ML093430213
| ML093430213 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/07/2009 |
| From: | Bruno Caballero NRC/RGN-II/DRS/OLB |
| To: | Southern Nuclear Operating Co |
| References | |
| 50-321/09-302, 50-366/09-302 | |
| Download: ML093430213 (142) | |
Text
FACILITY NAME: _~H.;.;..A..;;..;T....;;C;...;..H-=---_________ _
Section 4 REPORT NUMBER: 05000321/2009302 AND 05000366/2009302 DRAFT SIMULATOR SCENARIOS CONTENTS:
o Draft Simulator Scenarios o Each containing ES-D-1 "Scenario Outline" o Each containing ES-D-2 "Required Operator Actions" Location of Electronic Files:
O;\\Hatch Examinations\\lnitial Exam 2009-302 Submitted By:
Bruno Caballero FACILITY NAME: _~H.;.;;...A..;;..;;T __
C;...;...H ____________ _
Section 4 REPORT NUMBER: 05000321/2009302 AND 05000366/2009302 DRAFT SIMULATOR SCENARIOS CONTENTS:
o Draft Simulator Scenarios o Each containing ES-D-1 "Scenario Outline" o Each containing ES-D-2 "Required Operator Actions" Location of Electronic Files:
O:\\Hatch Examinations\\lnitial Exam 2009-302 Submitted By:
Bruno Caballero verifiedBy1YlJj. ~k
Page 1 of 31 Appendix D Scenario Outline Form ES-D-l NRC Draft Facility:
E. I Hatch Scenario No.:
5-01 Op-Test No.:
2009-302 Examiners:
Operators:
SRO RO BOP Initial Conditions. Unit 2 is at 60% RTP Turnover: Continue reactor startup and place the '2A' RFPT in service. 2D11-K615B, Offgas Post treatment radiation monitor, failed Downscale, RAS written. 2C Condo Booster pump is Danger Tagged Out for breaker pm with tag out restoration in progress.
Event Malf. No.
Event Event No.
Type*
Description 1
Continue startup and place the RFPT '2A' in service.
Raise reactor power with Recirc to 65% power.
3 mtP42_71 A C (ATC)
RBCCW Pump '2A' (simulate sheared shaft) mtP42_72C Standby RBCCW pump fails to start loP42-C001AA3 (manually started) loP42-COOIAG 1 loP42-C001AR2 ET-53 4-diD11-K615A-Sl I (BOP) 2D 11-K615A, Offgas Post treatment radiation monitor, intermittently fails Inop. Stack isolation valves closes and must be re-opened.
5 mfR22_183 C (BOP) 4160 V Emergency Bus '2F' de-energizes. With time compression mfR22_256 TS (SRO) repair and re-energizes. 1B EDG Generator Over current Alarm mf65223700 (OFF)
ET-R43-1 6
C (ATC)
Loss ofCRD.
TS (SRO) 7 mfR22_181 M (ALL) 4160 V Station Service Bus '2D' Fault L.;:;""
mfE4L107 HPCI Failure To Start (2E41-FOOl Stuck) mfG3L242 RWCU Non-Isol Leak in DW diC11B-S4A CRD LOCA Reset A diC11B-S4B CRD LOCA Reset B 8
diE11-F027 A C (ATC)
RHR 2E11-F027A or B RHR Torus Spray or Test Valve failed diE11-F027B closed. (Critical Task) rET-E11-1 IET-Ell-2 9
mfE51_61 C (BOP)
RCIC trips on Overspeed Start CBP 2C then RFPT prior to RWL reaching -100" OR at -155", Emergency Depress due to low reactor water level.
1*
(Critical Task)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
, i\\ ij Page 1 of 31 Appendix D Scenario Outline Form ES-D-1 NRC Draft Facility:
E.IHatch Scenario No.:
5-01 Op-Test No.:
2009-302 Examiners:
Operators:
SRO RO BOP Initial Conditions. Unit 2 is at 60% RTP Turnover: Continue reactor startup and place the '2A' RFPT in service. 2DII-K615B, Offgas Post treatment radiation monitor, failed Downscale, RAS written. 2C Condo Booster pump is Danger Tagged Out for breaker pm with tag out restoration in progress.
Event Malf. No.
Event Event No.
Type*
Description 1
N/A N (BOP)
Continue startup and place the RFPT '2A' in service.
2 N/A R (ATC)
Raise reactor power with Recirc to 65% power.
3 mfP42_71A C (ATC)
RBCCW Pump '2A' (simulate sheared shaft) mfP42_72C Standby RBCCW pump fails to start
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loP42-COOlAA3 (manually started) loP42-COOlAG 1 loP42-COOlAR2 ET-53
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diDII-K615A-SI I (BOP) 2DII-K615A, Offgas Post treatment radiation monitor, intermittently fails Inop. Stack isolation valves closes and must be re-opened.
5 mfR22_183 C (BOP) 4160 V Emergency Bus '2F' de-energizes. With time compression mfR22_256 TS (SRO) repair and re-energizes. IB EDG Generator Over current Alarm rnf65223700 (OFF)
ET-R43-1 6
C (ATC)
Loss ofCRD.
TS (SRO) 7 mfR22_181 M (ALL) 4160 V Station Service Bus '2D' Fault L
mfE4L107 HPCI Failure To Start (2E41-FOOl Stuck)
\\A' rnfG3L242 RWCU Non-Isol Leak in DW diCIIB-S4A CRD LOCA Reset A diCIIB-S4B CRD LOCA Reset B 8
diE 11-F027 A C (ATC)
RHR 2EII-F027 A or B RHR Torus Spray or Test Valve failed diEII-F027B closed. (Critical Task)
ET-Ell-l ET-EII-2 9
mfE51_61 C (BOP)
RCIC trips on Overspeed Start CBP 2C then RFPT prior to RWL reaching -100" OR at -155", Emergency Depress due to low reactor water level.
I (Critical Task) 1*
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Required Operator Actions Form ES-D-2 I ~
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
1 Page 2 of 31 Event
Description:
Placing the "2A" RFPT in service Time I Position I Applicant's Actions or Behavior I
12 mins SRO Orders Operator to place 2A "RFPT" in service BOP
- Enters 34S0-N21-007-2 at step 7.1.11.9.
- Increases speed with the Speed Setter switch to 2100 rpm
- Verifies MIA station permissive light illuminates and that the MIA station is following the Speed Setter.
- Places the TMR Mode switch to MIA.
- Confirms the MIA Station green light illuminates.
- Slowly increases the MIA station to match input and output while monitoring RWL, RFPT 2A discharge pressure and RFPT 2A & 2B speed.
Alarm 656-039, "RFP C005A Disch Flow Low" will clear when RFPT 2A is placed into service. Alarm 650-135, "Heater Trouble" may come in and clear. This is expected for this plant condition.
- Places MIA station for RFPT 2A in auto
- As required, adjust RFP 2A Speed Control Bias Setting to maintain RFPT 2A and 2B speed within 100 RPM.
- Informs ATC to increase power with Recirc to 65% power.
Appendix D Required Operator Actions Form ES-D-2 I,
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
1 Page 2 of 31 Event
Description:
Placing the "2A" RFPT in service Time I Position I Applicant's Actions or Behavior 12 mins SRO Orders Operator to place 2A "RFPT" in service BOP
- Enters 34S0-N21-007-2 at step 7.1.11.9.
- Increases speed with the Speed Setter switch to 2100 rpm
- Verifies MIA station permissive light illuminates and that the MIA station is following the Speed Setter.
- Places the TMR Mode switch to MIA.
- Confirms the MIA Station green light illuminates.
- Slowly increases the MIA station to match input and output while monitoring RWL, RFPT 2A discharge pressure and RFPT 2A & 2B speed.
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Alarm 656-039, "RFP C005A Disch Flow Low" will clear when RFPT 2A is placed into service. Alarm 650-135, "Heater Trouble" may come in and clear. This is expected for this plant condition.
- Places MIA station for RFPT 2A in auto
- As required, adjust RFP 2A Speed Control Bias Setting to maintain RFPT 2A and 2B speed within 100 RPM.
- Informs ATC to increase power with Recirc to 65% power.
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Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
2 Page 3 of 31 Event
Description:
Raise reactor power to approximately 65%
Time I Position I Applicant's Actions or Behavior 10 min SRO
- Directs A TC to increase reactor power to 65 % by increasing Recirc flow. Power increases should be made as recommended by the ST AlReactor Engineering at a rate not to exceed 10 MWe/min.
- Recommends to increase to 65 % power via Recirc not to exceed 10 MWe/min.
- Increases reactor power with Recirc flow IA W 34GO-OPS-005-2 and 34S0-B31-001-2 by depressing either the Master Recirc Flow Control raise pushbuttons or the individual pump Speed Control raise pushbuttons.
- Monitors power increase by observing APRM and generator output indications.
May get the (603-202) "RBM Upscale" and (603-238) "Rod Out Block" alarm, if a peripheral control rod is not selected. This is expected and the operator may select a peripheral rod at this time.
May also get Alarm 650-135, "Heater Trouble" alarm. This is expected at this power level.
Simulator Operator enters the next event after power has been increased by 5% or at the Chief Examiner's request.
Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
2 Page 3 of31 Event
Description:
Raise reactor power to approximately 65%
I Time I Position I Applicant's Actions or Behavior I
10 min SRO
- Directs A TC to increase reactor power to 65 % by increasing Recirc flow. Power increases should be made as recommended by the STAJReactor Engineering at a rate not to exceed 10 MWe/min.
- Recommends to increase to 65 % power via Recirc not to exceed 10 MWe/min.
- Increases reactor power with Recirc flow IA W 34GO-OPS-005-2 and 34S0-B31-001-2 by depressing either the Master Recirc Flow Control
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raise pushbuttons or the individual pump Speed Control raise pushbuttons.
- Monitors power increase by observing APRM and generator output indications.
May get the (603-202) "RBM Upscale" and (603-238) "Rod Out Block" alarm, if a peripheral control rod is not selected. This is expected and the operator may select a peripheral rod at this time.
May also get Alarm 650-135, "Heater Trouble" alarm. This is expected at this power level.
Simulator Operator enters the next event after power has been increased by 5% or at the Chief Examiner's request.
Appendix D Required Operator Actions Form ES-D-2
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, Op* Test No.: 2009*302 Scenario No.:
5*01 Event No.:
3 Page 4 of31 Event
Description:
2A RBCCW Pump shaft shears, 2C RBCCW pump fails to auto start, must be manually started; RB-3 (mfP42_71A, mfP42_72C, loP42_COOIAR2, loP42 COOIAGl,loP42 COOlAA3)
I Position I Applicant's Actions or Behavior 8 min At the Chief Examiner's direction, Simulator operator, INSTRUCT the BOP operator by phone to stay on the line until told to hang up. THEN ENTER:
RB-3
- mfP42_71A
- mfP42_72C, loP42_COOlAR2 (On), loP42_COOIAGl (Off),
loP42_COOlAA3 (Off)
- Acknowledges the alarms and informs the SS that the RBCCW system pressure is low and that the "2C" RBCCW pump did not auto start.
(2C RBCCW may be started manually prior to recognizing failure to auto start.) (There is not an obvious reason for the pressure being low.)
- Directs an Operator to start the 2C RBCCW pump.
- Manually starts the "2C" RBCCW pump per 34AR-650-239-2 or 34AB-P42-001-2, "Loss of RBCCW". (May not pull procedures until after the pump has been started.
- Monitors for increasing system pressure (>90psig).
- Dispatches SO/Maint to investigate the cause of the RBCCW Low system pressure.
I
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Appendix 0 Required Operator Actions Form ES-O-2
'I
, Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
3 Page 4 of 31 Event
Description:
2A RBCCW Pump shaft shears, 2C RBCCW pump fails to auto start, must be manually started; RB-3 (mfP42_71A, mfP42_72C, loP42_COOlAR2, loP42_COOlAGl, loP42_COOJAA3)
I I Position I Applicant's Actions or Behavior 8 min At the Chief Examiner's direction, Simulator operator, lNSTRUCT the BOP operator by phone to stay on the line until told to hang up. THEN ENTER:
RB-3
- mfP42_7lA
- mfP42_72C, loP42_COOJAR2 (On), loP42_COOJAGl (Off),
loP42_COOJAA3 (Off)
- Acknowledges the alarms and informs the SS that the RBCCW system pressure is low and that the "2C" RBCCW pump did not auto start.
(2C RBCCW may be started manually prior to recognizing failure to auto start.) (There is not an obvious reason for the pressure being low.)
- Directs an Operator to start the 2C RBCCW pump.
- Manually starts the "2C" RBCCW pump per 34AR-650-239-2 or 34AB-P42-001-2, "Loss of RBCCW". (May not pull procedures until after the pump has been started.
- Monitors for increasing system pressure (>90psig).
- Dispatches SOlMaint to investigate the cause of the RBCCW Low system pressure.
Appendix D Reauired Operator Actions Form ES-D-2 I,
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
3 Page 5 of31 Event
Description:
2A RBCCW Pump shaft shears, 2C RBCCW pump fails to auto start, must be manually started; RB-3 (mfP42_71A, mfP42_72C, loP42_COOIAR2, loP42 COOIAGI,loP42 COOlAA3)
Position Applicant's Actions or Behavior I
- Confirms/sends SOlMaint to investigate RBCCW Low system pressure.
Simulator Operator ensures the RBCCW TRIGGER is entered, then After 3 minutes of being sent to investigate the RBCCW system low pressure, the Simulator Operator reports that the "2A" RBCCW pump motor is running, but the pump shaft is not turning.
- Places 2P42-COOIA control switch to PTL OFF position and reports this to the SS.
Simulator operator proceeds to the next event at the Chief Examiner's direction.
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
3 Page 5 of 31 Event
Description:
2A RBCCW Pump shaft shears, 2C RBCCW pump fails to auto start, must be manually started; RB-3 (mfP42_71A, mfP42_72C, loP42_COOIAR2, loP42 COOIAGl, loP42 COOlAA3)
Position Applicant's Actions or Behavior SRO
- Confirms/sends SOlMaint to investigate RBCCW Low system pressure.
Simulator Operator ensures the RBCCW TRIGGER is entered, then After 3 minutes of being sent to investigate the RBCCW system low pressure, the Simulator Operator reports that the "2A" RBCCW pump motor is running, but the pump shaft is not turning.
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- Places 2P42-C001A control switch to PTL OFF position and reports this to the SS.
Simulator operator proceeds to the next event at the Chief Examiner's direction.
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
4 Page 6 of 31 Event
Description:
2DII-K615A, Offgas Post treatment radiation monitor, fails INOP. Stack isolation valves closes and must be re-opened. (diD II_K615A S 1 to Inop)
II Time I Position I Applicant's Actions or Behavior At the Chief Examiner's direction, Simulator Operator enters RB-4 (diDll_K615A S1 to Inop) 601-405, "Post Treatment O/G Radiation HI HI HI I Inop" alarm is received followed shortly by N62-029, "Inlet Flow To Stack Low".
- Enters ARP 34AR-601-405-2
- Verifies 2N62-F057 and Offgas drain valves are closed
- Determines that DII-K615A is reading normal.
- May Notify Lab and Verify Charcoal adsorbers are not being bypassed.
- N62-029, "Inlet Flow To Stack Low" alarm is received.
- Sends operator to 34S0-N62-001-2, Off-Gas system.
After one minute, Simulator Operator, DELETE (diDll_K615A Sl to Inop)
AND, as I &C tech, report to the Control Room that you were dispatched to work on 2D 11-K615B and inadvertently unplugged the cable to 2D 11-K615A, instead of 2D ll-K615B. The cable has been re-connected and a CR will be initiated.
- Directs operator to open 2N62-F057 which will clear N62-029, "Inlet Flow To Stack Low" alarm.
- 601-405, "Post Treatment O/G Radiation HI HI HI I Inop" alarm Clears.
Note: May receive 650-232, "3lill Stage SJAE A Steam Flow Low" alarm, if 2N62-F057 is not opened within about 2 minutes.
BOP Enters 34S0-N62-001-2 to open 2N62-F057, Stack Isolation Valve.
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Appendix 0 Required Operator Actions Form ES-O-2
,I Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
4 Page 6 of 31 Event
Description:
2DII-K615A, Offgas Post treatment radiation monitor, fails INOP. Stack isolation valves closes and must be re-opened. (diDll_K615A SI to Inop)
Time I Position I Applicant's Actions or Behavior I
At the Chief Examiner's direction, Simulator Operator enters RB-4 (diDll_K615A Sl to Inop) 601-405, "Post Treatment O/G Radiation HI HI HI I Inop" alarm is received followed shortly by N62-029, "Inlet Flow To Stack Low".
- Enters ARP 34AR-601-405-2
- Verifies 2N62-F057 and Offgas drain valves are closed
- Determines that Dll-K615A is reading normal.
- May Notify Lab and Verify Charcoal adsorbers are not being bypassed.
- N62-029, "Inlet Flow To Stack Low" alarm is received.
- Sends operator to 34S0-N62-001-2, Off-Gas system.
After one minute, Simulator Operator, DELETE (diD11_K615A S1 to 1nop)
AND, as I&C tech, report to the Control Room that you were dispatched to work on 2D11-K615B and inadvertently unplugged the cable to 2D11-K615A, instead of2D11-K615B. The cable has been re-connected and a CR will be initiated.
- Directs operator to open 2N62-F057 which will clear N62-029, "Inlet Flow To Stack Low" alarm.
- 601-405, "Post Treatment O/G Radiation HI HI HI I Inop" alarm Clears.
Note: May receive 650-232, "3K1J Stage SJAE A Steam Flow Low" alarm, if 2N62-F057 is not opened within about 2 minutes.
BOP Enters 34S0-N62-00l-2 to open 2N62-F057, Stack Isolation Valve.
Appendix 0 Reguired Operator Actions Form ES-O-2 II Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
4 Page 7 of31 Event
Description:
2D11-K615A, Offgas Post treatment radiation monitor, fails INOP. Stack isolation valves closes and must be re-opened. (diD11_K615A Sl to Inop)
I Time Position Applicant's Actions or Behavior BOP
- OPEN 2N62-F057, Off Gas Stack Inlet valve at pane12N62-P600.
BOP Verifies that 2N62-F057 opens.
Note: Annunciator N62-029, "Inlet Flow To Stack Low" AND 650-232, "3RD Stage SJAE A Steam Flow Low" alarms will clear soon after 2N62-F057 is opened
,1 Appendix D Required Operator Actions Form ES-D-2
'I Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
4 Page 7 of 31 Event
Description:
2D11-K615A, Offgas Post treatment radiation monitor, fails INOP. Stack isolation valves closes and must be re-opened. (diD11_K615A Sl to Inop)
II Time Position Applicant's Actions or Behavior I
- OPEN 2N62-F057, Off Gas Stack Inlet valve at pane12N62-P600.
BOP Verifies that 2N62-F057 opens.
Note: Annunciator N62-029, "Inlet Flow To Stack Low" AND 650-232, "3RD Stage SJAE A Steam Flow Low" alarms will clear soon after 2N62-F057 is opened.
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Appendix D Required Operator Actions Form ES-D-2 "I
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
5 Page 8 of31 Event
Description:
2F Emergency Bus de-energizes/restoration Time Position Applicant's Actions or Behavior 15 min Note to Chief examiner:
Event 5 (4160V Emergency Bus 2F loss) and Event 6 (Loss of CRD) will be running concu"ently.
Simulator Operator
- At direction of the lead examiner, ACTIVATE: (RB-5) and Event Trigger ET-R43-1
- mfR22_183, "2F" 4160 bus fault
- ET-R43-1 Note: With the loss of2F 4160V bus, the BOP may address 34AB-R22-002-2, Loss of 4160V Emergency Bus",jirst. Also thefollowing alarms may be addressed in any order.
The following alarms associated with 2F 4160V bus will be received:
- 652-202, "Loss Of Off Site Power"
- 652-210, "PSW Press Low"
- 652-217, "4160V Bus 2F BRKR 135564 TRIPPEDILKDOUT'
- Responds to annunciators 652-202, "LOSS Of OFF SITE POWER",
652-217, "4160V Bus 2F BRKR 135564 TRIPPEDILKDOUT" AND 652-210, "PSW Press Low".
Appendix 0 Required Operator Actions Form ES-O-2 I
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
5 Page 8 of 31 Event
Description:
2F Emergency Bus de-energizes/restoration Time Position Applicant's Actions or Behavior 15 min Note to Chief examiner:
Event 5 (4160 V Emergency Bus 2F loss) and Event 6 (Loss of CRD) will be running concurrently.
Simulator Operator
- At direction of the lead examiner, ACTIVATE: (RB-5) and Event Trigger ET-R43-1
- mfR22_183, "2F" 4160 bus fault
- ET-R43-1
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Note: With the loss of2F 4160V bus, the BOP may address 34AB-R22-002-2, Loss of 4160V Emergency Bus ", first. Also the following alarms may be addressed in any order.
The following alarms associated with 2F 4160V bus will be received:
- 652-202, "Loss Of Off Site Power"
- 652-210, "PSW Press Low"
- 652-217, "4160V Bus 2F BRKR 135564 TRIPPEDILKDOUT"
- 650-137, "4160 STA SVC FDR BRKR Trip" BOP Responds to annunciators 652-202, "LOSS Of OFF SITE POWER",
652-217, "4160V Bus 2F BRKR 135564 TRIPPEDILKDOUT" AND 652-210, "PSW Press Low".
Appendix 0 Reguired Operator Actions Form ES-O-2 tr Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
5 Page 9 of31
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Event
Description:
2F Emergency Bus de-energizes/restoration Time Position Applicant's Actions or Behavior I
- Responds to annunciator, "LOSS Of OFF SITE POWER,"
- Confirms the following on 2H11-P652:
- EDG IB is operating 4160V Bus 2F LOSP Lockout Relay is locked out 4160V Emergency Bus 2F is energized.
- Responds to annunciator 652-217, "4160V Bus 2F BRKR 135564 TRIPPEDILKDOUT,"
- On 2H11-P652 confirms the following:
- Normal Supply breaker 135574 open
- Alternate Supply breaker 135564 open
- 1B EDG Output breaker 135570 open:
- Dispatches SOlMaintenance to investigate the loss of 4160V Bus 2F Simulator Operator
- When directed by operator, ACTIVATE: (RB-I) "4KV 2F ALTERNATE SUPPLY BKR LOCKOUT" to RESET
- Once 2F Emergency bus is energized, notifies SOlMaint to reset relay trips.
- Responds to annunciator, 652-210, "PSW Press Low"
- On 2H11-P652 confirms the following;
Appendix D Required Operator Actions Form ES-D-2
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If Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
5 Page 9 of 31 Event
Description:
2F Emergency Bus de-energizes/restoration Time Position Applicant's Actions or Behavior I
- Responds to annunciator, "LOSS Of OFF SITE POWER,"
- Confirms the following on 2H 11-P65 2:
- EDG IB is operating
- 4I60V Bus 2F LOSP Lockout Relay is locked out
- 4I60V Emergency Bus 2F is energized.
- Responds to annunciator 652-217, "4160V Bus 2F BRKR 135564 TRIPPEDILKDOUT,"
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- On 2H11-P652 confirms the following:
- Normal Supply breaker 135574 open
- Alternate Supply breaker 135564 open
- IB EDG Output breaker 135570 open:
Dispatches SOlMaintenance to investigate the loss of 4I60V Bus 2F Simulator Operator
- When directed by operator, ACTIVATE: (RB-I) "4KV 2F ALTERNATE SUPPLY BKR LOCKOUT" to RESET
- Once 2F Emergency bus is energized, notifies SOlMaint to reset relay trips.
- Responds to annunciator, 652-210, "PSW Press Low"
- On 2HII-P652 confirms the following;
- lR24-S026 is energized (IT IS NOT)
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Appendix D Required Operator Actions Form ES-D-2 II Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
5 Page 10 of 31 Event
Description:
2F Emergency Bus de-energizes/restoration Time Position Applicant's Actions or Behavior I
- Enters 34AB-R22-002-2. "Loss of 4I60V Emergency Bus"
- Confirm 1 B Diesel Generator has auto started
- Ensure adequate cooling water is available to the IB Diesel Generator
- Observes 2P4I-C002, "STBY PSW Pump", has no lights illuminated.
- Observes 2P4I-C002, "STBY PSW Pump", red light illuminates. (This restores cooling water to the IB Diesel Generator. )
- Directs the BOP to enter 34AB-R22-002-2 for the loss of 4I60V Emergency Bus
- As time allows, addresses Tech Specs 3.8.7 and enters an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> RAS per TS 3.8.7.C to restore AC electrical power distribution subsystem to operable status.
- Terminates RAS once 4I60V Emergency Bus 2F is energized.
Appendix D Required Operator Actions Form ES-D-2
'I Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
5 Page 10 of 31 Event
Description:
2F Emergency Bus de-energizes/restoration Time Position Applicant's Actions or Behavior I
- Enters 34AB-R22-002-2. "Loss of 4160V Emergency Bus"
- Confirm 1 B Diesel Generator has auto started
- Ensure adequate cooling water is available to the 1B Diesel Generator
- Observes 2P41-C002, "STBY PSW Pump", has no lights illuminated.
- Observes 2P4l-C002, "STBY PSW Pump", red light illuminates. (This restores cooling water to the 1B Diesel Generator. )
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- Directs the BOP to enter 34AB-R22-002-2 for the loss of 4160V Emergency Bus
- As time allows, addresses Tech Specs 3.8.7 and enters an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> RAS per TS 3.8.7.C to restore AC electrical power distribution subsystem to operable status.
- Terminates RAS once 4160V Emergency Bus 2F is energized.
Appendix 0 Required Operator Actions Form ES-O-2
'I Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
5 Page 11 of 31 Event
Description:
2F Emergency Bus de-energizes/restoration Time Position Applicant's Actions or Behavior I
Simulator Operator
- At direction of the Chief Examiners, DELETE:
(RB-S) mfR22_183, "2F" 4160 bus fault
- At Chief Examiners direction, contact the U2 SS and INFORM, as Shift Manager, that the Maintenance Electrical Team Leader notified you that the fault on 2F Emergency bus was a loose cable connector and (with time compression) has now been repaired. You have my permission and the Maintenance Electrical Team Leaders permission to reset the 86 lockout and energize the 2F Emergency bus from the 2D Startup Auxiliary Transformer (SAT).
- As Shift Manager, INFORM the U2 SS that it is not desired for the diesel generator 1B to be tripped AND tagged out OR the Alternate (Startup) Supply Breaker, ACB 135564, racked out, OR the B Diesel Test SAT 2C OUT OF SVC Interlock switch placed to TEST.
SRO Directs the BOP to re-energize 2F Emergency bus from 2D SAT.
- IA W 34AB-R22-002-2 step 4.6.1 enters 34S0-R22-001-2, "4160VAC System", to energize 2F Emergency bus.
Appendix 0 Required Operator Actions Form ES-O-2
(
II Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
5 Page 11 of 31 Event
Description:
2F Emergency Bus de-energizes/restoration Time Position Applicant's Actions or Behavior I
Simulator Operator
- At direction of the Chief Examiners, DELETE:
(RB-5) mfR22_183, "2F" 4160 bus fault
- At Chief Examiners direction, contact the U2 SS and INFORM, as Shift Manager, that the Maintenance Electrical Team Leader notified you that the fault on 2F Emergency bus was a loose cable connector and (with time compression) has now been repaired. You have my permission and the Maintenance Electrical Team Leaders permission to reset the 86 lockout and energize the 2F Emergency bus from the 2D Startup Auxiliary Transformer (SAT).
- As Shift Manager, INFORM the U2 SS that it is not desired for the diesel generator 1B to be tripped AND tagged out OR the Alternate
(
(Startup) Supply Breaker, ACB 135564, racked out, OR the B Diesel Test SAT 2C OUT OF SVC Interlock switch placed to TEST.
SRO Directs the BOP to re-energize 2F Emergency bus from 2D SAT.
- IAW 34AB-R22-002-2 step 4.6.1 enters 34S0-R22-001-2, "4160VAC System", to energize 2F Emergency bus.
Appendix 0 Required Operator Actions Form ES-O-2 I
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
5 Page 12 of 31 Event
Description:
2F Emergency Bus de-energizes/restoration Time Position Applicant's Actions or Behavior I
- Section 7.3.1.2 of 34S0-R22-00l-2.
- Place Diesel Generator 1B Mode Select Switch in Test. (652-205 will alarm)
- Place Sync Switch (SSW) ACB 135574 in ON.
- Requests permission from SS to reset the 4160V Bus 2F LOSP Lockout Relay, IA W 30AC-OPS-003-0, Plant Operations, AND 31GO-OPS-021-0, Manipulation of Control and Equipment, SRO Grants permission to reset the Loss of Off-Site Power Relay.
(SM & Maintenance Electrical Team Leader have already granted permission)
BOP Simultaneously performs the following steps:
- Holds 4160V Bus 2F LOSP Lockout Relay in RESET.
- Holds ACB 135574, 4160V Bus 2F Normal Supply, control switch to CLOSE until breaker closes.
- Place Sync Switch (SSW) ACB 135574 in OFF.
- Place the Diesel Generator 1B Mode Select Switch in NORM.
- Responds to annunciator 650-137, "4160 STA SVC FDR BRKR Trip"
- On 2H11-P650 confirms that 2C PSW pump amber light is illuminated.
- Once cause has been determined and corrected, takes the control switch for 2C PSW pump to off and spring returns to auto to clear amber light.
Appendix 0 Required Operator Actions Form ES-O-2 l
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
5 Page 12 of 31 Event
Description:
2F Emergency Bus de-energizes/restoration Time Position Applicant's Actions or Behavior I
- Section 7.3.1.2 of 34S0-R22-001-2.
- Place Diesel Generator 1B Mode Select Switch in Test. (652-205 will alarm)
- Place Sync Switch (SSW) ACB 135574 in ON.
- Requests permission from SS to reset the 4160V Bus 2F LOSP Lockout Relay, IA W 30AC-OPS-003-0, Plant Operations, AND 31 GO-OPS-021-0, Manipulation of Control and Equipment, SRO
- Grants permission to reset the Loss of Off-Site Power Relay.
(SM & Maintenance Electrical Team Leader have already granted permission)
(
- Simultaneously performs the following steps:
- Holds 4160V Bus 2F LOSP Lockout Relay in RESET.
- Holds ACB 135574, 4160V Bus 2F Normal Supply, control switch to CLOSE until breaker closes.
- Place Sync Switch (SSW) ACB 135574 in OFF.
- Place the Diesel Generator 1B Mode Select Switch in NORM.
- Responds to annunciator 650-137, "4160 STA SVC FDR BRKR Trip"
- On 2H11-P650 confirms that 2C PSW pump amber light is illuminated.
- Once cause has been determined and corrected, takes the control switch for 2C PSW pump to off and spring returns to auto to clear amber light.
(
Appendix 0 Required Operator Actions Form ES-O-2 II Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
6 Page 13 of 31 Event
Description:
Loss of CRD due to power failure I Time Position Applicant's Actions or Behavior I
Note to Simulator Operator: No additional malfunctions need to be entered for this event. This event stems from the loss of 2F 4160V bus.
Note: With the loss of CRD, the ATC may address 34AB-Cll-001-2, "Loss Of CRD ", first. The following alarms may be addressed in any order.
The following alarms associated with 2F 4160V bus will be received:
- 603-129, "CRD Pump B Breaker Trip"
- 603-140, "CRD Temp High"
- 603-148, "CRD Accumulator Press Low or Level High" ATC
SRO Directs ATC to enter 34AB-C 11-00 1-2, "Loss Of CRD" ATC
- Responds to annunciator, "CRD Pump B Breaker Trip" (603-129)
- Check the following indications on 2HII-P603:
- Pump indicating lights.
- 2CII-R605, Cooling Wtr indicator, indicates zero flow.
- 2CII-R601, Charging Water Pressure indicator decreasing.
- 2CII-R602, Drive Water DP indicator decreasing.
- 2C 11-R603, Cooling Water D P indicator decreasing.
Appendix 0 Required Operator Actions Form ES-O-2 II Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
6 Page 13 of 31 Event
Description:
Loss of CRD due to power failure Time Position Applicant's Actions or Behavior Note to Simulator Operator: No additional malfunctions need to be enteredfor this event. This event stems from the loss of2F 4J60V bus.
Note: With the loss of CRD, the ATC may address 34AB-CJJ-OOJ-2, "Loss Of CRD",first. Thefollowing alarms may be addressed in any order.
The following alarms associated with 2F 4160V bus will be received:
- 603-129, "CRD Pump B Breaker Trip"
- 603-140, "CRD Temp High"
- 603-148, "CRD Accumulator Press Low or Level High" ATC
(
SRO Directs ATC to enter 34AB-C11-00l-2, "Loss Of CRD" ATC
- Responds to annunciator, "CRD Pump B Breaker Trip" (603-129)
- Check the following indications on 2H11-P603:
- Pump indicating lights.
- 2C11-R605, Cooling Wtr indicator, indicates zero flow.
- 2C11-R60l, Charging Water Pressure indicator decreasing.
- 2Cll-R602, Drive Water DP indicator decreasing.
- 2C11-R603, Cooling Water DP indicator decreasing.
(
\\
Appendix 0 Required Operator Actions Form ES-D-2 If Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
6 Page 14 of 31 Event
Description:
Loss of CRD due to power failure Time Position Applicant's Actions or Behavior I
- Responds to annunciators CRD HYD TEMP HIGH, 603-140 and CRD ACCUMULATOR PRESS LOW OR LEVEL HIGH, 603-148
- Enter 34AB-C11-00l-2, Loss Of CRD.
- Dispatches an operator to determine local accumulator pressures.
Simulator Operator after 3 minutes, As the operator sent to the CRD temperature recorder, report that the highest temperature was 270 of and several CRDs at this temperature. Also inform that the operator sent to the CRD accumulators, reports that there are several accumulators with pressures less than 940 psig.
- Enters 34AB-Cll-001-2, "Loss of CRD."
- Starts the A CRD pump.
- Returns the flow controller to auto and output to the pre-trip position.
- IF the applicant does not start the A CRD pump and the following conditions exist:
- Two or more withdrawn control rod scram accumulators inoperable
- AND
(
Appendix 0 Required Operator Actions Form ES-D-2 II Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
6 Page 14 of 31 Event
Description:
Loss of CRD due to power failure Time Position Applicant's Actions or Behavior ATC
- Responds to annunciators CRD HYD TEMP HIGH, 603-140 and CRD ACCUMULATOR PRESS LOW OR LEVEL HIGH, 603-148
- Enter 34AB-CII-00l-2, Loss Of CRD.
- Dispatches an operator to determine local accumulator pressures.
Simulator Operator after 3 minutes, As the operator sent to the CRD temperature recorder, report that the highest temperature was 270 of and several CRDs at this temperature. Also inform that the operator sent to the
(
CRD accumulators, reports that there are several accumulators with pressures less than 940 psig.
- Enters 34AB-Cll-00l-2, "Loss of CRD."
- Starts the A CRD pump.
- Returns the flow controller to auto and output to the pre-trip position.
- IF the applicant does not start the A CRD pump and the following conditions exist:
- Two or more withdrawn control rod scram accumulators inoperable
- AND
Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
6 Page 15 of 31 Event
Description:
Loss of CRD due to power failure Time Position Applicant's Actions or Behavior SRO
- As time allows, addresses Tech Specs 3.1.5
- By the time the SS addresses TS 3.1.5; two or more accumulators will have a trouble alarm lit. Once it has been determined that 2 or more accumulators are inoperable, the SS begins a 20 minute RAS per TS 3.1.5.B to insert a scram and declares the rods slow or inoperable in one hour.
- Terminates RAS once charging water pressure is restored above 940 psig.
Simulator Operator After 2F 4160V Emergency bus is energized from 2D SAT AND CRD has been II returned to service AND at the direction of the Chief examiner, enter next malfunction to start the major event.
Appendix 0 Required Operator Actions Form ES-O-2 I
II
\\
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
6 Page 15 of 31 Event
Description:
Loss of CRD due to power failure Time Position Applicant's Actions or Behavior SRO
- As time allows, addresses Tech Specs 3.1.5
- By the time the SS addresses TS 3.1.5; two or more accumulators will have a trouble alarm lit. Once it has been determined that 2 or more accumulators are inoperable, the SS begins a 20 minute RAS per TS 3.1.5.B to insert a scram and declares the rods slow or inoperable in one hour.
- Terminates RAS once charging water pressure is restored above 940 psig.
Simulator Operator
(
After 2F 4160V Emergency bus is energized from 2D SAT AND CRD has been II returned to service AND at the direction of the Chief examiner, enter next malfunction to start the major event.
(
\\
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
7 Page 16 of 31 Event
Description:
4160 VAC "D" trips causing a loss of 2 condensate and condensate booster pumps, HPCI fails to start due to 2E41-F001 (Turbine Steam Supply) is stuck closed. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.
II Time I Position I Applicant's Actions or Behavior 10 min Simulator Operator, at Chief Examiners direction, stage an operator in the simulator control room ready to remove the Danger tag on the 2C CBP.
START the major event. Once both RFPTs have tripped, report to the SS for permission to remove the Danger tag and place 2C CBP switch in automatic.
Remove the Danger tag and place the control switchfor 2C CBP in the automatic position. As the operator, inform the SS that the Danger Tag on 2C CBP has been removed and the 2C CBP automatically started when you placed the control switch to automatic.
Simulator Operator, at Chief Examiners direction, ACTIVATE RB-7 (mjR22_l8l (4KV Bus 2D Fault), mfE4l_l07 (HPCI FOOl fails to open) and mfG3l 242)
ALL
- Recognizes a loss of "D" 4160 V AC station service electrical bus has occurred resulting in a loss of condensate and condensate booster pumps A and B.
- The team may insert a scram manually due to decreasing reactor water level.
- Identify drywell pressure is greater than 1.85 psig and increasing.
- Assigns the ATC to perform RC-l.
- Assigns the BOP operator to perform RC-2 and RC-3.
- Enters 3 1 EO-EOP-O 10-2, RC EOP flow chart
- Enters 31EO-EOP-012-2, Primary Containment flow chart.
- Assigns a RWL band between 3" and 50"
(
(
Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
7 Page 16 of 31 Event
Description:
4160 V AC "D" trips causing a loss of 2 condensate and condensate booster pumps, HPCI fails to start due to 2E41-F001 (Turbine Steam Supply) is stuck closed. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.
I Time I Position I Applicant's Actions or Behavior 10 min Simulator Operator, at Chief Examiners direction, stage an operator in the simulator control room ready to remove the Danger tag on the 2C CBP.
START the major event. Once both RFPTs have tripped, report to the SS for permission to remove the Danger tag and place 2C CBP switch in automatic.
Remove the Danger tag and place the control switchfor 2C CBP in the automatic position. As the operator, inform the SS that the Danger Tag on 2C CBP has been removed and the 2C CBP automatically started when you placed the control switch to automatic.
Simulator Operator, at Chief Examiners direction, ACTIVATE RB-7 (mfR22_l8l (4KV Bus 2D Fault), mfE4l_l07 (HPCI FOOl fails to open) and mfG3l 242)
ALL
- Recognizes a loss of "D" 4160 V AC station service electrical bus has occurred resulting in a loss of condensate and condensate booster pumps A and B.
- The team may insert a scram manually due to decreasing reactor water level.
- Identify drywell pressure is greater than 1.85 psig and increasing.
- Assigns the A TC to perform RC-1.
- Assigns the BOP operator to perform RC-2 and RC-3.
- Enters 31EO-EOP-01O-2, RC EOP flow chart
- Enters 31EO-EOP-012-2, Primary Containment flow chart.
- Assigns a R WL band between 3" and 50" I
Appendix D Required Operator Actions Form ES-D-2 Op* Test No.: 2009*302 Scenario No.:
5*01 Event No.:
7 Page 17 of 31 Event
Description:
4160 V AC "D" trips causing a loss of 2 condensate and condensate booster pumps, HPCI fails to start due to 2E41-F001 (Turbine Steam Supply) is stuck closed. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.
II Time Position Applicant's Actions or Behavior SRO
- As time allows,
- Notifies maintenance to repair 2D 4160 VAC
- Dispatches personnel to the EDGs to check for proper operation.
- Directs reopening 2P41-F316A-D IA W 34AB-P41-001-2, Loss of PSW ATC
- Performs RC-1 consisting of:
(
- Inserts a manual scram.
- Places the mode switch to shutdown.
- Notifies SS of rod position check.
- Places SDV isolation valve switch to "isolate" & confirms closed.
- If not tripped, places the Recirc pumps at minimum speed.
- Shifts recorders to read IRMS, when required.
- Ranges IRMS to bring reading on scale.
- Notifies the SS when the above actions are complete.
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
7 Page 17 of 31 Event
Description:
4160 V AC "D" trips causing a loss of 2 condensate and condensate booster pumps, HPCI fails to start due to 2E41-F001 (Turbine Steam Supply) is stuck closed. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.
I Time Position Applicant's Actions or Behavior I
- As time allows,
- Notifies maintenance to repair 2D 4160 VAC
- Dispatches personnel to the EDGs to check for proper operation.
- Directs reopening 2P41-F316A-D IA W 34AB-P41-001-2, Loss of PSW ATC
- Performs RC-1 consisting of:
(
- Inserts a manual scram.
- Places the mode switch to shutdown.
- Notifies SS of rod position check.
- Places SDV isolation valve switch to "isolate" & confirms closed.
- If not tripped, places the Recirc pumps at minimum speed.
- Shifts recorders to read IRMS, when required.
- Ranges IRMS to bring reading on scale.
- Notifies the SS when the above actions are complete.
(
Appendix 0 Required Operator Actions Form ES-D-2
(.
~
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
7 Page 18 of 31 Event
Description:
4160 VAC "D" trips causing a loss of 2 condensate and condensate booster pumps, HPCI fails to start due to 2E41-F001 (Turbine Steam Supply) is stuck closed. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.
Time Position Applicant's Actions or Behavior I
- Performs RC-2 actions consisting of:
- Confirms proper Level Control response:
- Checks ECCS Injection Systems and secure as necessary.
- Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value.
- IF set down does not auto function, then manually reduces FW Master Controller setpoint to approximately 9 inches.
- Starts RCIC for level control
- When feed flow is less than the capacity of the sru level control valve
(;::::: 1.5 mlbmlhr), then:
- Opens 2N21-F125.
- Closes 2N21-F11O.
- May attempt to start the CRD pumps
Appendix D Required Operator Actions Form ES-D-2
(
I, Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
7 Page 18 of 31 Event
Description:
4160 VAC "D" trips causing a loss of 2 condensate and condensate booster pumps, HPCr fails to start due to 2E41-F001 (Turbine Steam Supply) is stuck closed. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.
Time Position Applicant's Actions or Behavior I
- Performs RC-2 actions consisting of:
- Confirms proper Level Control response:
- Checks ECCS Injection Systems and secure as necessary.
- Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value.
- IF set down does not auto function, then manually reduces FW Master Controller setpoint to approximately 9 inches.
- Starts RCrC for level control
- Notifies SS that the HPCr FOOl valve will not open and dispatches SO/Maint to investigate.
(
- When feed flow is less than the capacity of the sru level control valve
(;::::: 1.5 mlbmlhr), then:
- Opens 2N21-F125.
- Closes 2N21-F11O.
- May attempt to start the CRD pumps
- Controls RWL with the RCrc. Notifies SS if RWL gets outside assigned band.
(
Appendix D Required Operator Actions Form ES-D-2
" Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
7 Page 19 of 31 Event
Description:
4160 VAC "D" trips causing a loss of 2 condensate and condensate booster pumps, HPCI fails to start due to 2E41-FOOl (Turbine Steam Supply) is stuck closed. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.
I Time Position Applicant's Actions or Behavior BOP
- At panel 2H11-P60 1, Confirms 4 RHR pumps and 2 Core Spray pumps are running.
- Performs RC-3 consisting of:
- Monitor RPV pressure.
- Maintain RPV pressure between 1074 and 800 psig.
- Notify SS of pressure control system operation.
- Re-opens 2P41-F316s due to high temp on the Condensate Pumps/Booster pumps per 34AB-P41-001-2, Loss ofPSW, Placard.
- Places the "A" and "B" Isolation Override switches on the 2H11-P652 panel to Override
- Fully opens 2P41-F316A or C and 2P41-F316B or D
- Throttles 2P41-F316C or A and 2P41-F316D or B to open while monitoring PSW division 1 and 2 pressure on 2H11-P650 panel ensuring that PSW pressure remains above 80 psig.
,I Appendix D Required Operator Actions Form ES-D-2 I ~
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
7 Page 19 of 31 Event
Description:
4160 VAC "D" trips causing a loss of 2 condensate and condensate booster pumps, HPCI fails to start due to 2E41-F001 (Turbine Steam Supply) is stuck closed. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.
II Time Position Applicant's Actions or Behavior I
- At panel 2H11-P60 1, Confirms 4 RHR pumps and 2 Core Spray pumps are running.
- Performs RC-3 consisting of:
- Monitor RPV pressure.
- If necessary, allow RPV pressure to exceed 1074 psig then cycle
(
- Maintain RPV pressure between 1074 and 800 psig.
- Notify SS of pressure control system operation.
- Re-opens 2P41-F316s due to high temp on the Condensate Pumps/Booster pumps per 34AB-P41-00l-2, Loss of PSW, Placard.
- Places the "A" and "B" Isolation Override switches on the 2H11-P652 panel to Override
- Fully opens 2P41-F316A or C and 2P41-F316B or D
- Throttles 2P41-F316C or A and 2P41-F316D or B to open while monitoring PSW division 1 and 2 pressure on 2H11-P650 panel ensuring that PSW pressure remains above 80 psig.
(
,I
Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
8 Page 20 of31 Event
Description:
RHR 2E11-F028AIB Torus Spray valve fails. 1 Loop of Torus spray Inop (diE11-F027 A and diE11-F027B)
I Time Position Applicant's Actions or Behavior SRO
- Per the PC flowchart, verifies torus level is <285 inches and directs an operator to place Torus Sprays in service Simulator Operator, confirm EVENT TRIGGER (Ell-1 or E11-2) is activated when the operator positions 2EII-F027 A or B to open.
- Sprays the Torus per 34S0-Ell-01O-2 placard on the 2Hll-P601 Panel as follows:
- Places Cnmt Spray Vlv Cntl switch in the MANUAL position.
- Starts RHR pump(s) in loop A (B), if not already running.
- Opens 2E 11-F028A or B
- Opens 2Ell-F027A or B (ONE WILL NOT OPEN AND OPERATOR TRANSITIONS TO THE OTHER LOOP)
- Throttles Open 2E11-F027 A(B) (Critical Task)
- Notifies SS that RHR is in Torus Sprays (The flow is only 700gpm, so it may be difficult to see flow indication from a distance.)
Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
8 Page 20 of 31 Event
Description:
RHR 2E11-F028A!B Torus Spray valve fails. 1 Loop of Torus spray Inop (diE11-F027A and diE11-F027B)
Time Position Applicant's Actions or Behavior SRO
- Per the PC flowchart, verifies torus level is <285 inches and directs an operator to place Torus Sprays in service Simulator Operator, confirm EVENT TRIGGER (Ell-lor Ell-2) is activated when the operator positions 2Ell-F027A or B to open.
- Sprays the Torus per 34S0-E 11-01 0-2 placard on the 2H 11-P60 1 Panel as follows:
- Places Cnmt Spray Vlv Cntl switch in the MANUAL position.
- Starts RHR pump(s) in loop A (B), if not already running.
(
- Opens 2E 11-F028A or B
- Throttles Open 2E11-F027 A(B) (Critical Task)
- Notifies SS that RHR is in Torus Sprays (The flow is only 700gpm, so it may be difficult to see flow indication from a distance.)
- Informs SS that the 2Ell-F027A (or B) will not Open SRO
(
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
8 Page 21 of 31 Event
Description:
RHR 2EII-F028AJB Torus Spray valve fails. I Loop of Torus spray Inop (diE II-F027 A and diE II-F027B)
Time Position Applicant's Actions or Behavior SRO
- If time allows, directs an operator to restore drywell chillers and coolers per 31EO-EOP-100-2.
- Restores drywell chillers per 31EO-EOP-100-2 section 3.7 by:
- Verifies drywell temperature is below 250°F using SPDS and/or recognizes the leak in primary containment is small.
- Has the SSS Reset 86 lockout relays on drywell chiller breaker on 4160V buses "E" and "G" (2R22-S005 Fr. 11 and 2R22-S007 Fr.
11
- May have the SSS to reset the POR relay for each chiller.
- Restores the drywell coolers per 31EO-EOP-100-2 section 3.6 by:
- Verifies drywell temperature is below 250 OF on SPDS and/or recognizes there is not a leak in primary containment.
- Observes the drywell cooler fans start by observing their red lights illuminating on 2HII-P654 and panel P657.
Appendix 0 Required Operator Actions Form ES-O-2
~
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
8 Page 21 of 31 Event
Description:
RHR 2EII-F028AJB Torus Spray valve fails. 1 Loop of Torus spray Inop (diEll-F027 A and diEll-F027B)
II Time Position Applicant's Actions or Behavior I
- If time allows, directs an operator to restore drywell chillers and coolers per 31EO-EOP-100-2.
- Restores drywell chillers per 31EO-EOP-100-2 section 3.7 by:
- Verifies drywell temperature is below 250°F using SPDS and/or recognizes the leak in primary containment is small.
- Has the SSS Reset 86 lockout relays on drywell chiller breaker on 4160V buses "E" and "G" (2R22-S005 Fr. 11 and 2R22-S007 Fr.
(
11
- May have the SSS to reset the POR relay for each chiller.
- Restores the drywell coolers per 31EO-EOP-100-2 section 3.6 by:
- Verifies drywell temperature is below 250 OF on SPDS and/or recognizes there is not a leak in primary containment.
- Observes the drywell cooler fans start by observing their red lights illuminating on 2H II-P654 and panel P657.
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Appendix 0 Required Operator Actions Form ES-O-2
'I Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
8 Page 22 of 31 Event
Description:
RHR 2EII-F028AIB Torus Spray valve fails. 1 Loop of Torus spray Inop (diEII-F027A and diEII-F027B)
Time Position Applicant's Actions or Behavior SRO
- If Torus pressure exceeds 11 psig, verifies that Torus Level is <215 inches, in the safe area of Graph 8 (DWSIL) and Directs an operator to:
- Place the DW cooling fans to Off
- Shutdown Recirc pumps (if running)
- SpraytheDW ATC
- Places all DW cooling fans control switches in the OFF position.
- Notifies the SS that the fans are Off.
- Sprays the Drywell using 34S0-EI1-010-2 placard at the 2HI1-P601 panel.
- Places Cnmt Spray (A or B) Vlv Cntl switch in the MANUAL position.
- Starts RHR pump(s) in loop A (B), if not already running.
- Opens 2E II-F021A or B
- Opens 2Ell-F0l6A or B Appendix D Required Operator Actions Form ES-D-2
'l Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
8 Page 22 of 31 Event
Description:
RHR 2E11-F028AIB Torus Spray valve fails. 1 Loop of Torus spray Inop (diEll-F027A and diEll-F027B)
Time Position Applicant's Actions or Behavior SRO
- If Torus pressure exceeds 11 psig, verifies that Torus Level is <215 inches, in the safe area of Graph 8 (DWSIL) and Directs an operator to:
- Place the DW cooling fans to Off
- Shutdown Recirc pumps (if running)
- Places all DW cooling fans control switches in the OFF position.
- Notifies the SS that the fans are Off.
(
- Sprays the Drywell using 34S0-E11-0l0-2 placard at the 2H11-P601 panel.
- Places Cnmt Spray (A or B) Vlv Cntl switch in the MANUAL position.
- Starts RHR pump(s) in loop A (B), if not already running.
- Opens 2Ell-F021A or B
- Opens 2E11-F0l6A or B
(
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
9 Page 23 of 31 Event
Description:
RCIC trips on Overspeed; RWL recovered via RFPT Time Position Applicant's Actions or Behavior I
Simulator Operator, 10 minutes after removing the Danger tag on 2C CBP OR when the operator starts to place either RFPT in service, ACTIVATE RB-9 (mfE51 61)
- Recognize that RCIC tripped and responds to annunciator RCIC Turbine Trip, 34AR-602-301-2.
- Confirms RCIC Turbine Tripped per the following indications:
0 2E51-F524, Trip & Throttle Valve, indicates closed.
0 Turbine Speed decreasing 0
2E52-F013, Pump Discharge Valve, indicates closed.
0 2E51-FOI9, Min Flow Valve, indicates closed.
- Recognizes that the 2E51-F524, Trip & Throttle Valve actuator will not run down and determines that RCIC has tripped on Overspeed.
SRO Directs the operator to restart a RFPT for injection BOP
- Enters Attachment 15 (placard) of 34S0-N21-007-2 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
9 Page 23 of 31 Event
Description:
RCIC trips on Overspeed; RWL recovered via RFPT II Time Position Applicant's Actions or Behavior I
Simulator Operator, 10 minutes after removing the Danger tag on 2C CBP OR when the operator starts to place either RFPT in service, ACTIVATE RB-9 (mfE51_61)
- Recognize that RCIC tripped and responds to annunciator RCIC Turbine Trip, 34AR-602-301-2.
- Confirms RCIC Turbine Tripped per the following indications:
0 2E5l-F524, Trip & Throttle Valve, indicates closed.
0 Turbine Speed decreasing 0
2E52-F013, Pump Discharge Valve, indicates closed.
0 2E51-FOI9, Min Flow Valve, indicates closed.
- Recognizes that the 2E5l-F524, Trip & Throttle Valve actuator will
(
not run down and determines that RCIC has tripped on Overspeed.
SRO Directs the operator to restart a RFPT for injection BOP
- Enters Attachment 15 (placard) of 34S0-N21-007-2
Appendix 0 Required Operator Actions Form ES-O-2
'I Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
9 Page 24 of31 Event
Description:
RCIC trips on Overspeed; RWL recovered via RFPT Time Position Applicant's Actions or Behavior I
- Starts RFPT per placard:
- Confirm the trip condition has reset AND the condensate system is available.
- Take RFPT 2A or 2B Reset-Trip control switch to RESET AND confirm:
- RFPT 2A or 2B TRIP annunciator 650-325 (650-326) CLEAR
- Slowly raise RFPT 2A or 2B speed with RFPT 2A or 2B Speed Setter Switch, UNTIL RFPT 2A or 2B speed is at 2100 rpm +/- 100 rpm, as indicated at 2N32-R603A (2N32-R603B) AND confirm MIA Station Permissive 2A or 2B, White light ILLUMINATES.
- Place the RFPT 2A or 2B TMR Mode Switch to MIA, confirm MIA Station GREEN light ILLUMINATES.
- Slowly increase RFPT 2A or 2B speed with RFP A or B MIA Station, UNTIL 2N21-R635A or B, RFP Disch Press is:::: 2C32-R605A, Reactor Pressure.
- Controls Reactor Water Level Manually by performing one of the following:
IF controlling the 2A or 2B Rx Feed Pump with 2C32-R601A or B, perform the following:
- Ensure the RFPT 2A or 2B TMR Mode Switch MIA Station green light is ILLUMINATED.
- Adjust the manual open/close lever to control level.
Appendix 0 Required Operator Actions Form ES-O-2
'I Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
9 Page 24 of 31 Event
Description:
RCIC trips on Overspeed; RWL recovered via RFPT Time Position Applicant's Actions or Behavior BOP
- Starts RFPT per placard:
- Confirm the trip condition has reset AND the condensate system is available.
- Take RFPT 2A or 2B Reset-Trip control switch to RESET AND confirm:
- RFPT 2A or 2B TRIP annunciator 650-325 (650-326) CLEAR
- Slowly raise RFPT 2A or 2B speed with RFPT 2A or 2B Speed Setter Switch, UNTIL RFPT 2A or 2B speed is at 2100 rpm+/- 100 rpm, as indicated at 2N32-R603A (2N32-R603B) AND confIrm MIA Station Permissive 2A or 2B, White light ILLUMINATES.
- Place the RFPT 2A or 2B TMR Mode Switch to MIA, confirm MIA Station GREEN light ILLUMINATES.
(
- Slowly increase RFPT 2A or 2B speed with RFP A or B MIA Station, UNTIL 2N21-R635A or B, RFP Disch Press is:::: 2C32-R605A, Reactor Pressure.
- Controls Reactor Water Level Manually by performing one of the following:
IF controlling the 2A or 2B Rx Feed Pump with 2C32-R601A or B, perform the following:
- Ensure the RFPT 2A or 2B 1MR Mode Switch MIA Station green light is ILLUMINATED.
- Adjust the manual open/close lever to control leveL
Appendix 0 Required Operator Actions Form ES-O-2 l!
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
9 Page 25 of 31 Event
Description:
RCIC trips on Overspeed; RWL recovered via RFPT Time Position Applicant's Actions or Behavior BOP
- IF controlling the 2A or 2B Rx Feed Pump with the Speed Setter, perform the following:
- Adjust the 2A or 2B Speed Setter to make control RWL level.
- IF desired, place Feedwater Control in Single Element Mode as follows
- Confirm OR place 2C32-R600, FW Master Controller, and 2C32-R601A or B, RFP A or B MIA Station, in MANUAL.
- Confirm OR place the Reactor Level Mode Select Switch to AUTO position AND confirm its indicating light ILLUMINATED.
- Place Feedwater Control Mode Select switch in the I ELEM position.
- Match the input and the output of Pump A or B MIA Station by depressing the PF key and reading the controller output (PF lamp, lit), THEN depress the PF key so the input to the controller is displayed (PF lamp is OFF). Adjust the manual output lever on 2C32-R600, FW Master Controller, UNTIL the input and output of the Pump A or B MIA Station are equal as indicated on the digital display.
- Place RFP A or B MIA Station in AUTOMATIC by depressing the
'A' pushbutton UNTIL it ILLUMINATES.
- Null out 2C32-R600, FW MASTER CONTROLLER, by adjusting setpoint, AND place it in AUTOMATIC by depressing the 'A' pushbutton, UNTIL it ILLUMINATES.
Appendix D Required Operator Actions Form ES-D-2 I ~
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
9 Page 25 of 31 Event
Description:
RCIC trips on Overspeed; RWL recovered via RFPT II Time Position Applicant's Actions or Behavior BOP
- IF controlling the 2A or 2B Rx Feed Pump with the Speed Setter, perform the following:
- Adjust the 2A or 2B Speed Setter to make control RWL level.
- IF desired, place Feedwater Control in Single Element Mode as follows
(
- Confirm OR place 2C32-R600, FW Master Controller, and 2C32-R601A or B, RFP A or B MIA Station, in MANUAL.
- Confirm OR place the Reactor Level Mode Select Switch to AUTO position AND confirm its indicating light ILLUMINATED.
- Place Feedwater Control Mode Select switch in the 1 ELEM position.
- Match the input and the output of Pump A or B MIA Station by depressing the PF key and reading the controller output (PF lamp, lit), THEN depress the PF key so the input to the controller is displayed (PF lamp is OFF). Adjust the manual output lever on 2C32-R600, FW Master Controller, UNTIL the input and output of the Pump A or B MIA Station are equal as indicated on the digital display.
- Place RFP A or B MIA Station in AUTOMATIC by depressing the
'A' pushbutton UNTIL it ILLUMINATES.
- Null out 2C32-R600, FW MASTER CONTROLLER, by adjusting setpoint, AND place it in AUTOMATIC by depressing the 'A' pushbutton, UNTIL it ILLUMINATES.
(
Appendix 0 Required Operator Actions Form ES-O-2 I
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
9 Page 26 of31 Event
Description:
RCIC trips on Overspeed; RWL recovered via RFPT II Time Position Applicant's Actions or Behavior BOP
- Maintains RWL above -100 inches. (Critical Task)
Note: If R WL drops below -101 inches, the MSIV s will close requiring the following actions to take place.
NOTE The following steps are contingent on whether RWL can be maintained above
-100 inches.
- Confirms all MSIV s close
- Monitors RPV water level as it trends down.
- Informs the S S of water level reaching -155."
- Manually arms LLS actuation logic by performing the following:
- Confirms RPV pressure> 1074 psig
- Opens any SRV by placing control switch to open
- Confirms red and yellow indicator light for SRV illuminated
- Per CP-l
- Orders emergency depressurization after RWL level decreases to below -155 inches; but prior to RWL decreasing to below
-185 inches
- Orders all available table 8 systems injecting until RWL increases to above -155 inches Appendix 0 Required Operator Actions Form ES-O-2 I
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
9 Page 26 of 31 Event
Description:
RCIC trips on Overspeed; RWL recovered via RFPT Time Position Applicant's Actions or Behavior I
- Maintains RWL above -100 inches. (Critical Task)
Note: If RWL drops below -101 inches, the MSIVs will close requiring the following actions to take place.
NOTE The following steps are contingent on whether RWL can be maintained above
-100 inches.
(
\\
- Confirms all MSIV s close
- Monitors RPV water level as it trends down.
- Informs the SS of water level reaching -155."
- Manually arms LLS actuation logic by performing the following:
- Confirms RPV pressure> 1074 psig
- Opens any SRV by placing control switch to open
- Confirms red and yellow indicator light for SRV illuminated
- Per CP-l
- Orders emergency depressurization after RWL level decreases to below -155 inches; but prior to RWL decreasing to below
-185 inches
- Orders all available table 8 systems injecting until RWL increases to above -155 inches
(
Appendix 0 Required Operator Actions Form ES-O-2 1\\
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
9 Page 27 of 31 Event
Description:
RCIC trips on Overspeed; RWL recovered via RFPT Time Position Applicant's Actions or Behavior ATC
- Opens 7 ADS valves prior to -185 inches. (Critical Task)
- Places switches for the ADS valves to OPEN.
- Recognizes all ADS valves amber lights illuminate.
- If SBLC was started previously, directs that SBLC be secured following the Emergency Depress before SBLC tank level decreases to below 8%.
ATCIBOP
- Verifies I Opens RHR and Core Spray injection valves open once the Reactor Pressure Low 500 psig alarm illuminates.
- Verifies injection from Core Spray and RHR pumps begins as soon as reactor pressure decreases below the shut off head of the pumps.
- When water level is restored above Top of Active Fuel throttles flow for CIS and RHR per the SS directions.
- If directed by the SS, places the SBLC switch (P603) to the off (mid) position.
- May use I transfer to the Condensate system for RWL control
- Monitors and I or throttles the Feedwater Startup Level Control Valve (SULCV) following Emergency Depress II Appendix D Required Operator Actions Form ES-D-2
-\\
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
9 Page 27 of 31 Event
Description:
RCIC trips on Overspeed; RWL recovered via RFPT Time Position Applicant's Actions or Behavior I
- Opens 7 ADS valves prior to -185 inches. (Critical Task)
- Places switches for the ADS valves to OPEN.
- Recognizes all ADS valves amber lights illuminate.
- If SBLC was started previously, directs that SBLC be secured
(
following the Emergency Depress before SBLC tank level decreases to below 8%.
ATC/BOP
- Verifies I Opens RHR and Core Spray injection valves open once the Reactor Pressure Low 500 psig alarm illuminates.
- Verifies injection from Core Spray and RHR pumps begins as soon as reactor pressure decreases below the shut off head of the pumps.
- When water level is restored above Top of Active Fuel throttles flow for CIS and RHR per the SS directions.
- If directed by the SS, places the SBLC switch (P603) to the off (mid) position.
- May use I transfer to the Condensate system for RWL control
- Monitors and I or throttles the Feedwater Startup Level Control Valve (SULCV) following Emergency Depress II
Appendix 0 Required Operator Actions Form ES-O-2 I
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
9 Page 28 of 31 Event
Description:
RCIC trips on Overspeed; RWL recovered via RFPT Time Position Applicant's Actions or Behavior With Chief Examiners Permission:
- The scenario should be terminated when the crew has:
0 Started the RFPT AND established injection prior to RWL reaching
-100 inches OR 0
Emergency depressurized the reactor AND re-established adequate core cooling with water level above TAF Appendix 0 Required Operator Actions Form ES-O-2
\\
Op-Test No.: 2009-302 Scenario No.:
5-01 Event No.:
9 Page 28 of 31 Event
Description:
RCIC trips on Overspeed; RWL recovered via RFPT II Time Position Applicant's Actions or Behavior With Chief Examiners Permission:
- The scenario should be terminated when the crew has:
0 Started the RFPT AND established injection prior to RWL reaching
-100 inches OR 0
Emergency depressurized the reactor AND re-established adequate core cooling with water level above TAF
(
(
Page 29 of 31 AppendixD Scenario Outline Form ES-D-l NRC Draft Facility:
E. I Hatch Scenario No.: 5-01 Op-Test No.:
2009-302 Examiners:
Operators:
SRO RO BOP Initiating Conditions:
Unit 2 is at 60%.
Turnover Continue reactor startup and place the '2A' RFPT in service. 2D11-K615B, Offgas Post treatment radiation monitor, failed Downscale. RAS written. 2C Condo Booster pump is filled and vented with tag out restoration in progress.
Summary:
Event 1: The "2A" RFPT will be placed into service.
Event 2: After the "2A" RFPT is in service the A TC operator will raise reactor power using the Recirc system to approximately 65% power.
Event 3: Component; RBCCW Pump '2A' will experience a sheared shaft and the standby RBCCW pump will not automatically start. The operator will manually start the standby RBCCW pump to restore system flow/pressure to normal.
Event 4: Component; 2D11-K615A, Offgas Post treatment radiation monitor, fails !NOP. Stack isolation valves closes and must be re-opened. The ATC operator dispatches I&C to investigate.
The ATC will re-align the stack isolation valve once I&C recovers the monitor.
Event 5: ComponentlTS; 4160 V Emergency Bus '2F' will de-energize causing a loss of 2B CRD pump. The SS addresses Tech Specs for inoperable AC electrical distribution subsystem.
BOP will restore cooling water to the running EDG. With time compression repair 4160 V Emergency Bus '2F' will be re-aligned to Startup Auxiliary Transformer 2D.
Event 6: Loss of CRD due to loss of electrical power. The ATC will address loss of CRD and start the A CRD pump.
Event 7: Major; A loss of all high pressure injection occurs as a result of the following: 4160 V Station Service Bus '2D' experiences a fault and de-energizes, "2C" Condensate Booster pump is tagged out (control switch PTL), HPCI fails to start due to 2E41-F001 (Turbine Steam Supply) is stuck closed. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.
Event 8: Component; RHR 2EI1-F027 A or B Torus Spray/Test Valve (depends on which loop of RHR the operator attempts first) will fail closed when the operator attempts to place Torus Spray/Cooling in service. The operator must transition to the other loop of RHR to spray/cool the Torus. (Critical Task)
Event 9: Component; RCIC trips on Overspeed causing RWL to decrease. The SS will direct an operator to establish injection with a RFPT. If RFPT is not restored prior to -100", then at TAF, the SS will direct the A TC operator to open all SRV s to Emergency Depressurize the RPV and restore RWL with low pressure ECCS pumps. The plant will be emergency depressed due to low reactor water level or the RFPT will be placed into service to restore RWL prior to -100".
(Critical Task)
(
(
Page 29 of 31 AppendixD Scenario Outline Form ES-D-l NRC Draft Facility:
E. I Hatch Scenario No.:
5-01 Op-Test No.:
2009-302 Examiners: ______________________ Operators: _______________________________ S_R_O __
Unit 2 is at 60%.
Turnover Continue reactor startup and place the '2A' RFPT in service. 2D11-K615B, Offgas Post treatment radiation monitor, failed Downscale. RAS written. 2C Condo Booster pump is filled and vented with tag out restoration in progress.
Summary:
Event 1: The "2A" RFPT will be placed into service.
Event 2: After the "2A" RFPT is in service the A TC operator will raise reactor power using the Recirc system to approximately 65% power.
Event 3: Component; RBCCW Pump '2A' will experience a sheared shaft and the standby RBCCW pump will not automatically start. The operator will manually start the standby RBCCW pump to restore system flow/pressure to normal.
Event 4: Component; 2D11-K615A, Offgas Post treatment radiation monitor, fails INOP. Stack isolation valves closes and must be re-opened. The A TC operator dispatches I&C to investigate.
The A TC will re-align the stack isolation valve once I&C recovers the monitor.
Event 5: ComponentlTS; 4160 V Emergency Bus '2F' will de-energize causing a loss of 2B CRD pump. The SS addresses Tech Specs for inoperable AC electrical distribution subsystem.
BOP will restore cooling water to the running EDG. With time compression repair 4160 V Emergency Bus '2F' will be re-aligned to Startup Auxiliary Transformer 2D.
Event 6: Loss of CRD due to loss of electrical power. The A TC will address loss of CRD and start the A CRD pump.
Event 7: Major; A loss of all high pressure injection occurs as a result of the following: 4160 V Station Service Bus '2D' experiences a fault and de-energizes, "2C" Condensate Booster pump is tagged out (control switch PTL), HPCI fails to start due to 2E41-F001 (Turbine Steam Supply) is stuck closed. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.
Event 8: Component; RHR 2Ell-F027 A or B Torus Spray/Test Valve (depends on which loop of RHR the operator attempts first) will fail closed when the operator attempts to place Torus Spray/Cooling in service. The operator must transition to the other loop of RHR to spray/cool the Torus. (Critical Task)
Event 9: Component; RCIC trips on Overspeed causing RWL to decrease. The SS will direct an operator to establish injection with a RFPT. If RFPT is not restored prior to -100", then at TAP, the SS will direct the ATC operator to open all SRVs to Emergency Depressurize the RPV and restore RWL with low pressure ECCS pumps. The plant will be emergency depressed due to low reactor water level or the RFPT will be placed into service to restore RWL prior to -100".
(Critical Task)
Page 30 of31 Critical Tasks DRAFT Facility:
E. I Hatch Scenario No.:
5-01 Op-Test No.:
2009-302 Critical Tasks
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
Manually open RHR 2EII-F027 AlB Torus Sprayffest Valve prior to exceeding 11 psig in the Torus to preclude damage to the downcomers. (Event 8)
Restore RWL with RFPT injection prior to -100" OR open ADS valves before RWL reaches -185 inches (Event 9)
ES 301-4 Attributes Required Actual Items Total Malfunctions 5-8 6
- 1. RBCCW 2A fails; stby does not start (Event 3)
- 2. 2Dll-K615A, Off gas Post treatment radiation monitor inop (Event 4)
- 3. 2F Emergency Bus de-energizes (Event 5)
- 4. Loss HP feed (Event 7)
- 5. 2E 11-F027 A or B fails (Event 8)
Malfunctions After 1-2 2
- 1. 2E 11-F027 A or B fails (Event 8)
EOPEntry
Abnormal Events 2-4 3
- 1. RBCCW 2A fails; stby does not start (Event 3)
- 2. 2F Emergency Bus de-energizes (Event 5)
- 3. Loss of CRD (Event 6)
Major Transients 1-2 1
- 1. Loss HP feed (Event 7)
EOPs entered, 1-2 2
- 1. RC EOP Flow Chart (Event 7) requiring substantive
- 1. CP 1 flow chart (Event 9) requiring substantive actions Critical Tasks 2-3 2
- 2. Restore RWL with RFPT injection prior to -100" OR open ADS valves before RWL reaches -185 inches (Event 9)
(
Page 30 of 31 Critical Tasks DRAFT Facility:
E. I Hatch Scenario No.:
5-01 Op-Test No.:
2009-302 Critical Tasks
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
Manually open RHR 2Ell-F027 AlB Torus SprayfTest Valve prior to exceeding 11 psig in the Torus to preclude damage to the downcomers. (Event 8)
Restore RWL with RFPT injection prior to -100" OR open ADS valves before RWL reaches -185 inches (Event 9)
ES 301-4 Attributes Required Actual Items Total Malfunctions 5-8 6
- 1. RBCCW 2A fails; stby does not start (Event 3)
- 2. 2Dll-K6l5A, Offgas Post treatment radiation monitor inop (Event 4)
- 3. 2F Emergency Bus de-energizes (Event 5)
- 4. Loss HP feed (Event 7)
- 5. 2Ell-F027A or B fails (Event 8)
Malfunctions After 1-2 2
- 1. 2E 11-F027 A or B fails (Event 8)
EOP Entry
Abnormal Events 2-4 3
- 1. RBCCW 2A fails; stby does not start (Event 3)
- 2. 2F Emergency Bus de-energizes (Event 5)
- 3. Loss of CRD (Event 6)
Major Transients 1-2 1
- 1. Loss HP feed (Event 7)
EOPs entered, 1-2 2
- 1. RC EOP Flow Chart (Event 7) requiring substantive
- 1. CP 1 flow chart (Event 9) requiring substantive actions Critical Tasks 2-3 2
- 1. Manually open RHR 2Ell-F027AIB (Event 8)
- 2. Restore RWL with RFPT injection prior to -100" OR open ADS valves before RWL reaches -185 inches (Event 9)
UNIT 1 STATUS Power:
Activities in progress:
UNIT 2 STATUS Power:
HLT 5 NRC Operating Exam Scenario 1 SIDFT TURNOVER l00%RTP None Approximately 60% RTP The following equipment is 2Dll-K615B, Offgas Post treatment radiation monitor.
inoperable:
2C Condensate Booster pump Scheduled evolutions:
Surveillances due this shift:
Active clearances:
Rod Configuration:
Place RFPT '2A' in service IA W 34S0-N21-007-2, "Condensate And Feedwater System" starting at step 7.1.11.9.
Return 2C Condensate Booster pump to service after tag out restoration. Return to 100% power IA W the reactivity plan.
None 2C Condensate Booster pump SeeRWM
(
UNIT 1 STATUS Power:
Activities in progress:
Power:
HLT 5 NRC Operating Exam Scenario 1 SIDFT TURNOVER l00%RTP None Approximately 60% R TP The following equipment is 2DII-K615B, Offgas Post treatment radiation monitor.
inoperable:
2C Condensate Booster pump Scheduled evolutions:
Surveillances due this shift:
Active clearances:
Rod Configuration:
Place RFPT '2A' in service lAW 34S0-N21-007-2, "Condensate And Feedwater System" starting at step 7.1.11.9.
Return 2C Condensate Booster pump to service after tag out restoration. Return to 100% power IA W the reactivity plan.
None 2C Condensate Booster pump SeeRWM
AppendixD Scenario Outline Form ES-D-l NRC Dralt
(
Facility:
E.IHatch Scenario No.: 5-1 Op-Test No.:
2009-302 Examiners:
Operators:
".--"-"~
Initial Conditions. Unit 2 is operating at approximate(y 65% RTP with the '2C' Condensate Pump out
"."."....... "... ~
of service for bearing replacement. Continue reactor staftup and place the '2A' RFPT in service.
The 'B' APRM is bypassed due to failed CPU.
Turnover:
Event Malf. No.
~vent Event No.
Type*
Description 1
N (BOP)
Continue startup and place the RFPT '2A' in service.
2 lR (ATC)
Raise reactor power with Recirc to 65% power.
3 C (BOP)
~
60 y~ergency Bus '2F' de-energizes with time compression TS (SRO) q:e12air and re-en~I$lZ!~D VlSure ;;(6 C~D ivl
',~
4 C (ATC)
Feedwater master controller losses power with time compression ~ ~t cWair and re-ali!:mmenDto Auto.
- JOb (
5(;f#.PA~ 3.: f'VC,I.) 3 Ii: ~
5 C (BOP)
RBCCW Pump '2A' (simulate sheared shaft)
Standby RBCCW pump fails to start (manually started) 6 C (ATC)
~~IC Inad:v.ertent$Lat1_~iQ1~~~~~P5~
TS (SRO) ~lignment to_Auto
_£<po1 >ce.:tCV'v~ 3;J- <[,~::1' 1.... -,,-~
7
,;::~.
". l."
L) 4160 V Station Service Bus '2D' Fault
~
(J ;J,,-,IE HPCI Failure To Start (2E41-F001 Stuck)
If!
I Y&vw1 ~!2--< (
RCIC Trip
~.
/Mtq'W;;
~~
8 I
--..-.~.......
RHR 2E11-F028A or B RHR Torus Spray or Test Valve failed C (BOP)
I closed. (Critical Task)
I 9
1M (ALL)
Emergency Depress due to low reactor water level. (Critical Task)
(
-.~~.-.--
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 NRC Draft Facility:
E. I Hatch Scenario No.:
5-1 Op-Test No.:
2009-302 Examiners:
Operators:
-- -- ----........ ~
Initial Conditions. Unit 2 is operating at approximateiy 65% RTPwith the '2C' Condensate Pump out of service for bearing replacement. Continue reactor startup andplace the '2A' RFPT in service.
The 'B' APRM is bypassed due to failed CPU.
Turnover:
Event Malf. No.
Event Event No.
Type*
Description 1
N (BOP)
Continue startup and place the RFPT '2A' in service.
2 R (ATC)
Raise reactor power with Recirc to 65% power.
3 C (BOP) 4160 V Emergency Bus '2F' de-energizes with time compression TS (SRO) (.!egaiX-itna-re:'energizilig:)
f VlSCuC
- 2 e (' (Z I) i;.
c" 4
C (ATC)
Feedwater master controller losses power with time compression 'L~" d a@air and re-alignmenDto Auto.
J,O!)';
5lG;',;{.:t:5 C:.* *f 3 tJ.: I'u 5
C (BOP)
RBCCW Pump '2A' (simulate sheared shaft)
Standby RBCCW pump fails to start (manually started) 6 C (ATC)
.. RCIClnad-vertentStart with time compression.:repai~ andfe=-7 TS (SRO) \\ alignment to Auto
- <oorr<;;
- c.~*! :,,:~.;-cz~;e-:.*_~ 7
.. '... _-/
.~ ~ __.... ~ __
- _~ *..
-., r_'~',_~.
7
~,
)-
M-(ALL) I 4160 V Station Service Bus '2D' Fault
~ "
)
c,_./ E i~~\\_ ~ HPCI Failure To Start (2E41-FOOl Stuck)
[i 1 I'
"--.1 l".
SIhi.!U' ;;.-, c:L.. '
(~
RCIC Trip
~-
I V,It' (::H,,'
\\
8 I
RHR 2E11-F028A or B RHR Torus Spray or Test Valve failed C (BOP) closed. (Critical Task) 9 1\\1 (ALL) 1 Emergency Depress due to low reactor water level. (Critical Task)
(N)ormal, (R )eacti vi ty, (I)nstrument, (C)omponent, (M)ajor
./
(
Page 2 of3 Scenario Summary Facility:
E. I Hatch Scenario No.:
5-01 Op-Test No.:
2009-302 NRC Dralt Initiating Conditions:
Unit 2 is at 65%.
Turnover Continue reactor startup and place the '2A' RFPT in service Summary:
Event 1: The "2A" RFPT will be placed into service.
Event 2: After the "2A" RFPT is in service the ATC operator will raise reactor power using the Recirc system to approximately 65% power.
Event 3: ComponentlTS; 4160 V Emergency Bus '2F' will de-energize. The SS addresses Tech Specs for inoperable AC electrical distribution subsystem. With time compression repair 4160 V Emergency Bus '2F' will be re-aligned to Startup Auxiliary Transformer 2D.
Event 4: Component; The Feedwater master controller losses power with time compression repair and re-alignment to Auto.
Event 5: Component; RBCCW Pump '2A' will experience a sheared shaft and the standby RBCCW pump will not automatically start. The operator will manually start the standby RBCCW pump to restore system flow/pressure to normal.
Event 6: ComponentlTS; RCIC will experience an inadvertent start with time compression repair and re-alignment to standby.
Event 7: Major; A loss of all high pressure injection occurs as a result of the following: 4160 V Station Service Bus '2D' experiences a fault and de-energizes, "2C" Condensate Booster pump trips on low suction pressure (Time Delay), HPCI fails to start due to 2E41-FOOl (Turbine Steam Supply) is stuck closed, RCIC receives an unrecoverable trip. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.
Event 8: Component; RHR 2E11-F028A or B Torus Spray/Test Valve (depends on which loop of RHR the operator attempts first) will fail closed when the operator attempts to place Torus Spray/Cooling in service. The operator must transition to the other loop of RHR to spray/cool the Torus. (Critical Task)
Event 9: RWL will decrease to TAP. The SS will direct the ATC operator to open all SRVs to Emergency Depressurize the RPV. Reactor pressure will decrease to below the shut-off head of the low pressure ECCS pumps and RWL will be restored to above TAF using all available injection systems. After RWL is determined to be above TAP, injection valves will be throttled to control injection and raise RWL to the normal EOP RWL band. The plant will be emergency depressed due to low reactor water level. (Critical Task)
(
Page 2 of 3 Scenario Summary Facility:
E. I Hatch Scenario No.:
5-01 ap-Test No.:
2009-302 NRC Draft Initiating Conditions:
Unit 2 is at 65%.
Turnover Continue reactor startup and place the '2A' RFPT in service Summary:
Event 1: The "2A" RFPT will be placed into service.
Event 2: After the "2A" RFPT is in service the A TC operator will raise reactor power using the Recirc system to approximately 65% power.
Event 3: ComponentlTS; 4160 V Emergency Bus '2F' will de-energize. The SS addresses Tech Specs for inoperable AC electrical distribution subsystem. With time compression repair 4160 V Emergency Bus '2F' will be re-aligned to Startup Auxiliary Transformer 2D.
Event 4: Component; The Feedwater master controller losses power with time compression repair and re-alignment to Auto.
Event 5: Component; RBCCW Pump '2A' will experience a sheared shaft and the standby RBCCW pump will not automatically start. The operator will manually start the standby RBCCW pump to restore system flow/pressure to normal.
Event 6: ComponentlTS; RCIC will experience an inadvertent start with time compression repair and re-alignment to standby.
Event 7: Major; A loss of all high pressure injection occurs as a result of the following: 4160 V Station Service Bus '2D' experiences a fault and de-energizes, "2C" Condensate Booster pump trips on low suction pressure (Time Delay), HPCI fails to start due to 2E41-F001 (Turbine Steam Supply) is stuck closed, RCIC receives an unrecoverable trip. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.
Event 8: Component; RHR 2E11-F028A or B Torus Spray/Test Valve (depends on which loop of RHR the operator attempts first) will fail closed when the operator attempts to place Torus Spray/Cooling in service. The operator must transition to the other loop of RHR to spray/cool the Torus. (Critical Task)
Event 9: RWL will decrease to TAF. The SS will direct the ATC operator to open all SRVs to Emergency Depressurize the RPV. Reactor pressure will decrease to below the shut-off head of the low pressure ECCS pumps and RWL will be restored to above TAF using all available injection systems. After RWL is determined to be above TAF, injection valves will be throttled to control injection and raise RWL to the normal EOP RWL band. The plant will be emergency depressed due to low reactor water level. (Critical Task)
Page 3 of3 Critical Tasks NRC Draft Facility:
E. I Hatch Scenario No.:
5-01 Op-Test No.:
2009-302 Critical Tasks Manually open RHR 2EII-F028A1B Torus Spray/Test Valve prior to exceeding 11 psig in the Torus to preclude damage to the downcomers. (Event 8)
Open ADS valves before RWL reaches -185 inches (Event 9)
(
Page 3 of 3 Critical Tasks NRC Draft Facility:
E. I Hatch Scenario No.:
5-01 Op-Test No.:
2009-302 Critical Tasks Manually open RHR 2EII-F028NB Torus Spray/Test Valve prior to exceeding 11 psig in the Torus to preclude damage to the downcomers. (Event 8)
Open ADS valves before RWL reaches -185 inches (Event 9)
Page 1 of 19 AppendixD Scenario Outline Form ES-D-l NRC Draft Facility:
E. I Hatch Scenario No.:
5-02 Op-Test No.:
2009-302 Examiners:
Operators:
SRO RO BOP Initial Conditions. Reactor power is approximately 70% power holding for control rod sequence exchange due next shift.
Turnover: APRM 'B' is bypassed due to failed CPU. RCIC is isolated following repair of the outboard isolation valve breaker. System restoration to standby per 34S0-E51-00l-2, RCIC System, is in progress at step 7.1.1.36. The functional test for the Valve has been performed. RCIC system will be unisolated and placed in standby.
Event Malf. No.
Event Event No.
Type*
Description 1
N/A
~ (BOP)
Unisolate RCIC and place in standby 2
mfE5L250 C (BOP)
RCIC Steam Line breaks in the Rx bldg.
svoE51074 TS (SRO)
RCIC isolation valves fail to auto close (Critical Task) svoE51075 3
mfC5L14A TS (SRO)
APRM '2A' Failure 4
mfN2L88A C (ATC)
mf70022407 C (BOP)
'2C' SSAC high temp condition
'2A & 2B' SSACs are manually started by BOP 6
mfN21_87A C (ATC)
RFPT '2A' receives High vibration trip signal but does not trip. ATC manually trips RFPT '2A' 7
N/A R (ATC)
Insert Control Rods to exit RPI 8
mfS11_161 M(ALL)
Loss of Offsite Power mfR43_167A
'2A' & '2C' EDG Fails to Start and cannot be started.
mfR43 49C
'lB' EDG supplies power to '2F' 4160 V bus 9
mfE41_235A C (BOP)
HPCI fails to auto start on low RPV level or high DW pressure mfE41 235B (Critical Task)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 19 AppendixD Scenario Outline Form ES-D-l NRC Draft Facility:
E. I Hatch Scenario No.:
5-02 Op-Test No.:
2009-302 Examiners:
Operators:
SRO RO BOP Initial Conditions. Reactor power is approximately 70% power holding for control rod sequence exchange due next shift.
Turnover: APRM 'B' is bypassed due to failed CPU. RCIC is isolated following repair of the outboard isolation valve breaker. System restoration to standby per 34S0-E51-00l-2, RCIC System, is in progress at step 7.1.1.36. The functional test for the Valve has been performed. RCIC system will be unisolated and placed in standby.
Event Malf. No.
Event Event
(
No.
Type*
Description 1
N/A N (BOP)
Unisolate RCIC and place in standby 2
mfE5L250 C (BOP)
RCIC Steam Line breaks in the Rx bldg.
svoE51074 TS (SRO)
RCIC isolation valves fail to auto close (Critical Task) svoE51075 3
mfC5L14A TS (SRO)
APRM '2A' Failure
~
mfN2L88A C (ATC)
mf70022407 C (BOP)
'2C' SSAC high temp condition
'2A & 2B' SSACs are manually started by BOP 6
mfN21_87A C (ATC)
RFPT '2A' receives High vibration trip signal but does not trip. ATC manually trips RFPT '2A' 7
IN/A R (ATC)
Insert Control Rods to exit RPI 8
mfS11_161 M (ALL)
Loss of Offsite Power mfR43_167A
'2A' & '2C' EDG Fails to Start and cannot be started.
mfR43 49C
'lB' EDG supplies power to '2F' 4160 V bus 9
mfE41_235A C (BOP)
HPCI fails to auto start on low RPV level or high DW pressure mfE41 235B (Critical Task)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix 0 Required Operator Actions Form ES-O-2 II Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
1 Page 2 of 19 Event
Description:
Unisolate RCIC and place in standby II Time I Position I Applicant's Actions or Behavior SRO Directs BOP to unisolate RCIC and place in standby IA W 34S0-E51-001-2, RCIC System, starting at step 7.1.1.36.
SIMULATOR OPERATOR: When 2E51-F007 is open, ENSURE Event Trigger (E51-1) is ACTWATED BOP
- Opens 2E51-F054 Steam Line Drain Valve
- Opens 2E51-F008 Steam Supply Line Isol Valve
- Throttles 2E51-F007 Steam Supply Isol Valve
- Fully Opens 2E51-F007 when turbine steam inlet pressure is within 50 psig of reactor pressure on 2B21-R623A or B (P601 panel)
- Closes 2E51-F054, Steam Line Drain Valve when annunciator 602-308, 'RCIC Turbine Inlet Drain Pot Level High' clears Simulator Operator: At the direction of the Chief Examiner proceed to the next event.
Appendix 0 Required Operator Actions Form ES-O-2 II Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
1 Page 2 of 19 Event
Description:
Unisolate RCIC and place in standby I Time I Position I Applicant's Actions or Behavior I
SRO Directs BOP to unisolate RCIC and place in standby lAW 34S0-E51-001-2, RCIC System, starting at step 7.1.1.36.
SIMULATOR OPERATOR: When 2E51-F007 is open, ENSURE Event Trigger (E51-1) is ACTIVATED BOP
- Opens 2E51-F054 Steam Line Drain Valve
- Opens 2E51-F008 Steam Supply Line Isol Valve
- Throttles 2E5l-F007 Steam Supply Isol Valve
- Fully Opens 2E51-F007 when turbine steam inlet pressure is within 50 psig of reactor pressure on 2B 21-R623 A or B (P60 1 panel)
- Closes 2E51-F054, Steam Line Drain Valve when annunciator
(
602-308, 'RCIC Turbine Inlet Drain Pot Level High' clears Simulator Operator: At the direction of the Chief Examiner proceed to the next event.
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
2 Page 3 of 19 Event
Description:
RCIC steam line break Time I Position I Applicant's Actions or Behavior Simulator Operator: At the direction of the Chief Examiner, ACTIVATE (RB-2)
- mfE51_250 (RCIC Leak)
- svoE51075 (F008 stuck open)
NOTE: It takes approximately 3 minutesfor the "Stm Chase SEC Clr Auto Started" to alarm.
When "Stm Chase SEC Clr Auto Started" alarms, ACTIVATE (RB-I):
- svoDll174 D11-K609A Rx Bldg Pot ContamArea Vnt 10 ramp 20
- svoDll175 Dll-K609B RxBldg Pot ContamArea Vnt 10 ramp 20
- svoDll176 Dll-K609C Rx Bldg Pot ContamArea Vnt 10 ramp 20
- svoD11177 Dll-K609D Rx Bldg Pot ContamArea Vnt 10 ramp 20
- mj601411 026 Rx Bldg Pot Contam Area Radiation High (Annunciator On)
ALL Recognize annunciators:
- 657-006, 'Stm Chase SEC Clr Auto Started'
- 601-321, 'Leak Det Diff Temp High' BOP Responds to annunciator, 'Stm Chase SEC Clr Auto Started'"
Enters 657-006 and starts investigating the cause of the cooler auto start.
- Confirms 2T41-B009, Secondary Stm. Chase Cooler is running
- Monitors Steam Tunnel temps
- Enters 34AB-T22-001-2, 'Primary Coolant System Pipe Break - Rx Building.
Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
2 Page 3 of 19 Event
Description:
RCIC steam line break Time I Position I Applicant's Actions or Behavior Simulator Operator: At the direction of the Chief Examiner, ACTIVATE (RB-2)
- mfE51_250 (RCIC Leak)
- svoE51075 (F008 stuck open)
NOTE: It takes approximately 3 minutes for the "Stm Chase SEC Clr Auto Started" to alarm.
When "Stm Chase SEC Clr Auto Started" alarms, ACTIVATE (RB-l):
- svoDll174 D11-K609A Rx Bldg Pot Contam Area Vnt 10 ramp 20
- svoDll175 D11-K609B Rx Bldg Pot Contam Area Vnt 10 ramp 20
- svoD 11176 D 11-K609C Rx Bldg Pot Contam Area Vnt 10 ramp 20
- svoDll177 Dll-K609D Rx Bldg Pot ContamArea Vnt 10 ramp 20
- mf601411 026 Rx Bldg Pot Contam Area Radiation High (Annunciator On)
(
ALL Recognize annunciators:
- 657-006, 'Stm Chase SEC Clr Auto Started'
- 601-321, 'Leak Det Diff Temp High' BOP Responds to annunciator, 'Stm Chase SEC Clr Auto Started'"
Enters 657-006 and starts investigating the cause of the cooler auto start.
- Confirms 2T41-B009, Secondary Stm. Chase Cooler is running
- Monitors Steam Tunnel temps
- Enters 34AB-T22-001-2, 'Primary Coolant System Pipe Break - Rx Building.
(
Appendix 0 Required Operator Actions Form ES-O-2
'l Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
2 Page 4 of 19 Event
Description:
RCIC steam line break Time Position Applicant's Actions or Behavior I
ATC Acknowledges 601-321, 'Leak Det DiffTemp High' and reports to SS.
Enters 601-321 and starts investigating.
- Confirms which area is producing alarm
- Enters 34AB-T22-003-2, 'Secondary Containment Control' SIMULATOR OPERATOR: ENSURE Event Trigger (ESl-2) is ACTIVATED when Steam Chase diff temp red light illuminates.
Note: It will take about 30 minutes for a Group 1 isolation to occur. At direction of the Chief Examiner, if P603-2 "Group 1 System A Trip" alarms, IMMEDIATELY DELETE mjESl_2S0.
- Enters the 31EO-EOP-014-2, 'Secondary Containment' EOP Flowchart on Secondary Containment High Differential Temperature.
- Has an operator monitor Sec Cont. Temps.
- Has operators monitor systems for source of the leak.
SIMULATOR OPERATOR: When EOP SC entered and Chief Examiner concurs:
- ACTIVATE mfESl_1l3 (RB-7) (RCIC Auto Isolation ESI-FOO8)
- ENSURE Event Trigger (ESl-l) is ACTIVATED when F007 is manually closed:
- svoDl1l74
- svoDll17S
- svoDll176
- svoDll177
(
- mf601411026 Appendix 0 Required Operator Actions Form ES-O-2 I,
Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
2 Page 4 of 19 Event
Description:
RCIC steam line break Time Position Applicant's Actions or Behavior ATC Acknowledges 601-321, 'Leak Det Diff Temp High' and reports to SS.
Enters 601-321 and starts investigating.
- Confirms which area is producing alarm
- Enters 34AB-T22-003-2, 'Secondary Containment Control' SIMULATOR OPERATOR: ENSURE Event Trigger (E51-2) is ACTIVATED when Steam Chase diff temp red light illuminates.
Note: It will take about 30 minutes for a Group I isolation to occur. At direction of the Chief Examiner, if P603-2 "Group I System A Trip" alarms,
(
IMMEDIATELY DELETE mfE51_250.
- Enters the 31EO-EOP-014-2, 'Secondary Containment' EOP Flowchart on Secondary Containment High Differential Temperature.
- Has an operator monitor Sec Cont. Temps.
- Has operators monitor systems for source of the leak.
SIMULATOR OPERATOR: When EOP SC entered and Chief Examiner concurs:
- ENSURE Event Trigger (E51-1) is ACTIVATED when F007 is manually closed:
- svoDIII74
- svoDIII75
- svoDIII76
- svoDIII77
(
- mf60I4II026
Appendix D Required Operator Actions Form ES-D-2
~
Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
2 Page 5 of 19 Event
Description:
RCIC steam line break Time Position Applicant's Actions or Behavior I
ALL Recognize annunciators:
- 602-302, 'RCIC Steam Line Diff Press High'
- 602-301, 'RCIC Turbine Trip'
- 602-313, 'RCIC Isolation Signal Logic A' BOP Responds to the following annunciators:
- 602-302, 'RCIC Steam Line Diff Press High'
- 602-301, 'RCIC Turbine Trip'
- Places 2E51-F007 control switch to CLOSE.
- Places 2E51-F008 control switch to CLOSE.
- Informs SS of failure of 2E51-F008 to close SRO Reviews Tech Specs section 3.6.1.3.A "Primary Containment Isolation Valves" and determines:
- 2E51-F008 Inop
- 2E51-F007 must be closed and deactivated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SIMULATOR OPERATOR; At Chief Examiners direction, proceed to the next event.
Appendix D Required Operator Actions Form ES-D-2 I
Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
2 Page 5 of 19 Event
Description:
RCIC steam line break Time Position Applicanfs Actions or Behavior I
ALL Recognize annunciators:
- 602-302, 'RCIC Steam Line Diff Press High'
- 602-301, 'RCIC Turbine Trip'
- 602-313, 'RCIC Isolation Signal Logic A' BOP Responds to the following annunciators:
- 602-302, 'RCIC Steam Line Diff Press High'
- 602-301, 'RCIC Turbine Trip'
- 602-313, 'RCIC Isolation Signal Logic A'
(
Responds to failure of RCIC Isolation:
- Places 2E51-F007 control switch to CLOSE.
- Places 2E51-F008 control switch to CLOSE.
- Informs SS of failure of 2E51-F008 to close SRO Reviews Tech Specs section 3.6.1.3.A "Primary Containment Isolation Valves" and determines:
- 2E51-F008 Inop
- 2E51-F007 must be closed and deactivated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SIMULATOR OPERATOR; At Chief Examiners direction, proceed to the next event.
Appendix D Required Operator Actions Form ES-D-2 If Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
3 Page 6 of 19 Event
Description:
APRM 2A failure II Time Position Applicant's Actions or Behavior I
SIMULATOR OPERATOR: After Primary Containment Tech Spec cali, and as directed by the Chief Examiner, ENTER (RB-3) mfC51_14A (APRM 'A' Failure)
ALL Recognize annunciators:
- 603-210, 'APRM/OPRM Trip'
- 603-238, 'Rod Out Block'
- 603-239, 'RMCS/RWM Rod Block or Sys Trouble' ATC Responds to annunciators:
- 603-210, 'APRM/OPRM Trip'
- 603-238, 'Rod Out Block'
- Reviews Tech Specs section 3.3.1.1 Condition A and determines that one required channel is inoperable and must be placed in trip in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SIMULATOR OPERATOR; At Chief Examiners direction, proceed to the next event.
\\
(
(
Appendix 0 Required Operator Actions Form ES-O-2
,~ Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
3 Page 6 of 19 Event
Description:
APRM 2A failure Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR: After Primary Containment Tech Spec call, and as directed by the Chief Examiner, ENTER (RB-3) mfC51_14A (APRM 'A' Failure)
ALL Recognize annunciators:
- 603-210, 'APRM/OPRM Trip'
- 603-238, 'Rod Out Block'
- 603-239, 'RMCS/RWM Rod Block or Sys Trouble' ATC Responds to annunciators:
- 603-210, 'APRM/OPRM Trip'
- 603-238, 'Rod Out Block'
- Reviews Tech Specs section 3.3.1.1 Condition A and determines that one required channel is inoperable and must be placed in trip in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SIMULATOR OPERATOR; At Chief Examiners direction, proceed to the next event.
Appendix 0 Required Operator Actions Form ES-O-2 I~
Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
4 Page 7 of 19 Event
Description:
RFPT loop seal failure II Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR: At the direction of the Chief Examiner, ACTIVATE (RB-4)
- mj65031541 "RFP Loop Seal Level Low (Annunciator On)"
- mfN61_73 "Main Condenser Air In-leakage" NOTE: It takes approximately 10 minutes for vacuum to decrease to 25.7".
ALL Recognize "RFP Loop Seal Level Low" annunciator SIMULATOR OPERATOR: When sent as an SO out to the plant, wait 3 minutes and report:
(
- 2N22-F398 was closed and now is open
- Seal water pressures are normal andlbut the lineup check is not completed.
ATe Respond to annunciator RFP Loop Seal Level Low
- Sends an SO to confirm seal water lineup and pressures BOP Monitors Inlet Flow to Stack on 2N62-P600 Appendix D Required Operator Actions Form ES-D-2
. Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
4 Page 7 of 19 Event
Description:
RFPT loop seal failure I Time Position Applicant's Actions or Behavior I
SIMULATOR OPERATOR: At the direction of the Chief Examiner, ACTIVATE (RB-4)
- mj65031541 "RFP Loop Seal Level Low (Annunciator On)"
- mfN61_73 "Main Condenser Air In-leakage" NOTE: It takes approximately 10 minutes for vacuum to decrease to 25.7".
ALL Recognize "RFP Loop Seal Level Low" annunciator SIMULATOR OPERATOR: When sent as an SO out to the plant, wait 3 minutes and report:
(
- 2N22-F398 was closed and now is open
- Seal water pressures are normal andlbut the lineup check is not completed.
ATe Respond to annunciator RFP Loop Seal Level Low
- Sends an SO to confirm seal water lineup and pressures BOP Monitors Inlet Flow to Stack on 2N62-P600
Appendix 0 Required Operator Actions Form ES-O-2 II
. Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
4 Page 8 of 19 Event
Description:
RFPT loop seal failure II Time Position Applicant's Actions or Behavior I
SIMULATOR OPERATOR: Delete m/65031541 when one o/thefollowing occurs:
- Condenser vacuum drops to 25.7"
- 2N21-F265 is closed DELETE mfN61_73 one minute after mf65031541 is deleted.
ATC With seal water pressures normal, closes 2N2l-F265 after 5 minutes of alarm 650-319, 'RFP Loop Seal Level Low' being received.
ATC Opens 2N21-F265 when 650-319, 'RFP Loop Seal Level Low' clears.
SIMULATOR OPERATOR; At Chief Examiners direction, proceed to the next event.
Appendix D Required Operator Actions Form ES-D-2 II Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
4 Page 8 of 19 Event
Description:
RFPT loop seal failure Time Position Applicant's Actions or Behavior I
SIMULATOR OPERATOR: Delete mf65031541 when one of the following occurs:
- Condenser vacuum drops to 25.7"
- 2N21-F265 is closed DELETE mfN61_73 one minute after mf65031541 is deleted.
ATC With seal water pressures normal, closes 2N2l-F265 after 5 minutes of alarm 650-319, 'RFP Loop Seal Level Low' being received.
ATC Opens 2N21-F265 when 650-319, 'RFP Loop Seal Level Low' clears.
(
SIMULATOR OPERATOR; At Chief Examiners direction, proceed to the next event.
Appendix D Required Operator Actions Form ES-D-2
'I Op-Test No.: 2009-301 Scenario No.:
5-02 Event No.:
5 Page 9 of 19 Event
Description:
'2C' SSAC high temp condition and secured. '2A & 2B' SSACs are manually started.
I Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR: At the direction of the Chief Examiner ACTIVATE (RB-S)
- mj70022407 Control Bldg Aftclr BODlC Disch Temp High (Annunciator On)
- aoPS2-R600 "Service Air Pressure"
- aoPSI-R600 "Control Air Pressure" SIMULATOR OPERATOR: When the operator dispatches a SO locally, wait 3 minutes, then NOTIFY operator that local temp on 2P51-R312C is 125°F and 2P51-R302C is reading 385°F.
BOP Responds to annunciator 700-216, 'Control Bldg Aftclr B001C Disch Temp High':
- Sends SO to locally confirm temperature is> 120 deg F on 2P51-R312C and 2P51-R302C.
- Starts the 2A or 2B Service Air Compressor
- Secures the 2C Service Air Compressor by placing its control switch in Pull-to-Lock.
SIMULATOR OPERATOR: When the operator secures the 2C Service Air Compressor, ENSURE Event Trigger (PSI-I) is ACTIVATED:
DELETES the following:
- aoPS2-R600 "Service Air Pressure"
- aoPSI-R600 "Control Air Pressure"
- mj70022407 Control Bldg Aftclr BODlC Disch Temp High (Annunciator On)
SIMULATOR OPERATOR; At Chief Examiners direction, proceed to the next event.
Appendix 0 Required Operator Actions Form ES-O-2 II Op-Test No.: 2009-301 Scenario No.:
5-02 Event No.:
5 Page 9 of 19 Event
Description:
'2C' SSAC high temp condition and secured. '2A & 2B' SSACs are manually started.
II Time Position Applicant's Actions or Behavior I
SIMULATOR OPERATOR: At the direction of the Chief Examiner ACTIVATE (RB-S)
- mj70022407 Control Bldg Aftclr BOOlC Disch Temp High (Annunciator On)
- aoPS2-R600 "Service Air Pressure"
- aoPSI-R600 "Control Air Pressure" SIMULATOR OPERATOR: When the operator dispatches a SO locally, wait 3 minutes, then NOTIFY operator that local temp on 2P5l-R312C is l25°F and 2P5l-R302C is reading 385°F.
BOP Responds to annunciator 700-216, 'Control Bldg Aftclr BOOlC Disch Temp High':
- Sends SO to locally confirm temperature is > 120 deg F on 2P51-R312C and 2P51-R302C.
(
- Starts the 2A or 2B Service Air Compressor
- Secures the 2C Service Air Compressor by placing its control switch in Pull-to-Lock.
SIMULATOR OPERATOR: When the operator secures the 2C Service Air Compressor, ENSURE Event Trigger (PSI-I) is ACTIVATED:
DELETES the following:
- aoPS2-R600 "Service Air Pressure"
- aoPSI-R600 "Control Air Pressure"
- mj70022407 Control Bldg Aftclr BOOl C Disch Temp High (Annunciator On)
SIMULATOR OPERATOR; At Chief Examiners direction, proceed to the next event.
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Appendix D Required Operator Actions Form ES-D-2 II Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
6 Page 10 of 19 Event
Description:
RFPT 2A high vibration trip signal I Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR: At the direction of the Chief Examiner, ACTIVATE mj6503I553 (RB-6) RFPT '2A' Excessive Vibration (Annunciator On).
ALL Recognize "RFPT 2A Excessive Vibration" ATC Responds to annunciator 650-331, 'RFPT 2A Excessive Vibration' and executes the Alarm Response Procedure:
- Dispatches an SO to report local vibration on TMR Workstation Mark V Control Panel.
- Confirm oil temperature is being maintained at 120 to 130°F
- Contact System Engineer for further instructions SIMULATOR OPERATOR: When contacted by the ATC, as the System Engineer, tell the operator you will look into the RFPT vibration and get back to the operator As the SO, wait two minutes after being dispatched and then report that 2A RFPT vibrations are 8 mils and increasing.
ATC With RFPT vibration> 6.0 mils, trips 2A RFPT.
SRO Directs ATe to trip 2A RFPT.
SIMULATOR OPERATOR: When the operator trips the 2A RFPT, ENSURE Event Trigger (N21-1) is ACTIVATED:
- DELETES 'RFPT '2A' Excessive Vibration' alarm II SIMULATOR OPERATOR; At Chief Examiners direction, proceed to the next event.
Appendix 0 Required Operator Actions Form ES-D-2 II Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
6 Page 10 of 19 Event
Description:
RFPT 2A high vibration trip signal Time Position Applicant's Actions or Behavior I
SIMULATOR OPERATOR: At the direction of the Chief Examiner, ACTIVATE mf65031553 (RB-6) RFPT '2A' Excessive Vibration (Annunciator On).
ALL Recognize "RFPT 2A Excessive Vibration" ATC Responds to annunciator 650-331, 'RFPT 2A Excessive Vibration' and executes the Alarm Response Procedure:
- Dispatches an SO to report local vibration on TMR Workstation Mark V Control Panel.
- Confirm oil temperature is being maintained at 120 to 130°F
- Contact System Engineer for further instructions
(
SIMULATOR OPERATOR: When contacted by the ATC, as the System Engineer, tell the operator you will look into the RFPT vibration and get back to the operator As the SO, wait two minutes after being dispatched and then report that 2A RFPT vibrations are 8 mils and increasing.
ATC With RFPT vibration> 6.0 mils, trips 2A RFPT.
SRO Directs A TC to trip 2A RFPT.
SIMULATOR OPERATOR: When the operator trips the 2A RFPT, ENSURE Event Trigger (N21-1) is ACTIVATED:
- DELETES 'RFPT '2A' Excessive Vibration' alarm II SIMULATOR OPERATOR; At Chief Examiners direction, proceed to the next event.
Appendix D Required Operator Actions Form ES-D-2 II Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
7 Page 11 of 19 Event
Description:
Inserting control rods to exit RPI Time Position Applicant's Actions or Behavior ALL Recognize annunciator "Recirc A(B) Flow Limit" ATC Responds to annunciators 602-134 & 602-234, 'Recirc A & B Flow Limit'
- Confirms Recirc pump A (B) speed has ronback by observing percent speed or RPMs.
- Evaluate for Loop Flow Mismatch by observing there is NOT> 7.7 Mlbmlhr difference between the two loop flows.
- Determine which speed limiter is enforcing by observing 33% speed on the speed meter.
- Determines Region of Potential Instabilities is entered and requests STA's direction SIMULATOR OPERATOR: As the STA, when the operator asks for direction, then instructs the operator to insert control rods until Reactor Power is 30%.
- Within 15 minutes of entering the Immediate Exit Region of the Power to Flow map, directs operator to exit the region by inserting control rods.
- Ensures the plant has exited the Immediate Exit Region of the Power to Flow map within one hour.
- Has a control rod movement brief per 34GO-OPS-065-0
- Contacts Georgia Control Center (GCC) and Power Coordination Center (PCC)
SIMULATOR OPERATOR: As the STA, when the SS directs crew entry into 34GO-OPS-005-2, Power Changes, calls the SS and informs him that you will perform the computer feedwater flow cross over corrections.
SIMULATOR OPERATOR: When contacted as the GCC and pec, acknowledge the communication.
/
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Appendix 0 Required Operator Actions Form ES-O-2 If Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
7 Page 11 of 19 Event
Description:
Inserting control rods to exit RPI Time Position Applicant's Actions or Behavior ALL Recognize annunciator "Recirc A(B) Flow Limit" ATC Responds to annunciators 602-134 & 602-234, 'Recirc A & B Flow Limit'
- Confirms Recirc pump A (B) speed has ronback by observing percent speed or RPMs.
- Evaluate for Loop Flow Mismatch by observing there is NOT> 7.7 Mlbmlhr difference between the two loop flows.
- Determine which speed limiter is enforcing by observing 33% speed on the speed meter.
- Determines Region of Potential Instabilities is entered and requests STA's direction SIMULATOR OPERATOR: As the STA, when the operator asks Jor direction, then instructs the operator to insert control rods until Reactor Power is 30%.
- Within 15 minutes of entering the Immediate Exit Region of the Power to Flow map, directs operator to exit the region by inserting control rods.
- Ensures the plant has exited the Immediate Exit Region of the Power to Flow map within one hour.
- Has a control rod movement brief per 34GO-OPS-065-0
- Contacts Georgia Control Center (GCC) and Power Coordination Center (PCC)
SIMULATOR OPERATOR: As the STA, when the SS directs crew entry into 34GO-OPS-005-2, Power Changes, calls the SS and iriforms him that you will peiform the computer Jeedwater flow cross over corrections.
SIMULATOR OPERATOR: When contacted as the GCC and PCC, acknowledge the communication.
Appendix 0 Required Operator Actions Form ES-O-2
(\\
Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
7 Page 12 of 19 Event
Description:
Inserting control rods to exit RPI Time Position Applicant's Actions or Behavior I
- Inserts control rods per 34GO-OPS-065-0, starting with control rod Group 54.
- During rod insertion, rod steps will be performed in reverse sequential order, starting at the highest numbered step. (** rod steps are not required to be performed sequentially, but must be positioned to their RWM insert limit prior to inserting lower numbered groups).
- Selects Rod
- Places Control Rod movement switch to the IN position
- Verifies Rod moves using Rod display information and Rx and Generator power decreasing.
- If required, adjust 2C11-F003 to get 220 - 280 psid drive water dp.
ATC Note: RBM Downscale alarm may alarm during this movement due to the significant rod worth of these rods. It is allowed to flag the RBM Downscale and Rod Block alarm.
- Releases Rod movement switch so that the control rod stops 1 position before the insert limit unless the insert limit is 00.
- Initials Rod movement Sheet.
- Verifier, if available, Initials Rod movement sheet.
- Notifies the SS when they are out of the region of potential instabilities.
BOP Removes a CBP from service.
Note; It is not intended to wait until a Condensate Booster pump is removed from service, at Chief Examiner's direction, move on to the next Event Appendix 0 Required Operator Actions Form ES-O-2
(
'\\ Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
7 Page 12 of 19 Event
Description:
Inserting control rods to exit RPI Time Position Applicant's Actions or Behavior I
- Inserts control rods per 34GO-OPS-065-0, starting with control rod Group 54.
- During rod insertion, rod steps will be performed in reverse sequential order, starting at the highest numbered step. (** rod steps are not required to be performed sequentially, but must be positioned to their RWM insert limit prior to inserting lower numbered groups).
- Selects Rod
- Places Control Rod movement switch to the IN position
- Verifies Rod moves using Rod display information and Rx and Generator power decreasing.
- If required, adjust 2CII-F003 to get 220 - 280 psid drive water dp.
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ATC Note: RBM Downscale alarm may alarm during this movement due to the significant rod worth of these rods. It is allowed to flag the RBM Downscale and Rod Block alarm.
- Releases Rod movement switch so that the control rod stops 1 position before the insert limit unless the insert limit is 00.
- Initials Rod movement Sheet.
- Verifier, if available, Initials Rod movement sheet.
- Notifies the SS when they are out of the region of potential instabilities.
BOP Removes a CBP from service.
Note; It is not intended to wait until a Condensate Booster pump is removed from service, at Chief Examiner's direction, move on to the next Event
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Appendix D Required Operator Actions Form ES-D-2
.~
Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
8 Page 13 of 19 Event
Description:
LOSP with 2A & 2C EDGs failure I Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR: At the direction of the Chief Examiner, ACTIVATE (RB-8), mfSll_161, "Loss of Off site Power".
ALL Recognize a loss of offsite power and plant scram.
Note: The SS may assign one operator to perform Scram procedure placards RC-1, RC-2 and RC-3.
- Assigns the ATC to perform RC-1.
- Assigns the BOP operator to perform RC-2 and RC-3.
- If time allows assigns TC-1 to be performed.
- Enters the RC EOP flow chart, 31EO-EOP-01O-2, once reactor water level decreases to 3,"or reactor pressure increases to 1074 psig.
- Performs RC-l consisting of:
- Inserts a manual scram.
- Places the mode switch to shutdown.
- NotifIes the SS of rod position check.
- Places SDV isolation valve switch to "isolate" & confIrms closed.
- Shifts recorders to read IRMS, when required.
- Ranges IRMS to bring reading on scale.
- NotifIes the SS when the above actions are complete.
Note: With a Loss of Offsite Power, the pertinent operator RC-2 actions are limited to checking ECCS.
- 11 Appendix D Required Operator Actions Form ES-D-2 I,
Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
8 Page 13 of 19 Event
Description:
LOSP with 2A & 2C EDGs failure Time Position Applicant's Actions or Behavior I
SIMULATOR OPERATOR: At the direction of the Chief Examiner, ACTIVATE (RB-8), mfSlI_I6I, "Loss of Off site Power".
ALL Recognize a loss of offsite power and plant scram.
Note: The SS may assign one operator to perform Scram procedure placards RC-1, RC-2 and RC-3.
- Assigns the A TC to perform RC-1.
- Assigns the BOP operator to perform RC-2 and RC-3.
- If time allows assigns TC-1 to be performed.
- Enters the RC EOP flow chart, 31EO-EOP-01O-2, once reactor water level decreases to 3,"or reactor pressure increases to 1074 psig.
- Directs EOP RC level control band of +3" to +50"
(
- Performs RC-1 consisting of:
- Inserts a manual scram.
- Places the mode switch to shutdown.
- Notifies the SS of rod position check.
- Places SDV isolation valve switch to "isolate" & confirms closed.
- Shifts recorders to read IRMS, when required.
- Ranges IRMS to bring reading on scale.
- Notifies the SS when the above actions are complete.
Note: With a Loss of Offsite Power, the pertinent operator RC-2 actions are limited to checking ECCS.
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II
Appendix D Required Operator Actions Form ES-D-2
'I Op. Test No.: 2009*302 Scenario No.:
5*02 Event No.:
8 Page 14 of 19 Event
Description:
LOSP with 2A & 2C EDGs failure Time Position Applicant's Actions or Behavior BOP
- Checks ECCS Injection Systems and verifies no initiation signal present.
- Performs RC-3 consisting of:
- Monitor RPV pressure.
- Maintain RPV pressure between 1074 and 800 psig.
- Directs ATC to address the plant electrical systems and enter the "Station Black" abnormal procedure, 34AB-R22-003-2, and "Diesel Generator Recovery" abnormal, 34AB-R43-001-2.
- Calls for maintenance support in restoring all emergency 4160 VAC buses.
ATC Reviews EDG "2A" annunciators and determines there is a "Start Failure".
IA W 34AB-R43-001-2, Diesel Generator Recovery, for EDG "A" :
- Determines the EDG is not running
- Determines the Auto Start System Operative Light is NOT lit.
- Depresses the Shutdown Relay Pushbutton
- Determines the EDG did NOT start.
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Appendix 0 Required Operator Actions Form ES-O-2
'\\
Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
8 Page 14 of 19 Event
Description:
LOSP with 2A & 2C EDGs failure I Time Position Applicant's Actions or Behavior BOP
- Checks ECCS Injection Systems and verifies no initiation signal present.
- Performs RC-3 consisting of:
- Monitor RPV pressure.
- Maintain RPV pressure between 1074 and 800 psig.
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- Directs A TC to address the plant electrical systems and enter the "Station Black" abnormal procedure, 34AB-R22-003-2, and "Diesel Generator Recovery" abnormal, 34AB-R43-001-2.
- Calls for maintenance support in restoring all emergency 4160 VAC buses.
ATC Reviews EDG "2A" annunciators and determines there is a "Start Failure".
IA W 34AB-R43-00l-2, Diesel Generator Recovery, for EDG "A" :
- Determines the EDG is not running
- Determines the Auto Start System Operative Light is NOT lit.
- Depresses the Shutdown Relay Pushbutton
- Determines the EDG did NOT start.
Appendix D Reguired Operator Actions Form ES-D-2
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II Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
8 Page 15 of 19 Event
Description:
LOSP with 2A & 2C EDGs failure Time Position Applicant's Actions or Behavior I
ATC Reviews EDG "2C" annunciators and determines a "Lube Oil Press Low" and "Emergency Engine Shutdown".
ATC Sends an SO to investigate the shutdown of the EDG SIMULATOR OPERATOR: When called about EDG "B" local switch, activate remote function ifR43_241, (RB-9) "Diesel Gen IB Engine Control Switch, assigned to U2, and inform the operator it is now selected to Unit 2.
Note: When Unit 2 is selected, the EDG will automatically align and energize Unit 2.
ATC lAW 34AB-R43-00l-2, Diesel Generator Recovery, for EDG "B" :
- Determines the EDG is running
- Coordinates with Unit 1 SS to take the local switch to Unit 2
- Reports to SS Bus 2F is now energized SIMULATOR OPERATOR: When called as the SO to investigate the EDGs, wait two minutes and report:
- EDG "A" will not start locally, you will investigate further
- EDG "c" has a break on the oil pump discharge line Note: The crew may start HPCI before -35" RWL or DW pressures increases to 1.85psig and therefore not be aware the auto initiation signal has failed.
f------+--+-------i Appendix 0 Required Operator Actions Form E8-0-2 II Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
8 Page 15 of 19 Event
Description:
LOSP with 2A & 2C EDGs failure Time Position Applicant's Actions or Behavior I
ATC Reviews EDG "2C" annunciators and determines a "Lube Oil Press Low" and "Emergency Engine Shutdown".
ATC Sends an SO to investigate the shutdown of the EDG SIMULATOR OPERATOR: "When called about EDG "B" local switch, activate remote function ifR43_241, (RB-9) "Diesel Gen lB Engine Control Switch, assigned to U2, and inform the operator it is now selected to Unit 2.
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Note: "When Unit 2 is selected, the EDG will automatically align and energize Unit 2.
ATC lAW 34AB-R43-001-2, Diesel Generator Recovery, for EDG "B" :
- Determines the EDG is running
- Coordinates with Unit 1 SS to take the local switch to Unit 2
- Reports to SS Bus 2F is now energized SIMULATOR OPERATOR: "When called as the SO to investigate the EDGs, wait two minutes and report:
- EDG "A" will not start locally, you will investigate further
- EDG "c" has a break on the oil pump discharRe line Note: The crew may start HPCI before -35" RWL or DW pressures increases to 1.85psig and therefore not be aware the auto initiation signal has failed.
I
Appendix D Required Operator Actions Form ES-D-2
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Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
8 Page 16 of 19 Event
Description:
LOSP with 2A & 2C EDGs failure Time I Position J Applicant's Actions or Behavior BOP
- Recognizes HPCI fails to auto start at -35" or 1.85 psig DW pressure and manually starts per 34S0-E41-001-2, prior to emergency depressurization.
- Starts 2E41-C002-2, Barometric Condenser Vacuum Pump.
- Opens 2E41-F001, Turbine Stearn Supply Vlv
- Takes 2E41-C002-3, Aux Oil Pump, control switch to the START position.
- Opens 2E41-F006, Pump Discharge Valve.
- Confirm the following valves OPENED:
0 Turbine Control Vlv 0
Turbine Stop Vlv
- Confirm the turbine comes up to speed
- When flow increases to 790 GPM, confirms 2E41-FOI2, Min Flow Vlv, closed.
- Adjust flow with 2E41-R612, Flow Control to maintain water level.
- If water level is above the auto initiation setpoint the operator may secure HPCI by:
0 Reducing speed to 2000 rpm using the flow controller in manual.
0 Depressing the trip pushbutton and holding until the 2E41-FOOI is fully closed.
0 Closing the stearn supply valve 2E41-FOO1.
Termination criteria: The scenario may be terminated, at the direction of the Chief Examiner, water level is being controlled with HPCI and 4160 VAC Bus F is re-energized.
Appendix 0 Required Operator Actions Form ES-O-2
'I Op-Test No.: 2009-302 Scenario No.:
5-02 Event No.:
8 Page 16 of 19 Event
Description:
LOSP with 2A & 2C EDGs failure II Time I Position I Applicant's Actions or Behavior BOP
- Recognizes HPCI fails to auto start at -35" or 1.85 psig DW pressure and manually starts per 34S0-E41-001-2, prior to emergency depressurization.
- Starts 2E41-C002-2, Barometric Condenser Vacuum Pump.
- Opens 2E41-F001, Turbine Steam Supply Vlv
- Takes 2E41-C002-3, Aux Oil Pump, control switch to the START position.
- Opens 2E41-F006, Pump Discharge Valve.
- Confirm the following valves OPENED:
(
0 Turbine Control Vlv 0
Turbine Stop Vlv
- Confirm the turbine comes up to speed
- When flow increases to 790 GPM, confirms 2E41-F012, Min Flow Vlv, closed.
- Adjust flow with 2E41-R612, Flow Control to maintain water level.
- If water level is above the auto initiation setpoint the operator may secure HPCI by:
0 Reducing speed to 2000 rpm using the flow controller in manual.
0 Depressing the trip pushbutton and holding until the 2E41-F001 is fully closed.
0 Closing the steam supply valve 2E41-FOOl.
Termination criteria: The scenario may be terminated, at the direction of the Chief Examiner, water level is being controlled with HPCI and 4160 VAC Bus
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F is re-energized.
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Facility:
E. I Hatch Initiating Conditions:
Turnover Summary:
Page 17 of 19 Scenario Summary Scenario No.: S*02 OR* Test No.:
2009-302 NRC Draft Unit 2 is at 70% power holding for control rod sequence exchange on next shift.
APRM 'B' is bypassed due to failed CPU. RCIC is isolated following repair of the outboard isolation valve breaker. System restoration to standby per 34S0-E51-001-2, RCIC System, is in progress at step 7.1.1.36. The functional test for the Valve has been performed. RCIC system will be unisolated and placed in standby Event 1: Unisolate RCIC system and place in standby.
Event 2: ComponentlTS; A RCIC steam line will break outside of Primary Containment. The outboard isolation valve is failed open and cannot be closed. Both isolation valves fail to automatically close on an automatic isolation signal and must be manually closed. (Critical Task) The SS addresses Tech Specs for inoperable Primary Containment Isolation Valve.
Event 3: TS; APRM '2A' will experience a CPU failure and trip. The SS addresses Tech Specs for inoperable RPS instrumentation.
Event 4: Component; The RFPT loop seal will experience a low level condition causing condenser vacuum to degrade. The ATC operator will isolate the loop seal drain which stops condenser vacuum decreasing. Once the loop seal level is restored, the operator returns the loop seal system to normal lineup.
EventS: Component; The "2C" Station Service Air Compressor (SSAC) will receive a high discharge air temp alarm. The operator will start the 2A & 2B SSAC's and shutdown 2C SSAC.
Event 6: Component; The '2A' RFPT receives a high vibration trip signal but does not automatically trip. The ATC manually trips the '2A' RFPT Event 7: The ATC inserts control rods to exit the Region of Potential Instabilities.
Event 8: Major; The plant will experience a Loss of Offsite power with the failure of the '2A' and '2C' Emergency Diesel Generators to start. 4160 V '2F' Emergency bus will be energized by the operator taking manual control of the 'lB' Emergency Diesel Generator or when the high DW pressure condition is received.
Event 9: As RWL decreases the HPCI system will fail to auto start on low RWL or high DW pressure. The operator will have to manually start the HPCI system to maintain RWL. (Critical Task)
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Facility:
E. I Hatch Initiating Conditions:
Turnover Summary:
Page 17 of 19 Scenario Summary Scenario No.:
5-02 On-Test No.:
2009-302 NRC Draft Unit 2 is at 70% power holding for control rod sequence exchange on next shift.
APRM 'B' is bypassed due to failed CPU. RCIC is isolated following repair of the outboard isolation valve breaker. System restoration to standby per 34S0-E51-001-2, RCIC System, is in progress at step 7.1.1.36. The functional test for the Valve has been performed. RCIC system will be unisolated and placed in standby Event 1: Unisolate RCIC system and place in standby.
Event 2: ComponenUTS; A RCIC steam line will break outside of Primary Containment. The outboard isolation valve is failed open and cannot be closed. Both isolation valves fail to automatically close on an automatic isolation signal and must be manually closed. (Critical Task) The SS addresses Tech Specs for inoperable Primary Containment Isolation Valve.
Event 3: TS; APRM '2A' will experience a CPU failure and trip. The SS addresses Tech Specs for inoperable RPS instrumentation.
Event 4: Component; The RFPT loop seal will experience a low level condition causing condenser vacuum to degrade. The ATC operator will isolate the loop seal drain which stops condenser vacuum decreasing. Once the loop seal level is restored, the operator returns the loop seal system to normal lineup.
Event 5: Component; The "2C" Station Service Air Compressor (SSAC) will receive a high discharge air temp alarm. The operator will start the 2A & 2B SSAC's and shutdown 2C SSAC.
Event 6: Component; The '2A' RFPT receives a high vibration trip signal but does not automatically trip. The ATC manually trips the '2A' RFPT Event 7: The ATC inserts control rods to exit the Region of Potential Instabilities.
Event 8: Major; The plant will experience a Loss of Offsite power with the failure of the '2A' and '2C' Emergency Diesel Generators to start. 4160 V '2F' Emergency bus will be energized by the operator taking manual control of the '1 B' Emergency Diesel Generator or when the high DW pressure condition is received.
Event 9: As RWL decreases the HPCI system will fail to auto start on low RWL or high DW pressure. The operator will have to manually start the HPCI system to maintain RWL. (Critical Task)
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Page 18 of 19 Critical Tasks NRC Draft Facility:
E. I Hatch Scenario No.:
5-02 Op-Test No.:
2009-302 Critical Tasks
- 1.
')
- 3.
- 4.
- 5.
- 6.
- 7.
Manually isolate the RCIC isolation valves prior to exceeding the Maximum Safe Operating Temperature on the EOP Secondary Containment Flowchart. (Event 2)
Restores RWL injection with HPCI before RWL reaches -185 inches (Event 9)
ES 301-4 Attributes Required Actual Items Total Malfunctions 5-8 7
- 1. RCIC steam line break outside Primary Containment (Event 2)
- 2. APRM '2A' CPU failure (Event 3)
- 4. "2C" SSAC high discharge air temp (Event 5)
- 5. '2A' RFPT high vibration trip signal (Event 6)
- 7. HPCI fail to start (Event 9)
Malfunctions After 1-2 1
- 1. HPCI fail to start (Event 9)
EOPEntry Abnormal Events 2-4 3
- 1. RCIC steam line break outside Primary Containment (Event 2)
- 3. "2C" SSAC high discharge air temp (Event 5)
Major Transients 1-2 1
EOPs entered, 1-2 2
- 1. EOP SC/RR flowchart requiring substantive
requiring substantive actions Critical Tasks 2-3 2
- 1. Isolate RCIC isolation valves (Event 2)
- 2. Maintain RWL> -185 inches (Event 9)
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Page 18 of 19 Critical Tasks NRC Draft Facility:
E. I Hatch Scenario No.:
5-02 Op-Test No.:
2009-302 Critical Tasks
- 1.
")
- 3.
- 4.
- 5.
- 6.
- 7.
Manually isolate the RCIC isolation valves prior to exceeding the Maximum Safe Operating Temperature on the EOP Secondary Containment Flowchart. (Event 2)
Restores R WL injection with HPCI before RWL reaches -185 inches (Event 9)
ES 301-4 Attributes Required Actual Items Total Malfunctions 5-8 7
- 1. RCIC steam line break outside Primary Containment (Event 2)
- 2. APRM '2A' CPU failure (Event 3)
- 4. "2C" SSAC high discharge air temp (Event 5)
- 5. '2A' RFPT high vibration trip signal (Event 6)
- 7. HPCI fail to start (Event 9)
Malfunctions After 1-2 1
- 1. HPCI fail to start (Event 9)
EOP Entry Abnormal Events 2-4 3
- 1. RCIC steam line break outside Primary Containment (Event 2)
- 3. "2C" SSAC high discharge air temp (Event 5)
Major Transients 1-2 1
EOPs entered, 1-2 2
- 1. EOP SC/RR flowchart requiring substantive
requiring substantive actions Critical Tasks 2-3 2
- 1. Isolate RCIC isolation valves (Event 2)
- 2. Maintain RWL > -185 inches (Event 9)
HLT 5 NRC Operating Exam Scenario 2 SHIFT TURNOVER Power:
100%
Activities in progress:
None Power:
Approximately 70% power The following equipment is APRM 2B is bypassed due to failed CPU inoperable:
Scheduled evolutions:
Surveillances due this shift:
Active clearances:
Rod Configuration:
RCIC is isolated following repair of the outboard isolation valve breaker.
Turbine Eccentricity Vibration recorder 2N32-R600 is Out of Service and being worked by I&C.
System restoration to standby per 34S0-E51-00l-2, RCIC System, is in progress at step 7.1.1.36. The functional test for the Valve has been performed. Complete the procedure for placing RCIC in standby.
None None SeeRWM I \\
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HLT 5 NRC Operating Exam Scenario 2 SHIFT TURNOVER UNIT 1 STATUS Power:
100%
Activities in progress:
None Power:
Approximately 70% power The following equipment is APRM 2B is bypassed due to failed CPU inoperable:
Scheduled evolutions:
Surveillances due this shift:
Active clearances:
Rod Configuration:
RCIC is isolated following repair of the outboard isolation val ve breaker.
Turbine Eccentricity Vibration recorder 2N32-R600 is Out of Service and being worked by I&C.
System restoration to standby per 34S0-E51-001-2, RCIC System, is in progress at step 7.1.1.36. The functional test for the Valve has been performed. Complete the procedure for placing RCIC in standby.
None None SeeRWM
Page 1 of 3 AppendixD Scenario Outline Form ES-D-l NRC Draft Facility:
E. I Hatch Scenario No.:
5-2 Op-Test No.:
2009-302 Examiners:
Operators:
SRO RO BOP Initial Conditions. APRM 'B' is bypassed due to failed CPU. Reactor power is approximately 70%
power holding for control rod sequence exchange due next shift. RCIC system will be unisolatedaucr place in standby.
Turnover:
Event Malf. No.
Event Event No.
Type*
Description 1
N (BOP)
Unisolate RCIC and place in standby
~ ;} 00-:1,>:::'
2
/
RCIC Steam Line breaks in the Rx bldg.
\\
c.'i,
,,' ?
, C (BOP)
.,.,,""\\
TS (SRO) RCIC isolation valves fail to auto close. (Critical Task)
J 3
TS (SRO) APRM '2A' Failure O(C
~
C (ATC)
RFPT '2A' Lube Oil Cooling Failure 5J 0 0 ~ 5cov'ce>tA.,) ~ (l)fut \\
I'~:
5 i <ld; 4
Loss of '2C' SSAC Co,..t0b" dL.ce.
, 17(:/'f~'5""
-*h i
.:f C (BOP) q)~(/Jt I
/
'2B' SSAC does not start. BOP manually starts '2A' SSAC.-\\
6 C (ATC)
RFPT '2A' receives High vibrati0n,Jrci'fFstgfi1it-l?ut-does-not-trip.-_-.-. 1/
- ?ve(e&"" vi
~z}afif'!v,,,c.d:"*~' )
i
~',,.,,
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7 Insert Control Rods to exit RPI-"
[('!' "';".. (y., U?_~_.~ __
R (ATC) 8 M(ALL)
'2A' & '2C' EDG Fails to Start and cannot be started.
'lB' EDG supplies power to '2F' 4160 V bus.
9 C (BOP)
HPCI fails to auto start on low RPV level or high DW pressure (Critical Task)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 3 Appendix D Scenario Outline Form ES-D-l NRC Draft Facility:
E. I Hatch Scenario No.:
5-2 Op-Test No.:
2009-302 Examiners:
Operators:
./
Initial Conditions. APRM 'B' is bypassed due to failed CPU. Reactor power is approximately 70%
power holding for control rod sequence exchange due next shift. RCIC system will be unisolated and place in standby.
Turnover:
Event Malf. No.
Event Event No.
Type*
Description 1
N (BOP)
Unisolate RCIC and place in standby
~
- 007 >
. "-i.
f'/
RCIC Steam Line breaks in the Rx bldg.
(
2 f< \\,.../
C (BOP)
'0/
.-I TS (SRO) RCIC isolation valves fail to auto close. (Critical Task)
I 3
TS (SRO) APRM '2A' Failure 0(,/
,L
~
C (ATC)
RFPT '2A' Lube Oil Cooling Failure S) DD~ ;,cOvYe'-J'c' J, Yt!ftct \\ ~
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5 Z otCJ <;/'? "
- ,4 Loss of '2C' SSAC COV£.,1.,.:#." !'"(l-t-e.
j<";. -
~?,~~:",,\\ \\)Cc \\._ :,I-C **_*f--;:;.
l ~"-;
~.,.:/-
o
/, l
'-'~.
C (BOP)
(/~V1~ (
'2B' SSAC does not start. BOP manually starts '2A' SSAC. '\\ ;1 ItA 6
C (ATC)
RFPT '2A' receives High vibrationJr4'fFstgnatbut-does'-not-trip. "-;'~_ /
/
ATCmanuallytripsRFPT '2A'.,'P,UtiJ..e v.-)
C;~;/J v,viv';_:~0fj;:'--
!-: '.1' C' *. IY:-'.',:_.L._.--"
7 R (ATC)
Insert Control Rods to exit RPI 8
M(ALL)
'2A' & '2C' EDG Fails to Start and cannot be started.
'lB' EDG sUPRliesp_ower to '2F' 4160 V bus.
9 C (BOP)
HPCI fails to auto start on low RPV level or high DW pressure (Critical Task)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Page 2 of3 Facility:
E. I Hatch Initiating Conditions:
Turnover Summary:
Scenario Summary Scenario No.:
5-02 OD-Test No.:
2009-302 NRC Draft Unit 2 is at 70% power holding for control rod sequence exchange on next shift.
APRM 'B' is bypassed due to failed CPU. Reactor power is approximately 70%
power holding for control rod sequence exchange due next shift. RCIC system will be unisolated and place in standby.
Event 1: Unisolate RCIC system and place in standby.
Event 2: ComponentlTS; A RCIC steam line will break outside of Primary Containment. The inboard isolation valve is failed open and cannot be closed. Both isolation valves fail to automatically close on an automatic isolation signal and must be manually closed (Critical Task). The SS addresses Tech Specs for inoperable Primary Containment Isolation Valve Event 3: TS; APRM '2A' will experience a CPU failure and trip. The SS addresses Tech Specs for inoperable RPS instrumentation.
Event 4: Component; The RFPT '2A' lube oil cooling water temperature control valve will fail in the closed direction causing temperatures to rise on the '2A' RFPT. The operator takes manual control of the temperature control valve and re-establishes cooling water flow.
Event 5: Component; The "2C" Station Service Air Compressor (SSAC) will trip. The "2B" SSAC will not auto start, and the BOP operator will start the "2A" SSAC restoring air system.
Event 6: Component; The '2A' RFPT receives a high vibration trip signal but does not automatically trip. The ATC manually trips the '2A' RFPT Event 7: The ATC inserts control rods to exit the Region of Potential Instabilities.
Event 8: Major; The plant will experience a Loss of Offsite power with the failure of the '2A' and '2C' Emergency Diesel Generators to start. 4160 V '2F' Emergency bus will be energized by the operator taking manual control of the 'IB' Emergency Diesel Generator or when the high DW pressure condition is received.
Event 9: As RWL decreases the HPCI system will fail to auto start on low RWL or high DW pressure. The operator will have to manually start the HPCI system to maintain RWL. (Critical Task)
/" \\
(
Facility:
E. I Hatch Initiating Conditions:
Turnover Summary:
Page 2 of 3 Scenario Summary Scenario No.:
5-02 Op-Test No.:
2009-302 NRC Draft Unit 2 is at 70% power holding for control rod sequence exchange on next shift.
APRM 'B' is bypassed due to failed CPU. Reactor power is approximately 70%
power holding for control rod sequence exchange due next shift. RCIC system will be unisolated and place in standby.
Event 1: Unisolate RCIC system and place in standby.
Event 2: ComponentlTS; A RCIC steam line will break outside of Primary Containment. The inboard isolation valve is failed open and cannot be closed. Both isolation valves fail to automatically close on an automatic isolation signal and must be manually closed (Critical Task). The SS addresses Tech Specs for inoperable Primary Containment Isolation Valve Event 3: TS; APRM '2A' will experience a CPU failure and trip. The SS addresses Tech Specs for inoperable RPS instrumentation.
Event 4: Component; The RFPT '2A' lube oil cooling water temperature control valve will fail in the closed direction causing temperatures to rise on the '2A' RFPT. The operator takes manual control of the temperature control valve and re-establishes cooling water flow.
Event 5: Component; The "2C" Station Service Air Compressor (SSAC) will trip. The "2B" SSAC will not auto start, and the BOP operator will start the "2A" SSAC restoring air system.
Event 6: Component; The '2A' RFPT receives a high vibration trip signal but does not automatically trip. The ATC manually trips the '2A' RFPT Event 7: The ATC inserts control rods to exit the Region of Potential Instabilities.
Event 8: Major; The plant will experience a Loss of Offsite power with the failure of the '2A' and '2C' Emergency Diesel Generators to start. 4160 V '2F' Emergency bus will be energized by the operator taking manual control of the '1 B' Emergency Diesel Generator or when the high DW pressure condition is received.
Event 9: As RWL decreases the HPCI system will fail to auto start on low RWL or high DW pressure. The operator will have to manually start the HPCI system to maintain RWL. (Critical Task)
Page 3 of 3 Critical Tasks NRC Draft Facility:
E. I Hatch Scenario No.:
5-02 Op-Test No.:
2009-302 Critical Tasks Manually isolate the RCIC isolation valves prior to exceeding the Maximum Safe Operating Temperature on the EOP Secondary Containment Flowchart. (Event 2)
Restores RWL injection with HPCI before RWL reaches -185 inches (Event 9)
(
(
Page 3 of 3 Critical Tasks NRC Draft Facility:
E. I Hatch Scenario No.:
5-02 Op-Test No.:
2009-302 Critical Tasks Manually isolate the RCIC isolation valves prior to exceeding the Maximum Safe Operating Temperature on the EOP Secondary Containment Flowchart. (Event 2)
Restores RWL injection with HPCI before RWL reaches -185 inches (Event 9)
AppendixD Scenario Outline Form ES*D*1 NRC Drajt Facility:
E. I Hatch Scenario No.: 5*03 Op* Test No.:
2009*302 Examiners:
Operators:
SRO RO BOP Initial Conditions. Unit 2 is operating at 75% power reducing to 70% making preparations for Main Turbine Control Valve Instrument Functional Testing.
Turnover: Perform 34SV-C71-005-2," Turbine Control Valve Fast Closure Instrument Functional Test", for CV -1.
Event Malf.No.
Event Event No.
Type*
Description 1
N/A R (ATC)
Reduce reactor power to 70% for Turbine Testing
~
~/A N (BOP)
Perform 34SV-C71-005-2," Turbine Control Valve Fast Closure Instrument Functional Test", for CV -1 ONLY starting at step 7.2.6.
3 mfE51_65 I (ATC)
RCIC Torus Level Sensor Fails High; with failure of CST valve in loE51_FO 10G 1 TS (SRO) mid position (Valve overload). Time compression repair and re-loE51_F01OR2 alignment back to CST.
mf60231261
~
mfCll_31A C (ATC)
CRD FCV '2A' Slow Failure mf60311327 TS (SRO) aoC11-R600-1 aoC11-R600-2 aoCll-R601 aoCll-R602 aoCll-R603 aoCll-R605
~
mfE41_103 C (BOP)
Inadvertent start of HPCI. (Critical Task) 6 mfP64_193A C (BOP)
Loss of DW Chillers mfP64 193B f7 mfB21_123A M(ALL)
Steam Line Break inside Drywell 8
diE11-F016A C (ATC)
RHR 2E11-F016A/B Containment Spray Valve fails to OPEN and
~iE11-F016B RHR Loop A pumps trip iET-XXXfor (mfE11_115A mfE11 115C) 9 M(ALL)
Emergency Depress prior to Bulk Average DW temperature of 340°F (Critical Task)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor AppendixD Scenario Outline Form ES-D-l NRC Draft Facility:
E.IHatch Scenario No.:
5-03 Op-Test No.:
2009-302 Examiners:
Operators:
SRO RO BOP Initial Conditions. Unit 2 is operating at 75% power reducing to 70% making preparations for Main Turbine Control Valve Instrument Functional Testing.
Turnover: Perform 34SV-C71-005-2," Turbine Control Valve Fast Closure Instrument Functional Test", for CV-l.
Event Malf. No.
~vent Event No.
Type*
Description 1
N/A R (ATC)
Reduce reactor power to 70% for Turbine Testing 2
N/A N (BOP)
Perform 34SV-C7l-005-2," Turbine Control Valve Fast Closure Instrument Functional Test", for CV -1 ONLY starting at step 7.2.6.
(
,3 mfE5L65 I (ATC)
RCIC Torus Level Sensor Fails High; with failure of CST valve in 10E5 LFO lOG 1 TS (SRO) mid position (Valve overload). Time compression repair and re-10E5LFOlOR2 alignment back to CST.
mf6023l26l
~
mfClL3lA C (ATC)
CRD FCV '2A' Slow Failure mf603l1327 TS (SRO) aoCll-R600-l aoCll-R600-2 aoClI-R60l aoCll-R602 aoCll-R603 aoClI-R605 5
mfE4L103 C (BOP)
Inadvertent start of HPCI. (Critical Task) 6 mtP64_l93A C (BOP)
Loss of DW Chillers mtP64 193B 17 mfB2L123A M (ALL)
Steam Line Break inside Drywell 8
diEll-F0l6A C (ATC)
RHR 2Ell-F016AIB Containment Spray Valve fails to OPEN and diElI-F016B
~T-XXXfor RHR Loop A pumps trip (mfElLl15A mfElI 1I5C) 9 M (ALL)
Emergency Depress prior to Bulk Average DW temperature of 340°F (Critical Task)
(
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix 0 Reguired Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
1 Page 2 of 30 Event
Description:
Trip of "2C" Station Service Air Compressor I Time I Position I Applicant's Actions or Behavior SRO
- Directs RO to decrease reactor power to 70% by decreasing Recirc flow. Power decreases should be made as recommended by the ST AlReactor Engineering at a rate not to exceed 10 MWe/min.
- Decreases reactor power with Recirc flow IA W 34GO-OPS-005-2 and 34S0-B31-001-2 by depressing either the Master Recirc Flow Control lower pushbuttons or the individual pump Speed Control lower pushbuttons.
- Monitors power decrease by observing APRM and generator output indications.
May get the RBM Upscale and Rod Out Block alarm, if a peripheral control rod is not selected. This is expected and the operator may select a peripheral rod at this time.
May also get some F eedwater heater level alarms. This is expected at this power level.
Simulator Operator enters the next event after power has been decreased by 5% or at the Chief Examiner's request.
Appendix 0 Reguired Operator Actions Form ES-O-2 II Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
1 Page 2 of 30 Event
Description:
Trip of "2C" Station Service Air Compressor Time I Position I Applicant's Actions or Behavior I
- Directs RO to decrease reactor power to 70% by decreasing Recirc flow. Power decreases should be made as recommended by the ST AlReactor Engineering at a rate not to exceed 10 MWe/min.
- Decreases reactor power with Recirc flow lAW 34GO-OPS-005-2 and 34S0-B31-001-2 by depressing either the Master Recirc Flow Control lower pushbuttons or the individual pump Speed Control lower pushbuttons.
- Monitors power decrease by observing APRM and generator output indications.
(
May get the RBM Upscale and Rod Out Block alarm, if a peripheral control rod is not selected. This is expected and the operator may select a peripheral rod at this time.
May also get some Feedwater heater level alarms. This is expected at this power level.
Simulator Operator enters the next event after power has been decreased by 5% or at the Chief Examiner's request.
(
Appendix D Reguired Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
2 Page 3 of30 Event
Description:
Perform 34SV-C71-005-2," Turbine Control Valve Fast Closure Instrument Functional Test", for CV-1 starting at step 7.2.6.
Time I Position I Applicant's Actions or Behavior BOP
- From the MSV -CV test screen
- Select CV#1
- Select Test START
- Confirm CV#1 slowly closes to 5% then fast closes from 5% to 0%
- Confirm CV#4 opens, if CV#2 and CV#3 approach full open
- Confirm annunciators alarm:
603-102, TURB CNTL VLV FAST CLOSURE TRIP,
- WHEN plant conditions have stabilized
- Select Test OFF
- CONFIRM CV # 1 slowly opens from 0% to pretest position
- CONFIRM all reactor parameters return to normal
- RESET Half Scram using 2C71-S5, Reactor Scram Reset switch, 2H11-P603
- CONFIRM Control Valve CV # 1 OPENS
- CONFIRM CV # 4 CLOSES
- CONFIRM the following annunciators CLEAR:
- 603-117, REACTOR AUTO SCRAM SYSTEM A TRIP
- 603-102, TURB CNTL VLV FAST CLOSURE TRIP, ATC Enters 34AR-603-117-2, and confirms no control rod movement by running a Control Rod position check. Notifies SS of results I
(
(
Appendix D Reguired Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
2 Page 3 of 30 Event
Description:
Perform 34SV-C71-005-2," Turbine Control Valve Fast Closure Instrument Functional Test", for CV-l starting at step 7.2.6.
Time 1 Position I Applicant's Actions or Behavior BOP
- From the MSV -CV test screen
- Select CV#1
- Select Test START
- Confirm CV#1 slowly closes to 5% then fast closes from 5% to 0%
- Confirm CV#4 opens, if CV#2 and CV#3 approach full open
- Confirm annunciators alarm:
603-102, TURB CNTL VLV FAST CLOSURE TRIP, 603-117, REACTOR AUTO SCRAM SYSTEM A TRIP BOP
- WHEN plant conditions have stabilized
- Select Test OFF
- CONFIRM CV # 1 slowly opens from 0% to pretest position
- CONFIRM all reactor parameters return to normal
- RESET Half Scram using 2C71-S5, Reactor Scram Reset switch, 2Hll-P603
- CONFIRM Control Valve CV # 1 OPENS
- CONFIRM CV # 4 CLOSES
- CONFIRM the following annunciators CLEAR:
603-117, REACTOR AUTO SCRAM SYSTEM A TRIP 603-102, TURB CNTL VLV FAST CLOSURE TRIP, ATC
- Enters 34AR-603-117-2, and confirms no control rod movement by running a Control Rod position check. Notifies SS of results
Appendix D Required Operator Actions Form ES-D-2
'\\ Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
2 Page 4 of30 Event
Description:
Perform 34SV-C71-005-2," Turbine Control Valve Fast Closure Instrument Functional Test", for CV-l starting at step 7.2.6.
I Time Position Applicant's Actions or Behavior BOP
- Contacts SSS to confirm:
- Notifies the SS that CV#l Test in complete.
Simulator Operator enters the next event after surveillance is complete OR at the Chief Examiner's request.
Appendix D Required Operator Actions Form ES-D-2 II Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
2 Page 4 of 30 Event
Description:
Perform 34SV -C71-005-2," Turbine Control Valve Fast Closure Instrument Functional Test", for CV -1 starting at step 7.2.6.
Time Position Applicant's Actions or Behavior BOP Contacts SSS to confirm:
A1l2C71A-K8A, 2C71A-K8B, 2C71A-K8C, 2C71A-K8D, relays, are energized.
- Notifies the SS that CV#1 Test in complete.
(
Simulator Operator enters the next event after surveillance is complete OR at the Chief Examiner's request.
(
Appendix D Reguired Operator Actions Form ES-D-2
'\\
Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
3 Page 5 of30 Event
Description:
RCIC Torus Level Sensor Fails High; with failure of CST valve in mid position.
Time Position Applicant's Actions or Behavior At the Chief Examiner's direction, Simulator operator enters: RB-3 mfE51_65 loE51_FOIOGl loE51_FOIOR2 mj60231261 All
- "TORUS LEVEL HIGH RCIC", (602-230) and "RCIC VALVES MOTOR OVERLOAD" (602-309) alarms are received on P601 SS
- Directs an operator to enter 34AR-602-230-2 and 34AR-602-309-2 ATC
- Enters 34AR-602-230-2
- Determines that RCIC Suction has aligned to the torus
- Verifies that 2E51-FOlO is closed. (Cannot perform this step because 2E51-FOIO has no light indication)
- Determines that Torus level is not high and is stable.
- Determines that RCIC should not have auto swapped to the torus.
ATC Enters 34AR-602-309-2
- Determines that 2E51-FOIO has no lights illuminated.
Appendix 0 Reguired Operator Actions Form ES-O-2
~ ~
Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
3 Page 5 of30 Event
Description:
RCIC Torus Level Sensor Fails High; with failure of CST valve in mid position.
I Time Position Applicant's Actions or Behavior At the Chief Examiner's direction, Simulator operator enters: RB-3 mfE51_65 loE51_F01OGl loE51_F01OR2 mj60231261 All
- "TORUS LEVEL HIGH RCIC", (602-230) and "RCIC VALVES MOTOR OVERLOAD" (602-309) alarms are received on P601 SS
- Directs an operator to enter 34AR-602-230-2 and 34AR-602-309-2
(
ATC Enters 34AR-602-230-2
- Determines that RCIC Suction has aligned to the torus
- Verifies that 2E51-FOlO is closed. (Cannot perform this step because 2E51-FOlO has no light indication)
- Determines that Torus level is not high and is stable.
- Determines that RCIC should not have auto swapped to the torus.
ATC Enters 34AR-602-309-2
- Determines that 2E51-FOlO has no lights illuminated.
(
Appendix D Required Operator Actions Form ES-D-2
~r Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
3 Page 6 of 30
~.
Event
Description:
RCIC Torus Level Sensor Fails High; with failure of CST valve in mid position.
II Time Position Applicant's Actions or Behavior SS
- Dispatches operatorlMaint to reset the thermal overload for 2E51-FOI0 (MCC 2R24-S021 Brkr # 2B) (ATC may do this also)
- Directs operator to monitor suction pressure on HPCI.
Simulator Operator, 5 minutes after Maint is sent to investigate, notify the control room that 2E51-LS-N062B hasfailed upscale.
- Reports to the SS that 2E51-LS-N662B has failed upscale SS
- Enters Tech Specs 3.3.5.2, Condition D.2.1 & D.2.2, to place the channel in trip or align RCIC suction to the Suppression pool within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Simulator Operator, after 3 minutes from being dispatched to the breaker, DELETE overrides loE51-F010G1, loE51-F010R2 and mf60231261 AND As operator, notifies the control room that the breaker for 2E51-FO 10 has been reset.
- Confirms 2E51-FOlO has traveled full closed.
Appendix D Reguired Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
3 Page 6 of30 Event
Description:
RCIC Torus Level Sensor Fails High; with failure of CST valve in mid position.
I Time Position Applicant's Actions or Behavior SS
- Dispatches operatorlMaint to reset the thermal overload for 2E51-FOIO (MCC 2R24-S021 Brkr # 2B) (ATC may do this also)
- Directs operator to monitor suction pressure on HPCI.
Simulator Operator, S minutes after Maint is sent to investigate, notify the control room that 2ES1-LS-N062B has failed upscale.
- Reports to the SS that 2E51-LS-N662B has failed upscale SS
- Enters Tech Specs 3.3.5.2, Condition D.2.1 & D.2.2, to place the channel in trip or align RCIC suction to the Suppression pool within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Simulator Operator, after 3 minutes from being dispatched to the breaker, DELETE overrides loES1-F010G1, loES1-F010R2 and mf60231261 AND As operator, notifies the control room that the breaker for 2ES1-F010 has been reset.
- Confirms 2E51-FOIO has traveled full closed.
Appendix 0 Required Operator Actions Form ES-O-2 If Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
3 Page 7 of 30 Event
Description:
RCIC Torus Level Sensor Fails High; with failure of CST valve in mid position.
Time Position Applicant's Actions or Behavior I
At the Chief Examiner's direction, Simulator Operator, DELETE mfE51_65, then as I & C, report that it is now one hour later (time compression) and that 2E51-N062B repair and calibration is complete.
- Enters 34S0-ESI-001-2 step 7.3.7 to align RCIC to the CST.
- Starts' closing 2ESI-F029 and 2ESI-F031, then starts opening 2ESI-FOlO prior to 2ESI-F029 and 2 ESI-F031 going full closed.
- Determines that the LCO for 2ESI-N062B is met.
Simulator Operator Proceed to the next Event at the Chief Examiner's direction.
Appendix 0 Required Operator Actions Form ES-O-2
(.
~
Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
3 Page 7 of 30 Event
Description:
RCIC Torus Level Sensor Fails High; with failure of CST valve in mid position.
Time Position Applicant's Actions or Behavior I
At the Chief Examiner's direction, Simulator Operator, DELETE mfE51_65, then as 1& C, report that it is now one hour later (time compression) and that 2E51-N062B repair and calibration is complete.
- Enters 34S0-E51-001-2 step 7.3.7 to align RCIC to the CST.
(
- Starts' closing 2E51-F029 and 2E51-F031, then starts opening 2E51-FOlO prior to 2E51-F029 and 2E51-F031 going full closed.
- Determines that the LCO for 2E51-N062B is met.
Simulator Operator Proceed to the next Event at the Chief Examiner's direction.
Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
4 Page 8 of 30 Event
Description:
CRD FCV '2A' Slow Failure; Places standby FCV in service Time I Position I Applicant's Actions or Behavior At the Chief Examiner's direction, Simulator operator enters: RB-2 aoCll-R601 aoC11-R605 aoC11-R600-1 aoC11-R600-2 aoC11-R602 Simulator operator when aoC11-R601 indicates 1482 psig enters RB-3 and 30 seconds later enter RB-4.
- Receives Charging Water Pressure High alarm
- Will also receive CRD Hydraulic Temp High alarm a short time later
- Determines that the CRD Flow Control Valve A has failed closed.
- Enters
- 603-139, Charging Water pressure High
- 603-140, CRD Hydraulic Temp High
- 34AB-Cll-001-2, Loss ofCRD System Note: With the loss of the CRD FCY, the ATC may address 34AB-C11-001-2, Loss ofCRD",jirst.
- Directs the operator to perform actions per the ARPs and 34AB-Cll-001-2, Loss ofCRD system.
- May direct operator to swap Flow Control Valves at this time, or may wait for report from SO, before ordering the swap.
Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
4 Page 8 of 30 Event
Description:
CRD FCV '2A' Slow Failure; Places standby FCV in service Time I Position I Applicant's Actions or Behavior At the Chief Examiner's direction, Simulator operator enters: RB-2 aoC11-R60l aoC11-R605 aoC11-R600-1 aoC11-R600-2 aoC11-R602 Simulator operator when aoC11-R601 indicates 1482 psig enters RB-3 and 30 seconds later enter RB-4.
- Recei ves Charging Water Pressure High alann
- Will also receive CRD Hydraulic Temp High alann a short time later
- Determines that the CRD Flow Control Valve A has failed closed.
- Enters
- 603-139, Charging Water pressure High
- 603-140, CRD Hydraulic Temp High
- 34AB-Cll-001-2, Loss of CRD System Note: With the loss of the CRD FCV, the ATC may address 34AB-Cll-00l-2, Loss ofCRD",jirst.
- Directs the operator to perform actions per the ARPs and 34AB-C11-001-2, Loss of CRD system.
- May direct operator to swap Flow Control Valves at this time, or may wait for report from SO, before ordering the swap.
(
Appendix 0 Required Operator Actions Form ES-O-2
'\\
Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
4 Page 9 of30 Event
Description:
CRD FCV '2A' Slow Failure; Places standby FCV in service I Time Position Applicant's Actions or Behavior ATC
- 603-139, Charging Water pressure High step 5.6 directs operator to shift to standby flow control valve per 34S0-C11-005-2.
- 603-140, CRD Hydraulic Temp High
Simulator Operator reports, as SO at the FCV, that the FCV has failed closed due to an air leak on the supply line, and that you have isolated the air line and stopped the leak.
IflWhen requested and if the CRD High Temp alarm is illuminated, Simulator Operator, as operator checking CRD Temps, reports that 2 CRD drives are
>250°F. 30-11 at 260°F, 22-35 at 265°F and some others are slowly increasing.
SS Directs operator to swap Flow Control Valves ATC Enters:
- 34S0-C11-005-2, CRD System, to swap Flow Control valves
- Places 2C11-R600 to Manual
aoCII-R600-1 aoCII-R600-2 aoCII-R602 aoCII-R603 aoCII-R605 Simulator Operator, if the operator does not place 2CII-R600 to manual with the output at "0", tell him as the SO that the system flow is matched at "0" gpm and tell him that you are ready for him to take control of the system from the Control Room.
Appendix 0 Required Operator Actions Form ES-O-2 I ~
Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
4 Page 9 of 30 Event
Description:
CRD FCV '2A' Slow Failure; Places standby FCV in service Time Position Applicant's Actions or Behavior ATC
- 603-139, Charging Water pressure High step 5.6 directs operator to shift to standby flow control valve per 34S0-Cll-005-2.
- 603-140, CRD Hydraulic Temp High
Simulator Operator reports, as SO at the FCV, that the FCV has failed closed due to an air leak on the supply line, and that you have isolated the air line and stopped the leak.
lflWhen requested and if the CRD High Temp alarm is illuminated, Simulator Operator, as operator checking CRD Temps, reports that 2 CRD drives are
>250°F. 30-11 at 260°F, 22-35 at 265°F and some others are slowly increasing.
SS Directs operator to swap Flow Control Valves ATC Enters:
- 34S0-CII-005-2, CRD System, to swap Flow Control valves
- Places 2CII-R600 to Manual
aoCJJ-R600-J aoCJJ-R600-2 aoCJJ-R602 aoCJJ-R603 aoCJJ-R605
(
Simulator Operator, if the operator does not place 2C11-R600 to manual with the output at "0", tell him as the SO that the system flow is matched at "0" gpm and tell him that you are ready for him to take control of the system from the Control Room.
Appendix 0 Required Operator Actions Form ES-O-2
!~
Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
4 Page 10 of 30 Event
Description:
CRD FCV '2A' Slow Failure; Places standby FCV in service I Time Position Applicant's Actions or Behavior Simulator Operator ENTER rfCll_24 to "B", then as the SO, report that the CRD FCV's have been shifted locally and that control room actions to complete the shift can be taken.
- Returns CRD System to normal configuration by:
- Adjusting 2CII-R600 to desired flow
- Places 2CII-R600 to AUTO
- Confirms system parameters are normal Simulator Operator, as the operator increases 2CJJ-R600 output, DELETE aoCll-R60J and mj60311327.
- "Charging Water Pressure High" alarm clears
- "CRD Hydraulic Temp High" alarm clears
- Reports to SS that CRD flow control valves have been shifted and the CRD System has been restored to normal configuration.
Simulator Operator Proceed to the next IIC failure at the Chief Examiner's direction.
Appendix 0 Required Operator Actions Form ES-O-2 I,
(
Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
4 Page 10 of30 Event
Description:
CRD FCV '2A' Slow Failure; Places standby FCV in service II Time Position Applicant's Actions or Behavior Simulator Operator ENTER rfCll_24 to "B", then as the SO, report that the CRD FCV's have been shifted locally and that control room actions to complete the shift can be taken.
- Returns CRD System to normal configuration by:
- Adjusting 2CII-R600 to desired flow
- Places 2CII-R600 to AUTO
- Confirms system parameters are normal Simulator Operator, as the operator increases 2Cll-R600 output, DELETE aoCll-R601 and mf60311327.
(
- "Charging Water Pressure High" alarm clears
- "CRD Hydraulic Temp High" alarm clears
- Reports to SS that CRD flow control valves have been shifted and the CRD System has been restored to normal configuration.
Simulator Operator Proceed to the next llC failure at the Chief Examiner's direction.
(
Appendix 0 Reguired Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
5 Page 11 of 30 Event
Description:
HPCI system inadvertent start I Time I Position I Applicant's Actions or Behavior Simulator Operator, at Chief Examiner's direction, call the ATC operator and as the Lab request the control room get a routine reading on the Inlet Flow to Stack on recorder 2N62-R604 located on 2N62-P600 panel.
(This is to get the ATC operator to go away from the HPCI panel, allowing the BOP the opportunity to respond to HPCI.)
Simulator Operator, at Chief Examiner's direction, ENTER RB-5, mfE41 103, HPCI Inadvertent Initiation.
ALL
- Recognize and report HPCI has started from an invalid initiation signal.
- Verifies reactor water level is stable.
(May receive APRM Hi Alarm and Reactor Water Level Hi alarm.)
- Verifies Drywell Pressure is normal.
- Enters 34AB-ElO-001-2 SS
- Direct the operator to secure HPCI from placard IA W 34S0-E41-001-2, High Pressure Coolant Injection (HPCI) System.
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
5 Page 11 of 30 Event
Description:
HPCI system inadvertent start II Time I Position I Applicant's Actions or Behavior I
Simulator Operator, at Chief Examiner's direction, call the ATC operator and as the Lab request the control room get a routine reading on the Inlet Flow to Stack on recorder 2N62-R604located on 2N62-P600 panel.
(This is to get the ATC operator to go away from the HPCI panel, allowing the BOP the opportunity to respond to HPCI.)
Simulator Operator, at Chief Examiner's direction, ENTER RB-S, mfE41 103, HPCI Inadvertent Initiation.
ALL
- Recognize and report HPCI has started from an invalid initiation signal.
(
- Verifies reactor water level is stable.
(May receive APRM Hi Alarm and Reactor Water Level Hi alarm.)
- Verifies Drywell Pressure is normal.
- Enters 34AB-ElO-001-2 SS
- Direct the operator to secure HPCI from placard IA W 34S0-E41-001-2, High Pressure Coolant Injection (HPCI) System.
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
5 Page 12 of 30 Event
Description:
HPCI system inadvertent start Time Position Applicant's Actions or Behavior BOP
- Secure HPCI as follows: (Critical Task)
- Depresses and holds the HPCI Turbine Trip push-button.
- When the "HPCI Turbine Brg Oil Press Low" alarm is received, releases the HPCI Turbine Trip push-button.
- Enters ARP and places Reactor Level Mode Select Switch to MAN and Feedwater Control Mode select switch to l-ELEM.
- After HPCI is shutdown, returns the Reactor Level Mode Select Switch to AUTO and Feedwater Control Mode select switch to 3-ELEM lAW 34S0-N21-007-2.
Appendix 0 Reguired Operator Actions Form ES-O-2
'\\
(
Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
5 Page 12 of 30 Event
Description:
HPCI system inadvertent start Time Position Applicant's Actions or Behavior BOP
- Secure HPCI as follows: (Critical Task)
- Depresses and holds the HPCI Turbine Trip push-button.
- When the "HPCI Turbine Brg Oil Press Low" alarm is received, releases the HPCI Turbine Trip push-button.
(
- Enters ARP and places Reactor Level Mode Select Switch to MAN and Feedwater Control Mode select switch to l-ELEM.
- After HPCI is shutdown, returns the Reactor Level Mode Select Switch to AUTO and Feedwater Control Mode select switch to 3-ELEM lAW 34S0-N21-007-2.
(
Appendix 0 Required Operator Actions Form ES-O-2
~I Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
5 Page 13 of 30 Event
Description:
HPCI system inadvertent start Time Position Applicant's Actions or Behavior Simulator Operator - After the SS declares HPCI inop per tech spec 3.5.1. C, as I & C tech called to resolve the HPCI problem, inform the SS that the HPCI initiation logic appears to be causing the inadvertent start signal and that you will be investigating the problem further.
- Declares HPCI inoperable and determines that Tech Spec 3.5.1 Condition C.1 and C.2 must be met consisting of:
(
Proceed to the next event at the Chief Examiner's direction Appendix 0 Required Operator Actions Form ES-O-2 I ~
Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
5 Page 13 of 30 Event
Description:
HPCI system inadvertent start Time Position Applicant's Actions or Behavior Simulator Operator - After the SS declares HPCI inop per tech spec 3.S.1.C, as I & C tech called to resolve the HPCI problem, inform the SS that the HPCI initiation logic appears to be causing the inadvertent start signal and that you will be investigating the problem further.
- Declares HPCI inoperable and determines that Tech Spec 3.5.1 Condition C.1 and C.2 must be met consisting of:
(
Proceed to the next event at the Chief Examiner's direction
Appendix D Required Operator Actions Form ES-D-2 1\\
Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
6 Page 14 of30 Event
Description:
Loss of Drywell Chillers II Time Position Applicant's Actions or Behavior I
At the Chief Examiner's direction, Simulator Operator enters RB-6, (mjP64_193A&nifP64_193B)
ALL
- The following alarms will be received:
- 650-201, DRYWELLrrORUS RCDR R627 TEMP HIGH
- 700-105, DRWL CHILLED WTR B006A SAFETY SID
- 657-025, MULTIPOINT TEMP RCDR 2T47-R626 TEMP HIGH
- 654-004, MULTIPOINT TEMP RCDR 2T47-R620 TEMP HIGH
- 650-214, PANEL 2HI1-P654 SYSTEM TROUBLE
- 650-224, PANEL 2HI1-P657 SYSTEM TROUBLE
- 603-115, PRIMARY CNMT PRESSURE HIGH Note: With the loss of both DW chillers, the BOP/SS may address 34AB-T47-001-2, Loss of DW Coolers", first.
- When venting is required; Directs Operator to vent the drywell.
Appendix 0 Required Operator Actions Form ES-O-2 I,
Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
6 Page 14 of 30 Event
Description:
Loss of Drywell Chillers Time Position Applicant's Actions or Behavior I
At the Chief Examiner's direction, Simulator Operator enters RB-6, (mjP64_193A&mjP64_193B)
ALL
- The following alarms will be received:
- 650-201, DRYWELLrrORUS RCDR R627 TEMP HIGH
- 700-105, DRWL CHILLED WTR B006A SAFETY SID
- 657-025, MULTIPOINT TEMP RCDR 2T47-R626 TEMP HIGH
- 654-004, MULTIPOINT TEMP RCDR 2T47-R620 TEMP HIGH
- 650-214, PANEL 2HII-P654 SYSTEM TROUBLE
- 650-224, PANEL 2HII-P657 SYSTEM TROUBLE
- 603-115, PRIMARY CNMT PRESSURE HIGH
(
Note: With the loss of both DW chillers, the BOP/SS may address 34AB-T47-001-2, Loss of DW Coolers ", first.
- When venting is required; Directs Operator to vent the drywell.
Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
6 Page 15 of 30 Event
Description:
Loss of Drywell Chillers Time Position Applicant's Actions or Behavior BOP
- Enters 34S0-T46-00l-2, "Standby Gas Treatment System" procedure or uses placard at the 2HII-P657/P654 panel to start SBGT 2A or 2B.
BOP 0
Opens 2T46-FOOI (A or B) or 2T46-F003 (A or B) for the (Placard) subsequent train.
0 Places SBGT Fan (2A or 2B) control switch to "RUN."
0 Receives alarm 2B (or 2A) SBGT Switch Not In Auto (654-076)
(or 657-091) 0 Confirms 2T46-F002 (A or B) OPENS 0
Confirms SBGT Heater red light illuminates.
- Enters 34S0-T48-002-2, "Containment Atmosphere Dilution System" or uses placard to vent the Drywell.
BOP 0
Opens 2T48-F334A or 2T48-F334B (both valves may be opened)
(Placard) 0 Receives alarm DW Vent Exh Bypass Vlv Open (654-002) or (657-008) 0 Receives alarm DRWUTorus N2 MIU 2 Inch Isol Valves Open (654-035) or (657-042) 0 Opens 2T48-F335A or 2T48-F335B(both valves may be opened) 0 Opens 2T48-F336A or 2T48-F336B. (both valves may be opened) 0 Monitors DW pressure Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
6 Page 15 of 30 Event
Description:
Loss of Drywell Chillers Time Position Applicant's Actions or Behavior I
- Enters 34S0-T46-00l-2, "Standby Gas Treatment System" procedure or uses placard at the 2HII-P657/P654 panel to start SBGT 2A or 2B.
BOP 0
Opens 2T46-FOOl (A or B) or 2T46-F003 (A or B) for the (Placard) subsequent train.
0 Places SBGT Fan (2A or 2B) control switch to "RUN."
0 Receives alarm 2B (or 2A) SBGT Switch Not In Auto (654-076)
(or 657-091) 0 Confirms 2T46-F002 (A or B) OPENS 0
Confirms SBGT Heater red light illuminates.
(
- Enters 34S0-T48-002-2, "Containment Atmosphere Dilution System" or uses placard to vent the Drywell.
BOP 0
Opens 2T48-F334A or 2T48-F334B (both valves may be opened)
(Placard) 0 Receives alarm DW Vent Exh Bypass Vlv Open (654-002) or (657-008) 0 Receives alarm DRWUTorus N2 MID 2 Inch Isol Valves Open (654-035) or (657-042) 0 Opens 2T48-F335A or 2T48-F335B(both valves may be opened) 0 Opens 2T48-F336A or 2T48-F336B. (both valves may be opened) 0 Monitors DW pressure
(
\\
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
6 Page 16 of 30 Event
Description:
Loss of Drywell Chillers I Time Position Applicant's Actions or Behavior SS
- Direct the operator to fast vent the Drywell lAW 34S0-T48-002-2.
- Confirms that none of the following alarms are illuminated:
- SBGTIDRYWELL AND TORUS RADIATION mGH (601-402)
- FISSION PRODUCT PARTIC RADN mGHllNOP (602-406)
- FISSION PRODUCT IODINE RADN HIGHIINOP (602-412)
- FISSION PRODUCT GAS mGHllNOP (602-418)
- CONTAINMENT RADIATION HIGHIINOP (602-436)
- WHEN Drywell pressure is < 0.5 PSIG on 2T48-R607A OR 2T48-R607B, close 2T48-F320, Drywell Vent Vlv.
- Close 2T48-F319, Drywell Vent Vlv.
Appendix 0 Reguired Operator Actions Form ES-D-2 I ~
Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
6 Page 16 of 30 Event
Description:
Loss of Drywell Chillers Time Position Applicant's Actions or Behavior I
- Direct the operator to fast vent the Drywell IA W 34S0-T48-002-2.
- Confirms that none of the following alarms are illuminated:
SBGT/DRYWELL AND TORUS RADIATION HIGH (601-402)
- FISSION PRODUCT PARTIC RADN HIGHIINOP (602-406)
- FISSION PRODUCT IODINE RADN HIGHIINOP (602-412)
FISSION PRODUCT GAS HIGHIINOP (602-418)
- CONTAINMENT RADIATION HIGHIINOP (602-436)
(
- WHEN Drywell pressure is < 0.5 PSIG on 2T48-R607 A OR 2T48-R607B, close 2T48-F320, Drywell Vent Vlv.
- Close 2T48-F319, Drywell Vent Vlv.
(
Appendix D Required Operator Actions Form ES-D-2
'I Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
6 Page 17 of 30 Event
Description:
Loss of Drywell Chillers II Time Position Applicant's Actions or Behavior I
- Enters 34AB-T47-001-2, Loss ofDW Coolers
- Monitors Drywell pressure and temperature
- Corrects reactor water level indications as necessary for high Drywell temperatures per 34AB-B21-002-2, RPV Water Level Corrections
- Monitors for any peak Drywell temperatures per Attachment 1 on SPDS panel and if exceeded for 30 minutes, enters 34GO-OPS-014-2, Fast Reactor Shutdown
- May request to crosstie Rx Bldg Chilled Water to the Drywell Chilled Water System per the Cross Connecting The 2P64 and 2P65 Systems section of 34S0-P64-00l-2.
- Enters 31EO-EOP-012-2, Primary Containment flow chart.
Simulator Operator enters the next event at the Chief Examiner's request.
Appendix D Required Operator Actions Form ES-D-2
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'l Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
6 Page 17 of 30 Event
Description:
Loss of Drywell Chillers Time Position Applicant's Actions or Behavior ATC
- Enters 34AB-T47-001-2, Loss ofDW Coolers
- Monitors Drywell pressure and temperature
- Corrects reactor water level indications as necessary for high Drywell temperatures per 34AB-B21-002-2, RPV Water Level Corrections
- Monitors for any peak Drywell temperatures per Attachment 1 on SPDS panel and if exceeded for 30 minutes, enters 34GO-OPS-014-2, Fast Reactor Shutdown
- May request to crosstie Rx Bldg Chilled Water to the Drywell Chilled Water System per the Cross Connecting The 2P64 and 2P65 Systems section of 34S0-P64-001-2.
(
- Enters 31EO-EOP-012-2, Primary Containment flow chart.
Simulator Operator enters the next event at the Chief Examiner's request.
(
Appendix 0 Reguired Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
7 Page 18 of 30 Event
Description:
Steam line breaks inside containment Time I Position I Applicant's Actions or Behavior I
At the Chief Examiner's direction, Simulator operator enters: RB-7
- mfB2L123A All
- Determines that DW pressure is increasing and approaching 1.85 psig.
- Orders the Rx manually scrammed (may not have time to insert manual scram before the Rx auto scrams).
- Directs ATC to perform RC-l placard
- Directs BOP to perform RC-2 and RC-3 placards
- Enters RC EOP Flowchart
- As time allows,
- Dispatches personnel to the EDGs to check for proper operation.
- Directs reopening 2P41-F316A-D lAW 34AB-P41-00l-2, Loss of PSW Appendix 0 Reguired Operator Actions Form ES-O-2 If Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
7 Page 18 of 30 Event
Description:
Steam line breaks inside containment Time I Position I Applicant's Actions or Behavior At the Chief Examiner's direction, Simulator operator enters: RB-7
- mfB2L123A All
- Determines that DW pressure is increasing and approaching 1.85 psig.
- Orders the Rx manually scrammed (may not have time to insert manual scram before the Rx auto scrams).
(
- Directs A TC to perform RC-l placard
- Directs BOP to perform RC-2 and RC-3 placards
- Enters RC EOP Flowchart
- As time allows,
- Dispatches personnel to the EDGs to check for proper operation.
- Directs reopening 2P41-F316A-D JAW 34AB-P41-001-2, Loss of PSW
(
Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
7 Page 19 of 30 Event
Description:
Stearn line breaks inside containment Time Position Applicant's Actions or Behavior ATC
- Performs RC-1 consisting of:
- Inserts a manual scram.
- Places the mode switch to shutdown.
- Notifies SS of rod position check.
- Places SDV isolation valve switch to "isolate" & confirms closed.
- If not tripped, places the Recirc pumps at minimum speed.
- Shifts recorders to read IRMS, when required.
- Ranges IRMS to bring reading on scale.
- Notifies the SS when the above actions are complete.
- Performs RC-2 actions consisting of:
- Confirms proper Level Control response:
- Checks ECCS Injection Systems and secure as necessary.
- Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value.
- IF set down does not auto function, then manually reduces FW Master Controller setpoint to approximately 9 inches.
Appendix 0 Required Operator Actions Form ES-O-2 If Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
7 Page 19 of 30 Event
Description:
Stearn line breaks inside containment II Time Position Applicant's Actions or Behavior ATC
- Performs RC-1 consisting of:
- Inserts a manual scram.
- Places the mode switch to shutdown.
- Notifies SS of rod position check.
- Places SDV isolation valve switch to "isolate" & confirms closed.
- If not tripped, places the Recirc pumps at minimum speed.
- Shifts recorders to read IRMS, when required.
- Ranges IRMS to bring reading on scale.
- Notifies the SS when the above actions are complete.
- Performs RC-2 actions consisting of:
- Confirms proper Level Control response:
- Checks ECCS Injection Systems and secure as necessary.
- Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value.
- IF set down does not auto function, then manually reduces FW Master Controller setpoint to approximately 9 inches.
Appendix 0 Required Operator Actions Form ES-O-2 II Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
7 Page 20 of 30 Event
Description:
Steam line breaks inside containment Time Position Applicant's Actions or Behavior BOP
- When feed flow is less than the capacity of the Stu level control valve
(::::: 1.5 mlbmlhr), then:
- Opens 2N21-F125.
- Closes 2N21-FIlO.
- Trips One RFPT.
All
- At paneI2HII-P601, Confirms 2 Core Spray pumps are running and that ONLY the BLoop RHR pumps are running (A Loop RHR pumps failed and will not run)
- Notifies Maintenance to investigate the A Loop of RHR pump failure Appendix D Required Operator Actions Form ES-D-2 II
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Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
7 Page 20 of30 Event
Description:
Steam line breaks inside containment Time Position Applicant's Actions or Behavior I
- When feed flow is less than the capacity of the Stu level control valve
(~ 1.5 mlbmlhr), then:
- Opens 2N21-FI25.
- Closes 2N21-FllO.
- Trips One RFPT.
(
All
- At paneI2HII-P601, Confirms 2 Core Spray pumps are running and that ONLY the BLoop RHR pumps are running (A Loop RHR pumps failed and will not run)
- Notifies Maintenance to investigate the A Loop of RHR pump failure
(
Appendix D Reguired Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
8 Page 21 of30 Event
Description:
RHR 2E11-F016AIB Containment Spray Valve failure with RHR Loop A pump failure Time I Position I Applicant's Actions or Behavior SS
- Per the PC flowchart, verifies torus level is <285 inches and directs an operator to place Torus Sprays in service ATC
- Sprays the Torus per 34S0-E11-010-2 placard on the 2H11-P601 Panel as follows:
- Places Cnmt Spray Vlv Cntl switch in the MANUAL position.
- Starts RHR pump(s) in loop AlB, if not already running.
- Opens 2E 11-F028A1B
- Throttles Open 2E11-F027A1B
- Notifies SS that RHR is in Torus Sprays (One loop of RHR will be placed in Torus Sprays. The flow is only 700gpm, so it may be difficult to see flow indication from a distance.)
- When Torus pressure exceeds 11 psig, verifies that Torus Level is <215 inches, in the safe area of Graph 8 (DWSIL) and Directs an operator to:
- Place all DW cooling fans to off
- Place both Recirc pumps to PTL off
(
(
Appendix 0 Reguired Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
8 Page 21 of 30 Event
Description:
RHR 2EII-FOI6AIB Containment Spray Valve failure with RHR Loop A pump failure Time I Position I Applicant's Actions or Behavior SS
- Per the PC flowchart, verifies torus level is <285 inches and directs an operator to place Torus Sprays in service ATC
- Sprays the Torus per 34S0-EII-010-2 placard on the 2Hll-P601 Panel as follows:
- Places Cnmt Spray Vlv Cntl switch in the MANUAL position.
- Starts RHR pump(s) in loop AlB, if not already running.
- Opens 2Ell-F028A1B
- Throttles Open 2Ell-F027A1B
- Notifies SS that RHR is in Torus Sprays (One loop of RHR will be placed in Torus Sprays. The flow is only 700gpm, so it may be difficult to see flow indication from a distance.)
- When Torus pressure exceeds 11 psig, verifies that Torus Level is <215 inches, in the safe area of Graph 8 (DWSIL) and Directs an operator to:
- Place all D W cooling fans to off
- Place both Recirc pumps to P1L off I
Appendix D Required Operator Actions Form ES-D-2
~,
Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
8 Page 22 of30 Event
Description:
RHR 2E11-F016NB Containment Spray Valve failure with RHR Loop A pump failure Time Position Applicant's Actions or Behavior I
- Places all DW cooling fans control switches in the OFF position.
- Places both Recirc pumps to the PTL Off
- Notifies the SS that the fans are off.
- Notifies the SS that both Recirc pumps are off.
- Sprays the Drywell using 34S0-E11-010-2 placard at the 2HII-P601 panel.
- Places Cnmt Spray NB Vlv Cntl switch in the MANUAL position.
Starts RHR pump(s) in loop AlB, if not already running.
- Opens 2E11-F021A1B
- Opens 2E11-FOI6A1B (NEITHER VALVE WILL OPEN AND BOTH RHR LOOP A PUMPS HA VE TRIPPED)
Note: If the operator starts with the B Loop of RHR to spray the DW, the 2E11-FOl6B valve will not open requiring the operator to transition to the A Loop of RHR. Once the control switch is placed to OPEN on 2Ell-FOl6A both RHR pumps in the A Loop will trip.
- Informs SS that the 2EII-FOI6B will not open and both RHR Loop A pumps have tripped and DW sprays cannot be performed.
- Dispatches SOlMaint to investigate 2EII-FOI6B and both RHR Loop A pumps.
SS May direct the operator to crosstie RHR loops using the 2E 11-FO 1 0 crosstie valve and spray using the A RHR Loop DW spray valves.
(
\\
Simulator operator, if the crew requests the breaker to be turned onfor 2E11-FOlO, after 4 minutes, inform the SS that the breaker for this valve will not close in.
Appendix D Reguired Operator Actions Form ES-D-2 I ~
Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
8 Page 22 of30 Event
Description:
RHR 2EII-F016NB Containment Spray Valve failure with RHR Loop A pump failure II Time Position Applicant's Actions or Behavior ATC
- Places all DW cooling fans control switches in the OFF position.
- Places both Recirc pumps to the PTL Off
- Notifies the SS that the fans are off.
- Notifies the SS that both Recirc pumps are off.
- Sprays the Drywell using 34S0-EII-0l0-2 placard at the 2HII-P601 panel.
Places Cnmt Spray NB Vlv Cntl switch in the MANUAL position.
Starts RHR pump(s) in loop AlB, if not already running.
- Opens 2EII-F021NB
- Opens 2Ell-F016NB (NEITHER VALVE WILL OPEN AND BOTH RHR LOOP A PUMPS HAVE TRIPPED)
(
Note: If the operator starts with the B Loop of RHR to spray the DW, the 2EII-F0I6B valve will not open requiring the operator to transition to the A Loop of RHR. Once the control switch is placed to OPEN on 2E11-F016A both RHR pumps in the A Loop will trip.
- Informs SS that the 2EII-F016B will not open and both RHR Loop A pumps have tripped and DW sprays cannot be performed.
- Dispatches SOlMaint to investigate 2EII-F016B and both RHR Loop A pumps.
SS May direct the operator to crosstie RHR loops using the 2EII-FOlO crosstie valve and spray using the A RHR Loop DW spray valves.
(
Simulator operator, if the crew requests the breaker to be turned on for 2E11-FOIO, after 4 minutes, inform the SS that the breaker for this valve will not close in.
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
9 Page 23 of 30 Event
Description:
Emergency Depress prior to Bulk Average DW temperature of 3400P I Time I Position I Applicant's Actions or Behavior I
- Prior to Bulk Average DW Temp exceeding 340°F.
- Directs Anticipating Emergency Depressurization Note: Based on the timing of the transition to the RC-RPV Control (Non ATWS), there may not be time to Anticipate Emergency Depress prior to performing Emergency Depressurization
- Orders 7 ADS valves open for Emergency Depress.
(Critical Task - Open 7 SRVs prior to Bulk Average DW Temp exceeding 340°F. Critical task is met when 5 SRVs have been opened).
- If the need to Emergency Depressurize is recognized in time, then Anticipates Emergency Depressurization.
- Assign an operator to fully open all Main Turbine Bypass Valves.
Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
9 Page 23 of 30 Event
Description:
Emergency Depress prior to Bulk Average DW temperature of 340°F II Time I Position I Applicant's Actions or Behavior I
- Prior to Bulk Average DW Temp exceeding 340°F.
- Directs Anticipating Emergency Depressurization Note: Based on the timing of the transition to the RC-RPV Control (Non A TWS), there may not be time to Anticipate Emergency Depress prior to performing Emergency Depressurization
- Orders 7 ADS valves open for Emergency Depress.
(Critical Task - Open 7 SRVs prior to Bulk Average DW Temp exceeding 340°F. Critical task is met when 5 SRVs have been opened).
- If the need to Emergency Depressurize is recognized in time, then Anticipates Emergency Depressurization.
- Assign an operator to fully open all Main Turbine Bypass Valves.
(
Appendix 0 Required Operator Actions Form ES-O-2
'I Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
9 Page 24 of 30 Event
Description:
Emergency Depress prior to Bulk Average DW temperature of 340°F Time Position Applicant's Actions or Behavior I
ATCIBOP
- On the DEHC panel 0
Select the Control> Bypass Valve screen.
0 Insert a ramp rate of 100, then press OK.
0 Insert a bypass valve position of 100, then press OK.
0 Checks that the Bypass Valve Jack status is active.
0 Recognizes that all Bypass Valves open.
0 Reports to the SS that all Bypass Valves open ATCIBOP
- Places the switches for 7 ADS valves in the open position.
(Critical Task - Open 7 SRVs prior to Bulk Average DW Temp exceeding 340°F. Critical task is met when 5 SRVs have been opened).
0 If Anticipate Emergency Depressurization was performed, the amber lights for the SRV s will not illuminate if pressure has been reduced to below approximately 300 psig. In this case the operator must use 2HI1-P614 recorder indication to monitor tail pipe temperatures for the SRVs to verify the valves actually opened (Recorder 2B21-R614).
0 Depending on Reactor Water Level prior to opening ADS valves, RWL may swell to above 60 inches, requiring the operator to enter 34AB-C32-001-2, Reactor Water Level Above 60 inches.
~ I Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
9 Page 24 of 30 Event
Description:
Emergency Depress prior to Bulk Average DW temperature of 340°F Time Position Applicant's Actions or Behavior I
ATCIBOP
- On the DEHC panel 0
Select the Control> Bypass Valve screen.
0 illsert a ramp rate of 100, then press OK.
0 illsert a bypass valve position of 100, then press OK.
0 Checks that the Bypass Valve Jack status is active.
0 Recognizes that all Bypass Valves open.
0 Reports to the SS that all Bypass Valves open ATCIBOP
- Places the switches for 7 ADS valves in the open position.
(
(Critical Task - Open 7 SRVs prior to Bulk Average DW Temp exceeding 340°F. Critical task is met when 5 SRVs have been opened).
0 If Anticipate Emergency Depressurization was performed, the amber lights for the SRV s will not illuminate if pressure has been reduced to below approximately 300 psig. ill this case the operator must use 2HII-P614 recorder indication to monitor tail pipe temperatures for the SRVs to verify the valves actually opened (Recorder 2B21-R614).
0 Depending on Reactor Water Level prior to opening ADS valves, RWL may swell to above 60 inches, requiring the operator to enter 34AB-C32-00l-2, Reactor Water Level Above 60 inches.
- Operator secures all injection other than CRD
(
Appendix D Required Operator Actions Form ES-D-2
~,
Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
9 Page 25 of 30 Event
Description:
Emergency Depress prior to Bulk Average DW temperature of 3400P I Time Position Applicant's Actions or Behavior BOP
- Starts controlling RWL with low pressure systems (LPCI, Core Spray, or Condensate) as Rx pressure decreases. During the Emergency Depress will not be able to maintain inside the RWL band, but should restore RWL to within the band at some point after the Emergency Depress.
Simulator Operator - The scenario can be stopped at any time after emergency depress is peiformed and when the crew determines that RPV Flooding is required OR as directed by the Chief Examiner. Placing Torus cooling in service is not a required part of this event.
- If time and man power allows, places torus cooling in service per 34S0-EII-01O-2, RHR System, using the placard.
NOTE: Only the B Loop of RHR will be placed into service due to the A Loop RHR pump failures Appendix D Required Operator Actions Form ES-D-2 I,
Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
9 Page 25 of 30 Event
Description:
Emergency Depress prior to Bulk: Average DW temperature of 340°F Time Position Applicant's Actions or Behavior I
- Starts controlling RWL with low pressure systems (LPCI, Core Spray, or Condensate) as Rx pressure decreases. During the Emergency Depress will not be able to maintain inside the RWL band, but should restore RWL to within the band at some point after the Emergency Depress.
Simulator Operator - The scenario can be stopped at any time after emergency depress is performed and when the crew determines that RPV Flooding is required OR as directed by the Chief Examiner. Placing Torus cooling in service is not a required part of this event.
- If time and man power allows, places torus cooling in service per 34S0-EII-01O-2, RHR System, using the placard.
NOTE: Only the B Loop of RHR will be placed into service due to the A Loop RHR pump failures
(
Appendix 0 Required Operator Actions Form ES-O-2 If Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
9 Page 26 of30 Event
Description:
Emergency Depress prior to Bulk Average DW temperature of 340°F Time Position Applicant's Actions or Behavior
- Place RHRSW in operation per 34S0-EII-010-2 by performing the following:
- Prelube RHRSW pump.
- Override 2EII-F068B Low Discharge Pressure Interlock.
- Position 2EII-F068B to 45% OPEN
- Start RHRSW pump.
- Place 2EII-F068B Low Discharge Pressure Interlock switch to NORMAL position.
- Position 2EII-F068B to obtain < 4400 GPM AND < 450 PSIG.
- IF desired to start SECOND pump,
- Throttle 2EII-F068B to achieve max flow rate (not to exceed 4400 GPM).
- Open 2EII-F068B an additional 5%.
- Start Second RHRSW Pump.
- Position 2EII-F068B to obtain < 7600 GPM or with SS approval
<8800 GPM AND < 450 PSIG.
NOTE; Since operation is lAW the EOPs, Shift Supervisor approval is required prior to exceeding 7600 GPM. In this case, flow is limited to ~ 8800 GPM with two RHR Service Water Pumps operating in a single RHR Service Water loop.
- Open 2E 11-F048B.
- Open 2EII-F003B.
- Start RHR Loop B pump(s).
- Open 2EII-F028B.
Appendix 0 Required Operator Actions Form ES-O-2
'I Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
9 Page 26 of 30 Event
Description:
Emergency Depress prior to Bulk Average DW temperature of 340°F I Time Position Applicant's Actions or Behavior
- Place RHRSW in operation per 34S0-EII-010-2 by performing the following:
- Prelube RHRSW pump.
- Override 2EII-F068B Low Discharge Pressure Interlock.
- Position 2EII-F068B to 45% OPEN
- Start RHRSW pump.
- Place 2EII-F068B Low Discharge Pressure Interlock switch to NORMAL position.
- Position 2EII-F068B to obtain < 4400 GPM AND < 450 PSIG.
(
- IF desired to start SECOND pump,
- Throttle 2EII-F068B to achieve max flow rate (not to exceed 4400 GPM).
- Open 2Ell-F068B an additional 5%.
- Start Second RHRSW Pump.
- Position 2EII-F068B to obtain < 7600 GPM or with SS approval
<8800 GPM AND < 450 PSIG.
NOTE; Since operation is lAW the EOPs, Shift Supervisor approval is required prior to exceeding 7600 GPM. In this case, flow is limited to ::{ 8800 GPM with two RHR Service Water Pumps operating in a single RHR Service Water loop.
- Open 2EII-F048B.
- Open 2E 11-F003B.
- Start RHR Loop B pump(s).
- Open 2EII-F028B.
(
Appendix D Reguired Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
9 Page 27 of30 Event
Description:
Emergency Depress prior to Bulk Average DW temperature of 340°F Time Position Applicant's Actions or Behavior I
NOTE: RHR system rated flow is 7700 gpm with one pump or 17,000 gpm with two pumps.
- IF the Hx Bypass Vlv, 2EII-F048B is NOT full OPEN, RHR Flow is limited to :s; 11,500 gpm.
- Throttle Open 2EII-F024B.
- Open 2EII-F047B.
- Close 2EII-F048B
- Throttle 2EII-F068B to maintain> 20 PSID Hx B dp.
- Refer to 34S0-EII-01O-2.
Simulator Operator - The scenario can be stopped at any time after emergency depress is peiformed and when the crew determines that RPV Flooding is required OR as directed by the Chief Examiner.
Appendix 0 Reguired Operator Actions Form ES-O-2
(,
~
Op-Test No.: 2009-302 Scenario No.:
5-03 Event No.:
9 Page 27 of 30 Event
Description:
Emergency Depress prior to Bulk Average DW temperature of 340°F I Time Position Applicant's Actions or Behavior NOTE: RHR system rated flow is 7700 gpm with one pump or 17,000 gpm with two pumps.
- IF the Hx Bypass Vlv, 2EII-F048B is NOT full OPEN, RHR Flow is limited to ::; 11,500 gpm.
- Throttle Open 2EII-F024B.
- Open 2EII-F047B.
- Close 2EII-F048B
- Throttle 2EII-F068B to maintain> 20 PSID Hx B dp.
(
- Refer to 34S0-Ell-0l0-2.
Simulator Operator - The scenario can be stopped at any time after emergency depress is performed and when the crew determines that RPV Flooding is required OR as directed by the Chief Examiner.
(
Page 28 of 30 AppendixD Scenario Outline Form ES-D-l NRC Draft Facility:
E. I Hatch Scenario No.:
5-03 0 0-Test No.:
2009-302 Examiners: ___________ Operators: ______________
--=S:..::R.:..O:::-
Turnover Summary:
Unit 2 is at 75%.
Perform 34SV-C71-005-2," Turbine Control Valve Fast Closure Instrument Functional Test", for CV -1 ONLY Event 1: Reduce reactor power to 70% using Recirc for Turbine Testing.
Event 2: Perform 34SV-C71-005-2," Turbine Control Valve Fast Closure Instrument Functional Test", for CV-l ONLY starting at step 7.2.6.
Event 3: InstrumentffS; The RCIC Torus Level Sensor Fails High; with failure of CST valve in mid position (Valve overload). Time compression repair and re-alignment back to CST.
Event 4: Component; The CRD FCV '2A' will slowly fail causing a loss of CRD. The operator will take manual actions to swap FCV and return the CRD system to normaL Event 5: Component; ITS; The HPCI system will experience an inadvertent start. The operator takes manual control to secure HPCI. (Critical Task)
Event 6: Component; Loss OF DW Chillers.
Event 7: Major; Steam line breaks inside DrywelL Event 8: Component; The RHR 2Ell-FOI6A or B Containment Spray Valve will not open requiring the operator to transition to the other loop of RHR to spray the DrywelL When 2Ell-F016A is positioned to open, RHR A and C pumps will trip.
Event 9: Major; Emergency Depress prior to Bulk Average DW temperature of 340°F (Critical Task)
(
(
Page 28 of30 AppendixD Scenario Outline Form ES-D-l NRC Draft Facility:
E. I Hatch Scenario No.:
5-03 Op-Test No.:
2009-302 Examiners:
Operators:
SRO RO BOP Initiating Conditions:
Turnover Summary:
Unit 2 is at 75%.
Perform 34SV -C71-005-2," Turbine Control Valve Fast Closure Instrument Functional Test", for CV -1 ONLY Event 1: Reduce reactor power to 70% using Recirc for Turbine Testing.
Event 2: Perform 34SV -C71-005-2," Turbine Control Valve Fast Closure Instrument Functional Test", for CV-l ONLY starting at step 7.2.6.
Event 3: InstrumentrrS; The RCIC Torus Level Sensor Fails High; with failure of CST valve in mid position (Valve overload). Time compression repair and re-alignment back to CST.
Event 4: Component; The CRD FCV '2A' will slowly fail causing a loss of CRD. The operator will take manual actions to swap FCV and return the CRD system to normal.
Event 5: Component; rrs; The HPCI system will experience an inadvertent start. The operator takes manual control to secure HPCI. (Critical Task)
Event 6: Component; Loss OF DW Chillers.
Event 7: Major; Steam line breaks inside Drywell.
Event 8: Component; The RHR 2E 11-FO 16A or B Containment Spray Valve will not open requiring the operator to transition to the other loop of RHR to spray the Drywell. When 2E 11-F016A is positioned to open, RHR A and C pumps will trip.
Event 9: Major; Emergency Depress prior to Bulk Average DW temperature of 340°F (Critical Task)
Page 29 of 30 Critical Tasks NRC DRAFT Facility:
E. I Hatch Scenario No.:
5-03 On-Test No.:
2009-302 Critical Tasks Secure HPCI system prior to receiving the APRMlOPRM high reactor power trip. (Event 5)
Emergency Depress prior to Bulk Average DW temperature of 340°F. (Event 9)
ES 301-4 Attributes Required Actual Items
- 1.
Total Malfunctions 5-8 6
- 1. RCIC Torus Level Sensor Fails High (Event 3)
- 3. HPCI system will inadvertently start (Event 5)
- 4. Loss OF DW Chillers (Event 6)
- 5. Steam line breaks inside containment with A Loop RHR pumps failed (Event 7)
- 6. RHR 2EII-FOI6A/B Containment Spray Valve will not open along with RHR Loop A pumps tripping (Event 8)
- 2.
Malfunctions After 1-2 1
- 1. RHR 2Ell-FOI6A/B Containment Spray Valve EOPEntry will not open along with RHR Loop A pumps tripping (Event 8)
- 3.
Abnormal Events 2-4 3
- 2. HPCI system will inadvertently start (Event 5)
- 3. Loss OF DW Chillers (Event 6)
- 4.
Major Transients 1-2 2
- 1. Steam line breaks inside containment with A Loop RHR pumps failed (Event 7)
- 2. Emergency Depress prior to 340°F (Event 9)
- 5.
EOPs entered, 1-2 2
- 1. RC EOP Flow Chart (Event 7) requiring substantive
- 2. PC EOP Flow Chart (Event 7) actions
- 6.
EOPs contingencies 0-2 1
- 7.
Critical Tasks 2-3 2
- 2. Emergency Depress prior to Bulk Average DW temperature of 340°F. (Event 9)
Page 29 of 30 Critical Tasks NRC DRAFT Facility:
E. I Hatch Scenario No.:
5-03 On-Test No.:
2009-302 Critical Tasks Secure HPCI system prior to receiving the APRMlOPRM high reactor power trip. (Event 5)
Emergency Depress prior to Bulk Average DW temperature of 340°F. (Event 9)
ES 301-4 Attributes Required Actual Items
- 1.
Total Malfunctions 5-8 6
- 1. RCIC Torus Level Sensor Fails High (Event 3)
- 3. HPCI system will inadvertently start (Event 5)
- 4. Loss OF DW Chillers (Event 6)
- 5. Steam line breaks inside containment with A Loop RHR pumps failed (Event 7)
- 6. RHR 2E11-F016AJB Containment Spray Valve will not open along with RHR Loop A pumps
(
tripping (Event 8)
- 2.
Malfunctions After 1-2 1
- 1. RHR 2Ell-F016AJB Containment Spray Valve EOPEntry will not open along with RHR Loop A pumps tripping (Event 8)
- 3.
Abnormal Events 2-4 3
- 2. HPCI system will inadvertently start (Event 5)
- 3. Loss OF DW Chillers (Event 6)
- 4.
Major Transients 1-2 2
- 1. Steam line breaks inside containment with A Loop RHR pumps failed (Event 7)
- 2. Emergency Depress prior to 340°F (Event 9)
- 5.
EOPs entered, 1-2 2
- 1. RC EOP Flow Chart (Event 7) requiring substantive
- 2. PC EOP Flow Chart (Event 7) actions
- 6.
EOPs contingencies 0-2 1
- 7.
Critical Tasks 2-3 2
- 2. Emergency Depress prior to Bulk Average DW temperature of 340°F. (Event 9)
HLT 5 NRC Operating Exam Scenario 3 SIDFT TURNOVER UNIT 1 STATUS Power:
100%
Activities in progress:
None Power:
Unit 2 is operating at approximately 75% power.
The following equipment is None inoperable:
Scheduled evolutions:
Surveillances due this shift:
Active clearances:
Rod Configuration:
Lower reactor power IA W 34GO-OPS-005-2 to 70% and then perform 34SV-C71-005-2," Turbine Control Valve Fast Closure Instrument Functional Test", for CV-1 ONLY starting at step 7.2.6.
34SV-C71-005-2," Turbine Control Valve Fast Closure Instrument Functional Test", for CV -1 ONLY.
None SeeRWM
(
(
HLT 5 NRC Operating Exam Scenario 3 SIDFT TURNOVER UNIT 1 STATUS Power:
100%
Activities in progress:
None Power:
Unit 2 is operating at approximately 75% power.
The following equipment is None inoperable:
Scheduled evolutions:
Surveillances due this shift:
Active clearances:
Rod Configuration:
Lower reactor power IA W 34GO-OPS-005-2 to 70% and then perform 34SV-C71-005-2," Turbine Control Valve Fast Closure Instrument Functional Test", for CV-l ONLY starting at step 7.2.6.
34SV-C71-005-2," Turbine Control Valve Fast Closure Instrument Functional Test", for CV-l ONLY.
None SeeRWM
Page 1 of3 AppendixD Scenario Outline Form ES-D-l NRC Draft Facility:
E. I Hatch Scenario No.:
5-3 Op-Test No.:
2009-302 Examiners:
Operators:
SRO RO BOP Initial Conditions. Unit 2 is operating at~ng preparations to reduce reactor power to 94% for Main Turbine Stop Valve Instrument u onal Testing. Off-Gas Cooler Condensers will be shifted after reactor power is reduced.
Turnover:
Event Malf. No.
Event Event No.
r Type*
Description 1
~~~7~1Q/t ~ (ATC)
Reduce reactor power to 94% for Turbine Testing 2
1(\\17" ( 07/;
\\ n IN (BOP)
Shift Off-Gas Cooler Condensers ~
we -t:?-(,. vaflA.re s '?
3
~\\~~
~ (ATC)
RCIC Torus Level Sensor Fails High; with time compression repair 1
'v
\\rl.v~6f' I TS (SRO) and re-alignment back to CST.
"40 tAJ"V'4 vil-vt{<2..
I
~
,u.
C (BOP)
Inadvertent start of HPCI. (Critical Task)
TS (SRO)
[tAQw1.L
{If'1/ LC tr, rt4..fo 5
C (ATC)
CRD FCV '2A' Failure, M4h j V\\;{VLl,yt'/ ~&v'J: -rtti}v,t t oyw.duae 6
- i.
~
C (BOP)
Stator Cooling Pump '2B' Trips 2001
. ~13v~2' Stator Cooling Pump '2A' fails to Auto Start (manually start '2A'),
7 M(ALL)
Steam Line Break inside DW 5-Je~ l£-.A ; v Dw
'1 8
C (ATC)
RHR 2EII-F016NB Containment Spray Valve fails to OPEN
/;;
therefore requiring the opposite loop of DW spray to be used.
(Critical Task) 9 C (BOP)
RCIC Overspeed trip when started requiring RFPTs for RWL control.
(Critical Task)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor tst
/1 \\
Page 1 of 3 AppendixD Scenario Outline Form ES-D-l NRC Draft Facility:
E. I Hatch Scenario No.:
5-3 Op-Test No.:
2009-302 Examiners:
Operators:
SRO RO BOP Initial Conditions. Unit 2 is operating at CfQO~aking preparations to reduce reactor power to 94% for Main Turbine Stop Valve InstrumentFlfITc(lonal Testing. Off-Gas Cooler Condensers will be shifted after reactor power is reduced.
Turnover:
Event Malf. No.
Event Event No.
I, Type*
Description
'I 1
VV)l;:,~;:~v~;Y. /1.,
- 1 Q R (ATC)
Reduce reactor power to 94% for Turbine Testing
\\ "
'G V
l~/YL vuC.k-j,t
~ ??
2
~6v I., ~ /
N (BOP)
Shift Off-Gas Cooler Condensers
\\, :.
3
~l:(~~-:~; I (ATC)
RCIC Torus Level Sensor Fails High; with time compression repair
'1";
~', '~ "
/ TS (SRO) and re-alignment back to CST.
~o VVV'_c}/c"q :)""/: {C
(
4 C (BOP)
Inadvertent start of HPCI. (Critical Task)
(e. {l L,(
(. } 1; ;) "~1-(.....
I'~
-,j.
TS (SRO)
~' V',,~(.t.,..,*
/'~'
5 C (ATC)
/i!Li{.h, j Vvf.C/l
'itf/V} -\\/ '.
- /
~,
6 i
C (BOP)
Stator Cooling Pump '2B' Trips ;2001,<.,', >:'1.,C.',' ?13vVV'~t 2' Stator Cooling Pump '2A' fails to Auto Start (manually start '2A')
7 Steam Line Break inside DW yW M (ALL)
~-
8 C (ATC)
RHR 2EII-F016A1B Containment Spray Valve fails to OPEN 4/
therefore requiring the opposite loop of DW spray to be used.
(Critical Task) 9 C (BOP)
RCIC Overspeed trip when started requiring RFPTs for RWL control.
(Critical Task)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
{
Page 2 of3 Scenario Summary Facility:
E. I Hatch Scenario No.:
5-03 Oo-Test No.:
2009-302 NRC Draft Initiating Conditions:
Unit 2 is operating at 100% RTP making preparations to reduce reactor power to 94% for Main Turbine Stop Valve Instrument Functional Testing.
Turnover Off-Gas Cooler Condensers will be shifted after reactor power is reduced per 34S0-N61-001-2.
Summary:
Event 1: Reduce reactor power to 94% using Recirc for Turbine Testing.
Event 2: Shift Off-Gas Cooler Condensers Event 3: Instrument/TS; The RCIC Torus Level Sensor Fails High causing a suction swap for RCIC. Using time compression repair, RCIC is re-aligned back to the CST.
Event 4: ComponentlTS; The HPCI system will experience an inadvertent start. The operator takes manual control to secure HPCI. (Critical Task)
Event 5: Component; The CRD FCV '2A' will fail causing a loss of CRD. The operator will take manual actions to swap FCV and return the CRD system to normal.
Event 6: Component; The Stator Cooling Pump '2B' trips and the '2A' pump fails to auto start requiring the operator to take manual actions to place the '2A' pump in service.
Event 7: Major; Steam line breaks inside containment. HPCI system will become unavailable due to the failure of the auxiliary oil pump.
Event 8: Component; The RHR 2Ell-F016A or B Containment Spray Valve will not open (depends on which loop of RHR the operator attempts first) requiring the operator to transition to the other loop of RHR to spray the Drywell. (Critical Task)
Event 9: As RWL decreases the RCIC system will trip on Overspeed. The operator will have to maintain RWL using the Feedwater system. (Critical Task)
" r \\
Page 2 of 3 Scenario Summary Facility:
E. I Hatch Scenario No.:
5-03 aD-Test No.:
2009-302 NRC Draft Initiating Conditions:
Unit 2 is operating at 100% RTP making preparations to reduce reactor power to 94% for Main Turbine Stop Valve Instrument Functional Testing.
Turnover Off-Gas Cooler Condensers will be shifted after reactor power is reduced per 34S0-N61-001-2.
Summary:
Event 1: Reduce reactor power to 94% using Recirc for Turbine Testing.
Event 2: Shift Off-Gas Cooler Condensers Event 3: InstrumentlTS; The RCIC Torus Level Sensor Fails High causing a suction swap for RCIC. Using time compression repair, RCIC is re-aligned back to the CST.
Event 4: ComponentlTS; The HPCI system will experience an inadvertent start. The operator takes manual control to secure HPCI. (Critical Task)
Event 5: Component; The CRD FCV '2A' will fail causing a loss of CRD. The operator will take manual actions to swap FCV and return the CRD system to normal.
Event 6: Component; The Stator Cooling Pump '2B' trips and the '2A' pump fails to auto start requiring the operator to take manual actions to place the '2A' pump in service.
Event 7: Major; Steam line breaks inside containment. HPCI system will become unavailable due to the failure of the auxiliary oil pump.
Event 8: Component; The RHR 2EIl-FOI6A or B Containment Spray Valve will not open (depends on which loop of RHR the operator attempts first) requiring the operator to transition to the other loop of RHR to spray the Drywell. (Critical Task)
Event 9: As RWL decreases the RCIC system will trip on Overspeed. The operator will have to maintain RWL using the Feedwater system. (Critical Task)
(
Page 3 of3 Critical Tasks NRC Draft Facility:
E. I Hatch Scenario No.:
5-03 Oo-Test No.:
2009-302 Critical Tasks Secure HPCI system prior to receiving the APRMlOPRM high reactor power trip. (Event 4)
Manually open RHR 2EII-POI6A1B Containment Spray Valve prior to exceeding 3400 P in the Drywell or exceeding EOP Graph 7 Pressure Suppression Pressure to preclude damage to containment. (Event 8)
Using the CondensatelFeedwater system maintain RWL above TAP (-155"). (Event 9)
\\\\ '\\
(
Page 3 of 3 Critical Tasks NRC Draft Facility:
E. I Hatch Scenario No.:
5-03 Op-Test No.:
2009-302 Critical Tasks Secure HPCI system prior to receiving the APRM/OPRM high reactor power trip. (Event 4)
Manually open RHR 2EII-POI6A1B Containment Spray Valve prior to exceeding 340 0 P in the Drywell or exceeding EOP Graph 7 Pressure Suppression Pressure to preclude damage to containment. (Event 8)
Using the CondensatelFeedwater system maintain RWL above TAP (-155"). (Event 9)
Page 1 of 31 AppendixD Scenario Outline Form ES-D-l NRC Draft Facility:
E. I Hatch Scenario No.: 5-04 Op-Test No.:
2009-302 Examiners:
Operators:
SRO RO BOP Initial Conditions. Unit 2 is operating at approximately 90% RTP. Raise reactor power to 100% after 34IT-N30-001-2, "Main Turbine & Auxiliaries Weekly Test", PowerlLoad Unbalance Test is performed.
Turnover: After the Turbine test is complete, have the ATC Increase Reactor Pressure to 1025 psig (Ops Management has determined that Attachment 3 of 34GO-OPS-005-2 is NOT required.), then increase Reactor power to 95% using the Rx Recirc system, with a 10 MWe limit on power change rate.
Event Malf. No.
~vent Event No.
Type*
Description 1
N/A
~(BOP) 34IT-N30-00l-2, "Main Turbine & Auxiliaries Weekly Test",
PowerlLoad Unbalance Test
,.. 2 N/A
[R (ATC)
Increase reactor power to 95% using Recirc and adjusting DEHC pressure set to achieve reactor pressure >1025 psig.
'3 mfDRL_509 12 (BOP)
Reactor Building Exhaust fan failure with the Standby Exhaust fan failing to start. Standby Exhaust fan manually started or SBGT fan started to re-establish Rx Bldg dp. (Critical Task) 4 mfB31_135B 12 (ATC)
Recirc '2B' ASD Cell Bypass; "2B" Recirc speed decreases IrS (SRO) resulting in a flow mismatch 5
mfB31_41B C (ATC)
Recirc Pump '2B' High Vibration requiring reducing reactor power in an attempt to clear alarm. Alarm remains in until pump is tripped.
6 N/A C (BOP)
Irs (SRO)
HPCI Room fire 7
N7L70 M(ALL)
Con Bay Flooding svoE41102
'B' MSL fails to isolate automatically on low vacuum, manual loB21-F022BGI isolation required loB21-F022BR2 HPCI Gov valve will not open to provide sufficient steam to loB21-F022BMGl turbine.
loB21-F022BMR2 j
loB21-F028BGI J
loB21-F028BR2
!,' i J
loB21-F028BMGl loB21-F028BMR2 8
mfB21_130B 1'-' (ATC)
'B' SRV fails open and remains partially open after fuses are pulled.
~
mfE51_113 C (BOP)
RCIC 2E51-F008 isolation rnfN2L99 SULCV 2N21-Fl11 fails closed (Critical Task)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 31 AppendixD Scenario Outline Form ES-D-l NRC Draft Facility:
E.IHatch Scenario No.:
5-04 Op-Test No.:
2009-302 Examiners:
Operators:
SRO RO BOP Initial Conditions. Unit 2 is operating at approximately 90% RTP. Raise reactor power to 100% after 34IT-N30-001-2, "Main Turbine & Auxiliaries Weekly Test", PowerlLoad Unbalance Test is performed.
Turnover: After the Turbine test is complete, have the A TC Increase Reactor Pressure to 1025 psig (Ops Management has determined that Attachment 3 of 34GO-OPS-005-2 is NOT required.), then increase Reactor power to 95% using the Rx Recirc system, with a 10 MWe limit on power change rate.
Event Malf. No.
IEvent Event No.
Type*
Description 1
N/A
~ (BOP) 34IT-N30-00l-2, "Main Turbine & Auxiliaries Weekly Test",
PowerlLoad Unbalance Test
(
2 N/A R (ATC)
Increase reactor power to 95% using Recirc and adjusting DEHC pressure set to achieve reactor pressure> 1 025 psig.
3 mfDRL_509 C (BOP)
Reactor Building Exhaust fan failure with the Standby Exhaust fan failing to start. Standby Exhaust fan manually started or SBGT fan started to re-establish Rx Bldg dp. (Critical Task)
~
mfB31_135B C (ATC)
Recirc '2B' ASD Cell Bypass; "2B" Recirc speed decreases Irs (SRO) resulting in a flow mismatch 5
mfB31_41B C (ATC)
Recirc Pump '2B' High Vibration requiring reducing reactor power in an attempt to clear alarm. Alarm remains in until pump is tripped.
6 N/A C (BOP)
HPCI Room fire ITS (SRO) 7 N71_70 M (ALL)
Con Bay Flooding svoE41102
'B' MSL fails to isolate automatically on low vacuum, manual 10B21-F022BG 1 isolation required 10B21-F022BR2 HPCI Gov valve will not open to provide sufficient steam to loB21-F022BMG1 turbine.
loB21-F022BMR2 Ct.
/>/
loB21-F028BG 1
,,,.,..C-10B21-F028BR2 loB21-F028BMG1 loB21-F028BMR2 8
mfB21_130B C (ATC)
'B' SRV fails open and remains partially open after fuses are pulled.
9 mfE5L113 C (BOP)
RCIC 2E51-F008 isolation mfN2L99 SULCV 2N21-F111 fails closed (Critical Task)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Required Operator Actions Form ES-D-2
'I Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
1 Page 2 of31 Event
Description:
34IT-N30-001-2, "Main Turbine & Auxiliaries Weekly Test" surveillance for Power-Load-Unbalance only Time Position Applicant's Actions or Behavior I
SRO Directs the BOP to perform 34IT-N30-001-2, "Main Turbine & Auxiliaries Weekly Test", PowerlLoad Unbalance Test.
BOP Enters 34IT-N30-001-2, "Main Turbine & Auxiliaries Weekly Test", Section 7.2, "PowerlLoad Unbalance Test" (All Steps are performed from 2N32-K4001A or B (DEHC Computers) I Tests!
screen)
Enters the I PLU test I screen: A or B CONFIRMs that the Intermediate Pressure is > 40% (will be approx. 92%
and is read at the bottom of the PLU TEST page)
Observes the PLU Status for slots 17 and 18 are I oFF1 Selects PLU TEST ~
Clicks the OK button on the "Tum PLU Test On?" message box CONFIRMs "PLU TEST SUCCESSFUL IN <R>, , and <T> CORE" for:
PLU TEST-Slot 17 AND PLU TEST-Slot 18 Selects PLU TEST I OFF1 Clicks the OK button on the "Tum PLU Test Off?" message box
\\
CONFIRMs PLU Status for slot 17 (all three) reads "OFF" AND CONFIRMs PLU Status for slot 18 (all three) reads "OFF" Notifies the SS that the test has been completed satisfactorily.
Appendix 0 Required Operator Actions Form ES-O-2 I~
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
1 Page 2 of 31 Event
Description:
34IT-N30-001-2, "Main Turbine & Auxiliaries Weekly Test" surveillance for Power-Load-Unbalance only II Time Position Applicant's Actions or Behavior SRO Directs the BOP to perform 34IT-N30-001-2, "Main Turbine & Auxiliaries Weekly Test", PowerlLoad Unbalance Test.
BOP Enters 34IT-N30-001-2, "Main Turbine & Auxiliaries Weekly Test", Section 7.2, "PowerlLoad Unbalance Test" (All Steps are performed from 2N32-K4001A or B (DEHC Computers) I Test~
screen)
Enters the I PLU test I screen: A or B CONFIRMs that the Intermediate Pressure is> 40% (will be approx. 92%
and is read at the bottom of the PLU TEST page)
(
Observes the PLU Status for slots 17 and 18 are I OFF1 Selects PLU TEST ~
Clicks the OK button on the "Tum PLU Test On?" message box CONFIRMs "PLU TEST SUCCESSFUL IN <R>, , and <T> CORE" for:
PLU TEST-Slot 17 AND PLU TEST-Slot 18 Selects PLU TEST I OFF1 Clicks the OK button on the "Tum PLU Test Off?" message box CONFIRMs PLU Status for slot 17 (all three) reads "OFF" AND CONFIRMs PLU Status for slot 18 (all three) reads "OFF" Notifies the SS that the test has been completed satisfactorily.
(
\\
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
2 Page 3 of31 Event
Description:
Increase reactor power to 95% using Recirc and adjust pressure set for 1025#
Time Position Applicant's Actions or Behavior SRO Directs the A TC to increase reactor pressure to 1025 psig using ERC pressure set.
ATC Enters 34GO-OPS-005-2, Power Changes, at step 7.1.10 and at the DERC panel computer, perform the following steps:
Selects the 1 Control 1--+-1 psi-load 1 screen Intermittently uses (Clicks) the 1 Raise 1 button to increase reactor pressure to 1025 psig. (This will take approx. 4 minutes.)
Notifies the SS that Rx pressure is at 1025 psig.
SRO Directs the ATC to increase Rx Power to 95% using Recirc.
ATC IA W 34S0-B31-001-2, the ATC increases Recirc pump speed, not to exceed 10 MWE per minute by depressing the RAISE SLOW or RAISE MEDIUM pushbuttons on the Master or Individual controls until reactor power is 95%.
Notifies the SS that reactor power has been increased to 95%.
Appendix D Required Operator Actions Form ES-D-2
(,
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
2 Page 3 of 31 Event
Description:
Increase reactor power to 95% using Recirc and adjust pressure set for 1025#
II Time Position Applicant's Actions or Behavior I
SRO Directs the A TC to increase reactor pressure to 1025 psig using ERC pressure set.
ATC Enters 34GO-OPS-005-2, Power Changes, at step 7.1.10 and at the DERC panel computer, perform the following steps:
Selects the 1 Control 1---+ 1 psi-load 1 screen Intermittently uses (Clicks) the I Raise I button to increase reactor pressure to 1025 psig. (This will take approx. 4 minutes.)
Notifies the SS that Rx pressure is at 1025 psig.
SRO Directs the ATC to increase Rx Power to 95% using Recirc.
(
ATC IA W 34S0-B31-001-2, the ATC increases Recirc pump speed, not to exceed 10 MWE per minute by depressing the RAISE SLOW or RAISE MEDIUM pushbuttons on the Master or Individual controls until reactor power is 95%.
Notifies the SS that reactor power has been increased to 95%.
(
Appendix 0 Required Operator Actions Form ES-O-2
~
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
3 Page 4 of 31 Event
Description:
Reactor Building Exhaust fan failure Time Position Applicant's Actions or Behavior I
At Chief Examiners direction the Simulator Operator ENTERS (RB-3) mfDRL 509, Rx Bldg Exhaust Fan A fails & standby does not start On the 2HII-P650 panel alarms 650-214, 'PaneI2HII-P654 Panel System Trouble' and 650-224, 'PaneI2HII-P657 Panel System Trouble' are received BOP
Appendix 0 Required Operator Actions Form ES-O-2 I
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
3 Page 4 of 31 Event
Description:
Reactor Building Exhaust fan failure Time Position Applicant's Actions or Behavior At Chief Examiners direction the Simulator Operator ENTERS (RB-3) mfDRL 509, Rx Bldg Exhaust Fan A fails & standby does not start On the 2H11-P650 panel alarms 650-214, 'PaneI2H11-P654 Panel System Trouble' and 650-224, 'PaneI2H11-P657 Panel System Trouble' are received BOP
(
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
3 Page 5 of 31 Event
Description:
Reactor Building Exhaust fan failure Time Position Applicant's Actions or Behavior Note: This failure will require entry into the SC EOP Flow Chart as well as two Abnormal procedures. The following sequence may be slightly out of order because of this.
If the operator enters 657-081 first, then the following actions will be addressed, otherwise skip to the next alarm.
- Acknowledges 657-081, 'RB Exhaust Fan 2T41-C007A1B Flow Low' alarm and enters 657-081.
- Confirms the Standby Rx Bldg Vent Exhaust Fan has not automatically started (IT SHOULD HAVE AUTO STARTED), the operator will place the control switch for 2T41-C007A to OFF AND 2T41-C007B to Run.
(
- Confirm the following dampers are OPEN:
- 2T41-F044A, RIB Inboard Isol Dampers Inacc. Areas Exhaust Fans Disch on 2H11-P657.
- 2T41-F044B, RIB Outboard Isol Dampers Inacc Areas Exhaust Fans Dish on 2H11-P654.
- Once RB Exhaust and Supply flows have stabilized, confirms 654-001,
'RB Inside To Outside Air Diff Press Low' clears and notifies SS.
II Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
3 Page 5 of 31 Event
Description:
Reactor Building Exhaust fan failure II Time Position Applicant's Actions or Behavior I
Note: This failure will require entry into the SC EOP Flow Chart as well as two Abnormal procedures. The following sequence may be slightly out of order because of this.
If the operator enters 657-081 first, then the following actions will be addressed, otherwise skip to the next alarm.
- Acknowledges 657-081, 'RB Exhaust Fan 2T41-C007A1B Flow Low' alarm and enters 657-081.
- Confirms the Standby Rx Bldg Vent Exhaust Fan has not automatically started (IT SHOULD HAVE AUTO STARTED), the operator will place the control switch for 2T41-C007A to OFF AND 2T41-C007B to Run.
(
- Confirm the following dampers are OPEN:
- 2T41-F044A, RIB Inboard Isol Dampers Inacc. Areas Exhaust Fans Disch on 2H11-P657.
- 2T41-F044B, RIB Outboard Isol Dampers Inacc Areas Exhaust Fans Dish on 2Hll-P654.
- Once RB Exhaust and Supply flows have stabilized, confirms 654-001,
'RB Inside To Outside Air Diff Press Low' clears and notifies SS.
(
\\
II
Appendix D Required Operator Actions Form ES-D-2
.~
Op. Test No.: 2009*302 Scenario No.:
5*04 Event No.:
3 Page 6 of31 Event
Description:
Reactor Building Exhaust fan failure Time Position Applicant's Actions or Behavior I
If the operator enters 654-001 first, then the following actions will be addressed.
- Acknowledges 654-001, 'RB Inside To Outside Air Diff Press Low' alarm and enters 654-001 and performs the following actions:
- Confirms Reactor Building to outside air differential pressure, is less than -0.06" WC, as indicated on 2T46-R604B, Sec Cnmt Diff Press B, red pen, 2HII-P700.
- Determines that the 2T41-C007A, 'Rx Bldg Exhaust' fan red light is illuminated and the 2T41-COOIA, 'Rx Bldg Supply' fan red light is illuminated.
- Informs the SS that the 2T41-C007A, 'Rx Bldg Exhaust' fan is running (Red light illuminated) and the 2T41-COOIA, 'Rx Bldg Supply' fan is running (Red light illuminated) and that Rx Bldg dp is 0".
- Enters 34AB-T22-002-2, 'Loss of Secondary Containment Integrity' and 34AB-T22-003-2, 'Secondary Containment Control', and notifies Management of the plant conditions.
Appendix 0 Required Operator Actions Form ES-O-2 If
\\
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
3 Page 6 of 31 Event
Description:
Reactor Building Exhaust fan failure Time Position Applicant's Actions or Behavior I
If the operator enters 654-001 first, then the following actions will be addressed.
- Acknowledges 654-001, 'RB Inside To Outside Air DiffPress Low' alarm and enters 654-001 and performs the following actions:
- Confirms Reactor Building to outside air differential pressure, is less than -0.06" WC, as indicated on 2T46-R604B, Sec Cnmt Diff Press B, red pen, 2HII-P700.
- Determines that the 2T41-C007A, 'Rx Bldg Exhaust' fan red light is illuminated and the 2T41-COOIA, 'Rx Bldg Supply' fan red light is illuminated.
(
- Informs the SS that the 2T41-C007A, 'Rx Bldg Exhaust' fan is running (Red light illuminated) and the 2T41-COOIA, 'Rx Bldg Supply' fan is running (Red light illuminated) and that Rx Bldg dp is 0".
- Enters 34AB-T22-002-2, 'Loss of Secondary Containment Integrity' and 34AB-T22-003-2, 'Secondary Containment Control', and notifies Management of the plant conditions.
Appendix 0 Required Operator Actions Form ES-D-2 1
Op. Test No.: 2009*302 Scenario No.:
5*04 Event No.:
3 Page 7 of31 Event
Description:
Reactor Building Exhaust fan failure Time Position Applicant's Actions or Behavior BOP
- Enters 34AB-T22-003-2, 'Secondary Containment Control'.
- Monitors secondary containment parameters.
- Notifies the SS to enter 31EO-EOP-014-2, EOP Secondary Containment flowchart due to low RB dp.
- Dispatches a SOlMaint to investigate the low RB dp.
- Enters 34AB-T22-002-2, 'Loss of Secondary Containment Integrity'.
- Dispatches a SOlMaint to determine why the Rx Bldg Fan experienced low flow and why the standby fan did not start.
- Enters 31EO-EOP-014-2, EOP Secondary Containment flowchart.
Simulator Operator waits 2 minutes and reports to the SS, as a SO, that Breaker 15 at 2R25-S065 is closed. Also report as Maintenance that the ARB Exhaust fan motor was running but the fan was not turning.
SRO Directs operator to start SBGT with suction from the Rx Bldg or restart RB Ventilation using the 2T41-C007B, 'RB Exhaust' fan.
Appendix 0 Required Operator Actions Form ES-O-2 I
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
3 Page 7 of 31 Event
Description:
Reactor Building Exhaust fan failure Time Position Applicant's Actions or Behavior BOP
- Enters 34AB-T22-003-2, 'Secondary Containment Control'.
- Monitors secondary containment parameters.
- Notifies the SS to enter 31EO-EOP-OI4-2, EOP Secondary Containment flowchart due to low RB dp.
- Dispatches a SOlMaint to investigate the low RB dp.
- Enters 34AB-T22-002-2, 'Loss of Secondary Containment Integrity'.
- Dispatches a SOlMaint to determine why the Rx Bldg Fan experienced low flow and why the standby fan did not start.
- Enters 3 I EO-EOP-014-2, EOP Secondary Containment flowchart.
Simulator Operator waits 2 minutes and reports to the SS, as a SO, that Breaker 15 at 2R25-S065 is closed. Also report as Maintenance that the A RB Exhaust fan motor was running but the fan was not turning.
SRO Directs operator to start SBGT with suction from the Rx Bldg or restart RB Ventilation using the 2T41-C007B, 'RB Exhaust' fan.
Appendix 0 Required Operator Actions Form ES-O-2 (I
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
3 Page 8 of 31 Event
Description:
Reactor Building Exhaust fan failure II Time Position Applicant's Actions or Behavior If the SS directs SBGT started, the following actions will be taken, otherwise skip this part.
- Starts the 2A or 2B SBGT with a suction from the Rx Bldg by performing the following:
- Opens 2T46-FOOIA(B)
- Places SBGT A (B) in RUN position.
- Confirms 2T46-F002A (B) OPENS.
- Confirms SBGT A (B) HTR Red Light ILLUMINATES.
- Orders the Rx Bldg Ventilation system re-started IA W 34S0-T41-005-2.
lfthe SS directs RB Ventilation started the following actions will be taken, otherwise skip this part.
- Enters 34S0-T41-005-2 and performs the following actions:
- Momentarily depresses Rx Bldg Supply Fans Reset.
- Momentarily depresses Rx Bldg Recirc Fan 2T41-B017 Reset.
Appendix 0 Required Operator Actions Form ES-O-2 I
(
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
3 Page 8 of 31 Event
Description:
Reactor Building Exhaust fan failure I Time Position Applicant's Actions or Behavior If the SS directs SBGT started, the following actions will be taken, otherwise skip this part.
- Starts the 2A or 2B SBGT with a suction from the Rx Bldg by performing the following:
- At 2H 11-P657 for "2A" or 2H 11-P654 for "2B" performs the following action IA W the SBGT Placard or 34S0-T46-001-2, SBGT System.
- Opens 2T46-F001A(B)
- Places SBGT A (B) in RUN position.
- Confirms 2T46-F002A (B) OPENS.
- Confirms SBGT A (B) HTR Red Light ILLUMINATES.
(
- Orders the Rx Bldg Ventilation system re-started IA W 34S0-T41-005-2.
If the SS directs RB Ventilation started the following actions will be taken, otherwise skip this part.
- Enters 34S0-T41-005-2 and performs the following actions:
- Momentarily depresses Rx Bldg Supply Fans Reset.
- Momentarily depresses Rx Bldg Recirc Fan 2T41-B017 Reset.
Appendix 0 Required Operator Actions Form ES-O-2 I
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
3 Page 9 of 31 Event
Description:
Reactor Building Exhaust fan failure II Time Position Applicant's Actions or Behavior Simulator Operator, when requested to peiform the following, inform the operator that the Unit 1 pushbuttons have been depressed.
- Momentarily depresses 1T4112T41, Rx Bldg/RfFlr ISOL DMPR RESET A pushbutton, pane11H11-P657.
- Momentarily depresses 1T4112T41, Rx BldglRfFlr ISOL DMPR Reset B pushbutton, pane11H11-P654.
- Momentarily depresses 2T41-D005, Reactor Building Filter, Deluge reset.
- Confirm Open/Open 2T41-F044A, Rx Bldg Inboard Isol Dampers Inaccessible Areas Exhaust Fans Disch.
- Confirm Open/Open 2T4l-F044B, Rx Bldg Outboard Isol Dampers Inaccessible Areas Exhaust Fans Disch, panel 2Hll-P654.
- Place in RUN 2T4l-C007B, Rx Bldg Vent Exhaust Fan.
- Place in STBY 2T41-C007A, Rx Bldg Vent Exhaust Fan.
(Fan Broke)
- Confirm Open/Open 2T41-FOllA, Rx Bldg Inboard Isol Dampers Supply Fans Disch.
- Confirm Open/Open 2T41-FOIIB, Rx Bldg Outboard Isol Dampers Supply Fans Disch, pane12Hll-P654.
- Place in RUN 2T41-COOIA or 2T41-COOIB, Rx Bldg Supply Fan.
- Place in STBY 2T41-COOIB or 2T41-COOIA, Rx Bldg Supply Fan.
Appendix 0 Required Operator Actions Form ES-O-2 I
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
3 Page 9 of 31 Event
Description:
Reactor Building Exhaust fan failure Time Position Applicant's Actions or Behavior I
Simulator Operator, when requested to peiform the following, inform the operator that the Unit 1 pushbuttons have been depressed.
- Momentarily depresses 1T4112T41, Rx BldglRfFIr ISOL DMPR RESET A pushbutton, pane11H11-P657.
- Momentarily depresses 1 T4112T41, Rx BldglRf FIr ISOL DMPR Reset B pushbutton, panel1H11-P654.
- Momentarily depresses 2T41-D005, Reactor Building Filter, Deluge reset.
- Confirm Open/Open 2T41-F044A, Rx Bldg Inboard Isol Dampers Inaccessible Areas Exhaust Fans Disch.
(
- Confirm Open/Open 2T41-F044B, Rx Bldg Outboard Isol Dampers Inaccessible Areas Exhaust Fans Disch, panel 2H11-P654.
- Place in RUN 2T41-C007B, Rx Bldg Vent Exhaust Fan.
- Place in STBY 2T41-C007A, Rx Bldg Vent Exhaust Fan.
(Fan Broke)
- Confirm Open/Open 2T41-FOllA, Rx Bldg Inboard Isol Dampers Supply Fans Disch.
- Confirm Open/Open 2T41-F011B, Rx Bldg Outboard Isol Dampers Supply Fans Disch, paneI2H11-P654.
- Place in RUN 2T41-C001A or 2T41-C001B, Rx Bldg Supply Fan.
- Place in STBY 2T41-C001B or 2T41-COOlA, Rx Bldg Supply Fan.
Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
3 Page 10 of31 Event
Description:
Reactor Building Exhaust fan failure I Time Position Applicant's Actions or Behavior I
- ADJUST 2T41-FC-R027 to maintain Rx Bldg Vent Exhaust Flow approximately 6.5 KCFM as indicated by the green pen on 2T41-R618, flow recorder, located on 2HII-P657.
- ADJUST 2T41-FC-R022 to maintain Rx Bldg Vent Supply Flow approximately 5.3 KCFM as indicated by the red pen on 2T41-R618, flow recorder, located on 2HI1-P657.
- While maintaining approximately 6.5 KCFM for Rx Bldg Vent Exhaust Flow and
- 5.3 KCFM Bldg Vent Flow respectively,
- ADJUST Flow Controllers 2T41-FC-R027 and 2T41-FC-R022 to obtain 0.25 inches water pressure on 2T46-DPR-R604A&B.
(
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
3 Page 10 of 31 Event
Description:
Reactor Building Exhaust fan failure Time Position Applicant's Actions or Behavior I
- ADJUST 2T41-FC-R027 to maintain Rx Bldg Vent Exhaust Flow approximately 6.5 KCFM as indicated by the green pen on 2T41-R618, flow recorder, located on 2H11-P657.
- ADJUST 2T41-FC-R022 to maintain Rx Bldg Vent Supply Flow approximately 5.3 KCFM as indicated by the red pen on 2T41-R618, flow recorder, located on 2H11-P657.
- While maintaining approximately 6.5 KCFM for Rx Bldg Vent Exhaust Flow and
- 5.3 KCFM Bldg Vent Flow respectively,
- ADJUST Flow Controllers 2T41-FC-R027 and 2T41-FC-R022 to obtain 0.25 inches water pressure on 2T46-DPR-R604A&B.
(
(
\\
Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
4 Page 11 of 31 Event
Description:
"2B" Recirculation Pump ASD Cell will auto bypass Time Position Applicant's Actions or Behavior I
Simulator Operator At Chief Examiner's direction, press (RB-4) to activate:
- mfB31_135B, Recirc ASD B Cell Bypass SRO/TS
- Direct ATC to respond to 602-208, "ASD B TROUBLE" Annunciator
- Direct maintenance be contacted to determine cause of Recirc speed decrease
- TS LCOIRAS Recirculation Loops Operating (TS 3.4.1 Condition A.l is to satisfy the LCO within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).
Simulator Operator At Chief Examiner's direction:
- Call the Control Room as I&C with the following message:
0 The "2B" Recirculation Pump ASD has automatically bypassed a cell, conditions at the ASD are normal for this condition.
(
Appendix D Required Operator Actions Form ES-D-2 I
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
4 Page 11 of 31 Event
Description:
"2B" Recirculation Pump ASD Cell will auto bypass Time Position Applicant's Actions or Behavior Simulator Operator At Chief Examiner's direction, press (RB-4) to activate:
- mfB31_135B, Recirc ASD B Cell Bypass SRO/TS
- Direct ATC to respond to 602-208, "ASD B TROUBLE" Annunciator
- Direct maintenance be contacted to determine cause of Recirc speed decrease
- TS LCOIRAS Recirculation Loops Operating (TS 3.4.1 Condition A.l is to satisfy the LCO within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).
(
Simulator Operator At Chief Examiner's direction:
- Call the Control Room as I&C with the following message:
0 The "2B" Recirculation Pump ASD has automatically bypassed
\\
a cell, conditions at the ASD are normal for this condition.
(
Appendix 0 Required Operator Actions Form ES-O-2 I,
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
4 Page 12 of 31 Event
Description:
"2B" Recirculation Pump ASD Cell will auto bypass Time Position Applicant's Actions or Behavior Note: With the 2B ASD Cell Bypassed, the operator may enter 34AB-B31-001-2, Reactor Recirculation Pump(s) Trip, Recirc Loops Mismatch, OR ASD Cell Bypass",first due to Recircflow mismatch.
- Respond to 602-208, "ASD B TROUBLE" Annunciator
- Diagnose Recirc pump speed mismatch
- Enter 34AB-B31-001-2, "Reactor Recirculation Pump(s) Trip, Recirc Loops Mismatch, or ASD Cell Bypass"
- Confirm the "SPD HLD RESET" pushbutton is illuminated
- Enter section ill of 34AB-B31-001-2
- If Recirc speed mismatch >35%, inform SS of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> limit to balance Recirc Pump flows If the SS decides to increase Recirc flow to exit the region, then the following actions will be taken, otherwise skip this part and go to the next.
STA If asked, Reactor Engineering guidance for raising power is:
- "Limit the rate of power change to 10 MWe/minute."
Appendix 0 Required Operator Actions Form ES-O-2 I,
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
4 Page 12 of 31 Event
Description:
"2B" Recirculation Pump ASD Cell will auto bypass I Time Position Applicant's Actions or Behavior Note: With the 2B ASD Cell Bypassed, the operator may enter 34AB-B3J-OOJ-2, Reactor Recirculation Pump(s) Trip, Recirc Loops Mismatch, OR ASD Cell Bypass ", first due to Recirc flow mismatch.
- Respond to 602-208, "ASD B TROUBLE" Annunciator
- Diagnose Recirc pump speed mismatch
- Enter 34AB-B3l-00l-2, "Reactor Recirculation Pump(s) Trip, Recirc Loops Mismatch, or ASD Cell Bypass"
- Confirm the "SPD HLD RESET" pushbutton is illuminated
- Enter section ill of 34AB-B31-00l-2
(
- If Recirc speed mismatch >35%, inform SS of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> limit to balance Recirc Pump flows If the SS decides to increase Recirc flow to exit the region, then the following actions will be taken, otherwise skip this part and go to the next.
STA If asked, Reactor Engineering guidance for raising power is:
- "Limit the rate of power change to 10 MWe/minute."
Appendix 0 Required Operator Actions Form ES-O-2 I
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
4 Page 13 of 31 Event
Description:
"2B" Recirculation Pump ASD Cell will auto bypass I Time Position Applicant's Actions or Behavior I
- Depress the respective SPD HLD RESET pushbutton indicating lamp
- Increase speed of the "2B" Recirc Pump per 34S0-B31-001-2, Reactor Recirc System"
- After 34AB-B31-001-2 has been addressed entered, the operator will depress the Fault Reset pushbutton to reset the "ASD B Trouble" alarm IA W 34AR-602-108-2, "ASD Trouble."
Note to examiners: TS SR 3.4.1.1 requires Recirc flow mismatch be less than 5% if operating at greater than or equal to 70% rated core flow, and mismatch be less than 10% if operating at less than 70% rated core flow.
Simulator Operator At Chief Examiner's direction:
(
- Call the Control Room as I&C with the following message:
The "2B" Recirculation Pump ASD has automatically bypassed a cell, conditions at the ASD are normal for this condition.
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
4 Page 13 of 31 Event
Description:
"2B" Recirculation Pump ASD Cell will auto bypass Time Position Applicant's Actions or Behavior I
- Depress the respective SPD HLD RESET pushbutton indicating lamp
- Increase speed of the "2B" Recirc Pump per 34S0-B31-00 1-2, Reactor Recirc System"
- After 34AB-B31-001-2 has been addressed entered, the operator will depress the Fault Reset pushbutton to reset the "ASD B Trouble" alarmIAW 34AR-602-108-2, "ASD Trouble."
Note to examiners: TS SR 3.4.1.1 requires Recirc flow mismatch be less than 5% if operating at greater than or equal to 70% rated core flow, and mismatch be less than 10% if operating at less than 70% rated core flow.
Simulator Operator At Chief Examiner's direction:
(
- Call the Control Room as I&C with the following message:
The "2B" Recirculation Pump ASD has automatically bypassed a cell, conditions at the ASD are normal for this condition.
Appendix D Required Operator Actions Form ES-D-2
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Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
4 Page 14 of 31 Event
Description:
"2B" Recirculation Pump ASD Cell will auto bypass Time Position Applicant's Actions or Behavior I
- Within 15 minutes of entering the Immediate Exit Region of the Power to Flow map, directs operator to exit the region by inserting control rods.
- Ensures the plant has exited the Immediate Exit Region of the Power to Flow map within one hour.
- Has a control rod movement brief per 34GO-OPS-065-0 Simulator Operator lfthe Team calls for the STA or Reactor Engineering, for rod movement recommendations:
- Respond as follows:
- "Use the Reactivity Manipulations Turnover."
Appendix 0 Required Operator Actions Form ES-O-2 1\\
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
4 Page 14 of 31 Event
Description:
"2B" Recirculation Pump ASD Cell will auto bypass Time Position Applicant's Actions or Behavior SRO
- Within 15 minutes of entering the Immediate Exit Region of the Power to Flow map, directs operator to exit the region by inserting control rods.
- Ensures the plant has exited the Immediate Exit Region of the Power to Flow map within one hour.
- Has a control rod movement brief per 34GO-OPS-065-0 Simulator Operator
(
lfthe Team calls for the STA or Reactor Engineering, for rod movement recommendations:
- Respond as follows:
- "Use the Reactivity Manipulations Turnover."
Appendix 0 Required Operator Actions Form ES-O-2
.~
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
4 Page 15 of 31 Event
Description:
"2B" Recirculation Pump ASD Cell will auto bypass I Time Position Applicant's Actions or Behavior ATC
- Inserts control rods per 34GO-OPS-065-0, starting with control rod Group 54.
- During rod insertion, rod steps will be performed in reverse sequential order, starting at the highest numbered step. (** rod steps are not required to be performed sequentially, but must be positioned to their RWM insert limit prior to inserting lower numbered groups).
- Selects Rod
- Places Control Rod movement switch to the IN position
- Verifies Rod moves using Rod display information and Rx and Generator power decreasing.
- If required, adjust 2CII-F003 to get 220 - 280 psid drive water dp.
ATC Note: RBM Downscale alarm may alarm during this movement due to the significant rod worth of these rods. It is allowed to flag the RBM Downscale and Rod Block alarm.
- Releases Rod movement switch so that the control rod stops 1 position before the insert limit unless the insert limit is 00.
- Initials Rod movement Sheet.
- Verifier, if available, Initials Rod movement sheet.
- Notifies the SS when they are out of the region of potential instabilities.
Note: Advise the STA to recommend inserting the current rod group to its insert limit.
- Directs the operator to insert the rods to the insert limit after consulting with the ST A.
Note; At Chief Examiner's direction, move on to the next Event Appendix 0 Required Operator Actions Form ES-O-2 II
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Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
4 Page 15 of 31 Event
Description:
"2B" Recirculation Pump ASD Cell will auto bypass I Time Position Applicant's Actions or Behavior ATC
- Inserts control rods per 34GO-OPS-065-0, starting with control rod Group 54.
- During rod insertion, rod steps will be performed in reverse sequential order, starting at the highest numbered step. (** rod steps are not required to be performed sequentially, but must be positioned to their RWM insert limit prior to inserting lower numbered groups).
- Selects Rod
- Places Control Rod movement switch to the IN position
- Verifies Rod moves using Rod display information and Rx and Generator power decreasing.
- If required, adjust 2CII-F003 to get 220 - 280 psid drive water dp.
(
ATC Note: RBM Downscale alarm may alarm during this movement due to the significant rod worth of these rods. It is allowed to flag the RBM Downscale and Rod Block alarm.
- Releases Rod movement switch so that the control rod stops 1 position before the insert limit unless the insert limit is 00.
- Initials Rod movement Sheet.
- Verifier, if available, Initials Rod movement sheet.
- Notifies the SS when they are out of the region of potential instabilities.
Note: Advise the STA to recommend inserting the current rod group to its insert limit.
- Directs the operator to insert the rods to the insert limit after consulting with the STA.
Note; At Chief Examiner's direction, move on to the next Event
Appendix D Required Operator Actions Form ES-D-2
,~
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Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
5 Page 16 of 31 Event
Description:
Recirc Pump '2B' will experience high vibration Time Position Applicant's Actions or Behavior Simulator Operator At Chief Examiner's direction, press (RB-S) to activate:
- mfB31 41B, Recirc Pump B High Vibration All
- Receives 602-204, "Recirc Pump B High Vibration" alarm SRO
- Directs operator to enter 602-204 ATe
- Enters 602-104
- Depresses the Hi vibration reset pushbutton and determines that the alarm does not clear.
- Notifies the SS that the vibration alarm did not clear.
- Directs the operator to reduce Rx power with Recirc per 34GO-OPS-005 and 34S0-B31-001-2, exceeding 10 MWE/minute if necessary.
- Reminds the operator that entry into the immediate exit region of the Power to Flow map is allowed.
- Notifies Plant Management, Load Dispatcher, and Engineering that the power increase has been halted pending investigation of Recirc Pump 2B high vibration condition.
Appendix 0 Required Operator Actions Form ES-O-2
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Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
5 Page 16 of 31 Event
Description:
Recirc Pump '2B' will experience high vibration I Time Position Applicant's Actions or Behavior Simulator Operator At Chief Examiner's direction, press (RB-S) to activate:
- mfB31_41B, Recirc Pump B High Vibration All
- Receives 602-204, "Recirc Pump B High Vibration" alarm SRO
- Directs operator to enter 602-204 ATe
- Enters 602-104
- Depresses the Hi vibration reset pushbutton and determines that the alarm does not clear.
- Notifies the SS that the vibration alarm did not clear.
- Directs the operator to reduce Rx power with Recirc per 34GO-OPS-005 and 34S0-B31-001-2, exceeding 10 MWE/minute if necessary.
- Reminds the operator that entry into the immediate exit region of the Power to Flow map is allowed.
- Notifies Plant Management, Load Dispatcher, and Engineering that the power increase has been halted pending investigation of Recirc Pump 2B high vibration condition.
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\\
Appendix 0 Required Operator Actions Form ES-D-2
~,
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
5 Page 17 of 31 Event
Description:
Recirc Pump '2B' will experience high vibration I Time Position Applicant's Actions or Behavior I
- Enters the following procedures
- 34S0-B31-00 1-2, "Recirculation System"
- lAW 34S0-B31-001-2, the ATC decreases Recirc pump speed by depressing the Slow, Medium or Fast LOWER pushbuttons on the Master or Individual controls.
- Monitors power decrease by observing APRM and generator output indications.
- Stops power reduction periodically and depresses the High vibration reset pushbutton.
- The alarm will not remain clear until the pump is tripped.
- Continues to decrease Recirc pump speed until minimum
- Notifies SS when B Recirc Pump is at minimum.
- Directs the operator to shutdown the B ASD lAW 34S0-B31-001-2 section 7.2.1.4.
- Place ASD B control switch 2B31-S002B to Pull to Lock or depresses the ASD B Shutdown pushbutton on panel 2H11-P602.
- Enters 34AB-B31-001-2, Reactor Recirculation Pump(s) Trip, Recirc Loops Flow Mismatch, Or ASD Cell Bypass for single Recirc pump trip.
Appendix D Required Operator Actions Form ES-D-2 I ~
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
5 Page 17 of 31 Event
Description:
Recirc Pump '2B' will experience high vibration I Time Position Applicant's Actions or Behavior I
- Enters the following procedures
- 34S0-B3l-00 1-2, "Recirculation System"
- IA W 34S0-B31-001-2, the ATC decreases Recirc pump speed by depressing the Slow, Medium or Fast LOWER pushbuttons on the Master or Individual controls.
- Monitors power decrease by observing APRM and generator output indications.
- Stops power reduction periodically and depresses the High vibration reset pushbutton.
- The alarm will not remain clear until the pump is tripped.
- Continues to decrease Recirc pump speed until minimum
- Notifies SS when B Recirc Pump is at minimum.
(
reducing Recirc pump speed.
- Directs the operator to shutdown the B ASD IA W 34S0-B3l-00l-2 section 7.2.1.4.
- Place ASD B control switch 2B31-S002B to Pull to Lock or depresses the ASD B Shutdown pushbutton on pane12H11-P602.
- Enters 34AB-B3l-001-2, Reactor Recirculation Pump(s) Trip, Recirc Loops Flow Mismatch, Or ASD Cell Bypass for single Recirc pump trip.
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Appendix D Required Operator Actions Form ES-D-2
'~ Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
5 Page 18 of 31 Event
Description:
Recirc Pump '2B' will experience high vibration Time Position Applicant's Actions or Behavior I
- Has the operator determine if the plant is in the analyzed region of the Power to Flow map.
ATe
- Determines that the plant is in the immediate exit region of the Power to Flow map.
The intent is NOT to watch the crew again insert controls rods to exit the Immediate Exit Region. The intent is to move on to the next event.
Note; At Chief Examiner's direction, move on to the next Event Appendix 0 Required Operator Actions Form ES-O-2
'\\ Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
5 Page 18 of 31 Event
Description:
Recirc Pump '2B' will experience high vibration Time Position Applicant's Actions or Behavior SRO
- Has the operator determine if the plant is in the analyzed region of the Power to Flow map.
ATe
- Determines that the plant is in the immediate exit region of the Power to Flow map.
The intent is NOT to watch the crew again insert controls rods to exit the
(
Immediate Exit Region. The intent is to move on to the next event.
Note; At Chief Examiner's direction, move on to the next Event
Appendix D Required Operator Actions Form ES-D-2 II Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
6 Page 19 of 31 Event
Description:
HPCI Room Fire I Time Position Applicant's Actions or Behavior Simulator Operator At Chief Examiner's direction, NOTIFY the Shift Supervisor, as the SO on rounds, that smoke is coming from the Unit 2 HPCI room and you cannot see what is actually burning. You are leaving the area.
- Directs BOP to enter 34AB-X43-001-2, 'Fire Procedure' and make the announcement.
- Enters 34AB-X43-001-2, 'Fire Procedure' and performs the following:
- Sounds the fire alarm (SIREN) over the plant P A system
- Notifies Rad Waste Control room that Reactor Building floor drain sump pumps are in Automatic
- Notifies Health Physics to respond to the fire area
- Transitions to section 8.0 for Fire in 'Reactor Bldg.'
- Stops the following equipment at Panels 2H11-P654 & P657:
- 2T41-C001A, Rx Bldg Supply Fan.
- 2T41-C001B, Rx Bldg Supply Fan.
- 2T41-C007A, Rx Bldg Exhaust Fan.
- 2T4l-C007B, Rx Bldg Exhaust Fan.
- 2T4l-C002A, Refuel FIr Vent Supply Fan.
- 2T4l-C002B, Refuel FIr Vent Supply Fan.
- 2T41-C005A, Refuel FIr Vent Exh Fan.
- 2T41-C005B, Refuel FIr Vent Exh Fan.
Simulator Operator Wait 2 minutes and NOTIFY the Shift Supervisor, as the Fire Brigade Leader, to place HPCI Aux Oil pump in PTL-Off to prevent HPCI from starting while Fire Brigade is in the HPCI room.
Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
6 Page 19 of 31 Event
Description:
HPCI Room Fire I Time Position Applicant's Actions or Behavior I
Simulator Operator At Chief Examiner's direction, NOTIFY the Shift Supervisor, as the SO on rounds, that smoke is coming from the Unit 2 HPCI room and you cannot see what is actually burning. You are leaving the area.
- Directs BOP to enter 34AB-X43-001-2, 'Fire Procedure' and make the announcement.
- Enters 34AB-X43-001-2, 'Fire Procedure' and performs the following:
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\\
- Sounds the fire alarm (SIREN) over the plant P A system
- Notifies Rad Waste Control room that Reactor Building floor drain sump pumps are in Automatic
- Notifies Health Physics to respond to the fire area
- Transitions to section 8.0 for Fire in 'Reactor Bldg.'
- Stops the following equipment at Panels 2H11-P654 & P657:
- 2T41-COOlA, Rx Bldg Supply Fan.
- 2T41-C001B, Rx Bldg Supply Fan.
- 2T41-C007A, Rx Bldg Exhaust Fan.
- 2T41-C007B, Rx Bldg Exhaust Fan.
- 2T41-C002A, Refuel FIr Vent Supply Fan.
- 2T41-C002B, Refuel FIr Vent Supply Fan.
- 2T41-C005A, Refuel FIr Vent Exh Fan.
- 2T41-C005B, Refuel FIr Vent Exh Fan.
Simulator Operator Wait 2 minutes and NOTIFY the Shift Supervisor, as the Fire Brigade Leader,
(
to place HPCI Aux Oil pump in PTL-Off to prevent HPCI from starting while Fire Brigade is in the HPCI room.
Appendix D Required Operator Actions Form ES-D-2 I
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
6 Page 20 of 31 Event
Description:
HPCI Room Fire I Time Position Applicant's Actions or Behavior I
- Transitions to section 8.5 for Fire in 'South Half of Reactor Bldg.'
- Transitions to section 8.5.6 for Fire in 'HPCI Room'
- Places 2T4I-B005A HPCI Pump Rm Cooler in Off, P657.
- Places 2T4I-B005B HPCI Pump Rm Cooler in Off, P654.
- Closes the following HPCI Valves on P601
- Announces to the crew the fire is out.
- As time allows, Directs the operator to leave the HPCI Aux oil pump in PTLOff
- Refers to TS for HPCI inop
- 3.5.1 ECCS Operating Enters a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> RAS per TS 3.5.1.C.I to verify by admin means RCIC is operable and per TS 3.5.1.C.2 to restore HPCI to operable status within 14 days.
Simulator operator, proceed to the next event at the Chief Examiner's direction Appendix 0 Required Operator Actions Form ES-O-2 II Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
6 Page 20 of 31 Event
Description:
HPCI Room Fire Time Position Applicant's Actions or Behavior BOP
- Transitions to section 8.5 for Fire in 'South Half of Reactor Bldg.'
- Transitions to section 8.5.6 for Fire in 'HPCI Room'
- Places 2T41-B005A HPCI Pump Rm Cooler in Off, P657.
- Places 2T41-B005B HPCI Pump Rm Cooler in Off, P654.
- Closes the following HPCI Valves on P601
(
Simulator Operator Wait 5 minutes and NOTIFY the Shift Supervisor, that the fire in the HPCI room is OUT. A storage locker under the stairwell was onfire. We put out the fire without spraying water on any HPCI components.
- Announces to the crew the fire is out.
- As time allows, Directs the operator to leave the HPCI Aux oil pump in PTLOff
- Refers to TS for HPCI inop
- 3.5.1 ECCS Operating Enters a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> RAS per TS 3.5.1.C.l to verify by admin means RCIC is operable and per TS 3.5.1.C.2 to restore HPCI to operable status within 14 days.
Simulator operator, proceed to the next event at the Chief Examiner's
(
direction
Appendix D Required Operator Actions Form ES-D-2
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Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
7 Page 21 of 31 Event
Description:
Circ Water Leak causing Con Bay Flooding Time Position Applicant's Actions or Behavior Simulator Operator At Chief Examiner's direction, press (RB-7) to activate:
- mfN71_71, Circulation Water System Leak (0 - 100, 00 gpm)
Simulator Operator After 2 minutes notify the SS, that as Unit 2 Inside rounds, there is water coming out from under the Con Bay door on the 112' elevation. (It will take approximately 3 minutes to receive the Condenser Room Flooding alarm.)
All
- Recognizes that Condenser Water Box A R602A dp is approaching O.
- As time allows, dispatches a SO to locally investigate the reduced Circ Water dp and for a possible leak.
- When 650-164, "Condenser Room Flooding" alarm is received, directs the ATC enter 34AB-C71-00l-2, Scram Procedure, and scram the reactor.
- Assigns the ATC to perform RC-1.
- Assigns the BOP operator to perform RC-2 and RC-3.
- Assigns a RWL band between 3" and 50" Appendix 0 Required Operator Actions Form ES-O-2
~
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
7 Page 21 of 31 Event
Description:
Circ Water Leak: causing Con Bay Flooding Time Position Applicant's Actions or Behavior I
Simulator Operator At Chief Examiner's direction, press (RB-7) to activate:
- mfN71_71,Circulation Water System Leak (0-100,00 gpm)
Simulator Operator After 2 minutes notify the SS, that as Unit 2 Inside rounds, there is water coming out from under the Con Bay door on the 112' elevation. (It will take approximately 3 minutes to receive the Condenser Room Flooding alarm.)
All
- Recognizes that Condenser Water Box A R602A dp is approaching O.
(
- As time allows, dispatches a SO to locally investigate the reduced Circ Water dp and for a possible leak:.
- When 650-164, "Condenser Room Flooding" alarm is received, directs the ATC enter 34AB-C71-001-2, Scram Procedure, and scram the reactor.
- Assigns the A TC to perform RC-1.
- Assigns the BOP operator to perform RC-2 and RC-3.
- Assigns a RWL band between 3" and 50"
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Appendix D Required Operator Actions Form ES-D-2 I
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
7 Page 22 of 31 Event
Description:
Circ Water Leak causing Con Bay Flooding I Time Position Applicant's Actions or Behavior I
- Performs RC-l consisting of:
- Inserts a manual scram.
- Places the mode switch to shutdown.
- Notifies SS of rod position check.
- Places SDV isolation valve switch to "isolate" & confirms closed.
- If not tripped, places the Recirc pumps at minimum speed.
- Shifts recorders to read IRMS, when required.
- Ranges IRMS to bring reading on scale.
- Notifies the SS when the above actions are complete.
- Performs RC-2 actions consisting of:
- Confirms proper Level Control response:
- Checks ECCS Injection Systems and secure as necessary.
- Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value.
- IF set down does not auto function, then manually reduces FW Master Controller setpoint to approximately 9 inches.
Notifies MaintlI&C to investigate and repair.
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Appendix 0 Required Operator Actions Form ES-O-2 I
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
7 Page 22 of 31 Event
Description:
Circ Water Leak causing Con Bay Flooding I Time Position Applicant's Actions or Behavior ATC
- Performs RC-1 consisting of:
- Inserts a manual scram.
- Places the mode switch to shutdown.
- Notifies SS of rod position check.
- Places SDV isolation valve switch to "isolate" & confirms closed.
- If not tripped, places the Recirc pumps at minimum speed.
- Shifts recorders to read IRMS, when required.
- Ranges IRMS to bring reading on scale.
- Notifies the SS when the above actions are complete.
(
- Performs RC-2 actions consisting of:
- Confirms proper Level Control response:
- Checks ECCS Injection Systems and secure as necessary.
- Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value.
- IF set down does not auto function, then manually reduces FW Master Controller setpoint to approximately 9 inches.
Notifies MaintlI&C to investigate and repair.
Appendix 0 Required Operator Actions Form ES-O-2 II Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
7 Page 23 of 31 Event
Description:
Circ Water Leak causing Con Bay Flooding Time Position Applicant's Actions or Behavior I
- When feed flow is less than the capacity of the S/U level control valve
(~ 1.5 mlbmlhr), then:
- Opens 2N21-F125.
- Closes 2N21-F11O.
- May attempt to start the CRD pumps
- Performs RC-3 consisting of:
- Monitor RPV pressure.
- Maintain RPV pressure between 1074 and 800 psig.
- Notify SS of pressure control system operation.
Simulator operator ensures ET-B21-10 & ET-B21-11 for deleting MSIV lights is ACTIVATED when the 2B21-F022B AND F028B is positioned to close.
All
- Recognizes the B MSL failed to isolate on low condenser vacuum and places both control switches for 2B21-F022B and F028B to close.
- Directs operator to place B MSL control switches, 2B21-F022B and F028B, to close and confirm valves indicates close.
Appendix 0 Required Operator Actions Form ES-O-2 I
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
7 Page 23 of 31 Event
Description:
Circ Water Leak causing Con Bay Flooding Time Position Applicant's Actions or Behavior I
- When feed flow is less than the capacity of the S/U level control valve
(~ 1.5 mlbrnlhr), then:
- Opens 2N21-F125.
- Closes 2N21-F11O.
- May attempt to start the CRD pumps
(
- Performs RC-3 consisting of:
- Monitor RPV pressure.
- Maintain RPV pressure between 1074 and 800 psig.
- Notify SS of pressure control system operation.
Simulator operator ensures ET-B21-10 & ET-B21-11 for deleting MSIV lights is ACTIVATED when the 2B21-F022B AND F028B is positioned to close.
All
- Recognizes the B MSL failed to isolate on low condenser vacuum and places both control switches for 2B21-F022B and F028B to close.
- Directs operator to place B MSL control switches, 2B21-F022B and F028B, to close and confirm valves indicates close.
Appendix D Required Operator Actions Form ES-D-2
~
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 24 of31 Event
Description:
'B' SRV fails open and remains partially open after fuses are pulled I Time Position Applicant's Actions or Behavior I
Simulator Operator After LLS is armed or when the B SRV is open, press (RB-8) to activate:
- mfB21_130B SRO
- Directs operator to enter 34AB-B21-003-2, "Failure of SafetylRelief valves".
- Determines that SRV "B" is open.
- Attempts to reset LLS as follows:
- Directs operator to pull the fuses for SRV "B".
- Enters 34AB-B21-003-2, Failure of SafetylRelief valves
- Dispatches an operator to pull the fuses for SRV "B".
Appendix D Required Operator Actions Form ES-D-2 I ~
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 24 of 31 Event
Description:
'B' SRV fails open and remains partially open after fuses are pulled II Time Position Applicant's Actions or Behavior Simulator Operator After LLS is armed or when the B SRV is open, press (RB-8) to activate:
- mfB21_130B SRO
- Directs operator to enter 34AB-B2l-003-2, "Failure of SafetylRelief valves".
- Determines that SRV "B" is open.
- Attempts to reset LLS as follows:
- Directs operator to pull the fuses for SRV "B".
- Enters 34AB-B2l-003-2, Failure of SafetylRelief valves
- Dispatches an operator to pull the fuses for SRV "B".
Appendix D Required Operator Actions Form ES-D-2 I
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 25 of 31 Event
Description:
'B' SRV fails open and remains partially open after fuses are pulled Time Position Applicant's Actions or Behavior Simulator Operator-after 3 minutes, ENTER (RB-2) for leaking SRV Band ifB21_301 to pull the fuses for SRV B, THEN, notify the crew thefuses have been pulled for SRV "B".
- Confirms that SRV "B" is still partially open by monitoring:
- SRV tailpipe temperature stabilizing at value and not decreasing
- Torus Temp still increasing
- Torus level still increasing
Appendix 0 Required Operator Actions Form ES-O-2 I
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 25 of 31 Event
Description:
'B' SRV fails open and remains partially open after fuses are pulled Time Position Applicant's Actions or Behavior Simulator Operator-after 3 minutes, ENTER (RB-2) for leaking SRV Band ifB21_301 to pull the fuses for SRV B, THEN, notify the crew the fuses have been pulledfor SRV "B".
- Confirms that SRV "B" is still partially open by monitoring:
- SRV tailpipe temperature stabilizing at value and not decreasing
- Torus Temp still increasing
- Torus level still increasing
- Resets the SRV leak detection by placing the Leak Detection Logic A Reset keylock switch andlor Leak Detection Logic B Reset keylock
(
switch to Reset position and back to Normal position and confirm that the Amber SRV indicating lights have NOT Extinguished.
Appendix D Required Operator Actions Form ES-D-2
'. Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
9 Page 26 of 31 Event
Description:
RCIC 2E51-F008 isolation along with SULCV 2N21-FIll fails closed II Time Position Applicant's Actions or Behavior Simulator Operator At Chief Examiner's direction, press (RB-9) to activate:
- mfE51_113 RCIC isolation & mfN21_99 fails closed All
- The following alarms are received:
- RCIC Isolation Signal Logic A
- RCIC Steam Line Diff Press High
- RCIC Isolation Vlv F007IF008 Not Fully Open
NOTE: The operators may transition to inject with the condensatelFeedwater system prior to entering the following ARPs. The operators may enter different ARPs first. The following actions are for all four ARPs. The evaluator will have to determine which ARP has been entered to follow the correct set of actions.
Appendix 0 Required Operator Actions Form ES-O-2
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Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
9 Page 26 of 31 Event
Description:
RCIC 2E51-F008 isolation along with SULCV 2N21-Flll fails closed I Time Position Applicant's Actions or Behavior I
Simulator Operator At Chief Examiner's direction, press (RB-9) to activate:
- mfE51_113 RCIC isolation & mfN21_99 fails closed All
- The following alarms are received:
- RCIC Isolation Signal Logic A
- RCIC Steam Line Diff Press High
- RCIC Isolation Vlv F007/F008 Not Fully Open
NOTE: The operators may transition to inject with the condensatelFeedwater system prior to entering the following ARPs. The operators may enter different ARPs first. The following actions are for all four ARPs. The evaluator will have to determine which ARP has been entered to follow the correct set of actions.
Appendix D Required Operator Actions Form ES-D-2 II Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
9 Page 27 of 31 Event
Description:
RCIC 2E51-F008 isolation along with SULCV 2N21-F111 fails closed Time Position Applicant's Actions or Behavior BOP
- Enters ARP 602-302, for the RCIC Stearn Line Diff Press High annunciator and performs the following actions.
- Confirms 2E51-F008 is closed
- Closes 2E51-F007 (This valve does not have an isolation signal, but may be closed)
- Notifies the SS that RCIC has a HIGH stearn flow (stearn line dp) signal and that 2E51-N657A&B and 2E51-N660AlB at the ATTS panels provide inputs to this signal.
- Dispatches an operator to and requests maintenance help for determining the status of 2E51-N657 AlB and 2E51-N660AlB at the ATTS panels.
- Enters ARP 602-301, RCIC Turbine Trip
- Confirms 2E51-F524, Trip & Throttle Vlv, indicates CLOSED
- Confirms 2E51-F013, Pump Discharge Vlv, indicates CLOSED
- Confirms 2E51-F008, Stearn Supply Line Isol Vlv, is CLOSED.
(
II Appendix 0 Required Operator Actions Form ES-O-2 II Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
9 Page 27 of 31 Event
Description:
RCIC 2E51-F008 isolation along with SULCV 2N21-F111 fails closed Time Position Applicant's Actions or Behavior BOP
- Enters ARP 602-302, for the RCIC Steam Line Diff Press High annunciator and performs the following actions.
- Confirms 2E51-F008 is closed
- Closes 2E51-F007 (This valve does not have an isolation signal, but may be closed)
- Notifies the SS that RCIC has a HIGH steam flow (steam line dp) signal and that 2E51-N657A&B and 2E51-N660A/B at the ATTS panels provide inputs to this signal.
- Dispatches an operator to and requests maintenance help for
(
determining the status of2E51-N657A1B and 2E51-N660A/B at the ATTS panels.
- Enters ARP 602-301, RCIC Turbine Trip
- Confirms 2E51-F524, Trip & Throttle Vlv, indicates CLOSED
- Confirms 2E51-F013, Pump Discharge Vlv, indicates CLOSED
- Confirms 2E51-F008, Steam Supply Line Isol Vlv, is CLOSED.
(
\\
II
Appendix D Required Operator Actions Form ES-D-2
~
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
9 Page 28 of31 Event
Description:
RCIC 2E51-F008 isolation along with SULCV 2N21-Flll fails closed Time Position Applicant's Actions or Behavior I
- Confirms 2E51-F008, Steam Supply Line Isol Vlv, is CLOSED
- Determines that RCIC needs to be returned to standby line-up per 34S0-E51-001-2, RCIC System, when the isolation signal is cleared.
- The BOP recognizes the SULCV has failed closed.
- Performs the following to inject water into the reactor.
0 Throttles open 2N21-FIlO, and injects water into the reactor.
- Reports SULCV problem to the SS.
Critical Task - Aligns 2N21-F11 0 for vessel injection to maintain RWL greater than -155 inches.
Simulator Operator
- With Chief Examiners permission AND
- When reactor water is being controlled after reactor pressure is below the Condensate Booster pump discharge head, THEN II Terminate the scenario.
Appendix 0 Required Operator Actions Form ES-O-2
(
I ~
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
9 Page 28 of 31 Event
Description:
RCIC 2E51-F008 isolation along with SULCV 2N21-F111 fails closed Time Position Applicant's Actions or Behavior BOP
- Confirms 2E5l-F008, Steam Supply Line Isol Vlv, is CLOSED
- Determines that RCIC needs to be returned to standby line-up per 34S0-E5l-001-2, RCIC System, when the isolation signal is cleared.
- The BOP recognizes the SULCV has failed closed.
- Performs the following to inject water into the reactor.
0 Throttles open 2N21-FllO, and injects water into the reactor.
- Reports SULCV problem to the SS.
Critical Task - Aligns 2N21-Fll 0 for vessel injection to maintain RWL greater than -155 inches.
Simulator Operator
- With Chief Examiners permission AND
- When reactor water is being controlled after reactor pressure is below the Condensate Booster pump discharge head, THEN
(
II Terminate the scenario.
Page 29 of 31 AppendixD Scenario Outline Form ES-D-1 NRC Draft
.iacility:
E. I Hatch Scenario No.:
5-04 Op-Test No.:
2009-302 Examiners:
Operators:
SRO RO BOP Initiating Conditions:
Turnover Summary:
Unit 2 is operating at approximately 90% RTP.
Raise reactor power to 92% then raise pressure set lAW 34GO-OPS-005-2.
After pressure adjustment, raise reactor power to 95%.
Event 1: Perform 34IT-N30-001-2, "Main Turbine & Auxiliaries Weekly Test" surveillance for Power-Load-Unbalance only.
Event 2: Increase reactor power to 95% using Recirc and adjusting DEHC pressure set to achieve reactor pressure> 1 025 psig.
Event 3: Component; Reactor Building Exhaust fan failure with the Standby Exhaust fan failing to start. The operator takes manual control to place the Standby Exhaust fan or SBGT in service to re-establish the required Reactor Building DP. (Critical Task).
Event 4: Reactivity/ComponentlTS; A "2A" Recirculation Pump ASD Cell will auto bypass.
This will result in a flow and power reduction. The ASD Cell Bypass and Recirc flow mismatch will be addressed by annunciator response procedures and an abnormal procedure. The SS will address TS for Recirc flow mismatch. The plant will be operating in the Immediate Exit Region of the Power-to-Flow map. The ATC operator will insert control rods or increase Recirc Pump speed to exit the Immediate Exit Region of the P/F map.
Event 5: ComponentlTS; Recirc Pump '2A' will experience high vibration requiring reducing reactor power in an attempt to clear the alarm. Alarm remains in until pump is tripped. The SS addresses TS for an inoperable Recirc pump. The plant will be operating in the Immediate Exit Region of the Power-to-Flow map. The ATC operator will insert control rods to exit the Immediate Exit Region of the P/F map.
Event 6: ComponentlTS; HPCI Room fire.
Event 7. Major; Condenser Bay Flooding is received which de-energizes 4160V 2A & 2B, requiring the operator to insert a manual scram. HPCI governor valve will not open to provide sufficient steam to the HPCI turbine. B MSL fails to automatically close; manual works.
Event 8: Component; SRV 'B' fails open and remains partially open after the fuses are pulled.
Event 9: Component; RCIC isolates due to false high flow signal and the Startup Level Control Valve 2N21-Flll will fail in the closed direction prohibiting Feedwater flow for injection. The operator will take manual actions to maintain RWL above TAF (-155") (Critical Task)
(
Page 29 of 31 Appendix D Scenario Outline Form ES-D-1 NRC Draft
.iacility:
E. I Hatch Scenario No.:
5-04 Op-Test No.:
2009-302 Examiners:
Operators:
~~
Turnover Summary:
Unit 2 is operating at approximately 90% RTP.
Raise reactor power to 92% then raise pressure set lAW 34GO-OPS-005-2.
After pressure adjustment, raise reactor power to 95%.
Event 1: Perform 34IT-N30-001-2, "Main Turbine & Auxiliaries Weekly Test" surveillance for Power-Load-Unbalance only.
Event 2: Increase reactor power to 95% using Recirc and adjusting DEHC pressure set to achieve reactor pressure> 1 025 psig.
Event 3: Component; Reactor Building Exhaust fan failure with the Standby Exhaust fan failing to start. The operator takes manual control to place the Standby Exhaust fan or SBGT in service to re-establish the required Reactor Building DP. (Critical Task).
Event 4: Reactivity/ComponentlTS; A "2A" Recirculation Pump ASD Cell will auto bypass.
This will result in a flow and power reduction. The ASD Cell Bypass and Recirc flow mismatch will be addressed by annunciator response procedures and an abnormal procedure. The SS will address TS for Recirc flow mismatch. The plant will be operating in the Immediate Exit Region of the Power-to-Flow map. The ATC operator will insert control rods or increase Recirc Pump speed to exit the Immediate Exit Region of the P/F map.
Event 5: ComponentlTS; Recirc Pump '2A' will experience high vibration requiring reducing reactor power in an attempt to clear the alarm. Alarm remains in until pump is tripped. The SS addresses TS for an inoperable Recirc pump. The plant will be operating in the Immediate Exit Region of the Power-to-Flow map. The ATC operator will insert control rods to exit the Immediate Exit Region of the P/F map.
Event 6: ComponentlTS; HPCI Room fire.
Event 7. Major; Condenser Bay Flooding is received which de-energizes 4160V 2A & 2B, requiring the operator to insert a manual scram. HPCI governor valve will not open to provide sufficient steam to the HPCI turbine. B MSL fails to automatically close; manual works.
Event 8: Component; SRV 'B' fails open and remains partially open after the fuses are pulled.
Event 9: Component; RCIC isolates due to false high flow signal and the Startup Level Control Valve 2N21-Flll will fail in the closed direction prohibiting Feedwater flow for injection. The operator will take manual actions to maintain RWL above TAF (-155") (Critical Task)
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Page 30 of31 Critical Tasks NRC Draft Facility:
E. I Hatch Scenario No.:
5-04 Op-Test No.:
2009-302 Critical Tasks
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
Manually start the standby reactor building exhaust fan or SBGT to return Reactor Building DP to a more negative value. (Event 3)
Throttle open the 2N21-FIlO Startup Level Control Valve and use the CondensatelFeedwater system to maintain RWL above TAF (-ISS"). (Event 9)
ES 301-4 Attributes Required Actual Items Total Malfunctions 5-8 7
- 1. Reactor Building Exhaust fan failure. (Event 3)
- 2. Recirculation Pump "2B" ASD Cell bypass.
(Event 4)
- 3. Recirc Pump '2B' high vibration (Event 5)
- 4. HPCI Room fire (Event 6)
- 5. Condenser Bay Flooding (Event 7)
- 6. SRV 'B' OPENSlleaks partially open (Event 8)
Malfunctions After 1-2 2
- 1. SRV 'B' OPENSlleaks partially open (Event 8)
EOPEntry
Abnormal Events 2-4 4
- 1. Reactor Building Exhaust fan failure. (Event 3)
- 2. Recirculation Pump "2B" ASD Cell bypass.
(Event 4)
- 3. HPCI Room fire (Event 6)
- 4. Condenser Bay Flooding (Event 7)
Major Transients 1-2 1
- 1. Condenser Bay Flooding (Event 7)
EOPs entered, 1-2 2
- 1. EOP RC (Non-ATWS) requiring substantive
- 2. EOPPC actions EOPs contingencies 0-2 0
requiring substantive actions Critical Tasks 2-3 2
- 1. Manually start the standby reactor building exhaust fan or SBGT (Event 3)
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Page 30 of 31 Critical Tasks NRC Draft
~"'acility:
E. I Hatch Scenario No.:
5-04 Op-Test No.:
2009-302 Critical Tasks
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
Manually start the standby reactor building exhaust fan or SBGT to return Reactor Building DP to a more negative value. (Event 3)
Throttle open the 2N21-FIlO Startup Level Control Valve and use the CondensatelFeedwater system to maintain RWL above TAP (-ISS"). (Event 9)
ES 301-4 Attributes Required Actual Items Total Malfunctions 5-8 7
- 1. Reactor Building Exhaust fan failure. (Event 3)
- 2. Recirculation Pump "2B" ASD Cell bypass.
(Event 4)
- 3. Recirc Pump '2B' high vibration (Event 5)
- 4. HPCI Room fire (Event 6)
- 5. Condenser Bay Flooding (Event 7)
- 6. SRV 'B' OPENSlleaks partially open (Event 8)
Malfunctions After 1-2 2
- 1. SRV 'B' OPENS/leaks partially open (Event 8)
EOP Entry
Abnormal Events 2-4 4
- 1. Reactor Building Exhaust fan failure. (Event 3)
- 2. Recirculation Pump "2B" ASD Cell bypass.
(Event 4)
- 3. HPCI Room fire (Event 6)
- 4. Condenser Bay Flooding (Event 7)
Major Transients 1-2 1
- 1. Condenser Bay Flooding (Event 7)
EOPs entered, 1-2 2
- 1. EOP RC (Non-ATWS) requiring substantive
- 2. EOPPC actions EOPs contingencies 0-2 0
requiring substantive actions Critical Tasks 2-3 2
- 1. Manually start the standby reactor building exhaust fan or SBGT (Event 3)
HLT 5 NRC Operating Exam Scenario 4 SHIFT TURNOVER Power:
100 % power Activities in progress:
None Power:
92.5% power with RPV pressure at 1020 psig The following equipment is None inoperable:
Scheduled evolutions:
Surveillances due this shift:
Active clearances:
Rod Configuration:
Have the BOP operator perform 34IT-N30-00l-2, "Main Turbine & Auxiliaries Weekly Test", PowerlLoad Unbalance Test section 7.2 only.
After the Turbine test is complete, have the OATe Increase Reactor Pressure to 1025 psig (Ops Management has determined that Attachment 3 of 34GO-OPS-005-2 is NOT required.), then increase Reactor power to 95% using the Rx Recirc system, with a 10 MWe limit on power change rate.
34IT-N30-001-2, "Main Turbine & Auxiliaries Weekly Test",
PowerlLoad Unbalance Test section 7.2 only.
None SeeRWM
(
HLT 5 NRC Operating Exam Scenario 4 SHIFT TURNOVER UNIT 1 S'FATUS Power:
100 % power Activities in progress:
None Power:
92.5% power with RPV pressure at 1020 psig The following equipment is None inoperable:
Scheduled evolutions:
Surveillances due this shift:
Active clearances:
Rod Configuration:
Have the BOP operator perform 34IT-N30-00l-2, "Main Turbine & Auxiliaries Weekly Test", PowerlLoad Unbalance Test section 7.2 only.
After the Turbine test is complete, have the OA TC Increase Reactor Pressure to 1025 psig COps Management has determined that Attachment 3 of 34GO-OPS-005-2 is NOT required.), then increase Reactor power to 95% using the Rx Recirc system, with a 10 MWe limit on power change rate.
34IT-N30-00l-2, "Main Turbine & Auxiliaries Weekly Test",
PowerlLoad Unbalance Test section 7.2 only.
None SeeRWM
Page 1 of 21 AppendixD Scenario Outline Form ES*D*1 Draft Facility:
E. I Hatch Scenario No.:
5*05 Op* Test No.:
2009*302 Examiners:
Operators:
SRO RO BOP Initial Conditions. Unit 2 is operating at approximately 5% power preparing to remove the Mechanical Vacuum Pump from service per step 7.3.26,o~ 34GO-OPS-OOI-2.
Turnover: Continue with startup IA W 34GO-OPS-001-2. RWM is inoperable and a second licensed operator is available for rod movement verifications.
Event Malf. No.
IEvent Event No.
Type*
Descrl:l!tion 1
aoN22_FOO7R2 IN (BOP) Secure Mechanical Vacuum Pump per 34S0-N61-001-2 with suction Ivalve 2N22-F007 failing to full close 2
~/A
~ (ATC) Pull control rods to continue Startup to - 8% power and raise pressure set fwm 915 to 920 psig~
3 mfC12_23 26-23 C (ATC) Control Rod (pick one from pull sequence) uncoupled and allowed to rrS (SRO) Irecouple per Annunciator Response Procedure.
14-mfN33_154 C (BOP) Turbine Gland Seal Reg Fails Closed (must be in chest warming)
~
mfG3L207A C(BOP)
RWCU line breaks outside of Primary Containment. Must be manually svoG31071 TS (SRO) isolated (Critical Task), with failure of outboard isolation valve to ImfG31_52 close.
k>
svoB21220 C (ATC) SRV 2B21-F013G opens. The SRV will close after the ATC depresses loB2LF013GR2 he LLS Reset PB IA W section for electrically open. (Critical Task)
The SS will initiate a tracking RAS.
~
~21_247A M (ALL) Inadvertent Group 1 Isolation, MSIV closure mfB21 247B Scram Discharge Volume A TWS (Critical task)
~Cl1-211 8
ImfC4L240A 2 (ATC) SBLC Pump '2A' start failure
~C4L240B SBLC Pump '2B' start failure Iniect SBLC locally
~
diE51 S33 C (BOP) RCIC Manual Initiation PB fails
~5L109 RCICIHPCI fails to Auto start on low levellhi DW pressure. Manual
~L235A actions required for injection.
mfE41 235B (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 21 AppendixD Scenario Outline Form ES-D-l Draft Facility:
E. I Hatch Scenario No.:
5-05 Op-Test No.:
2009-302 Examiners:
Operators:
SRO RO BOP Initial Conditions. Unit 2 is operating at approximately 5% power preparing to remove the Mechanical Vacuum Pump from service per step 7.3.26,o~ 34GO-OPS-001-2.
Turnover: Continue with startup lAW 34GO-OPS-001-2. RWM is inoperable and a second licensed operator is available for rod movement verifications.
Event Malf. No.
IEvent Event No.
Type*
Description 1
loN22_FOO7R2 N (BOP) Secure Mechanical Vacuum Pump per 34S0-N61-001-2 with suction valve 2N22-F007 failing to full close 2
N/A R (ATC) Pull control rods to continue Startup to - 8% power and raise pressure set fmm 915 to 920 psig.
3 mfC12_2326-23 C (ATC) Control Rod (pick one from pull sequence) uncoupled and allowed to
(
TS (SRO) Irecouple per Annunciator Response Procedure.
j4 mfN33_154 C (BOP) Turbine Gland Seal Reg Fails Closed (must be in chest warming) 5 mfG3L207A C(BOP)
RWCU line breaks outside of Primary Containment. Must be manually svoG31071 TS (SRO) isolated (Critical Task), with failure of outboard isolation valve to mfG3L52 close.
6 svoB21220 C (ATC) SRV 2B21-F013G opens. The SRV will close after the ATC depresses loB2LF013GR2 the LLS Reset PB lAW section for electrically open. (Critical Task)
The SS will initiate a tracking RAS.
7 WS21_247A M (ALL) Inadvertent Group 1 Isolation, MSN closure mfB21_247B Scram Discharge Volume ATWS (Critical task) mfC11 211 8
mfC4L240A C (ATC) SBLC Pump '2A' start failure mfC4L240B SBLC Pump '2B' start failure Inject SBLC locally 9
diE51_S33 C (BOP) RCIC Manual Initiation PB fails mfE51_109 RCICIHPCI fails to Auto start on low level/hi DW pressure. Manual mfE41_235A actions required for injection.
mfE41 235B (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix 0 Required Operator Actions Form ES-O-2 II Op-Test No.: 2009-302 Scenario No.:
5-05 Event No.:
1 Page 2 of21 Event
Description:
Remove Mechanical Vacuum Pump from service with valve failure Time Position Applicant's Actions or Behavior BOP Removes MVP from service:
- Confirms 2N22-FOlO Vacuum Pump Disch Vlv CLOSED
- Recognizes 2N22-F007 Vacuum Pump Suction Vlv did NOT fully close
- Sends an SO to:
0 confirm the seal pump stops 0
Close 2P21-F021 Makeup Valve 0
Investigate failure of N22-F007 to close Simulator Operator: After the SO is sent to the MVP, wait 2 minutes and DELETE loN22_F007R2 and report thefollowing:
- 2N22-F007 was manually closed and you will write a CR and Work Order for it
- The seal pump is stopped
Appendix 0 Required Operator Actions Form ES-D-2
'I Op-Test No.: 2009-302 Scenario No.:
5-05 Event No.:
1 Page 2 of 21 Event
Description:
Remove Mechanical Vacuum Pump from service with valve failure Time Position Applicant's Actions or Behavior I
- Confirms 2N22-FOlO Vacuum Pump Disch Vlv CLOSED
- Recognizes 2N22-F007 Vacuum Pump Suction Vlv did NOT fully close
- Sends an SO to:
0 confirm the seal pump stops 0
Close 2P21-F021 Makeup Valve 0
Investigate failure of N22-F007 to close Simulator Operator: After the SO is sent to the MVP, wait 2 minutes and DELETE loN22_F007R2 and report the following:
- 2N22-F007 was manually closed and you will write a CR and Work Order for it
- The seal pump is stopped
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-05 Event No.:
2 Page 3 of 21 Event
Description:
Pull control rods to - 8% power, raise pressure set to 920 psig and transfer the reactor mode switch to run Time Position Applicant's Actions or Behavior I
Note: lAW 34GO-OPS-00l -2, Attachment 15, the maximum increase above 500 psig is < 1.6 psig/min due to SRV leakage considerations.
SRO Directs the ATC to increase reactor pressure to 920 psig using ERC pressure set.
ATC Enters 34GO-OPS-00l-2, 'Plant Startup', at step 7.4.1 and at the DERC panel computer, performs the following steps:
Selects the I Control I ~ I psi-load I screen Intermittently uses (Clicks) the I Raise I button to increase reactor pressure to 920 psig. (This will take approx. 4 minutes.)
Notifies the SS that Rx pressure is at 920 psig.
BOP Notifies Lab Foreman to take required samples for power operation.
II Appendix D Required Operator Actions Form ES-D-2 I,
Op-Test No.: 2009-302 Scenario No.:
5-05 Event No.:
2 Page 3 of 21
(
Event
Description:
Pull control rods to - 8% power, raise pressure set to 920 psig and transfer the reactor mode switch to run Time Position Applicant's Actions or Behavior I
Note: lAW 34GO-OPS-001 -2, Attachment 15, the maximum increase above 500 psig is < 1.6 psig/min due to SRV leakage considerations.
SRO Directs the A TC to increase reactor pressure to 920 psig using ERC pressure set.
ATC Enters 34GO-OPS-001-2, 'Plant Startup', at step 7.4.1 and at the DERC panel computer, performs the following steps:
Selects the I Control I ~ I psi-load I screen
(
Intermittently uses (Clicks) the I Raise I button to increase reactor pressure to 920 psig. (This will take approx. 4 minutes.)
Notifies the SS that Rx pressure is at 920 psig.
BOP Notifies Lab Foreman to take required samples for power operation.
(
II
Appendix D Required Operator Actions Form ES-D-2 II Op-Test No.: 2009-302 Scenario No.:
5-05 Event No.:
2 Page 4 of21 Event
Description:
Pull control rods to - 8% power, raise pressure set to 920 psig and transfer the reactor mode switch to run II Time Position Applicant's Actions or Behavior I
Note:
- When asked, tell the operator that you are the second licensed operator and peer checker.
- When the operator selects a rod, as peer checker state the rod number (e.g. 22-23) and the operator will state "/ agree".
- For other communications the operator makes (e.g. stating where the rod is to be moved to), as peer checker, state "/ agree".
- Withdraws the control rods within a step to the withdraw limit
- Initials for control rod withdrawal
- Dates for control rod withdrawal
- If the rod is a position 48 performs a coupling check by:
- Apply a withdraw signal by placing the Rod Movement Control switch to the withdraw position.
- Confirm the withdraw logic actuates by illumination of the red withdraw light.
- Confirm the rod attempts to move by a momentary loss of the "48" position indication.
- Confirm the rod does NOT move beyond position 48.
- Confirm annunciator ROD OVERTRA VEL (603-248) is NOT received.
- Document the coupling check on a Control Rod Movement Sequence form Note; When control rod 26-23 is moved the rod will be uncoupled, which will start the next event.
- Stops control rod withdrawal when highest reading APRM is reading between 6%-7%.
II Appendix 0 Required Operator Actions Form ES-O-2 II
(
Op-Test No.: 2009-302 Scenario No.:
5-05 Event No.:
2 Page 4 of 21 Event
Description:
Pull control rods to - 8% power, raise pressure set to 920 psig and transfer the reactor mode switch to run Time Position Applicant's Actions or Behavior Note:
- When asked, tell the operator that you are the second licensed operator and peer checker.
- When the operator selects a rod, as peer checker state the rod number (e.g. 22-23) and the operator will state "I agree".
- For other communications the operator makes (e.g. stating where the rod is to be moved to), as peer checker, state "I agree".
- Withdraws the control rods within a step to the withdraw limit
- Initials for control rod withdrawal
- Dates for control rod withdrawal
- If the rod is a position 48 performs a coupling check by:
- Apply a withdraw signal by placing the Rod Movement Control switch to the withdraw position.
- Confirm the withdraw logic actuates by illumination of the red withdraw light.
- Confirm the rod attempts to move by a momentary loss of the "48" position indication.
- Confirm the rod does NOT move beyond position 48.
- Confirm annunciator ROD OVERTRA VEL (603-248) is NOT received.
- Document the coupling check on a Control Rod Movement Sequence form Note; When control rod 26-23 is moved the rod will be uncoupled, which will start the next event.
- Stops control rod withdrawal when highest reading APRM is reading between 6%-7%.
(
II
Appendix D Required Operator Actions Form ES-D-2 (I
Op-Test No.: 2009-302 Scenario No.:
5-05 Event No.:
3 Page 5 of21 Event
Description:
Control rod uncoupled when moved Time Position Applicant's Actions or Behavior ATC
- Enters the following alarm procedures:
- 603-248, 'Rod Overtravel'
- 603-247, 'Rod Drift'
- Determines controlrod 26-23 is the affected rod
- Notifies the SS Simulator Operator: If contacted as REIManagement about determining if the control rod is uncoupled, inform the operator that it has been determined the control rod IS uncoupled.
Simulator Operator: After the operator inserts the rod, delete the uncoupled rod malfunction mjC12 23 26-23.
- Attempt to recouple the rod by moving in not more than 3 notches
- Withdraw the rod and confirm the rod is coupled by performing a coupling check
- Notifies the SS of the Tech Spec 3.1.3 and that the rod is now coupled
- Resets the Rod Drift alarm Note: Due to the short period of time the rod will be inoperable the SS may not declare that the rod was inoperable during the scenario.
Simulator Operator: For conservatism, the SS may still consider the rod inoperable even though coupled, and stop the startup. With Chief Examiner approval, call as the Shift Manager and inform the SS that Licensing and Engineering agree that the rod is operable.
SRO Reviews Tech Spec 3.1.3 and determines the rod was inoperable requiring it to be fully inserted within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and disarmed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> but is now operable.
Simulator Operator, at the direction of the Chief Examiner, proceed to next event.
Appendix D Required Operator Actions Form ES-D-2
'I Op-Test No.: 2009-302 Scenario No.:
5-05 Event No.:
3 Page 5 of 21 Event
Description:
Control rod uncoupled when moved Time Position Applicant's Actions or Behavior I
- Enters the following alarm procedures:
- 603-248, 'Rod Overtravel'
- 603-247, 'Rod Drift'
- Determines control' rod 26-23 is the affected rod
- Notifies the SS Simulator Operator: If contacted as REI Management about determining if the control rod is uncoupled, inform the operator that it has been determined the control rod IS uncoupled.
Simulator Operator: After the operator inserts the rod, delete the uncoupled rod malfunction mfC12 23 26-23.
(
- Attempt to recouple the rod by moving in not more than 3 notches
- Withdraw the rod and confirm the rod is coupled by performing a coupling check
- Notifies the SS of the Tech Spec 3.1.3 and that the rod is now coupled
- Resets the Rod Drift alarm Note: Due to the short period of time the rod will be inoperable the SS may not declare that the rod was inoperable during the scenario.
Simulator Operator: For conservatism, the SS may still consider the rod inoperable even though coupled, and stop the startup. With Chief Examiner approval, call as the Shift Manager and inform the SS that Licensing and Engineering agree that the rod is operable.
SRO Reviews Tech Spec 3.1.3 and determines the rod was inoperable requiring it to be fully inserted within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and disarmed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> but is now operable.
(
Simulator Operator, at the direction of the Chief Examiner, proceed to next event.
Appendix D Required Operator Actions Form ES-D-2
'I Op-Test No.: 2009-302 Scenario No.:
5-05 Event No.:
4 Page 6 of21 Event
Description:
Main Turbine Gland Seal Regulator valve fails closed Time Position Applicant's Actions or Behavior I
Simulator Operator: At the direction of the Chief Examiner, ENTER malfunction mfN33_154 (RB-4).
Note: If the F004 valve is not opened, it takes approximately 2.5 minutes for the turbine to trip on low vacuum.
ALL Recognize 650-125, 'Steam Seal Press Low' annunciator BOP Responds to 650-125, 'Steam Seal Press Low' annunciator
- Confirms 2N33-R601A, Steam Seal Hdr Pressure Indicator, is below 1.5 psig, panel 2H11-P650.
- Confirms OPEN 2N33-F003, Steam Seal Main Steam Feed Vlv.
- Confirms CLOSED 2N33-FOO5, Unloading Bypass Vlv.
- Confirms CLOSED 2N33-F008, Aux Steam Feed Vlv.
- Sends an SO to the Steam Seal Feed Valve Controller to confirm> 20 #
Air Inlet Pressure AND < 15 # Air Outlet Pressure.
Simulator Operator: If sent as the SO to check on Steam Seal Feed Valve Controller air pressure, wait 2 minutes and report air inlet is > 20 psig and air outlet is 0.5 psig.
Simulator Operator, at the direction of the Chief Examiner, proceed to next event.
Appendix 0 Required Operator Actions Form ES-O-2 II Op-Test No.: 2009-302 Scenario No.:
5-05 Event No.:
4 Page 6 of 21 Event
Description:
Main Turbine Gland Seal Regulator valve fails closed I Time Position Applicant's Actions or Behavior Simulator Operator: At the direction of the Chief Examiner, ENTER malfunction mjN33_154 (RB-4).
Note: If the F004 valve is not opened, it takes approximately 2.5 minutes for the turbine to trip on low vacuum.
ALL Recognize 650-125, 'Steam Seal Press Low' annunciator BOP Responds to 650-125, 'Steam Seal Press Low' annunciator
- Confirms 2N33-R601A, Steam Seal Hdr Pressure fudicator, is below 1.5 psig, panel 2Hll-P650.
- Confirms OPEN 2N33-F003, Steam Seal Main Steam Feed Vlv.
- Confirms CLOSED 2N33-F005, Unloading Bypass Vlv.
(
- Confirms CLOSED 2N33-F008, Aux Steam Feed Vlv.
- Sends an SO to the Steam Seal Feed Valve Controller to confirm> 20 #
Air fulet Pressure AND < 15 # Air Outlet Pressure.
Simulator Operator: If sent as the SO to check on Steam Seal Feed Valve Controller air pressure, wait 2 minutes and report air inlet is > 20 psig and air outlet is 0.5 psig.
Simulator Operator, at the direction of the Chief Examiner, proceed to next event.
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-05 Event No.:
5 Page 7 of21 Event
Description:
RWCU line will break outside of Primary Containment I Time Position Applicant's Actions or Behavior Simulator Operator: When power is approximately 7%, at the direction of the Chief Examiner:
- ENTER malfunction mfG31_52. (RB-S)
- DELETE svoG31071 when the F004 control switch is taken to close.
ALL Recognize "RWCU Sys Leak" annunciator BOP Responds to "RWCU Sys Leak" annunciator
- Determines that an isolation is required and enters 34AB-G31-001-2.
- Confirms automatic actions by:
- Tripping RWCU Pump "2B
- Places control switch for 2G31-F001 to close
- Places control switch 2G31-F004 to the close (Critical Task)
- Notifies SS of possible SC-Secondary Containment Control Entry
- Suspects a leak has occurred and enters 34AB-T22-001-2
- Dispatches SOlMaintenance to determine why 2G31-F001 and FOO4 did not auto close.
- Enters TS for 2G31-FOO1.
- Determines that LCO 3.6.1.3.A applies and that the RWCU Line must be isolated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- Enters TRM for continuous conductivity monitoring
- Determines the TSR 3.4.1.1 requires 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> surveillance requirement
5-05 Event No.:
5 Page 7 of 21 Event
Description:
RWCU line will break outside of Primary Containment Time Position Applicanfs Actions or Behavior Simulator Operator: When power is approximately 7%, at the direction of the Chief Examiner:
- ENTER malfunction mfG31_52. (RB-S)
- DELETE svoG31071 when the F004 control switch is taken to close.
ALL Recognize "RWCU Sys Leak" annunciator BOP Responds to "RWCU Sys Leak" annunciator
- Determines that an isolation is required and enters 34AB-G31-001-2.
- Confirms automatic actions by:
- Tripping RWCU Pump "2B
- Places control switch for 2G31-FOOI to close
- Places control switch 2G31-F004 to the close (Critical Task)
- Notifies SS of conductivity monitoring requirements of
(
TRM T3.4.1.
- Notifies SS of possible SC-Secondary Containment Control Entry
- Suspects a leak has occurred and enters 34AB-T22-001-2
- Dispatches SOlMaintenance to determine why 2G31-F001 and FOO4 did not auto close.
- Enters TS for 2G31-FOOl.
- Determines that LCO 3.6.1.3.A applies and that the RWCU Line must be isolated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- Enters TRM for continuous conductivity monitoring
- Determines the TSR 3.4.1.1 requires 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> surveillance requirement
- Reviews EOP SC for possible entry conditions
Appendix D Required Operator Actions Form ES-D-2
" Op-Test No.: 2009-302 Scenario No.:
5-05 Event No.:
6 Page 8 of 21 Event
Description:
SRV "2G" Opens Time Position Applicant's Actions or Behavior Simulator Operator: To insure the ATC operator gets the next malfunction, wait until the BOP is in the back panels OR as Shift Manger, request the BOP to get some back panel readings.
Simulator Operator: When RWCU actions are complete and at the direction of the Chief Examiner, ACTIVATE: (RB-6)
- svoB21220 loB21_F013GR2 Simulator Operator: When the operator depresses the LLS Reset PB, then delete above overrides.
All
- Recognize annunciators:
- 602-311, 'Safety Blowdown Valve Leaking'
- Enters 602-311 and 603-122 annunciators
- Confirm which safety relief valve has opened using the amber valve leakage indicator
- Confirms green light is OFF
5-05 Event No.:
6 Page 8 of 21 Event
Description:
SRV "2G" Opens Time Position Applicant's Actions or Behavior Simulator Operator: To insure the ATC operator gets the next malfunction, wait until the BOP is in the back panels OR as Shift Manger, request the BOP to get some back panel readings.
Simulator Operator: When RWCU actions are complete and at the direction of the Chief Examiner, ACTIVATE: (RB-6) svoB21220
- loB21_F013GR2 Simulator Operator: When the operator depresses the LLS Reset PB, then delete above overrides.
All
- Recognize annunciators:
- 602-311, 'Safety Blowdown Valve Leaking'
- 603-122, 'Safety Blowdown Pressure High'
(
The ATC may enter the abnormal procedure first before addressing the ARPs.
- Enters 602-311 and 603-122 annunciators
- Confirm which safety relief valve has opened using the amber valve leakage indicator
- Confirms green light is OFF
- Directs BOP to check back panel tail pipe temperatures
Appendix 0 Required Operator Actions Form ES-O-2 II Op-Test No.: 2009-302 Scenario No.:
5-05 Event No.:
6 Page 9 of 21 Event
Description:
SRV "2G" Opens Time Position Applicant's Actions or Behavior I
- Confirm "G" is leaking using the indication on 2B21-R614, Auto BlowdowniSafety Vlv Temps recorder.
- Executes 34AB-B21-003-2 steps
- Confirms the Red Light is illuminated
- Cycle the SRV control switch several times between OPEN/CLOSE
- Depress the ADS Logic AlB Timer Reset pushbuttons
- Depress the LLS Reset pushbuttons (Critical Task)
- When SRV closes confirms;
- Torus water level increase has stopped.
- Torus temperature increase has stopped.
- Reactor Power is at its original value
- Resets the SRV leak: detection AMBER SRV indicating lights SRO IA W TS 3.3.6.3, Condition D, Declares 'G' SRV inoperable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or IA W TS 3.6.1.6 declares 'G' inoperable and initiates a tracking RAS.
Simulator Operator, at the Chief Examiners direction, proceed to the next event.
Appendix 0 Required Operator Actions Form ES-O-2 II
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Op-Test No.: 2009-302 Scenario No.:
5-05 Event No.:
6 Page 9 of 21 Event
Description:
SRV "2G" Opens I Time Position Applicant's Actions or Behavior BOP
- Confirm "G" is leaking using the indication on 2B21-R614, Auto Blowdown/Safety Vlv Temps recorder.
- Executes 34AB-B21-003-2 steps
- Confirms the Red Light is illuminated
- Cycle the SRV control switch several times between OPEN/CLOSE
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- Depress the ADS Logic AlB Timer Reset pushbuttons
- Depress the LLS Reset pushbuttons (Critical Task)
- When SRV closes confirms;
- Torus water level increase has stopped.
- Torus temperature increase has stopped.
- Reactor Power is at its original value
- Resets the SRV leak: detection AMBER SRV indicating lights SRO IA W TS 3.3.6.3, Condition D, Declares 'G' SRV inoperable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or IAW TS 3.6.1.6 declares 'G' inoperable and initiates a tracking RAS.
Simulator Operator, at the Chief Examiners direction, proceed to the next event.
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Appendix D Required Operator Actions Form ES-D-2
'\\
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
7 Page 10 of21 Event
Description:
Inadvertent Group 1 and A TWS
'I Time I Position Applicant's Actions or Behavior Simulator Operator: After SRV actions are complete and at the direction of the Chief Examiner, activate: (RB-7)
- mfB21_247A mfB21 247B ALL Recognizes annunciators and plant conditions:
- Group 1 System AlB Trip - Full Group 1, MSN isolation SRO
- Assigns the ATC to perform RC-I.
- Assigns the BOP operator to perform RC-2 and RC-3.
- If time allows assigns TC-I to be performed.
- Enters the RCA EOP flow chart, 31EO-EOP-Oll-2, for a scram condition and reactor power above 5%.
- Enters CP-3 EOP flow chart, 31EO-EOP-017-2, for ATWS level control.
Appendix 0 Required Operator Actions Form ES-O-2
(
'I Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
7 Page 10 of 21 Event
Description:
fuadvertent Group 1 and A TWS Time J Position Applicant's Actions or Behavior Simulator Operator: After SRV actions are complete and at the direction of the Chief Examiner, activate: (RB-7)
- mjB21_247A
- mfB21 247B ALL Recognizes annunciators and plant conditions:
- Group 1 System AlB Trip - Full Group 1, MSN isolation SRO
- Assigns the A TC to perform RC-1.
- Assigns the BOP operator to perform RC-2 and RC-3.
- If time allows assigns TC-1 to be performed.
- Enters the RCA EOP flow chart, 31EO-EOP-Oll-2, for a scram condition and reactor power above 5%.
- Enters CP-3 EOP flow chart, 31EO-EOP-017-2, for ATWS level control.
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Appendix 0 Required Operator Actions Form ES-O-2 II Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 11 of21 Event
Description:
RCICIHPCI Failures and A TWS Time I Position Applicant's Actions or Behavior ATC
- Performs RC-l consisting of:
- Inserts a manual scram.
- Places the mode switch to shutdown.
- Notifies the SS that control rods are out
- Places SDV isolation valve switch to "isolate" & confirms closed.
- Trips Recirc Pumps (power >5%)
- Injects SBLC (power >5%)
- Unlocks and places SBLC pump select switch in "Start Sys A" or "Start Sys B" position.
- Confirms Squib Valve Ready Lights are extinguished.
- Confirms SBLC Loss of Continuity to Squib Valve annunciator is alarmed.
- Recognizes that the selected SBLC pump DID NOT start.
- Places SBLC pump select switch in "Start Sys B" or "Start Sys A" position. (The pump not attempt first.)
- Recognizes that the selected SBLC pump DID NOT start.
- Reports to SS failure of SBLC to inject from control room and local initiation lAW 34S0-C41-003-2 is required.
- Shifts recorders to read IRMs, when required.
- Ranges IRMs to bring reading on scale.
- NotifIes the SS when the above actions are complete.
ATC Directs SO to manually initiate SLC locally lAW 34S0-C41-003-2.
Simulator Operator: When called as the SO and SLC initiation, acknowledge the communication. If called again, say that you are working on it and will call when completed.
Note: With MSIV closure, checking of ECCS is the only pertinent RC-2 action.
Appendix D Required Operator Actions Form ES-D-2
(
'\\ Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 11 of 21 Event
Description:
RCICIHPCI Failures and A TWS Time I Position Applicant's Actions or Behavior I
- Performs RC-1 consisting of:
- Inserts a manual scram.
- Places the mode switch to shutdown.
- Notifies the SS that control rods are out
- Places SDV isolation valve switch to "isolate" & confirms closed.
- Trips Recirc Pumps (power >5%)
- Injects SBLC (power >5%)
- Unlocks and places SBLC pump select switch in "Start Sys A" or "Start Sys B" position.
- Confirms Squib Valve Ready Lights are extinguished.
- Confirms SBLC Loss of Continuity to Squib Valve annunciator is alarmed.
(
- Recognizes that the selected SBLC pump DID NOT start.
- Places SBLC pump select switch in "Start Sys B" or "Start Sys A" position. (The pump not attempt first.)
- Recognizes that the selected SBLC pump DID NOT start.
- Reports to SS failure of SBLC to inject from control room and local initiation lAW 34S0-C41-003-2 is required.
- Shifts recorders to read IRMs, when required.
- Ranges IRMs to bring reading on scale.
- Notifies the SS when the above actions are complete.
ATC Directs SO to manually initiate SLC locally lAW 34S0-C41-003-2.
Simulator Operator: When called as the SO and SLC initiation, acknowledge
(
the communication. If called again, say that you are working on it and will call when completed.
Note: With MSIV closure, checking of ECCS is the only pertinent RC-2 action.
Appendix D Required Operator Actions Form ES-D-2 I ~
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 12 of 21 Event
Description:
RCICIHPCI Failures and A TWS Time I Position Applicant's Actions or Behavior BOP Performs RC-2 by checking status of ECCS systems.
- Performs RC-3 consisting of:
- Monitor RPV pressure.
- Maintain RPV pressure between 1074 and 800 psig.
Notify SS that LLS is the pressure control system.
- Directs A TC to:
- Confirm the reactor Mode Switch in Shutdown.
- Confirm ARI Initiation.
- Reports to the SS that:
The Reactor Mode Switch is in the Shutdown position.
- Recirc is at minimum speed or tripped if power> 5%.
Appendix D Required Operator Actions Form ES-D-2
(.
~
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 12 of21 Event
Description:
RCICIHPCI Failures and A TWS I Time I Position Applicant's Actions or Behavior I
BOP Performs RC-2 by checking status of ECCS systems.
- Performs RC-3 consisting of:
- Monitor RPV pressure.
- Maintain RPV pressure between 1074 and 800 psig.
Notify SS that LLS is the pressure control system.
(
- Directs A TC to:
- Confirm the reactor Mode Switch in Shutdown.
- Confirm ARI Initiation.
- Reports to the SS that:
The Reactor Mode Switch is in the Shutdown position.
- Recirc is at minimum speed or tripped if power> 5%.
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Appendix 0 Required Operator Actions Form ES-O-2 I,
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 13 of 21 Event
Description:
RCICIHPCI Failures and ATWS Time I Position Applicant's Actions or Behavior I
- Directs A TC to Reset ARI and insert control rods IA W 31EO-EOP-I03-2.
Note: If asked, STA will direct the ATe to start in the center of the core and spiral out in a "black and white" pattern.
- Enters 31EO-EOP-103-2, "EOP Control Rod Insertion Methods".
- Confirms ARI initiation signals are clear
- Depresses ARI Reset pushbutton
- Check annunciator ARI INITIATED, clear
- Attempts to drive rods by:
- Place Reactor Mode switch to REFUEL.
- Place Rod Worth Minimizer bypass switch to BYPASS.
- Obtain recommendations from STA
- May start second CRD pump
- Drive rods to at least 02 using the Emerg In or IN (Critical Task)
- As time allows, performs TC-l
- Confirm Trip of the Turbine.
- Confirm/Place TGM in auto.
- Start TG Oil Pump
- Motor Suction Pump
- Lift Pumps I
Appendix 0 Required Operator Actions Form ES-O-2
(
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 13 of 21 Event
Description:
RCICIHPCI Failures and A TWS Time I Position Applicant's Actions or Behavior I
- Directs A TC to Reset ARI and insert control rods IA W 31EO-EOP-103-2.
Note: If asked, STA will direct the ATe to start in the center of the core and spiral out in a "black and white" pattern.
- Enters 31EO-EOP-103-2, "EOP Control Rod Insertion Methods".
- Confirms ARI initiation signals are clear
- Depresses ARI Reset pushbutton
(
- Check annunciator ARI INITIATED, clear
- Attempts to drive rods by:
- Place Reactor Mode switch to REFUEL.
- Place Rod Worth Minimizer bypass switch to BYPASS.
- Obtain recommendations from STA
- May start second CRD pump
- Drive rods to at least 02 using the Emerg In or IN (Critical Task)
- As time allows, performs TC-1
- Confirm Trip of the Turbine.
- Confirm/Place TGM in auto.
- Start TG Oil Pump
- Motor Suction Pump
- Lift Pumps
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I
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 14 of21 Event
Description:
RCIC/HPCI Failures and A TWS Time I Position Applicant1s Actions or Behavior SRO
- Directs BOP control RWL -60 inches to -90 inches.
- Reduces injection to control RWL -60 inches to -90 inches.
- To control HPCI injection the operator may place 2E41-C002-3, HPCI Aux. Oil Pump, in PULL-TO-LOCK or reduce controller output.
- To control RCIC injection the operator may depress the RCIC turbine trip push-button or reduce controller output.
ALL
- Recognizes torus temperature is above 95°F.
- Enters 34AB-T23-003-2, Torus Temperature Above 95°F
- Confirms the high temperature by observing the Suppression Pool bulk average temperature on the SPDS primary display
- Places RHR in Suppression Pool cooling per 34S0-E 11-0 1 0-2, Residual Heat Removal.
Appendix D Required Operator Actions Form E8-D-2 i
II
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Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 14 of 21 Event
Description:
RCIC/HPCI Failures and ATWS Time I Position Applicant's Actions or Behavior I
- Directs BOP control RWL -60 inches to -90 inches.
- Reduces injection to control RWL -60 inches to -90 inches.
- To control HPCI injection the operator may place 2E41-C002-3, HPCI Aux. Oil Pump, in PULL-TO-LOCK or reduce controller output.
- To control RCIC injection the operator may depress the RCIC turbine trip push-button or reduce controller output.
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ALL
- Recognizes torus temperature is above 95°F.
- Enters 34AB-T23-003-2, Torus Temperature Above 95°F
- Confirms the high temperature by observing the Suppression Pool bulk average temperature on the SPDS primary display
- Places RHR in Suppression Pool cooling per 34S0-E11-010-2, Residual Heat Removal.
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Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 15 of 21 Event
Description:
RCICIHPCI Failures and A TWS
!I Time I Position Applicant's Actions or Behavior BOP (Placard)
NOTE: The operator may place torus cooling in service by using the Placard that's available or using the appropriate section of the procedure. These steps assume the Placard is used.
The A or B loop of RHR may be used. The following steps are written assuming "B" loop and "B" pump is used. If "A" loop is used, substitute "A" for "B" for valves and if "B" pump is not used substitute "A", "C", or "D" for "B" pump.
Enters 34S0-EII-01O-2, Residual Heat Removal or uses placard on 2HII-P601.
Places RHRSW in service Prelubes RHRSW pump Overrides 2EII-F068B Low Discharge Pressure Interlock Positions 2EII-F068B to 45% OPEN Starts RHRSW pump B
- RHR HX B Diff Press Low (601-215) alarms Places 2EII-F068B Low Discharge Pressure Interlock switch to normal position.
Positions 2EII-F068B to obtain < 4400 GPM AND < 450 PSIG RHR HX B DiffPress Low (601-215) alarm clears
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(
Appendix 0 Required Operator Actions Form ES-O-2
'\\
Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 15 of21 Event
Description:
RCICIHPCI Failures and A TWS Time I Position Applicant's Actions or Behavior BOP (Placard)
NOTE: The operator may place torus cooling in service by using the Placard that's available or using the appropriate section of the procedure. These steps assume the Placard is used.
The A or B loop of RHR may be used. The following steps are written assuming "B" loop and "B" pump is used. If "A" loop is used, substitute "A" for "B" for valves and if "B" pump is not used substitute "A ", "e", or "D" for "B" pump.
Enters 34S0-EII-0I0-2, Residual Heat Removal or uses placard on 2HII-P601.
Places RHRSW in service Prelubes RHRSW pump Overrides 2EII-F068B Low Discharge Pressure Interlock Positions 2EII-F068B to 45% OPEN Starts RHRSW pump B
- RHR HX B DiffPress Low (601-215) alarms Places 2EII-F068B Low Discharge Pressure Interlock switch to normal position.
Positions 2EII-F068B to obtain < 4400 GPM AND < 450 PSIG RHR HX B Diff Press Low (601-215) alarm clears
Appendix D Required Operator Actions Form ES-D-2 II Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 16 of 21 Event
Description:
RCICIHPCI Failures and A TWS Time I Position Applicant's Actions or Behavior I
- Place RHR loop B in Suppression Pool Cooling (Placard)
- Does NOT position the 2/3 Core Height Permissive switch.
(RWL will NOT be lowered to below 2/3 core height)
- Does NOT place the Containment Spray valve Control switch in the manual position. (LOCA signal is not present)
- Confirm open 2EII-F048B, HX Bypass Vlv.
- Close 2EII-F047B, Hx Inlet Vlv.
- Confirm open 2Ell-F003A, HX Outlet Vlv
- Start "2B RHR pump
- SEC System Auto Initiation Signal Present (650-234) alarms
- Auto Blow Down CS or RHR Press Permissive (602-312) alarms
- RHR Flow Low (601-215) alarms
- Open 2EII-F028B, Torus Spray or Test Vlv.
- Throttle open 2EII-F024B, Full Flow Test Line Vlv. and establish RHR flow of less than or equal to 7700 gpm (R603B)
- RHR Flow Low (601-215) alarm clears
- Open 2EI1-F047B, Hx Inlet Vlv.
- Close 2EII-F048B, Hx Bypass Vlv.
BOP Controls RWL -60 inches to -90 inches.
Appendix D Required Operator Actions Form ES-D-2
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II Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 16 of 21 Event
Description:
RCICIHPCI Failures and A TWS Time I Position Applicant's Actions or Behavior BOP
- Place RHR loop B in Suppression Pool Cooling (Placard)
- Does NOT position the 2/3 Core Height Permissive switch.
(RWL will NOT be lowered to below 2/3 core height)
- Does NOT place the Containment Spray valve Control switch in the manual position. (LOCA signal is not present)
- Confirm open 2E11-F048B, HX Bypass Vlv.
- Close 2E11-F047B, Hx Inlet Vlv.
- Confirm open 2Ell-F003A, HX Outlet Vlv
- Start "2B RHR pump
- SEC System Auto Initiation Signal Present (650-234) alarms
- Auto Blow Down CS or RHR Press Permissive (602-312) alarms
- RHR Flow Low (601-215) alarms
- Open 2E11-F028B, Torus Spray or Test Vlv.
- Throttle open 2E11-F024B, Full Flow Test Line Vlv. and establish
(
RHR flow of less than or equal to 7700 gpm (R603B)
- RHR Flow Low (601-215) alarm clears
- Open 2Ell-F047B, Hx Inlet Vlv.
- Close 2E11-F048B, Hx Bypass Vlv.
BOP Controls RWL -60 inches to -90 inches.
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Appendix 0 Required Operator Actions Form ES-O-2 I,
. Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 17 of 21 Event
Description:
RCIC/HPCI Failures and A TWS Time I Position Applicant's Actions or Behavior BOP IF RCIC injection is attempted AND RCIC was manually tripped:
- Transfers 2E51-R612, Turbine Controller, to MANUAL AND adjust output to 50%.
- Closes 2E51-F524, Trip & Throttle Valve.
- Opens 2E51-F045, Stm to Turb Valve.
- Opens 2E51-F046, Turb Clg Water Valve.
- Starts 2E51-C002-2, Barom Cndsr Vac Pump.
- Confirms 2E51-F019, Min Flow Valve, Opens, AND subsequently Closes, WHEN system flow is greater than 79.3 gpm.
- Fully opens 2E51-F524, Trip & Throttle Valve.
- Increases 2E51-R612, Turbine Controller, output to achieve 3000 to 4000 rpm.
- Transfers 2E51-R612, Turbine Controller, to AUTO AND adjust to desired flow rate.
- Depresses RCIC Manual Initiation PIB (failed)
- Opens 2E51-F046
- Starts Barom Cndsr Vac Pmp
- Opens 2E51-F045
- Confirms open 2E51-FO 19
- Confirms closed 2E51-F019 at flow> 79.3 gpm
- Opens 2E51-FO 13
- Adjusts controller for desired flow
- Maintains level -60" to -90"
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Appendix D Required Operator Actions Form ES-D-2
~,
. Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 17 of 21 Event
Description:
RCIC/HPCI Failures and A TWS Time J Position Applicant's Actions or Behavior BOP IF RCIC injection is attempted AND RCIC was manually tripped:
- Transfers 2E51-R612, Turbine Controller, to MANUAL AND adjust output to 50%.
- Closes 2E51-F524, Trip & Throttle Valve.
- Opens 2E51-F045, Stm to Turb Valve.
- Opens 2E51-F046, Turb Clg Water Valve.
- Starts 2E51-C002-2, Barom Cndsr Vac Pump.
- Confirms 2E51-F019, Min Flow Valve, Opens, AND subsequently Closes, WHEN system flow is greater than 79.3 gpm.
- Fully opens 2E51-F524, Trip & Throttle Valve.
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- Increases 2E51-R612, Turbine Controller, output to achieve 3000 to 4000 rpm.
- Transfers 2E51-R612, Turbine Controller, to AUTO AND adjust to desired flow rate.
- Depresses RCIC Manual Initiation PIB (failed)
- Opens 2E51-F046
- Starts Barom Cndsr Vac Pmp
- Opens 2E51-F045
- Confirms open 2E51-F019
- Confirms closed 2E51-F019 at flow> 79.3 gpm
- Opens 2E51-F013
- Adjusts controller for desired flow
- Maintains level -60" to -90"
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Appendix 0 Required Operator Actions Form ES-O-2 II
. Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 18 of 21 Event
Description:
RCICIHPCI Failures and A TWS I Time I Position Applicant's Actions or Behavior I
Note: With an initial torus temperature of 86 deg F., after the Group 1 isolation and without rod insertion or Torus Cooling, it takes - 6 minutes for torus temperature to reach 100 deg F.
SRO Enters EOP PC chart on a Torus Temperature of 100 deg F and directs BOP:
- To monitor:
- Torus Temp
- Torus Level
- Drywell Temp
- Containment Pressure
- Place Hydrogen and Oxygen analyzers in service lAW 34S0-P33-001-2 Simulator Operator With Chief Examiner's permission Scenario will stop here.
Appendix 0 Required Operator Actions Form ES-O-2
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I,
. Op-Test No.: 2009-302 Scenario No.:
5-04 Event No.:
8 Page 18 of 21 Event
Description:
RCICIHPCI Failures and A TWS II Time I Position Applicant's Actions or Behavior Note: With an initial torus temperature of 86 deg F., after the Group 1 isolation and without rod insertion or Torus Cooling, it takes - 6 minutes for torus temperature to reach 100 deg F.
SRO Enters EOP PC chart on a Torus Temperature of 100 deg F and directs BOP:
- To monitor:
- Torus Temp
- Torus Level
- Drywell Temp
- Containment Pressure
- Place Hydrogen and Oxygen analyzers in service IA W 34S0-P33-001-2
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Simulator Operator With Chief Examiner's permission Scenario will stop here.
Facility:
E. I Hatch Initiating Conditions:
Turnover Summary:
Page 19 of 21 Scenario Summary Scenario No.:
5-05 Op-Test No.:
2009-302 NRC Dra/t Unit 2 is operating at approximately 5% RTP in Chest Warming Continue startup lAW 34GO-OPS-001-2 and remove the Mechanical Vacuum Pump from service Event 1: Remove the Mechanical Vacuum Pump from service with suction valve 2N22-F007 failing to full close.
Event 2: Pull control rods to continue Startup to - 7% power, raise pressure set to 920.
Event 3: ComponentfTS; While withdrawing control rods a control rod will become uncoupled.
The operator takes manual control to re-couple the control rod per the annunciator response procedures. The SS will address Tech Specs for the uncoupled control rod.
Event 4: Component; The main turbine Gland Seal Regulator valve will fail closed while in chest warming. The operator will take manual actions to restore the steam seal header pressure to normal.
Event 5: ComponentfTS; A RWCU line will break outside of Primary Containment. The inboard and outboard isolation valves fail to close automatically. The operator will take manual actions to isolate the leaking RWCU line. (Critical Task) The SS addresses Tech Specs for inoperable Primary Containment Isolation Valves.
Event 6: ComponentfTS; SRV "2G" opens. The ATC operator will attempt to close the SRV lAW the abnormal procedure for an electrically open SRV. After the ATC operator depresses the LLS Reset pushbuttons (PB), the SRV will close. (Critical task). If Torus temperature exceeds 95°F, the BOP operator will place RHR in Suppression Pool Cooling. SS addresses TS for inoperable SRV.
Event 7: Major; Inadvertent Group 1 isolation causes MSNs closure. An ATWS condition will exist, requiring the ATC operator to manually insert control rods (Critical task).
Event 8: Component; Both SBLC pumps will fail to start from the control room. The operator will take manual actions to inject SBLC locally.
Event 9: RCIC and HPCI fail to auto start. RCIC must be manually aligned and started to maintain RWL-60" to -90".
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Facility:
E. I Hatch Initiating Conditions:
Turnover Summary:
Page 19 of 21 Scenario Summary Scenario No.:
5-05 Op-Test No.:
2009-302 NRC Draft Unit 2 is operating at approximately 5% RTP in Chest Warming Continue startup lAW 34GO-OPS-00 1-2 and remove the Mechanical Vacuum Pump from service Event 1: Remove the Mechanical Vacuum Pump from service with suction valve 2N22-F007 failing to full close.
Event 2: Pull control rods to continue Startup to ~ 7% power, raise pressure set to 920.
Event 3: ComponentfTS; While withdrawing control rods a control rod will become uncoupled.
The operator takes manual control to re-couple the control rod per the annunciator response procedures. The SS will address Tech Specs for the uncoupled control rod.
Event 4: Component; The main turbine Gland Seal Regulator valve will fail closed while in chest warming. The operator will take manual actions to restore the steam seal header pressure to normal.
Event 5: ComponentffS; A RWCU line will break outside of Primary Containment. The inboard and outboard isolation valves fail to close automatically. The operator will take manual actions to isolate the leaking RWCU line. (Critical Task) The SS addresses Tech Specs for inoperable Primary Containment Isolation Valves.
Event 6: ComponentfTS; SRV "2G" opens. The ATC operator will attempt to close the SRV lAW the abnormal procedure for an electrically open SRV. After the ATC operator depresses the LLS Reset pushbuttons (PB), the SRV will close. (Critical task). If Torus temperature exceeds 95°F, the BOP operator will place RHR in Suppression Pool Cooling. SS addresses TS for inoperable SRV.
Event 7: Major; Inadvertent Group 1 isolation causes MSIVs closure. An ATWS condition will exist, requiring the ATC operator to manually insert control rods (Critical task).
Event 8: Component; Both SBLC pumps will fail to start from the control room. The operator will take manual actions to inject SBLC locally.
Event 9: RCIC and HPCI fail to auto start. RCIC must be manually aligned and started to maintain R WL -60" to -90".
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Page 20 of21 Critical Task List Facility:
E. I Hatch Scenario No.:
5-05 Op-Test No.:
2009-302 Critical Tasks
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
Manually isolate RWCU before exceeding maximum safe Secondary Containment Control EOP parameters (Temperatures, Radiation levels or SC water levels). (Event 5)
Depresses the LLS Reset pushbuttons to close SRV (Event 6)
Commence insertion of control rods within 20 minutes and before entering the unsafe region of the Heat Capacity Temperature Limit graph (Event 7)
ES 301-4 Attributes Required Actual Items Total Malfunctions 5-8 7
- 1. Control rod becomes uncoupled (Event 3)
- 2. Gland Seal Regulator valve fails (Event 4)
- 3. RWCU line break outside of Primary Containment (Event 5)
- 4. SRV "2G" begins leaking (Event 6)
- 5. Inadvertent Group 1 on low vacuum along with an ATWS (Event 7)
- 6. Both SBLC pumps will fail (Event 8)
Malfunctions After 1-2 2
- 1. Both SBLC pumps will fail (Event 8)
EOPEntry
Abnormal Events 2-4 2
- 1. RWCU line break outside of Primary Containment (Event 5)
- 2. SRV "2G" opens (Event 6)
Major Transients 1-2 1
- 1. Inadvertent Group 1 on low vacuum along with an A TWS (Event 7)
EOPs entered, 1-2 2
- 2. EOPCP-3 actions EOPs contingencies 0-2 1
- 1. Manually isolate RWCU. (Event 5)
- 3. Insert Rods during A TWS (Event 7)
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Page 20 of 21 Critical Task List Facility:
E. I Hatch Scenario No.:
5-05 Op-Test No.:
2009-302 Critical Tasks
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
Manually isolate RWCU before exceeding maximum safe Secondary Containment Control EOP parameters (Temperatures, Radiation levels or SC water levels). (Event 5)
Depresses the LLS Reset pushbuttons to close SRV (Event 6)
Commence insertion of control rods within 20 minutes and before entering the unsafe region of the Heat Capacity Temperature Limit graph (Event 7)
ES 301-4 Attributes Required Actual Items Total Malfunctions 5-8 7
- 1. Control rod becomes uncoupled (Event 3)
- 2. Gland Seal Regulator valve fails (Event 4)
- 3. RWCU line break outside of Primary Containment (Event 5)
- 4. SRV "2G" begins leaking (Event 6)
- 5. Inadvertent Group 1 on low vacuum along with an A TWS (Event 7)
- 6. Both SBLC pumps will fail (Event 8)
Malfunctions After 1-2 2
- 1. Both SBLC pumps will fail (Event 8)
EOP Entry
Abnormal Events 2-4 2
- 1. RWCU line break outside of Primary Containment (Event 5)
- 2. SRV "2G" opens (Event 6)
Major Transients 1-2 1
- 1. Inadvertent Group 1 on low vacuum along with an A TWS (Event 7)
EOPs entered, 1-2 2
- 2. EOPCP-3 actions EOPs contingencies 0-2 1
- 1. Manually isolate RWCU. (Event 5)
- 3. Insert Rods during A TWS (Event 7)
UNIT 1 STATUS Power:
Activities in progress:
UNIT 2 STATUS Power:
HLT 5 NRC Operating Exam Scenario 5 SIDFT TURNOVER 100%
None Unit 2 is operating at approximately 5% power preparing to remove the Mechanical Vacuum Pump from service per step 7.3.26 of 34GO-OPS-OOl-2.
The following equipment is Rod Worth Minimizer. A second licensed operator is available inoperable:
for rod movement verifications and peer check.
Scheduled evolutions:
Surveillances due this shift:
Active clearances:
Rod Configuration:
Continue with startup lAW 34GO-OPS-001-2.
There are no further Drywell entries to be made.
Hydrogen Water Chemistry Injection is ready for service at 35% power lAW 34S0-P73-001-2.
None None Sequence A2, Step 19, Rod 34-31
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UNIT 1 STATUS Power:
Activities in progress:
Power:
HLT 5 NRC Operating Exam Scenario 5 SIDFT TURNOVER 100%
None Unit 2 is operating at approximately 5% power preparing to remove the Mechanical Vacuum Pump from service per step 7.3.26 of 34GO-OPS-001-2.
The following equipment is Rod Worth Minimizer. A second licensed operator is available inoperable:
for rod movement verifications and peer check.
Scheduled evolutions:
Surveillances due this shift:
Active clearances:
Rod Configuration:
Continue with startup lAW 34GO-OPS-001-2.
There are no further Drywell entries to be made.
Hydrogen Water Chemistry Injection is ready for service at 35% power lAW 34S0-P73-001-2.