Text

Initial Exam 2008-301 Final Simulator Scenarios
	ML101970321
Person / Time
Site:	Robinson
Issue date:	06/28/2010
From:	; NRC/RGN-II
To:	; Progress Energy Carolinas
References
	50-261/08-301 50-261/08-301
	Download: ML101970321 (92)
	v • d • e

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

HB ROBINSON Scenario No.:

1 Op Test No.:

Examiners:

Operators:

SRO RO BOP Initial Conditions:

68% EOL, 17,000 MWD/MTU, 106 ppm Boron.

SW Booster Pump A is Out-Of-Service for Motor Coupling Alignment.

o LCO 3.7.7-A has been entered and is in hour 18 of a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action statement.

o Expected return is within 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

Main Turbine Vibration for #2, 3 and 4 bearings is elevated.

Turnover:

Returning to RTP following a short Maintenance Outage. Awaiting results of post-outage testing. Maintain power at current level.

Critical Task:

Manually restart SW pump to provide cooling to only running EDG before damaging the EDG.

Isolate feedwater to the faulted S/Gs using Foldout A OR Supplement G prior to transitioning to PATH-i, Entry Point C.

Event MaIf.

Event Type*

Event No.

No.

Description 1

(C) BOP, SRO HVH-9A/B AIR FLOW LOST alarm.

2 (TS) SRO PR N-42 Upper Detector Fails Low.

3 (I) BOP, SRO Feed Flow Channel FT-477 Fails High.

(TS) SRO 4

(R) RO Plant down power resulting from loss of Condensate Pump which (N) SRO, BOP trips Main Feed Pump.

5 (I) RO, SRO PT-444, Controlling PZR Pressure channel fails High.

6 (C) RO, SRO RCP C #2 Seal fails, requiring a Reactor Trip.

7 (M) ALL Steam Break from S/Gs B and C on the Reactor Trip.

8 (C) BOP EDG A fails to start on the Safety Injection.

9 (M) ALL Loss of Off-Site power. (Loss of SUT) 10 (C) BOP SW Pumps fail to start following restoration of power.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-i 021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 Facility:

HB ROBINSON Scenario No.:

1 Op Test No.:

Examiners:

Operators:

SRO -

RO -

BOP-Initial Conditions:

68% EOL, 17,000 MWD/MTU, 106 ppm Boron.

SW Booster Pump "A" is Out-Of-Service for Motor Coupling Alignment.

0 LCO 3.7.7 -A has been entered and is in hour 18 of a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action statement.

0 Expected return is within -18 hours.

Main Turbine Vibration for #2, 3 and 4 bearings is elevated.

Turnover:

Returning to RTP following a short Maintenance Outage. Awaiting results of post-outage testing. Maintain power at current level.

Critical Task:

Manually restart SW pump to provide cooling to only running EDG before damaging the EDG.

Isolate feedwater to the faulted S/Gs using Foldout A OR Supplement G prior to transitioning to PATH-1, Entry Point C.

Event Malf.

Event Type*

Event No.

No.

Description 1

(C) BOP, SRO HVH-9A/B AIR FLOW LOST alarm.

2 (TS) SRO PR N-42 Upper Detector Fails Low.

3 (I) BOP, SRO Feed Flow Channel FT-477 Fails High.

(TS) SRO 4

(R) RO Plant down power resulting from loss of Condensate Pump which (N) SRO, BOP trips Main Feed Pump.

5 (I) RO, SRO PT-444, Controlling PZR Pressure channel fails High.

6 (C) RO, SRO RCP "C" #2 Seal fails, requiring a Reactor Trip.

7 (M) ALL Steam Break from S/Gs "B" and "C" on the Reactor Trip.

8 (C) BOP EDG "A" fails to start on the Safety Injection.

9 (M) ALL Loss of Off-Site power. (Loss of SUT) 10 (C) BOP SW Pumps fail to start following restoration of power.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 1

SUMMARY

DESCRIPTION The crew will assume the watch with the plant at 68% RTP. The previous shift identified increased vibration on Main Turbine bearing #3 and has taken all necessary actions to inform station management. Service Water Booster Pump A is under clearance for Motor Coupling Alignment. Shift instructions are to maintain power at current level.

On cue from the Chief Examiner, APP-010-A7, HVH-9NB AIR FLOW LOST/OVLD alarm will illuminate. The BOP will reference APP-01 0-A7 and stop Concrete Shield Cooling Fan HVH-9A and start HVH-9B.

On cue from the Chief Examiner, PR N-42 Upper Detector will fail low. The RO should identify that it is an instrument failure, NOT a dropped rod and respond lAW APP-005-A3. The crew will NOT remove the instrument from service, but the SRO will enter LCO 3.3.1 Conditions D, E, S and T for the failed instrument.

After ITS has been addressed for the N-42 detector failure, the Chief Examiner can cue the FT 477, S/G A Feed Flow instrument failure. The BOP should respond by taking Manual control of SIG A FRV and controlling SIG level within normal parameters. An alternate instrument will be placed in service and the FRV will be returned to automatic control. The crew should respond lAW AOP-025, RTGB INSTRUMENT FAILURE and remove the instrument from service. The SRO should enter LCO 3.3.1, Condition E for the failed instrument.

On cue from the Chief Examiner, Condensate Pump A will trip causing Feedwater Pump A to trip. This will result in an entry into AOP-O10, MAIN FEEDWATER I CONDENSATE MALFUNCTION. The crew should reduce Turbine load to less than 50% RTP lAW Attachment 1 of AOP-010.

When the Chief Examiner is satisfied with the power reduction, he can cue the PT-444, PZR Pressure controlling channel failure. PZR PORV PCV-455C and PZR Spray valves will open causing pressure to decrease. The RO will manually close PCV-455C and take manual control of PZR pressure and return it to the normal control band. If pressure decreases below 2205 PSIG, the crew will enter LCO 3.4.1, Condition A for the Low Pressure condition.

On cue from the Chief Examiner, the RCP C #2 seal leak will begin. The crew should respond using AOP-01 8, REACTOR COOLANT PUMP ABNORMAL CONDITIONS, calculating a high seal leakoff and determine a plant shutdown lAW GP-006, NORMAL PLANT SHUTDOWN FROM POWER OPERATION TO HOT SHUTDOWN is required. At that time seal leakage will degrade to the point where the SRO will direct a Reactor Trip.

PATH-i will be entered and on the Reactor Trip a Steam Break will develop in SIGs B and C.

After the Safety Injection has been reset and SIGs B and C have been isolated, the Chief Examiner can cue the Loss of Off-Site power. The Start-Up Transformer will be lost and EDG B will load to the bus. Auxiliary Feedwater and Component Cooling Water loads will be restored.

The crew should respond lAW PATH-i and restart safeguards equipment (SI pump, RHR pump, HVH units and SW pumps) manually.

The Chief Examiner may terminate the scenario at any time after the SIGs have been isolated and Service Water cooling to the EDG has been restored.

Appendix D NUREG-102i, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 1

SUMMARY

DESCRIPTION The crew will assume the watch with the plant at 68% RTP. The previous shift identified increased vibration on Main Turbine bearing #3 and has taken all necessary actions to inform station management. Service Water Booster Pump "A" is under clearance for Motor Coupling Alignment. Shift instructions are to maintain power at current level.

On cue from the Chief Examiner, APP-01 0-A7, HVH-9A/B AIR FLOW LOST/OVLD alarm will illuminate. The BOP will reference APP-01 0-A7 and stop Concrete Shield Cooling Fan HVH-9A and start HVH-9B.

On cue from the Chief Examiner, PR N-42 Upper Detector will fail low. The RO should identify that it is an instrument failure, NOT a dropped rod and respond lAW APP-005-A3. The crew will NOT remove the instrument from service, but the SRO will enter LCO 3.3.1 Conditions D, E, S and T for the failed instrument.

After ITS has been addressed for the N-42 detector failure, the Chief Examiner can cue the FT-477, S/G "A" Feed Flow instrument failure. The BOP should respond by taking Manual control of S/G "A" FRV and controlling S/G level within normal parameters. An alternate instrument will be placed in service and the FRV will be returned to automatic control. The crew should respond lAW AOP-025, RTGB INSTRUMENT FAILURE and remove the instrument from service. The SRO should enter LCO 3.3.1, Condition E for the failed instrument.

On cue from the Chief Examiner, Condensate Pump "A" will trip causing Feedwater Pump "A" to trip. This will result in an entry into AOP-010, MAIN FEEDWATER / CONDENSATE MALFUNCTION. The crew should reduce Turbine load to less than 50% RTP lAW Attachment 1 of AOP-010.

When the Chief Examiner is satisfied with the power reduction, he can cue the PT-444, PZR Pressure controlling channel failure. PZR PORV PCV-455C and PZR Spray valves will open causing pressure to decrease. The RO will manually close PCV-455C and take manual control of PZR pressure and return it to the normal control band. If pressure decreases below 2205 PSIG, the crew will enter LCO 3.4.1, Condition A for the Low Pressure condition.

On cue from the Chief Examiner, the RCP "C" #2 seal leak will begin. The crew should respond using AOP-018, REACTOR COOLANT PUMP ABNORMAL CONDITIONS, calculating a high sealleakoff and determine a plant shutdown lAW GP-006, NORMAL PLANT SHUTDOWN FROM POWER OPERATION TO HOT SHUTDOWN is required. At that time seal leakage will degrade to the point where the SRO will direct a Reactor Trip.

PATH-1 will be entered and on the Reactor Trip a Steam Break will develop in S/Gs "B" and "C".

After the Safety Injection has been reset and S/Gs "B" and "C" have been isolated, the Chief Examiner can cue the Loss of Off-Site power. The Start-Up Transformer will be lost and EDG "B" will load to the bus. Auxiliary Feedwater and Component Cooling Water loads will be restored.

The crew should respond lAW PATH-1 and restart safeguards equipment (SI pump, RHR pump, HVH units and SW pumps) manually.

The Chief Examiner may terminate the scenario at any time after the S/Gs have been isolated and Service Water cooling to the EDG has been restored.

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 1 SIMULATOR SETUP IC/SETUP IC-601, SON: 006_Sim_1.

SW Booster Pump A is OFF, breaker OPEN and switch is RED CAPPED.

Main Turbine Bearing #2 is OFFSET by 1.5, #3 by 2.3 and #4 by 1.7.

Status board updated to reflect 10-17.

PRE-LOADED EVENTS:

The following events should occur on the reactor trip:

Event 7: Steam Break from S/Gs B and C on the Reactor Trip.

Event 8: EDG A fails to start on the Safety Injection.

Event 10: SW Pumps fail to start on restoration following LOOP.

EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:

Event 1: HVH-9NB AIR FLOW LOST alarm.

Event 2: PR N-42 Upper Detector fails low.

Event 3: Feed Flow channel FT-477 fails high.

Event 4: Plant down power from Condensate Pump A and Feedwater Pump A trip.

Event 5: PT-444, Controlling PZR pressure channel fails High.

Event 6: RCP C #2 Seal fails, requiring a Reactor Trip.

Event 9: Loss of Off-Site Power. (Loss of SUT)

EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

AOP-025, Section E; OWP-026, FWF-2; AOP-01 0; AOP-025, Section C; AOP-01 8; PATH-i; Foldouts A & B; EPP-i 1; EPP-7; Supplement G.

Appendix D NUREG-i 021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 1 SIMULATOR SETUP IC/SETUP IC-601, SCN: 006_Sim_1.

SW Booster Pump "A" is OFF, breaker OPEN and switch is RED CAPPED.

Main Turbine Bearing #2 is OFFSET by 1.5, #3 by 2.3 and #4 by 1.7.

Status board updated to reflect IC-17.

PRE-LOADED EVENTS:

The following events should occur on the reactor trip:

Event 7: Steam Break from S/Gs "B" and "c" on the Reactor Trip.

Event 8: EDG "A" fails to start on the Safety Injection.

Event 10: SW Pumps fail to start on restoration following LOOP.

EVENTSITRIGGERS INITIATED DURING THE SCENARIO:

Event 1: HVH-9A/B AIR FLOW LOST alarm.

Event 2: PR N-42 Upper Detector fails low.

Event 3: Feed Flow channel FT-477 fails high.

Event 4: Plant down power from Condensate Pump "A" and Feedwater Pump "A" trip.

Event 5: PT-444, Controlling PZR pressure channel fails High.

Event 6: RCP "c" #2 Seal fails, requiring a Reactor Trip.

Event 9: Loss of Off-Site Power. (Loss of SUT)

EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

AOP-025, Section E; OWP-026, FWF-2; AOP-010; AOP-025, Section C; AOP-018; PATH-1; Foldouts A & B; EPP-11; EPP-7; Supplement G.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

1 Page 4

of 29 Event

Description:

HVH-9AIB AIR FLOW LOST alarm.

Time Position Applicants Actions or Behavior BOP Recognizes APP-O10-A7 alarm and references actions.

BOP IF the operating fan has NOT tripped, THEN perform the following:

Stop the running fan.

Start the standby fan.

Verify APP-01 0-A7 clears.

BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 1, HVH-9NB AIR FLOW LOST alarm.

EVENT INDICATIONS:

APP-O1O-A7; HVH-9AIB AIR FLOW LOST/OVLD Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

--..;.....- Scenario #

1 Event #

Page 4

of 29

~--------

~~----~I Event

Description:

HVH-9A/B AIR FLOW LOST alarm.

Time II Position

~

Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 1, HVH-9A1B AIR FLOW LOST alarm.

EVENT INDICATIONS:

APP-010-A7; HVH-9A1B AIR FLOW LOST/OVLD BOP Recognizes APP-010-A? alarm and references actions.

BOP IF the operating fan has NOT tripped, THEN perform the following:

Stop the running fan.

Start the standby fan.

Verify APP-01 O-A? clears.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

2 Page 5

of 29 Event

Description:

PR N-42 Upper Detector fails Low.

Time II Position Applicants Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 2, PR N-42 Upper Detector fails low.

EVENT INDICATIONS:

APP-003-B6; Overpower T APP-003-C6; Overtemp tT APP-005-A3; PR Dropped Rod APP-005-C3; PR Channel Dcv APP-005-D5; OThT/OPT Turbine Runback Rod Stop APP-005-F3; PR Upper Ch Hi Flux Dev I Auto Defeat APP-005-D6; t Flux Warning I Status (later)

N-42 t Flux meter (Nl-42C) pegged LOW Upper Detector (A) on N-42 Drawer indicates low On NR-45 and NR-47 Recorders, N-42 reads lower than other Power Range NIs RO Recognizes that N-42 has failed and there is NO dropped rod.

References APPs to determine actions or recommendations.

SRO Reviews, briefs and directs taking N-42 instrument out of service using OWP-011, NI-2.

Reviews ITS for applicable LCOs Table 3.3.1-1, #2 Condition D; Place channel in Trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Table 3.3.1 -1, #5 and 6

- Condition E: Place channel in Trip SRO within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Table 3.3.1-1, #17c

- Condition T; Verify interlock is in required state within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Table 3.3.1-1, Item #17d

- Condition S: Verify interlock is in required state within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

NOTE:

As soon as the Chief Examiner is satisfied with the SRO referencing ITS, the next event can be inserted.

The OWP does NOT need to be implemented in order to continue with the scenario.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

--.;.....- Scenario #

Event #

2 Page 5

of 29

~---------

~~------~I Event

Description:

PR N-42 Upper Detector fails Low.

Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 2, PR N-42 Upper Detector fails low.

EVENT INDICATIONS:

APP-003-86; Overpower LlT APP-003-C6; Overtemp LlT APP-005-A3; PR Dropped Rod APP-005-C3; PR Channel Dev APP-005-D5; OTLlT/OPLlT Turbine Runback Rod Stop APP-005-F3; PR Upper Ch Hi Flux Dev I Auto Defeat APP-005-D6; Ll Flux Warning I Status (later)

N-42 Ll Flux meter (NI-42C) pegged LOW Upper Detector (A) on N-42 Drawer indicates low On NR-45 and NR-47 Recorders, N-42 reads lower than other Power Range Nls RO Recognizes that N-42 has failed and there is NO dropped rod.

References APPs to determine actions or recommendations.

SRO Reviews, briefs and directs taking N-42 instrument out of service using OWP-011, NI-2.

Reviews ITS for applicable LCOs Table 3.3.1-1, #2 - Condition D; Place channel in Trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Table 3.3.1-1, #5 and 6 - Condition E: Place channel in Trip SRO within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Table 3.3.1-1, #17c - Condition T; Verify interlock is in required state within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Table 3.3.1-1, Item #17d - Condition S: Verify interlock is in required state within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

NOTE:

As soon as the Chief Examiner is satisfied with the SRO referencing ITS, the next event can be inserted.

The OWP does NOT need to be implemented in order to continue with the scenario.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

3 Page 6

of 29 Event

Description:

Feed Flow channel FT-477 fails high.

Time Position Applicants Actions or Behavior BOOTH OPERATOR:

At the discretion of the Chief Examiner, insert Event 3, Feed Flow channel FT-477 fails high.

EVENT INDICATIONS:

APP-006-A1; SIG A FW > STM FLOW (Clears on Lamp Acknowledge)

APP-006-A2; SIG A STM> FW FLOW APP-006-A3; SIG A LVL DEV APP-006-D1: SIG A NAR RANGE LO/LO-LO LEVEL FR-478 Green Pen goes high and FCV-478 closes BOP Recognizes FT-477 has failed and performs Immediate Actions for AOP-025, RTGB INSTRUMENT FAILURE.

SRO Enters AOP-025, RTGB INSTRUMENT FAILURE, Section E.

Immediate Action Step:

BOP Place the affected FRV (FCV-478 for S/G A) in MAN.

Immediate Action Step:

BOP Restore Affected S/G Level To Between 39% And 52%.

RO/BOP Make PA announcement for entry into AOP-025.

BOP Place the affected SIG Feed Flow Selector Switch to the alternate channel. (CH-476, FR478 recorder pen will return to normal status)

Continuous Action Step:

Restore Affected Controller To Automatic:

BOP Check S/G level within +/- 1 % of programmed level. (If YES, place in Auto and Go To Step 6)

WHEN S/G level is within +/- 1 % of programmed level, THEN place the affected Controller in AUTO.

Appendix D NUREG.1O21, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

.-;....- Scenario #

1 Event #

_3;;..-. ____ Page 6

of

.....:2~9 ___

-I1 Event

Description:

Feed Flow channel FT-477 fails high.

Position A

licant's Actions or Behavior BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 3, Feed Flow channel FT-477 fails high.

EVENT INDICATIONS:

APP-006-A1; S/G A FW > STM FLOW (Clears on lamp Acknowledge)

APP-006-A2; S/G A STM > FW FLOW APP-006-A3; S/G A lVl DEV APP-006-D1: S/G A NAR RANGE lO/lO-lO lEVEL FR-478 Green Pen goes high and FCV-478 closes BOP Recognizes FT-477 has failed and performs Immediate Actions for AOP-025, RTGB INSTRUMENT FAILURE.

SRO Enters AOP-025, RTGB INSTRUMENT FAILURE, Section E.

BOP Immediate Action Step:

Place the affected FRV (FCV-478 for S/G "A") in MAN.

BOP Immediate Action Step:

Restore Affected S/G Level To Between 39% And 52%.

ROIBOP Make PA announcement for entry into AOP-025.

BOP Place the affected S/G Feed Flow Selector Switch to the alternate channel. (CH-476, FR-478 recorder pen will return to normal status)

Continuous Action Step:

Restore Affected Controller To Automatic:

BOP

Check S/G level within +/- 1 % of programmed level. (If YES, place in Auto and Go To Step 6)

WHEN S/G level is within +/- 1 % of programmed level, THEN place the affected Controller in AUTO.

Appendix D NUREG-1021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

3 Page 7

of 29 Event

Description:

Feed Flow channel FT-477 fails high.

Time II Position Applicants Actions or Behavior SRO BOP Reviews, briefs and directs taking FT-477 instrument out of service using OWP-026, FWF-2.

OWP-026, FWF-2 actions Precautions:

Ensure FR-478 Feed Flow Selector switch on the RTGB is selected to FT-476 prior to flow transmitter isolation.

Refer to ITS Table 3.3.1-1 Item 14 for Feedwater flow OPERABILITY and applicability requirements.

With Reactor Trip Breakers closed, ensure A S/G level channels LT-474 AND LT-475 are in service.

Maintain S/G A level above Lo Level setpoint.

Remove the affected transmitter from service using OWP-026, FWF-2.

FR-478 selector switch selected to CH-476.

Delete input FT-477 from CALO processing. (FWFO4O4A)

(May be removed by using the DR Delete/Restore function of ERFIS)

(APP-036-L1 will be received when Hagan Rack door is opened)

Trip bistable FC-478B-1, STM-FW FLO DEV.

(APP-006-A2 and B/S STATUS LIGHT SG NO 1 STM-FW FLO DEV FC-478B1 will be received)

SRO Return to procedure and step in effect.

SRO SRO SRO Go To Procedure (AOP-025) Main Body, Step 2.

Implement the EALs.

Review LCO 3.3.1-1, #14 Condition E

- Trip bistable within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

......;...- Scenario #

1 Event #

3 Page 7

of 29

~--------

~------~I Event

Description:

Feed Flow channel FT-477 fails high.

Time II Position

~

Applicant's Actions or Behavior SRO Reviews, briefs and directs taking FT-477 instrument out of service using OWP-026, FWF-2.

OWP-026, FWF-2 actions Precautions:

Ensure FR-478 Feed Flow Selector switch on the RTGB is selected to FT-476 prior to flow transmitter isolation.

Refer to ITS Table 3.3.1-1 Item 14 for Feedwater flow OPERABILITY and applicability requirements.

With Reactor Trip Breakers closed, ensure "A" S/G level channels LT-474 AND LT-475 are in service.

Maintain S/G "A" level above Lo Level setpoint.

BOP Remove the affected transmitter from service using OWP-026, FWF-2.

FR-478 selector switch selected to CH-476.

Delete input FT-477 from CALO processing. (FWF0404A)

(May be removed by using the "DR" Delete/Restore function of ERFIS)

(APP-036-L 1 will be received when Hagan Rack door is opened)

Trip bistable FC-478B-1, STM-FW FLO DEV.

(APP-006-A2 and B/S STATUS LIGHT SG NO 1 STM-FW FLO DEV FC-478B1 will be received)

SRO Go To Procedure (AOP-025) Main Body, Step 2.

SRO Implement the EALs.

SRO Review LCO 3.3.1-1, #14 Condition E - Trip bistable within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SRO Return to procedure and step in effect.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

4 Page 8

of 29 Event

Description:

Plant down power from Condensate Pump A trip which tripped Feedwater Pump A.

Time Position Applicants Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 4, Condensate Pump A trips which results in the tripping of MFP A.

EVENT INDICATIONS:

APP-007-A1; COND PMP A MOTOR OVLD)TRIP (Extinguishes on Lamp acknowledge)

APP-006-A3; SIG A LVL DEV, APP-006-B3; SIG B LVL DEV, APP-006-C3; S!G C LVL DEV (later)

Condensate Pump A and Main Feedwater Pump A breaker open.

Recognizes loss of Condensate/Feed Pump and performs immediate BOP actions of AOP-0i0, MAIN FEEDWATER/CONDENSATE MALFUNCTION.

Immediate Action Step:

BOP Check Feedwater Regulating Valves Operating Properly in Manual OR Auto. (YES)

Continuous Action Step:

SRO Check Reactor Trip Setpoint Being Approached. (NO)

IF a Reactor Trip Setpoint is approached, THEN trip the Reactor and Go To PATH-i. (Go To Step 4)

RO Make PA Announcement for Procedure Entry into AOP-Oi 0.

SRO Go to appropriate step: Condensate AND Feed Pump Trip, Step 10.

RO Check Reactor Power less than 70%. (YES)

RO Check Reactor Power greater than 50%. (YES)

BOP Reduce Turbine load at i%/MIN to 5%/MIN to achieve less than 50%

Reactor Power using Attachment i.

Appendix D NUREG-102i, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

......;.-.- Scenario #

Event #

_4~ ____ Page 8

of _2_9;.....-__

.....,1 Event

Description:

Plant down power from Condensate Pump "An trip which tripped Feedwater Pump "An.

Time Position Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 4, Condensate Pump "A" trips which results in the tripping of MFP "A".

EVENT INDICATIONS:

APP-007-A1; COND PMP A MOTOR OVLDrrRIP (Extinguishes on Lamp acknowledge)

APP-006-A3; S/G A LVL DEV, APP-006-B3; S/G B LVL DEV, APP-006-C3; S/G C LVL DEV (later)

Condensate Pump "A" and Main Feedwater Pump "A" breaker open.

Recognizes loss of Condensate/Feed Pump and performs immediate BOP actions of AOP-010, MAIN FEEDWATER/CONDENSATE MALFUNCTION.

Immediate Action Step:

BOP Check Feedwater Regulating Valves Operating Properly in Manual OR Auto. (YES)

Continuous Action Step:

SRO Check Reactor Trip Setpoint Being Approached. (NO)

IF a Reactor Trip Setpoint is approached, THEN trip the Reactor and Go To PATH-1..(Go To Step 4)

RO Make PA Announcement for Procedure Entry into AOP-01 O.

SRO Go to appropriate step: Condensate AND Feed Pump Trip, Step 10.

RO Check Reactor Power less than 70%. (YES)

RO Check Reactor Power greater than 50%. (YES)

BOP Reduce Turbine load at 1 %/MIN to 5%/MIN to achieve less than 50%

Reactor Power using Attachment 1.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

4 Page 9

of 29 Event

Description:

Plant down power from Condensate Pump A trip which tripped Feedwater Pump A.

Time Position Aoolicants Actions or Behavior BOP Turbine Load Reduction

Check Turbine Control Mode in automatic. (YES)

. Depress the IMP IN Pushbutton.

Set the desired load in the SETTER.

. Set desired load rate.

. Depress the GO Pushbutton.

NOTE:

OP-301, Section 8.2.8 Quick Boration Checklist (shaded area) is included in the following steps, but may be used following the commencement of the plant down power.

The crew should add 100 gallons of Boric Acid for the 18%

downpower. (The crew will add Boric Acid in 2-4 batches)

RD DETERMINE the amount of Boric Acid to add to the RCS and OBTAIN an independent check of the volume required.

RD OBTAIN permission from the CRSS OR the SSO to borate.

RD PLACE the RCS MAKEUP MODE selector switch to BORATE.

RD SET YIC-1 13, BORIC ACID TOTALIZER to desired quantity.

RD IF desired, THEN PLACE FCV-1 13A, BORIC ACID FLOW, in MAN AND_ADJUST_using_the_UP_and_DOWN_pushbuttons RD Momentarily PLACE the RCS MAKEUP SYSTEM switch to START.

IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:

RD Rod Motion is blocked OR is in the wrong direction TAVG increases Boric Acid addition exceeds the desired value Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: --

Scenario #

1 Event #

4 Page 9

of 29

~--------

~------~I Event

Description:

Plant down power from Condensate Pump "An trip which tripped Feedwater Pump "An.

Position A

licant's Actions or Behavior - Turbine Load Reduction

Check Turbine Control Mode in automatic. (YES)

BOP

Depress the IMP IN Pushbutton.

Set the desired load in the SETTER.

Set desired load rate.

Depress the GO Pushbutton.

NOTE:

OP-301, Section 8.2.8 Quick Boration Checklist (shaded area) is included in the following steps, but may be used following the commencement of the plant down power.

The crew should add - 100 gallons of Boric Acid for the 18%

down power. (The crew will add Boric Acid in 2-4 batches)

RO DETERMINE the amount of Boric Acid to add to the RCS and OBTAIN an independent check of the volume required.

RO OBTAIN permission from the CRSS OR the SSO to borate.

RO PLACE the RCS MAKEUP MODE selector switch to BORATE.

RO SET YIC-113, BORIC ACID TOTALIZER to desired quantity.

RO IF desired, THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN AND ADJUST using the UP and DOWN pushbuttons.

RO Momentarily PLACE the RCS MAKEUP SYSTEM switch to START.

IF any of the below conditions occur, THEN momentarily place the ReS MAKEUP SYSTEM switch in the STOP position:

RO Rod Motion is blocked OR is in the wrong direction

T AvGincreases

Boric Acid addition exceeds the desired value Appendix 0 NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 1

Scenario #

1 Event #

4 Page 10 of 29 Event

Description:

Plant down power from condensate Pump A trip which tripped Feedwater Pump A.

Time Position Applicants Actions or Behavior Op Test No.:

WHEN the desired amount of Boric Acid has been added, THEN verify the following:

RD FCV-1 13A, BORIC ACID FLOW, closes.

FCV-1 13B, BLENDED MU TO CHG SUCT, closes.

IF in Auto, THEN the operating Boric Acid Pump stops.

The RCS MAKEUP SYSTEM is OFF.

IF desired, THEN FLUSH the Boric Acid flow path as follows:

PLACE the RCS MAKEUP MODE selector switch in the ALT DILUTE position.

SET YIC-114, PRIMARY WTR TOTALIZERto 15-20 gallons.

PLACE FCV-114B, BLENDED MU TO VCTto CLOSE.

Momentarily PLACE the RCS MAKEUP SYSTEM switch to the START position.

IF any of the below conditions occur, THEN momentarily place RO the RCS MAKEUP SYSTEM switch in the STOP position:

o Unanticipated Rod Motion o

Primary Water addition reaches the desired value WHEN the desired amount of Primary Water has been added to the RCS, THEN verify the following:

o FCV-ll4Acloses.

o FCV-1 13B closes.

o IF in Auto, THEN the operating PW Pump stops.

o The RCS MAKEUP SYSTEM is OFF.

RETURN the RCS Makeup System to automatic as follows:

VERIFY FCV-1 1 4A is in AUTO.

PLACE FCV-1 14B to the AUTO position.

RD PLACE the RCS MAKEUP MODE switch in AUTO.

VERIFY FCV-1 13A is in AUTO.

Momentarily PLACE the RCS MAKEUP SYSTEM switch in the START position.

RECORD, in AUTO LOG, as indicated by PRIMARY WATER RD TOTALIZER, YIC-1 14 AND Boric Acid TOTALIZER, YIC-1 13 the total amount of Primary Water AND Boric Acid added during the boration.

RD MONITOR parameters for the expected change in reactivity AND inform_the_CRSS_OR_the_SSO_of the_results_of the_boration.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: -- Scenario #

1 Event #

4 Page 10 of 29

~---~I Event

Description:

Plant down power from Condensate Pump "A" trip which tripped Feedwater Pump "A".

Time

~

Position

~

Applicant's Actions or Behavior WHEN the desired amount of Boric Acid has been added, THEN verify the following:

FCV-113A, BORIC ACID FLOW, closes.

RO FCV-113B, BLENDED MU TO CHG SUCT, closes.

IF in Auto, THEN the operating Boric Acid Pump stops.

The RCS MAKEUP SYSTEM is OFF.

IF desired, THEN FLUSH the Boric Acid flow path as follows:

PLACE the RCS MAKEUP MODE selector switch in the AL T DILUTE position.

SETYIC-114, PRIMARYWTR TOTALIZER to 15-20 gallons.

PLACE FCV-114B, BLENDED MU TO VCT to CLOSE.

Momentarily PLACE the RCS MAKEUP SYSTEM switch to the START position.

IF any of the below conditions occur, THEN momentarily place RO the RCS MAKEUP SYSTEM switch in the STOP position:

0 Unanticipated Rod Motion 0

Primary Water addition reaches the desired value

WHEN the desired amount of Primary Water has been added to the RCS, THEN verify the following:

0 FCV -114A closes.

0 FCV-113B closes.

0 IF in Auto, THEN the operating PW Pump stops.

0 The RCS MAKEUP SYSTEM is OFF.

RETURN the RCS Makeup System to automatic as follows:

VERIFY FCV~114A is in AUTO.

PLACE FCV-114B to the AUTO position.

RO PLACE the RCS MAKEUP MODE switch in AUTO.

VERIFY FCV-113A isin AUTO.

Momentarily PLACE the RCS MAKEUP SYSTEM switch in the START position.

RECORD, in AUTO LOG, as indicated by PRIMARY WATER RO TOTALIZER, YIC-1 14 AND Boric Acid TOTALIZER, YIG.. 113 the total amount of Primary Water AND Boric.Acid added during the boration.

RO MONITOR parameters for the expected change in reactivity AND inform the CRSS OR the SSO of the results of the boration.

Appendix 0 NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

4 Page 11 of 29 Event

Description:

Plant down power from Condensate Pump A trip which tripped Feedwater Pump A.

Time Position Applicants Actions or Behavior BOP Check at least 1 Main Feed Pump running. (YES, Go To Step 37)

BOP Check S/G Level at or trending to program. (YES)

RO Check TAVG at or trending to TREF. (YES)

SRO Contact Maintenance to troubleshoot and correct Feedwater problem.

SRO Implement the EALs.

Check current loading for the following pumps less than maximum.

Main Feedwater Pump 0.715 KAMPS BOP

. Condensate Pump 370 AMPS

Heater Drain Pumps 90 AMPS BOOTH OPERATOR:

When contacted, wait 3 minutes and report that Main Feedwater Pump B is 530 AMPS, Condensate Pump B is 320 AMPS and Heater Drain Pumps are 80 AMPS each.

RO Determine Iodine Sampling Requirements:

Check Power change> 15% in one hour. (NO, Go To Step 43)

Continuous Action Step:

Check APP-005-B5, ROD BANKS A/B/C/D LO LIMIT extinguished.

RO (YES)

IF alarm is illuminated, THEN Borate to clear the alarm using OP-301 while continuing in this procedure RO Monitor Axial Flux Difference to ensure compliance with LCO 3.2.3 Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

.....;...- Scenario #

1 Event #

_4..:.....-____ Page 11 of...,;2;;.;;.9 ___

-lI Event

Description:

Plant down power from Condensate Pump "Au trip which tripped Feedwater Pump "Au.

I Time I

Position I

Applicant's Actions or Behavior BOP Check at least 1 Main Feed Pump running. (YES, Go To Step 37)

BOP Check S/G Level at or trending to program. (YES)

RO Check T AVG at or trending to T REF. (YES)

SRO Contact Maintenance to troubleshoot and correct Feedwater problem.

SRO Implement the EALs.

Check current loading for the following pumps less than maximum.

BOP

Main Feedwater Pump - 0.715 KAMPS

Condensate Pump - 370 AMPS

Heater Drain Pumps - 90 AMPS 800TH OPERATOR: When contacted, wait 3 minutes and report that Main Feedwater Pump "8" is 530 AMPS, Condensate Pump "8" is 320 AMPS and Heater Drain Pumps are 80 AMPS each.

RO Determine Iodine Sampling Requirements:

Check Power change> 15% in one hour. (NO, Go To Step 43)

Continuous Action Step:

Check APP-005-B5, ROD BANKS AlB/C/D LO LIMIT extinguished.

RO (YES)

IF alarm is illuminated, THEN Borate to clear the alarm using OP-301 while continuing in this procedure.

RO Monitor Axial Flux Difference to ensure compliance with LCO 3.2.3 Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

4 Page 12 of 29 Event

Description:

Plant down power from Condensate Pump A trip which tripped Feedwater Pump A.

Time Position Applicants Actions or Behavior SRO Notify Load Dispatcher of the units load capability.

SRO Return to procedure and step in effect.

At the discretion of the Chief Examiner, insert Event 5.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

-.;...- Scenario #

Event #

~4 _________ Page 12 of

_2;;;.;9~ __ ---I1 Event

Description:

Plant down power from Condensate Pump "A" trip which tripped Feedwater Pump "A".

Time II Position Applicant's Actions or Behavior SRO Notify Load Dispatcher of the unit's load capability.

SRO Return to procedure and step in effect.

At the discretion of the Chief Examiner, insert Event 5.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

5 Page 13 of 29 Event

Description:

PT-444, Controlling PZR pressure channel fails High.

Time Position Applicants Actions or Behavior BOOTH OPERATOR: When directed, insert Event 5, PT-444 failed high.

EVENT INDICATIONS:

APP-003-D8, PZR CONTROL HI/LO PRESS APP-003-F3, CHG PMP LO SPEED APP-003-E6, PZR PORV LN HI TEMP APP-003-F6, PZR SAFETY LINE HI TEMP APP-003-C3, PRT HIGH PRESS APP-003-C7, PZR PRESS CONTROLLER HI OUTPUT RO Recognizes that PT-444 is failed high and performs Immediate Actions of AOP-025.

SRO Enters AOP-025, RTGB INSTRUMENT FAILURE, Section C.

Immediate Action Step:

Determine if PORVs should be closed.

RO Check Pressurizer pressure less than 2335 psig (YES).

Verify both PORVs CLOSED (NO, PCV-455C OPEN).

NOTE:

May use PC-444J or Close PORV & Spray Valves in Manual.

Immediate Action Step:

RO Control Pressurizer Spray Valves and Pressurizer Heaters to restore RCS pressure to the desired control band.

NOTE:

Crew will enter LCO 3.4.1.A if pressure decreases < 2205 PSIG.

Pressure must be restored > 2205 PSIG within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

RO/BOP Make PA announcement for entry into AOP-025.

SRO/RO Check PT-444 is the failed transmitter. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

--..;.....- Scenario #

1 Event #

5 Page 13 of 29

~--------

~------~I Event

Description:

PT-444, Controlling PZR pressure channel fails High.

Time

~

Position

~

Applicant's Actions or Behavior BOOTH OPERATOR: When directed, insert Event 5, PT-444 failed high.

EVENT INDICATIONS:

APP-003-D8, PZR CONTROL HIILO PRESS APP-003-F3, CHG PMP LO SPEED APP-003-ES, PZR PORV LN HI TEMP APP-003-FS, PZR SAFETY LINE HI TEMP APP-003-C3, PRT HIGH PRESS APP-003-C7, PZR PRESS CONTROLLER HI OUTPUT RO Recognizes that PT-444 is failed high and performs Immediate Actions of AOP-025.

SRO Enters AOP-025, RTGB INSTRUMENT FAILURE, Section C.

Immediate Action Step:

Determine if PORVs should be closed.

RO

Check Pressurizer pressure less than 2335 psig (YES).

Verify both PORVs CLOSED (NO, PCV-455C OPEN).

NOTE:

May use PC-444J or Close PORV & Spray Valves in Manual.

Immediate Action Step:

RO Control Pressurizer Spray Valves and Pressurizer Heaters to restore RCS pressure to the desired control band.

NOTE:

Crew will enter LCO 3.4.1.A if pressure decreases < 2205 PSIG.

Pressure must be restored> 2205 PSIG within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

RO/BOP Make PA announcement for entry into AOP-025.

SRO/RO Check PT-444 is the failed transmitter. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

5 Page 14 of 29 Event

Description:

PT-444, Controlling PZR pressure channel fails High.

Time Position II Applicants Actions or Behavior RO RO Control Pressurizer pressure controller PC-444J:

Place PC-444J in MAN.

Verify PZR SPRAY VALVES IN AUTO.

Verify PZR Heaters energized as desired.

Restore PZR Pressure to the desired control band.

Verify PCV.455C in AUTO.

RO SRO SRO Verify Selector Switch PM-444 is selected to operable channel:

REC-445.

Informs SSO to implement EALs.

Enters LCO 3.4.1, Condition A.

NOTE:

Crew should notify WCC SRO and/or l&C to write a work request, investigate and initiate repairs, and notify the Operations Manager.

At Chief Examiners discretion after ITS is addressed, proceed to Event 6.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.:

....;...- Scenario #

1 Event #

_5;;;..-.____ Page 14 of

_2;;;;.;9~ __ --I1 Event

Description:

PT-444, Controlling PZR pressure channel fails High.

Time J

Position II Applicant's Actions or Behavior Control Pressurizer pressure controller PC-444J:

Place PC-444J in MAN.

RO

Verify PZR SPRAY VALVES IN AUTO.

Verify PZR Heaters energized as desired.

Restore PZR Pressure to the desired control band.

RO Verify PCV-455C in AUTO.

RO Verify Selector Switch PM-444 is selected to operable channel:

REC-445.

SRO Informs SSO to implement EAL's.

SRO Enters LCO 3.4.1, Condition A.

NOTE:

Crew should notify WCC SRO and/or I&C to write a work request, investigate and initiate repairs, and notify the Operations Manager.

At Chief Examiner's discretion after ITS is addressed, proceed to Event 6.

Appendix 0 NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

6, 7 & 8 Page 15 of 29 Event

Description:

RCP C #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs B and C on the Reactor Trip.

EDG A fails to start on Safety Injection.

Time Position fi Applicants Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 6, RCP C #2 Seal failure requiring Reactor Trip.

EVENT INDICATIONS:

APP-OO1-C5; RCP STAN DPIPE HI/LO LVL (RCP C STP HI)

FR 154A, Pen 3 (Blue), C RCP Seal Leakoff decreasing RO Recognizes decreasing seal leakoff and references APP-O01 -C5.

RO IF Standpipe level is High, THEN check for rising level in the Reactor Coolant Drain Tank.

BOOTH OPERATOR:

When requested by the crew wait 3 minutes and inform the crew that RCDT level is slowly rising. (1% in the last 3 mm.)

SRO Enters AOP-01 8, RCP ABNORMAL CONDITIONS, Section A.

Continuous Action Step:

RO Check any RCP #1 Seal leakoff flow> 5.7 GPM. (NO, Go To Step 8)

IF seal leakoff exceeds 5.7 GPM, THEN Go To Step 2.

Continuous Action Step:

RO Check indicated #1 Seal Leakoff < 0.8 GPM. (NO, Go To Step 14)

IF Seal Leakoft decreases to < 0.8 GPM, THEN Go To Step 9.

RO Check RCP #2 Seal problem suspected. (YES)

Check RCP #2 Seal Leakoff rate known. (NO)

SRO Dispatch an operator to perform Att. 2, RCP Seal Leak Rate Calculation. WHEN calculation is complete, THEN Go To Step 16.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: --

Event

Description:

Operator Action Form ES-D-2 Scenario #

1 Event #

6, 7 & 8 Page 15 of 29

~~~---

~---~I RCP "C" #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs "B" and "C" on the Reactor Trip.

EDG "A" fails to start on Safety Injection.

Time II Position

~

Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 6, RCP "C" #2 Seal failure requiring Reactor Trip.

EVENT INDICATIONS:

APP-001-C5; RCP STANDPIPE HI/LO LVL (RCP C STP HI)

FR 154A, Pen 3 (Blue), C RCP Seal Leakoff decreasing RO Recognizes decreasing seal leakoff and references APP-001-C5.

RO IF Standpipe level is High, THEN check for rising level in the Reactor Coolant Drain Tank.

BOOTH OPERATOR: When requested by the crew wait 3 minutes and inform the crew that RCDT level is slowly rising. (1 % in the last 3 min.)

SRO Enters AOP-018, RCP ABNORMAL CONDITIONS, Section A.

Continuous Action Step:

RO Check any RCP #1 Sealleakoff flow> 5.7 GPM. (NO, Go To Step 8)

IF sealleakoff exceeds 5.7 GPM, THEN Go To Step 2.

Continuous Action Step:

RO Check indicated #1 Seal Leakoff < 0.8 GPM. (NO, Go To Step 14)

IF Seal Leakoff decreases to < 0.8 GPM, THEN Go To Step 9.

RO Check RCP #2 Seal problem suspected. (YES)

Check RCP #2 Seal Leakoff rate known. (NO)

SRO Dispatch an operator to perform Att. 2, RCP Seal Leak Rate Calculation. WHEN calculation is complete, THEN Go To Step 16.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

6, 7 & 8 Page 16 of 29 Event

Description:

RCP c #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs B and c on the Reactor Trip.

EDG A fails to start on Safety Injection.

Time Position

[

Applicants Actions or Behavior BOOTH OPERATOR:

When requested to perform Leak Rate Calculation, wait 5 minutes and inform the crew that RCP #2 Seal leakoff is 1.3 GPM.

Continuous Action Step:

RO Check calculated RCP #2 Seal leakoff < 1.1 GPM. (NO)

Place the plant in Mode 3 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months using GP-006. WHEN the plant is in Mode 3, THEN stop the affected RCP.

BOOTH OPERATOR: The crew will make the decision to shut down the plant lAW GP 006. As soon as Step 16 (above) is performed, insert the higher RCS leak rate.

The crew will identify the increased leakage and return to Continuous Action Step 1.

EVENT INDICATIONS:

APP-OO1-B2; RCP LABYRTH SEAL LO DP APP-OO1-D2; RCP #1 SEAL LEAKOFF HI FLOW APP-OO1-E2; RCP #1 SEAL LEAKOFF LO FLOW PZR level decreasing, Charging Pump Speed increasing FR 154A; A and B Pens decreasing, C Pen pegged HIGH.

RO Check Plant in MODE 1. (YES)

Perform the following:

RO Trip the reactor.

__Trip_RCP_C.

RO RO Continuous Action Step:

Check any RCP #1 Seal leakoff flow> 5.7 GPM. (YES)

Check RCP #1 seal leakoff flow on unaffected RCP(s)

DECREASED (YES)

OR RCP Thermal Barrier tP on affected RCP(s)

- DECREASED (YES)

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.:

Event

Description:

Operator Action Form ES-D-2 Scenario #

1 Event #

_6;...:.,..;..7...;;&;....;;8;....-__ Page 16 of..,;2:;;,;9:...-__ --11 Rep "e" #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs "B" and "e" on the Reactor Trip.

EDG "A" fails to start on Safety Injection.

Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR: When requested to perform Leak Rate Calculation, wait 5 minutes and inform the crew that RCP #2 Seal leakoff is 1.3 GPM.

Continuous Action Step:

RO Check calculated RCP #2 Sealleakoff < 1.1 GPM. (NO)

Place the plant in Mode 3 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months using GP-006. WHEN the plant is in Mode 3, THEN stop the affected RCP.

BOOTH OPERATOR: The crew will make the decision to shut down the plant lAW GP-006. As soon as Step 16 (above) is performed, insert the higher RCS leak rate.

The crew will identify the increased leakage and return to Continuous Action Step 1.

EVENT INDICATIONS:

APP-001-B2; RCP LABYRTH SEAL LO DP APP-001-D2; RCP #1 SEAL LEAKOFF HI FLOW APP-001-E2; RCP #1 SEAL LEAKOFF LO FLOW PZR level decreasing, Charging Pump Speed increasing FR 154A; A and B Pens decreasing, C Pen pegged HIGH.

RO Continuous Action Step:

Check any RCP #1 Sealleakoff flow> 5.7 GPM. (YES)

Check RCP #1 sealleakoff flow on unaffected RCP(s) - DECREASED RO (YES)

OR RCP Thermal Barrier boP on affected RCP(s) - DECREASED (YES)

RO Check Plant in MODE 1. (YES)

Perform the following:

RO Trip the reactor.

TrifJ RCP "C".

Appendix D NUREG-1021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

6, 7 & 8 Page 17 of 29 Event

Description:

RCP C #2 Seal fails, requiring a Reactor Trip.

Steam Break from S!Gs B and C on the Reactor Trip.

EDG A fails to start on Safety Injection.

Time Position Applicants Actions or Behavior Go To Path-i while continuing with this procedure.

NOTE:

Following the performance and verification of PATH-i Immediate Actions, the crew will continue with AOP-018. These steps may be handed off to the RO/BOP to perform independently.

The remaining steps of AOP-0i8 are listed here.

PATH-i actions begin on Page i8.

PHASE B isolation has occurred, so ALL RCPs will be secured.

AOP-018 actions RO WHEN at least 3 minutes have elapsed since tripping the affected RCP, THEN Close Seal leakoff valve for RCP C. (CVC-303C)

RO Check RCP B or C running. (NO)

RO Check RCP seal injection flow between 8 and 13 GPM. (YES)

RO Check FCV-626, THERM BAR FLOW CONT Valve CLOSED. (YES)

Continuous Action Step:

RO Check Thermal Barrier intact. (YES)

WHEN this procedure is completed, THEN Go To AOP-014, CCW SYSTEM MALFUNCTION.

RO Check APP-002-D2, CV ISOL PHASE B extinguished. (NO)

SRO Implement EAL5.

SRO Review ITS for applicable LCOs:

LCO 3.4.13, Condition A

- Reduce leakage to within limits within 4 hrs.

Appendix D NUREG-i021, Rev. 9, Supp. 1 Appendix D Op Test No.:

Event

Description:

Operator Action Form ES-D-2 Scenario #

1 Event #

_6;,:,'...;..7..;;.;&;..;;8~ __ Page 17 of....::2:.;;.9 ___

-11 Rep "e" #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs "B" and "e" on the Reactor Trip.

EDG "A" fails to start on Safety Injection.

Time II Position II Applicant's Actions or Behavior Go To Path-1 while continuing with this procedure.

NOTE:

Following the performance and verification of PATH-1 Immediate Actions, the crew will continue with AOP-018. These steps may be handed off to the RO/BOP to perform independently.

The remaining steps of AOP-018 are listed here.

PATH-1 actions begin on Page 18.

PHASE B isolation has occurred, so ALL RCPs will be secured.

AOP-018 actions RO WHEN at least 3 minutes have elapsed since tripping the affected RCP, THEN Close Sealleakoff valve for RCP "C". (CVC-303C)

RO Check RCP "B" or "C" running. (NO)

RO Check RCP seal injection flow between 8 and 13 GPM. (YES)

RO Check FCV-626, THERM BAR FLOW CO NT Valve CLOSED. (YES)

Continuous Action Step:

RO Check Thermal Barrier intact. (YES)

WHEN this procedure is completed, THEN Go To AOP-014, CCW SYSTEM MALFUNCTION.

RO Check APP-002-D2, CV ISOL PHASE B extinguished. (NO)

SRO Implement EALs.

SRO Review ITS for applicable LCOs:

LCO 3.4.13, Condition A - Reduce leakage to within limits within 4 hrs.

Appendix D NUREG-1021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

6, 7 & 8 Page 18 of 29 Event

Description:

RCP C #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs B and C on the Reactor Trip.

EDG A fails to start on Safety Injection.

Time Position Applicants Actions or Behavior BOOTH OPERATOR:

Steam break for SIGs B and C are triggered to occur when the Reactor Trip Breakers open. Verify steam break malfunction is inserted.

SRO Directs tripping the Reactor, tripping RCP C and enters PATH-i.

PATH-i actions Immediate Action Step:

RO Reactor Tripped. (YES)

Immediate Action Step:

BOP Turbine Tripped. (YES)

Immediate Action Step:

BOP E-1 AND E-2 energized (YES)

Immediate Action Step:

RO SI Initiated. (YES)

NOTE:

Phase B isolation has occurred; the crew will stop ALL RCPs due to a loss of RCP cooling.

When Foldout A is addressed the crew may isolate S/Gs B and C using Foldout A.

SI will have to be reset prior to manipulating valves.

SRO Open Foldout A.

RCP Trip criteria. IF BOTH conditions are met, THEN stop all RCPs: (NO) o SI Pumps

- AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE o

RCS Subcooling

- < 35 degrees F [55 degrees F]

Appendix D NUREG-iO2i, Rev. 9, Supp. 1 Appendix D Op Test No.:

Event

Description:

Operator Action Form ES-D-2 Scenario #

1 Event #

_6

.....,_7_&_8 ___ Page 18 of....;2::.;9:.....-__

---11 RCP "C" #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs "B" and "C" on the Reactor Trip.

EDG "A" fails to start on Safety Injection.

Time II Position II Applicant's Actions or Behavior 800TH OPERATOR: Steam break for SIGs "8" and "e" are triggered to occur when the Reactor Trip 8reakers open. Verify steam break malfunction is inserted.

SRO Directs tripping the Reactor, tripping Rep "en and enters PATH-1.

PATH-1 actions RO Immediate Action Step:

Reactor Tripped. (YES)

BOP Immediate Action Step:

Turbine Tripped. (YES)

BOP Immediate Action Step:

E-1 AND E-2 energized. (YES)

RO Immediate Action* Step:

SI Initiated. (YES)

NOTE:

Phase 8 isolation has occurred; the crew will stop ALL Reps due to a loss of Rep cooling.

When Foldout A is addressed the crew may isolate SIGs "8" and "e" using Foldout A.

SI will have to be reset prior to manipulating valves.

SRO Open Foldout A.

Rep Trip criteria. IF BOTH conditions are met, THEN stop all Reps: (NO) 0 SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 0

RCS Subcooling - < 35 degrees F [55 degrees F]

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

Event

Description:

RCP C, #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs B and C on the Reactor Trip.

EDG A fails to start on Safety Injection.

Position Applicants Actions or Behavior Time 1

Scenario #

1 Event #

6, 7 & 8 Page 19 of 29 SI actuation criteria. IF EITHER condition occurs, THEN Actuate SI and Go To PATH-i, Entry Point A:

o RCS Subcooling

- < 35 degrees F [55 degrees F]

o PZR Level

- CAN NOT BE MAINTAINED > 10% [32%]

MSR Isolation criteria. IF ANY Purge OR Shutoff Valve does NOT indicate fully closed, THEN place the associated RTGB Switch to CLOSE.

S/G isolation criteria. IF both the following conditions are met, THEN perform the following:

Any SIG pressure is decreasing in an uncontrolled manner OR Any S/G has completely depressurized.

AND At least ONE SIG is intact.

o Reset SI.

o CLOSE the appropriate AFW isolation valves to the faulted S/Gs AND OPEN the associated breaker for the valves closed.

SIG B V2-14B, SDAFW PUMP DISCH, MCC-9, CMPT-1C V2-16B, AFW HDR DISCH, MCC-10, CMPT

- 4F a

s V2-14C, SDAFW PUMP DISCH, MCC 10, CMPT

- 4M V2-16C, AFW HDR DISCH, MCC-9, CMPT

- 3J o

WHEN the faulted S/Gs dry out, THEN dump steam from intact SIG to control RCS repressurization.

PATH-i actions RO Verify Phase A Isolation valves are closed. (YES)

BOP Verify FW Isolation valves are closed. (YES)

BOP Verify both FW pumps are tripped. (YES)

Appendix D NUREG-i021, Rev. 9, Supp. 1 Appendix D Op Test No.:

Event

Description:

Operator Action Form ES-D-2 Scenario #

Event #

_6;;;;.l.,..;.7...;;&;..;:8:.....-__ Page 19 of _2;;;;.,9 ___

---i1 Rep "e" #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs "B" and "e" on the Reactor Trip.

EDG "A" fails to start on Safety Injection.

Time II Position II Applicant's Actions or Behavior SI actuation criteria. IF EITHER condition occurs, THEN Actuate SI and Go To PATH-1, Entry Point A:

0 RCS Subcooling - < 35 degrees F [55 degrees F]

0 PZR Level-CAN NOT BE MAINTAINED> 10% [32%]

MSR Isolation criteria. IF ANY Purge OR Shutoff Valve does NOT indicate fully closed, THEN place the associated RTGB Switch to CLOSE.

S/G isolation criteria. IF both the following conditions are met, THEN perform the following:

Any S/G pressure is decreasing in an uncontrolled manner OR Any S/G has completely depressurized.

AND At least ONE S/G is intact.

0 Reset SI.

0 CLOSE the appropriate AFW isolation valves to the faulted S/Gs AND OPEN the associated breaker for the valves closed.

S/G "B" V2-14B, SDAFW PUMP DISCH, MCC-9, CMPT - 1C V2-16B, AFW HDR DISCH, MCC-10, CMPT - 4F S/G "c" V2-14C, SDAFW PUMP DISCH, MCC-10, CMPT - 4M V2-16C, AFW HDR DISCH, MCC-9, CMPT - 3J 0

WHEN the faulted S/Gs dry out, THEN dump steam from intact S/G to control RCS repressurization.

PATH-1 actions RO Verify Phase A Isolation valves are closed. (YES)

BOP Verify FW Isolation valves are closed. (YES)

BOP Verify both FW pumps are tripped. (YES)

Appendix D NUREG-1 021, Rev. g, Supp. 1

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

1 Scenario #

1 Event #

6, 7 & 8 Page 20 of 29 Event

Description:

RCP C, #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs B and C on the Reactor Trip.

EDG A fails to start on Safety Injection.

Time Position Applicants Actions or Behavior BOP Verify both MDAFW pumps are running. (YES)

NOTE:

Crew may elect to reset SI in order to control AFW and SIG levels.

BOP If additional Feedwater is required, start the SDAFW pump.

RO Verify 2 SI pumps running. (YES)

RD Verify Both RHR pumps running. (YES)

RD Verify SI valves are properly aligned. (YES)

RD At least 1 COW pump is running. (YES)

BOP All SW and SW Booster pumps running. (NO)

BOP Attempt to start all SW and SW Booster pumps. (NO, SW Booster Pump A is unavailable)

BOP North OR South SW Header Lo Pressure alarm illuminated. (NO)

RD Verify CV Fans HVH-1, 2, 3, 4 running. (YES)

RD Verify IVSW initiated. (YES)

BOP Verify CV Ventilation isolation. (YES)

BOP Verify Control Room Vent aligned for Pressurization Mode. (YES)

Appendix D NUREG..1 021, Rev. 9, Supp. 1 Appendix 0 Op Test No.: --

Event

Description:

Operator Action Form ES-D-2 Scenario #

1 Event #

6, 7 & 8 Page 20 of 29

~~~----

~------~I Rep "e" #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs "B" and "e" on the Reactor Trip.

EDG "A" fails to start on Safety Injection.

Time II Position II Applicant's Actions or Behavior BOP Verify both MDAFW pumps are running. (YES)

NOTE:

Crew may elect to reset 51 in order to control AFW and 5/G levels.

BOP If additional Feedwater is required, start the SDAFW pump.

RO Verify 2 SI pumps running. (YES)

RO Verify Both RHR pumps running. (YES)

RO Verify SI valves are properly aligned. (YES)

RO At least 1 CCW pump is running. (YES)

BOP All SW and SW Booster pumps running. (NO)

BOP Attempt to start all SW and SW Booster pumps. (NO, SW Booster Pump "A" is unavailable)

BOP North OR South SW Header Lo Pressure alarm illuminated. (NO)

RO Verify CV Fans HVH-1, 2, 3, 4 running. (YES)

RO Verify IVSW initiated. (YES)

BOP Verify CV Ventilation isolation. (YES)

BOP Verify Control Room Vent aligned for Pressurization Mode. (YES)

Appendix 0 NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

6, 7 & 8 Page 21 of 29 Event

Description:

RCP C #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs B and C on the Reactor Trip.

EDG A fails to start on Safety Injection.

Time Position Applicants Actions or Behavior BOP Verify both EDGs running. (NO)

NOTE:

If requested to investigate what is wrong with the EDG, report that the EDG has tripped on OVERSPEED and you were unable to reset the fuel racks.

Continuous Action Step:

BOP Restart battery chargers within 30 minutes of power loss using OP 601.

Continuous Action Step:

RO CV Pressure has remained below 10 psig. (NO)

RO Verify approximately 12 GPM Spray additive tank flow. (Flow will be adjusted from. 30 GPM to 12 GPM)

BOP Verify ALL MSIVs and MSIV bypasses closed. (YES, operator will take MSIV switches to CLOSE)

BOP Locally open breaker for HVS-1 at MCC-5.

RO RO RO RO Verify CV Spray initiated. (YES)

Verify ALL CV Spray pumps running with valves aligned. (YES)

Verify Phase B isolation valves closed. (YES)

Stop ALL RCPs. (May be stopped previously)

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.:

~-

Event

Description:

Operator Action Form ES-D-2 Scenario #

1 Event #

_6;;,:,'..;..7..;;;;&~8 ___ Page 21 of --=2:;;,9 ___

-11 RCP "C" #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs "B" and "C" on the Reactor Trip.

EDG "A" fails to start on Safety Injection.

Time I

Position I

Applicant's Actions or Behavior BOP Verify both EDGs running. (NO)

NOTE:

If requested to investigate what is wrong with the EDG, report that the EDG has tripped on OVERSPEED and you were unable to reset the fuel racks.

Continuous Action Step:

BOP Restart battery chargers within 30 minutes of power loss using OP-601.

RO Continuous Action Step:

CV Pressure has remained below 10 psig. (NO)

RO Verify CV Spray initiated. (YES)

RO Verify ALL CV Spray pumps running with valves aligned. (YES)

RO Verify approximately 12 GPM Spray additive tank flow. (Flow will be adjusted from - 30 GPM to 12 GPM)

RO Verify Phase B isolation valves closed. (YES)

RO Stop ALL RCPs. (May be stopped previously)

BOP Verify ALL MSIVs and MSIV bypasses closed. (YES, operator will take MSIV switches to CLOSE)

BOP Locally open breaker for HVS-1 at MCC-5.

Appendix D NUREG-1021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

6, 7 & 8 Page 22 of 29 Event

Description:

RCP C #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs B and C on the Reactor Trip.

EDG A fails to start on Safety Injection.

Time Position Applicants Actions or Behavior RCS pressure> 1350 psig. [1250 psig]

RO (YES, RCS pressure is> 1250, skip the following 2 steps)

(NO, RCS pressure is < 1250, Go To the next step)

RO SI Flow Verified. (YES)

RO RCS Pressure Greater than 125 psig. (YES)

BOP At least 300 GPM AFW flow available. (YES)

BOP Verify AFW valves properly aligned.

BOP Control AFW flow to maintain S/G levels between 8% [18%] and 50%.

RO RCP Thermal barrier cooling water Hi/Lo flow alarm illuminated. (YES)

RO At least one Charging Pump running. (YES)

BOP Place Steam Dump Mode Switch to Steam Pressure.

RO RCS Temp stable at OR trending to 547 degrees F. (NO)

RO RCS temperature> 547 degrees F. (NO)

BOP Attempt to limit cooldown.

BOP IF RCS cooldown continues and is NOT due to SI flow, THEN close MSIVs and MSIV bypasses.

AppendixD NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.:

Event

Description:

Operator Action Form ES-D-2 Scenario #

1 Event #

6, 7 & 8 Page 22 of 29

~~~----

~------~I Rep "e" #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs "B" and "e" on the Reactor Trip.

EDG "A" fails to start on Safety Injection.

Time I

Position I

Applicant's Actions or Behavior RCS pressure> 1350 psig. [1250 psig]

RO (YES, RCS pressure is > 1250, skip the following 2 steps)

(NO, RCS pressure is < 1250, Go To the next step)

RO SI Flow Verified. (YES)

RO RCS Pressure Greater than 125 psig. (YES)

BOP At least 300 GPM AFW flow available. (YES)

BOP Verify AFW valves properly aligned.

BOP Control AFW flow to maintain SIG levels between 8% [18%] and 50%.

RO RCP Thermal barrier cooling water HilLo flow alarm illuminated. (YES)

RO At least one Charging Pump running. (YES)

BOP Place Steam Dump Mode Switch to Steam Pressure.

RO RCS Temp stable at OR trending to 547 degrees F. (NO)

RO RCS temperature> 547 degrees F. (NO)

BOP Attempt to limit cooldown.

BOP IF RCS cool down continues and is NOT due to SI flow, THEN close MSIVs and MSIV bypasses.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 OpTestNo.:

Event

Description:

Time RO PZR PORVs closed. (YES)

RO PZR Spray and Aux Spray valves closed. (YES)

RO At least 1 RCP running. (NO)

BOP Any S/G with uncontrolled depressurization. (YES)

RO Reset SPDS and initiate monitoring of CSFSTs.

SRO Go To EPP-11, FAULTED STEAM GENERATOR ISOLATION.

EPP-11 actions BOP Maintain At Least One S/G Available For RCS Cooldown.

BOP Any S/G pressure stable or increasing. (YES)

BOP Any SIG pressure decreasing in an uncontrolled manner OR any SIG completely depressurized. (YES)

BOP Isolate faulted S/Gs using Supplement G, SIG ISOLATION.

(Supplement G Steps are listed on pages 24-26)

BOP Maintain A Faulted SIG In The Isolated Condition During Subsequent Recovery Actions Unless Needed For Cooldown.

BOP Check CST level greater than 10%. (YES)

BOP Check Available Secondary Radiation Monitors normal. (YES)

Scenario #

1 Event #

6, 7 & 8 Page 23 of 29 Rcp c #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs B and c on the Reactor Trip.

EDG A fails to start on Safety Injection.

Position Applicants Actions or Behavior Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: --

Event

Description:

Operator Action Form ES-D-2 Scenario #

1 Event #

6, 7 & 8 Page 23 of 29

~I RCP "C" #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs "B" and "C" on the Reactor Trip.

EDG "A" fails to start on Safety Injection.

Time II Position II Applicant's Actions or Behavior RO PZR PORVs closed. (YES)

RO PZR Spray and Aux Spray valves closed. (YES)

RO At least 1 RCP running. (NO)

BOP Any S/G with uncontrolled depressurization. (YES)

RO Reset SPDS and initiate monitoring of CSFSTs.

SRO Go To EPP-11, FAULTED STEAM GENERATOR ISOLATION.

EPP-11 actions BOP Maintain At Least One S/G Available For RCS Cooldown.

BOP Any S/G pressure stable or increasing. (YES)

BOP Any S/G pressure decreasing in an uncontrolled manner OR any S/G completely depressurized. (YES)

BOP Isolate faulted S/Gs using Supplement G, S/G ISOLATION.

(Supplement G Steps are listed on pages 24-26)

BOP Maintain A Faulted S/G In The Isolated Condition During Subsequent Recovery Actions Unless Needed For Cooldown.

BOP Check CST level greater than 10%. (YES)

BOP Check Available Secondary Radiation Monitors normal. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

6, 7 & 8 Page 24 of 29 Event

Description:

RCP C #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs B and C on the Reactor Trip.

EDG A fails to start on Safety Injection.

Time I

Position Applicants Actions or Behavior CRITICAL TASK:

Isolate feedwater to the faulted SIGs using Foldout A OR Supplement G prior to transitioning to PATH-i, Entry point C.

RO Check any SIG with an uncontrolled level increase. (NO, Go To Path-1, Entry Point C) (PATH-i Steps continue on Page 28)

Supplement G, STEAM GENERATOR ISOLATION actions to isolate S/Gs B and C as faulted Steam Generators.

Go to the appropriate step from following table:

BOP SIG B to be isolated, Go To Step 18.

S/G C to be isolated, Go To Step 34.

Check S/G B faulted. (YES)

BOP Check S/G C faulted. (YES)

Verify Vi -3B, MSIV CLOSED. (YES)

BOP Verify Vi -3C, MSIV CLOSED. (YES)

Verify MS-353B, MSIV Vi -3B BYP CLOSED. (YES)

BOP Verify MS-353C, MSIV Vi -3C BYP CLOSED. (YES)

Verify FRV B CLOSED. (YES)

BOP Verify FRV C CLOSED. (YES)

Verify FRV B BYP CLOSED. (YES)

BOP Verify FRV C BYP CLOSED. (YES)

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --

Event

Description:

Operator Action Form ES-D-2 Scenario #

1 Event #

6, 7 & 8 Page 24 of 29

~~~---

~---~I RCP "C" #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs "B" and "C" on the Reactor Trip.

EDG "A" fails to start on Safety Injection.

Time I

Position I

Applicant's Actions or Behavior CRITICAL TASK:

Isolate feedwater to the faulted S/Gs using Foldout A OR Supplement G prior to transitioning to PA TH-1, Entry point C.

RO Check any S/G with an uncontrolled level increase. (NO, Go To Path-1, Entry Point C) (PATH-1 Steps continue on Page 28)

Supplement G, STEAM GENERATOR ISOLATION actions to isolate S/Gs "8" and "e" as faulted Steam Generators.

Go to the appropriate step from following table:

BOP S/G B to be isolated, Go To Step 18.

S/G C to be isolated, Go To Step 34.

BOP Check S/G "B" faulted. (YES)

Check S/G "c" faulted. (YES)

BOP Verify V1-3B, MSIV CLOSED. (YES)

Verify V1-3C, MSIV CLOSED. (YES)

BOP Verify MS-353B, MSIV V1-3B BYP CLOSED. (YES)

Verify MS-353C, MSIV V1-3C BYP CLOSED. (YES)

BOP Verify FRV B CLOSED. (YES)

Verify FRV C CLOSED. (YES)

BOP Verify FRV B BYP CLOSED. (YES)

Verify FRV C BYP CLOSED. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

6, 7 & 8 Page 25 of 29 Event

Description:

RCP C#2 Seal fails, requiring a Reactor Trip.

Steam Break from S!Gs B and C on the Reactor Trip.

EDO A fails to start on Safety Injection.

Time Position Applicants Actions or Behavior Verify V2-6B, FW HDR SECTION Valve CLOSED. (YES)

BOP Verify V2-6C, FW HDR SECTION Valve CLOSED. (YES)

Verify V2-14B, SDAFW PUMP DISCH Valve CLOSED. (YES)

BOP Verify V2-14C, SDAFW PUMP DISCH Valve CLOSED. (YES)

Verify V2-16B, AFW HDR DISCH Valve CLOSED. (YES)

BOP Verify V2-1 6C, AFW HDR DISCH Valve CLOSED. (YES)

BOP Verify STEAM LINE PORVs CLOSED. (YES)

Verify Vi -8B, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)

BOP Verify Vi -8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)

BOP Verify S/Gs B and C Blowdown and Blowdown Sample Valve Status Light Indication CLOSED. (YES)

Dispatch an operator to the Pipe Jungle to close MS-29 and MS-38, BOP SIG B and SIG C BYPASS DRN and WARM.UP LINE TO AFW PUMP.

B Check S/Gs B and C MSIV Above and Below Seat Drain Valves OP CLOSED. (YES)

Appendix D NUREG-i 02i, Rev. 9, Supp. 1 Appendix D Op Test No.:

Event

Description:

Operator Action Form ES-D-2 Scenario #

1 Event #

_6;.:.,...;..7...;;&:...;;8 ___ Page 25 of

.....:2~9 ___

~1 Rep "e" #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs "B" and "e" on the Reactor Trip.

EDG "A" fails to start on Safety Injection.

Time

~

Position II Applicant's Actions or Behavior SOP Verify V2-6S, FW HDR SECTION Valve CLOSED. (YES)

Verify V2-6C, FW HDR SECTION Valve CLOSED. (YES)

SOP Verify V2-14S, SDAFW PUMP DISCH Valve CLOSED. (YES)

Verify V2-14C, SDAFW PUMP DISCH Valve CLOSED. (YES)

SOP Verify V2-16S, AFW HDR DISCH Valve CLOSED. (YES)

Verify V2-16C, AFW HDR DISCH Valve CLOSED. (YES)

SOP Verify STEAM LINE PORVs CLOSED. (YES)

SOP Verify V1-8S, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)

Verify V1-8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)

SOP Verify S/Gs "S" and "C" Slowdown and Slowdown Sample Valve Status Light Indication CLOSED. (YES)

Dispatch an operator to the Pipe Jungle to close MS-29 and MS-38, SOP S/G "S" and S/G "C" SYPASS DRN and WARM-UP LINE TO AFW PUMP.

SOP Check S/Gs "S" and "C" MSIV Above and Selow Seat Drain Valves CLOSED. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

6, 7 & 8 Page 26 of 29 Event

Description:

RCP C #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs B and C on the Reactor Trip.

EDG A fails to start on Safety Injection.

Time Position Annlicants Actions or Behavior BOP BOP Dispatch an operator to E-l/E-2 Room to perform the following:

At MCC-9, verify V2-i 4B and V2-i 60 closed and open breakers o

V2-14B, SDAFW PUMP TO SIG B.

o V2-16C, MDAFW PUMP HDR DISCH TO S/G C.

At MCC-6, verify Vi -8B and Vi -8C closed and open breakers o

Vi-8B, SDAFW PUMP STEAM ISOLATION.

o Vi-80, SDAFW PUMP STEAM ISOLATION.

Dispatch operator to the Aux. Bldg. to perform the following:

At MCC-i 0, verify V2-1 6B closed and open breaker V2-1 6B, MDAFW PUMP HEADER DISCHARGE TO SIG B.

At MCC-i 0, verify V2-i 4C closed and open breaker V2-i 4C, SDAFW PUMP TO S/G C.

BOP Check Any S/G ruptured. (NO)

SRO Return to procedure and step in effect.

BOP BOP Check All Faulted and Ruptured S/Gs isolated. (YES)

WHEN the faulted S/Gs dry out, THEN dump steam from intact S/G to control RCS repressurization.

Appendix D NUREG-i 021, Rev. 9, Supp. 1 Appendix D Op Test No.:

~-

Event

Description:

Operator Action Form ES-D-2 Scenario #

1 Event #

_6;;,:,'...;..7...;;&~8~ __ Page 26 of.....:2:;;9 ___

-!1 RCP "C" #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs "B" and "C" on the Reactor Trip.

EDG "A" fails to start on Safety Injection.

Time II Position II Applicant's Actions or Behavior Dispatch an operator to E-1/E-2 Room to perform the following:

At MCC-9, verify V2-14B and V2-16C closed and open breakers 0

V2-14B, SDAFW PUMP TO S/G B.

BOP V2-16C, MDAFW PUMP HDR DISCH TO S/G C.

0 At MCC-6, verify V1-SB and V1-SC closed and open breakers 0

V1-SB, SDAFW PUMP STEAM ISOLATION.

0 V1-SC, SDAFW PUMP STEAM ISOLATION.

Dispatch operator to the Aux. Bldg. to perform the following:

At MCC-10, verify V2-16B closed and open breaker V2-16B, BOP MDAFW PUMP HEADER DISCHARGE TO S/G B.

At MCC-10, verify V2-14C closed and open breaker V2-14C, SDAFW PUMP TO S/G C.

BOP Check All Faulted and Ruptured S/Gs isolated. (YES)

BOP WHEN the faulted S/Gs dry out, THEN dump steam from intact S/G to control RCS repressurization.

BOP Check Any S/G ruptured. (NO)

SRO Return to procedure and step in effect.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

9 & 10 Page 27 of 29 Event

Description:

Loss of Off-Site Power.

SW Pumps fail to start following restoration of power Time II Position ApIicants Actions or Behavior BOOTH OPERATOR:

After SIGs B and C are isolated and at the discretion of the Chief Examiner, insert Events 9 and 10, Loss of Off-Site Power with a failure of SW Pumps to restart.

The crew will continue in PATH-i, but will address components that did NOT restart using Supplement L:

o Service Water Pump C or D to provide EDG cooling.

o RHR Pump B, HVH Units 3 & 4, SI Pump C.

o Charging Pump C started OR FCV-626 opened to provide RCP Seal cooling.

lAW the note in PATH-i, the crew may choose to enter EPP-25, ENERGIZING SUPPLEMENTAL PLANT EQUIPMENT USING THE DSDG and start the DS Diesel following the loss of power.

RO Check Any CCW Pump RUNNING. (YES)

SRO Direct Steps 6 and 7 of EPP-25 be performed to start the DS Diesel.

RO RO BOP RO RO/BOP RO/BOP Supplement L actions Verify Two SI Pumps RUNNING. (NO, will manually start SI Pump C)

Verify Both RHR Pumps RUNNING. (NO, will manually start RHR Pump B)

Verify ALL SW Pumps RUNNING. (NO, will manually start SW Pump C OR Verify CV RECIRC FANS RUNNING. (NO, will manually start HVH-3 and HVH-4)

EPP-25 actions Check Desired Power Source DS Bus. (YES)

Check DS Bus DEENERGIZED. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.:

......;....- Scenario #

1 Event #

.....;9;;...&;;;....;..;1 O~ __ Page 27 of

...;2;;;.;9~ __

--11 Event

Description:

Loss of Off-Site Power.

SW Pumps fail to start following restoration of power.

Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR: After SIGs "B" and "C" are isolated and at the discretion of the Chief Examiner, insert Events 9 and 10, Loss of Off-Site Power with a failure of SW Pumps to restart.

The crew will continue in PATH-1, but will address components that did NOT restart using Supplement L:

a Service Water Pump "C" or "0" to provide EDG cooling.

a RHR Pump "B", HVH Units 3 & 4, SI Pump "C".

a Charging Pump "c" started OR FCV-626 opened to provide RCP Seal cooling.

lAW the note in PATH-1, the crew may choose to enter EPP-25, ENERGIZING SUPPLEMENTAL PLANT EQUIPMENT USING THE DSDG and start the OS Diesel following the loss of power.

Supplement L actions RO Verify Two SI Pumps RUNNING. (NO, will manually start SI Pump "C")

RO Verify Both RHR Pumps RUNNING. (NO, will manually start RHR Pump "B")

BOP Verify ALL SW Pumps RUNNING. (NO, will manually start SW Pump "C" OR "0")

RO Verify CV RECIRC FANS RUNNING. (NO, will manually start HVH-3 and HVH-4)

EPP-25 actions RO/BOP Check Desired Power Source OS Bus. (YES)

RO/BOP Check OS Bus DEENERGIZED. (YES)

RO Check Any CCW Pump RUNNING. (YES)

SRO Direct Steps 6 and 7 of EPP-25 be performed to start the OS Diesel.

Appendix 0 NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

1 Event #

9 & 10 Page 28 of 29 Event

Description:

Loss of Off-Site Power.

SW Pumps fail to start following restoration of power.

Time II Position Arolicants Actions or Behavior CRITICAL TASK:

Manually restart a Service Water Pump to provide cooling to the only running EDG before damaging the EDG.

RO Sf0 PATH-i, Entry Point C Actions Reset SPDS and initiate monitoring of Critical Safety Function Status Trees.

Open Foldout B.

Continuous Action Step:

BOP Check DC Busses A and B energized. (YES)

Once S/Gs B and C have been isolated and a SW pump has been started, the scenario may be terminated.

SRO SRO IF all conditions below occur, THEN Go To EPP-7, SI TERMINATION:

RCS Subcooling > 35 degrees F [55 degrees F]

Heat Sink established as follows:

o Total Feed flow to intact S/Gs> 300 GPM or 0.2x10 6 PPH OR o

Level in at least one intact S/G greater than 8% [18%]

RCS pressure o

Greater than 1650 PSIG [1750 PSIG]

AND o

Stable or Increasing PZR level greater than 10% [32%]

EPP-7 Actions Open Foldout B.

Check SW Header Pressure AND Transition To Step 5.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --

Scenario #

1 Event #

9 & 10 Page 28 of 29

~I Event

Description:

Loss of Off-Site Power.

SW Pumps fail to start following restoration of power.

Time II Position I

Applicant's Actions or Behavior CRITICAL TASK:

Manually restart a Service Water Pump to provide cooling to the only running EDG before damaging the EDG.

PATH-1, Entry Point C Actions RO Reset SPDS and initiate monitoring of Critical Safety Function Status Trees.

SRO Open Foldout B.

IF all conditions below occur, THEN Go To EPP-7, SI TERMINATION:

RCS Subcooling > 35 degrees F [55 degrees F]

Heat Sink established as follows:

0 Total Feed flow to intact S/Gs > 300 GPM or 0.2x106 PPH OR 0

Level in at least one intact S/G greater than 8% [18%]

RCS pressure 0

Greater than 1650 PSIG [1750 PSIG]

AND 0

Stable or Increasing PZR level greater than 10% [32%]

EPP-7 Actions SRO Open Foldout B.

SRO Check SW Header Pressure AND Transition To Step 5.

BOP Continuous Action Step:

Check DC Busses "A" and "B" energized. (YES)

Once SIGs "8" and "C" have been isolated and a SW pump has been started, the scenario may be terminated.

Appendix D NUREG-1021, Rev. 9, Supp. 1

HLC-O8 NRC SCENARIO 1 TURNOVER SHEET POWER LEVEL: 68%, 17,000 MWD/MTU.

Returning to RTP following a short Maintenance Outage.

Awaiting results of post-outage testing.

BORON CONCENTRATION: 106 ppm EQUIPMENT UNDER CLEARANCE:

SW Booster Pump A is Out-Of-Service for Motor Coupling Alignment.

o LCO 3.7.7-A has been entered and is in hour 18 of a 72 TSAS.

o Expected return is within -18 hours.

EQUIPMENT STATUS:

Main Turbine bearings #2, 3 and 4 vibration is elevated. All actions to inform station management have been performed.

INSTRUCTIONS FOR THE WATCH:

Maintain power at 68% RTP.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 HLC-08 NRC SCENARIO 1 TURNOVER SHEET POWER LEVEL: 68%, 17,000 MWD/MTU.

Returning to RTP following a short Maintenance Outage.

Awaiting results of post-outage testing.

BORON CONCENTRATION: 106 ppm EQUIPMENT UNDER CLEARANCE:

SW Booster Pump "A" is Out-Of-Service for Motor Coupling Alignment.

o LCO 3.7.7 -A has been entered and is in hour 18 of a 72 TSAS.

o Expected return is within -18 hours.

EQUIPMENT STATUS:

Main Turbine bearings #2, 3 and 4 vibration is elevated. All actions to inform station management have been performed.

INSTRUCTIONS FOR THE WATCH:

Maintain power at 68% RTP.

Appendix 0 NUREG-1 021, Rev. 9, Supp. 1

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

HB ROBINSON Scenario No.:

3 Op Test No.:

Examiners:

Operators:

SRO RO BOP Initial Conditions:

7% BOL, 150 MWD/MTU, 1645 ppm Boron.

SW Booster Pump A is Out-Of-Service for Motor Coupling Alignment.

o LCO 3.7.7-A has been entered and is in hour 18 of a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action statement.

o Expected return is within 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

Main Turbine Vibration for #2, 3 and 4 bearings is elevated.

Turnover:

Continue with GP-005 to synchronize the Generator to the grid.

Critical Task:

Manually trip the Reactor prior to transitioning out of AOP-001.

Recognize that a SGTR has occurred and isolate the applicable S/G before transitioning to EPP-17.

Event MaIf. No.

Event Type*

Event No.

Description 1

(N) BOP, SRO Place the Generator Voltage Regulator in service.

2 (R) RO Inadvertent Turbine Trip with Power < P-7.

(C) SRO 3

(C) BOP, SRO Service Water Pump A breaker trips on overload.

4 (C) RO Low pressure on SI Accumulator B.

(TS) SRO 5

(M) ALL Multiple dropped rods requiring a Reactor Trip.

6 (M) ALL S/G Tube Rupture on S/G C.

(TS) SRO 7

(C) BOP S/G C Safety fails 15% open.

8 (C) RO Safety Injection Pump C fails to start.

9 (C) BOP S/G Blowdown Sample valves fail to close.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1 021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 Facility:

HB ROBINSON Scenario No.:

3 Op Test No.:

Examiners:

Operators:

SRO -

RO -

BOP-Initial Conditions:

7% BOL, 150 MWD/MTU, 1645 ppm Boron.

SW Booster Pump "A" is Out-Ot-Service tor Motor Coupling Alignment.

0 LCO 3.7.7 -A has been entered and is in hour 18 of a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action statement.

0 Expected return is within -18 hours.

Main Turbine Vibration for #2, 3 and 4 bearings is elevated.

Turnover:

Continue with GP-005 to synchronize the Generator to the grid.

Critical Task:

Manually trip the Reactor prior to transitioning out of AOP-001.

Recognize that a SGTR has occurred and isolate the applicable S/G before transitioning to EPP-17.

Event Malf. No.

Event Type*

Event No.

Description 1

(N) BOP, SRO Place the Generator Voltage Regulator in service.

2 (R) RO Inadvertent Turbine Trip with Power < P-7.

(C) SRO 3

(C) BOP, SRO Service Water Pump "A" breaker trips on overload.

4 (C) RO Low pressure on SI Accumulator "B".

(TS) SRO 5

(M) ALL Multiple dropped rods requiring a Reactor Trip.

6 (M) ALL S/G Tube Rupture on S/G "C".

(TS) SRO 7

(C) BOP S/G "c" Safety fails 15% open.

8 (C) RO Safety Injection Pump "C" fails to start.

9 (C) BOP S/G Blowdown Sample valves fail to close.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 3

SUMMARY

DESCRIPTION The crew will assume the watch with the plant at 7% Reactor Power, with the Turbine rolling at 1800 RPM, but not synchronized to the grid. A Dedicated Operator (Surrogate) required by procedure, will be stationed for S/G level control. The previous shift identified increased vibration on Main Turbine bearing #3 during rollup and has taken all necessary actions to inform station management. Power was stabilized for shift turnover and to obtain vibration data on the Turbine. Service Water Booster Pump A is under clearance for Motor Coupling Alignment.

Shift instructions are to continue with GP-005, POWER OPERATION, to synchronize the Generator to the grid.

The crew will use GP-005 to place the Generator Voltage Regulator in service in preparation to synchronize the Generator to the grid. On cue from the Chief Examiner, the Turbine will inadvertently trip. The crew should respond lAW AOP-007, TURBINE TRIP BELOW P-7, by stabilizing Reactor Power at 3%. During stabilization, the BOP will verify proper operation of the Condenser Steam Dumps. Following plant stabilization the Dedicated Operator will no longer be required and exit the simulator.

On cue from the Chief Examiner, Service Water Pump A breaker will trip on overload. RTGB Annunciator APP-008-F4 will direct the operators to start a standby Service Water Pump. All of the actions will be directed from annunciators received during the Service Water pressure transient.

When Tech Specs are addressed, the Chief Examiner can cue a Low Pressure on SI Accumulator B. The RO will reference APP-002-D4 and take action to repressurize the Accumulator lAW OP-202. The SRO will enter LCO 3.5.1, Condition C for the Low Pressure condition.

On cue from the Chief Examiner, all Control Bank C, Group 2 rods will drop. The SRO should respond by directing a Reactor trip and enter PATH-i. On the Reactor trip, S/G C will develop a 500 gpm tube rupture which will require a Safety Injection.

On the Safety Injection, S/G C Safety Valve will fail 15% open and will not close, SI Pump C will fail to start, requiring the RO to start it manually, and SIG C Blowdown Sample valves will not close as expected.

The Chief Examiner may terminate the scenario at any time after all possible S/G isolation actions have been taken and the crew has transitioned to EPP-i7.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 3

SUMMARY

DESCRIPTION The crew will assume the watch with the plant at 7% Reactor Power, with the Turbine rolling at 1800 RPM, but not synchronized to the grid. A Dedicated Operator (Surrogate) required by procedure, will be stationed for S/G level control. The previous shift identified increased vibration on Main Turbine bearing #3 during rollup and has taken all necessary actions to inform station management. Power was stabilized for shift turnover and to obtain vibration data on the Turbine. Service Water Booster Pump "A" is under clearance for Motor Coupling Alignment.

Shift instructions are to continue with GP-OOS, POWER OPERATION, to synchronize the Generator to the grid.

The crew will use GP-OOS to place the Generator Voltage Regulator in service in preparation to synchronize the Generator to the grid. On cue from the Chief Examiner, the Turbine will inadvertently trip. The crew should respond lAW AOP-007, TURBINE TRIP BELOW P-7, by stabilizing Reactor Power at - 3%. During stabilization, the BOP will verify proper operation of the Condenser Steam Dumps. Following plant stabilization the Dedicated Operator will no longer be required and exit the simulator.

On cue from the Chief Examiner, Service Water Pump "A" breaker will trip on overload. RTGB Annunciator APP-008-F4 will direct the operators to start a standby Service Water Pump. All of the actions will be directed from annunciators received during the Service Water pressure transient.

When Tech Specs are addressed, the Chief Examiner can cue a Low Pressure on SI Accumulator "B". The RO will reference APP-002-D4 and take action to repressurize the Accumulator lAW OP-202. The SRO will enter LCO 3.S.1, Condition C for the Low Pressure condition.

On cue from the Chief Examiner, all Control Bank C, Group 2 rods will drop. The SRO should respond by directing a Reactor trip and enter PATH-1. On the Reactor trip, S/G "C" will develop a SOO gpm tube rupture which will require a Safety Injection. On the Safety Injection, S/G "C" Safety Valve will fail 1S% open and will not close, SI Pump "C" will fail to start, requiring the RO to start it manually, and S/G "C" Blowdown Sample valves will not close as expected.

The Chief Examiner may terminate the scenario at any time after all possible S/G isolation actions have been taken and the crew has transitioned to EPP-17.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Scenario Outline Form ES-D-1 I

HLC-08 NRC SCENARIO 3 SIMULATOR SETUP IC/SETUP:

IC-603, SON 006_Sim_3.

SW Booster Pump A is OFF, breaker OPEN and switch is RED CAPPED.

Main Turbine Bearing #2 is OFFSET by 1.5, #3 by 2.3 and #4 by 1.7.

Status board is correctly marked up for 10-3.

Provide candidates with a marked up (up to Step 8.4) copy of GP-005 to synchronize the Generator to the Grid.

PRE-LOADED EVENTS:

The following events should occur on the reactor trip:

Event 8: SI Pump C fails to start.

Event 9: S/G Blowdown Sample valves fail to close.

EVENTSITRIGGERS INITIATED DURING THE SCENARIO:

Event 2: Inadvertent Turbine Trip with Power < P-7.

Event 3: SW Pump A Breaker trips on overload.

Event 4: Low pressure on SI Accumulator B.

Event 5: Multiple dropped rods requiring a Reactor Trip.

Event 6: S!G Tube Rupture on S/G C.

Event 7: S/G C Safety Valve fails 15% open.

EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

GP-005, Section 8.4; AOP-007; OP-202, Section 8.2.3; AOP-001; PATH-i; Foldout A; Supplement G; EPP-i 1; PATH-2; Foldout C.

Appendix D NUREG-i 021, Rev. 9, Supp. 1 I Appendix 0 Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 3 SIMULATOR SETUP IC/SETUP:

IC-603, SCN 006_Sim_3.

SW Booster Pump "A" is OFF, breaker OPEN and switch is RED CAPPED.

Main Turbine Bearing #2 is OFFSET by 1.5, #3 by 2.3 and #4 by 1.7.

Status board is correctly marked up for IC-3.

Provide candidates with a marked up (up to Step 8.4) copy of GP-005 to synchronize the Generator to the Grid.

PRE-LOADED EVENTS:

The following events should occur on the reactor trip:

Event 8: SI Pump "c" fails to start.

Event 9: S/G Blowdown Sample valves fail to close.

EVENTSITRIGGERS INITIATED DURING THE SCENARIO:

Event 2: Inadvertent Turbine Trip with Power < P-7.

Event 3: SW Pump "A" Breaker trips on overload.

Event 4: Low pressure on SI Accumulator "B".

Event 5: Multiple dropped rods requiring a Reactor Trip.

Event 6: S/G Tube Rupture on S/G "C".

Event 7: S/G "c" Safety Valve fails 15% open.

EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

GP-005, Section 8.4; AOP-007; OP-202, Section 8.2.3; AOP-001; PATH-1; Foldout A; Supplement G; EPP-11; PATH-2; Foldout C.

Appendix 0 NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

1 Page 4

of 27 Event

Description:

Place the Generator VR in service and synchronize the Generator to the grid.

Time II Position II Applicants Actions or Behavior NOTE:

The crew will brief Generator synchronization prior to entering the simulator. They will start with Step 8.4 of GP-005.

SRO BOP BOP BOP Verify TAVG is at the high end of the 547°F to 551°F band and Reactor Power is < 8%.

BOP BOP BOP Inform the Load Dispatcher that the unit will be placed on the grid.

WHEN the turbine is at 1800 rpm, THEN close the Exciter Field Breaker.

Place the Voltage Regulator in service:

Slowly raise Generator volts to 22KV using the Manual Field Current Adjuster.

IF Generator voltage exceeds 22KV and the Exciter Field breaker has not tripped, THEN reduce voltage as soon as possible.

Place the VOLTAGE REGULATOR in the TEST position.

Adjust Regulator Balance to zero using the VOLTAGE ADJUSTER.

Place the VOLTAGE REGULATOR in AUTO.

Place the MAIN GENERATOR synchroscope key switch in the GEN NORTH position.

Adjust the % DIFF VOLTS to zero using the VOLTAGE ADJUSTER.

Adjust Turbine speed so that the synchroscope is rotating SLOWLY in the FAST direction. (Using Reference Setter, sets turbine speed to

...1802 RPM and depresses GO)

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

Scenario #

3 Event #

_____ Page 4

of _2=..:7 ___

"",,1 Event

Description:

Place the Generator VR in service and synchronize the Generator to the grid.

Time I

Position II Applicant's Actions or Behavior NOTE:

The crew will brief Generator synchronization prior to entering the simulator. They will start with Step 8.4 of GP-OOS.

SRO Inform the Load Dispatcher that the unit will be placed on the grid.

BOP WHEN the turbine is at 1800 rpm, THEN close the Exciter Field Breaker.

Place the Voltage Regulator in service:

Slowly raise Generator volts to 22KV using the Manual Field Current Adjuster.

I F Generator voltage exceeds 22KV and the Exciter Field BOP breaker has not tripped, THEN reduce voltage as soon as possible.

Place the VOLTAGE REGULATOR in the TEST position.

Adjust Regulator Balance to zero using the VOLTAGE ADJUSTER.

Place the VOLTAGE REGULATOR in AUTO.

BOP Place the MAIN GENERATOR synchroscope key switch in the GEN NORTH position.

BOP Adjust the % DIFF VOLTS to zero using the VOLTAGE ADJUSTER.

Adjust Turbine speed so that the synchroscope is rotating SLOWL Y in BOP the FAST direction. (Using Reference Setter, sets turbine speed to

-1802 RPM and depresses GO)

BOP Verify TAVG is at the high end of the 547°F to 551°F band and Reactor Power is.:s. 8%.

Appendix D NUREG-1021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

1 Page 5

of 27 Event

Description:

Place the Generator VR in service and synchronize the Generator to the grid.

Time Position II Applicants Actions or Behavior NOTE:

The sequence of actions necessary to synchronize the unit to the grid is TIME CRITICAL. The RO, BOP and FW Operator shall verbally rehearse the actions of the following steps and coordinate their actions while synchronizing to the grid and loading the unit.

NOTE:

Prior to the Generator output breaker being closed, insert Event 2, Inadvertent Turbine trip with Power < P-7.

Synchronize the Main Generator to the grid:

WHEN the synchroscope is rotating SLOWLY in the FAST direction and reaches the 5 minutes to 12 oclock position, THEN close the NORTH OCB BKR 52/9.

IF GLU and GLL remain closed, THEN within 30 seconds adjust Turbine load until GLU and GLL are off their closed seats. (Not to exceed 70 MWe)

BOP IF the Turbine cannot pick up at least 20 MWe, THEN reopen the OCB and inform the SSO and DO NOT CONTINUE.

IF the unit is at 70 MWe and none of the GV closed lights are extinguished, THEN within the next 30 seconds:

o Place Turbine Control in TURB MANUAL and use GV Down to shed load to minimum.

o Verify Reactor Power is < 10%.

o Open the North OCB BKR 52/9.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

.-;..._ Scenario #

3 Event #

Page 5

of 27

~--------

~------~I Event

Description:

Place the Generator VR in service and synchronize the Generator to the grid.

Time I

Position II Applicant's Actions or Behavior NOTE:

The sequence of actions necessary to synchronize the unit to the grid is TIME CRITICAL. The RO, BOP and FW Operator shall verbally rehearse the actions of the following steps and coordinate their actions while synchronizing to the grid and loading the unit.

NOTE:

Prior to the Generator output breaker being closed, insert Event 2, Inadvertent Turbine trip with Power < P-7.

Synchronize the Main Generator to the grid:

WHEN the synchroscope is rotating SLOWLY in the FAST direction and reaches the 5 minutes to 12 o'clock position, THEN close the NORTH OCB BKR 52/9.

IF GLU and GLL remain closed, THEN within 30 seconds adjust Turbine load until GLU and GLL are off their closed seats. (Not to exceed 70 MWe)

BOP IF the Turbine cannot pick up at least 20 MWe, THEN reopen the OCB and inform the SSO and DO NOT CONTINUE.

IF the unit is at 70 MWe and none of the GV closed lights are extinguished, THEN within the next 30 seconds:

0 Place Turbine Control in TURB MANUAL and use GV Down to shed load to minimum.

0 Verify Reactor Power is < 10%.

0 Open the North OCB BKR 52/9.

Appendix D NUREG-1021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

2 Page 6

of 27 Event

Description:

Inadvertent Turbine Trip with power < P-7.

Time Position Applicants Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 2, Inadvertent trip of the Turbine. (Ensure Reactor Power is below P-7)

EVENT INDICATIONS:

APP-008-B1; EH FLUID PMP NB AUTO START APP-008-B2; EH FLUID SYSTEM HI/LO PRESS APP-008-C2; EH FLUID HI/LO-LO LEVEL APP-009-E2; GOV CAB MONITOR TROUBLE Turbine speed is decreasing and all Turbine valves indicate closed.

SRO Enters AOP-007, TURBINE TRIP BELOW P-7.

Check Turbine trip as follows:

Both Turbine Stop Valves closed (YES)

BOP OR All Governor Valves Closed (YES)

RO/BOP Make PA announcement for AOP-007 entry.

Check Reactor Power less than 3%. (NO)

RO Manually insert control rods or borate to reduce reactor power less than 3%.

Check Turbine Oil system status:

Turbine Bearing Oil Pressure> 6 psig. (YES)

BOP Turning Gear and Seal Oil Backup pumps running. (NO)

IF the Lube Oil system is intact, THEN start the Turning Gear and Seal Oil Backup pumps. (Will start Pumps using Manual switch)

NOTE:

The crew will declare MODE 2 after going below 5% Reactor Power.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

-.;...- Scenario #

3 Event #

2 Page 6

of 27

~------~I Event

Description:

Inadvertent Turbine Trip with power < P-7.

Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 2, Inadvertent trip of the Turbine. (Ensure Reactor Power is below P-7)

EVENT INDICATIONS:

APP-008-B1; EH FLUID PMP AlB AUTO START APP-008-B2; EH FLUID SYSTEM HIILO PRESS APP-008-C2; EH FLUID HI/LO-LO LEVEL APP-009-E2; GOV CAB MONITOR TROUBLE Turbine speed is decreasing and all Turbine valves indicate closed.

SRO Enters AOP-007, TURBINE TRIP BELOW P-7.

Check Turbine trip as follows:

Both Turbine Stop Valves closed (YES)

BOP OR All Governor Valves Closed (YES)

RO/BOP Make PA announcement for AOP-007 entry.

Check Reactor Power less than 3%. (NO)

RO Manually insert control rods or borate to reduce reactor power less than 3%.

NOTE:

The crew will declare MODE 2 after going below 5% Reactor Power.

Check Turbine Oil system status:

Turbine Bearing Oil Pressure> 6 psig. (YES)

BOP Turning Gear and Seal Oil Backup pumps running. (NO)

IF the Lube Oil system is intact, THEN start the Turning Gear and Seal Oil Backup pumps. (Will start Pumps using Manual switch)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

2 Page 7

of 27 Event

Description:

Inadvertent Turbine Trip with power < P-7.

Time Position I

Applicants Actions or Behavior Continuous Action Step:

Verify Bearing Oil Lift Pump running:

BOP Check TurbIne Speed < 600 RPM. (NO)

WHEN Turbine Speed is < 600 RPM, THEN verify Bearing Oil Lift Pump is running.

Check North OCB BKR 52/9, South OCB BKR 52/8 and Exciter Field Breaker tripped. (NO, Exciter Field Breaker is still CLOSED)

BOP IF the Exciter Field Breaker has NOT tripped, THEN momentarily place the control switch in TRIP.

Check TAvG 547 °F to 551 °F.

(NO) IF Steam Dumps are available THEN:

Adjust PC-464B to maintain 547-551 °F.

RO/BOP Verify Steam Dump Control switch is ON.

Verify Steam Dump Mode switch in Steam Press.

(YES) Continue with Step 8.

BOP Check 1 Main Condensate Pump AND 1 Feed Pump running. (YES)

BOP Maintain S/G levels 35 to 44% using FRV Bypass Valves.

Check PZR pressure between 2220 and 2250 PSIG. (YES)

RO IF pressure is < 2220, THEN Control Heaters and Spray valves to restore pressure to between 2220-2250.

RO Control Charging and Letdown to maintain PZR level 22%.

Determine if the Reactor should be shutdown:

SRO Check Reactor Power stable. (YES)

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -- Scenario #

3 Event #

2 Page 7

of 27

~---~I Event

Description:

Inadvertent Turbine Trip with power < P-7.

Time

~

Position I

Applicant's Actions or Behavior Continuous Action Step:

Verify Bearing Oil Lift Pump running:

BOP Check Turbine Speed < 600 RPM. (NO)

WHEN Turbine Speed is < 600 RPM, THEN verify Bearing Oil Lift Pump is running.

Check North OCB BKR 52/9, South OCB BKR 52/8 and Exciter Field BOP Breaker tripped. (NO, Exciter Field Breaker is still CLOSED)

IF the Exciter Field Breaker has NOT tripped, THEN momentarily place the control switch in TRIP.

Check TAVG 547 of to 551°F.

(NO) IF Steam Dumps are available THEN:

Adjust PC-464B to maintain 547-551 of.

RO/BOP

Verify Steam Dump Control switch is ON.

Verify Steam Dump Mode switch in Steam Press.

(YES) Continue with Step 8.

BOP Check 1 Main Condensate Pump AND 1 Feed Pump running. (YES)

BOP Maintain S/G levels 35 to 44% using FRV Bypass Valves.

Check PZR pressure between 2220 and 2250 PSIG. (YES)

RO IF pressure is < 2220, THEN Control Heaters and Spray valves to restore pressure to between 2220-2250.

RO Control Charging and Letdown to maintain PZR level -22%.

Determine if the Reactor should be shutdown:

SRO Check Reactor Power stable. (YES)

Appendix D NUREG-1021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

3 Page 8

of 27 Event

Description:

SW Pump A trip.

I Applicants Actions or Behavior Time II Position BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 3, Service Water Pump A trips on breaker overload.

EVENT INDICATIONS:

APP-008-F4; SW PMP AIBICID OVLD APP-008-F7; SOUTH SW HDR LO PRESS APP-008-F8; NORTH SW HDR LO PRESS APP-002-A8/B8/C81D8; HVH-1121314 WTR OUTLET LO FLOW RO/BOP Recognizes SW Pump A has tripped and references APP-008-F4.

APP-008-F4 actions:

If an operating SW Pump has tripped, perform the following:

o Start a standby pump. (Will start SW Pump B or D)

BOP o

Dispatch an operator to check breaker and current limiter fuses for SW Pump A 480V Bus E-1, CMPT 20B.

o Throttle CCW Heat Exchanger return valves to maintain header pressure at 40 50 psig.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

....;...- Scenario #

3 Event #

3 Page 8

of 27

~--------

~------~I Event

Description:

SW Pump "A" trip.

Time II Position I

Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 3, Service Water Pump "A" trips on breaker overload.

EVENT INDICATIONS:

APP-OOS-F4; SW PMP AlB/C/D OVLD APP-OOS-F7; SOUTH SW HDR LO PRESS APP-OOS-FS; NORTH SW HDR LO PRESS APP-002-AS/BS/CS/DS; HVH-1/2/3/4 WTR OUTLET LO FLOW ROISOP Recognizes SW Pump "A" has tripped and references APP-008-F4.

APP-008-F4 actions:

If an operating SW Pump has tripped, perform the following:

0 Start a standby pump. (Will start SW Pump "S" or "D")

SOP Dispatch an operator to check breaker and current limiter fuses 0

for SW Pump A - 480V Sus E-1, CMPT 20S.

0 Throttle CCW Heat Exchanger return valves to maintain header pressure at 40 - 50 psig.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

4 Page 9

of 27 Event

Description:

Low pressure on SI Accumulator B.

Time Position Applicants Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 4, Low pressure on SI Accumulator B.

EVENT INDICATIONS:

APP-002-D4; SI ACCUM B HI/LO PRESS Decreasing Accumulator B pressure RO Recognizes that SI Accumulator B pressure is decreasing slowly and references APP-002-D4.

Reviews, briefs and directs Accumulator repressurization using OP SRO 202, SAFETY INJECTION AND CONTAINMENT VESSEL SPRAY SYSTEM, Section 8.2.3.

RO Verify HIC-936, ACC VENT HDR FLOW CLOSED. (YES)

RO Verify SI-855, ACC NITROGEN ISOLATION OPEN. (YES)

RO OPEN Sl-853B, VENT.

RO WHEN the desired pressure is obtained, (Normal operating pressure is 630 PSIG) THEN close SI-853B. (APP-002-D4 will clear)

Review ITS for applicable LCOs:

SRO LCO 3.5.1 Condition C; Restore Accumulator to OPERABLE within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

Scenario #

3 Event #

4 Page 9

of 27

~I Event

Description:

Low pressure on SI Accumulator "B".

Time II Position

~

Applicant's Actions or Behavior 800TH OPERATOR: When directed by the Chief Examiner, insert Event 4, Low pressure on SI Accumulator "8".

EVENT INDICATIONS:

APP-002-D4; SI ACCUM B HI/LO PRESS Decreasing Accumulator B pressure RO Recognizes that SI Accumulator "B" pressure is decreasing slowly and references APP-002-D4.

Reviews, briefs and directs Accumulator repressurization using OP-SRO 202, SAFETY INJECTION AND CONTAINMENT VESSEL SPRAY SYSTEM, Section 8.2.3.

RO Verify HIC-936, ACC VENT HDR FLOW CLOSED. (YES)

RO Verify SI-855, ACC NITROGEN ISOLATION OPEN. (YES)

RO OPEN SI-853B, VENT.

RO WHEN the desired pressure is obtained, (Normal operating pressure is 630 PSIG) THEN close SI-853B. (APP-002-D4 will clear)

Review ITS for applicable LCOs:

SRO LCO 3.5.1 - Condition C; Restore Accumulator to OPERABLE within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

5, 6 Page 10 of 27 Event

Description:

Multiple dropped rods requiring a Reactor Trip.

S!G Tube Rupture on S/G C.

Time Position Applicants Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 5, Multiple dropped rods. When the reactor has been tripped, verify that Event 6, SIG C Tube Rupture has been entered.

EVENT INDICATIONS:

APP-005-F2; ROD BOTTOM ROD DROP RBLs for Control Bank C, Group 2 are LIT Decreasing SUR Decreasing power.

RO Recognizes multiple dropped rods and performs Immediate actions of AOP-O01, MALFUNCTION OF REACTOR CONTROL SYSTEM.

RO Check unexpected rod motion in progress. (NO)

RO/BOP Make PA Announcement for entry into AOP-0O1.

Determine if multiple rods have dropped:

RO Prompt drop present. (YES)

More than 1 RBL illuminated. (YES)

More than 1 IRPI indicates on bottom. (YES)

RO Check multiple dropped rods present. (YES)

RO Check Reactor in MODE 1 or 2. (YES)

SRO Directs tripping the reactor and enters PATH-i.

IMMEDIATE ACTION STEP:

RO Reactor Tripped (YES)

Appendix D NUREG-i 021, Rev. 9, Supp. 1 Appendix D Op Test No.:

~-

Event

Description:

Operator Action Form ES-D-2 Scenario #

3 Event #

5,6 Page 10 of 27

~~------

~----~I Multiple dropped rods requiring a Reactor Trip.

S/G Tube Rupture on S/G "C n

Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 5, Multiple dropped rods. When the reactor has been tripped, verify that Event 6, SIG "C" Tube Rupture has been entered.

EVENT INDICATIONS:

APP-005-F2; ROD BOTTOM ROD DROP RBLs for Control Bank C, Group 2 are LIT Decreasing SUR Decreasing power.

RO Recognizes multiple dropped rods and performs Immediate actions of AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM.

RO Check unexpected rod motion in progress. (NO)

RO/BOP Make PA Announcement for entry into AOP-001.

Determine if multiple rods have dropped:

Prompt drop present. (YES)

RO More than 1 RBL illuminated. (YES)

More than 1 IRPI indicates on bottom. (YES)

RO Check multiple dropped rods present. (YES)

RO Check Reactor in MODE 1 or 2. (YES)

SRO Directs tripping the reactor and enters PATH-1.

IMMEDIATE ACTION STEP:

RO Reactor Tripped. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

5, 6 Page 11 of 27 Event

Description:

Multiple dropped rods requiring a Reactor Trip.

S/G Tube Rupture on SIG C.

Time I

Position Applicants Actions or Behavior BOP BOP RO IMMEDIATE ACTION STEP:

Turbine Tripped. (YES)

IMMEDIATE ACTION STEP:

SI Initiated. (NO)

SI Initiation required. (NO)

CRITICAL TASK:

Manually trip the Reactor prior to transitioning out of AOP-OO1.

IMMEDIATE ACTION STEP:

E-i AND E-2 energized. (YES)

RO Verify two Charging Pumps running.

SRO Transition to EPP-4, REACTOR TRIP RESPONSE.

Continuous Action Step:

Determine if procedure exit is warranted:

SRO Check attack on RNP site in progress. (NO)

Check a total loss of SW OR Loss of Lake Robinson Dam integrity in progress._(NO, Go to Step_2)

Continuous Action Step:

RO Check SI signal initiated. (NO, Go to Step 4)

IF SI initiation occurs during this procedure, THEN Go to PATH-i, Entry Point A.

Appendix D NUREG-i021, Rev. 9, Supp. i Appendix D Op Test No.:

~-

Event

Description:

Operator Action Form ES-D-2 Scenario #

3 Event #

_5;;.:"...;.6 ____ Page 11 of _2:;.;7 ___

--11 Multiple dropped rods requiring a Reactor Trip.

S/G Tube Rupture on S/G "C".

Time II Position II Applicant's Actions or Behavior IMMEDIATE ACTION STEP:

BOP Turbine Tripped. (YES)

IMMEDIATE ACTION STEP:

BOP E-1 AND E-2 energized. (YES)

IMMEDIATE ACTION STEP:

RO SI Initiated. (NO)

SI Initiation required. (NO)

CRITICAL TASK:

Manually trip the Reactor prior to transitioning out of AOP-001.

RO Verify two Charging Pumps running.

SRO Transition to EPP-4, REACTOR TRIP RESPONSE.

Continuous Action Step:

Determine if procedure exit is warranted:

SRO

Check attack on RNP site in progress. (NO)

Check a total loss of SW ORLoss of Lake Robinson Dam integrity in progress. (NO, Go to Step 2)

Continuous Action Step:

RO Check SI signal initiated. (NO, Go to Step 4)

IF SI initiation occurs during this procedure, THEN Go to PATH-1, Entry Point A.

Appendix D NUREG-1021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

5, 6 Page 12 of 27 Event

Description:

Multiple dropped rods requiring a Reactor Trip.

S/G Tube Rupture on SIG C.

Time II Position II Arlicants Actions or Behavior SRO CREW Reset SPDS and initiate monitoring of CSFSTs.

Open Foldout A.

RCP Trip criteria, IF BOTH conditions are met, THEN stop all RCPs: (NO)

RO o

SI Pumps

- AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE o

RCS Subcooling

- < 35 degrees F [55 degrees F]

SI actuation criteria. IF EITHER condition occurs, THEN Actuate SI and Go To PATH-i, Entry Point A: (YES)

SRO/RO o

RCS Subcooling

- < 35 degrees F [55 degrees F]

o PZR Level

- CAN NOT BE MAINTAINED> 10% [32%].

MSR Isolation criteria. IF ANY Purge OR Shutoff Valve does BOP not indicate fully closed, THEN place the associated RTGB Switch to CLOSE.

SRO Direct a manual SI and Transition to PATH-i, Entry Point A.

Appendix D NUREG-i 021, Rev. 9, Supp. 1 Appendix D Op Test No.:

Event

Description:

Operator Action Form ES-D-2 Scenario #

3 Event #

_5;.:,.,...;;,6 ____ Page 12 of...;2:;;.:7 ___

---11 Multiple dropped rods requiring a Reactor Trip.

S/G Tube Rupture on S/G "e".

Time II Position II Applicant's Actions or Behavior SRO Reset SPDS and initiate monitoring of CSFSTs.

CREW Open Foldout A.

RCP Trip criteria. IF BOTH conditions are met, THEN stop all RCPs: (NO)

RO 0

SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 0

RCS Subcooling - < 35 degrees F [55 degrees F]

SI actuation criteria. IF EITHER condition occurs, THEN Actuate SI and Go To PATH-1, Entry Point A: (YES)

SRO/RO RCS Subcooling - < 35 degrees F [55 degrees F]

0 0

PZR Level-CAN NOT BE MAINTAINED> 10% [32%].

MSR Isolation criteria. IF ANY Purge OR Shutoff Valve does BOP not indicate fully closed, THEN place the associated RTGB Switch to CLOSE.

SRO Direct a manual SI and Transition to PATH-1, Entry Point A.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

7, 8, & 9 Page 13 of 27 Event

Description:

Sf0 C Safety Valve fails open. Safety Injection Pump C fails to start.

5/0 Blowdown Sample valves fail to close.

Time Position Applicants Actions or Behavior BOOTH OPERATOR:

When the crew actuates Safety Injection, verify Events 7, 8 and 9 are inserted.

NOTE:

When radiation alarm R-19C is received, the CRSS may direct a member of the crew to take actions lAW AOP-005, RADIATION MONITORING SYSTEM.

The actions taken lAW AOP-005 are listed on Page 26 at the back of the exercise guide.

PATH-i actions continue below.

CREW Open Foldout A. (nothing additional to address)

RO Verify Phase A Isolation valves are closed. (NO, crew will direct local isolation of FCV-1 935NB, S/G Blowdown Sample valves)

BOP Verify FW Isolation valves are closed. (YES)

BOP Verify both FW pumps are tripped. (YES)

BOP Verify both MDAFW pumps are running. (YES)

BOP If additional Feedwater is required, start the SDAFW pump.

RD Verify 2 SI pumps running. (NO, C will be manually started)

RO Verify Both RHR pumps running. (YES)

RO Verify SI valves are properly aligned. (YES)

RD At least 1 CCW pump is running. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Op Test No.:

~-

Event

Description:

Operator Action Form ES-D-2 Scenario #

3 Event #

_7~'...;;.8~,

&;.;...9~ __ Page 13 of.....:2:..;.7 ___

-11 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start.

S/G Blowdown Sample valves fail to close.

Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR: When the crew actuates Safety Injection, verify Events 7,8 and 9 are inserted.

NOTE:

When radiation alarm R-19C is received, the CRSS may direct a member of the crew to take actions lAW AOP-005, RADIATION MONITORING SYSTEM.

The actions taken lAW AOP-005 are listed on Page 26 at the back of the exercise guide.

PATH-1 actions continue below.

CREW Open Foldout A. (nothing additional to address)

RO Verify Phase A Isolation valves are closed. (NO, crew will direct local isolation of FCV -1935A1B, S/G Blowdown Sample valves)

BOP Verify FW Isolation valves are closed. (YES)

BOP Verify both FW pumps are tripped. (YES)

BOP Verify both MDAFW pumps are running. (YES)

BOP If additional Feedwater is required, start the SDAFW pump.

RO Verify 2 SI pumps running. (NO, "c" will be manually started)

RO Verify Both RHR pumps running. (YES)

RO Verify SI valves are properly aligned. (YES)

RO At least 1 CCW pump is running. (YES)

Appendix 0 NUREG-1 021, Rev. 9, Supp. 1

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

Event

Description:

Time II BOP All SW and SW Booster pumps running. (NO)

BOP Attempt to start all SW and SW booster pumps. (NO, SW Booster Pump A is unavailable and SW Pump A is tripped)

BOP North OR South SW Header Lo Pressure alarm illuminated. (NO)

RO Verify CV Fans HVH-1, 2, 3, 4 running. (YES)

RO Verify IVSW System Initiated. (YES)

RO Verify CV Ventilation isolation. (YES)

BOP Verify Control Room Vent aligned for Pressurization Mode. (YES)

BOP Verify both EDGs running. (YES)

CONTINUOUS ACTION STEP:

BOP Restart battery chargers within 30 minutes of power loss using OP 601.

CONTINUOUS ACTION STEP:

RO CV Pressure has remained below 10 psig. (YES)

RO Automatic Steam Line Isolation initiated. (NO)

RO Automatic Steam Line Isolation required. (NO)

Scenario #

3 Event #

7, 8, & 9 Page 14 of 27 S!G c Safety Valve fails open. Safety Injection Pump C fails to start.

S!G Blowdown Sample valves fail to close.

Position Applicants Actions or Behavior Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix 0 Op Test No.:

Event

Description:

Operator Action Form ES-D-2 Scenario #

3 Event #

7,8,&9 Page 14 of 27

~~~----

~------~I S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start.

S/G Blowdown Sample valves fail to close.

Time II Position i

Applicant's Actions or Behavior BOP All SW and SW Booster pumps running. (NO)

BOP Attempt to start all SW and SW booster pumps. (NO, SW Booster Pump "A" is unavailable and SW Pump "A" is tripped)

BOP North OR South SW Header Lo Pressure alarm illuminated. (NO)

RO Verify CV Fans HVH-1, 2, 3, 4 running. (YES)

RO Verify IVSW System Initiated. (YES)

RO Verify CV Ventilation isolation. (YES)

BOP Verify Control Room Vent aligned for Pressurization Mode. (YES)

BOP Verify both EDGs running. (YES)

CONTINUOUS ACTION STEP:

BOP Restart battery chargers within 30 minutes of power loss using OP-601.

CONTINUOUS ACTION STEP:

RO CV Pressure has remained below 10 psig. (YES)

RO Automatic Steam Line Isolation initiated. (NO)

RO Automatic Steam Line Isolation required. (NO)

Appendix 0 NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

7, 8, & 9 Page 15 of 27 Event

Description:

SIG C Safety Valve fails open. Safety Injection Pump C fails to start.

SIG Blowdown Sample valves fail to close.

Time Position Applicants Actions or Behavior SRO Locally open breaker for HVS-1 at MCC-5.

P0 RCS pressure> 1350 psig. [1250 psig] (YES)

BOP At least 300 GPM AFW flow available. (YES)

BOP Verify AFW valves properly aligned.

BOP Control AFW flow to maintain SIG levels between 8% [18%] and 50%.

RO RCP Thermal barrier cooling water Hi/Lo flow alarms illuminated. (NO)

BOP Place Steam Dump Mode Switch to Steam Pressure.

RO RCS Temp stable at OR trending to 547 degrees F. (NO)

P0 RCS temperature> 547 degrees F. (NO)

RO Attempt to limit cooldown.

RO If RCS cooldown continues and is not due to SI flow, then close MSIVs and MSIV bypasses.

P0 PZR PORVs closed. (YES)

RO PZR Spray and Aux Spray valves closed. (YES)

P0 At least 1 RCP running. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.:

Event

Description:

Operator Action Form ES-D-2 Scenario #

3 Event #

_7;":"..;;.8:..;' &;.;..9~ __ Page 15 of....;2:.;,.7 ___

-i1 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start.

S/G Blowdown Sample valves fail to close.

Time II Position II Applicant's Actions or Behavior SRO locally open breaker for HVS-1 at MCC-5.

RO RCS pressure> 1350 psig. [1250 psig] (YES)

BOP At least 300 GPM AFW flow available. (YES)

BOP Verify AFW valves properly aligned.

BOP Control AFW flow to maintain S/G levels between 8% [18%] and 50%.

RO RCP Thermal barrier cooling water Hillo flow alarms illuminated. (NO)

BOP Place Steam Dump Mode Switch to Steam Pressure.

RO RCS Temp stable at OR trending to 547 degrees F. (NO)

RO RCS temperature> 547 degrees F. (NO)

RO Attempt to limit cooldown.

RO If RCS cooldown continues and is not due to SI flow, then close MSIVs and MSIV bypasses.

RO PZR PORVs closed. (YES)

RO PZR Spray and Aux Spray valves closed. (YES)

RO At least 1 RCP running. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

7, 8, & 9 Page 16 of 27 Event

Description:

SIG C Safety Valve fails open. Safety Injection Pump C fails to start.

SIG Blowdown Sample valves fail to close.

Time Position Applicants Actions or Behavior RD At least 1 SI Pump Running. (YES)

RO RCS Subcooling less than 35 degrees F [55]. (NO)

BOP Any S/G with uncontrolled depressurization. (YES)

RD Reset SPDS and initiate monitoring of CSFSTs.

SRO Transition to EPP-11, FAULTED SIG ISOLATION.

BOP Maintain At Least One S/G Available For RCS Cooldown.

BOP Any SIG pressure stable or increasing. (YES)

BOP Any S/G pressure decreasing in an uncontrolled manner OR any S/G completely depressurized. (YES)

BOP Isolate faulted S/G using Supplement G, S/G ISOLATION.

(Supplement G Steps are listed on Pages 22-25)

BOP Maintain A Faulted SIG In The Isolated Condition During Subsequent Recovery Actions Unless Needed For Cooldown.

BOP Check CST level greater than 10%. (YES)

BOP Check Available Secondary Radiation Monitors normal. (NO)

SRO Transition to PATH-2, Entry Point J.

RO Reset SPDS and initiate monitoring of CSFSTs.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --

Event

Description:

Operator Action Form ES-D-2 Scenario #

3 Event #

_7;..:.,...;;.8:..;,

&;;...;9~ __ Page 16 of.....;2;;.;.7 ___

-11 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start.

S/G Slowdown Sample valves fail to close.

Time II Position II Applicant's Actions or Behavior RO At least 1 SI Pump Running. (YES)

RO RCS Subcooling less than 35 degrees F [55]. (NO)

BOP Any S/G with uncontrolled depressurization. (YES)

RO Reset SPDS and initiate monitoring of CSFSTs.

SRO Transition to EPP-11, FAULTED SIG ISOLATION.

BOP Maintain At Least One S/G Available For RCS Cooldown.

BOP Any S/G pressure stable or increasing. (YES)

BOP Any S/G pressure decreasing in an uncontrolled manner OR any S/G completely depressurized. (YES)

BOP Isolate faulted S/G using Supplement G, S/G ISOLATION.

(Supplement G Steps are listed on Pages 22-25)

BOP Maintain A Faulted S/G In The Isolated Condition During Subsequent Recovery Actions Unless Needed For Cooldown.

BOP Check CST level greater than 10%. (YES)

BOP Check Available Secondary Radiation Monitors normal. (NO)

SRO Transition to PATH-2, Entry Point J.

RO Reset SPDS and initiate monitoring of CSFSTs.

Appendix D NUREG-1021, Rev. 9, Supp. 1

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

Event

Description:

CREW Open Foldout C.

RO WHEN below 10b0 amps, THEN energize Source Range detectors and monitor recorder.

BOP Request periodic activity samples of all S/Gs BOP Place Steam Dump Mode Switch to Steam Pressure.

BOP Open QCV-1 0426, Bypass Condensate Polishers.

BOP Close C-48A and 48B to isolate Hotwell Return to CST.

RO At Least 1 RCP running. (YES)

RO At Least 1 SI pump running. (YES)

P0 RCS Subcooling less than 35 degrees F. [55] (NO)

BOP Ruptured SIG identified. (YES)

RD Maintain at least 1 SIG available for RCS Cooldown.

BOP Verify ruptured steam line PORV setpoint at 1035 psig using status board.

P0 Verify RCS temperature < 547 degrees F prior to MSIV closure.

Time Scenario #

3 Event #

7, 8, & 9 Page 17 of 27 SIG c Safety Valve fails open. Safety Injection Pump c fails to start.

SIG Blowdown Sample valves fail to close.

Position Applicants Actions or Behavior Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.:

~-

Event

Description:

Operator Action Form ES-D-2 Scenario #

3 Event #

_7;...l"...;,8...,;, &;;;..9~__ Page 17 of _2;;.;7 ___

l1 S/G "c" Safety Valve fails open. Safety Injection Pump "c" fails to start.

S/G Blowdown Sample valves fail to close.

Time II Position II Applicant's Actions or Behavior CREW Open Foldout C.

RO WHEN below 10-10 amps, THEN energize Source Range detectors and monitor recorder.

BOP Request periodic activity samples of all S/Gs BOP Place Steam Dump Mode Switch to Steam Pressure.

BOP Open QCV -10426, Bypass Condensate Polishers.

BOP Close C-48A and 48B to isolate Hotwell Return to CST.

RO At Least 1 RCP running. (YES)

RO At Least 1 SI pump running. (YES)

RO RCS Subcooling less than 35 degrees F. [55] (NO)

BOP Ruptured S/G identified. (YES)

RO Maintain at least 1 S/G available for RCS Cooldown.

BOP Verify ruptured steam line PORV setpoint at 1035 psig using status board.

RO I Verify RCS temperature < 547 degrees F prior to MSIV closure.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

7, 8, & 9 Page 18 of 27 Event

Description:

S/G C Safety Valve fails open. Safety Injection Pump C fails to start.

S/G Blowdown Sample valves fail to close.

Time Position Applicants Actions or Behavior RD Close ruptured S/G MSIV and MSIV Bypass.

RO Ruptured S/G MSIV and MSIV bypass closed. (YES)

Continuous Action Step:

RD WHEN ruptured S/G pressure decreases below 1035 psig, THEN verify ruptured Steam Line PORV closed.

RD IF MDAFW pump is not available, THEN maintain at least 1 S/G supply to SDAFW pump.

CREW Close ruptured SIG steam shutoff to SDAFW pump.

BOP Verify S/G Blowdown Isolation and Sample Valves Closed.

BOP Locally close warmup steam supply from ruptured S/G to SDAFW pump.

BOP Locally close above and below seat drains from ruptured S/G.

Isolate Feed Flow to any ruptured SIG that is faulted unless needed BOP for RCS cooldown.

Recognize that a Steam Generator Tube Rupture has occurred and isolate the affected SIG before transitioning to EPP-17.

CRITICAL TASK:

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Op Test No.: --

Event

Description:

Operator Action Form ES-D-2 Scenario #

3 Event #

7,8,&9 Page 18 of 27

~~~----

~I S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start.

S/G Blowdown Sample valves fail to close.

Time

~

Position II Applicant's Actions or Behavior RO Close ruptured S/G MSIV and MSIV Bypass.

RO Ruptured S/G MSIV and MSIV bypass closed. (YES)

Continuous Action Step:

RO WHEN ruptured S/G pressure decreases below 1035 psig, THEN verify ruptured Steam Line PORV closed.

RO IF MDAFW pump is not available, THEN maintain at least 1 S/G supply to SDAFW pump.

CREW Close ruptured S/G steam shutoff to SDAFW pump.

BOP Verify S/G Blowdown Isolation and Sample Valves Closed.

BOP Locally close warmup steam supply from ruptured S/G to SDAFW pump.

BOP Locally close above and below seat drains from ruptured S/G.

BOP Isolate Feed Flow to any ruptured S/G that is faulted unless needed for RCS cooldown.

CRITICAL TASK:

Recognize that a Steam Generator Tube Rupture has occurred and isolate the affected SIG before transitioning to EPP-17.

Appendix 0 NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

7, 8, & 9 Page 19 of 27 Event

Description:

S/G C Safety Valve fails open. Safety Injection Pump C fails to start.

S/G Blowdown Sample valves fail to close.

Time II Position II ApIicants Actions or Behavior Continuous Action Step:

BOP WHEN ruptured S/G level is greater than 8% [18%], THEN isolate Feed Flow.

Continuous Action Step:

BOP Open breakers for Vi -8, V2-1 4 and V2-1 6 valve closed to isolate ruptured SIG.

BOP Control Feed Flow to maintain intact S/G level between 8% [18%] and BOP Any other SIG with uncontrolled level increase. (NO)

RO PZR PORVs closed. (YES)

RO Open at least one PORV block unless closed to isolate an open PORV.

RO IF PORV opens on high pressure, THEN verify reclosure at or below 2335 PSIG, close PORV blocks as necessary.

AC Reset SI.

CREW IF offsite power is lost, THEN restart emergency safeguards equipment.

AO Reset CV Spray.

RO Reset Phase A and Phase B.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Op Test No.:

Event

Description:

Operator Action Form ES-O-2 Scenario #

3 Event #

_7;":"...;.8':...;&;.;..;9~ __ Page 19 of _2;;;.;7 ___

--11 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start.

S/G Blowdown Sample valves fail to close.

Time II Position II Applicant's Actions or Behavior Continuous Action Step:

BOP WHEN ruptured S/G level is greater than 8% [18%], THEN isolate Feed Flow.

Continuous Action Step:

BOP Open breakers for V1-8, V2-14 and V2-16 valve closed to isolate ruptured S/G.

BOP Control Feed Flow to maintain intact S/G level between 8% [18%] and 50%.

BOP Any other S/G with uncontrolled level increase. (NO)

RO PZR PORVs closed. (YES)

RO Open at least one PORV block unless closed to isolate an open PORV.

RO IF PORV opens on high pressure, THEN verify reclosure at or below 2335 PSIG, close PORV blocks as necessary.

RO Reset SI.

CREW IF offsite power is lost, THEN restart emergency safeguards equipment.

RO Reset CV Spray.

RO Reset Phase A and Phase B.

Appendix 0 NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

7, 8, & 9 Page 20 of 27 Event

Description:

S/G C Safety Valve fails open. Safety Injection Pump C fails to start.

S/G Blowdown Sample valves fail to close.

Time Position Applicants Actions or Behavior RO Establish Instrument Air to CV. IF compressor NOT running

, THEN start compressor.

BOP All AC Busses energized by offsite power. (YES)

RO IF RCS pressure decreases below 275 PSG, THEN restart RHR Pumps.

BOP Ruptured S/G isolated. (YES, completed during Supplement G)

BOP Ruptured S/G pressure> 220 PSIG. (YES)

BOP At least one intact S/G available for RCS cooldown. (YES)

Sf0 Determine required core exit temperature from Table 3.

RO WHEN PZR press decreases to < 2000 PSIG, THEN block PZR Pressure/Hi Steam Line SI signals.

RO IF RCPs are NOT running, THEN do NOT monitor CSF-4.

BOP Condenser available for Steam Dump. (YES)

RO Verify TAVG < 543 degrees F AND block TAvG SI signal prior to maximum steam dump.

BOP Dump steam from intact S/G to condenser at maximum rate.

RO Align Charging Pump suction to RWST.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

-.;..._ Scenario #

3 Event #

7,8, & 9 Page 20 of 27

~~~----

~------~I Event

Description:

S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start.

S/G Blowdown Sample valves fail to close.

Time

~

Position II Applicant's Actions or Behavior RO Establish Instrument Air to CV. IF compressor NOT running, THEN start compressor.

BOP All AC Busses energized by offsite power. (YES)

RO IF RCS pressure decreases below 275 PSIG, THEN restart RHR Pumps.

BOP Ruptured S/G isolated. (YES, completed during Supplement G)

BOP Ruptured S/G pressure> 220 PSIG. (YES)

BOP At least one intact S/G available for RCS cooldown. (YES)

SRO Determine required core exit temperature from Table 3.

RO WHEN PZR press decreases to < 2000 PSIG, THEN block PZR Pressure/Hi Steam Line SI signals.

RO IF RCPs are NOT running, THEN do NOT monitor CSF-4.

BOP Condenser available for Steam Dump. (YES)

RO Verify TAVG < 543 degrees F AND block TAVG SI signal prior to maximum steam dump.

BOP Dump steam from intact S/G to condenser at maximum rate.

RO Align Charging Pump suction to RWST.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

7, 8, & 9 Page 21 of 27 Event

Description:

SIG C Safety Valve fails open. Safety Injection Pump C fails to start.

SIG Blowdown Sample valves fail to close.

Time Position Applicants Actions or Behavior RO Establish Charging flow to maintain PZR level.

RO Core Exit Temperature less than required temperature. (YES)

BOP Reduce Steam flow to stabilize RCS temperature.

CREW Allow RCS temperature to stabilize from cooldown prior to continuing.

BOP Ruptured SIG pressure stable or increasing. (NO)

BOP Ruptured SIG pressure decreases to < 250 PSIG above pressure of intact S/G used for cooldown. (YES)

RO Transition to EPP-17, SGTR WITH LOSS OF REACTOR

COOLANT: SUBCOOLED RECOVERY.

At the discretion of the Chief Examiner, when the crew has transitioned to EPP-17 and SIG C has been isolated as a faulted and ruptured SIG, the scenario may be terminated.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.:

Event

Description:

Operator Action Form ES-D-2 Scenario #

3 Event #

_7;...l"..;.8.:...;, &;,;..9=.....-__ Page 21 of....;2:;.;7 ___

---i1 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start.

S/G Blowdown Sample valves fail to close.

Time II Position II Applicant's Actions or Behavior RO Establish Charging flow to maintain PZR level.

RO Core Exit Temperature less than required temperature. (YES)

BOP Reduce Steam flow to stabilize RCS temperature.

CREW Allow RCS temperature to stabilize from cooldown prior to continuing.

BOP Ruptured S/G pressure stable or increasing. (NO)

BOP Ruptured S/G pressure decreases to < 250 PSIG above pressure of intact S/G used for cooldown. (YES)

SRO Transition to EPP-17, SGTR WITH LOSS OF REACTOR COOLANT: SUBCOOLED RECOVERY.

At the discretion of the Chief Examiner, when the crew has transitioned to EPP-17 and S/G "C" has been isolated as a faulted and ruptured S/G, the scenario may be terminated.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

7, 8, & 9 Page 22 of 27 Event

Description:

S!G C Safety Valve fails open. Safety Injection Pump C fails to start.

S!G Blowdown Sample valves fail to close.

Time Position fi Acolicants Actions or Behavior Supplement G, STEAM GENERATOR ISOLATION, Actions (to isolate S/G C as a faulted SIG AND to isolate S/G C as a ruptured S/G)

BOP Go to the appropriate step from following table:

S/G C to be isolated, Go To Step 34.

BOP Check S/G C faulted. (YES)

BOP Verify Vi -3C, MSIV CLOSED. (YES)

BOP Verify MS-353C, MSIV Vl-3C BYP CLOSED. (YES)

BOP Verify FRV C CLOSED. (YES)

BOP Verify FRV C BYP CLOSED.(YES)

BOP Verify V2-6C, FW HDR SECTION Valve CLOSED. (YES)

BOP Verify V2-14C, SDAFW PUMP DISCH Valve CLOSED. (YES)

BOP Verify V2-1 6C, AFW HDR DISCH Valve CLOSED. (YES)

BOP Verify STEAM LINE PORV CLOSED. (YES)

BOP Verify Vi -8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)

BOP Verify S/G C Blowdown and Blowdown Sample Valve Status Light Indication CLOSED. (NO)

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: -----

Event

Description:

Operator Action Form ES-D-2 Scenario #

3 Event #

_7;...., *..;;.8l,..;' &;.;..9~ __ Page 22 of.....:2=.;.,7 ___

-11 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start.

S/G Blowdown Sample valves fail to close.

Time II Position

~

Applicant's Actions or Behavior Supplement G, STEAM GENERATOR ISOLATION, Actions (to isolate SIG "C" as a faulted SIG AND to isolate SIG "C" as a ruptured S/G)

BOP Go to the appropriate step from following table:

S/G C to be isolated. Go To Step 34.

BOP Check S/G "c" faulted. (YES)

BOP Verify V1-3C, MSIV CLOSED. (YES)

BOP Verify MS-353C, MSIV V1-3C BYP CLOSED. (YES)

BOP Verify FRV C CLOSED. (YES)

BOP Verify FRV C BYP CLOSED.(YES)

BOP Verify V2-6C, FW HDR SECTION Valve CLOSED. (YES)

BOP Verify V2-14C, SDAFW PUMP DISCH Valve CLOSED. (YES)

BOP Verify V2-16C, AFW HDR DISCH Valve CLOSED. (YES)

BOP Verify STEAM LINE PORV CLOSED. (YES)

BOP Verify V1-8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)

BOP Verify S/G "C" Blowdown and Blowdown Sample Valve Status Light Indication CLOSED. (NO)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

7, 8, & 9 Page 23 of 27 Event

Description:

S!G C Safety Valve fails open. Safety Injection Pump C fails to start.

S/G Blowdown Sample valves fail to close.

Time Position II Applicants Actions or Behavior BOP BOP BOP Deenergize R-1 9C. (May have already been performed lAW AOP-005)

IF S/G C Blowdown and Sample valves fail to close, THEN close:

SGB-38C, SGBD HX C INLET.

SGB-56C, SGBD HX C BYPASS/HX FLOW CONTROL ISOLATION.

SGB-60C, SGBD LINE C TO WLU SYSTEM.

SGB-38, S/G C SAMPLE FLOW ISOLATION.

Dispatch an operator to the Pipe Jungle to close MS-38, S/G C BYPASS DRN and WARM-UP LINE TO AFW PUMP.

Check S/G C MSIV Above and Below Seat Drain Valves CLOSED.

(YES)

Dispatch operator to the Aux. Bldg. to perform the following:

BOP At MCC-1O, verify V2-14C closed and open breaker V2-14C, SDAFW PUMP HEADER DISCHARGE TO S/G C.

BOP Check All Faulted and Ruptured S/Gs ISOLATED. (NO, Go To Step 1)

BOP Go to the appropriate step from following table:

S/G C to be isolated, Go To Step 34.

BOP Dispatch an operator to E-1IE-2 Room to perform the following:

At MCC-9, verify V2-1 6C closed and open breaker V2-1 6C, MDAFW PUMP TO S/G C.

At MCC-6, verify Vi -8C closed and open breaker Vi -8C, SDAFW PUMP STEAM ISOLATION.

Appendix D NUREG-iO2i, Rev. 9, Supp. 1 Appendix D Op Test No.:

Event

Description:

Operator Action Form ES-D-2 Scenario #

3 Event #

_7;..:. *....;;.8:....;. &;;..;9~ __ Page 23 of.....:2;;.;.,7 ___

....,1 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start.

S/G Blowdown Sample valves fail to close.

Time II Position II Applicant's Actions or Behavior Deenergize R-19C. (May have already been performed lAW AOP-OOS)

IF S/G "c" Blowdown and Sample valves fail to close, THEN close:

SGB-38C, SGBD HX "c" INLET.

BOP SGB-S6C, SGBD HX "c" BYPASS/HX FLOW CONTROL ISOLATION.

SGB-60C, SGBD LINE "c" TO WLU SYSTEM.

SGB-38, S/G "c" SAMPLE FLOW ISOLATION.

BOP Dispatch an operator to the Pipe Jungle to close MS-38, S/G "c" BYPASS DRN and WARM-UP LINE TO AFW PUMP.

BOP Check S/G C MSIV Above and Below Seat Drain Valves CLOSED.

(YES)

Dispatch an operator to E-1/E-2 Room to perform the following:

At MCC-9, verify V2-16C closed and open breaker V2-16C, BOP MDAFW PUMP TO S/G C.

At MCC-6, verify V1-8C closed and open breaker V1-8C, SDAFW PUMP STEAM ISOLATION.

Dispatch operator to the Aux. Bldg. to perform the following:

BOP

At MCC-10, verify V2-14C closed and open breaker V2-14C, SDAFW PUMP HEADER DISCHARGE TO S/G C.

BOP Check All Faulted and Ruptured S/Gs ISOLATED. (NO, Go To Step 1)

BOP Go to the appropriate step from following table:

S/G C to be isolated, Go To Step 34.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

7, 8, & 9 Page 24 of 27 Event

Description:

S/G C Safety Valve fails open. Safety Injection Pump C fails to start.

SIG Blowdown Sample valves fail to close.

Time Position II Applicants Actions or Behavior Check SIG C faulted. (NO)

BOP Verify ruptured Steam Line PORV setpoint at 1035 PSIG using Status Board.

BOP Verify Vi -8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)

BOP Verify SIG C Blowdown and Blowdown Sample Valve Status Light Indication CLOSED. (NO)

Deenergize R-19C.

IF SIG C Blowdown and Sample valves fail to close, THEN close:

SGB-38C, SGBD HX C INLET.

BOP SGB-56C, SGBD HX C BYPASS/HX FLOW CONTROL ISOLATION.

SGB-60C, SGBD LINE C TO WLU SYSTEM.

SGB-38, SIG C SAMPLE FLOW ISOLATION.

BOP Dispatch an operator to the Pipe Jungle to close MS-38, S/G C BYPASS DRN and WARM-UP LINE TO AFW PUMP.

Check S/G C MSIV Above and Below Seat Drain Valves CLOSED.

BOP (YES)

Dispatch an operator to E-1IE-2 Room to perform the following:

At MCC-9, verify V2-i 6C closed and open breaker V2-i 6C, BOP MDAFW PUMP TO SIG C.

At MCC-6, verify Vi -SC closed and open breaker Vi -SC, SDAFW PUMP STEAM ISOLATION.

Appendix D NUREG-i 021, Rev. 9, Supp. 1 Appendix D Op Test No.:

Event

Description:

Operator Action Form ES-D-2 Scenario #

3 Event #

_7;...:.,.;;;..8,:....;;&;.;..;9:......-__ Page 24 of....;2;;.;.7 ___

...,1 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start.

S/G Blowdown Sample valves fail to close.

Time II Position II Applicant's Actions or Behavior Check S/G "C" faulted. (NO)

BOP Verify ruptured Steam Line PORV setpoint at 1035 PSIG using Status Board.

BOP Verify V1-8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)

BOP Verify S/G C Blowdown and Blowdown Sample Valve Status Light Indication CLOSED. (NO)

Deenergize R-19C.

IF S/G "C" Blowdown and Sample valves fail to close, THEN close:

SGB-38C, SGBD HX "C" INLET.

BOP SGB-56C, SGBD HX "C" BYPASS/HX FLOW CONTROL ISOLATION.

SGB-60C, SGBD LINE "C" TO WLU SYSTEM.

SGB-38, S/G "C" SAMPLE FLOW ISOLATION.

BOP Dispatch an operator to the Pipe Jungle to close MS-38, S/G "C" BYPASS DRN and WARM-UP LINE TO AFW PUMP.

BOP Check S/G C MSIV Above and Below Seat Drain Valves CLOSED.

(YES)

Dispatch an operator to E-1/E-2 Room to perform the following:

At MCC-9, verify V2-16C closed and open breaker V2-16C, BOP MDAFW PUMP TO S/G C.

At MCC-6, verify V1-8C closed and open breaker V1-8C, SDAFW PUMP STEAM ISOLATION.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

7, 8, & 9 Page 25 of 27 Event

Description:

SIG C Safety Valve fails open. Safety Injection Pump C fails to start.

SIG Blowdown Sample valves fail to close.

[

Time Position Applicants Actions or Behavior Dispatch operator to the Aux. Bldg. to perform the following:

BOP At MOO-jo, verify V2-14C closed and open breaker V2-14C, SDAFW PUMP HEADER DISCHARGE TO SIG C.

BOP Check All Faulted and Ruptured S/Gs ISOLATED. (YES)

BOP WHEN the faulted S/Gs dry out, THEN dump steam from intact SIG to control RCS repressurization.

BOP Check Any S/G RUPTURED. (YES)

Perform the following to minimize Secondary system contamination:

Use Auxiliary boilers for auxiliary steam.

Bypass the condensate polishers.

Verify hotwell return to CST isolated:

o Locally verify O-48A and C-48B CLOSED.

SRO/BOP Dispatch an operator to close GS-36, MANUAL GLAND STEAM DUMP.

SRO Return to procedure and step in effect.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.:

Event

Description:

Operator Action Form ES-D-2 Scenario #

3 Event #

7, 8, & 9 Page 25 of 27

~~~---

~I S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start.

S/G Blowdown Sample valves fail to close.

I Time II Position II Applicant's Actions or Behavior Dispatch operator to the Aux. Bldg. to perform the following:

BOP

At MCC-10, verify V2-14C closed and open breaker V2-14C, SDAFW PUMP HEADER DISCHARGE TO S/G C.

BOP Check All Faulted and Ruptured S/Gs ISOLATED. (YES)

BOP WHEN the faulted S/Gs dry out, THEN dump steam from intact S/G to control RCS repressurization.

BOP Check Any S/G RUPTURED. (YES)

Perform the following to minimize Secondary system contamination:

Use Auxiliary boilers for auxiliary steam.

Bypass the condensate polishers.

Verify hotwell return to CST isolated:

0 Locally verify C-48A and C-48B CLOSED.

SRO/BOP Dispatch an operator to close GS-36, MANUAL GLAND STEAM DUMP.

SRO Return to procedure and step in effect.

Appendix D NUREG-1021, Rev. 9, Supp. 1

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

1 Scenario #

3 Event #

Page 26 of 27 Event

Description:

AOP-005 actions for R-1 9C alarm.

Time II Position Applicants Actions or Behavior AOP-005 Actions BOP Makes announcement for AOP-005 entry and Goes to Attachment 20.

BOP Verify S/G C Blowdown AND Blowdown Sample Valves CLOSED.

(NO)

BOP Deenergize R-1 9C. (Directs the AC to Push the Power Switch located in R-1 9C Cabinet bottom right)

IF S/G C Blowdown and Sample isolation valves fail to close, THEN close:

SGB-38C, SGBD HX C INLET.

SGB-56C, SGBD HX C BYPASS/HX FLOW CONTROL BOP ISOLATION.

SGB60C, SGBD LINE C TO WLU SYSTEM.

SGB-38, S/G C SAMPLE FLOW ISOLATION.

(BOP will contact the AO and direct closing of the above valves)

Verify FCV-4204C, SG C BLOWDOWN FLOW RATE CONTROL BOP Valve CLOSED. (IF NO, THEN Close SGB-65C, FCV-4204C INLET)

(BOP will contact the AC and direct closing of the above valve)

BOP Check R-1 9 Radiation Monitors HIGH ALARM ALL ILLUMINATED.

(NO. Go To Step 6)

BOP Check SGTR OR AOP-035 IN PROGRESS. (YES, Return to Procedure And Step In Effect)

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -- Scenario #

3 Event #

Page 26 of 27

~I Event

Description:

AOP-005 actions for R-19C alarm.

Time II Position

~

Applicant's Actions or Behavior AOP-005 Actions BOP Makes announcement for AOP-005 entry and Goes to Attachment 20.

BOP Verify S/G "C" Blowdown AND Blowdown Sample Valves CLOSED.

(NO)

BOP Deenergize R-19C. (Directs the AO to Push the Power Switch located in R-19C Cabinet bottom right)

IF S/G "C" Blowdown and Sample isolation valves fail to close, THEN close:

SGB-38C, SGBD HX "C" INLET.

SGB-56C, SGBD HX "C" BYPASS/HX FLOW CONTROL BOP ISOLATION.

SGB-60C, SGBD LINE "C" TO WLU SYSTEM.

SGB-38, S/G "C" SAMPLE FLOW ISOLATION.

(BOP will contact the AO and direct closing of the above valves)

Verify FCV-4204C, SG "C" BLOWDOWN FLOW RATE CONTROL BOP Valve CLOSED. (IF NO, THEN Close SGB-65C, FCV-4204C INLET)

(BOP will contact the AO and direct closing of the above valve)

BOP Check R-19 Radiation Monitor's HIGH ALARM ALL ILLUMINATED.

(NO, Go To Step 6)

BOP Check SGTR OR AOP-035 IN PROGRESS. (YES, Return to Procedure And Step In Effect)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

HLC-08 NRC SCENARIO 3 TURNOVER SHEET POWER LEVEL: 7% BOL, 150 MWD/MTU.

BORON CONCENTRATION: 1645 ppm EQUIPMENT UNDER CLEARANCE:

SW Booster Pump A is out of service and under clearance for Motor Coupling Alignment.

o LCO 3.7.7-A has been entered and is in hour 18 of a 72 Action Statement.

o Expected return is within 1 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

EQUIPMENT STATUS:

Main Turbine bearings #2, 3 and 4 vibration is elevated. All actions to inform station management have been performed.

INSTRUCTIONS FOR THE WATCH:

Continue with GP-005 and synchronize the Generator to the Grid.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 HLC-08 NRC SCENARIO 3 TURNOVER SHEET POWER LEVEL: 7% BOL, 150 MWD/MTU.

BORON CONCENTRATION: 1645 ppm EQUIPMENT UNDER CLEARANCE:

SW Booster Pump "A" is out of service and under clearance for Motor Coupling Alignment.

o LCO 3.7.7-A has been entered and is in hour 18 of a 72 Action Statement.

o Expected return is within -18 hours.

EQUIPMENT STATUS:

Main Turbine bearings #2, 3 and 4 vibration is elevated. All actions to inform station management have been performed.

INSTRUCTIONS FOR THE WATCH:

Continue with GP-005 and synchronize the Generator to the Grid.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

HB ROBINSON Scenario No.:

4 Op Test No.:

Examiners:

Operators:

SRO RO BOP Initial Conditions:

50% BOL, 150 MWD/MTU, 1306 ppm Boron.

SW Booster Pump A is Out-Of-Service for Motor Coupling Alignment.

o LCO 3.7.7-A has been entered and is in hour 18 of a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action statement.

o Expected return is within 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

Main Turbine Vibration for #2, 3 and 4 bearings is elevated.

Turnover:

Returning to RTP following a Maintenance Outage. Increase power to 75%.

Critical Task:

Manually initiate SI to provide injection flow from at least 1 SI Pump before Reactor Vessel level reaches 41% by Full Range RVLIS indication.

Ensure that ALL Phase A valves are closed upon receipt of a valid actuation signal prior to completion of Grid Location B-9 (SI Flow Verified).

Event MaIf.

Event Type*

Event No.

No.

Description 1

(R) RO Increase power to 75% RTP.

(N) SRO, BOP 2

(TS) SRO Loop 1 THQT Fails Low.

3 (C) BOP, SRO SW flooding from the South SW Header.

(TS) SRO 4

(C) RO, SRO PZR PORV PCV-456 fails 70% open.

(TS) SRO 5

(C) BOP, SRO HCV-1 459, Heater Bypass Valve fails OPEN.

6 (M) ALL High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

7 (M) ALL Failure of the Reactor to trip. (ATWS) SDAFW Pump trips.

8 (M) ALL Small Break LOCA.

9 (C) RO Phase A fails to automatically actuate and several valves fail to automatically close.

10 (C) RO Safety Injection fails to automatically actuate.

1 1 (C) BOP Control Room HVAC Train A and Train B fail to automatically actuate. (HVE-1 9A fails to start and HVE-1 6 fails to stop)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 Facility:

HB ROBINSON Scenario No.:

4 Op Test No.:

Examiners:

Operators:

SRO -

RO -

BOP-Initial Conditions:

50% BOL, 150 MWD/MTU, 1306 ppm Boron.

SW Booster Pump "A" is Out-Of-Service for Motor Coupling Alignment.

0 LCO 3.7.7 -A has been entered and is in hour 18 of a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action statement.

0 Expected return is within -18 hours.

Main Turbine Vibration for #2, 3 and 4 bearings is elevated.

Turnover:

Returning to RTP following a Maintenance Outage. Increase power to 75%.

Critical Task:

Manually initiate SI to provide injection flow from at least 1 SI Pump before Reactor Vessel level reaches 41 % by Full Range RVLlS indication.

Ensure that ALL Phase A valves are closed upon receipt of a valid actuation signal prior to completion of Grid Location B-9 (SI Flow Verified).

Event Malf.

Event Type*

Event No.

No.

Description 1

(R) RO Increase power to 75% RTP.

(N) SRO, BOP 2

(TS) SRO Loop 1 T HOT Fails Low.

3 (C) BOP, SRO SW flooding from the South SW Header.

(TS) SRO 4

(C) RO, SRO PZR PORV PCV-456 fails 70% open.

(TS) SRO 5

(C) BOP, SRO HCV-1459, Heater Bypass Valve fails OPEN.

6 (M) ALL High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

7 (M) ALL Failure of the Reactor to trip. (ATWS) SDAFW Pump trips.

8 (M) ALL Small Break LOCA.

9 (C) RO Phase A fails to automatically actuate and several valves fail to automatically close.

10 (C) RO Safety Injection fails to automatically actuate.

11 (C) BOP Control Room HVAC Train A and Train B fail to automatically actuate. (HVE-19A fails to start and HVE-16 fails to stop)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1 021, Rev. 9, Supp. 1

I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 4

SUMMARY

DESCRIPTION The crew will assume the watch with the plant at 50% RTP. The previous shift identified increased vibration on Main Turbine bearing #3 and has taken all necessary actions to inform station management. Service Water Booster Pump A is under clearance for Motor Coupling Alignment. Shift instructions are to increase power to 75% and hold for Reactor Engineering instructions.

On cue from the Chief Examiner, Loop 1 THOT will fail low. The crew will respond lAW APP-003-A4, but will NOT remove the instrument from service using OWP- 028, T/DeltaTl. The SRO will enter LCO 3.3.1-1, Condition E for the failed instrument.

On cue from the Chief Examiner, flooding will occur from the discharge of SW Pump A at the Service Water intake. The BOP will take immediate actions to split the North and South SW headers. The crew should respond lAW AOP-022, LOSS OF SERVICE WATER and isolate the South SW Header, isolating the source of the flooding. The SRO will enter LCO 3.8.1, Condition B for the inoperable EDG.

On cue from the Chief Examiner, PZR PORV PCV-456 will fail 70% open. The crew should attempt to close PCV-456, which will not respond, requiring closing the block valve (RC-535).

The RO should control PZR Heaters and Spray valves to maintain RCS pressure above 2205 psig. The crew should respond using AOP-01 9, MALFUNCTION OF RCS PRESSURE CONTROL. The SRO should enter LCO 3.4.11, Condition B for the inoperable PORV, and may enter LCO 3.4.1, Condition A if pressure falls below 2205 psig. The PORV will remain unavailable throughout the scenario.

On cue from the Chief Examiner, HCV-1 459, Heater Bypass Valve will fail OPEN. The crew will implement AOP-010, MAIN FEEDWATER / CONDENSATE MALFUNCTION. The crew will close HCV-1 459 from the RTGB control switch and the valve will remain in the closed position as long as the valve switch remains in the CLOSE position.

On cue from the Chief Examiner, Turbine bearing #3 vibration will increase to the alarm point and AOP-006, TURBINE ECCENTRICITY/VIBRATION, will be entered. High bearing vibrations will be reflected on adjacent bearings #2 and #4. Vibrations will increase to 14 mils and actions in AOP-006 will require the SRO to direct a manual Reactor trip and enter PATH-1. When the crew attempts to trip the reactor, both Reactor Trip pushbuttons will fail and the SRO will enter FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS. The SDAFW Pump will trip and remain unavailable for the remainder of the scenario. The AO will be successful in tripping the Reactor locally when directed.

When the crew has transitioned to EPP-.4, REACTOR TRIP RESPONSE and on cue from the Chief Examiner, a Small Break LOCA will be inserted. The LOCA will require a Safety Injection initiation and Phase A isolation, which will fail to automatically actuate. Manual operator actuation will be successful, but three Phase A valves will fail to close and require the RO to manually close these valves from the RTGB. The Control Room HVAC System Train A and Train B will fail to automatically actuate, requiring the BOP to manually align HVAC for Emergency Pressurization Mode.

The scenario can be terminated, at the Chief Examiners discretion, after it is determined that SI termination criteria will not be met.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 4

SUMMARY

DESCRIPTION The crew will assume the watch with the plant at 50% RTP. The previous shift identified increased vibration on Main Turbine bearing #3 and has taken all necessary actions to inform station management. Service Water Booster Pump "A" is under clearance for Motor Coupling Alignment. Shift instructions are to increase power to 75% and hold for Reactor Engineering instructions.

On cue from the Chief Examiner, Loop 1 T HOT will fail low. The crew will respond lAW APP-003-A4, but will NOT remove the instrument from service using OWP- 028, T/DeltaT1. The SRO will enter LCO 3.3.1-1, Condition E for the failed instrument.

On cue from the Chief Examiner, flooding will occur from the discharge of SW Pump "A" at the Service Water intake. The BOP will take immediate actions to split the North and South SW headers. The crew should respond lAW AOP-022, LOSS OF SERVICE WATER and isolate the South SW Header, isolating the source of the flooding. The SRO will enter LCO 3.8.1, Condition B for the inoperable EDG.

On cue from the Chief Examiner, PZR PORV PCV-456 will fail 70% open. The crew should attempt to close PCV-456, which will not respond, requiring closing the block valve (RC-535).

The RO should control PZR Heaters and Spray valves to maintain RCS pressure above 2205 psig. The crew should respond using AOP-019, MALFUNCTION OF RCS PRESSURE CONTROL. The SRO should enter LCO 3.4.11, Condition B for the inoperable PORV, and may enter LCO 3.4.1, Condition A if pressure falls below 2205 psig. The PORV will remain unavailable throughout the scenario.

On cue from the Chief Examiner, HCV-1459, Heater Bypass Valve will fail OPEN. The crew will implement AOP-010, MAIN FEEDWATER I CONDENSATE MALFUNCTION. The crew will close HCV-1459 from the RTGB control switch and the valve will remain in the closed position as long as the valve switch remains in the CLOSE position.

On cue from the Chief Examiner, Turbine bearing #3 vibration will increase to the alarm point and AOP-006, TURBINE ECCENTRICITY I VIBRATION, will be entered. High bearing vibrations will be reflected on adjacent bearings # 2 and #4. Vibrations will increase to 14 mils and actions in AOP-006 will require the SRO to direct a manual Reactor trip and enter PATH-1. When the crew attempts to trip the reactor, both Reactor Trip pushbuttons will fail and the SRO will enter FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS. The SDAFW Pump will trip and remain unavailable for the remainder of the scenario. The AO will be successful in tripping the Reactor locally when directed.

When the crew has transitioned to EPP-4, REACTOR TRIP RESPONSE and on cue from the Chief Examiner, a Small Break LOCA will be inserted. The LOCA will require a Safety Injection initiation and Phase A isolation, which will fail to automatically actuate. Manual operator actuation will be successful, but three Phase A valves will fail to close and require the RO to manually close these valves from the RTGB. The Control Room HVAC System Train A and Train B will fail to automatically actuate, requiring the BOP to manually align HVAC for Emergency Pressurization Mode.

The scenario can be terminated, at the Chief Examiner's discretion, after it is determined that SI termination criteria will not be met.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 4 SIMULATOR SETUP IC/SETUP 10-604, SCN: 006_Sim_4.

Status board updated to reflect 10-4.

PRE-LOADED EVENTS:

The following events should occur on the reactor trip:

Event 7: Failure of the Reactor to trip. (ATWS) SDAFW Pump trips.

Event 9: Phase A valves CVC-204B, CCW-739 and SI-855 fail to close on SI actuation.

Event 10: Safety Injection fails to automatically actuate.

Event 11: Control Room HVAC Train A and Train B fail to automatically actuate.

EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:

Event 1: Increase power to 75%.

Event 2: Loop 1 THQT fails low.

Event 3: SW flooding from the South SW Header.

Event 4: PZR PORV PCV-456 fails 70% open.

Event 5: HCV-1 459, Heater Bypass Valve fails OPEN.

Event 6: High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Event 8: Small Break LOCA.

EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

OP-i 05, Section 8.4.2; AOP-022, Section F; AOP-019; AOP-006; PATH-i, FRP-S.1; EPP-4; FRP-P.1.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 4 SIMULATOR SETUP IC/SETUP IC-604, SCN: 006_Sim_ 4.

Status board updated to reflect IC-4.

PRE-LOADED EVENTS:

The following events should occur on the reactor trip:

Event 7: Failure of the Reactor to trip. (A TWS) SDAFW Pump trips.

Event 9: Phase A valves CVC-204B, CCW-739 and SI-855 fail to close on SI actuation.

Event 10: Safety Injection fails to automatically actuate.

Event 11: Control Room HVAC Train A and Train B fail to automatically actuate.

EVENTSITRIGGERS INITIATED DURING THE SCENARIO:

Event 1: Increase power to 75%.

Event 2: Loop 1 T HOT fails low.

Event 3: SW flooding from the South SW Header.

Event 4: PZR PORV PCV-456 fails 70% open.

Event 5: HCV-1459, Heater Bypass Valve fails OPEN.

Event 6: High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Event 8: Small Break LOCA.

EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

OP-105, Section 8.4.2; AOP-022, Section F; AOP-019; AOP-006; PATH-1, FRP-S.1; EPP-4; FRP-P.1.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

1 Page 4

of 36 Event

Description:

Increase power to 75%.

Time Position Applicants Actions or Behavior BOOTH OPERATOR:

Event 1 is normal power ascension to 75% lAW OP-i 05. The crew will brief the event in the classroom prior to entering the simulator and begin the ascension as soon as they take the shift.

OP-i 05 Actions SRO Begins power ascension using OP-i 05 Section 8.4.2.

SRO IF Reactor Engineering has not provided technical guidance, THEN determine the reactivity change required.

SRO Notify the Load Dispatcher that unit load will be increased.

RO TAvG is within 5 °F of TREF.

RO Monitor the highest operable PR and IR channels on NR-45.

Steam Dump controls are set as follows:

BOP Potentiometer set at 7.28 (1020 psig).

In Automatic and TAVG Control.

BOP FRVs in AUTO and S/Gs are being maintained at programmed level.

BOP IF the EH Turbine Control is in OPER AUTO, THEN verify the Turbine Control is in IMP IN. (Preferred)

RO Check the ERFIS PDCIII Delta Flux monitoring program enabled.

BOP Check the Turbine Lube Oil Cooler is maintaining the oil temperature leaving the bearings within the limits of OP-506.

BOP The Bulk Auxiliary electrical loads should be on the Unit Auxiliary Transformer lAW OP-603.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.:

-.;...- Scenario #

4 Event #

Page 4

of 36

~--------

~~----~I Event

Description:

Increase power to 75%.

Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR: Event 1 is normal power ascension to 75% lAW OP-105. The crew will brief the event in the classroom prior to entering the simulator and begin the ascension as soon as they take the shift.

OP-105 Actions SRO Begins power ascension using OP-1 05 Section 8.4.2.

SRO IF Reactor Engineering has not provided technical guidance, THEN determine the reactivity change required.

SRO Notify the Load Dispatcher that unit load will be increased.

RO T AVG is within 5 of of T REF.

RO Monitor the highest operable PR and IR channels on NR-45.

Steam Dump controls are set as follows:

BOP Potentiometer set at 7.28 (1020 psig).

In Automatic and TAVG Control.

BOP FRVs in AUTO and S/Gs are being maintained at programmed level.

BOP IF the EH Turbine Control is in OPER AUTO, THEN verify the Turbine Control is in IMP IN. (Preferred)

RO Check the ERFIS PDCIII Delta Flux monitoring program enabled.

BOP Check the Turbine Lube Oil Cooler is maintaining the oil temperature leaving the bearings within the limits of OP-506.

BOP The Bulk Auxiliary electrical loads should be on the Unit Auxiliary Transformer lAW OP-603.

Appendix 0 NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

1 Page 5

of 36 Event

Description:

Increase power to 75%.

Time Position Applicants Actions or Behavior SRO BOP BOP BOP For each power change greater than or equal to 10%, update the power change log in the Reactor Startups/Shutdowns/Trips Book.

While increasing power, Generator MVAR loading should be lAW the Robinson Plant Voltage Support and Coordination Procedure.

Verify the Valve Position Limit is adjusted to maximum.

IF EH Turbine Control is in OPER AUTO, THEN increase turbine load as follows:

Adjust the SETTER indication using the REF UP pushbutton to the desired load.

Depress the GO and/or HOLD pushbuttons and the REF UP as necessary to continue the load increase.

DETERMINE the amount of water to add to the RCS.

(The crew will calculate 2000 gallons of water needed for the dilution to 75% power, based on Rods at 175 steps. Water will be added in 4-6 dilutions)

OBTAIN an independent check of the volume of water required.

OBTAIN permission from the CRSS OR the SSO to dilute.

PLACE the RCS MAKEUP MODE selector switch in DILUTE NOTE:

OP-301, Section 8.2.7 Quick Dilution Checklist (shaded area) is included in the following steps, but may be used prior to the commencement of the plant up power.

When power is between 55-60%, the crew will start the second MFP.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-O-2 Op Test No.:

~- Scenario #

4 Event #

......;.,. ____ Page 5

of _3,;;.;6;...... __

--11 Event

Description:

Increase power to 75%.

Time II Position

~

Applicant's Actions or Behavior SRO For each power change greater than or equal to 10%, update the power change log in the Reactor Startups/Shutdowns/Trips Book.

BOP While increasing power, Generator MVAR loading should be lAW the Robinson Plant Voltage Support and Coordination Procedure.

BOP Verify the Valve Position Limit is adjusted to maximum.

IF EH Turbine Control is in OPER AUTO, THEN increase turbine load as follows:

BOP Adjust the SETTER indication using the REF UP pushbutton to the desired load.

Depress the GO and/or HOLD pushbuttons and the REF UP as necessary to continue the load increase.

NOTE:

OP-301, Section 8.2.7 Quick Dilution Checklist (shaded area) is included in the following steps, but may be used prior to the commencement of the plant up power.

When power is between 55-60%, the crew will start the second MFP.

DETERMINE the amount of water to add to the RCS.

(The crew will calculate - 2000 gallons of water needed for the dilution to 75% power, based on Rods at -175 steps. Water will be added in 4-6 dilutions)

OBTAIN an independent check of the volume of water required.

OBTAIN permission from the CRSS OR the SSO to dilute.

PLACE the RCS MAKEUP MODE selector switch in DILUTE.

Appendix 0 NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 1

Op Test No.:

Event

Description:

Increase power to 75%.

Time Position Applicants Actions or Behavior Scenario #

4 Event #

1 Page 6

of 36 SET YIC-1 14, PRIMARY WTR TOTALIZER to the desired quantity.

IF desired, THEN PLACE FCV-1 14A, PRIMARY WTR FLOW DILUTE MODE, in MAN AND adjust Primary Water Flow rate using the UP/DOWN pushbuttons.

Momentarily PLACE the RCS MAKEUP SYSTEM switch to START.

VERIFY proper operation of LCV-1 1 5A, VCT/HLDP TK DIV valve.

IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:

Unanticipated Rod Motion Primary Water addition exceeds the desired value WHEN desired amount of PW has been added, THEN verify:

FCV 11 4A, PW TO BLENDER, closes.

FCV-1 1 4B, BLENDED MU TO VCT, closes.

IF in Auto, THEN the operating Primary Water Pump stops.

The RCS MAKEUP SYSTEM is OFF.

RETURN the RCS Makeup System to automatic:

VERIFY FCV-1 14A, PRIMARY WTR FLOW DILUTE MODE is in AUTO.

PLACE the RCS MAKEUP MODE switch in AUTO.

Momentarily PLACE RCS MAKEUP SYSTEM switch to START.

RECORD, in AUTO LOG, as indicated by PRIMARY WATER TOTALIZER, YIC-1 14 total amount of PW added during the dilution.

MONITOR parameters for the expected change in reactivity AND inform_the_CRSS_OR_the_SSO_of_the_results_of_the_dilution.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --

Scenario #

4 Event #

Page 6

of 36

~-------

~---~I Event

Description:

Increase power to 75%.

Time Position I

Applicant's Actions or Behavior SET YIC-114, PRIMARY WTR TOTALIZER to the desired quantity.

IF desired, THEN PLACE FCV-114A, PRIMARY WTR FLOW DILUTE MODE, in MAN AND adjust Primary Water Flow rate using the UP/DOWN pushbuttons.

Momentarily PLACE the RCS MAKEUP SYSTEM switch to START.

VERIFY proper operation of LCV-115A, VCT/HLDP TK DIV valve.

IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:

Unanticipated Rod Motion.

Primary Water addition exceeds the desired value.

WHEN desired amount of PW has been added, THEN verify:

FCV-114A, PW TO BLENDER, closes.

FCV-114B, BLENDED MU TO VCT, closes.

IF in Auto, THEN the operating Primary Water Pump stops.

The RCS MAKEUP SYSTEM is OFF.

RETURN the RCS Makeup System to automatic:

VERIFY FCV-114A, PRIMARY WTR FLOW DILUTE MODE is in AUTO.

PLACE the ReS MAKEUP MODE switch in AUTO.

Momentarily PLACE RCS MAKEUP SYSTEM switch to START.

RECORD, in AUTO LOG, as indicated by PRIMARY WATER TOTALIZER, YIC-114 total amount of PW added during the dilution.

MONITOR parameters for the expected change in reactivity AND inform the CRSS OR the SSO of the results of the dilution.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

2 Page 7

of 36 Event

Description:

Loop 1 THOT Fails Low.

Time I

Position Applicants Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 2, Loop 1 THOT failure.

EVENT INDICATIONS:

APP-003-A4; RC LOOPS T DEV APP-003-A6; RCS HI/LO TAVG APP-003-B4; RC LOOPS TAVG DEV TR-412 Pen 1, T (RED) pegged low.

TR-412 T Power fails low.

RO Recognizes that instrument has failed and references APP-003-A4.

Recommends removing the instrument from service.

SRO Reviews, briefs and directs taking Loop 1 THQT instrument out of service using OWP-028, T/tiTl.

Review ITS for applicable LCOs:

Table 3.3.1-1, #5, 6 Condition E; Place channel in Trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SRO Table 3.3.2-1, # 1.f Condition D; Place channel in Trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Table 3.3.2-1, # 4.d & 6.b Condition H; Verify interlock is in required state for existing unit condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

......;....- Scenario #

4 Event #

....;2=---____ Page 7

of _3:..;6:....-__ ---l1 Event

Description:

Loop 1 T HOT Fails Low.

Time I

Position II Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 2, Loop 1 T HOT failure.

EVENT INDICATIONS:

APP-003-A4; RC LOOPS llT DEV APP-003-A6; RCS HIILO TAVG APP-003-B4; RC LOOPS TAVG DEV TR-412 Pen 1, llT (RED) pegged low.

TR-41211T Power fails low.

RO Recognizes that instrument has failed and references APP-003-A4.

Recommends removing the instrument from service.

SRO Reviews, briefs and directs taking Loop 1 T HOT instrument out of service using OWP-028, TILH1.

Review ITS for applicable LCOs:

Table 3.3.1-1, #5, 6 - Condition E; Place channel in Trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SRO Table 3.3.2-1, # 1.f - Condition D; Place channel in Trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Table 3.3.2-1, # 4.d & 6.b - Condition H; Verify interlock is in required state for existing unit condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

3 Page 8

of 36 Event

Description:

SW flooding from the South SW Header.

Time

]

Position Applicants Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 3, SW Flooding in the Intake Bay from the South SW Header.

EVENT INDICATIONS:

APP-008-F7; SOUTH SW HDR LO PRESS APP-008-F8; NORTH SW HDR LO PRESS APP-008-E7; S SW HDR STRAINER PIT HI LEVEL APP-008-E8; N SW HDR STRAINER PIT HI LEVEL APP-002-A8; HVH-1 WTR OUTLET LO FLOW APP-002-B8; HVH-2 WTR OUTLET LO FLOW APP-002-C8; HVH-3 WTR OUTLET LO FLOW APP-002-D8; HVH-4 WTR OUTLET LO FLOW APP-008-D7; S SW HDR STRAINER PIT HI-HI LVL (Delayed)

APP-008-D8; N SW HDR STRAINER PIT HI-HI LVL (Delayed)

SW Booster Pump B trips due to low suction pressure.

BOP Recognizes a Loss of Service Water has occurred and performs Immediate Actions of AOP-022, LOSS OF SERVICE WATER.

NOTE:

The crew will place the Turbine ramp on hold while this malfunction is addressed.

BOP Verify SW X-CONN Valves V6-12B and V6-12C CLOSED. (YES)

SRO BOP SRO RO/BOP Enters AOP-022, LOSS OF SERVICE WATER.

Immediate Action Step:

Check APP-008-E7 AND APP-008-E8 Extinguished. (NO)

Closes valves V6-12B and V6-12C.

Transitions to Section F.

Makes PA announcement for entry into AOP-022.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

~- Scenario #

4 Event #

3 Page 8

of 36

~--------

~~----~I Event

Description:

SW flooding from the South SW Header.

Time II Position I

Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 3, SW Flooding in the Intake Bay from the South SW Header.

EVENT INDICATIONS:

APP-OOS-F7; SOUTH SW HDR LO PRESS APP-OOS-FS; NORTH SW HDR LO PRESS APP-OOS-E7; S SW HDR STRAINER PIT HI LEVEL APP-OOS-ES; N SW HDR STRAINER PIT HI LEVEL APP-002-AS; HVH-1 WTR OUTLET LO FLOW APP-002-BS; HVH-2 WTR OUTLET LO FLOW APP-002-CS; HVH-3 WTR OUTLET LO FLOW APP-002-DS; HVH-4 WTR OUTLET LO FLOW APP-OOS-D7; S SW HDR STRAINER PIT HI-HI LVL (Delayed)

APP-OOS-DS; N SW HDR STRAINER PIT HI-HI LVL (Delayed)

SW Booster Pump "B" trips due to low suction pressure.

BOP Recognizes a Loss of Service Water has occurred and performs Immediate Actions of AOP-022, LOSS OF SERVICE WATER.

NOTE:

The crew will place the Turbine ramp on hold while this malfunction is addressed.

SRO Enters AOP-022, LOSS OF SERVICE WATER.

Immediate Action Step:

BOP Check APP-00S-E7 AND APP-OOS-ES Extinguished. (NO)

Closes valves V6-12B and V6-12C.

SRO Transitions to Section F.

RO/BOP Makes PA announcement for entry into AOP-022.

BOP Verify SW X-CONN Valves V6-12B and V6-12C CLOSED. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

3 Page 9

of 36 Event

Description:

SW flooding from the South SW Header.

Time II Position Anolicants Actions or Behavior Crew BOP BOP BOP NOTE:

With Service Water Pumps A AND B isolated, EDG A is inoperable. ITS 3.8.1 requires SR 3.8.1.1 to be performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

With low flow to all CV HVH units, LCO 3.6.6 applies for both CV Cooling Trains inoperable.

The crew may start SWBP B using APP-002-A81B81C81D8 guidance.

BOP Close V6-12A. (APP-008-E4/E5/E6/F8 will clear)

Evaluate Control Room Indications and perform local inspections to determine source of leakage.

BOOTH OPERATOR:

Report that water is gushing up through the deck plates above the South Service Water header. If the crew has closed both cross-connect valves and V6-12A, then report water has stopped, but was from the South header.

SRO/BOP Check SW source of flooding. (YES)

Check SW leak on the South Header. (YES)

Verify the following:

SW Pump C Running. (YES)

SW Pump D Running. (NO, will start pump) o Will receive APP-008-E4, E5 & E6 alarms SW Pump A Stopped. (NO, will stop pump)

SW Pump B Stopped. (YES)

Evaluate SW Header Pressure:

Check South SW pressure Decreasing. (YES)

Check North SW pressure Stable or Increasing. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

.-;....- Scenario #

4 Event #

_3~ ____ Page 9

of.....;3;.;6 ___

....,1 Event

Description:

SW flooding from the South SW Header.

Time II Position I

Applicant's Actions or Behavior Crew Evaluate Control Room Indications and perform local inspections to determine source of leakage.

BOOTH OPERATOR: Report that water is gushing up through the deck plates above the South Service Water header. If the crew has closed both cross-connect valves and V6-12A, then report water has stopped, but was from the South header.

BOP Check SW source of flooding. (YES)

BOP Check SW leak on the South Header. (YES)

Verify the following:

SW Pump "C" Running. (YES)

SW Pump "D" Running. (NO, will start pump)

BOP 0

Will receive APP-OOS-E4, ES & E6 alarms

SW Pump "A" Stopped. (NO, will stop pump)

SW Pump "B" Stopped. (YES)

Evaluate SW Header Pressure:

SRO/BOP Check South SW pressure Decreasing. (YES)

Check North SW pressure Stable or Increasing. (YES)

NOTE:

With Service Water Pumps "A" AND "B" isolated, EDG "A" is inoperable. ITS 3.B.1 requires SR 3.B.1.1 to be performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

With low flow to all CV HVH units, LCO 3.6.6 applies for both CV Cooling Trains inoperable.

The crew may start SWBP "B" using APP-002-ABIBBICBIDB guidance.

BOP Close V6-12A. (APP-00S-E4/ES/E6/FS will clear)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

Event

Description:

BOP Verify SW-851 and SW-857 closed.

BOOTH OPERATOR:

When requested, report that SW-851 and SW-857 are closed. (Not modeled on simulator)

SRO/BOP Check Flooding status stopped. (YES)

BOOTH OPERATOR:

Report water is no longer gushing up above the South SW header.

BOP Check North SW header pressure > 40 psig. (YES)

SRO Remove Control Power fuses from breakers for SW Pumps A & B at 480V Bus E-1.

BOOTH OPERATOR:

Rack out the breakers for SW Pumps A & B on 480V Bus E-1.

When requested, report that leak is from the connection of SW Pump A and the 30 inch header.

Determine if a SW Booster Pump should be started:

SRO/BOP Check SW Booster pumps all stopped. (YES)

Start one SW Booster Pump. (APP-002-A8/B8/C8/D8 clear).

Time II Position Scenario #

4 Event #

3 Page 10 of 36 SW flooding from the South SW Header.

Applicants Actions or Behavior Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

......;....- Scenario #

4 Event #

3 Page 10 of 36

~I Event

Description:

SW flooding from the South SW Header.

Time II Position I

Applicant's Actions or Behavior BOP Verify SW-851 and SW-857 closed.

BOOTH OPERATOR: When requested, report that SW-851 and SW-857 are closed. (Not modeled on simulator)

SRO/BOP Check Flooding status stopped. (YES)

BOOTH OPERATOR: Report water is no longer gushing up above the South SW header.

BOP Check North SW header pressure> 40 psig. (YES)

SRO Remove Control Power fuses from breakers for SW Pumps "A" & "B" at 480V Bus E-1.

BOOTH OPERATOR: Rack out the breakers for SW Pumps "A" & "B" on 480V Bus E-1.

When requested, report that leak is from the connection of SW Pump "A" and the 30 inch header.

Determine if a SW Booster Pump should be started:

SRO/BOP Check SW Booster pumps all stopped. (YES)

Start one SW Booster Pump. (APP-002-A8/B8/C8/D8 clear).

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

3 Page 11 of 36 Event

Description:

SW flooding from the South SW Header.

Time Position Applicants Actions or Behavior NOTE:

When SWBP B is started, SW pressure may drop to <40 PSIG. If so, the crew may use Step 19 RNO to increase SW pressure.

Step 19, RNO Actions Check South SW Header pressure > 40 PSIG. (NO)

BOP Perform 1 or both of the following to restore South SW header pressure to between 40 and 50 PSIG:

Throttle SW flow from the COW HX using SW-739.

Throttle SW flow from the COW HX using SW-740.

BOP Check any OW Pump running. (YES)

Determine if adequate seal water is available to OW:

APP-008-E4, OW PMP A SEAL WTR LOST extinguished.

BOP APP-008-E5, OW PMP B SEAL WTR LOST extinguished.

APP-008-E6, OW PMP C SEAL WTR LOST extinguished.

(YES, ALL extinguished)

Determine maximum allowable COW temperature as follows:

RO Check ROS temperature 350 degrees F. (NO)

Maintain COW Heat Exchanger outlet temperature indicated on TI-607 less than or equal to 105 degrees F.

Perform the following:

Inspect the area of the leak.

SRO Report findings to the SSO.

Identify and isolate the source of the SW leak.

SRO Contact Maintenance to install temporary pumps to dewater Service Water pits.

AOP-022 Actions Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --

Scenario #

4 Event #

3 Page 11 of 36

~--------

~~----~I Event

Description:

SW flooding from the South SW Header.

Time

~

Position

~

Applicant's Actions or Behavior NOTE:

When SW8P "8" is started, SW pressure may drop to < 40 PSIG. If so, the crew may use Step 19 RNO to increase SW pressure.

Step 19, RNO Actions Check South SW Header pressure> 40 PSIG. (NO)

BOP Perform 1 or both of the following to restore South SW header pressure to between 40 and 50 PSIG:

Throttle SW flow from the CCW HX using SW-739.

Throttle SW flow from the CCW HX using SW-740.

AOP-022 Actions BOP Check any CW Pump running. (YES)

Determine if adequate seal water is available to CW:

APP-008-E4, CW PMP A SEAL WTR LOST extinguished.

BOP

APP-008-E5, CW PMP B SEAL WTR LOST extinguished.

APP-008-E6, CW PMP C SEAL WTR LOST extinguished.

(YES, ALL extinguished)

Determine maximum allowable CCW temperature as follows:

RO Check RCS temperature $. 350 degrees F. (NO)

Maintain CCW Heat Exchanger outlet temperature indicated on TI-6071ess than or equal to 105 degrees F.

Perform the following:

Inspect the area of the leak.

SRO Report findings to the SSO.

Identify and isolate the source of the SW leak.

SRO Contact Maintenance to install temporary pumps to dewater Service Water pits.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

3 Page 12 of 36 Event

Description:

SW flooding from the South SW Header.

Position Applicants Actions or Behavior SRO Contact Engineering to perform the following:

Evaluate operability of equipment affected by flooding.

Provide corrective actions for flooding.

SRO SRO Return to procedure and step in effect.

Refer to ITS for any applicable LCOs.

LCO 3.6.6, Condition D

- Restore one containment cooling train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . (Will only be in this LCO until a SW Booster Pump is started)

LCO 3.7.7, Condition A

- Restore SWS train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . (This LCO has already been entered due to the SWBP being out of service)

LCO 3.8.1, Condition B o

Perform SR 3.8.1.1 for the offsite circuit within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

(Cascaded LCO from SW NOT available to EDG A) o Perform SR 3.8.1.2 to verify EDG OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SRO Implement the EALs.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.:

-..;...- Scenario #

4 Event #

3 Page 12 of 36

~--------

~---~I Event

Description:

SW flooding from the South SW Header.

Time II Position I

Applicant's Actions or Behavior Contact Engineering to perform the following:

SRO Evaluate operability of equipment affected by flooding.

Provide corrective actions for flooding.

Refer to ITS for any applicable LCOs.

LCO 3.6.6, Condition 0 - Restore one containment cooling train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . (Will only be in this LCO until a SW Booster Pump is started)

LCO 3.7.7, Condition A - Restore SWS train to OPERABLE SRO status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . (This LCO has already been entered due to the SWBP being out of service)

LCO 3.8.1, Condition B 0

Perform SR 3.8.1.1 for the offsite circuit within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

(Cascaded LCO from SW NOT available to EDG "A")

0 Perform SR 3.8.1.2 to verify EDG OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SRO Implement the EALs.

SRO Return to procedure and step in effect.

Appendix 0 NUREG-1021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

4 Page 13 of 36 Event

Description:

PZR PORV PCV-456 fails 70% OPEN.

Time Position Applicants Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 4, PZR PORV PCV-456 fails 70% OPEN.

EVENT INDICATIONS:

APP-003-C3;PRT HI PRESS APP-003-D6;PZR PORV/SAFETY VLV OPEN APP-003-E6;PZR PORV LN HI TEMP APP-003-F6;PZR SAFETY VLV LINE HI TEMP APP-003-D8;PZR CONTROL HI/LO PRESS RO Recognizes PORV is OPEN and takes Immediate Actions of AOP 019, MALFUNCTION OF RCS PRESSURE CONTROL.

SRO Enters AOP-01 9, MALFUNCTION OF RCS PRESSURE CONTROL.

Immediate Action Step:

Determine if PZR PORVs should be CLOSED:

RO Check PZR Pressure less than 2335 PSIG (YES)

Verify both PZR PORVs CLOSED. (NO)

IF any PZR PORV can NOT be CLOSED, THEN close its PORV BLOCK valve.

Immediate Action Step:

RO Control Heaters and Spray valves to restore RCS Pressure to desired control band.

RO Check PZR Pressure under operator control. (YES)

RO Check PC-444J, PZR PRESSURE operating in AUTO. (YES)

RO Check RCS pressure < required for current plant conditions. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --

Scenario #

4 Event #

_4_____ Page 13 of _3;;,;6;;...-. __

---11 Event

Description:

PZR PORV PCV-456 fails 70% OPEN.

Time II Position Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 4, PZR PORV PCV-456 fails 70% OPEN.

EVENT INDICATIONS:

APP-003-C3;PRT HI PRESS APP-003-D6;PZR PORV/SAFETY VLV OPEN APP-003-E6;PZR PORV LN HI TEMP APP-003-F6;PZR SAFETY VLV LINE HI TEMP APP-003-D8;PZR CONTROL HIILO PRESS RO Recognizes PORV is OPEN and takes Immediate Actions of AOP-019, MALFUNCTION OF RCS PRESSURE CONTROL.

SRO Enters AOP-019, MALFUNCTION OF RCS PRESSURE CONTROL.

Immediate Action Step:

Determine if PZR PORVs should be CLOSED:

RO

Check PZR Pressure less than 2335 PSIG, (YES)

Verify both PZR PORVs CLOSED. (NO)

IF any PZR PORV can NOT be CLOSED, THEN close itsPORV BLOCK valve.

Immediate Action Step:

RO Control Heaters and Spray valves to restore RCS Pressure to desired control band.

RO Check PZR Pressure under operator control. (YES)

RO Check PC-444J, PZR PRESSURE operating in AUTO. (YES)

RO Check RCS pressure < required for current plant conditions. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

4 Page 14 of 36 Event

Description:

PZR PORV PcV-456 fails 70% OPEN.

Time I

Position Applicants Actions or Behavior Continuous Action Step:

RO Check PZR pressure less than 2205 PSIG.

IF pressure decreases to < 2205 PSIG, THEN restore pressure within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Or be in MODE 2 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . (lAW LCO 3.4.1)

RO Check BOTH PZR Spray valves CLOSED. (YES)

RO Check CVC-31 1, AUX PZR SPRAY valve CLOSED. (YES)

RO Check APP-003-F8, PZR LO LVL HTR OFF & LTDN SECURE extinguished. (YES)

Determine Heater Capacity:

SRO/RO Contact Maintenance and Engineering to check PZR Heater capacity.

Check PZR Heater capacity REDUCED. (NO)

BOOTH OPERATOR:

When requested, inform the crew that heater capacity has NOT changed since the last Refueling Outage test.

RO Check PZR Pressure stable or trending to required value. (YES)

SRO Implement The EALs.

SRO Contact l&C To Make Repairs To The PZR Pressure Control System.

Review ITS For Applicable LCOs:

LCO 3.4.1 1, Condition B, Close Block valve within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months oR.j AND Remove power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

......;....- Scenario #

4 Event #

_4~ ____ Page 14 of....;3;;.;;6 ___

~1 Event

Description:

PZR PORV PCV-456 fails 70% OPEN.

Time I

Position II Applicant's Actions or Behavior Continuous Action Step:

RO Check PZR pressure less than 2205 PSIG.

IF pressure decreases to < 2205 PSIG, THEN restore pressure within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Or be in MODE 2 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . (lAW LCO 3.4.1)

RO Check BOTH PZR Spray valves CLOSED. (YES)

RO Check CVC-311, AUX PZR SPRAY valve CLOSED. (YES)

RO Check APP-003-F8, PZR LO LVL HTR OFF & LTDN SECURE extinguished. (YES)

Determine Heater Capacity:

SRO/RO

Contact Maintenance and Engineering to check PZR Heater capacity.

Check PZR Heater capacity REDUCED. (NO)

BOOTH OPERATOR: When requested, inform the crew that heater capacity has NOT changed since the last Refueling Outage test.

RO Check PZR Pressure stable or trending to required value. (YES)

SRO Implement The EALs.

SRO Contact I&C To Make Repairs To The PZR Pressure Control System.

Review ITS For Applicable LCOs:

SRO LCO 3.4.11, Condition B, Close Block valve within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Remove power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

5 Page 15 of 36 Event

Description:

HCV-1 459, Heater Bypass Valve fails open.

Time Position Applicants Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 5, HCV-1 459, Heater Bypass Valve failing OPEN.

EVENT INDICATIONS:

APP-007-B6, HDT HI/LO LVL BOP Recognizes Heater Bypass is OPEN and takes Immediate Actions of AOP-01 0, MAIN FEEDWATER/CONDENSATE MALFUNCTION.

SRO Enters AOP-010.

Immediate Action Step:

BOP Check Feedwater Regulating Valves operating properly in Auto or Manual. (FCV-478, 488 and 498) (YES)

Continuous Action Step:

BOP Check Reactor Trip setpoint being approached. (NO)

IF a Reactor Trip Setpoint is being approached, THEN trip the Reactor and Go To PATH-i.

RO/BOP Makes PA announcement for entry into AOP-0i0.

SRO Goes to the appropriate Step from the table. (HCV-i 459 Failed OPEN, Step 35)

NOTE:

HCV-i 459, LP HEATERS BYP, is interlocked with QCV-i 0426, SECONDARY BYPASS. HCV-1 459 failing open will also result in QCV-i 0426 opening.

Appendix D NUREG-i 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

~- Scenario #

4 Event #

_5~ ____ Page 15 of...,;3;,;;6 ___

-l 1

Event

Description:

HCV-1459, Heater Bypass Valve fails open.

Time I

Position I

Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 5, HCV-1459, Heater Bypass Valve failing OPEN.

EVENT INDICATIONS:

APP-007-B6, HDT HI/LO LVL BOP Recognizes Heater Bypass is OPEN and takes Immediate Actions of AOP-010, MAIN FEEDWATER/CONDENSATE MALFUNCTION.

SRO Enters AOP-01 O.

Immediate Action Step~

BOP Check Feedwater Regulating Valves operating properly in Auto or Manual. (FCV-478, 488 and 498) (YES)

Continuous Action Step:

BOP Check Reactor Trip setpoint being approached. (NO)

IF a Reactor Trip Setpoint is being approached, THEN trip the Reactor and Go To PATH-1.

RO/BOP Makes PA announcement for entry into AOP-010.

SRO Goes to the appropriate Step from the table. (HCV-1459 Failed OPEN, Step 35)

NOTE:

HCV-1459, LP HEATERS BYP, is interlocked with QCV-10426, SECONDARY BYPASS. HCV-1459 failing open will also result in QCV-10426 opening.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

5 Page 16 of 36 Event

Description:

HCV-1459, Heater Bypass Valve fails open.

Time Position Applicants Actions or Behavior BOP BOP BOP RO/BOP BOP RO SRO SRO BOOTH OPERATOR:

When requested, inform the crew that:

MFP A is.605 KAMPS, MFP B is.590 KAMPS.

Condensate Pump A is 295 AMPS, B is 305 AMPS.

HDP A is 72 AMPS, B is 68 AMPS.

Determine If HCV-1 459 Has Failed:

Check HCV-1 459, LP HEATERS BYP, OPEN. (YES)

Maintain Reactor Power < 100% using Attachment 1.

(Due to the low power, a power reduction will not be necessary)

Continue to reduce power using Attachment 1 until Feed Water Pump suction pressures are > 400 PSIG. (Local Indication) o P1-1433

- A FW PUMP SUCTION PRESSURE.

o P1-i 434

- B FW PUMP SUCTION PRESSURE.

Check Feed Water Pump suction pressures > 400 PSIG. (YES)

Verify HCV-1 459 CLOSED. (Valve can be closed from the RTGB)

Contact I&C To Troubleshoot AND Correct HCV-1 459 Problem.

Check SIG Level at or trending to PROGRAM. (YES)

Check TAvG at or trending to TREF. (YES)

Implement the EALs.

Check current loading for the following pumps less than MAXIMUM:

Main Feedwater Pump

- 0.715 KAMPS Condensate Pumps

- 370 AMPS Heater Drain Pumps

- 90 AMPS Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

--..;.....- Scenario #

4 Event #

5 Page 16 of 36

~--------

~~----~I Event

Description:

HCV-1459, Heater Bypass Valve fails open.

Time II Position II Applicant's Actions or Behavior Determine If HCV-1459 Has Failed:

Check HCV-1459, LP HEATERS BYP, OPEN. (YES)

Maintain Reactor Power < 100% using Attachment 1.

BOP (Due to the low power, a power reduction will not be necessary)

Continue to reduce power using Attachment 1 until Feed Water Pump suction pressures are> 400 PSIG. (Local Indication) 0 PI-1433 - "A" FW PUMP SUCTION PRESSURE.

0 PI-1434 - "B" FW PUMP SUCTION PRESSURE.

BOP Check Feed Water Pump suction pressures> 400 PSIG. (YES)

BOP Verify HCV-1459 CLOSED. (Valve can be closed from the RTGB)

RO/BOP Contact I&C To Troubleshoot AND Correct HCV-1459 Problem.

BOP Check S/G Level at or trending to PROGRAM. (YES)

RO Check T AVG at or trending to T REF. (YES)

SRO Implement the EALs.

Check current loading for the following pumps less than MAXIMUM:

SRO Main Feedwater Pump - 0.715 KAMPS Condensate Pumps - 370 AMPS Heater Drain Pumps - 90 AMPS 800TH OPERATOR: When requested, inform the crew that:

MFP "A" is.605 KAMPS, MFP "8" is.590 KAMPS.

Condensate Pump "A" is 295 AMPS, "8" is 305 AMPS.

HOP "A" is 72 AMPS, "8" is 68 AMPS.

Appendix D NUREG-1021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

5 Page 17 of 36 Event

Description:

HCV-1 459, Heater Bypass Valve fails open.

Time Position Applicants Actions or Behavior SRO Determine Iodine Sampling Requirements:

Check Power Change> 15% IN ONE HOUR. (NO)

RO Check APP005-B5, ROD BANKS AIB/C/D LO LIMIT, extinguished.

(YES)

RO Monitor Axial Flux Difference To Ensure Compliance With ITS 3.2.3.

SRO Notify Load Dispatcher Of The Units Load Capability.

SRO Return To Procedure And Step In Effect.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: --

Scenario #

4 Event #

_5=--____ Page 17 of

.....;3;.,.;;6 ___

-iI Event

Description:

HCV-1459, Heater Bypass Valve fails open.

Time I

Position II Applicant's Actions or Behavior SRO Determine Iodine Sampling Requirements:

Check Power Change> 15% IN ONE HOUR. (NO)

RO Check APP-005-B5, ROD BANKS AlB/C/O LO LIMIT, extinguished.

(YES)

RO Monitor Axial Flux Difference To Ensure Compliance With ITS 3.2.3.

SRO Notify Load Dispatcher Of The Unit's Load Capability.

SRO Return To Procedure And Step In Effect.

Appendix 0 NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

6 & 7 Page 18 of 36 Event

Description:

High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time Position Applicants Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 6, Turbine bearing #3 vibrations will increase above the alarm setpoint and require manual Reactor and Turbine trips.

EVENT INDICATIONS:

APP-008-A8; TURBINE SUPERVISORY INSTRUMENT (Will reflash as each bearing vibration increases greater than 7 mils)

Turbine Generator Supervisory Recorder and Vibration module bearings in alarm.

BOP SRO BOP Recognizes alarm, monitors vibration and references APP-008-A8.

Verify lube oil cooler discharge temperature between 1 15

125 degrees F. (YES)

If turbine bearing temperature is > 225 degrees F, trip the turbine. (NO)

Enters AOP-006, TURBINE ECCENTRICITY / VIBRATION.

Check Turbine Speed < 600 RPM. (NO, Go To Step 4)

Vary load (MW and/or VARS) or turbine speed.

BOP o

(Crew may adjust VARS Up or Down using the Voltage Regulator to attempt to stabilize the vibration)

Vary Hydrogen Side or Air Side Seal Oil temperatures.

o__(Crew_may_direct the_AO_to_adjust_Seal_Oil BOP Continuous Action Step:

Check Bearing Vibration Levels on the TURBINE GENERATOR SUPERVISORY RECORDER less than 14.0 MILS. (YES)

NOTE:

At this time, vibration level is less than 14 mils but Step 4 RNO will be implemented as vibration increases to> 14 mils.

Attempt to decrease or stabilize vibration by at least one of the following methods:

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: --

Event

Description:

Operator Action Form ES-D-2 Scenario #

4 Event #

6 & 7 Page 18 of 36

~I High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 6, Turbine bearing #3 vibrations will increase above the alarm setpoint and require manual Reactor and Turbine trips.

EVENT INDICATIONS:

APP-OOS-AS; TURBINE SUPERVISORY INSTRUMENT (Will reflash as each bearing vibration increases greater than 7 mils)

Turbine Generator Supervisory Recorder and Vibration module bearings in alarm.

Recognizes alarm, monitors vibration and references APP-OOB-AB.

Verify lube oil cooler discharge temperature between 115 -

BOP 125 degrees F. (YES)

If turbine bearing temperature is > 225 degrees F, trip the turbine. (NO)

SRO Enters AOP-006, TURBINE ECCENTRICITY / VIBRATION.

BOP Check Turbine Speed:s 600 RPM. (NO, Go To Step 4)

Continuous Action Step:

BOP Check Bearing Vibration Levels on the TURBINE GENERATOR SUPERVISORY RECORDER less than 14.0 MILS. (YES)

NOTE:

At this time, vibration level is less than 14 mils but Step 4 RNO will be implemented as vibration increases to > 14 mils.

Attempt to decrease or stabilize vibration by at least one of the following methods:

Vary load (MW and/or VARS) or turbine speed.

BOP 0

(Crew may adjust VARS Up or Down using the Voltage Regulator to attempt to stabilize the vibration)

Vary Hydrogen Side or Air Side Seal Oil temperatures.

0 (Crew may direct the AO to adjust Seal Oil Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

6 & 7 Page 19 of 36 Event

Description:

High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time I

Position I

Anolicants Actions or Behavior BOOTH OPERATOR:

As a Security Officer patrolling the Protected Area, provide input to the crew that increased vibration is noted on the Turbine Deck and adjacent to the Control Room.

NOTE:

At this time, vibration level on #3 bearing will have increased to greater than 14 mils and Step 4 RNO actions will be implemented.

SRO Transitions to FRP-Si.

SRO SRO RO Temperatures in an attempt to stabilize the vibration)

Vary Turbine Lube Oil cooler discharge temperature.

Increase Exciter Air discharge temperature.

Continuous Action Step:

Check Bearing Vibration Levels on the TURBINE GENERATOR SUPERVISORY RECORDER less than 14.0 MILS. (NO)

IF vibration is felt in the Control Room, THEN perform one of the following:

IF the REACTOR TRIP FROM TURB BLOCK P-7 permissive light is extinguished, THEN trip the Reactor AND Go To PATH

1. (YES)

Directs the RO to manually trip the Reactor and perform the immediate actions of PATH-i.

PATH-i Actions Immediate Action Step Check REACTOR TRIP as follows:

Reactor trip main and bypass breakers OPEN. (NO)

Rod Position indication ZERO. (NO)

Rod Bottom Lights ILLUMINATED. (NO)

Neutron Flux DECREASING. (NO)

Appendix D NUREG-i021, Rev. 9, Supp. i Appendix D Op Test No.:

Event

Description:

Operator Action Form ES-D-2 Scenario #

4 Event #

_6;;..&;.;...;..7 ___ Page 19 of

_3.;..;6~ __

---!I High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

I Time I

Position II Applicant's Actions or Behavior Temperatures in an attempt to stabilize the vibration)

Vary Turbine Lube Oil cooler discharge temperature.

Increase Exciter Air discharge temperature.

BOOTH OPERATOR: As a Security Officer patrolling the Protected Area, provide input to the crew that increased vibration is noted on the Turbine Deck and adjacent to the Control Room.

NOTE:

At this time, vibration level on #3 bearing will have increased to greater than 14 mils and Step 4 RNO actions will be implemented.

Continuous Action Step:

Check Bearing Vibration Levels on the TURBINE GENERATOR SUPERVISORY RECORDER less than 14.0 MILS. (NO)

SRO IF vibration is felt in the Control Room, THEN perform one of the following:

IF the REACTOR TRIP FROM TURB BLOCK P-7 permissive light is extinguished, THEN trip the Reactor AND Go To PATH-

1. (YES)

SRO Directs the RO to manually trip the Reactor and perform the immediate actions of PA TH-1.

PATH-1 Actions Immediate Action Step:

Check REACTOR TRI P as follows:

Reactor trip main and bypass breakers OPEN. (NO)

RO Rod Position indication ZERO. (NO)

Rod Bottom Lights ILLUMINATED. (NO)

Neutron Flux DECREASING. (NO)

SRO Transitions to FRP-S.1.

Appendix D NUREG-1021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

6 & 7 Page 20 of 36 Event

Description:

High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time I

Position II Applicants Actions or Behavior RO/SRO BOP FRP-S.1 Actions Immediate Action Step:

Perform the following:

Depress both Reactor Trip pushbuttons.

If Reactor Trip breakers will not open, then perform the following:

Insert control rods Dispatch an operator to the MG Set Room to trip Reactor Trip Breakers A and B AND MG Set Generator Circuit Breakers A and B.

Dispatch an operator to 480V Busses 2B and 3 to trip Rod Drive MG Set Breakers A and B.

NOTE:

SRO will notify the Inside and Outside Auxiliary Operators while Control Room operators take appropriate actions. 3 minutes after being contacted, OPEN the RTBs and MG set breakers.

BOP Verify All AFW Pumps running. (NO, SDAFW Pump will NOT start and APP-007-F5, SD AFW PMP LO DISCH PRESS TRIP will illuminate)

BOP Immediate Action Step:

Check Turbine Trip as follows:

Both Turbine Stop valves closed. (NO)

OR All Governor valves closed. (NO)

Perform the following:

Manually trip the Turbine by simultaneously depressing the THINK and TURBINE TRIP Pushbuttons Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Op Test No.:

Event

Description:

Operator Action Form ES-D-2 Scenario #

4 Event #

_6;;;..&;;;;.....;..7 ___ Page 20 of

....,;3:;.;;;6 ___

...,1 High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time I

Position II Applicant's Actions or Behavior FRP-S.1 Actions Immediate Action Step:

Perform the following:

Depress both Reactor Trip pushbuttons.

If Reactor Trip breakers will not open, then perform the following:

RO/SRO I nsert control rods.

Dispatch an operator to the MG Set Room to trip Reactor Trip Breakers "A" and "B" AND MG Set Generator Circuit Breakers "A" and "B".

Dispatch an operator to 480V Busses 2B and 3 to trip Rod Drive MG Set Breakers 'W' and "B".

NOTE:

SRO will notify the Inside and Outside Auxiliary Operators while Control Room operators take appropriate actions. 3 minutes after being contacted, OPEN the RTBs and MG set breakers.

Immediate Action Step:

Check Turbine Trip as follows:

BOP Both Turbine Stop valves closed. (NO)

OR

All Governor valves closed. (NO)

Perform the following:

BOP Manually trip the Turbine by simultaneously depressing the THINK and TURBINE TRIP Pushbuttons BOP Verify All AFW Pumps running. (NO, SDAFW Pump will NOT start and APP-007-FS, SO AFW PMP LO DISCH PRESS TRIP will illuminate)

Appendix 0 NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

6 & 7 Page 21 of 36 Event

Description:

High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time Position II Applicants Actions or Behavior RO RO RO RO RO RO Initiate Emergency Boration, verify Charging flowpath established:

CVC-310B, LOOP 2 COLD LEG CHG, OPEN.

HIC-i 21, Charging Flow Controller demand at 0%.

Verify Two Charging Pumps running at full speed. (NO, will increase speed on the Charging Pump running in Manual)

Verify Boric Acid Pump aligned for blend running. (YES)

Verify MOV-350, BA TO CHARGING PMP SUCT, OPEN. (YES)

Check flow on Fl-i 10, BORIC ACID BYPASS FLOW, indicated. (YES)

Verify Charging Flow to RCS on Fl-i 22A. (YES)

Continuous Action Step:

RO Check SI initiated. (NO)

IF an SI Signal occurs, THEN verify auto start of all SI equipment using Supplement L while continuing with this procedure.

BOP Verify CONTAINMENT VENTILATION ISOLATION initiated. (NO)

NOTE:

It is expected that the CV Ventilation Signal has not been initiated.

To initiate the CV Ventilation Signal, the operator will take R-1 1 or R-12 high voltage pushbutton to OFF and return to ON to initiate the signal.

This can be verified by the 2 Amber lights ILLUMINATED below the Radiation Monitoring System panel labeled CV Ventilation Isolation Signal Relay V-i and V-2.

Appendix D NUREG-i 021, Rev. 9, Supp. 1 Appendix 0 Op Test No.:

~-

Event

Description:

Operator Action Form ES-O-2 Scenario #

4 Event #

6 & 7 Page 21 of 36

~~------

~I High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time II Position II Applicant's Actions or Behavior Initiate Emergency Boration, verify Charging flowpath established:

RO CVC-310B, LOOP 2 COLD LEG CHG, OPEN.

HIC-121, Charging Flow Controller demand at 0%.

RO Verify Two Charging Pumps running at full speed. (NO, will increase speed on the Charging Pump running in Manual)

RO Verify Boric Acid Pump aligned for blend running. (YES)

RO Verify MOV-350, BA TO CHARGING PMP SUCT, OPEN. (YES)

RO Check flow on FI-11 0, BORIC ACID BYPASS FLOW, indicated. (YES)

RO Verify Charging Flow to RCS on FI-122A. (YES)

BOP Verify CONTAINMENT VENTILATION ISOLATION initiated. (NO)

NOTE:

It is expected that the CV Ventilation Signal has not been initiated.

To initiate the CV Ventilation Signal, the operator will take R-11 or R-12 high voltage pushbutton to OFF and return to ON to initiate the signal.

This can be verified by the 2 Amber lights ILLUMINATED below the Radiation Monitoring System panel labeled "CV Ventilation Isolation Signal Relay V-1 and V-2."

Continuous Action Step:

RO Check SI initiated. (NO)

IF an SI Signal occurs, THEN verify auto start of all SI equipment using Supplement L while continuing with this procedure.

Appendix 0 NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

6 & 7 Page 22 of 36 Event

Description:

High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time Position Applicants Actions or Behavior Check if the following trips have occurred:

RO/BOP Reactor Trip. (YES)

Turbine Trip. (YES)

Continuous Action Step:

Check if Reactor is subcritical:

RO Check Power Range indication less than 5%. (YES)

Check Intermediate Range indication negative SUR. (YES, Go To Step 24)

RO Check IRPI less than two rods stuck out. (YES)

Stop the RCS Boration:

Verify MOV-350 closed.

RO Verify switch for Boric Acid pump aligned for blend in AUTO.

Check emergency boration performed using MOV-350.

Notify Engineering to evaluate RCP Bearing temperatures and No. 1 seal leakoff temperatures/flowrates.

Check emergency boration performed using RWST flowpath and it is RO desired to align Charging Pump suction to the VCT. (NO, Go To Step 25.i)

RO Control Charging Pump speed to control PZR Level.

RO Reset SPDS/lnitiate monitoring of Critical Safety Function Status Trees.

SRO Return to procedure and step in effect.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.:

~-

Event

Description:

Operator Action Form ES-D-2 Scenario #

4 Event #

_6;;..&;.;...;..7 ___ Page 22 of....;3;;.;.6 ___

~1 High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time II Position I

Applicant's Actions or Behavior Check if the following trips have occurred:

RO/SOP Reactor Trip. (YES)

Turbine Trip. (YES)

Continuous Action Step:

Check if Reactor is subcritical:

RO

Check Power Range indication less than 5%. (YES)

Check Intermediate Range indication negative SUR. (YES, Go To Step 24)

RO Check IRPIless than two rods stuck out. (YES)

Stop the RCS Soration:

Verify MOV-3S0 closed.

RO Verify switch for Soric Acid pump aligned for blend in AUTO.

Check emergency boration performed using MOV-3S0.

Notify Engineering to evaluate RCP Searing temperatures and No.1 seal leakoff temperatures/flowrates.

Check emergency boration performed using RWST flowpath and it is RO desired to align Charging Pump suction to the VCT. (NO, Go To Step

\\

2S.i)

RO Control Charging Pump speed to control PZR Level.

RO Reset SPDS/lnitiate monitoring of Critical Safety Function Status Trees.

SRO Return to procedure and step in effect.

Appendix D NUREG-1021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

6 & 7 Page 23 of 36 Event

Description:

High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time I

Position Anolicants Actions or Behavior SRO RO BOP BOP RO Directs entry at the beginning of PATH-i.

PATH-i Actions IMMEDIATE ACTION STEP:

Reactor Tripped. (YES)

IMMEDIATE ACTION STEP:

Turbine Tripped. (YES)

IMMEDIATE ACTION STEP:

E-1 AND E-2 energized. (YES)

IMMEDIATE ACTION STEP:

o SI Initiated. (NO) o SI Initiation Required. (NO)

Continuous Action Step:

RO Check SI signal initiated. (NO, Go to Step 4)

IF SI initiation occurs during this procedure, THEN Go to PATH-i, Entry Point A.

RO SRO SRO Verify two Charging Pumps running. (YES)

Transition to EPP-4, REACTOR TRIP RESPONSE.

Continuous Action Step:

Determine if procedure exit is warranted:

Check attack on RNP site in progress. (NO)

Check a total loss of SW OR Loss of Lake Robinson Dam integrity in progress. (NO, Go to Step 2)

Appendix D NUREG-iO2i, Rev. 9, Supp. 1 Appendix D Op Test No.: --

Event

Description:

Operator Action Form ES-D-2 Scenario #

4 Event #

_6_&_7 ___ Page 23 of......:3:;,.;6 ___

-l1 High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time II Position Applicant's Actions or Behavior SRO Directs entry at the beginning of PATH-1.

PATH-1 Actions IMMEDIATE ACTION STEP:

RO Reactor Tripped. (YES)

IMMEDIATE ACTION STEP:

BOP Turbine Tripped. (YES)

IMMEDIATE ACTION STEP:

BOP E-1 AND E-2 energized. (YES)

IMMEDIATE ACTION STEP:

RO 0

SI Initiated. (NO) 0 SI Initiation Required. (NO)

RO Verify two Charging Pumps running. (YES)

SRO Transition to EPP-4, REACTOR TRIP RESPONSE.

Continuous Action Step:

Determine if procedure exit is warranted:

SRO Check attack on RNP site in progress. (NO)

Check atotal loss of SW OR Loss of Lake Robinson Dam integrity in progress. (NO, Go to Step 2)

Continuous Action Step:

RO Check SI signal initiated. (NO, Go to Step 4)

IF SI initiation occurs during this procedure, THEN Go to PATH-1, Entry Point A.

Appendix D NUREG-1021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

6 & 7 Page 24 of 36 Event

Description:

High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time Position AnDlicants Actions or Behavior SRO CREW Reset SPDS and initiate monitoring of CSFSTs.

Open Foldout A.

RCP Trip criteria. IF BOTH conditions are met, THEN stop all RCPs: (NO) a SI Pumps

- AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE o

RCS Subcooling

- < 35 degrees F [55 degrees F]

SI actuation criteria. IF EITHER condition occurs, THEN Actuate SI and Go To PATH-i, Entry Point A:

o RCS Subcooling

- < 35 degrees F [55 degrees F]

o PZR Level

- CAN NOT BE MAINTAINED> 10% [32%]

MSR Isolation criteria. IF ANY Purge OR Shutoff Valve does not indicate fully closed, THEN place the associated RTGB Switch to CLOSE.

Continuous Action Step:

Determine Feedwater status:

Check RCS average temperature less than 554 °F. (YES)

BOP Verify FW REG VALVEs CLOSED. (YES)

Establish FW bypass flow to maintain level in intact S/Gs between 39% and 50%. (Will stop MDAFW pumps and throttle open ALL S/G Bypass valves to control SIG_level)

RO Check All Control Rods fully inserted. (YES)

RO SRO Check RCS temperature stable or trending to 547 degrees F. (YES)

Transitions to Step 12, based on SW pressure between 40-50 PSIG.

Appendix D NUREG-i 021, Rev. 9, Supp. 1 Appendix D Op Test No.: --

Event

Description:

Operator Action Form ES-D-2 Scenario #

4 Event #

6 & 7 Page 24 of 36

~I High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time I

Position II Applicant's Actions or Behavior SRO Reset SPDS and initiate monitoring of CSFSTs.

CREW Open Foldout A.

RCP Trip criteria. IF BOTH conditions are met, THEN stop all RCPs: (NO) 0 SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 0

RCS Subcooling - < 35 degrees F [55 degrees F]

SI actuation criteria. IF EITHER condition occurs, THEN Actuate SI and Go To PATH-1, Entry Point A:

0 RCS Subcooling - < 35 degrees F [55 degrees F]

0 PZR Level-CAN NOT BE MAINTAINED> 10% [32%]

MSR Isolation criteria. IF ANY Purge OR Shutoff Valve does not indicate fully closed, THEN place the associated RTGB Switch to CLOSE.

RO Check RCS temperature stable or trending to 547 degrees F. (YES)

SRO Transitions to Step 12, based on SW pressure between 40-50 PSIG.

Continuous Action Step:

Determine Feedwater status:

Check RCS average temperature less than 554 of. (YES)

BOP Verify FW REG VALVEs CLOSED. (YES)

Establish FW bypass flow to maintain.level in intact S/Gs between 39% and 50%. (Will stop MDAFW pumps and throttle open ALL S/G Bypass valves to control S/G level)

RO Check All Control Rods fully inserted. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

8, 9, 10 & 11 Page 25 of 36 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time Position Applicants Actions or Behavior BOOTH OPERATOR:

When directed by the Chief Examiner, insert Event 8, Small Break LOCA.

EVENT INDICATIONS:

PZR Level and Pressure decreasing RR-1 Recorder Point #11 for R-1 2 in alarm (later)

Phase A valves will not close automatically Control Room HVAC Exhaust Dampers are not closed.

HVE-19A did not start; HVE-16 did not stop.

NOTE:

The following actions may be performed using OMM-022 guidance:

Safety Injection fails to actuate on the LOCA, the crew will manually initiate SI which will start all SI and RHR pumps, but SI 870A and 870B valves will NOT open.

Sl-870A and Sl-870B must be opened manually and at least one valve must be opened to provide an injection path.

CR HVAC will fail to shift to PRESSURIZATION MODE. The crew will manually start HVE-19A and HVE-16 will have to be manually stopped. CR-D1A-SA and Dl B-SB will close -5 seconds after HVE-16 is stopped.

NOTE:

Phase A fails to actuate, the crew will manually actuate Phase A, but valves CCW-739, CVC-204B and Sl-855 will NOT close on manual actuation of the pushbutton.

RO Verify Phase A Isolation valves are closed. (NO, must be manually actuated using the pushbutton)

CREW Open Foldout A.

RCP Trip criteria. IF BOTH conditions are met, THEN stop all RCPs: (YES) o SI Pumps

- AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE o

RCS Subcooling

- < 35 degrees F [55 degrees F]

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.:

....;...- Scenario #

4 Event #

8,9,10&11 Page 25 of 36

";"~-----11 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 8, Small Break LOCA.

EVENT INDICATIONS:

PZR Level and Pressure decreasing RR-1 Recorder Point #11 for R-12 in alarm (later)

Phase "A" valves will not close automatically Control Room HVAC Exhaust Dampers are not closed.

HVE-19A did not start; HVE-16 did not stop.

NOTE:

The following actions may be performed using OMM-022 guidance:

Safety Injection fails to actuate on the LOCA, the crew will manually initiate SI which will start all SI and RHR pumps, but SI-870A and 870B valves will NOT open.

SI-870A and SI-870B must be opened manually and at least one valve must be opened to provide an injection path.

CR HVAC will fail to shift to PRESSURIZATION MODE. The crew will manually start HVE-19A and HVE-16 will have to be manually stopped. CR-D1 A-SA and D1 B-SB will close - 5 seconds after HVE-16 is stopped.

CREW Open Foldout A.

RCP Trip criteria. IF BOTH conditions are met, THEN stop all RCPs: (YES) 0 SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 0

RCS Subcooling - < 35 degrees F [55 degrees F]

NOTE:

Phase A fails to actuate, the crew will manually actuate Phase A, but valves CCW-739, CVC-204B and SI-855 will NOT close on manual actuation of the pushbutton.

RO Verify Phase A Isolation valves are closed. (NO, must be manually actuated using the pushbutton)

Appendix 0 NUREG-1021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

8, 9, 10 & 11 Page 26 of 36 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time Position I

Applicants Actions or Behavior NOTE:

Valves CCW-739, CVC-204B, Sl-855 will NOT close on manual actuation of the pushbutton. They will require manual closure from the RTGB control switches.

BOP Verify FW Isolation valves are closed. (YES)

BOP Verify both FW pumps are tripped. (YES)

BOP Verify both MDAFW pumps are running. (YES)

NOTE:

Crew may elect to reset SI in order to control AFW and SIG levels.

BOOTH OPERATOR:

If the crew requests for the vacuum breakers to be opened to assist in turbine coast down, report that the Turbine Engineer requests that they allow the turbine to coast down normally as long as lube oil pressure remains above 5 psig.

BOP If additional Feedwater is required, start the SDAFW pump. (Tripped and will NOT restart)

RO Verify 2 SI pumps running. (YES)

RO Verify Both RHR pumps running. (YES)

RO Verify SI valves are properly aligned. (NO, SI-870A and 870B were manually aligned)

RO At least 1 COW pump is running. (YES)

BOP All SW and SW Booster pumps running. (NO)

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

--.;...- Scenario #

4 Event #

8,9,10&11 Page 26 of...,;3;;.;;6 ___

-11 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time II Position I

Applicant's Actions or Behavior NOTE:

Valves CCW-739, CVC-204B, SI-855 will NOT close on manual actuation of the pushbutton. They will require manual closure from the RTGB control switches.

BOP Verify FW Isolation valves are closed. (YES)

BOP Verify both FW pumps are tripped. (YES)

BOP Verify both MDAFW pumps are running. (YES)

NOTE:

Crew may elect to reset SI in order to control AFW and S/G levels.

BOOTH OPERATOR: If the crew requests for the vacuum breakers to be opened to assist in turbine coast down, report that the Turbine Engineer requests that they allow the turbine to coast down normally as long as lube oil pressure remains above 5 psig.

BOP If additional Feedwater is required, start the SDAFW pump. (Tripped and will NOT restart)

RO Verify 2 SI pumps running. (YES)

RO Verify Both RHR pumps running. (YES)

RO Verify SI valves are properly aligned. (NO, SI-870A and 870B were manually aligned)

RO At least 1 CCW pump is running. (YES)

BOP All SW and SW Booster pumps running. (NO)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

8, 9, 10 & 11 Page 27 of 36 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time II Position Applicants Actions or Behavior BOP BOP RO RO BOP BOP Attempt to start all SW and SW Booster pumps. (NO, SW Booster Pump A and SW Pumps A & B are unavailable)

North OR South SW Header Lo Pressure alarm illuminated. (NO)

Verify CV Fans HVH-1, 2, 3, 4 running. (YES)

Verify IVSW initiated. (YES)

Verify CV Ventilation isolation. (YES)

Verify Control Room Vent aligned for Pressurization Mode. (NO, HVE 1 9A will be started using the control switch, HVE-1 6 will be stopped using the control switch)

NOTE:

HVE-19A will be manually started and HVE-16 will have to be manually stopped. CR-Di A-SA and Di B-SB will close 5 seconds after HVE-16 is stopped.

RO Continuous Action Step:

NOTE:

CSFSTs will indicate an ORANGE PATH on RCS INTEGRITY at some point while the crew is performing actions in PATH-i.

At the discretion of the Chief Examiner and when the crew transitions to FRP-P.i, the scenario can be terminated. If needed, actions for FRP-P.i begin on page 33.

BOP BOP Verify both EDGs running. (YES)

Continuous Action Step:

Restart battery chargers within 30 minutes of power loss using OP 601.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: -- Scenario #

4 Event #

8,9,10&11 Page 27 of

_3;;.;6~ __ ~

Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time II Position II Applicant's Actions or Behavior BOP Attempt to start all SW and SW Booster pumps. (NO, SW Booster Pump "A" and SW Pumps "A" & "B" are unavailable)

BOP North OR South SW Header Lo Pressure alarm illuminated. (NO)

RO Verify CV Fans HVH-1, 2, 3, 4 running. (YES)

RO Verify IVSW initiated. (YES)

BOP Verify CV Ventilation isolation. (YES)

Verify Control Room Vent aligned for Pressurization Mode. (NO, HVE-BOP 19A will be started using the control switch, HVE-16 will be stopped using the control switch)

NOTE:

HVE-19A will be manually started and HVE-16 will have to be manually stopped. CR-01 A-SA and 01 8-S8 will close - 5 seconds after HVE-16 is stopped.

NOTE:

CSFSTs will indicate an ORANGE PATH on RCS INTEGRITY at some point while the crew is performing actions in PATH-1.

At the discretion of the Chief Examiner and when the crew transitions to FRP-P.1, the scenario can be terminated. If needed, actions for FRP-P.1 begin on page 33.

BOP Verify both EDGs running. (YES)

Continuous Action Step:

BOP Restart battery chargers within 30 minutes of power loss using OP-601.

RO Continuous Action Step:

Appendix 0 NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

8, 9, 10 & 11 Page 28 of 36 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time Position fi Applicants Actions or Behavior CV Pressure has remained below 10 psig (YES)

BOP Automatic Steam Line Isolation Initiated. (NO)

BOP Automatic Steam Line Isolation Required. (NO)

BOP Locally open breaker for HVS-1 at MCC-5.

RO RCS pressure> 1350 psig. [1250 psig] (NO)

RO SI Flow Verified. (YES)

RO RCS Pressure Greater than 125 psig. (YES)

BOP At least 300 GPM AFW flow available. (YES)

BOP Verify AFW valves properly aligned.

BOP Control AFW flow to maintain S/G levels between 8% [18%] and 50%.

NOTE:

The crew may reset SI and secure a MDAFW Pump to control SIG level.

RO RCP Thermal barrier cooling water Hi/Lo flow alarms illuminated. (NO)

BOP Place Steam Dump Mode Switch to Steam Pressure.

RO RCS Temp stable at OR trending to 547 degrees F. (NO)

RO RCS temperature> 547 degrees F. (NO)

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -- Scenario #

4 Event #

8,9,10&11 Page 28 of.....;3;;.;;6 ___

-11 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time II Position II Applicant's Actions or Behavior CV Pressure has remained below 10 psig. (YES)

BOP Automatic Steam Line Isolation Initiated. (NO)

BOP Automatic Steam Line Isolation Required. (NO)

BOP Locally open breaker for HVS-1 at MCC-5.

RO RCS pressure> 1350 psig. [1250 psig] (NO)

RO SI Flow Verified. (YES)

RO RCS Pressure Greater than 125 psig. (YES)

BOP At least 300 GPM AFW flow available. (YES)

BOP Verify AFW valves properly aligned.

BOP Control AFW flow to maintain SIG levels between 8% [18%] and 50%.

NOTE:

The crew may reset SI and secure a MDAFW Pump to control S/G level.

RO RCP Thermal barrier cooling water HilLo flow alarms illuminated. (NO)

BOP Place Steam Dump Mode Switch to Steam Pressure.

RO RCS Temp stable at OR trending to 547 degrees F. (NO)

RO RCS temperature> 547 degrees F. (NO)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Scenario #

4 Event #

8, 9, 10 & 11 Page 29 of 36 Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

BOP Attempt to limit cooldown.

If RCS cooldown continues and is not due to SI flow, then close MSIVs and MSIV bypasses.

BOP (The crew should determine that cooldown IS due to SI flow and should NOT close the MSIVs at this time)

RO PZR PORVs closed. (NO)

RO RCS pressure > 2335 PSIG. (NO)

RO Close PZR PORVs.

RO PZR PORVs closed. (NO)

RO Close PORV blocks.

RO PORV blocks closed. (YES)

RO PZR Spray and Aux Spray valves closed. (YES)

RO At least 1 RCP running. (NO)

BOP Any SIG with uncontrolled depressurization. (NO)

BOP Any S/G Completely Depressurized (NO)

BOP R-19s, R-31s and R-15 Rad levels normal (YES)

Time Position Op Test No.:

Event

Description:

Applicants Actions or Behavior Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

~- Scenario #

4 Event #

8,9,10&11 Page 29 of..,.;3;;.,.;6 ___

-11 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time

~

Position II Applicant's Actions or Behavior BOP Attempt to limit cooldown.

If RCS cooldown continues and is not due to SI flow, then close MSIVs BOP and MSIV bypasses.

(The crew should determine that cooldown IS due to SI flow and should NOT close the MSIVs at this time)

RO PZR PORVs closed. (NO)

RO RCS pressure> 2335 PSIG. (NO)

RO Close PZR PORVs.

RO PZR PORVs closed. (NO)

RO Close PORV blocks.

RO PORV blocks closed. (YES)

RO PZR Spray and Aux Spray valves closed. (YES)

RO At least 1 RCP running. (NO)

BOP Any S/G with uncontrolled depressurization. (NO)

BOP Any S/G Completely Depressurized (NO)

BOP R-19s, R-31s and R-15 Rad levels normal (YES)

Appendix D NUREG-1021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

8, 9, 10 & 11 Page 30 of 36 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time Position Applicants Actions or Behavior BOP R-2, R-32A, R-32B Rad levels normal (YES)

RO CV Pressure Normal (NO)

(This is PATH-i, Entry Point C)

RO Reset SPDS and initiate monitoring of CSFSTs.

CREW Open Foldout B.

BOP Request periodic activity samples of all S/Gs.

RO At least 1 RCP running. (NO)

BOP Any S/G with uncontrolled depressurization in progress. (NO)

BOP Control AFW flow to maintain SIG levels between 8% [18%] and 50%.

BOP Any S/G with uncontrolled level increase. (NO)

BOP R-19s, R-31s and R-15 Rad levels normal. (YES)

RO PZR PORVs closed. (NO)

RO RCS pressure > 2335 PSIG. (NO)

RO Close PZR PORVs.

RO PZR PORVs closed. (NO)

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -- Scenario #

4 Event #

8,9,10&11 Page 30 of 36

II Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time II Position I

Applicant's Actions or Behavior BOP R-2, R-32A, R-32B Rad levels normal (YES)

RO CV Pressure Normal (NO)

RO (This is PATH-1, Entry Point C)

Reset SPDS and initiate monitoring of CSFSTs.

CREW Open Foldout B.

BOP Request periodic activity samples of all S/Gs.

RO At least 1 RCP running. (NO)

BOP Any S/G with uncontrolled depressurization in progress. (NO)

BOP Control AFW flow to maintain S/G levels between 8% [18%] and 50%.

BOP Any S/G with uncontrolled level increase. (NO)

BOP R-19s, R-31 sand R-15 Rad levels normal. (YES)

RO PZR PORVs closed. (NO)

RO RCS pressure> 2335 PSIG. (NO)

RO Close PZR PORVs.

RO PZR PORVs closed. (NO)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Event

Description:

Time II Position Scenario #

4 Event #

8, 9, 10 & 11 Page 31 of 36 Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

fi Applicants Actions or Behavior RO Close PORV blocks.

RO Open at least 1 PORV block unless closed to isolate open PZR PORV.

CONTINUOUS ACTION STEP RO If PZR PORV opens on high pressure, then verify reclosure at or below 2335 psig. Close PORV blocks as necessary.

RO Reset SI.

CONTINUOUS ACTION STEP:

CREW If offsite power is lost, then restart emergency safeguard equipment.

RO Reset CV Spray.

RO Reset Phase A and Phase B.

R0 Establish Instrument Air to CV. IF compressor not running, THEN start compressor.

BOP Offsite power available to Charging Pumps. (YES)

RO At least 1 Charging Pump running. (YES)

RO Establish charging flow as necessary.

RO CV Spray Pumps running. (NO)

RO RCS Subcooling greater than 35 [55] degrees F. (NO)

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

.-;...- Scenario #

4 Event #

8,9,10&11 Page 31 of...,;3;,;;6 ___

-l 1

Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time II Position II Applicant's Actions or Behavior RO Close PORV blocks.

RO Open at least 1 PORV block unless closed to isolate open PZR PORV.

CONTINUOUS ACTION STEP RO If PZR PORV opens on high pressure, then verify reclosure at or below 2335 psig. Close PORV blocks as necessary.

RO Reset SI.

CONTINUOUS ACTION STEP:

CREW If offsite power is lost, then restart emergency safeguard equipment.

RO Reset CV Spray.

RO Reset Phase A and Phase B.

RO Establish Instrument Air to CV. IF compressor not running, THEN start compressor.

BOP Offsite power available to Charging Pumps. (YES)

RO At least 1 Charging Pump running. (YES)

RO Establish charging flow as necessary.

RO CV Spray Pumps running. (NO)

RO RCS Subcooling greater than 35 [55] degrees F. (NO)

Appendix D NUREG-1021, Rev. 9, Supp.1

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

1 Scenario #

4 Event #

8, 9, 10 & 11 Page 32 of 36 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time I

Position Applicants Actions or Behavior RO When below 10.10 amps, then energize Source Range detectors and monitor recorder.

RO RCS pressure greater than 275 psig [400 psig] (YES)

RO RCS pressure stable or increasing (NO)

BOP Any S/G with uncontrolled depressurization in progress. (NO)

RCS pressure increasing.

RO (YES) Return to PATH-i, Entry Point C. (Page 30)

(NO) Continue below.

BOP E-1 and E-2 energized by offsite power. (YES)

BOP Starting air receivers re-pressurized to unloaded EDGs. (YES)

BOP Stop the unloaded EDGs.

RO Supplement D components capable of recirculation. (YES)

BOP Aux Building radiation normal. (YES)

RO RCS pressure greater than 275 psig [400 psig]. (YES)

BOP Obtain RCS boron, activity, and Hydrogen samples.

CREW Transition to EPP-8, POST LOCA CID AND DEPRESSURIZATION.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

Scenario #

4 Event #

8,9,10&11 Page 32 of.....;3;;,;6 ___

...,1 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time i

Position II Applicant's Actions or Behavior RO When below 10-10 amps, then energize Source Range detectors and monitor recorder.

RO RCS pressure greater than 275 psig [400 psig] (YES)

RO RCS pressure stable or increasing (NO)

BOP Any S/G with uncontrolled depressurization in progress. (NO)

RCS pressure increaSing.

RO (YES) Return to PATH-1, Entry Point C. (Page 30)

(NO) Continue below.

BOP E-1 and E-2 energized by offsite power. (YES)

BOP Starting air receivers re-pressurized to unloaded EDGs. (YES)

BOP Stop the unloaded EDGs.

RO Supplement D components capable of recirculation. (YES)

BOP Aux Building radiation normal. (YES)

RO RCS pressure greater than 275 psig [400 psig]. (YES)

BOP Obtain RCS boron, activity, and Hydrogen samples.

CREW Transition to EPP-8, POST LOCA C/D AND DEPRESSURIZATION.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

8, 9, 10 & 11 Page 33 of 36 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time Position Applicants Actions or Behavior FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK Actions.

Continuous Action Step BOP Check CST level less than 10%. (NO)

IF CST level decreases to less than 10%, THEN perform Step 2.

Determine If RCS Cooldown Is Due To A Large Break LOCA:

BOP RCS pressure is less than 275 PSIG [400 PSIG] (NO)

AND RHR flow on Fl-605 greater than 1200 GPM. (NO)

Check RCS Cold leg temperature decreasing.

BOP (NO, skip the next 5 Steps) (YES, continue below)

Attempt to Stop RCS cooldown:

Verify STEAM LINE PORVs CLOSED.

RO/BOP Verify Condenser Dumps CLOSED.

Check RHR system aligned for core cooling. (NO)

BOP Check any S/G intact. (YES)

Check level in at least one S/G > 8% [18%].

BOP WHEN level in at least one S/G is> 8% [18%], THEN perform Step 8.

BOP Control Feed flow to intact S/G to stop RCS cooldown.

Identify and Isolate faulted SIG:

BOP Any S/G pressure decreasing in an uncontrolled manner. (NO)

OR Any SIG completely depressurized. (NO)

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

Scenario #

4 Event #

8,9,10&11 Page 33 of.....;3:..;:;6 ___

-11 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time II Position I

Applicant's Actions or Behavior FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK Actions.

Continuous Action Step:

BOP Check CST level. less than 10%. (NO)

IF CST level decreases to less than 10%, THEN perform Step 2.

Determine If RCS Cool down Is Due To A Large Break LOCA:

BOP RCS pressure is less than 275 PSIG [400 PSIG] (NO)

AND RHR flow on FI-605 greater than 1200 GPM. (NO)

BOP Check RCS Cold leg temperature decreasing.

(NO, skip the next 5 Steps) (YES, continue below)

Attempt to Stop RCS cooldown:

Verify STEAM LINE PORVs CLOSED.

RO/BOP Verify Condenser Dumps CLOSED.

Check RHR system aligned for core cooling. (NO)

BOP Check any S/G intact. (YES)

BOP Check level in at least one S/G > 8% [18%].

WHEN level in at least one S/G is > 8% [18%], THEN perform Step 8.

BOP Control Feed flow to intact S/G to stop RCS cooldown.

Identify and Isolate faulted S/G:

Any S/G pressure decreasing in an uncontrolled manner. (NO)

BOP OR Any S/G completely depressurized. (NO)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

8, 9, 10 & 11 Page 34 of 36 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time Position II Applicants Actions or Behavior Check PORV block valves available.

RO Power available. (YES, Power is available to RC-536)

At least one open. (YES)

Continuous Action Step:

Check LTOP in service. (NO)

RO Check RCS pressure < 2335 PSIG. (YES)

Verify PORVs CLOSED. (NO, RC-535 is closed to isolate PCV-456) o Verify associated PORV block valve is closed.

RO Check SI Pumps running. (YES)

Determine if SI can be terminated.

RO Check RCS subcooling > 85 degrees F [105 degrees F]. (NO)

RO Check ALL RCPs stopped. (YES)

Determine If An RCP Can Be Started:

RO Check RCS Subcooling> 35 degrees F [55 degrees F]

(NO, GoTo Step 44)

RO Check Cooldown Rate In RCS Cold Legs> 100 degrees F in any 60 minute period. (YES)

RO Check RCS Temperature has been stable for ONE hour. (NO)

Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

......;....- Scenario #

4 Event #

8,9,10&11 Page 34 of......;3;.;;6 ___

..,1 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time A

licant's Actions or Behavior Check PORV block valves available.

RO Power available. (YES, Power is available to RC-536)

At least one open. (YES)

Continuous Action Step:

Check L TOP in service. (NO)

RO Check RCSpressure < 2335 PSIG. (YES)

Verify PORVs CLOSED. (NO, RC-535 is closed to isolate PCV-456) 0 Verify associated PORV block valve is closed.

RO Check SI Pumps running. (YES)

Determine if SI can be terminated.

RO

Check RCS subcooling > 85 degrees F [105 degrees F]. (NO)

RO Check ALL RCPs stopped. (YES)

Determine If An RCP Can Be Started:

RO

Check RCS Subcooling > 35 degrees F [55 degrees F]

(NO, Go To Step 44)

RO Check Cool down Rate In RCS Cold Legs> 100 degrees F in any 60 minute period. (YES)

RO Check RCS Temperature - has been stable for ONE hour. (NO)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

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

1 Scenario #

4 Event #

8,9, 10 & 11 Page 35 of 36 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time Position II Applicants Actions or Behavior Crew SRO Reset SPDS AND Return To Procedure And Step In Effect. (PATH-i)

Crew Observe The Following Restrictions:

Maintain RCS pressure and Cold Leg temperature within the limits of Attachment 1, Post Soak Cooldown Limit Curve, during ALL subsequent actions.

Maintain cooldown rate in RCS Cold Legs less than 50 degrees F/hr OR administrative limits of GP-007, PLANT COOLDOWN FROM HOT SHUTDOWN TO COLD SHUTDOWN, which ever is more restrictive in any 60 minute reriod.

Do NOT cooldown the RCS.

Do NOT increase RCS pressure.

Perform actions of any other procedures in effect which do NOT cooldown the RCS OR increase RCS pressure.

WHEN RCS temperature has been stable for one hour, THEN Go To Step 46.

Appendix D NUREG-i 021, Rev. 9, Supp. i Appendix D Operator Action Form ES-D-2 Op Test No.:

--.;...- Scenario #

4 Event #

8,9,10&11 Page 35 of

_3;;.;6~ __

--I1 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time

~

Position II Applicant's Actions or Behavior Do NOT cooldown the RCS.

Do NOT increase RCS pressure.

Perform actions of any other procedures in effect which do Crew NOT cool down the RCS OR increase RCS pressure.

WHEN RCS temperature has been stable for one hour, THEN Go To Step 46.

Observe The Following Restrictions:

Maintain RCS pressure and Cold Leg temperature within the limits of Attachment 1, Post Soak Cooldown Limit Curve, during ALL subsequent actions.

Crew Maintain cool down rate in RCS Cold Legs less than 50 degrees F/hr OR administrative limits of GP-007, PLANT COOLDOWN FROM HOT SHUTDOWN TO COLD SHUTDOWN, which ever is more restrictive in any 60 minute period.

SRO Reset SPDS AND Return To Procedure And Step In Effect. (PATH-1)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

HLC-08 NRC SCENARIO 4 TURNOVER SHEET POWER LEVEL: 50%, 150 MWD/MTU.

Returning to RTP following a short Maintenance Outage.

BORON CONCENTRATION: 1306 ppm EQUIPMENT UNDER CLEARANCE:

SW Booster Pump A is Out-Of-Service for Motor Coupling Alignment.

o LCO 3.7.7-A has been entered and is in hour 18 of a 72 TSAS.

o Expected return is within 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

EQUIPMENT STATUS:

Main Turbine bearings #2, 3 and 4 vibration is elevated. All actions to inform station management have been performed.

INSTRUCTIONS FOR THE WATCH:

Increase power to 75% RTP.

There are NO ramp rate restrictions.

Appendix D NUREG-1021, Rev. 9, Supp. 1 HLC-08 NRC SCENARIO 4 TURNOVER SHEET POWER LEVEL: 50%,150 MWD/MTU.

Returning to RTP following a short Maintenance Outage.

BORON CONCENTRATION: 1306 ppm EQUIPMENT UNDER CLEARANCE:

SW Booster Pump "A" is Out-Of-Service for Motor Coupling Alignment.

o LCO 3.7.7-A has been entered and is in hour 18 of a 72 TSAS.

o Expected return is within -18 hours.

EQUIPMENT STATUS:

Main Turbine bearings #2, 3 and 4 vibration is elevated. All actions to inform station management have been performed.

INSTRUCTIONS FOR THE WATCH:

Increase power to 75% RTP.

There are NO ramp rate restrictions.

Appendix D NUREG-1021, Rev. 9, Supp. 1

ML101970321

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