 RO

OPEN 1-FCV-63-7.

ENSURE 1-FCV-63-177 OPEN.

Potential PART OF

13. (#4) ALIGN RHR discharge to charging pump and SI pump suction:

CRITICAL TASK #2 RO

a. OPEN 1 -FCV-63-8.

b. OPEN 1-FCV-63-11.

14. DO NOT CONTINUE this Instruction UNTIL Steps 10 thru RO 13 complete.

15. RESTART any charging pumps and SI pumps as RO necessary.

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

NRC Scenario #

1 Event #

7 & 8 Page 36 of 58 Event

Description:

LBLOCA with failure of SI to auto actuate, Loss of 1A 6.9 KV Shutdown Board and failure of RHR Pump to auto swapover to CNTMT sump.

Time Position Applicants Actions or Behavior

16. (#5) RESET SI, and CHECK the following:

SI ACTUATED permissive DARK.

AUTO SI BLOCKED permissive LIT.

17. IF offsite power is lost, THEN:

a. PLACE charging pumps in PULL TO LOCK.

b. RESTART RHR pumps.

c. RESTART charging pumps.

d. IF RCS press less than 1350 psig, RESTART SI pumps.

18. (#6) ISOLATE charging pump suction from RWST:

a. CLOSE 1-LCV-62-135.

b. CLOSE 1-LCV-62-136.

R

c. ENSURE 1-HS-62-135A in A-AUTO (pushed in).

d. ENSURE 1-HS-62-136A in A-AUTO (pushed in).

19. (#7) ISOLATE SI pump suction from RWST:

CLOSE 1-FCV-63-5.

20. (#8) ISOLATE RHR suction from RWST:

a. ENSURE power restored to 1-FCV-63-1 USING Appendix A (ES-i.3), 1-FCV-63-i Breaker Operation.

b. CLOSE i-FCV-63-1.

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

NRC Scenario #

1 Event #

Event

Description:

Loss of 18 RHR Pump and ECA-1.

9 Page 37 of 58 Applicants Actions or Behavior Time 1

Position Booth Instructor:

When directed, initiate Event 9 (Trigger 7)

Indications Breaker disagreement light on 1 B RHR Pump hand switch.

Loss of RHR Flow SRO Directs Crew to ECA-1.1.

Evaluator Note:

The following are steps from ECA-1.1.

CAUTION IF RWST level drops to 8%, then any ECCS or cntmt spray pump taking suction from the RWST must be stopped.

1. CHECK cntmt sump recirculation equipment AVAILABLE:

Power to RHR pumps AVAILABLE.

RHR pumps AVAILABLE.

Cntmt sump valves AVAILABLE.

Perform RNO:

RESTORE at least one train.

2. IF RHR sump recirculation restored during performance of this Instruction, SRO THEN RETURN TO Instruction in effect.

3. MONITOR RWST level greater than 8%.

Appendix D Required Operator Actions Form ES-D-2 NRC Scenario #

1 Event #

9 Page 38 of 58 Op Test No.:

Event

Description:

Loss of lB RHR Pump and ECA-1.1 Applicants Actions or Behavior Time Position CONTAINMENT PRESS SPRAY PUMPS REQUIRED Greater than 13.5 psig 2

2.0 psig to 13.5 psig 1

Less than 2.0 psig 0

c.

CHECK number of spray pumps running equal to number required.

If any running, Perform RNO:

STOP and PULL TO LOCK any cntmt spray pump NOT

required, AND CLOSE discharge valve(s) 1-FCV-72-2 and/or 1-FCV-72-39 for pump(s) stopped.

Manually OPERATE spray pumps as required.

d.

DO NOT OPERATE cntmt spray pumps as required by FRZ.1, High Containment Pressure, UNTIL either of the following:

Cntmt spray pump suction aligned to cntmt sump.

RWST makeup sufficient to support cntmt spray pump operation.

Evaluator Note:

Actions to secure Containment Spray may have been performed earlier in E-1.

CRITICAL TASK #3 PART 1

4. DETERMINE cntmt spray pump alignment and operation:

a.

CHECK cntmt spray pump suction aligned to RWST.

b.

MONITOR cntmt press, and DETERMINE number of spray pumps required:

Appendix D Required Operator Actions Form ES-D-2 NRC Scenario #

1 Event #

9 Page 39 of 58 Event

Description:

Loss of 1 B RHR Pump and ECA-1.1 Position Applicants Actions or Behavior Op Test No.:

Time II

5. DETERMINE if cntmt spray should be aligned to cntmt sump:

a. CHECK spray pumps RUNNING.

RO Perform RNO:

a. IF spray pumps stopped, THEN GO TO Caution prior to Step 8.

CAUTION If offsite power is lost after SI reset, manual action may be required to restore ECCS equipment.

8. RESET SI, and CHECK the following:

SI ACTUATED permissive DARK.

RO AUTO SI BLOCKED permissive LIT.

9. RESET SI interlock to RHR sump suction AUTO-swapover:

1-HS-63-72D.

RO 1-HS-63-73D.

CRITICAL

10. INITIATE makeup to RWST:

TASK #3 a.

NOTIFY Radprot/Chemistry to evaluate radiation level of PART 2 water in cntmt sump for potential transfer to RWST.

b.

NOTIFY TSC to evaluate transferring water to RWST from one of the following:

Appendix C (ECA-1.1), Cntmt Spray Recirc to RWST Alignment.

Spent fuel pit.

Holdup tank.

Normal RWST fill USING SOI-62.02.

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

NRC Scenario #

1 Event #

9 Page 40 of 58 Event

Description:

Loss of 1 B RHR Pump and ECA-1.1 Applicants Actions or Behavior Time H

Position ii. MONITOR CST volume greater than 200,000 gal.

12. MAINTAIN Intact SIG NR levels:

a. MONITOR Intact SIG NR levels greater than 39% ADV.

b. CONTROL intact S/G levels 39% and 50% ADV.

13. MONITOR shutdown margin during RCS cooldown:

REFER TO 1-Sl-O-10, Shutdown Margin OR REACTINW Computer Program.

14. INITIATE RCS cooldown to cold shutdown:

a. WHEN RCS pressure is less than 1962 psig (P-il), THEN

BLOCK low pzr pressure SI.

BLOCK low steam pressure SI.

b. MAINTAIN T-cold cooldown less than 100°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

c. DUMP steam to condenser from Intact S/Gs.

PERFORM RNO:

IF condenser NOT available, THEN Manually or locally DUMP steam from Intact S/G:

USE Intact S/G PORV, OR

USE TD AFW pump supply from Intact SIG.

RESET Phase A, AND USE Intact S/G blowdown.

Evaluator Note:

The scenario may end when the crew has addressed initiating a RCS cooldown to cold shutdown or at the discretion of the Lead Evaluator

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

NRC Scenario #

1 Event #

8 Page 41 of 58 Event

Description:

E-O Appendix A and B Applicants Actions or Behavior Time H

Position N

Booth Instructor: NONE Indications: None Directs BOP to perform E-0 STEP 5:

5. EVALUATE support systems:

REFER TO Appendixes A and B (E-0), Equipment Verification pages 15-28.

Evaluator Note:

The following are E-O Appendix A steps.

Evaluator Note:

The SRO may at times interrupt the BOP, during the performance of Appendixes A and B, to perform other higher priority task.

1. ENSURE PCBs OPEN:

PCB 5044.

PCB 5088.

2 ENSURE AFW pump operation:

Both MD AFW pumps RUNNING.

TD AFW pump RUNNING.

LCVs in AUTO, or controlled in MANUAL.

3. ENSURE MEW isolation:

MFW isolation and bypass isolation valves CLOSED.

MFW reg and bypass reg valves CLOSED.

MFP A and B TRIPPED.

Standby MFP STOPPED.

Cond demin pumps TRIPPED.

Cond booster pumps TRIPPED.

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

NRC Scenario #

1 Event #

8 Page 42 of 58 Event

Description:

E-O Appendix A and B I

Applicants Actions or Behavior Time Position

4. MONITOR ECCS operation:

a. Charging pumps RUNNING.

b. Charging pump alignment:

RWST outlets 1-LCV-62-135 and 1-LCV-62-136 OPEN.

VCT outlets 1-LCV-62-132 and 1-LCV-62-133 CLOSED.

Charging 1-FCV-62-90 and 1-FCV-62-91 CLOSED.

c. RHR pumps RUNNING.

d. SI pumps RUNNING.

e. BIT alignment:

Outlets 1-FCV-63-25 and 1-FCV-63-26 OPEN.

Flow thru BIT.

f. RCS pressure greater than 1650 psig.

RNO not >l65Opsig:

f. ENSURE SI pump flow. IF RCS press drops to less than 150 p51g. THEN ENSURE RHR pump flow.

5 CHECK cntmt isolation:

a. Phase A isolation:

Train A GREEN.

Train B GREEN.

b. Cntmt vent isolation:

Train A GREEN.

Train B GREEN.

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

NRC Scenario #

1 Event #

8 Page 43 of 58 Event

Description:

E-O Appendix A and B Time Position Applicants Actions or Behavior

6. CHECK cntmt pressure:

Phase B DARK [MISSP].

Cntmt Spray DARK [MISSP}.

Cntmt press less than 2.8 psig.

Perform RNO:

PERFORM the following:

1) ENSURE Phase B actuated.

2) ENSURE Cntmt Spray actuated.

3) ENSURE cntmt spray pumps running.

4) ENSURE cntmt spray flow.

5) ENSURE Phase B isolation:

Train A GREEN.

Train B GREEN.

6) STOP all RCPs.

7) ENSURE MSIVs and bypasses CLOSED.

8) PLACE steam dump controls OFF.

9) WHEN 10 minutes has elapsed since Phase B actuated, THEN ENSURE air return fans start.

10) USE adverse cntmt [ADV] setpoints where provided.

7. CHECK plant radiation NORMAL:

S/G blowdown rad recorder 1-RR-90-120 NORMAL prior to isolation [M-12].

Condenser vacuum exhaust rad recorder 1 -RR.90-119 NORMAL prior to trip [M-12].

1-RR90-106 and 1-RR-90-1 12 radiation recorders NORMAL prior to isolation [M-12].

S/G main steamline discharge monitors NORMAL.

Upper and Lower containment high range monitors NORMAL [M-30].

NOTIFY Unit Supervisor conditions NORMAL.

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

NRC Scenario #

1 Event #

8 Page 44 of 58 Event

Description:

E-O Appendix A and B Time Position Applicants Actions or Behavior 8 ENSURE all DIGs RUNNING.

9. ENSURE ABGTS operation:

a. ABGTS fans RUNNING.

b. ABGTS dampers OPEN:

FCO-30-146A.

FCO-30-146B.

FCO-30-157A.

FCO-30-.157B.

10. ENSURE at least four ERCW pumps RUNNING, one on BOP each shutdown board preferred.

BOP ENSURE ERCW supply valves OPEN to running DIGs.

12. ENSURE CCS HX C ALT DISCH TO HDR B, O-FCV BOP 152, is open to position A.

13. CLOSE CCS HX C DISCH TO HDR A, 0-FCV-67-144.

14. MONITOR EGTS operation:

EGTS fans RUNNING.

ENSURE dampers OPEN VERIFY filter bank dp between 5 and 9 inches of water.

15. ENSURE CCS pumps RUNNING:

lA-A CCS pump.

1B-B CCS pump.

C-S OR 2B-B CCS pump.

16. CHECK CNTMT PURGE fans STOPPED:

Op Test No.:

Appendix D Required Operator Actions Form ES-D-2 NRC Scenario #

1 Event #

8 Page 45 of 58 Event

Description:

E-O Appendix A and B Time Position A

Applicants Actions or Behavior

17. CHECK FUEL HANDLING EXH fans STOPPED, Fuel and BOP Cask loading dampers CLOSED:

18. ENSURE AB GEN SUPPLY and EXH fans STOPPED.

19. ENSURE AB GEN SUP & EXH dampers CLOSED.

20. ENSURE MCR & SPREAD RM FRESH AIR dampers CLOSED:

FCV-31-3.

FCV-31-4.

21.

ENSURE at least one CB EMER CLEANUP fan RUNNING and associated damper OPEN:

CB EMERG CLEANUP FAN A-A, OR Fan B-B BOP RUNNING.

FCO-31-8, OPEN OR FCO-31-7, OPEN.

22. ENSURE at least one CB EMER PRESS fan RUNNING and associated damper OPEN:

CB EMERG PRESS FAN A-A, OR FAN B-B RUNNING.

FCO-31-6, OPEN. OR FCO-31-5, OPEN.

23. ENSURE Control Building fans STOPPED and dampers CLOSED:

SPREADING ROOM SUPPLY and EXH FANS AND BOP dampers.

TOILET & LKR RM EXHAUST FAN AND dampers.

24. INITIATE Appendix B.

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

NRC Scenario #

1 Event #

8 Page 46 of 58 Event

Description:

E-O Appendix A and B Time Position Applicants Actions or Behavior Evaluator Note:

E-O Appendix B is listed below BOP

1. CHECK PHASE B actuated

2. ENSURE 1-FCV-32-11O CLOSED. (CISP XX-55-6E) [A BOP train, window 13]

3. ENSURE 1-FCV-67-107 CLOSED. (CISP XX-55-6E) [A BOP train, window 43]

4. ENSURE 1 -FCV-70-92 CLOSED. (CISP XX-55-6E) [A BOP train, window 73]

5. ENSURE 1-FCV-70-140 CLOSED. (CISP XX-55-6F) [B BOP train, window 74]

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

NRC Scenario #

1 Event #

none Page 47 of 58 Event

Description:

AOl 43.01 LOSS OF UNIT 1 TRAIN A SHUTDOWN BOARDS Applicants Actions or Behavior Time Position Evaluator Note:

AOl-43.O1 actions will be performed as resources/priorities allow. Actions that are performed will be performed by the BOP. On the next page start AOl-43.O1 pages 4 thru 7, and 14 thru 16.

The crew will not be able to restore 1A 6.9 kv Shutdown board since a fault on the bus is simulated.

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

NRC Scenario #

1 Event #

none Page 48 of 58 Event

Description:

AOl 43.01 LOSS OF UNIT 1 TRAIN A SHUTDOWN BOARDS Time Position Applicants Actions or Behavior AOI-43.01 WBN LOSS OF UNIT I TRAIN A SHUTDOWN BOARDS Revision 6 Page 4 of 32 3.0 OPERATOR ACTIONS ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE I COP lA-A, SIP lA-A, RHR Pump lA-A, CS Pump lA-A, AFW Pump lA-A, ERCW Pumps A-A and B-A, Pressurizer Heaters Backup Group 1A, and Pressurizer Heaters Control Group 1D will be unavailable on a loss of 6.9KV Shutdown Board lA-A.

NOTE 2 Operability of remaining AC power sources must be determined within one hour per LCO 3.8.1.

NOTE 3 Steps to energize 6.9KV Shutdown Board lA-A (or intermediate supply paths) may be repeated based on completed repair(s), protective relay reset, or direction from TSC.

NOTE 4 RCPs can be operated for up to 10 minutes after loss of CCS flow.

MONITOR 1 B-B 6.9KV Shutdown EMERGENCY START Diesel Board ENERGIZED.

Generators:

l-HS-82-15 [l-M-l].

OR 2-HS-82-15 [2-M-1].

IF both Unit 1 6.9KV SD Bds still de-energized, AND Unit is in MODE 1, 2, or 3, THEN TRIP Reactor and RCPs and GO TO ECA-0.0, Loss of Shutdown Power.

IF Unit is in MODE 4, 5, or 6, THEN TRIP RCPs and PERFORM AOl-14, Loss of RHR Shutdown Cooling, WHILE continuing in this procedure.

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

NRC Scenario #

1 Event #

none Page 49 of 58 Event

Description:

AOl 43.01 LOSS OF UNIT 1 TRAIN A SHUTDOWN BOARDS Time Position Applicants Actions or Behavior AOl-43.01 WBN LOSS OF UNIT I TRAIN A SHUTDOWN BOARDS Revision 6 Page 5of32 3.0 OPERATOR ACTIONS (continued)

ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 2.

ENSURE Diesel Generators running:

EMERGENCY START Diesel DG lA-A Generators:

DG lB-B 1-HS-82-15 [1-M-1].

DG2A-A OR DG 2B-B 2-HS-82-15 [2-M-1].

FOR ANY NON-RUNNING DIG:

EVALUATE RESETTING EMERGENCY STOP BY:

PRESS and RELEASE DG AUTO SAFETY SHUTDOWN RELAY-RESET [0-M-26J:

1-HS-82-20 [IA-A].

1-HS-82-50 [lB-B].

2-HS-82-80 [2A-A].

2-HS-82-110 [28-B].

AND EMERGENCY START Diesel Generator [0-M-26]:

1-HS-82-16A [lA-A].

1-HS-82-46A [lB-B].

2-HS-82-76A [2A-A].

2-HS-82-106A [28-B].

3.

MONITOR RCP seal cooling available:

MANUALLY START opposite train Seal injection flow CCP or CCS pump.

OR IF seal cooling not restored, CCS flow through Thermal Barrier THEN Heat Exchangers MONITOR RCP trip criteria.

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

NRC Scenario #

1 Event #

none Page 50 of 58 Event

Description:

AOl 43.01 LOSS OF UNIT 1 TRAIN A SHUTDOWN BOARDS Time osition Applicants Actions or Behavior AOI-43.01 WBN LOSS OF UNIT I TRAIN A SHUTDOWN BOARDS Revision 6 Page 6 of 32 3.0 OPERATOR ACTIONS (continued)

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4.

DISPATCH personnel to Auxiliary Bldg to UNLOCK and RACK UP the following breakers:

NOMENCLATURE LOCATION UNID MAINT SUPPLY FROM 6.9kV SDB 1-BKR-21 1-1718/11 6.9KV UNIT BD I B IA-A, Cii MAINT SUPPLY FROM 6.9kV SDB 2-BKR-21 1-1818/11 6.9KV UNIT BD 2B 2A-A, Cli 5.

DISPATCH personnel to Turbine Bldg to CLOSE the following breakers:

NOMENCLATURE LOCATION UNID MAINT FEEDER TO 6.9 KV 6.9kV UNIT i-BKR-201-B18 SHUTDOWN BD lA-A BD lB MAINT FEEDER TO 6.9KV 6.9kV UNIT 2-BKR-20i-B18 SHUTDOWN BD 2A-A BD 29 6.

CHECK both lA-A and 2A-A 6.9 KV

- GO TO Step [9].

Shutdown bds DEENERGIZED.

7.

LOCALLY OPEN 1 -FCV-67-68, DIG lA-A Sup From Hdr. 26 MANUALLY.

8.

LOCALLY OPEN 2-FCV-67-68, D/G 2A-A Sup From Hdr. 2B MANUALLY 9.

DISPATCH personnel to the following locations to inspect for equipment damage:

6.9KV Shutdown Board 480V Shutdown Boards Diesel Generator Building

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

NRC Scenario #

1 Event #

none Page 51 of 58 Event

Description:

AOl 43.01 LOSS OF UNIT 1 TRAIN A SHUTDOWN BOARDS Time Position Applicants Actions or Behavior AOI-43.O1 WBN LOSS OF UNIT I TRAIN A SHUTDOWN BOARDS Revision 6 Page 7 of 32 3.0 OPERATOR ACTIONS (continued)

ACTION!EXPECTED RESPONSE RESPONSE NOT OBTAINED 10.

NOTIFY MAINTENANCE personnel of failure of Shutdown Board.

11.

ENSURE Unit I Instrument Power A Rack selected to ENERGIZED feeder (amber light ON)[1-M-7] (SOI-237.01).

12.

ALIGN BAT A for operation via BA Pump lB USING SOI-62.05.

13.

MONITOR Board Protective Relays GO TO Step [38].

NOT ACTUATED (local reports) 14.

NOTIFY Shift Manager to staff Technical Support Center for support (additional source of manpower).

(REFER TO EPIP-6).

NOTE Steps [14] through [21] attempt to energize 6.9KV SD BD lA-A from any available energized source, including the maintenance feeder breaker.

15.

ENSURE 1-XS-57-43, 6.9 SD BD lA-A XFER SELECTOR [l-M-l], in MAN.

16.

IF required, THEN TRIP the following breakers to clear DISAGREEMENT (WHITE) LIGHT:

NOMENCLATURE LOCATION UNID 1716 NORMAL-6.9 SD BD 1-M-1, OR 1-HS-57-41A, OR lA-A FROM CSST C O-M-26 1-HS-57-41B 1932-ALT 6.9 SD BD lA-A 1-M-1, OR 1-HS-57-97A, OR FROM CSST D O-M-26 1-HS-57-97B 1912-DG TO SD BD lA-A 0-M-26 1-HS-57-46A 1718 MAINTENANCE-6.9 1-M-1, OR 1-HS-57-44A, OR SD BD lA-A FROM UNIT 0-M-26 1-HS-57-44B BD lB

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

NRC Scenario #

1 Event #

none Page 52 of 58 Event

Description:

AOl 43.01 LOSS OF UNIT 1 TRAIN A SHUTDOWN BOARDS Time Position I

Applicants Actions or Behavior AOI-43.O1 WBN LOSS OF UNIT I TRAIN A SHUTDOWN BOARDS Revision 6 Page 14 of 32 3.0 OPERATOR ACTIONS (continued)

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38.

ENSURE affected equipment placed in STOP PULL TO LOCK/OFF:

lA-A CCP.

Pressurizer Heaters Group lA-A.

lA-A Motor Driven AFW Pump.

lA-A Component Cooling Water Pump.

lA-A Thermal Barrier Booster Pump.

A-AERCW Pump.

B-A ERCW Pump.

MCR Chiller A-A.

EBR Chiller A-A.

SD Bd Rm Chiller A-A.

39.

DISPATCH AUO to D/G Bldg to monitor D/G conditions USING SOI-82 series, Appendix A, for operating parameters 40.

ENSURE Train A ERCW pumps in EVALUATE stopping D/Gs without service as required to maintain ERCW.

pressure and flows (S0I-67.01):

C-A ERCW Pump.

D-A ERCW Pump.

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

NRC Scenario #

1 Event #

none Page 53 of 58 Event

Description:

AOl 43.01 LOSS OF UNIT 1 TRAIN A SHUTDOWN BOARDS Time Position Applicants Actions or Behavior AOI-43.O1 WBN LOSS OF UNIT I TRAIN A SHUTDOWN BOARDS Revision 6 Page 15 of 32 3.0 OPERATOR ACTIONS (continued)

ACTION1EXPECTED RESPONSE RESPONSE NOT OBTAINED 41.

CHECK any charging pump RUNNING PERFORMthefollowing:

a.

ISOLATE letdown:

CLOSE letdown orifice(s).

CLOSE 1-FCV-62-69A.

CLOSE 1-FCV-62-70A.

b.

RESTORE charging and letdown:

REFER TO Attachment 1 ALIGNMENT OF CHARGING AND LETDOWN.

NOTE I CCS Pump lA-A, Aux Bldg General Sup Fan lA-A, CRDM Cooler IA-A, Lower Cntmt Cooler lA-A, EBR Air Handling Unit A-A, and Cntmt Air Return Fan lA-A will be unavailable on a loss of 480V SD BD 1A1-A.

NOTE 2 Aux Bldg General Exh Fan lA-A, CRDM Cooler 10-A, Lower Cntmt Cooler IC-A, MCR Chlr A-A Compressor, 480V SDBR AHU A-A, Station Air Compr A, and HP Fire Pump lA-A will be unavailable on a loss of 480V SD BD 1A2-A.

42.

ENSURE lB-B CCS Pump Supplying REFER TO AOl-i 5, Loss of A Train (SOI-70.01).

Component Cooling Water (CCS)

FOR LOSS OF CCS FLOW.

43.

ENSURE Thermal Barrier Booster REFER TO AOl-is, Loss of Pump 1 B-B in service Component Cooling Water (CCS)

(SOl-70.01).

FOR LOSS OF CCS FLOW.

44.

EVALUATE starting additional Control MONITOR containment upper Rod Drive Mech Cooler Fans, Lower and lower compartment average air Compartment Cooler Fans, and Upper temperatures are within limits:

Compartment Cooler Fans S/R 3.6.5.1, Computer Point

).

U9019 S/R 3.6.5.2, Computer Point U9020

Appendix D Required Operator Actions Form ESD-2 Op Test No.:

NRC Scenario #

1 Event #

none Page 54 of 58 Event

Description:

AOl 43.01 LOSS OF UNIT 1 TRAIN A SHUTDOWN BOARDS Time I

Position Applicants Actions or Behavior AOI-43.01 WBN LOSS OF UNIT I TRAIN A SHUTDOWN BOARDS Revision 6 Page 16 of 32 3.0 OPERATOR ACTIONS (continued)

ACTION!EXPECTED RESPONSE RESPONSE NOT OBTAINED 45.

ENSURE Aux Bldg General Supply and Exhaust Fans in service as required to maintain ventilation and pressure (SOI-30.05).

46.

ENSURE EBR Air Conditioning Unit B-B and MCR Air Conditioning Unit B-B in service (SOI-31.01).

NOTE Radiation Monitors powered from 480V C & A Vent Board 1A1-A or Radiation Monitor & Sampling & Fire Protection 1-BD-242-1 will be inoperable on a loss of 480V C & A Vent Board 1AI-A.

47.

RESET Radiation Monitor modules and alarms on 0-M-12.

NOTE I Unit 1 A Train ESF Room Coolers, Area Coolers, and Space Coolers will be unavailable on a loss of 480V C & A Vent Board 1AI-A.

NOTE 2 Emergency Gas Treatment System Fan A-A will be unavailable on a loss of 480V C & A Vent Board I Al -A.

48.

ENSURE lB Primary Water Pump in service as required (When in bypass mode, ensure Primary Water System aligned per SOI-81.01).

49.

ENSURE lB Annulus Vacuum Fan in service (SOI-65.Ol).

50.

ENSURE A Train or B Train 480V and Shutdown Board Room Ventilation in service (SOl-30.07).

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

NRC Scenario #

1 Event #

None Page 55 of 58 Event

Description:

AOl-17 BOP Realignment Time Position II Applicants Actions or Behavior Booth Instructor: NONE Indications: NONE Evaluator Note:

The following are the first ten steps from AOl-17 Turbine Trip, it is not expected that the BOP will perform all of these steps due to other higher priority issues..

CAUTION Performance of this instruction should not be allowed to delay or interfere with actions required by applicable emergency procedures or abnormal operating procedures.

NOTE 1 Control room operators may initiate shutdown of pumps and equipment from the benchboard immediately after a trip. Performance of this instruction will subsequently verify proper secondary equipment alignment.

NOTE 2 Steps in this section and items in Attachment 1 may be performed out of sequence.

1. DISPATCH turbine building NAUO to perform Attachment 1.

2. NOTIFY condensate demineralizer NAUO prior to Operator BOP initiated press changes in condensate.

3. REMOVE generator excitation from service:

a. PLACE voltage regulator to TEST.

b. ZERO exciter base adjuster.

c. OPEN exciter field breaker.

d. PLACE exciter regulator control to OFF.

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

NRC Scenario #

1 Event #

None Page 56 of 58 Event

Description:

AOI-17 BOP Realignment Applicants Actions or Behavior Time Position

4. MONITOR main turbine:

a. WHEN less than 1500 rpm, THEN:

ENSURE seal oil backup pump RUNNING.

ENSURE turning gear oil pump RUNNING.

b. WHEN less than 600 rpm, THEN ENSURE bearing lift oil pump RUNNING.

c. WHEN turbine is at ZERO RPM, THEN ENSURE turbine on turning gear.

d. MAINTAIN MTOT lube oil temp between 95° and 100°F (may require RCW isolation if TCV has excessive leakage).

e. MAINTAIN GENERATOR H2 (Cold Gas) temp 95°F (may require RCW isolation if TCV has excessive leakage).

f. ENSURE Gland Steam Spillover Bypass valve is CLOSED using 1-HS-47-191A.

5. ALIGN MSRs:

a. PUSH RESET on MSR control panel.

b. CLOSE MSR HP steam and bypass isol.

c. ENSURE MSR warming valves CLOSED.

d. OPEN MSR startup vents.

e. CLOSE MSR operating vents.

6. CHECK MSIVs OPEN.

7. ENSURE adequate FW press:

a. ENSURE two hotwell pumps RUNNING.

b. IF FW isolation reset, THEN ENSURE one condensate booster pump RUNNING if needed for unit conditions.

c. ENSURE CNDS demin pumps OFF.

d. STOP #3 HDT pumps, and CLOSE the discharge valves to condensate heater strings. Notify NAUO performing that #3 HDT pumps are stopped.

e. STOP #7 HDT pumps, and CLOSE the discharge valves to condensate heater strings.

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

NRC Scenario #

1 Event #

None Page 57 of 58 Event

Description:

AOl-17 BOP Realignment Applicants Actions or Behavior Time II Position

8. SHUTDOWN any MFW pump NOT BOP required.

9. SHUTDOWN any ROW pumps NOT BOP required.

10. SHUTDOWN any COW pumps NOT BOP required.

APPENDIX E (E-l)

Page 1 of 1 EQUIPMENT EVALUATION 1.

EVALUATE plant equipment and systems needed to support long term cooling and recovery actions, as time and personnel availability permits:

a. Cntmt Isolation Status.

b. Emergency Gas Treatment System:

One train in operation, REFER TO SO 1-65.02.

c. Auxiliary Building Gas Treatment:

One train in operation, REFER TO SOI-30.06.

d.Auxiliary Building Isolation alignment:

REFER TO SO 1-30.06.

e. Main Control Room Isolation alignment:

REFER TO SOI-31.01.

f. ERCW System:

Both trains in operation.

g. Component Cooling Water System:

Both trains in operation.

SHIFT TURNOVER CHECKLIST Page of Q

SM US/MCR Unit E

UO Unit Off-going

- Name AUO Station STA (STA Function)

On-coming

- Name Part 1

- Completed by off-going shiftlReviewed by on-coming shift:

Cb= 1807 ppm Abnormal equipment lineup/conditions:

None.

Green risk associated with equipment OOS.

SIJTest in progress/planned: (including need for new brief)

See Schedule Major Activities/Procedures in progress/planned:

The plant is at BOL. A startup is in progress from a forced outage to repair an EHC high pressure piping leak.

Power is stable at 2%. GO-3 Section 5.2 step 12 which required the completion of Appendix A (Mode 2 to Mode 1 approval) was just completed. The Operation Superintendents approval to enter Mode I was just obtained. The crew is in GO-3 Unit Startup From Less Than 4% Reactor Power to 30% Reactor Power section 5.3 step 3.

Abnormal equipment lineup/conditions:

None.

Radiological changes in plant during shift:

None Part 2

- Performed by on-coming shift A review of the Operating Log since last held shift or 3 days, whichever is less (N/A for AUO5)

A review of the Rounds sheets/Abnormal readings (AUOs only)

Review the following programs for changes since last shift turnover:

Q Standing Orders E

LCO(s) in actions (N/A for AUOs)

Q Immediate required reading E1 TACF (N/A for AUOs Part 3

- Performed by both off-going and on-coming shift A walkdown of the MCR control boards (N/A for AUOs)

Relief Time:

Relief Date:

TVA40741 [03-2001]

Page I of 1 OPDP-l-I [03-14-20011

SHIFT TURNOVER CHECKLIST Page of El SM El US/MCR Unit UO Unit Off-going

- Name E

AUO Station STA (STA Function)

On-coming

- Name Part 1

- Completed by off-going shiftlReviewed by on-coming shift:

Cb= 1807 ppm Abnormal equipment lineup/conditions:

None.

Green risk associated with equipment OOS.

SIJTest in progress/planned: (including need for new brief)

See Schedule Major Activities/Procedures in progress/planned:

The plant is at BOL. A startup is in progress from a forced outage to repair an EHC high pressure piping leak.

Power is stable at 2%. 00-3 Section 5.2 step 12 which required the completion of Appendix A (Mode 2 to Mode 1 approval) was just completed. The Operation Superintendents approval to enter Mode I was just obtained. The crew is in 00-3 Unit Startup From Less Than 4% Reactor Power to 30% Reactor Power section 5.3 step 3.

Radiological changes in plant during shift:

None Part 2

- Performed by on-coming shift Q

A review of the Operating Log since last held shift or 3 days, whichever is less (N/A for AUOs)

El A review of the Rounds sheets/Abnormal readings (AUOs only)

Review the following programs for changes since last shift turnover:

El Standing Orders El LCO(s) in actions (N/A for AUO5)

El Immediate required reading El TACF (N/A for AUOs Part 3

- Performed by both off-going and on-coming shift El A walkdown of the MCR control boards (N/A for AUOs)

Relief Time:

Relief Date:

TVA 40741 [03-20011 Page 1 of 1 OPDP-1-1 [03-14-20011

SHIFT TURNOVER CHECKLIST Page of El SM El US/MCR Unit UO Unit Off-going

- Name E

AUO Station El STA (STA Function)

On-coming

- Name Part 1

- Completed by off-going shiftlReviewed by on-coming shift:

Cb= 1807 ppm Abnormal equipment lineup/conditions:

None.

Green risk associated with equipment OOS.

SJJTest in progress/planned: (including need for new brief)

See Schedule Major Activities/Procedures in progress/planned:

The plant is at BOL. A startup is in progress from a forced outage to repair an EHC high pressure piping leak.

Power is stable at 2%. GO-3 Section 5.2 step 12 which required the completion of Appendix A (Mode 2 to Mode 1 approval) was just completed. The Operation Superintendents approval to enter Mode 1 was just obtained. The crew is in GO-3 Unit Startup From Less Than 4% Reactor Power to 30% Reactor Power section 5.3 step 3.

Radiological changes in plant during shift:

None Part 2

- Performed by on-coming shift El A review of the Operating Log since last held shift or 3 days, whichever is less (N/A for AUO5)

El A review of the Rounds sheets/Abnormal readings (AUO5 only)

Review the following programs for changes since last shift turnover:

El Standing Orders El LCO(s) in actions (N/A for AUOs)

El Immediate required reading El TACF (N/A for AUOs Part 3

- Performed by both off-going and on-coming shift El A walkdown of the MCR control boards (N/A for AUOs)

Relief Time:

Relief Date:

TVA4O74I [03-2001]

Page 1 of 1 OPDP-l-l [03-14-2001]

Administration Of The Reactivity Briefing Sheets And Reactivity Control Plans Appendix A (Page 1 of 1)

Reactivity Control Plan (Example Form)

Station:

WBN Unit:

1 Cycle:

8 Burnup:

150 MWD/MTU Revision:

0 RXES or designee

/

Date Reviewer:

Authorizer:

Ops

/

Date RXE support required Onsite? DYes No Describe: Simulator Scenario Title of Reactivity Control Plan:

Power Escalation for Simulator Assumptions:

Major Steps:

1.

Criticality is attained with Control Bank D

(CBD) at 130 steps 2.

Power escalation proceeds according to schedule 1.

Reactor power raised from HZP to 15%

RTP 2.

Unit is maintained at 15%

RTP for 6 hrs 3.

Unit is ramped to 30% per the schedule 4.

Unit is maintained 30% for flux map Detailed

Description:

NOTE:

See attached plots.

NOTE:

Should deviations occur from the projected power ascension profile, particularly delays, there should be no major effects on the predicted parameters.

Should delays occur, lower dilution rates could be expected later due to the additional Xenon build-in during the delays.

NOTE:

This Reactivity Control Plan only covers power escalation through 30% RTP.

A Reactivity Control Plan covering the remainder of the power escalation will be issued prior to completion of the 30% RTP hold.

Power Increase to

-159 RTP:

1.

WITHDRAW CBD to facilitate power rise.

(The actual amount of rod withdrawal necessary to attain 15%

RTP depends upon the CBD position at criticality.)

2.

IF CBD has been withdrawn to -165 steps and reactor power has not reached 15%

RTP, THEN DILUTE as necessary to raise power to -15% for synchronization of the Turbine-Generator.

(The actual amount of dilution necessary depends upon the CBD position at criticality.)

Operation on Steam Dumps until Generator Synchronization:

WBN 1

TI-7.01 2 Rev. 0004 Page 21 of 23 Preparer:

Approver:

I Date I

RXE I

Date 1.

ENSURE CBD has been withdrawn to -165 steps.

2.

DILUTE 200 gal PW per hour to compensate for Xenon build-in.

WBN Administration Of The Tl-7.012 1

Reactivity Briefing Sheets And Rev. 0004 Reactivity Control Plans Page 21 of 23 Power Escalation for Simulator Continued Power Increase to 30% RTP:

1.

DILUTE -2700 gal PW to raise power to

-30% and maintain Tave matched with Tref.

2.

INITIATE ramp up.

3.

MAINTAIN CBD at 165 steps.

Temporary rod withdrawal above 165 steps is allowed to support increases in reactor power provided CBD is re-inserted to approximately 165 steps once the desired power level is achieved and the dilution effects have caught up.

30% RTP Power Maintenance:

1.

DILUTE -300 gal PW per hour to compensate for Xenon build-in.

2.

MAINTAIN CBD at 165 steps.

Critical Parameter Limit Required Action Rate of Power Increase As specified in TI-45 Reduce ramp rate or hold power until limits satisfied.

Activated:

Terminated:

SM or US I

Date SM or US I

Date

Appendix D Scenario Outline Form ES-D-1 I

Facility:

Watts Bar (2008-B)

Scenario No.:

2 Op Test No.:

1 Examiners:

Operators:

Initial Conditions:

100% power, ECL, 69 ppm boron. 1A MD AFW Pump COS for motor bearing replacement. 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months remain in LCC 3.7.5, Action B.

Turnover:

Maintain current power level. However, 1A Condensate Booster Pump has a small oil leak. A power reduction to 96% is being discussed by Ops Management in order to remove the pump from service.

Event MaIf. No.

Event Event Description No.

Type*

1 RP26E 0 1-BOP Steam Pressure Transmitter 1-PT-i -20A fails low. BOP manually I-SRO controls feed to #3 S/G. AOI-16 entry. Tech Spec evaluation.

2 ZAIPIC6834 C-RC 1 -PIC-68-340A PZR Master Controller fails. Spray valves open 100 TS-SRC and all heaters deenergize. RO manually controls PZR pressure.

RCRO5 AOl-lB entry.

3 RXO2D I-AC Loop 4 Cold Leg RTD fails high, resulting in rod insertion. Tech

- SRO Spec evaluation.

4 CCO5B C

- BOP CCS leak inside containment on thermal barrier supply line to 2 C

- SAC RCP. Entry into AOl-is..

5 THO5C M-ALL

3 S/G tube leak (40 gpm). ACI-33 entry. Tech Spec evaluation.

6 N/A A-AC Power reduction due to S/G Tube leak N-SAC N-BCP 7

THO5C M-ALL

3 S/G tube leak progresses to a S/G tube rupture. ECP network entry.

8 ZDIRT 1 C-AC Reactor Trip Switch on 1 -M-4 fails to initiate a reactor trip. RC Neutral operates i-M-6 trip switch.

9 SIO9L C-AC Containment Phase A fails to automatically actuate. AC manual SIO9M action.

10 MS13C M-ALL Steam leak #3 S/G @ 0.2%, when SI is reset in E-3 cooldown.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG 1021 Revision 9, Supplement 1

Appendix D Scenario Outline Form ES-D-1 Scenario 2 Summary Initial Conditions:

The plant is stable at 100%, EOL, 69 ppm boron. 1A MD AFW Pump OOS for motor bearing replacement.

28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months remain in LCO 3.7.5, Action B. Plan is to stay at current power level. However, 1A Condensate Booster Pump has a small oil leak. A power reduction to 96% is being discussed by Ops Management for removing the pump from service.

1 -PT-68-322, Channel IV Pressurizer Pressure Transmitter failed during the last shift and has been removed from service to comply with Tech Specs.

1.

Steam Pressure Transmitter i-PT-i -20A fails low. BOP takes manual control of #3 SIG feed flow to avoid a reactor trip lAW AOl-16 Loss of Normal Feedwater. Tech Spec evaluation.

2.

1 -PIC-68-340A PZR Master Controller fails, causing spray valves to open and all heaters to deenergize. RO manually controls i-PIC-68-340A to control PZR pressure. Enter AOl-18 Malfunction of Pressurizer Pressure Control System.

3.

Eagle-21 Rack 4 EAI board #3 loss of 15v power supply. Results in 1-PT-i -73 (Turbine Impulse Pressure) and 1-LT-63-i80 (Containment Sump Level) failing low. RO manually controls. Enter AOl-44 Eagle 21 Malfunctions, and AOl-2 Malfunction of Reactor Control System. Tech Spec evaluation.

4.

CCS leak occurs in containment on the supply line to the 1 B RCP Thermal Barrier. The crew enters AOl-is Loss of Component Cooling Water. Requires BOP actions to isolate the leak.

5.

A tube leak (40 gpm) occurs on # 3 S/G. Enter AOl-33, Steam Generator Tube Leak. Tech Spec evaluation.

6.

Either the crew decides to perform a rapid down power lAW AOl-39 or Operations management notifies the crew to do so.

7.

The # 3 S/G tube leak progresses to a S/G tube rupture, requiring the crew to trip the reactor and enter E-0. The manual trip switch on 1 -M-4 fails to initiate a reactor trip. RO operates the 1 -M-6 trip switch.

8.

When SI actuates in E-0, Containment Phase A fails to automatically actuate. RO manually actuates Phase A.

9.

After transition to E-3 and during the cooldown to target temperature, a fault occurs on # 3 S/G. Crew transitions to ECA-3.1.

10. Scenario terminates when the crew has started a plant cooldown lAW ECA-3.i.

1 2

Critical Tasks:

Close containment Isolate steam flow and isolation valves such feedwater flow to the that at least one valve is ruptured S/G prior to closed on each critical initiation of RCS cooldown phase-A penetration to the target temperature.

before transition out of E-0.

Appendix D NUREG 1021 Revision 9, Supplement 1

Page 1 of 4 NRCO8A Rev 0 CONSOLE OPERATOR INSTRUCTIONS SCENARIO #2 STEAM GENERATOR TUBE RUPTRE WITH FAULT EVENT I

IC/MF/RF/OR #

I DESCRIPTION/FEEDBACK rst 249, switch check, select RUN Sim. Setup 100% RTP, EOL, Cb - 69 ppm.

This IC contains the verify malfunctions and overrides listed overrides and triggers.

below 0

Turns off audible alarm for the simulator fault so the Disable simulator fault alarm crew cannot hear this alarm.

0 Place A Train week 1 placard on On entrance side panel.

entrance side panel.

0 Place DANGER Tag on 1A MDAFW 1A MDAFW out of service.

Hand Switch Indicate/Enter in the appropriate blanks Ensure EOL Reactivity Briefing Book is used. Item this information into the reactivity 3: Delta I -3 and AUTO rod control.

briefing book, (appendix B TI-7.012)

Item 4: Negative, i-CCP B, 70 0

Item 5: 69, Boron, BA 1, PW 70, BA Pot 2, PW POT 35 Item 6: PW 200 gal Item 7: PW 200 gal Sim Setup ifIC 249 rst 60, switch check, select run.

100% RTP, EOL, Cb - 69 ppm.

does not work.

1A MDAFW out of service. Prevents start of pump 0

batch OOSAFWP_A and turns breaker lamp off.

0 imf RX26E (el) 0 Steam Pressure Transmitter 1-PT-i -20A fails low 0

iorZAIPIC6834O 100 PRZR Master Controller fails high 0

imfRXO2D (e3) 100 Loop 4 Cold Leg RTD fails high imf CCO5B (e4)

CCS leak inside CNTMT on thermal barrier supply_to_RCP #2 0

imfTHO5C (e5) 2.5

3 S/G tube leak - 45 gpm imfMSl3 (e6) 5

3 S/G steam leak @ 2%

0 iorZDIRT 1 RTS on 1 -M-4 fails to initiate a reactor trip br SIO9L CNTMT Phase A fails to automatically actuate 0

iorSIO9M

Page 2 of 4 NRCO8A Rev 0 CONSOLE OPERATOR INSTRUCTIONS SCENARIO #2 STEAM GENERATOR TUBE RUPTRE WITH FAULT EVENT I

IC/MF/RF/OR #

I DESCRIPTION/FEEDBACK Event # 1:

imf RX26E (el) 0 Steam Pressure Transmitter 1-PT-1-20A fails low.

Insert this When MIG/ Work Control notified acknowledge Malfunction using report.

Trig2er 1 Event #2:

iorZAIPIC6834 100 PRZR Master Controller fails high When determined by mrf rcO5 remote NRC Examiner, Insert When MIG/ Work Control notified acknowledge this problem by report.

changing Remote Function RCROS to REMOTE Event #3:

1mfRXO2D (e3) 100 Loop 4 Cold Leg RTD fails high When actions When MIG/ Work Control notified acknowledge associated with AOl-report 18 are complete as determined by NRC Examiner, Insert this Malfunction using Trigger 3 Event #4:

CCS leak inside CNTMT on thermal barrier imf CCO5B (e4) supply line to #2 RCP When determined by NRC Examiner, Insert If notified as work control/maintenance concerning this Malfunction CCS leak acknowledge request.

using Tri2ger 4

Page 3 of 4 NRCO8A Rev 0 CONSOLE OPERATOR INSTRUCTIONS SCENARIO #2 STEAM GENERATOR TUBE RUPTRE WITH FAULT EVENT IC/MF/RF/OR #

I DESCRIPTION/FEEDBACK Event #5:

imf THO5C (e5) 2.5

3 SIG Tube leak of approximately 40 gpm..

When determined by NRC Examiner, Insert When RADPRO is notified state that you will send a this Malfunction Tech to survey the steam lines. Wait 15 minutes (or using TriggerS until MCR has identified #3 SIG) and report that # 3 SIG Main Steam Lines have higher radiation.

When Chemistry is notified state that you will send a tech to sample the SIGs. Wait 30 minutes and report that # 3 S/G has high activity.

If asked as AUO to open 1-FCV-14-3 wait 5 minutes and report valve is open.

Event #6 When directed by the Lead Examiner (or if the crew decides to utilize a rate of 1 %Ihr or less),

Rapid Load notify the crew of Managements decision to lower Reduction power at 2 %/hr.

When notified by the Lead Examiner increase the mmf THO5C 30 malfunction to 30 to input the SGTR.

Page 4 of 4 NRCO8A Rev 0 CONSOLE OPERATOR INSTRUCTIONS SCENARIO #2 STEAM GENERATOR TUBE RUPTRE WITH FAULT EVENT I

ICIMFIRFIOR #

I DESCRIPTION/FEEDBACK Events #7 imf msl3c (e6).2

3 S/G steam leak between CNTMT and MSIV When determined by NRC Lead Examiner, Insert this As AUO or Security, when asked to investigate the Malfunction using steam leak, wait 5 minutes and report that steam is Trigger 6 coming from the North Vault Room:

When notifeid as Chemistry acknowledge report When notified as RADPRO acknowledge report

I Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

NRC Scenario #

2 Event #

1 Page 1

of 44 Event

Description:

Steam Pressure Transmitter 1-PT-1-20A fails low Position Applicants Actions or Behavior Time Booth Instructor:

When directed, initiate Event 1 (Trigger 1)

Indications available:

3 SG Press Indicator (1-Pl-1-20A) tails to 0 Alarm 63-F SG Level Deviation Alarm 118-A SG 3 Press LO Crew Diagnose a reduction in Feed Water to # 3 S/G.

BOP May take PRUDENT Operator action lAW Tl-12.04 to take manual control of feed water flow to the #3 S/S SRO Direct crew actions lAW AOl-i 6 Loss of Normal Feedwater Evaluator Note: Following Steps are from AOI-16 Loss of Normal Feedwater, Section 3.1 Diagnostics and then to section 3.6 3.1 Diagnostics IF GOTO Subsection Standby MFWP TRIP without Main Turbine in service 3.2 Standby MFWP TRIP with Main Turbine in service 3.3 SRO MFWP TRIP less than 800 MWe 3.4 (67% Turbine Load)

MFWP TRIP greater than or equal to 800 MWe 3.5 (67% Turbine Load)

MEW reg or bypass reg valve control failure 3.6 MEW pump speed control circuit failure 3.7 BOP

1. CONTROL failed MFW reg or bypass reg valve in MANUAL.

2. EVALUATE placing control rods in MANUAL.

RO The SRO may or may not direct RO to place Rods in manual, depending upon how much of effect the feedwater transient has on Tavg.

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

NRC Scenario #

2 Event #

1 Page 2

of 44 Event

Description:

Steam Pressure Transmitter 1 -PT-i -20A fails low Time Position Applicants Actions or Behavior

3. CHECK SG levels on bypass reg valve control.

BOP GO TO Step 5

5. CHECK S/G levels returning to PROGRAM.

6. MONITOR TDMFW Pump speed normal for current power level.

BOP The SRO may or may not direct BOP to place TDMFW Pump speed control in manual, depending upon how effective automatic speed control responds to the transient.

7. WHEN any SIG MEW flow drops to less than 0.55 x 10 E6 lb/hr, THEN INITIATE manual anti-water hammer actions:

Step is N/A

8. CHECK power range NORMAL.

RO NOTE Steps 9 & 10 should end up having the same channel (A or B) selected for steam flow and teed flow on each SIG to ensure a loss of voltage to any one channel will have minimal effect on the affected S/G level.

9. CHECK controlling steam flow Channels NORMAL.

a. SELECT operable channel.

b. EVALUATE effect of the failed channel on the MEPs Speed Control and ADJUST in MANUAL as necessary while continuing this section.

Appendix D Required Operator Actions Form ES-D-2 NRC Scenario #

2 Event #

1 Page 3

of 44 Event

Description:

Steam Pressure Transmitter 1 -PT-i -20A fails low Applicants Actions or Behavior Op Test No.:

Time Position

10. CHECK controlling FW flow channels NORMAL.

Perform RNO:

BOP lAW Note above, even though a FWflow channel did not fail, another channel is selected, to match steam flow channels.

11. CHECK press compensation channel(s) NORMAL.

Perform RNO:

SRO REFER TO Tech Specs:

LCO 3.3.2. i.e condition D, LCO 3.3.2.4.d condition D, LCO 3.3.3 Condition A.

12. IF affected S/G controlling channel and level NORMAL, RO THEN RETURN MFW reg valve to AUTO.

13. WHEN conditions allow auto rod control, THEN,

a. ENSURE T-avg and T-ref within 1°F.

b. ENSURE zero demand on control rod position indication

[1 -M-4].

c. PLACE rods in AUTO.

13. INITIATE repairs to failed equipment.

SRO When technicai specifications have been identified or at discretion of the Lead Examiner, proceed to the next event

Appendix D Required Operator Actions Form ES-D-2 NRC Scenario #

Op Test No.:

Event

Description:

1-PIC-68-340A PZR Master Controller output signal fails high Applicants Actions or Behavior Time II Position 2

Event #

2 Page 4

of 44 Booth Instructor:

When directed, initiate Event 2 (mn RCRO5 remote)

Indications available:

Alarm 90A PZR Press Hi RCS Pressure Lowering Crew Diagnose a failure of 1-PIC-68-340A PZR Master Controller.

May take PRUDENT Operator action lAW Tl-12.04 to take RO manual control of 1-PIC-68-340A PZR Master Controller and lower the controller output to close the spray valves and energize heaters to raise RCS pressure to 2235 psig.

Direct crew actions lAW AOI-18 MALFUNCTION OF SRO PRESSURIZER PRESSURE CONTROL SYSTEM..

Evaluator Note: Following Steps are from AOI-18 MALFUNCTION OF PRESSURIZER PRESSURE CONTROL SYSTEM, section 3.0.

1. CHECK pressurizer pressure stable or trending to desired pressure:

Pl-68-340A, P1-68-334, P1-68-323, RO P1-68-322.

Perform RNO:

PLACE pzr master controller 1-PIC-68-340A in MANUAL and RESTORE press to normal

2. CHECK 1-XS-68-340D selected to a failed, controlling or backup channel.

RO Perform RNO:

IF pzr press is abnormally low, THEN ** GO TO Step 6.

I Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

NRC Scenario #

2 Event #

2 Page 5

of 44 Event

Description:

1-PIC-68-340A PZR Master Controller output signal fails high Applicants Actions or Behavior Time II Position

6. CHECK pzr spray valves CLOSED:

Green indicating lights LIT.

RO Pzr spray demand meters, 1-PIC-68-340B and 1-PlC-68-340D indicating ZERO [1-M-4].

7. CHECK pzr PORVs CLOSED:

RO EVALUATE tailpipe temperatures and acoustic monitor.

8. CHECK pzr Safeties CLOSED:

RO EVALUATE tailpipe temperatures and acoustic monitor.

9. ENSURE pzr heaters on as required:

RO Control Group on at 2220 psig.

Backup Groups on at 2210 psig.

10. CHECK aux spray, 1-FCV-62-84, CLOSED.

11. CHECK pzr press STABLE or RISING.

12. ** GO TO Step 16.

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

NRC Scenario #

2 Event #

2 Page 6

of 44 Event

Description:

1-PIC-68-340A PZR Master Controller output signal fails high Time Position Applicants Actions or Behavior Evaluator Note: The SRO should direct that Pzr Heater controllers and Spray controllers are placed in Auto, but the PZR Master controller remains in manual and direction given to the RO to control RCS pressure.

16. WHEN pressurizer pressure stable and equipment status supports returned to normal, THEN ENSURE the following in AUTO:

RO Pzr Master controller, Pzr spray controllers, All heater groups.

17. REFER TO the following Tech Specs:

SRO DNB Spec 3.4.1 if RCS Pressure lowers to 2214 psig or lower.

18. INITIATE repairs to failed equipment.

SRO At the discretion of the Lead Examiner, proceed to the next event

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

Applicants Actions or Behavior NRC Scenario #

2 Event #

3 Page 7

of 44 Event

Description:

Loop 4 Cold Leg RTD fails high, resulting in rod insertion.

Time Position Booth Instructor:

When directed, initiate Event 3 (Trigger 3)

Indications available:

Continuous Control Rod insertion.

Alarm 93-F EAGLE PROC PROT CH-IV RTD FAILURE Alarm 93A RCS LOOP AT DEVIATION Alarm 94A TAVG-TREF DEVIATION Alarm 94B TAVG-T AUCT DEVIATION Alarm 1 1OF PROT SET TROUBLE Loop 4 AT Power Indication 35% (1-TI-68-67B)

Loop 4 Tavg indication 604° F (1-Tl-68-67E)

Auctioneered Tavci indication 604° F (1-TR-68-2B)

The crew should diagnose that there has been a malfunction of Crew the Reactor Control system since the rods are continuously inserting, and there no indications of a plant runback since MWe is constant.

RO Takes Prudent Operator action lAW TI-12.04 to place Rod Control in MANUAL to stop continuous rod insertion.

Evaluator Note: Following Steps are from AOI-2 MALFUNCTION OF REACTOR CONTROL SYSTEM Directs actions lAW AOI-2 MALFUNCTION OF REACTOR CONTROL SYSTEM 31 Diagnostics Diagnostics IF GO TO Subsection SRO Continuous Rod Withdrawalllnsertion 3.2 (Page 6)

Instrument failure (e.g. T-avg, NIS, PT-i -73) with Rod Control in MAN 3.2 (Page 6)

Dropped RCCA 3.3 (Page ii)

RCCA Misalignment 3.4 (Page 21)

Rod Position Indicator (RPI) Malfunction 3.5 (Page 39)

Failure of Control Rods to Move on Demand 3.6 (Page 42)

Goes to Subsection 3.2

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

Op Test No.:

NRC Scenario #

2 Event #

3 Page 8

of 44 Event

Description:

Loop 4 Cold Leg RTD fails high, resulting in rod insertion.

Time Position N

Applicants Actions or Behavior 1.

PLACE control rods in MAN.

RO 2.

CHECK control rod movement STOPPED.

RO 3.

MAINTAIN T-avg on PROGRAM.

(Reference Attachment 1)

RO USE control rods.

OR ADJUST turbine load.

Evaluator Note:

The following is the portion of AOI-2 Attachment 1 that is expected to be use now in the scenario and later during the down power to remove the 1A CBP.

RX TAVE-PZR POWER TREF LEVEL 90%

583.3 °F 56.5 %

92%

583.9 °F 57.2 %

94%

584.4 °F 57.9 %

96%

585.0 °F 58.6 %

98%

585.6 °F 59.3 %

100%

586.2°F 60.0%

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

NRC Scenario #

2 Event #

3 Page 9

of 44 Event

Description:

Loop 4 Cold Leg RTD fails high, resulting in rod insertion.

Time Position Applicants Actions or Behavior

4. CHECK loop T-avg channels NORMAL.

Performs RNO DEFEAT failed loop AT and loop Tavg channels by placing 1-XS-68-2D, AT CHANNEL DEFEAT, and 1-XS-68-2M, TAVG CHANNEL DEFEAT, in failed channel position then PULL.

ENSURE TR-68-2A placed to operable channel using.1-XS-68..2B, AT RCDR TR-68-2A LOOP SELECT [1-M-5j.

RO NOTIFY Maintenance to implement IMI-1 60 for failed channel.

WHEN at least 3 minutes have elapsed since failed T-avg channel is defeated, THEN a) ENSURE T-avg and T-ref within 1 °F.

b) ENSURE zero demand on control rod position indication [1-M-4].

c) PLACE rods in AUTO.

5. CHECK Auct Tavg NORMAL on 1-TR-68-2B.

6. CHECK NIS power range channels NORMAL.

7. CHECK the following: PLACE steam dumps in pressure mode as follows:

Turbine impulse pressure channel 1-PI-1-73, RO NORMAL. a. PLACE steam dumps to OFF.

Tref and Auct Tavg NORMAL b. PLACE mode selector HS to on 1-TR-68-2B STEAM PRESS.

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

NRC Scenario #

2 Event #

3 Page 10 of 44 Event

Description:

Loop 4 Cold Leg RTD fails high, resulting in rod insertion.

Time Applicants Actions or Behavior Position

8. MONITOR core power distribution parameters:

Power range channels.

A Flux Indicators.

T-avg.

Loop AT.

RO Incore TCs.

Feed flow/Steam flow.

RO should make recommendations for withdrawing Control Bank D back out to 220 steps.

9. INITIATE repairs to failed equipment.

10. REFER TO Tech Specs:

Refers to Tech Specs, announces entry into:

SRO LCO 3.3.1, Table 3.3.1-1, item 6 & 7 condition W, item 13 condition V, LCO 3.3.2, Table 3.3.2-1, item 6.b, condition N.

When technical specifications have been identified or at discretion of the Lead Examiner, proceed to the next event

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

NRC Scenario #

2 Event #

4 Page 11 of 44 Event

Description:

CCS leak inside containment on thermal barrier supply line Applicants Actions or Behavior Time U

Position Booth Instructor:

When directed, initiate Event 4 (Trigger 4)

Indications available:

Alarm 237B RCP 1 Thermal barrier RET Flow LO Alarm 238B RCP 2 Thermal barrier RET Flow LO Alarm 239B RCP 3 Thermal barrier RET Flow LO Alarm 240B RCP 4 Thermal barrier RET Flow LO Thermal Barrier #2 HX AP (1 -PDI-70-1 04) reading 0 Thermal Barrier #2 HX Flow (1-PDI-70-105) reading 0 Thermal Barrier RET HDR Flow lowers to 112 gpm Alarm 83D Rx Bldg Pocket Sump Rate of Rise Alarm 160C Rx Bldg Pocket Sump Level Hi CCS Surge Tank slowly rising BOP Should diagnose that a leak is occurring in the CCS supply line to #2 RCP.

Direct crew actions lAW AOI-15 LOSS OF COMPONENT SRO COOLING WATER (CCS).

Evaluator Note: Following Steps are from AOl-i 5 LOSS OF COMPONENT COOLING WATER (CCS), section 3.2.

1. CHECK CCS pumps status:

a. CHECK any CCS pump TRIPPED or running pump NOT pumping forward BOP Perform RNO:

GO TO Caution prior to Step 2.

2. CHECK i-FCV-70-66, Ui Surge Tank Vent, OPEN.

3. IF surge tank level less than 57%, THEN ENSURE i-LCV BOP 70-63, Ui Surge Tank Makeup LCV, OPEN (Refer to SOI-70.Oi as required if makeup not available).

Appendix D Required Operator Actions Form ES-D-2 NRC Scenario #

2 Event #

4 Page 12 of 44 Event

Description:

CCS leak inside containment on thermal barrier supply line Time Position Applicants Actions or Behavior Op Test No.:

4. MONITOR A and B side surge tank levels greater than 10%.

5. IF RHR Shutdown Cooling is in service, THEN GO TO AOl-14, Loss Of RHR Shutdown Cooling.

6. MONITOR the following for Unit 1 CCS Train A:

U-i CCS Train A level ERCW flow to CCS Hx A IF loss of either is imminent, THEN PERFORM the following:

BOP PERFORM RNO:

GO TO Step 7.

7. MONITOR the following for Unit 1 CCS Train B:

U-i CCS Train B level ERCW flow to CCS Hx C BOP IF loss of either is imminent, THEN STOP and LOCKOUT the following Train B equipment:

STEP IS N/A

8. CHECK all RCP upper and lower oil cooler flows NORMAL:

BOP Upper Cooler flow: 150-220 gpm Lower Cooler flow: 5-10 gpm

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

Event

Description:

CCS leak inside containment on thermal barrier supply line Time Position Applicants Actions or Behavior NRC Scenario #

2 Event #

4 Page 13 of 44 Evaluator Note: In the following step, when the performer secures the TBBPs, the STBY Pump should be placed in PTL first, and then stop and place the running pump in PTL. This prevents auto start of the STBY pump.

9. CHECK Thermal Barrier Hx flows NORMAL.

Thermal Barrier flow 40-50 gpm Perform RNO:

IF flow abnormally high or low indicating possible line break, THEN:

a. ENSURE Thermal Barrier Booster pumps STOPPED.

b. ENSURE the following isol valves CLOSED:

FCV-70-133 or FCV-70-134, Thermal Barrier Supply FCV-70-87 or FCV-70-90, Thermal Barrier Return.

c. IF RCP lower bearing temp rising uncontrolled (180 °F max), THEN REFER TO AOl-24, Reactor Coolant Pump Seal Abnormalities.

10. CHECK 1A ESF Supply Header flow NORMAL, BOP 1-Fl-70-159A.

Normal --100 gpm with RHR out of service.

11. CHECK 1 B ESF Supply Header flow NORMAL, BOP 1-Fl-70-165A.

Normal 5000-6000 gpm with RHR in service.

12. CHECK SEP Hx A flow NORMAL, 0-Fl-70-20.

BOP Normal 2700-3500 gpm with SEP Hx A in service.

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

NRC Scenario #

2 Event #

4 Page 14 of 44 Event

Description:

CCS leak inside containment on thermal barrier supply line Time Position Applicants Actions or Behavior

13. CHECK SEP Hx B flow NORMAL, O-Fl-70-6.

BOP Normal top of scale with SEP Hx B in service (may require local observation to determine if leak exists).

14. IF leak location can be isolated, THEN RETURN CCS BOP surge tank to normal level (refer to SOl-70.O1).

15. EVALUATE affected equipment operation USING BOP Appendix A.

16. WHEN CCS returned normal, THEN BOP CHECK only one CCS pump per Train.

CHECK one TBBP running. (Step is N/A)

17. REFER TO Tech Specs 3.7.7, Component Cooling Water System (CCS).

SRO Step is N/A for CCS, however see ARI 83D and ARI 160C actions starting on the next page.

18. INITIATE repairs.

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

NRC Scenario#

2 Event#

4 Page 15 of 44 Event

Description:

CCS leak inside containment on thermal barrier supply line Applicants Actions or Behavior Time U

Position Evaluator Note:

The following are steps from AR! 83D Plant Computer Generated Alarm. (steps 1 and 5 are only steps that are applicable)

[1] CHECK ICS computer Annunciator 83D Alarms screen.

[5] IF pocket sump Rate of Rise in alarm, REFER TO window RO 160-C Evaluator Note:

The following are the first S steps from ARI-160C RX BLDG Pocket 1] CHECK pocket sump level by one or more of the following:

1-Ll-77-410, RB POCKET SUMP LEVEL [1-M-15].

SRO 1-Ll-77-411, RB POCKET SUMP LEVEL [1-M-15].

Plant Computer (L0472A & L0473A).

2] ENSURE window 159-C, RX BLDG F&EQ SUMP LEVEL SRO HI,NOTLIT.

SRO 3] START Pocket Sump Pump(s).

[4] IF Pocket Sump rate-of-rise alarms on plant computer, THEN

[a]

INITIATE 1-SI-68-32, Reactor Coolant System Water SRO Inventory Balance.

[b]

IF RCS leak is NOT suspected, THEN EVALUATE the need for entering LCO 3.4.15.

[5] IF Pocket Sump Inleakage Bias alarms on plant computer, THEN EVALUATE the need for entering LCO 3.4.15.

SRO SRO should declare Rate of Rise function of Pocket Sump level monitor inoperable while AR! 83D is in alarm for rate of rise. Tech Spec LCO 3.4.15 condition A.

At the Lead Evaluators discretion proceed to the next event.

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

NRC Scenario#

2 Event#

5 Page 16 of 44 Event

Description:

3 S/G tube leak (-.40 gpm). AOl-33 entry Applicants Actions or Behavior Time Position Booth Instructor:

When directed, initiate Event 5 (Trigger 5)

Indications available:

Vacuum Pump exhaust rad monitor RISING.

Alarm 175B Vac Pmp Exhaust 1-RM..1 19 Rad Hi Charging flow RISING.

Pressurizer Level lowering CREW Should diagnose that a S/G Tube Leak is occu ring Direct crew actions lAW AOI-33 STEAM GENERATOR SRO TUBE LEAK Evaluator Note: Following Steps are from AOl-33 STEAM GENERATOR TUBE LEAK, section 3.0.

1. CHECK If PZR Level Can Be Maintained:

a. CONTROL charging flow as necessary.

1. OPEN 1-FCV-62-93 as required.

2. OPEN 1-FCV-62-89 as required.

b. MONITOR pzr level STABLE or INCREASING.

2. IDENTIFY Leaking SG(s);

a. EVALUATE the following:

Unexpected rise in any SG narrow range level, Feedwater flow mismatches, High radiation from any Chemistry SG sample

results, BOP High radiation on any SG main steamline radiation

monitor, RADCON survey of main steamlines and SG blowdown lines.

b. MONITOR Condenser Vacuum Exhaust and SG Blowdown Radiation Monitors

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

Applicants Actions or Behavior NRC Scenario #

2 Event #

5 Page 17 of 44 Event

Description:

3 S/G tube leak (4O gpm).

AOI-33 entry Time II Position

3. CHECK If VCT Level Can Be Maintained:

a. MAINTAIN VCT level greater than 13%, using automatic OR manual makeup.

Evaluator Note: When management notified, the direction will be to shut down the plant at 2 %/hr.

CREW Determine SIG Tube Leak rate to be 45 gpm.

4. DETERMINE If Plant Shutdown Is Required:

High Secondary Radiation, AND SRO PZR level continues to decrease, OR Charging flow continues to rise.

5. NOTIFY The Following:

a. Plant personnel via PA system.

Attention plant personnel. The Unit has developed a SIG tube leak and Unit shutdown is in progress.

Treat all leaks as radioactive.

b. Operations Manager.

SRO C. RadCon to survey secondary plant and site environment.

d. Chemistry to initiate the following:

Hourly RCS Cb sampling.

CM..5.O1, Primary to Secondary Leak Rate Methods.

CM-9.93, Abnormal Release Assessment (for unmonitored steam releases such as SG PORVs and TD AFWP).

ODI-90-2, Steam Generator Blowdown Release.

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

NRC Scenario #

2 Event #

5 Page 18 of 44 Event

Description:

3 SIG tube leak (40 gpm). AOl-33 entry Position Applicants Actions or Behavior Time

6. PERFORM The Following Evaluations:

a. EVALUATE Tech Specs for applicability:

3.4.13, RCS Operational Leakage, SRO SRO to evaluate Tech Spec 3.4.13 and determine secondary leakage is out of spec and LCO states to be in spec within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and be in Mode 3, 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after that.

b. EVALUATE EPIP-1, Emergency Plan Classification Matrix.

7. CHECK Unit Load -GREATER THAN 30%:

a. INITIATE unit shutdown USING:

SRO AOI-39, Rapid Load Reduction.

AND CONTINUE performance of this procedure.

8. MONITOR CST Level

- GREATER THAN 200,000 GAL,

9. MINIMIZE Secondary System Contamination:

a. CONTROL Condensate return to CST:

1. PLACE 1-LIC-2-3, in MANUAL, and CLOSE.

2. MAINTAIN condenser level 1-LR-2-12 onscale [1-M-3].

Evaluator Note:

Event 6 Power Reduction IAWAOI-39 starts on the next page.

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

NRC Scenario #

2 Event #

6 Page 19 of 44 Event

Description:

AOI-39 Rapid Load Reduction Time Applicants Actions or Behavior Position Booth Instructor: NONE Indications: None SRO Directs the crew to perform a rapid load reduction lAW AOI-39

1. ESTABLISH a turbine load reduction rate less than or equal to 5%/mm:

a. SET a desired load in the SETTER with the REFERENCE CONTROL.

b. SET the LOAD RATE at less than or equal to 5%/rn in.

c. DEPRESS GO pushbutton.

2. INITIATE a manual boration:

a. DETERMINE recommended boration flowrate and volume from table below.

TURBINE LOAD BORATION BORIC ACID VOLUME REDUCTION RATE FLOWRATE TO REDUCE POWER

(%Imin)

(gallmin)

FROM 100% TO 20%

2%

20 GPM 3%

30 GPM 800 GALs 4%

40 GPM TOTAL

b. INITIATE boration to maintain control rods above low-low RO insertion limit:

1) ADJUST BA flow controller, 1-FC-62-139, to desired flow rate.

2) ADJUST BA batch counter 1-FQ-62-139 to required quantity.

3) PLACE mode selector 1-HS-62-140B to BOR.

4) PLACE VCT makeup control 1-HS-62-140A, to START.

5) VERIFY desired boric acid flow indicated on 1-FI 139.

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

Event

Description:

AOl-39 Rapid Load Reduction Applicants Actions or Behavior NRC Scenario #

2 Event #

6 Page 20 of 44 Time II Position

3. REFER TO EPIP-1, Emergency Plan Classification Flowchart.

4. NOTIFY the Load Coordinator of the required load reduction and expected ramp rate.

NOTE IF reactor power is stabilized at a lower level a drop in Tavg will occur due to Xenon build up. Dilution may be required to maintain power level.

5. MONITOR Tavg and Tref:

Tavg trending to Tref.

RO Mismatch less than 5°F.

RO 6.

CHECK rate of power reduction is rapid enough for existing plant conditions.

BOP BOP 7.

NOTIFY Cnds Demin AUO of impending pmp shutdowns.

8.

WHEN rated thermal power change exceeds 15% in one us hour, NOTIFY Chemistry to initiate 1 -Sl-68-28.

Lead Evaluator Note:

Cue console operator to implement the next event at your_discretion.

9.

WHEN between 70 and 75% power, THEN REMOVE one Cnds Bstr Pmp and one Cnds Demin Pmp from service:

PLACE selected Cnds Bstr Pmp handswitch to STOP.

BOP PLACE selected Cnds Demin Pmp handswitch to STOP, and CLOSE the suction valve.

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

NRC Scenario #

2 Event #

6 Page 21 of 44 Event

Description:

AOl-39 Rapid Load Reduction Time I

Position Applicants Actions or Behavior Evaluator Note: When Lead Evaluator cue console operator to raise the severity to a SGTR, the following AOl-33 MONITOR step will be applicable:

1. CHECK If PZR Level Can Be Maintained:

b. MONITOR pzr level STABLE or INCREASING.

Perform RNO:

b. PERFORM the following;

1. ISOLATE letdown as necessary.

2. INCREASE chg flow, and start additional chg pmp as needed.

3. IF loss of PZR level is imminent, THEN a) TRIP the reactor.

b) WHEN reactor trip is verified, THEN INITIATE Safety Injection.

c) GO TO E-O, Reactor Trip or Safety Injection, Step 1.

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

NRC Scenario #

2 Event #

7, 8, & 9 Page 22 of 44 Event

Description:

E-O, to E-3 cool down to target temperature Applicants Actions or Behavior Time II Position Booth Instructor: NONE Indications Directs RO to manual trip the Reactor, VERIFY that the SRO Reactor Trips, then manually actuate Safety Injection.

Evaluator Note: The Reactor Trip switch on 1 -M-4 will not work, if the RO attempts that switch first, the RO should go to Reactor Trip switch on 1-M-6.

RO Manual trip the Reactor, VERIFY that the Reactor Trips, RO Manually actuate Safety Injection Evaluator Note:

The following are steps from E-O.

NOTE 1 Steps 1 thru 4 are IMMEDIATE ACTION STEPS.

NOTE 2 Status Trees / SPDS should be monitored when transitioned to another instruction.

1. ENSURE reactor trip:

Reactor trip and bypass breakers OPEN.

RPI5 at bottom of scale.

Neutron flux DROPPING.

2. ENSURE Turbine Trip:

All turbine stop valves CLOSED.

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

NRC Scenario #

2 Event #

7, 8, & 9 Page 23 of 44 Event

Description:

E-O, to E-3 cool down to target temperature Time Position Applicants Actions or Behavior

3. CHECK 6.9 kV shutdown boards:

a. At least one board energized from: CSST (offsite), OR DIG (blackout).

4. CHECK SI actuated:

a. Any SI annunciator LIT.

b. Both trains SI ACTUATED.

1 -XX-55-6C

1 -XX-55-6D BOP Evaluator Note:

Appendix A (E-O), SI Support Systems, and Appendix B, Phase B Pipe Break Contingencies are contained at the end of this document.

5. EVALUATE support systems:

REFER TO Appendixes A and B (E-0), Equipment Verification pages 1 5-28.

6. ANNOUNCE reactor trip and BOP safety injection over PA system.

7. ENSURE secondary heat sink RO available with either:

Total AFW flow greater than 410 gpm, OR

At least one S/G NR level greater than 29% [39% ADV].

8. MONITOR RCS temp stable at or trending to 557° F:

IF any RCP running, THEN MONITOR RCS Loop T-avg trending to 557° F.

RO OR

IF NO RCP running, THEN MONITOR RCS Loop T-cold trending to 557° F.

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

NRC Scenario #

2 Event #

7, 8, & 9 Page 24 of 44 Event

Description:

E-O, to E-3 cool down to target temperature Time Position Applicants Actions or Behavior

9. ENSURE excess letdown valves CLOSED:

1-FCV-62-54

1-FCV-62-55

10. CHECK pzr PORVs and block valves:

a. Pzr PORVs CLOSED.

b. At least one block valve OPEN.

11. CHECK pzr safety valves CLOSED:

EVALUATE tailpipe temperatures and acoustic monitors.

12. CHECK pzr sprays CLOSED.

13. CHECK if RCPs should remain in service:

a. Phase B signals DARK [MISSPj.

b. RCS pressure greater than 1500 psig.

14. CHECK S/G pressures:

All SIG pressures controlled or rising.

All SIG pressures greater than 120 psig.

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

NRC Scenario #

2 Event #

7, 8, & 9 Page 25 of 44 Event

Description:

E-O, to E-3 cool down to target temperature Time Position Applicants Actions or Behavior

15. CHECK for RUPTURED SIG

All S/Gs narrow range levels CONTROLLED or DROPPING.

Secondary side radiation NORMAL from Appendix A.

RO Perform RNO:

IF any S/G has level rising in an uncontrolled manner or has high radiation, THEN

- GO TO E-3, Steam Generator Tube Rupture.

Evaluator Note:

SRO should direct the crew to GO TO E-3 at this point. The following steps are from E-3.

1. REFER TO EPIP-1, Emergency Plan Classification SRO Flowchart.

2. CHECK if RCPs should remain in service:

a. Phase B DARK [MISSP].

b. RCS pressure greater than 1500 psig.

Critical

3. IDENTIFY Ruptured S/G based on ANY of the following:

Unexpected rise in SIG NR level.

OR BOP

S/G discharge monitor high radiation.

OR RO

RADPROT Survey.

Chemistry sample.

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

NRC Scenario #

2 Event #

7, 8, & 9 Page 26 of 44 Event

Description:

E-O, to E-3 cool down to target temperature Time Position Applicants Actions or Behavior Critical

4. ENSURE Ruptured S/G PORV aligned:

Task

a. ENSURE controller in AUTO set at 90%.

b. ENSURE HS in P-AUTO.

c. WHEN Ruptured S/G pressure less than 1130 psig.

RD THEN BOP

1) ENSURE Ruptured S/G PORV CLOSED, OR

2) OBTAIN RADPROT support and Locally CLOSE Ruptured SIG isolation valve:

RD

5. ENSURE TD AFW pump being supplied from Intact S/G.

BOP Critical RD

6. ENSURE Ruptured S/G blowdown isolated.

Task BOP Critical RD

7. CLOSE Ruptured S/G MSIV and bypass valve.

BOP Critical

8. CONTROL Ruptured SIG level:

Task a.

CHECK Ruptured S/G NR level greater than 29%

[39% ADV].

b. ISOLATE AFW flow to Ruptured S/G.

R

c. ENSURE MEW ISOLATED to Ruptured SIG:

0

MEW isolation valves CLOSED.

MEW bypass isolations CLOSED.

MEW reg and bypass reg valves CLOSED.

MEW pumps TRIPPED.

d. CONTROL Ruptured SIG NR level greater than 29% [39% ADV].

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

NRC Scenario #

2 Event #

7, 8, & 9 Page 27 of 44 Event

Description:

E-O, to E-3 cool down to target temperature Applicants Actions or Behavior Time Position RO

9. PLACE dumpback valve to CST, 1-LIC-2-3, in MANUAL, and CLOSE valve.

BOP RO

10. MAINTAIN condenser level 1-LR-2-12 on-scale [M-3].

BOP RO 1 1. DISPATCH operator to OPEN 1-FCV-14-3 to bypass condensate DI.

12. ENSURE RADPROT dispatched to survey secondary SRO plant.

13. NOTIFY Chemistry to obtain samples as necessary for SRO confirming Ruptured S/G.

14. NOTIFY plant personnel of potential contaminated release.

Critical

15. ENSURE major steam flowpaths from the ruptured S/G Isolated:

a. TD AFW pump steam supply from Ruptured S/G CLOSED BOP

b. Ruptured SIG MSIV and bypass valve CLOSED, OR Intact S/G MSIVs and bypass valves CLOSED.

16. CHECK Ruptured S/G pressure greater than 690 psig.

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

NRC Scenario #

2 Event #

7, 8, & 9 Page 28 of 44 Event

Description:

E-O, to E-3 cool down to target temperature Time Position Applicants Actions or Behavior

17. DETERMINE target incore temp for RCS cooldown:

IF Ruptured S/G pressure is between listed values, THEN USE lower value:

RUPTURED TARGET SIG PRESSURE (PSIG)

INCORE TEMP (°F)

RO 1100 491°F

[471°FADV]

1000 479°F

[459°FADV]

900 466°F

[446°FADV]

800 451°F

[431°FADV]

700 434°F

[414°FADV]

690 433°F

[413°FADV]

18. INITIATE RCS cooldown to target incore temp, determined from Step 17.

a.

DUMP steam to condenser from Intact S/G(s) at maximum achievable rate IF dumps are in Tavg mode, THEN:

1) PLACE steam dump controls OFF.

2) PLACE steam dump mode switch in STEAM PRESSURE.

3) ENSURE steam dump demand indicator 1-XI-1-33 BOP reading zero.

4) PLACE steam dump controls ON.

5) PLACE steam dump controller in MAN, AND FULLY OPEN three cooldown valves (25% demand).

b.

WHEN RCS pressure is less than 1962 psig (P-i 1),

THEN

BLOCK low pzr pressure SI.

BLOCK low steam pressure SI.

c.

WHEN Tavg is less than 550 °F (P-12), THEN BYPASS_Lo-Lo_Tavg_interlock.

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

NRC Scenario #

2 Event #

7, 8, & 9 Page 29 of 44 Event

Description:

E-O, to E-3 cool down to target temperature Applicants Actions or Behavior Time Position

d. WHEN incore temp is less than target temp, THEN STOP RCS cooldown, AND MAINTAIN incore temperature less than or equal to target.

e. CONTINUE with Step 19 of this Instruction.

19. MONITOR Intact S/G levels:

BOP a.

At least one S/G NR level greater than 29%

b.

S/G NR levels less than 50% and controlled.

20. CONTROL Intact SIG NR levels between 29% and 50%.

21. MONITOR pzr PORVs and block RO valves:

a. Pzr PORVs CLOSED.

b. At least one block valve OPEN.

22. CHECK pzr safety valves CLOSED:

EVALUATE tailpipe temperatures and acoustic monitors.

23. RESET SI, and CHECK the following:

SI ACTUATED permissive DARK.

AUTO SI BLOCKED permissive LIT.

24. RESET Phase A and Phase B.

25. ENSURE cntmt air in service:

a. Aux air pressure greater than 75 psig

b. Cntmt air supply valves OPEN [M-15]:

1-FCV-32-80.

1-FCV-32-102.

1-FCV-32-110.

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

NRC Scenario #

2 Event #

7, 8, & 9 Page 30 of 44 Event

Description:

E-0, to E-3 cool down to target temperature Time Position Applicants Actions or Behavior

26. DETERMINE if RHR pumps should be stopped:

a. CHECK RHR suction aligned from RWST.

b. CHECK RCS pressure greater than 150 psig.

c. CHECK RCS pressure stable or rising.

RO Perform RNO:

c. ENSURE CCS aligned to RHR heat exchanger:

1-FCV-70-153 OPEN

1-FCV-70-156 OPEN.

CLOSE SEP heat exchanger A CCS supply 0-FCV-70-197.

GO TO Step 27.

Lead Evaluator NOTE:

When at Target Temperature, Cue console operator to insert_Trigger 6 to implement Steam Leak on_#3 SIG

27. CHECK target incore temperature:

a. VERIFY incore temperature less than target temperature.

RO DO NOT CONTINUE this instruction UNTIL incore BOP temperature less than target temperature.

b. STOP RCS cooldown.

c. MAINTAIN incore temperature less than target temperature.

EVALUATOR NOTE:

The crew should determine either in step 28 or 29 that a_transition_to_ECA-3. 1_is required.

28. MONITOR Ruptured SIG pressure stable or rising.

Perform RNO:

RO MAINTAIN Ruptured S/G at least 250 psig greater than the pressure of the S/G(s) used for cooldown:

Slowly DUMP steam from S/G(s) used for cooldown.

MAINTAIN RCS cooldown rate less than 1000 Fin one hour.

IF the Ruptured S/G depressurizes to less than 250 psig above the pressure of the S/G(s) used for cooldown, THEN GO TO ECA-3. 1, SGTR and LOCA Subcooled Recovery.

Event

Description:

E-O, to E-3 cool down to target temperature Time Position Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

NRC Scenario #

2 Event #

7, 8, & 9 Page 31 of 44 Applicants Actions or Behavior

29. CHECK RCS subcooling greater than 85°F [105°F ADV].

Perform RNO:

RO IF subcooling is less than 65°F[85°FADV], THEN GO TO ECA-3. 1, SGTR and LOCA Subcooled Recovery.

IF subcooling is STABLE OR DROPPING, THEN GO TO ECA-3. 1, SGTR and LOCA Subcooled Recovery.

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

NRC Scenario #

2 Event #

9 Page 32 of 44 Event

Description:

E-O Appendix A Time Position D

Applicants Actions or Behavior Booth Instructor: NONE Indications: None Directs BOP to perform E-O STEP 5:

5. EVALUATE support systems:

REFER TO Appendixes A and B (E-0), Equipment Verification pages 15-28.

Evaluator Note:

The following are E-O Appendix A steps.

Evaluator Note:

The SRO may at times interrupt the BOP, during the performance of Appendixes A and B, to perform other higher priority task.

1. ENSURE PCBs OPEN:

PCB 5044.

PCB 5088.

2 ENSURE AFW pump operation:

Both MD AFW pumps RUNNING.

TD AFW pump RUNNING.

LCVs in AUTO, or controlled in MANUAL.

3. ENSURE MEW isolation:

MEW isolation and bypass isolation valves CLOSED.

MEW reg and bypass reg valves CLOSED.

MFP A and B TRIPPED.

Standby MFP STOPPED.

Cond demin pumps TRIPPED.

Cond booster pumps TRIPPED.

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

NRC Scenario #

2 Event #

9 Page 33 of 44 Event

Description:

E-O Appendix A Time N

Position Applicants Actions or Behavior

4. MONITOR ECCS operation:

a. Charging pumps RUNNING.

b. Charging pump alignment:

RWST outlets 1-LCV-62-135 and 1-LCV-62-136 OPEN.

VCT outlets 1-LCV-62-132 and 1-LCV-62-133 CLOSED.

Charging 1-FCV-62-90 and 1-FCV-62-91 CLOSED.

c. RHR pumps RUNNING.

d. SI pumps RUNNING.

e. BIT alignment:

Outlets 1-FCV-63-25 and 1-FCV-63-26 OPEN.

Flow thru BIT.

f. RCS pressure greater than 1650 psig.

RNO if not >l65Opsig:

f. ENSURE SI pump flow. IF RCS press drops to less than 150 psig, THEN ENSURE RHR pump flow.

Evaluator Note:

The BOP or the RO may have already taken PRUDENT operator action lAW TI-i 204 to perform the next step.

Critical

5. CHECK cntmt isolation:

a. Phase A isolation:

Train A GREEN.

Train B GREEN.

b. Cntmt vent isolation:

Train A GREEN.

Train B GREEN.

Perform RNO:

ACTUATE Phase A and Cntmt Vent Isolation signal.

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

NRC Scenario #

2 Event #

9 Page 34 of 44 Event

Description:

E-O Appendix A Applicants Actions or Behavior Time 1

Position

6. CHECK cntmt pressure:

Phase B DARK {MISSP].

Cntmt Spray DARK [MISSP].

Cntmt press tess than 2.8 psig.

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

NRC Scenario #

2 Event #

9 Page 35 of 44 Event

Description:

E-O Appendix A Applicants Actions or Behavior Time II Position

7. CHECK plant radiation NORMAL:

S/G blowdown rad recorder 1-RR-90-120 NORMAL prior to isolation [M-12j.

Condenser vacuum exhaust rad recorder 1-RR 119 NORMAL prior to trip {M-12].

1-RR-90-106 and 1-RR-90-1 12 radiation recorders BOP NORMAL prior to isolation [M-12].

S/G main steamline discharge monitors NORMAL [M 30].

Upper and Lower containment high range monitors NORMAL [M-30].

NOTIFY Unit Supervisor conditions NORMAL.

8 ENSURE all D/Gs RUNNING.

9. ENSURE ABGTS operation:

a. ABGTS fans RUNNING.

b. ABGTS dampers OPEN:

FCO-30-1 46A.

FCO-30-146B.

FCO-30-157A.

FCO-30-157B.

10. ENSURE at least four ERCW pumps RUNNING, one on BOP each shutdown board preferred.

11. ENSURE ERCW supply valves OPENto running DIGs.

12. ENSURE CCS HX C ALT DISCH TO HDR B, 0-FCV BOP 152, is open to position A.

13. CLOSE CCS HX C DISCH TO HDR A, 0-FCV-67-144.

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

NRC Scenario #

2 Event #

9 Page 36 of 44 Event

Description:

E-O Appendix A Time Position Applicants Actions or Behavior

14. MONITOR EGTS operation:

EGTS fans RUNNING.

ENSURE dampers OPEN VERIFY filter bank dp between 5 and 9 inches of water.

15. ENSURE CCS pumps RUNNING:

lA-A CCS pump.

1B-B CCS pump.

C-S OR 28-B CCS pump.

16. CHECK CNTMT PURGE fans STOPPED:

17. CHECK FUEL HANDLING EXH fans STOPPED, Fuel and BOP Cask loading dampers CLOSED:

18. ENSURE AB GEN SUPPLY and EXH fans STOPPED.

19. ENSURE AB GEN SUP & EXH dampers CLOSED.

20. ENSURE MCR & SPREAD RM FRESH AIR dampers CLOSED:

FCV-31-3.

FCV-31-4.

21.

ENSURE at least one CB EMER CLEANUP fan RUNNING and associated damper OPEN:

CB EMERG CLEANUP FAN A-A, OR Fan B-B BOP RUNNING.

FCO-31-8, OPEN OR FCO-31-7, OPEN.

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

NRC Scenario #

2 Event #

9 Page 37 of 44 Event

Description:

E-O Appendix A Time T Position I Applicants Actions or Behavior

22. ENSURE at least one CB EMER PRESS fan RUNNING and associated damper OPEN:

CB EMERG PRESS FAN A-A, OR FAN B-B RUNNING.

FCO-31-6, OPEN. OR FCO-31-5, OPEN.

23. ENSURE Control Building fans STOPPED and dampers CLOSED:

SPREADING ROOM SUPPLY and EXH FANS AND BOP dampers.

TOILET & LKR RM EXHAUST FAN AND dampers.

24. INITIATE Appendix B.

BOP Evaluator Note:

Only step 1 of E-O Appendix B is listed below

1. CHECK PHASE B actuated BOP WHEN PHASE B actuation occurs; THEN GO TO step 2.

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

NRC Scenario #

2 Event #

10 Page 38 of 44 Event

Description:

ECA-3.1 Applicants Actions or Behavior Time Position Booth Instructor: NONE Indications None Directs the crew to ECA-3. 1, SGTR and LOCA Subcooled SRO Recovery due to ruptured S/G pressure lowering uncontrolled.

Evaluator Note: The crew should recognize ECA-3. 1 Foldout:

EVENT DIAGNOSTIC TRANSITIONS IF any S/G press low or dropping uncontrolled AND SIG has NOT been isolated, unless needed for RCS cooldown, THEN GO TO E-2, Faulted Steam Generator Isolation.

The crew may go to E-2 and perform steps to verify #3 SIG is isolated, or they may continue in ECA-3. 1, since they know that #3 SIG is already isolated IA W E-3.

E-2 Faulted Steam Generator steps start at page 43.

1. PREPARE for switchover to RHR cntmt sump:

a.

RESTORE power to 1-FCV-63-i USING Appendix A RO (ECA-3.i), i-FCV-63-i Breaker Operation.

b.

WHEN RWST level is less than 34%, THEN ** GO TO ES-i.3, Transfer to RHR Containment Sump.

2. RESET SI, and CHECK the following:

SI ACTUATED permissive DARK.

AUTO SI BLOCKED permissive LIT.

Op Test No.:

Appendix D Required Operator Actions Form ES-D-2 NRC Scenario #

2 Event #

10 Page 39 of 44 Event

Description:

ECA-3.1 Applicants Actions or Behavior Time Position

3. RESET Phase A and Phase B.

4. ENSURE cntmt air in service:

a. Aux air press greater than 75 psig

b. Cntmt air supply valves OPEN [M-15]:

1 -FCV-32-80.

1-FCV-32-102.

1-FCV-32-11O.

5. MONITOR electrical board status:

a. CHECK offsite power available.

b. CHECK all shutdown boards ENERGIZED by offsite BOP power.

c. CHECK all unit boards ENERGIZED.

d. PLACE any unloaded D/G in standby USING SOI-82 Diesel Generators.

6. ENSURE pzr heaters off:

PLACE Backup heaters A-A OFF.

PLACE Backup heaters B-B OFF.

PLACE Backup heaters C OFF.

PLACE Control heaters D OFF.

CAUTION If any Ruptured SIG is also faulted, feed flow should remain isolated in subsequent steps UNLESS needed for RCS cooldown.

7. CONTROL Ruptured S/G level:

a. CHECK Ruptured S/G NR level greater than 29%

b. ISOLATE feed flow to Ruptured S/G.

c. CONTROL Ruptured S/G NR level greater than 29%

ADoendix D Reauired Ooerator Actions Form ES-D-2 Op Test No.:

NRC Scenario #

2 Event #

10 Page 40 of 44 Event

Description:

ECA-3.1 Applicants Actions or Behavior Time Position

8. DETERMINE if RHR pumps should be stopped:

a. CHECK RHR suction aligned from RWST.

b. CHECK RCS pressure:

RCS pressure greater than 150 psig.

RCS pressure stable or rising.

c. STOP RHR pumps, and PLACE in A-AUTO.

d. MONITOR RCS pressure greater than 150 psig.

If pressure still lowering:

Perform RNO:

b. IF RCS pressure low or dropping, THEN GO TO Step 9.

9. DETERMINE if cntmt spray should be stopped:

10. NOTIFY Chemistry of event status and plant conditions.

SRO 1 1. NOTIFY Radiological Protection of event status and plant conditions.

Evaluator Note:

Appendix D (ECA-3. 1), Equipment Evaluation is at the end of this section

12. EVALUATE plant equipment status:

REFER TO Appendix D (ECA-3.1), Equipment Evaluation.

13. CHECK SIG pressure:

All S/G pressures controlled or rising.

All S/Gs pressures greater than 120 psig.

RO Perform ANO:

IF steamline AND feed/me isolation has been performed or attempted for the Faulted S/G, THEN ** GO TO Step 14.

Appendix D Required Operator Actions Form ES-D-2 NRC Scenario #

2 Event #

10 Page 41 of 44 Op Test No.:

Event

Description:

ECA-3.1 Time U

Applicants Actions or Behavior Position

14. MAINTAIN Intact SIG NR levels:

a. MONITOR levels greater than 29%

b. CONTROL intact S/G levels between 29% and 50%

15. MONITOR shutdown margin during cooldown:

a. NOTIFY Chemistry to initiate sampling for boron concentration:

Ruptured S/G.

RCS.

b. REFER TO 1-SI-0-10, Shutdown Margin OR REACTINW Computer Program.

c. INITIATE boration as necessary:

REFER TO SOI-62.02, CVCS Boron Concentration Control.

16. INITIATE RCS cooldown to cold shutdown:

a. MAINTAIN T-cold cooldown rate less than 100°F in one hour.

b. IF RHR in service, THEN USE RHR cooling.

c. DUMP steam to condenser from Intact S/Gs.

Evaluator Note:

At the Lead Evaluators discretion, the scenario may be terminated when crew has determined that the plant cooldown should not be initiated until a soak time has occurred to ensure 100 °FIhr will not be violated. Remainder of ECA-3. 1 procedure not included.

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

NRC Scenario #

2 Event #

10 Page 42 of 44 Event

Description:

ECA-3.1 Time Position Applicants Actions or Behavior The following pages are pages from E-2 and at the end is Appendix D (ECA-3. 1),

Equipment Evaluation BOP

1. ENSURE all MSIVs and MSIV bypasses CLOSED.

2. PLACE steam dump controls OFF:

1-HS-1-103A, STEAM DUMP FSVA

1-HS-1-103B, STEAM DUMP FSVB.

3. CHECK for at least one Intact SIG:

Any SIG pressure controlled or rising, BOP OR

Any SIG pressure greater than P-sat for RCS incore temperature.

4. IDENTIFY Faulted S/G based on ANY of the following:

Any SIG pressure dropping in an uncontrolled manner, OR

Any SIG pressure less than 120 psig,

5. ISOLATE Faulted S/G:

a. ISOLATE AFW flow to Faulted SIG.

b. ENSURE MEW ISOLATED to Faulted S/G:

MEW isolation and bypass isolation valves CLOSED.

MEW reg and bypass reg valves CLOSED.

MFPs TRIPPED.

c. ENSURE Faulted S/G PORV CLOSED.

d. ENSURE Faulted SIG blowdown ISOLATED.

6. ENSURE TD AFW pump being supplied from Intact S/G.

7. MONITOR CST volume greater than 200,000 gal.

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

NRC Scenario #

2 Event #

10 Page 43 of 44 Event

Description:

ECA-3.1 Applicants Actions or Behavior Time Position

8. WHEN RCS temperature is stable or rising following Faulted RO S/G blowdown, THEN ADJUST Intact SIG PORV controllers in AUTO to:

BOP This step is N/A

9. CHECK secondary side radiation:

BOP The crew will now go back to E-3, and then go to ECA-3. 1

WBN SGTR AND LOCA - SUBCOOLED RECOVERY ECA-3.1 Rev 11 APPENDIX D (ECA-3.1)

Page 1 of 1 EQUIPMENT EVALUATION 1.

EVALUATE plant equipment and systems needed to support long term cooling and recovery actions, as time and personnel availability permits:

a)

Cntmt Isolation Status.

b) Emergency Gas Treatment System:

One train in operation, REFER TO S0l-65.02.

C)

Auxiliary Building Gas Treatment:

One train in operation, REFER TO SOl-30.06.

d) Auxiliary Building Isolation alignment:

REFER TO S0l-30.06.

e)

Main Control Room Isolation alignment:

REFER TO SOl-31.O1.

if)

ERCW System:

Both trains in operation.

g) Component Cooling Water System:

Both trains in operation.

h) Auxiliary Building Radiation:

1-RR-90-1 O-RR-90-12A O-RM-90-1O1.

SHIFT TURNOVER CHECKLIST Page of LI SM US/MCR Unit LI UO Unit Off-going

- Name LI AUO Station LI STA (STA Function)

On-coming

- Name Part 1

- Completed by off-going shift/Reviewed by on-coming shift:

Cb= 69 ppm Abnormal equipment lineup/conditions:

1A MD AFW Pump OOS for motor bearing replacement. 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months remain in LCO 3.7.5, Action B.

Green risk associated with equipment OOS.

SlJTest in progress/planned: (including need for new brief)

See Schedule Major Activities/Procedures in progress/planned:

100% power, EOL, 69 ppm boron. IA Condensate Booster Pump has a small oil leak. A power reduction to 96% is being discussed by Ops Management in order to remove the pump from service Radiological changes in plant during shift:

None Part 2

- Performed by on-coming shift LI A review of the Operating Log since last held shift or 3 days, whichever is less (N/A for AUOs)

LI A review of the Rounds sheets/Abnormal readings (AUOs only)

Review the following programs for changes since last shift turnover:

LI Standing Orders LI LCO(s) in actions (N/A for AUOs)

LI Immediate required reading LI TACF (N/A for AUOs Part 3

- Performed by both off-going and on-coming shift LI A walkdown of the MCR control boards (N/A for AUOs)

Relief Time:

Relief Date:

TVA 40741 [03-20011 Page 1 of!

OPDP-l-l [03-14-20011

SHIFT TURNOVER CHECKLIST Page of Q

SM LI US/MCR Unit UO Unit Off-going

- Name LI AUO Station El STA (STA Function)

On-coming

- Name Part 1

- Completed by off-going shiftfReviewed by on-coming shift:

Cb= 69 ppm Abnormal equipment lineup/conditions:

1A MD AFW Pump OOS for motor bearing replacement. 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months remain in LCO 3.7.5, Action B.

Green risk associated with equipment 005.

SlJTest in progress/planned: (including need for new briet)

See Schedule Major Activities/Procedures in progress/planned:

100% power, EOL, 69 ppm boron.

1A Condensate Booster Pump has a small oil leak. A power reduction to 96% is being discussed by Ops Management in order to remove the pump from service Radiological changes in plant during shift:

None Part 2

- Performed by on-coming shift Q

A review of the Operating Log since last held shift or 3 days, whichever is less (N/A for AUOs)

El A review of the Rounds sheets/Abnormal readings (AUOs only)

Review the following programs for changes since last shift turnover:

El Standing Orders LI LCO(s) in actions (N/A for AUOs)

El Immediate required reading El TACF (N/A for AUOs Part 3

- Performed by both off-going and on-coming shift LI A walkdown of the MCR control boards (N/A for AUOs)

Relief Time:

Relief Date:

TVA 40741 [03-20011 Page! of!

OPDP-1-1 [03-14-2001]

SHIFT TURNOVER CHECKLIST Page of SM J

USIMCR Unit UO Unit Off-going

- Name Q

AUO Station 0

STA (STA Function)

On-coming

- Name Part 1

- Completed by off-going shift/Reviewed by on-coming shift:

Cb= 69 ppm Abnormal equipment lineup/conditions:

IA MD AFW Pump QOS for motor bearing replacement. 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months remain in LCO 3.7.5, Action B.

Green risk associated with equipment OOS.

SJlTest in progress/planned: (including need for new brief)

See Schedule Major Activities/Procedures in progress/planned:

100% power, EOL, 69 ppm boron. IA Condensate Booster Pump has a small oil leak. A power reduction to 96% is being discussed by Ops Management in order to remove the pump from service Radiological changes in plant during shift:

None Part 2-Performed by on-coming shift Q

A review of the Operating Log since last held shift or 3 days, whichever is less (N/A for AUO5)

Q A review of the Rounds sheets/Abnormal readings (AUOs only)

Review the following programs for changes since last shift turnover:

U Standing Orders U

LCO(s) in actions (N/A for AUO5)

U Immediate required reading U

TACF (N/A for AUOs Part 3

- Performed by both off-going and on-coming shift U

A walkdown of the MCR control boards (N/A for AUO5)

Relief Time:

Relief Date:

TVA 40741 [03-2001]

Page 1 of 1 OPDP-1-1 [03-14-2001]

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

Watts Bar (2008-B)

Scenario No.:

Spare Op Test No.:

1 Examiners:

Operators:

Initial Conditions:

75% power, 1305 ppm boron (BOL). 1A MD AFW Pump is out of service for pump bearing replacement. LCO 3.7.5.b was entered 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ago. Pump is expected to be returned to service in 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months . lB MFP tripped 5 days ago, and power has been maintained at 75% while repairs were completed. The lB MFP was started late during the last shift. Currently, the 1A MFP, lB MFP, and Standby MFP5 are in service.

Turnover:

Shutdown Standby MFP per SOl-2&3.01. Then, perform power escalation using GO-4, Section 5.2 at 3%/hour.

Event Malt No.

Event Event No.

Type*

Description 1

N/A N

- BOP Shutdown Standby MFP.

N

- SAC 2

N/A R

- RO Perform power escalation.

N

- SRO N

- BOP 3

RX2O I

- BOP 1 -PT-i -33 Main Steam Header Pressure transmitter fails low.

I

- so BOP takes manual control of the MFP Master Controller. AOl -16 entry.

4 RXO5 I

- RO 1-LT-68-339 fails high (charging flow and RCP seal injection I

- SRO flows lower). AOI-20 entry. Tech Spec evaluation.

TS-SRO 5

CH01 D TS

- SRO Containment Pressure transmitter PDT-30-45 fails high; Tech Spec evaluation.

6 FWO5B C

- BOP 1 B MFP trips. Standby MFP starts, but trips on overcurrent.

FWO6 C

- SRO BOP runs back the turbine to <800 MWe. AOl -16 entry.

7 RDO9 C

- RO Automatic rod control fails. AC inserts control rods manually to C

- SRO reduce power during the runback. AOl -2 entry.

8 MS06B M

- ALL SG #2 MSIV fails closed. Two safety valves fail open and remain MSO3F open. Reactor trip (manual) or on Overpower/delta T. EOP network entry.

MSO3G 9

RP13 C

- BOP Feedwater isolation signalfails. BOP manually isolates C

- SAC feedwater.

10 CV21 C-AC BIT Outlet Isolation Valve i-FCV-63-25 fails open.

C-SRO (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG 1021 Revision 9

I Appendix D Scenario Outline Form ESD-1 Scenario (Spare) Summary Initial Conditions:

75% power, BOL, 1305 ppm boron.

1 B Main Feedwater Pump tripped 5 days ago, and power has been maintained at 75% while repairs were being completed.

1 B MFP has been restarted and placed in service, minimizing some of the Standby MFP forward flow. The crew is to shutdown Standby MFP per SOl-2&3.01, section 5.11. [41.16]. The crew is then to perform a power escalation using GO-4, Section 5.2 at 2%/hour. 1A MD AFW Pump is out of service for pump bearing replacement. LCC 3.7.5.b was entered 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ago. 1A MD AFW Pump is expected to be returned to service in 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months .

1.

Shutdown Standby MFP using SOI-2&3.01 starting at step 5.11. [41.16].

2.

The crew performs a power escalation using GO-4, Section 5.2 at 2%/hour.

3.

1-PT-1-33 Main Steam Header Pressure transmitter fails low. Affects automatic MFP speed control for Feed Reg Valve AP. MFP speed drops, S/G levels lower. BOP takes MANUAL control of the MFP Master Controller and controls speed and Feed Reg Valve AP lAW AOl -16, Loss of Normal Feedwater.

4.

1-LT-68-339 fails high, causing charging flow and RCP seal injection flows to drop. RO takes 1-FCV-62-93 to MANUAL and raises charging and RCP seal injection flow. AOl-20, Malfunction of PZR Level Control, is entered. SRO evaluates Tech Specs.

5.

Containment Pressure transmitter PDT-30-45 fails high. SAC evaluates Tech Specs.

6.

1 B MFP trips due to low bearing oil pressure. Since the plant load is not >85%, an automatic runback does not occur, requiring the BOP to perform a manual runback. When the Standby MFP automatically starts, it trips on overcurrent. BOP runs back the turbine to <800 MWe. AOl -16, Loss of Normal Feedwater, is entered.

7.

During the plant runback and resulting Tave/Tref mismatch, automatic rod control fails. AC takes MANUAL control of rods to reduce reactor power during the runback. Crew enters AOl -2, Malfunction of Reactor Control System.

8.

SG #2 MSIV fails closed. The resultant pressure transient lifts S/G safety valves. Two safety valves on the same S/G stick open.

If the reactor is not tripped manually, a reactor trip occurs due to Cverpower AT. The steam leak requires the operators to actuate a safety injection. The crew performs E-0, and transitions to E-2. When termination criteria are met, the crew performs ES-i.1.

9.

On the reactor trip, feedwater isolation signal fails. BOP closes valves and stops pumps manually to isolate feedwater.

10. BIT Cutlet Isolation Valve i-FCV-63-25 fails to close from the Main Control Room handswitch. RO must implement ES-i.1 Appendix F, Operation of MOVs at Train B Electrical Board.

11. The scenario terminates when the crew secures both SI Pumps and places them in automatic lAW ES-1.1.

Critical 1

2 Tasks:

Identifies failure of Feedwater Isolation:

Isolates faulted S/G prior to transition from E-2:

Closes MEW isolation valves.

Isolates AFW flow.

Closes #1 EW Heater Outlet Valves.

Closes MEW reg and bypass reg valves.

Trips MEW pumps.

Trips demin pumps and cond booster pumps.

Appendix D NUREG 1021 Revision 9

CONSOLE OPERATOR INSTRUCTIONS SCENARIO (Spare) Faulted Steam Generator Page 1 of 4 NRCO8A Rev 0 EVENT IC/MF/RF/OR #

I DESCRIPTION/FEEDBACK rst 245, switch check, select RUN Sim. Setup 75% RTP, BOL, Cb-1305 ppm.

This IC contains the verify malfunctions and overrides listed overrides and triggers.

below 0

Turns off audible alarm for the simulator fault so the Disable simulator fault alarm crew cannot hear this alarm.

0 Place A Train week 1 placard on On entrance side panel.

entrance side panel.

0 Place DANGER Tag on 1A MDAFW 1A MDAFW out of service.

Hand Switch Indicate/Enter in the appropriate blanks Ensure BOL Reactivity Briefing Book is used. Item this information into the reactivity 3: Delta I -0.3 and AUTO rod control.

0 briefing book, (appendix B TI-7.012)

Item 4: Negative, 1-CCP B, 1308 Item 5: 1305, Boron, BA 16 PW 70, BA Pot 40, PW POT 35 Item 6: PW 33 gal Item 7: PW 35 gal Sim Setup ifIC 245 rst, switch check, select run.

75% RTP, MOL, Cb - 1305 ppm.

does not work.

0 batch OOS AFWP A 1 A MDAFW out of service. Prevents start of pump

and turns breaker lamp off.

0 imf rx2O (el) 0 1-PT-1-33 Main Steam Pressure transmitter fails low 0

imfrx05a (e2) 100 1-LT-68-339 fails high 0

imf chOld (e3) 15 CNTMT Pressure Transmitter PDT-30-45 fails high ior an:ov:11c040 (e4) alarm br an:ov:11c035 (e4) alarm br zaopi4639 (e4) 0 lB MFP trips; STBY MFP starts, but trips imf fwO5b (e4 15) on overcurrent imffw06 imfms06b (e5) 0 0

imfms03f (e5) 100

2 S/G MS1V fails closed. 2 S/G safety valves fail imfmsO3g (e5) 85 open 0

imf rpl3 Failure of FWI 0

imf cv2l (e18 15) 100 BiT Outlet Valve 1 -FCV-63-25 fails open.

0 imf rdO9 Failure of control rods to move in automatic

CONSOLE OPERATOR INSTRUCTIONS Page 2 of 4 NRCO8A Rev 0 SCENARIO (Spare) Faulted Steam Generator I EVENT I IC/MF/RFIOR #

I DESCRIPTION/FEEDBACK I

Event # 1& 2:

Stop the STBY MFP and increase power as determined by NRC Examiner.

Event#3:

When power increase complete as determined by NRC Examiner, Insert this Malfunction using Trigger 1 When actions associated with AOl-16 are complete as determined by NRC Examiner, Insert this Malfunction using Trigger 2 Event#5:

When actions associated with 1-LT-68-339 Transmitter are complete as determined by NRC Examiner, Insert this Malfunction using Trigger 3 Event #4:

none imf rx2O 0 (el) imf rx05a 100 (e2) imfch0ld 15 (e3)

When directed as AUO to close 1-FCV-3-205, wait 10 minutes and report valve is closed. mrf fw2l close.

When directed to reopen 1 -FCV-3-205, wait 5 minutes and report valve open. mrf fw2l open 1-PT-1-33 Main Steam Header Pressure Transmitter fails low.

If notified as work control/maintenance concerning 1-PT-1-33 problems, acknowledge request CNTMT Pressure Transmitter PDT-30-45 fails high If notified as work control/maintenance concerning PDT-30-45 acknowledge request.

If asked if anyone is in Protection Set I Racks, wait 2 minutes then respond NO work is being performed.

Stop the STBY MFP and increase power from 75% to 100%.

1-LT-68-339 fails high causing 1-FCV-62-93 Charging Flow Control Valve to close If notified as work control/maintenance concerning 1-LT-68-339 Level Transmitter failure acknowledge request

Page 3 of 4 NRCO8A Rev 0 CONSOLE OPERATOR INSTRUCTIONS SCENARIO (Spare) Faulted Steam Generator I EVENT I IC/MF/RF/OR #

I DESCRIPTION/FEEDBACK Event#6&7:

br an:ov:11c052 (e4) alarm lB MFP trips. STBY MFP starts but trips on When actions ior an:ov:11c035 (e4) alarm overcurrent. Manual plant runback to less than associated with PDT-ior zaopi4639 (e4) 0 800 MWe.

30-45 are complete as imf fw05b (e4 15) determined by NRC imffw06 (e4)

Examiner, Insert this Malfunction using Trger 4 As AUO, when dispatched, report the MFPT tripped on low oil pressure caused by an oil line break to the pressure switch. Leak has been isolated,oil spill has been wiped up.

As AUO, if asked to to investigate the STBY MFP trip, wait 5 minutes then inform MCR that the STBY MFP tripped on overcurrent.

If notifed as Chemistry of the power change, acknowledge request to sample the RCS.

If notified as work control/maintenance concerning the failure of control rods acknowledge request.

Page 4 of 4 NRCO8A Rev 0 CONSOLE OPERATOR INSTRUCTIONS SCENARIO (Spare) Faulted Steam Generator I EVENT I IC/MF/RF/OR #

I DESCRIPTION/FEEDBACK Events #8 & 9 ms06b 0 (e5)

S/G #2 MSIV fails closed. Manual Reactor trip When actions ms03f 100 (eS) with failure of automatic FWI and two (2) stuck associated with AOl-ms03g 85 (eS) open safeties on SIG #2.

16 & AOI-2 are complete as determined by NRC As AUO, when asked to investigate the owering S/G Examiner, Insert this

2 pressure, wait 5 minutes and report that steam is Malfunction using coming from the North Vault room..

Trigger 5 As Security, when asked to investigate the lowering S/G #2 pressure, wait 5 minutes and report that steam is coming from the North Vault room.

As AUO, when asked to perform AUO actions of AOI-17, Turbine Trip acknowledge request.

10 minutes after the Reactor trip, if the control room has not sent AUOs out to investigate, call the control room as Nuclear Security and inform them that a Security Officer on rounds has reported a lot of noise and steam coming from the North Vault Room.

Event # 10 imf cv2l (e18 15) 100 1-FCV-63-25, BIT Outlet Isolation valve fails to the full open position.

Perform actions to ior:an:

Switch taken to AUX on the lB 1-B Rx MOV Board.

close 1-FCV-63-25 BIT Outlet Isolation mrf cv2l 0 Closes l-FCV-63-25 BIT Outlet Isolation Valve.

Valve

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

Applicants Actions or Behavior Time Position NRC Scenario #

Spare Event #

1 & 2 Page 1

of 36 Event

Description:

Shutdown Standby MFP and Power Escalation Booth Instructor: None Indications available:

None SRO Direct the BOP to shutdown the Standby MFP in accordance with SOl-2&3.01.

Evaluator Note:

Following Step is from SOl-2&3.O1, Condensate and Feedwater System section 5.11.

[41.20J WHEN MFPT has been loaded enough to minimize SMFP forward flow, THEN PERFORM Section BOP 5.12[3j, Standby MFP Shutdown and Standby Alignment.

Evaluator Note:

Following Steps are from SOl-2&3.O1, Condensate and Feedwater System section 5.12.

Standby MFP Shutdown And Standby Alignment 1 IF TDMFP to carry load, PERFORM the following:

1.1 SLOWLY OPEN 1-FCV-3-208, STANDBY MAIN FEEDWATER PUMP MIN FLOW valve using 1-FIC 208 [1-M-3].

1.2 SLOWLY RAISE TDMFP output to minimize SMFP BOP forward flow USING the following controllers, as desired

[N/A option(s) NOT used]:

1-SIC-46-20A, MFPT A-SPEED CONTROL.

1-SIC-46-20B, MFPT B-SPEED CONTROL.

1-PC-46-20, MFPT A & B MASTER SPEED CONTROL.

[2] ENSURE 1-FCV-3-208, STANDBY MAIN FEEDWATER BOP PUMP MIN FLOW is full open when SMFP flow is reduced below 1500 gpm (minimum required flow).

I Appendix D Reciuired Operator Actions Form ES-D-2 NRC Scenario #

Spare Event #

1 & 2 Page 2

of 36 Event

Description:

Shutdown Standby MFP and Power Escalation Time Position I

Applicants Actions or Behavior Op Test No.:

[3] ENSURE 1-PIC-3-40 set at 1200 psia, and 1-PCV-3-40 BOP CLOSED.(May be N/Ad if 1-HS-3-45 is in Normal).

[4]

WHEN MFP(s) have stabilized, THEN

[4.1]

MONITOR MFP(s) picking up additional load,

[4.2] CLOSE SBMFP Discharge Valve 1-FCV-3-205, BOP

[4.3] PLACE 1 -HS-3-200A in STOP/PULL TO LOCK,

[4.4] OPEN SBMFP Discharge Valve 1-FCV-3-205

[4.5] PLACE 1-HS-3-200A in P-AUTO.

[5]

ENSURE 1-FIC-3-208, STANDBY MFWP RECIRC CONTROL, in AUTO at 90% (1500 gpm)[1-M-3], and 1-BOP FCV-3-208 CLOSED [T1J/729].

[6]

RETURN controller used in Step 5.1 2[1.2] to the as found BOP position or as required for current operating conditions.

[7]

IF in LONG CYCLE RECIRC and TDMFPs to remain in service, THEN SET 1-PIC-3-40 as desired (900

- 1200 BOP psia), and ENSURE 1-PCV-3-40 OPEN..

[8] IF SMFP is to be placed in AUTO Standby, THEN 8.1 ENSURE 1-HCV-3-208 is THROTTLED OPEN as required to maintain SMFP warmed and ready for BOP AUTO START.

8.2 ENSURE 1-THV-24-948, STANDBY MFW PMP OIL CLR RCW OUTLET THROTTLE, is THROTTLED as necessary to maintain lube oil temperature greater than 75°F.

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

NRC Scenario #

Spare Event #

1 & 2 Page 3

of 36 Event

Description:

Shutdown Standby MFP and Power Escalation Time Position Applicants Actions or Behavior

[9]

STOP one of the SMFP AUX OIL PUMPS using the following handswitches and then return to AUTO. (N/A switch NOT used)

BOP A.

1-HS-3-.210, STANDBY MAIN FEEDWATER PUMP AUX OIL PUMP A. [T1J/729]

B. 1-HS-3-211, STANDBY MAIN FEEDWATER PUMP AUX OIL PUMP B. [T1J/729]

Raise load in accordance with Reactivity Briefing book and SRO GO-4 Normal Power Operations, Section 5.2 starting at step 23 and skipping to step 40.

Evaluator Note: Following Steps are from SOI-62.02 Boron Concentration Control, Section 6.6 starting with step 2 (Dilution)

[2] ADJUST 1-FQ-62-142, PW BATCH COUNTER, for RO required quantity.

[3] PLACE 1-HS-62-140B, VCT MAKEUP MODE in DIL.

[4] TURN 1-HS-62-140A, VCTMAKEUP CONTROL, to RO START.

[4.1) CHECK_Red_light_is_LIT.

[53 MONITOR the following parameters:

Instrument Location Parameters 1-PI-62-122 1-M-6 VCT PRESS 1-Ll62-129A 1-M-6 VCT LEVEL RO 1-FI-62-142 1-M-6 PW TO BLENDER FLOW 1-FQ-62-142 1-M-6 PW BATCH COUNTER 1-FQ-62-139 1-M-6 BA BATCH COUNTER

[6] WHEN dilution is COMPLETE, AND 1-FCV-62-128 is RO closed, THEN PLACE 1-HS-62-140B, VCT MAKEUP MODE, in AUTO.

[ Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

NRC Scenario #

Spare Event #

1 & 2 Page 4

of 36 Event

Description:

Shutdown Standby MFP and Power Escalation Applicants Actions or Behavior Time Position

[7] TURN 1-HS-62-140A, VCT MAKEUP CONTROL, to RO START.

[7.1] CHECK_Red_light_is_LIT.

Evaluator Note: Following Steps are from GO-4, Normal Power Operation, Section 5.2 Step 23 and then skipping to step 40 thru 41.

Direct the crew to increase reactor power to 100%.

SRO RCS should be maintaining Tavg/Tref when Turbine load is RO raised. Control rods will be used along with dilution to maintain I and, temperature.

Evaluator Note: Following GO-4 step will be repeated as the crew bumps the turbine load up.

[23] CONTINUE ascension to 90% power by performing the following:

[23.1]

IF during any of the following steps the REFERENCE changes in an undesired manner, THEN ADJUST VPL to stop turbine load rise.

OR PUSH TURBINE MANUAL to place the turbine control mode in manual mode and PROCEED to section 5.6

[23.2]

ADJUST VALVE POSITION LIMIT to 90% or to 5% above the Gov Control Indication.

[23.3]

SET LOAD RATE at predetermined value.

[23.4]

PUSH REFERENCE CONTROL t\\ (raise) button to set desired load in SETTER display.

[23.5]

PUSH GO button.

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

NRC Scenario #

Spare Event #

1 & 2 Page 5

of 36 Event

Description:

Shutdown Standby MFP and Power Escalation Applicants Actions or Behavior Time Position

[23.6]

MONITOR Generator Megawatts RISING.

[23.7]

CHECK that load rise has STOPPED when reference display equals setter OR BOP IF desired to stop the load change THEN STOP the load change by DEPRESSING the HOLD pushbutton.

[23.8]

WHEN desired to resume the load change, THEN PRESS the GO push button and continue to monitor load.

[40) BEFORE raising above 80% power, THEN ENSURE the following:

[40.1] 1 -LCV 1 06A controlling properly.

[40.2) 1-LCV-6-105A and 105B are NOT open.

When a power increase has been initiated or at the Lead Examiners discretion, proceed to the next event.

[41] WHEN power is at or above 95%, THEN PERFORM the following

[41.1)

ADJUST PR NIS per 1-SI-92-1, NIS Daily Comparison.

[41.2] IF evaluation of Hot Channel Factors is required, THEN ENSURE 1Sl-0-20, COMPLETE.

[41.3) NOTIFY MIG to perform 1-SI68-30 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after power stabilizes at 90% or above (N/A if NOT applicable).

[41.4) ENSURE the following level controllers maintaining levels within normal ranges:

A. Feedwater heaters.

B. MSR drain tanks BOP

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

Event

Description:

1-PT-i -33, Main Steam Pressure Transmitter, fails low NRC Scenario #

1 Event #

3 Page 6

of 36 Applicants Actions or Behavior Time Position Booth Instructor:

Insert Event 3 - Trigger 1 Indications available:

Alarm 63E SIG Level Deviation.

All S/G Levels lowering.

Feedwater flow lowering.

lOS alarm FW Pump Suction Pressure Hi.

BOP Respond to annunciators and recognize i-PT-i-33 failure.

Informs crew.

SRO Direct crew actions lAW AOl.i6 LOSS OF NORMAL FEEDWATER.

Determines that MFPT speed control is NOT normal and takes Prudent Operator Action lAW Tl-i2.04 to place MEW pump BOP master controller in Manual, and raise MFP speed.

Evaluator Note: Following Steps are from IAWAOI-16 LOSS OF NORMAL FEEDWATER, section 3.7.

CHECK MFWPT speed controller(s) NORMAL.

Performs RNO:

CONTROL MFP speed using MANUAL control of master BOP controller or individual controller(s) as required.

IF MANUAL control of individual MFWPT controller is ineffective, THEN TRIP affected MFWPT, and GO TO Section 3.4 or 3.5 as applicable.

RO Place control rods in MANUAL.

RO CHECK MEW pumps recirc valves NORMAL.

RO Ensures T-avg and T-ref within 3°.

Appendix D Required Operator Actions Form ES-D-NRC Scenario #

1 Event #

3 Page 7

of 36 Event

Description:

1-PT-i -33, Main Steam Pressure Transmitter, fails low Time U

Applicants Actions or Behavior Position Op Test No.:

Adjusts pump speed to maintain MFW pump discharge BOP pressure normal.

Restore SG levels to program.

BOP Checks steam dump mode in T-AVG position.

SRO Notify Work Control to have instrument repaired.

May direct/request control rods be returned to Auto.

SRO/RO ENSURE Tavg and Tref within 10 PLACE control rods to auto.

When the plant has been stabilized or at the Lead Examiners discretion, proceed to the next event.

Appendix D Required Operator Actions Form ES-D-2 NRC Scenario #

1 Event #

4 Page 8

of 36 Event

Description:

1 -LT-68-339 fails high Time Applicants Actions or Behavior Position Op Test No.:

Booth Instructor:

When directed, initiate Event 4 (Trigger 2)

Indications available:

Alarm 92B PZR LEVEL HI DEVIATION.

Alarm 1O1E RCP SEAL SUPPLY FLOW LO.

Alarm 1 08A CHARGING FLOW HI/LO.

Alarm 124A PZR LEVEL HI/LO.

Crew Diagnose a failure of the controlling PZR Level channel HIGH.

May take PRUDENT Operator action lAW TI-12.04 to take RO manual control of 1-FCV-62-93 to raise charging flow to normal.

Direct crew actions lAW AOI-20 MALFUNCTION OF SRO PRESSURIZER LEVEL CONTROL SYSTEM.

Evaluator Note: Following Steps are from AOI-20 MALFUNCTION OF PRESSURIZER LEVEL CONTROL SYSTEM.

1. CHECK pzr level program signal NORMAL:

LR-68-339

2. CHECK if 1-XS-68-339E is selected to FAILED channel,(control or backup):

LI-68-339, RO Ll-68-320, LI-68-335.

3. CHECK failure HIGH.

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

Op Test No.:

NRC Scenario #

1 Event #

4 Page 9

of 36 Event

Description:

1 -LT-68-339 fails high Time Position Applicants Actions or Behavior

4. IF controlling channel failed,THEN PLACE charging valve RO controller 1-HIC-62-93A in MAN, and RESTORE level to program.

5. SELECT operable pzr level channels for control and indication [1-M-5]:

RO a.

SELECT operable channels for control and backup with 1 -XS-68-339E.

b.

ENSURE operable channel selected recording with 1 XS-68-339B.

Evaluator Note: If the crew elected to isolate letdown to control regenerative heat exchanger temperature then Step 6 RNO MUST BE IMPLEMENTED, AND ATTACHMENT 1 STEPS performed to restore charging and letdown to normal.

AOl-20 Attachment 1 begins on Page 26.

6. CHECK letdown IN SERVICE:

FCV-62-69 OPEN.

FCV-62-70 OPEN.

FCV-62-77 OPEN.

RO Letdown orifice OPEN.

If Letdown Isolated:

ESTABLISH letdown REFER TO Attachment 1.

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

NRC Scenario #

1 Event #

4 Page 10 of 36 Event

Description:

1 -LT-68-339 fails high Time Position Applicants Actions or Behavior

7. RESTORE pzr level control to normal:

a.

MAINTAIN regen hx letdown temp

< 380 °F.

b.

CONTROL charging and letdown to return pzr level to program.

c.

ENSURE pzr control heater bank D red light LIT.

RD d.

Momentarily PLACE 1-HS-68-341H, pzr backup heater bank C, to OFF.

e.

CHECK pzr program level NORMAL. 1-LR-68-339 (green pen) f.

RETURN charging valve controller 1-HIC-62-93A to AUTO.

8. NOTIFY Work Control to remove failed channel from SRO service.

9. REFER TO the following Tech Specs:

3.3.1, Reactor Trip System (RTS) Instrumentation.

3.3.3, Post Accident Monitoring.

SRO Refer to Tech Specs and enters:

LCO 3.3.1, Table 3.3. 1-1, item 9 condition X.

LCO 3.3.3, Table 3.3.3-1, item 14, condition F.

(Action A)

10. INITIATE repairs to failed instrument/circuitry.

When Tech Specs have been addressed or at the Lead Examiners discretion, proceed to the next event.

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

NRC Scenario #

1 Event #

5 Page 11 of 36 Event

Description:

PDT-30-45, Containment Pressure Transmitter, fails high Time Position Applicants Actions or Behavior Booth Instructor:

Insert Event 5 - Trigger 3 Indications available:

Alarm 125A Cntmt Hi-Hi-Press Steamline Isolation.

Containment Pressure Indicator 1-PDT-30-45 fails High.

Alarm 83D Plant Computer Generated Alarm

- High Containment Pressure Input.

SRO Refers to Technical Specification 3.3.2, Action E for required actions ACTIONS coot inued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One Containment E.1 NOTE Pressure channel One additional inoperable, channel nay be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing.

Place channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months bypass.

OR E.2.1 Na in NODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND E.2.2 Ne in MODE 4.

iS hours SRO Notify Work Control to initiate repairs.

When the SRO has referred to Tech Specs or at the Lead Examiners discretion, proceed to the next event.

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

Op Test No.:

NRC Scenario #

1 Event#

6&7 Page 12 of 36 Event

Description:

1 B MFP Trip & STBY MFP trip on overcurrent Time Position Applicants Actions or Behavior Booth Instructor:

When directed, initiate Event (Trigger 4)

Indications available:

Alarm 50B MFPT 1 B Abnormal.

Alarm 51A Tripped.

Alarm 52A Bearing Oil Press Lo.

White Breaker Disagreement light on STBY MFP.

Feed Flow lowering.

Lube Oil Pressure (1 -P1-46-39) reading 0.

Should diagnose a loss of the 1 B MFP and the SRO should go Crew toAOll6.

Evaluator Note: The following are steps in A01-16 starting in section 3.5 step 2.

2. CHECK turbine load less than or equal to 1000 MWe (85%).

BOP BOP

3. PLACE tripped MFP recirc valve controller in MANUAL, and CLOSE recirc valve.

Evaluator Note:

The BOP should recognize that the Standby MFWP has tripped.

4. CHECK turbine load less than 800 MWe (67%),

Perform RNO:

ENSURE Standby MFWP running.

BOP IF Standby MFWP NOT available, THEN REDUCE turbine load to less than 800 MWe with valve position limiter.

5. ENSURE MFWP speed rising to control S/G AP and levels on program.

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

NRC Scenario #

1 Event #

6 & 7 Page 13 of 36 Event

Description:

1 B MFP Trip & STBY MFP trip on overcurrent Applicants Actions or Behavior Time Position

6. ENSURE adequate feed flow for existing conditions:

BOP Feed flow greater than or equal to steam flow.

SIG levels returning to program.

Note: To prevent Rods from excessive insertion, the SRO may direct a Minor Boration in an amount as described in the Reactivity Briefing Book, lAW 62.02 Boron Concentration Control section 6.7.

7. ENSURE T-avg and T-ref within 30 RO recognizes that automatic rod insertion is not occurring.

RO RNO:

INSERT control rods to match reactor power with turbine load.

8. REFER TO Tech Specs:

3.2.3 AFD.

SRO Crew should also be prompted to review this Tech Spec from ARI-83 D PLANT COMPUTER GENERATED ALARM, if it is in alarm.

9. IF feed flow greater than 40%, THEN ENSURE tripped BOP MFWP turbine condenser valves CLOSED:

Pump B, 1 -FCV-2-206 and -211 BOP

10. MONITOR reg valves controlling SIG levels on program.

11. IF 0-7 LOSS OF LOAD STM DUMP INTERLOCK annunciator LIT [66E], THEN BOP

a. ENSURE steam dump valves have zero demand.

b. RESET loss-of-load interlock with steam dump mode switch.

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

NRC Scenario #

1 Event #

6 & 7 Page 14 of 36 Event

Description:

1 B MFP Trip & STBY MFP trip on overcurrent Applicants Actions or Behavior Time II Position

12. ENSURE Condensate System Pumps in service as

necessary:

SRO REFER TO GO-4, Normal Power Operation.

No Action necessary

13. IF reactor power dropped by greater than or equal to 15%

in one hour, THEN NOTIFY Chemistry to initiate power change SRO sampling requirements.

14. CHECK VALVE POS LIMIT LIT.

15. REDUCE turbine load setpoint using REFERENCE BOP CONTROL V (lower) AND GO button until VALVE POS LIMIT LIGHT not LIT, THEN SET valve position limiter to 95%.

SRO 16, INITIATE repairs on failed pumps.

17. RETURN TO Instruction in effect.

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

NRC Scenario #

1 Event #

6 & 7 Page 15 of 36 Event

Description:

1 B MFP Trip & STBY MFP trip on overcurrent Time Position Applicants Actions or Behavior Evaluator Note: The following are steps in ARI-87-B ROD INSERTION LIMIT LO-LO (The following actions are dependent upon how far control rods are manually inserted.)

[1] IF low-low rod insertion limit has been exceeded, THEN

[a] STOP all dilutions of RCS.

[b] SELECT manual rod control, and RESTORE Tavg to RO Tref, if necessary.

[C] INITIATE SDM determination.

[d] RESTORE rods to within limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

[e] GO TO AOI-34, IMMEDIATE BORATION.

Evaluator Note: The following are steps in AOI-34 IMMEDIATE BORATION, starting in section 3.2 step 1. Crew should reference Reactivity Briefing book to estimate amount of boric acid to add.

1. INITIATE normal boration to change CB as necessary:

a. PLACE BA flow controller, 1-FC-62-139, to desired flow rate.

b. ADJUST BA batch counter 1-FQ-62-139 to ensure RD boration continues.

c. PLACE mode selector 1-HS-62-140B to BOR.

d. PLACE VCT makeup control 1-HS-62-140A, to START.

e. VERIFY boric acid flow indicated on 1-Fl-62-139.

RD

2. ENSURE PW to blender isol 1-FCV-62-143, CLOSED.

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

NRC Scenario #

1 Event #

6 & 7 Page 16 of 36 Event

Description:

1 B MFP Trip & STBY MFP trip on overcurrent Time Position Applicants Actions or Behavior RO

3. CHECK PW to blender flow 1-Fl-62-142, indicating ZERO.

4. MONITOR for negative reactivity Insertion:

Neutron flux dropping.

RO TAVG dropping.

Control rod bank position rising (if in AUTO).

If Rods have been placed in Manual, RO shall withdraw control rods as necessary to maintain Tavg/Tref.

When the plant is stable or when determined by the NRC, Lead Examiner may cue the next event

Op Test No.:

Appendix D Required Operator Actions Form ES-D-2 NRC Scenario #

1 Event #

8

, 9 & 10 Page 17 of 36 Event

Description:

2 MSIV fails closed, E-0 entry with failure of FWI, transition to E-2, transition to ES-i.1 with 1 -FCV-63-25 BIT Outlet Isolation Valve failure to close.

Applicants Actions or Behavior Time Position Booth Instructor:

When directed by Lead Examiner, insert Trigger 5 Indications No. 2 MSIV fails closed, 2 SG safety valves open and fail to close.

Reactor Tripped.

Directs RO perform E-O.

SRO Evaluator Note:

The following are steps from E-O.

NOTE 1 Steps 1 thru 4 are IMMEDIATE ACTION STEPS.

NOTE 2 Status Trees / SPDS should be monitored when transitioned to another instruction.

1. ENSURE reactor trip:

Reactor trip and bypass breakers OPEN.

RPls at bottom of scale.

Neutron flux DROPPING.

2. ENSURE Turbine Trip:

All turbine stop valves CLOSED.

3. CHECK 6.9 kV shutdown boards:

a. At least one board energized from:CSST (offsite), OR D/G (blackout).

4. CHECK SI actuated:

a. Any SI annunciator LIT.

b. Both trains SI ACTUATED.

1 -XX-55-6C

1 -XX-55-6D

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

NRC Scenano#

1 Event#

8,9&1O Page 18 of 36 Event

Description:

2 MSIV fails closed, E-O entry with failure of FWI, transition to E-2, transition to ES-i.1 with 1 -FCV-63-25 BIT Outlet Isolation Valve failure to close.

Time I

Position Applicants Actions or Behavior BOP Evaluator Note:

Appendix A (E-O), SI Support Systems, and Appendix B, Phase B Pipe Break Contingencies are contained at the end of this document. Appendix A contains the steps that are required for Critical Task #1. Appendix A (E-O) starts on Page 28.

5. EVALUATE support systems:

REFER TO Appendixes A and B (E-0), Equipment Verification pages 15-28.

6. ANNOUNCE reactor trip and safety injection over PA BOP system.

7. ENSURE secondary heat sink available with either:

Total AFW flow greater than 410 gpm, OR

At least one S/G NR level greater than 29%

8. MONITOR RCS temp stable at or trending to 557° F:

IF any RCP running, THEN MONITOR RCS Loop T-avg trending to 557°F.

Perform RNO:

IF temp less than 557°F, THEN ENSURE steam dumps and SIG PORVs CLOSED.

RO IF cooldown continues, THEN:

PLACE steam dump controls OFF.

CONTROL total AFW flow to maintain greater than 410 gpm UNTIL NR level in at least one S/G greater than 29%

IF cooldown continues after AFW flow is controlled, THEN

CLOSE MSIVs.

ENSURE MSIV bypasses CLOSED.

Op Test No.:

Appendix D Required Operator Actions Form ES-D-2 NRC Scenario #

1 Event #

8

, 9 & 10 Page 19 of 36 Event

Description:

2 MSIV fails closed, E-0 entry with failure of FWI, transition to E-2, transition to ES-i.1 with 1 -FCV-63-25 BIT Outlet Isolation Valve failure to close.

Applicants Actions or Behavior Time N

Position

9. ENSURE excess letdown valves CLOSED:

1 -FCV-62-54

1 -FCV-62-55

10. CHECK pzr PORVs and block valves:

a. Pzr PORVs CLOSED.

b. At least one block valve OPEN.

1 1. CHECK pzr safety valves CLOSED:

EVALUATE tailpipe temperatures and acoustic monitors.

12. CHECK pzr sprays CLOSED.

13. CHECK if RCPs should remain in service:

a. Phase B signals DARK [MISSP].

b. RCS pressure greater than 1500 psig.

14. CHECK SIG pressures:

All SIG pressures controlled or rising.

All SIG pressures greater than 120 psig.

RO Perform RNO:

IF SIG pressure low OR dropping uncontrolled, THEN **

GO TO E-2, Faulted Steam Generator Isolation.

Evaluator Note:

SRO should direct the crew to GO TO E-2 at this point. The following steps are from E-2.

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

NRC Scenario #

1 Event #

8

, 9 & 10 Page 20 of 36 Event

Description:

2 MSIV fails closed, E-0 entry with failure of FWI, transition to E-2, transition to ES-i.1 with 1 -FCV-63-25 BIT Outlet Isolation Valve failure to close.

Time Position Applicants Actions or Behavior BOP ENSURE all MSIVs and MSIV bypasses CLOSED.

PLACE steam dump controls OFF:

BOP 1-HS-1-103A, STEAM DUMP FSV A.

1-HS-1-103B, STEAM DUMP FSV B.

CHECK for at least one Intact SIG:

Any S/G pressure controlled or rising, BOP OR Any S/G pressure greater than P-sat for RCS incore temperature Evaluator Note: the crew should identify #2 SIG as the faulted SIG.

IDENTIFY Faulted S/G based on ANY of the following:

Any SIG pressure dropping in an uncontrolled manner, OR Any S/G pressure less than 120 psig, OR BOP S/G enclosure temps high:

1)

TlOO2Afor2and3, 2)

TlOO3Aforl and 4.

OR Local indication of break in any of the following:

1)

Main steam lines, 2)

Main feedwater lines, 3)

Other secondary piping.

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

NRC Scenario #

1 Event #

8

, 9 & 10 Page 21 of 36 Event

Description:

2 MSIV fails closed, E-0 entry with failure of FWI, transition to E-2, transition to ES-i.1 with 1-FCV-63-25 BIT Outlet Isolation Valve failure to close.

Time Position F Applicants Actions or Behavior Evaluator Note: The feedwater isolation failure is addressed by the BOP during the performance of E-O, Appendix A, Step 3. RNO actions to close the #1 Feedwater Heater Isolation valves and to dispatch an AUO to manually close the MFW bypass isolation valves should have been completed.

CRITICAL ISOLATE Faulted S/G:

a.

ISOLATE AFW flow to Faulted S/G.

b.

ENSURE MFW ISOLATED to Faulted SIG:

MFW isolation valves CLOSED.

MFW bypass isolations CLOSED.

MEW reg and bypass reg valves CLOSED.

BOP Perform RNO:

Manually CLOSE valves as necessary.

Actions should have been completed during Appendix A performance.

MFW pumps TRIPPED.

c.

ENSURE Faulted S/G PORV CLOSED.

b.

ENSURE Faulted SIG blowdown ISOLATED.

BOP ENSURE TD AFW pump being supplied from Intact S/G.

BOP MONITOR CST volume greater than 200,000 gal.

NRC Scenario #

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

1 Event #

8

, 9 & 10 Page 22 of 36 Event

Description:

2 MSIV fails closed, E-0 entry with failure of FWI, transition to E-2, transition to ES-i.1 with i-FCV-63-25 BIT Outlet Isolation Valve failure to close.

Time L

Applicants Actions or Behavior Position WHEN RCS temperature is stable or rising following Faulted SIG blowdown, THEN BOP ADJUST Intact S/G PORV controllers in AUTO to P-sat for the hottest RCS temp.

CHECK secondary side radiation:

S/G discharge monitors NORMAL.

BOP Condenser vacuum exhaust rad monitors NORMAL.

SIG blowdown rad monitor recorders NORMAL trend prior to isolation.

S/G sample results by Chemistry.

MONITOR SI termination criteria:

a.

MONITOR RCS subcooling greater than 65°F ADV.

b.

MONITOR secondary heat sink available with either:

Total feed flow to Intact S/Gs greater than 410 gpm, RO OR At least one Intact S/G NR level greater than 29% ADV.

c.

MONITOR RCS pressure stable or rising.

d.

MONITOR pzr level greater than 15% ADV.

C.

GOTO ES-1.1,SI Termination.

NRC Scenario #

1 Event #

8

, 9 & 10 Page 23 of 36 Event

Description:

2 MSIV fails closed, E-0 entry with failure of FWI, transition to E-2, transition to ES-i.1 with i-FCV-63-25 BIT Outlet Isolation Valve failure to close.

Applicants Actions or Behavior Op Test No.:

Appendix D Required Operator Actions Form ES-D-2 Time Position Evaluator Note:

SRO should direct the crew to GO TO ES-i.1 at this point.

The following steps are from ES-i.1.

RESET SI, and CHECK the following:

RD SI ACTUATED permissive DARK.

AUTO SI BLOCKED permissive LIT.

RD RESET Phase A and Phase B.

ENSURE cntmt air in service:

a.

Aux air press greater than 75 psig [M-15].

BOP b.

Cntmt air supply valves OPEN [M-15]:

1-FCV-32-80.

1-FCV-32-102.

1-FCV-32-11O.

ENSURE ONLY one Charging Pump running:

RD

STOP all but one CCP and PLACE in A-AUTO.

CHECK RCS press stable or rising.

RD

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

NRC Scenario #

1 Event #

8

, 9 & 10 Page 24 of 36 Event

Description:

2 MSIV fails closed, E-0 entry with failure of FWI, transition to E-2, transition to ES-i.1 with 1 -FCV-63-25 BIT Outlet Isolation Valve failure to close.

Time Position Applicants Actions or Behavior ALIGN charging:

a.

CLOSE RCP seal flow control 1-FCV-62-89.

b.

OPEN charging isolation valves 1-FCV-62-90 and 1-FCV-62-91.

RO c.

ENSURE charging valve 1 -FCV-62-85 OR 1 -FCV-62-86 OPEN.

d. CHECK RHR Suction aligned from RWST.

e.

OPEN seal return valves 1 -FCV-62-61 and 1 -FCV-62-63.

Evaluator Note:

1-FCV-63-25 fails to close from the MCR. Steps required to close 1-FCV-63-25 are contained in ES-1.1 Appendix F, OPERATION OF MOVs AT TRAIN B ELECTRICAL BOARD.

Appendix F (ES-1.1) starts at Page 35.

CLOSE BIT outlet valves 1-FCV-63-25 and 1-FCV-63-26.

Perform RNO:

RO CLOSE BIT outlet valve(s) at RX MOV BD using Appendix E and/or F for failed train.

Dispatches AUO to the 1 Bi -B Rx MOV board, Compt 11 E.

ADJUST 1-FCV-62-89 and 1-FCV-62-93 to maintain:

Seal injection flow between 8 and 13 gpm for each RO RCP.

Pzr level stable or rising.

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

NRC Scenario #

1 Event #

8

, 9 & 10 Page 25 of 36 Event

Description:

2 MSIV fails closed, E-0 entry with failure of FWI, transition to E-2, transition to ES-i.1 with 1 -FCV-63-25 BIT Outlet Isolation Valve failure to close.

Position Applicants Actions or Behavior Time II CONTROL charging flow to maintain pzr level:

a.

IF any SIG Faulted, TH EN RO DO NOT CONTINUE this Instruction UNTIL Faulted S/G depressurization stops.

b.

CHECK pzr level stable or rising.

DETERMINE if SI pumps should be stopped:

a.

CHECK RCS pressure:

Stable or rising.

Greater than 1350 psig.

RO b.

CHECK RHR Suction aligned from RWST.

c.

CHECK RCS pressure:

Stable or rising.

Greater than 1650 psig.

11. STOP SI pumps, AND PLACE in A-AUTO.

RO Evaluator Note: Scenario may be terminated when crew has stopped and placed both SI Pumps in P-Auto, or at the discretion of the Lead Evaluator. Remainder of ES-i.1 procedure not included.

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

NRC Scenario #

1 Event #

8 & 9 Page 26 of 36 Event

Description:

AOl-20, Attachment 1 Restoring Charging and Letdown Applicants Actions or Behavior Time Position Booth Instructor: NONE Indications THE FOLLOWING STEPS ARE ASSOCIATED WITH AOI-20 ATTACHMENT 1 RESTORING CHARGING AND LETDOWN.

1. IF charging NOT established, THEN PERFORM the following:

a. CLOSE 1.-FCV-62-89, CHRG HDR-RCP SEALS FLOW CONTROL.

b. ENSURE Charging Pump running.

c. OPEN 1-FCV-62-90 and 1-FCV-62-91, CHARGING LINE ISOL.

d. ENSURE 1-FCV62-85, NORM CHARGING TO LOOP 1, or 1-FCV-62-86, ALT CHARGING TO LOOP 4, OPEN.

e. ADJUST 1-FCV-62-93 to maintain seal injection flow between 8 and 13 gpm for each RCP.

2. ENSURE letdown isol valves OPEN:

1-FCV-62-69, CVCS LETDOWN ISOLATION.

RO 1-FCV-62-70, CVCS LETDOWN ISOLATION.

1-FCV-62-77, CVCS LP LETDOWN ISOLATION.

R

3. PLACE 1-HIC-62.78A, LETDOWN HX OUTLET TEMP TCV-70-192 CNTL, in MANUAL at 25% OPEN.

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

NRC Scenario #

1 Event #

8 & 9 Page 27 of 36 Event

Description:

AOl-20, Attachment 1 Restoring Charging and Letdown Applicants Actions or Behavior Time I

Position

4. PLACE 1-HIC-62-81A, LETDOWN PRESS CONTROL, in RO MANUAL at 40-50% OPEN if using 75 gpm orifice (20-30%

OPEN if using 45 gpm orifice).

5. ESTABLISH 75 gpm or greater charging flow while RO maintaining seal injection flow between 8 and 13 gpm for each RCP.

Evaluator Note:

Candidate will place either 1-FCV-62-73 or -74 in service.

6. OPEN letdown orifices as needed:

1-FCV-62-72 (45 gpm).

RO 1-FCV-62-73 (75 gpm).

1-FCV-62-74 (75 gpm).

1-FCV-62-76 (5 gpm).

7. ADJUST 1-HIC-62-81A, LETDOWN PRESS CONTROL, for RO desired press, (320 psig at normal letdown temp), and PLACE in AUTO.

8. PLACE 1-HIC-62-78A, LETDOWN HX OUTLET TEMP TCV-70-192 CNTL, in AUTO.

9. RETURN pzr level to program.

10. RETURN 1-HIC-62-93A, CHARGING FLOW PZR LEVEL RO CONTROL, in AUTO.

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

NRC Scenario #

1 Event #

Page 28 of 36 Event

Description:

E-O Appendix A Time Position T Applicants Actions or Behavior Booth Instructor: NONE Indications THE FOLLOWING STEPS ARE ASSOCIATED WITH E-0 Appendix A Directs BOP to perform E-0 STEP 5:

SRD

5. EVALUATE support systems:

REFER TO Appendixes A and B (E-0), Equipment Verification pages 1 5-28.

Evaluator Note:

The following are E-0 Appendix A steps.

Evaluator Note:

The SRO may at times interrupt the BOP, during the performance of Appendixes A and B, to perform other higher priority task.

1. ENSURE PCBs OPEN:

PCB 5044.

PCB 5088.

2 ENSURE AFW pump operation:

Both MD AFW pumps RUNNING.

TD AFW pump RUNNING.

LCVs in AUTO, or controlled in MANUAL.

Evaluator Note:

The BOP or the RO may have already taken PRUDENT operator action lAW TI-i 204 to perform the next step.

If the Operator may either close the manual isolation for the MFW isolation (and Bypass isolation valves

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

NRC Scenario #

1 Event #

Page 29 of 36 Event

Description:

E-O Appendix A Time Position Applicants Actions or Behavior

3. ENSURE MFW isolation:

MFW isolation and bypass isolation valves CLOSED.

PERFORM RNO:

Manually CLOSE:

1-HS-3-33A (SIG #1 MFWISOL VLV)

BOP l-HS-3-47A (SIG #2 MFWISOL VLV 1-HS-3-87A (SIG #3 MFW ISOL VL V 1-HS-3-100A (SIG #4 MFWISOL VLV)

Manually CLOSE:

1-HS-3-1OA (Al Heater Outlet) l-HS-3-1OA (81 Heater Outlet) l-HS-3-1OA (Cl Heater Outlet)

Critical Task #1

MEW reg and bypass reg valves CLOSED.

PERFORM RNO:

Take the controllers to MANUAL and CLOSE for the MFW Reg Valves and MFW Bypass Reg valves, and verify valve positions on l-XX-3-35 and l-XX-3-35A 1-FIC 3-35 1-FIC 3-48 1-FIC 3-90 l-FIC 3-103 1-LIC 3-35A 1-LIC 3-48A 1-LIC 3-90A 1-LIC 3-103A

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

NRC Scenario #

1 Event #

Page 30 of 36 Event

Description:

E-0 Appendix A Time Position Applicants Actions or Behavior

MFP A and B TRIPPED.

BOP PERFORM RNO:

TRIP 1A MFP MANUALLY.

Task #1 BOP

Standby MFP STOPPED.

Critical Task #1

Cond demin pumps TRIPPED.

BOP PERFORM RNO:

TRIP COND Demin Pumps MANUALLY Critical Task #1

Cond booster pumps TRIPPED.

PERFORM RNO:

BOP TRIP Condensate Booster Pumps MANUALLY.

4. MONITOR ECCS operation:

a. Charging pumps RUNNING.

b. Charging pump alignment:

RWST outlets 1-LCV-62-135 and 1-LCV-62136 OPEN.

VCT outlets 1-LCV-62-132 and 1-LCV-62-133 BOP CLOSED.

Charging 1-FCV-62-90 and 1-FCV-62-91 CLOSED.

c. RHR pumps RUNNING.

d. SI pumps RUNNING.

Op Test No.:

Appendix D Required Operator Actions Form ES-D-2 NRC Scenario #

1 Event #

Page 31 of 36 Event

Description:

E-O Appendix A Applicants Actions or Behavior Time Position

e. BIT alignment:

Outlets 1-FCV-63-25 and 1-FCV-63-26 OPEN.

Flow thru BIT.

f. RCS pressure greater than 1650 psig.

RNO if not >l65Opsig:

f. ENSURE SI pump flow. IF RCS press drops to less than 150 psig, THEN ENSURE RHR pump flow.

5 CHECK cntmt isolation:

a. Phase A isolation:

Train A GREEN.

Train B GREEN.

b. Cntmt vent isolation:

Train A GREEN.

Train B GREEN.

6. CHECK cntmt pressure:

Phase B DARK [MISSP].

Cntmt Spray DARK [MISSP].

Cntmt press less than 2.8 psig.

Op Test No.:

NRC Scenario #

Appendix D Required Operator Actions Form ES-D2 1

Event #

Page 32 of 36 Event

Description:

E-O Appendix A Position Applicants Actions or Behavior Time

7. CHECK plant radiation NORMAL:

SIG blowdown rad recorder 1-RR-90-120 NORMAL prior to isolation [M-12].

Condenser vacuum exhaust rad recorder 1-RR.90-119 NORMAL prior to trip [M-12].

1-RR-90-106 and 1-RR-90-112 radiation recorders NORMAL prior to isolation [M-12].

S/G main steamline discharge monitors NORMAL [M 30].

Upper and Lower containment high range monitors NORMAL [M-30].

NOTIFY Unit Supervisor conditions NORMAL.

BOP 8 ENSURE all DIGs RUNNING BOP

9. ENSURE ABGTS operation:

a. ABGTS fans RUNNING.

b. ABGTS dampers OPEN:

FCO-30-146A.

FCO-30-146B.

FCO-30-157A.

FCO-30-157B.

10. ENSURE at least four ERCW pumps RUNNING, one on each shutdown board preferred.

11. ENSURE ERCW supply valves OPEN to running DIGs.

12. ENSURE CCS HX C ALT DISCH TO HDR B, 0-FCV 152, is open to position A.

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

NRC Scenario #

1 Event #

Page 33 of 36 Event

Description:

E-O Appendix A Time Position Applicants Actions or Behavior BOP

13. CLOSE CCS HX C DISCH TO HDR A, 0-FCV-67-144.

14. MONITOR EGTS operation:

EGTS fans RUNNING.

ENSURE dampers OPEN VERIFY filter bank dp between 5 and 9 inches of water.

15. ENSURE CCS pumps RUNNING:

lA-A CCS pump.

lB-B CCS pump.

C-S OR 2B-B CCS pump.

16. CHECK CNTMT PURGE fans STOPPED:

17. CHECK FUEL HANDLING EXH fans STOPPED, Fuel and Cask loading dampers CLOSED:

18. ENSURE AB GEN SUPPLY and EXH fans STOPPED.

19. ENSURE AB GEN SUP & EXH dampers CLOSED.

20. ENSURE MCR & SPREAD RM FRESH AIR dampers CLOSED:

FCV-31-3.

FCV-31-4.

21.

ENSURE at least one CB EMER CLEANUP fan RUNNING and associated damper OPEN:

CB EMERG CLEANUP FAN A-A, OR Fan B-B RUNNING.

FCO-31-8, OPEN OR FCO-31-7, OPEN.

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

NRC Scenario #

1 Event #

Page 34 of 36 Event

Description:

E-O Appendix A Time Position Applicants Actions or Behavior

22. ENSURE at least one CB EMER PRESS fan RUNNING and associated damper OPEN:

CB EMERG PRESS FAN A-A, OR FAN B-B RUNNING.

FCO-31-6, OPEN. OR FCO-31-5, OPEN.

23. ENSURE Control Building fans STOPPED and dampers CLOSED:

SPREADING ROOM SUPPLY and EXH FANS AND dampers.

TOILET & LKR RM EXHAUST FAN AND dampers.