ML13297A338: Difference between revisions
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EVENT 6 - The tube leak will degrade to a SGTR, the crew will trip the reactor enter E-0 REACTOR TRIP OR SAFETY INJECTION. | EVENT 6 - The tube leak will degrade to a SGTR, the crew will trip the reactor enter E-0 REACTOR TRIP OR SAFETY INJECTION. | ||
EVENT 7 - | EVENT 7 -. The Main Turbine will fail to trip when the Reactor Trips, the BOP will manually trip the Main Turbine. | ||
. The Main Turbine will fail to trip when the Reactor Trips, the BOP will manually trip the Main Turbine. | |||
EVENT 8 - When the reactor trips, the ruptured SG Atmospheric Dump will open, the crew will transition through E-2 FAULTED STEAM GENERATOR ISOLATION, E-3 STEAM GENERATOR TUBE RUPTURE, and eventually to ECA-3.1, SGTR AND LOCA - SUBCOOLED RECOVERY. | EVENT 8 - When the reactor trips, the ruptured SG Atmospheric Dump will open, the crew will transition through E-2 FAULTED STEAM GENERATOR ISOLATION, E-3 STEAM GENERATOR TUBE RUPTURE, and eventually to ECA-3.1, SGTR AND LOCA - SUBCOOLED RECOVERY. | ||
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== Description:== | == Description:== | ||
Rapid Power Reduction Time Position Applicant's Actions or Behavior ATC ATC Places FIC-62-139 to 15 to 45 gpm. | Rapid Power Reduction Time Position Applicant's Actions or Behavior ATC ATC Places FIC-62-139 to 15 to 45 gpm. | ||
ATC ATC Places FQ-62-139 to 550 gal. | ATC ATC Places FQ-62-139 to 550 gal. ATC ATC Places HS-62-140A to START ATC ATC ATC Adjusts FIC-62-139 as required. | ||
ATC ATC Places HS-62-140A to START ATC ATC ATC Adjusts FIC-62-139 as required. | |||
ATC ATC ATC Records time boration initiated. | ATC ATC ATC Records time boration initiated. | ||
ATC ATC Places HS-62-140A to STOP. | ATC ATC Places HS-62-140A to STOP. | ||
| Line 283: | Line 281: | ||
Critical Task ATC/BOP Places HS-3 174A S/G 1 Turbine AFP LCV to CLOSE and PTL. (If not already performed.) | Critical Task ATC/BOP Places HS-3 174A S/G 1 Turbine AFP LCV to CLOSE and PTL. (If not already performed.) | ||
ATC/BOP ATC/BOP Places HS-1-15A TDAFWP steam supply from S/G #1 to CLOSE and HS-1-16A TDAFWP steam supply from S/G #4 to OPEN. (If not already performed.) | ATC/BOP ATC/BOP Places HS-1-15A TDAFWP steam supply from S/G #1 to CLOSE and HS-1-16A TDAFWP steam supply from S/G #4 to OPEN. (If not already performed.) | ||
SRO SRO determines S/G #1 is ruptured and transitions to E-3, Steam Generator Tube Rupture. | SRO SRO determines S/G #1 is ruptured and transitions to E-3, Steam Generator Tube Rupture. SRO Direct performance of E-3, Steam Generator Tube Rupture SRO Addresses foldout page, see next page for details. | ||
SRO Direct performance of E-3, Steam Generator Tube Rupture SRO Addresses foldout page, see next page for details. | |||
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 6, 7, 8 Page 45 of 64 Event | Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 6, 7, 8 Page 45 of 64 Event | ||
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#1 S/G SGTR/#1 S/G ADV Fail Open Time Position Applicant's Actions or Behavior ATC/BOP Critical Task ATC/BOP Places HS-3 164A 1A-A AFP LCV to S/G #1 to RAMP CLOSE until valve indicates closed. (If not already performed.) | #1 S/G SGTR/#1 S/G ADV Fail Open Time Position Applicant's Actions or Behavior ATC/BOP Critical Task ATC/BOP Places HS-3 164A 1A-A AFP LCV to S/G #1 to RAMP CLOSE until valve indicates closed. (If not already performed.) | ||
Critical Task ATC/BOP Places HS-3 174A S/G 1 Turbine AFP LCV to CLOSE and PTL. (If not already performed.) | Critical Task ATC/BOP Places HS-3 174A S/G 1 Turbine AFP LCV to CLOSE and PTL. (If not already performed.) | ||
ATC/BOP SRO Examiner Note: If #1 S/G is NOT 550 psig or below go to page 55 for additional E-3 steps. Scenario may be terminated when the SRO transitions to ECA-3.1or earlier, at discretion of Lead Examiner | ATC/BOP SRO Examiner Note: If #1 S/G is NOT 550 psig or below go to page 55 for additional E-3 steps. Scenario may be terminated when the SRO transitions to ECA-3.1or earlier, at discretion of Lead Examiner Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # ES-0.5 Page 49 of 64 Event | ||
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # ES-0.5 Page 49 of 64 Event | |||
== Description:== | == Description:== | ||
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== Description:== | == Description:== | ||
Raise plant power to 13-15% RTP Time Position Applicant's Actions or Behavior ATC [2] ENSURE sufficient capacity available in the HUT selected to receive expected amounts of CVCS letdown: ( | Raise plant power to 13-15% RTP Time Position Applicant's Actions or Behavior ATC [2] ENSURE sufficient capacity available in the HUT selected to receive expected amounts of CVCS letdown: (N/A if not used) | ||
N/A if not used) | |||
HUT LEVEL INITIALS A ___________ | HUT LEVEL INITIALS A ___________ | ||
% ___________ | % ___________ | ||
| Line 423: | Line 417: | ||
ATC [5] PERFORM Appendix I Independent Verification of Calculation for Amount of Boric Acid or Primary Water. (N/A if App. D was performed by SRO to verify | ATC [5] PERFORM Appendix I Independent Verification of Calculation for Amount of Boric Acid or Primary Water. (N/A if App. D was performed by SRO to verify | ||
data from Rx Engineering) | data from Rx Engineering) (Step not required provided in shift turnover package) | ||
(Step not required provided in shift turnover package) | |||
ATC [6] PLACE [HS-62-140A], Boric Acid Supply to Blender Flow Control Switch to the STOP position. | ATC [6] PLACE [HS-62-140A], Boric Acid Supply to Blender Flow Control Switch to the STOP position. | ||
ATC [7] PLACE [HS-62-140B], CVCS Makeup Selector Switch to the DILUTE position. | ATC [7] PLACE [HS-62-140B], CVCS Makeup Selector Switch to the DILUTE position. | ||
ATC [8] ENSURE [HS-62-140D], Boric Acid Valve to the Blender is CLOSED (Green light is LIT). ATC [9] SET [FQ-62-142], Batch Integrator for the desired quantity | ATC [8] ENSURE [HS-62-140D], Boric Acid Valve to the Blender is CLOSED (Green light is LIT). ATC [9] SET [FQ-62-142], Batch Integrator for the desired quantity NOTE 4 Primary Water Flow Controller | ||
[FC-62-142] receives its reference signal (70 gpm) from setpoint potentiometer (dial indicator) located on panel M-6. A setpoint of 35% corresponds to a 70 gpm primary water flow rate ATC [10] ADJUST [FC-62-142], Primary Makeup Water Flow Controller for the desired flow rate ATC [11] PLACE [HS-62-140A], Boric Acid Supply to Blender Flow Control Switch to the START position. ATC [12] VERIFY the following; | [FC-62-142] receives its reference signal (70 gpm) from setpoint potentiometer (dial indicator) located on panel M-6. A setpoint of 35% corresponds to a 70 gpm primary water flow rate ATC [10] ADJUST [FC-62-142], Primary Makeup Water Flow Controller for the desired flow rate ATC [11] PLACE [HS-62-140A], Boric Acid Supply to Blender Flow Control Switch to the START position. ATC [12] VERIFY the following; | ||
[a] Inlet to top of VCT | [a] Inlet to top of VCT | ||
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Raise plant power to 13-15% RTP Time Position Applicant's Actions or Behavior NOTE Alternate dilution in small amounts is acceptable on a regular basis, provided no significant changes in seal water temperature or seal leakoff are indicated. Batches of 5 to 10 gallons may be added through FCV-62-144 on a frequency not to exceed once per 30 minutes. ICS points for No. 1 seal leakoffs and seal water temperatures on the RCPs should be monitored during and after dilution. | Raise plant power to 13-15% RTP Time Position Applicant's Actions or Behavior NOTE Alternate dilution in small amounts is acceptable on a regular basis, provided no significant changes in seal water temperature or seal leakoff are indicated. Batches of 5 to 10 gallons may be added through FCV-62-144 on a frequency not to exceed once per 30 minutes. ICS points for No. 1 seal leakoffs and seal water temperatures on the RCPs should be monitored during and after dilution. | ||
ATC [13] IF primary water addition to the bottom of the VCT [FCV-62-144] | ATC [13] IF primary water addition to the bottom of the VCT [FCV-62-144] | ||
is desired, THEN ATC [a] CLOSE | is desired, THEN ATC [a] CLOSE [FCV-62-128] | ||
with [HS-62-128]. ATC [b] OPEN [FCV-62-144] | |||
with [HS-62-128] | with [HS-62-144]. ATC [c] VERIFY Primary Water flow by | ||
. ATC [b] OPEN [FCV-62-144] | |||
with [HS-62-144] | |||
. ATC [c] VERIFY Primary Water flow by | |||
[FI-62-142A] | [FI-62-142A] | ||
OR [FQ-62-142] | OR [FQ-62-142]. NOTE 5 It may take approximately 15 minutes before any changes to reactivity are indicated on nuclear instrumentati on or RCS temperature indication. ATC [14] MONITOR nuclear instrumentation and reactor coolant temperature to ensure the proper response from dilution. | ||
. | |||
ATC [15] IF [LI-62-129], Volume Control Tank Level, increases to 63 percent, THEN ENSURE [LCV-62-118], Volume Control Tank Divert Valve OPENS to divert excess water to the Holdup Tanks. | ATC [15] IF [LI-62-129], Volume Control Tank Level, increases to 63 percent, THEN ENSURE [LCV-62-118], Volume Control Tank Divert Valve OPENS to divert excess water to the Holdup Tanks. | ||
ATC [16] WHEN dilution is complete, THEN ATC [a] PLACE [HS-62-140A], Boric Acid to Blender Flow Control Switch to the STOP position. ATC [b] IF [FCV-62-144] | ATC [16] WHEN dilution is complete, THEN ATC [a] PLACE [HS-62-140A], Boric Acid to Blender Flow Control Switch to the STOP position. ATC [b] IF [FCV-62-144] | ||
was previously OPENED, THEN CLOSE | was previously OPENED , THEN CLOSE | ||
[FCV-62-144] | [FCV-62-144] | ||
with [HS-62-144] | with [HS-62-144]. ATC [c] VERIFY no primary water flow on either | ||
. ATC [c] VERIFY no primary water flow on either | |||
[FI-62-142A] | [FI-62-142A] | ||
OR [FQ-62-142] | OR [FQ-62-142]. ATC [d] ENSURE | ||
. ATC [d] ENSURE | |||
[FCV-62-128] | [FCV-62-128] | ||
is CLOSED ATC [17] IF power increase in progress and additional dilutions will be required, THEN use this table to re-perform steps | is CLOSED ATC [17] IF power increase in progress and additional dilutions will be required, THEN use this table to re-perform steps | ||
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Raise plant power to 13-15% RTP Time Position Applicant's Actions or Behavior ATC [19] REALIGN the blender controls for AUTO makeup to the CVCS in accordance with Section 5.1. | Raise plant power to 13-15% RTP Time Position Applicant's Actions or Behavior ATC [19] REALIGN the blender controls for AUTO makeup to the CVCS in accordance with Section 5.1. | ||
ATC [20] ENSURE dilution(s) is logged in Unit Narrative Log. | ATC [20] ENSURE dilution(s) is logged in Unit Narrative Log. | ||
NOTE 6 Sample may be obtained at normal RCS sample intervals provided the unit is at power and the unit response following the dilution is as expected. | |||
ATC [21] IF RCS boron sample is required, THEN NOTIFY Chem Lab to obtain RCS boron sample. | ATC [21] IF RCS boron sample is required, THEN NOTIFY Chem Lab to obtain RCS boron sample. | ||
| Line 488: | Line 475: | ||
== Description:== | == Description:== | ||
Raise plant power to 13-15% RTP Time Position Applicant's Actions or Behavior N/A [6] IF Turbine Roll in parallel with power increase is desired, THEN PERFORM Section 5.3 in parallel with the remainder of this section. | Raise plant power to 13-15% RTP Time Position Applicant's Actions or Behavior N/A [6] IF Turbine Roll in parallel with power increase is desired, THEN PERFORM Section 5.3 in parallel with the remainder of this section. | ||
ATC [7] IF the intermediate range rod stop setpoint is reached before P-10 energizes, THEN [7.1] STOP the power escalation. | ATC [7] IF the intermediate range rod stop setpoint is reached before P-10 energizes, THEN [7.1] STOP the power escalation. | ||
[7.2] CONTACT Reactor Engineering to evaluate power range calibration. | [7.2] CONTACT Reactor Engineering to evaluate power range calibration. | ||
Revision as of 21:55, 13 July 2018
| ML13297A338 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/18/2013 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| Download: ML13297A338 (116) | |
Text
Appendix D Scenario Outline Form ES-D-1 Appendix D NUREG 1021 Revision 9 Facility: Sequoyah Scenario No.: 1 Op Test No.: 2013-301 Examiners: Operators: Initial Conditions: Unit 1 is in MODE 1 76%, BOL Turnover: Unit 1 is in MODE 1 76%, BOL raise power to 100%. D RCW pump is OOS for maintenance.
PT-3-1A is in Maintenance Bypass Target CTs: Manually trip the main turbine prior to the completion of E-0. Isolate AFW flow into the ruptured (#1) SG by closing FCV-3-164 and 3-174 before a transition to ECA-3.1 occurs. Establish cooldown and maintain RCS temperature so that transition from E3 does not occur because the RCS temperature causes an extreme (red-path) or a severe (orange-path) challenge to the subcriticality and/or the integrity CSF. (As required.) Event No. Malf. No. Event Type* Event Description 1. RX05A I-ATC/SRO TS-SRO The controlling pressurizer level channel LT 68-339 will fail high resulting in charging flow decreasing and energizing Pressurizer backup heaters. The ATC will remove the channel from service and restore Pressurizer heaters using AOP-I.04. The SRO will address Tech Specs and determines the instrument is INOPERABLE. 2. CC01 C BOP/SRO A small leak develops on the Component Cooling Water system (CCS) with a failure of the CCS Surge Tank Makeup valve to AUTO open. The BOP manually opens the CCS Surge Tank Makeup valve. 3. TH05A C- ATC/SRO TS-SRO A small Steam Generator Tube Leak develops, the crew will respond using AOP-R.01. The ATC will raise Charging flow to maintain Pressurizer Level on program. The SRO will enter LCO 3.4.6.2.c, Action a. 4. R ATC N SRO/BOP The crew will reduce power using AOP-C.03, Rapid Power Reduction in response to the SGTL. 5. FW11A C-SRO/BOP At approximately 70% power, Main Feed Pump 1A develops an oil leak. The BOP trips the A MFWPT using ARP 1-AR-M3-B MAIN FEEDWATER PUMPS. 6. TH05A M-All The tube leak will degrade to a SGTR, the crew will trip the reactor enter E-0. 7. TC11ALL TC12ALL C-BOP The Main Turbine will fail to trip when the Reactor Trips, the BOP will manually trip the Main Turbine. 8. MS12A M-All When the reactor trips, the ruptured SG Atmospheric Dump will open, the crew will transition through E-2, E-3, and eventually to ECA-3.1. (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2013-301 NRC Scenario 1 Summary EVENT 1 - When directed by the lead examiner, the controlling pressurizer level channel LT 68-339 will fail high resulting in charging flow decreasing and energizing Pressurizer backup heaters. The ATC will remove the channel from service and restore Pressurizer heaters using AOP-I.04. The SRO will address Tech Specs and determines the instrument is INOPERABLE and enters LCO 3.3.1.1 Action 6; and LCO 3.3.3.7 Action 2a.
EVENT 2 - When directed by the lead examiner, A small leak develops on the Component Cooling Water system (CCS) with a failure of the CCS Surge Tank Makeup valve to AUTO open. The BOP manually opens the CCS Surge Tank Makeup valve.
EVENT 3 - When directed by the lead examiner, a 15 gpm SG Tube Leak develops on the #1 S/G. The ATC will manually increase charging flow and subsequently isolate letdown using AOP-R.01 STEAM GENERATOR TUBE LEAK. The SRO addresses Tech Specs and determines entry into LCO 3.4.6.2.c Action a is required.
EVENT 4 - The crew initiates a power reduction using AOP-C.03 RAPID SHUTDOWN OR LOAD REDUCTION due to the SGTL.
EVENT 5 - When directed by the lead examiner, at approximately 70% power, Main Feed Pump 1A develops an oil leak. The BOP trips the A MFWPT using ARP 1-AR-M3-B MAIN FEEDWATER PUMPS.
EVENT 6 - The tube leak will degrade to a SGTR, the crew will trip the reactor enter E-0 REACTOR TRIP OR SAFETY INJECTION.
EVENT 7 -. The Main Turbine will fail to trip when the Reactor Trips, the BOP will manually trip the Main Turbine.
EVENT 8 - When the reactor trips, the ruptured SG Atmospheric Dump will open, the crew will transition through E-2 FAULTED STEAM GENERATOR ISOLATION, E-3 STEAM GENERATOR TUBE RUPTURE, and eventually to ECA-3.1, SGTR AND LOCA - SUBCOOLED RECOVERY.
The scenario may be terminated when the crew transitions to ECA-3.1.
EOP flow: E-0, E-2, E-3, ECA-3.1.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 1 Page 1 of 64 Event
Description:
Controlling Pzr Lvl Transmitter Fails High (LT 68-339)
Time Position Applicant's Actions or Behavior Direct the Simulator Operator to initiate Event 1 Controlling Pzr Lvl Transmitter Fails High (LT 68-339) Indications/Alarms Annunciator:
1-M-5 5B C-3, "FS-62-1 REAC COOL PMPS SEAL WATER FLOW LO" 6A A-5, "LS-68-339A PRESSURIZER HIGH WATER LEVEL" Indications:
1-M-4 1-LI-68-339 RCS PZR LEVEL indicates increasing level Pressurizer Backup Heaters ON BOP Responds to ARP 1-AR-M5B C-3.
ATC May adjust HIC-62-89A, Charging Seal Water Flow Controller to maintain seal injection flow alarms clear.
Examiner Note: Several steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 1 Page 2 of 64 Event
Description:
Controlling Pzr Lvl Transmitter Fails High (LT 68-339)
Time Position Applicant's Actions or Behavior BOP Responds to ARP 1-AR-M6A A-5.
SRO Transitions to AOP I.04, PRESSURIZER INSTRUMENT AND CONTROL MALFUNCTIONS ATC ATC Places LEVEL CONTROL CHANNEL SELECTOR switch XS-68-339E in LT 335 & 320.
ATC SRO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 1 Page 3 of 64 Event
Description:
Controlling Pzr Lvl Transmitter Fails High (LT 68-339)
Time Position Applicant's Actions or Behavior
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 1 Page 4 of 64 Event
Description:
Controlling Pzr Lvl Transmitter Fails High (LT 68-339)
Time Position Applicant's Actions or Behavior SRO Enters LCO 3.3.1.1 Action 6 and LCO 3.3.3.7 Action 2 ATC NOTE: If performing AOP in conjunction with AOP-I.11 for an Eagle LCP failure, then actions to hard trip bistables should be delayed until Eagle system reset is attempted. Actions to hard trip bistables must be completed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> UNLESS affected loop is restored to operable status by resetting Eagle rack.
L-68-339 Appendix I Crew Performs a Crew Brief as time allows.
Crew Notifications should be addressed as applicable if not specifically addressed by the procedure or in the crew brief. Operations Management - Typically Shift Manager.
Maintenance Personnel - Typically Maintenance Shift Supervisor (MSS). (Note: Maintenance notification may be delegated to the Shift Manager). Lead Examiner may cue the next event when Tech Specs have been addressed.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 2 Page 5 of 64 Event
Description:
CCS Leak Direct the Simulator Operator to initiate Event 2 Indications/Alarms Annunciator:
0-M-27B-B 27B-B C-2, "UNIT 1 CCS" SURGE TK LVL LO AUTO MAKEUP INITIATED 0-M-27B-D 27B-D C-2, "UNIT 2 CCS" SURGE TK LVL LO AUTO MAKEUP INITIATED 1-M-15B 15B -E3, "LS-59-180A/B DEM WTR ANDCASK DECON SYS ABN CONDITION" Indications:
1-1-M-27B-B 1-LI-70-99A and 63A CCS Surge Tank level decreasing BOP Responds to ARP 1-AR-M27BB C-2.
ATC Places 1-HS-70-63A CCS Surge Tank A Inlet Isolation to OPEN.
Examiner Note: Several steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide. Lead Examiner may cue the next event when level in the CCS Surge Tank makeup valve has been
opened.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # 3 Page 6 of 64 Event
Description:
Steam Generator Tube Leak Time Position Applicant's Actions or Behavior Direct the Simulator Operator to initiate Event 3, #1 SG Tube Leakage of ~15 gpm Indications available:
Annunciators: 0-M-12 0-XA-55-12A Window D-3, "1-RA-90-99A, CNDS VAC PMP LO RNG AIR EXH MON HIGH RAD" 0-XA-55-12A Window B-6, "1-RA-120A/121A, STM GEN BLDN LIQ SAMP MON HI RAD" (20 minutes later)
Indications available:
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # 3 Page 7 of 64 Event
Description:
Steam Generator Tube Leak Time Position Applicant's Actions or Behavior Examiner Note: Several steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.
SRO Transitions to AOP R.01 Examiner note if the crew implements section 2.2 go to page 12.
SRO ATC ATC Places FCV-62-93 in manual and controls charging flow, may adjust HIC-62-89A to maintain RCP Seal Flow
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # 3 Page 8 of 64 Event
Description:
Steam Generator Tube Leak Time Position Applicant's Actions or Behavior ATC ATC If pressurizer level is still dropping, places HS-FCV-62-72, FCV-62-73 CLOSED, and FCV-62-74 to CLOSE. Examiner Note: As the leak degrades, the ATC may take the RNO actions listed above, go to page 37 for additional details..
Examiner note; Appendix F starts on page 16 SRO ATC CREW CREW Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # 3 Page 9 of 64 Event
Description:
Steam Generator Tube Leak Time Position Applicant's Actions or Behavior CREW CREW Identifies SGTL on S/G # 1. Examiner Note: SRO may refer to Operations Chemistry Information Sheet in turnover package.
SRO SRO Enters 3.4.6.2.c, Operational Leakage action a.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # 3 Page 10 of 64 Event
Description:
Steam Generator Tube Leak Time Position Applicant's Actions or Behavior CREW SRO Transitions to AOP-C.03 Examiner note AOP-C.03 actions start on page 18.
CRO Continues with performance of AOP-R.01 BOP BOP Manually closes FCV-1-15 TDAFWP steam supply from S/G #1 and opens FCV-1-16 TDAFWP steam supply from S/G #4 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # 3 Page 11 of 64 Event
Description:
Steam Generator Tube Leak Time Position Applicant's Actions or Behavior BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # 3 Page 12 of 64 Event
Description:
Steam Generator Tube Leak Time Position Applicant's Actions or Behavior BOP Examiner note Section 2.2 starts here.
ATC SRO SRO Directs SM to evaluate EPIP-1.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # 3 Page 13 of 64 Event
Description:
Steam Generator Tube Leak Time Position Applicant's Actions or Behavior ATC SRO Enters 3.4.6.2.c, Operational Leakage action a.
CREW Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # 3 Page 14 of 64 Event
Description:
Steam Generator Tube Leak Time Position Applicant's Actions or Behavior SRO BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # 3 Page 15 of 64 Event
Description:
Steam Generator Tube Leak Time Position Applicant's Actions or Behavior BOP Examiner Note: crew should realize leak is sufficient and transitions to section 2.1, page 7 Step 6 RNO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # 3 Page 16 of 64 Event
Description:
Steam Generator Tube Leak
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # 3 Page 17 of 64 Event
Description:
Steam Generator Tube Leak
Appendix D Scenario Outline Attachment 1 Op Test No.: 2013-301 Scenario # 1 Event # 4 Page 18 of 64 Event
Description:
Rapid Power Reduction Time Position Applicant's Actions or Behavior No action required for Event 4, Rapid Power reduction SRO Directs performance of AOP-C.03 RAPID SHUTDOWN OR LOAD REDUCTION.
SRO Appendix D Scenario Outline Attachment 1 Op Test No.: 2013-301 Scenario # 1 Event # 4 Page 19 of 64 Event
Description:
Rapid Power Reduction Time Position Applicant's Actions or Behavior SRO Chooses a power reduction rate of 1% final power level of 20% and BAT as the boration source. (1% to 3% acceptable.)
CREW CREW Examiner note: Appendix B reactor and turbine trip criteria see page 31 CREW CREW Makes notifications as required.
ATC Appendix D Scenario Outline Attachment 1 Op Test No.: 2013-301 Scenario # 1 Event # 4 Page 20 of 64 Event
Description:
Rapid Power Reduction Time Position Applicant's Actions or Behavior ATC Examiner Note: The SRO addresses step 5b as no, but does not implement the RNO since a Turbine Runback has not occurred.
SRO SRO Determines ~550 gal as required to reduce power from 76% to 20%.
SRO SRO Chooses a 1% load reduction rate. (1% to 3% acceptable.)
ATC Appendix D Scenario Outline Attachment 1 Op Test No.: 2013-301 Scenario # 1 Event # 4 Page 21 of 64 Event
Description:
Rapid Power Reduction Time Position Applicant's Actions or Behavior ATC Examiner Note: If the SRO addresses step 5g RNO as required, Emergency Boration using Appendix I will be implemented, and the crew will go to step 5J go to page 24 for details.
ATC ATC Examiner note: Appendix H Actions are listed in the following steps.
ATC ATC Records 550 gal as required at 15 to 45 gpm ATC ATC Places HS-62-140A to STOP.
ATC ATC Places HS-62-140B to BORATE Appendix D Scenario Outline Attachment 1 Op Test No.: 2013-301 Scenario # 1 Event # 4 Page 22 of 64 Event
Description:
Rapid Power Reduction Time Position Applicant's Actions or Behavior ATC ATC Places FIC-62-139 to 15 to 45 gpm.
ATC ATC Places FQ-62-139 to 550 gal. ATC ATC Places HS-62-140A to START ATC ATC ATC Adjusts FIC-62-139 as required.
ATC ATC ATC Records time boration initiated.
ATC ATC Places HS-62-140A to STOP.
Appendix D Scenario Outline Attachment 1 Op Test No.: 2013-301 Scenario # 1 Event # 4 Page 23 of 64 Event
Description:
Rapid Power Reduction Time Position Applicant's Actions or Behavior ATC ATC ATC Places FIC-62-139 to 27.
ATC ATC Places HS-62-140B to AUTO.
ATC ATC Places HS-62-140A to START.
ATC ATC Places HS-62-230A BA Transfer Pump 1A to STOP Places HS-62-230A BA Transfer Pump 1A to START.
ATC Places HS-62-232A to BA Transfer Pump 1B to STOP Places HS-62-232A to BA Transfer Pump 1B to START.
ATC ATC Records 550 gal as required at 15 to 45 gpm ATC ATC Places HS-62-230D BA Transfer Pump 1A Speed Sel and or HS-62-232D BA Transfer Pump 1B Speed Sel to FAST AND Places HS-62-230A BA Transfer Pump 1A and or HS-62-232A BA Transfer Pump 1A Appendix D Scenario Outline Attachment 1 Op Test No.: 2013-301 Scenario # 1 Event # 4 Page 24 of 64 Event
Description:
Rapid Power Reduction Time Position Applicant's Actions or Behavior ATC ATC Adjusts FCV-62-138 to between 30 to 45 gpm.
ATC ATC Records the flow and time boration initiated.
ATC ATC Examiner Note: The crew continues actions to lower plant power using AOP-C.03 RAPID SHUTDOWN OR LOAD REDUCTION here.
BOP BOP Adjusts load rate approx 1% to 3% per minute
Appendix D Scenario Outline Attachment 1 Op Test No.: 2013-301 Scenario # 1 Event # 4 Page 25 of 64 Event
Description:
Rapid Power Reduction Time Position Applicant's Actions or Behavior BOP BOP Adjusts setter to approx. 15 BOP BOP Depresses GO pushbutton.
BOP ATC Appendix D Scenario Outline Attachment 1 Op Test No.: 2013-301 Scenario # 1 Event # 4 Page 26 of 64 Event
Description:
Rapid Power Reduction Time Position Applicant's Actions or Behavior ATC Coordinates with the BOP to maintain T-avg/Program T-ref mismatch less than 3°F using the TI-28 figure 3 or ICS.
BOP BOP Examiner Note: Appendix C, Secondary Plant Equipment starts at page 32.
Appendix D Scenario Outline Attachment 1 Op Test No.: 2013-301 Scenario # 1 Event # 4 Page 27 of 64 Event
Description:
Rapid Power Reduction Time Position Applicant's Actions or Behavior CREW CREW CREW ATC ATC Places Pressurizer Backup Heaters to ON, as required.
Appendix D Scenario Outline Attachment 1 Op Test No.: 2013-301 Scenario # 1 Event # 4 Page 28 of 64 Event
Description:
Rapid Power Reduction Time Position Applicant's Actions or Behavior CREW Appendix D Scenario Outline Attachment 1 Op Test No.: 2013-301 Scenario # 1 Event # 4 Page 29 of 64 Event
Description:
Rapid Power Reduction
Appendix D Scenario Outline Attachment 1 Op Test No.: 2013-301 Scenario # 1 Event # 4 Page 30 of 64 Event
Description:
Rapid Power Reduction Examiner Note: When the crew has sufficiently reduced power the Lead Examiner may go to the next event starting at page 35.
Appendix D Scenario Outline Attachment 1 Op Test No.: 2013-301 Scenario # 1 Event # 4 Page 31 of 64 Event
Description:
Rapid Power Reduction
Appendix D Scenario Outline Attachment 1 Op Test No.: 2013-301 Scenario # 1 Event # 4 Page 32 of 64 Event
Description:
Rapid Power Reduction
Appendix D Scenario Outline Attachment 1 Op Test No.: 2013-301 Scenario # 1 Event # 4 Page 33 of 64 Event
Description:
Rapid Power Reduction
Appendix D Scenario Outline Attachment 1 Op Test No.: 2013-301 Scenario # 1 Event # 4 Page 34 of 64 Event
Description:
Rapid Power Reduction
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 5 Page 35 of 64 Event
Description:
1A MFW Pump Oil Leak Time Position Applicant's Actions or Behavior Direct the Simulator Operator to initiate Event 5, 1A MFW Pump Oil Leak Indications/Alarms Annunciator: 1-M-5 3B A-1, "MAIN FEEDWATER PUMP TURBINE 1A ABNORMAL" 3B A-3, "TURBINE OR PMP BEARING OIL PRESSURE LOW" Indications:
1-M-5 PI-46-12 Bearing Oil Pressure.
Examiner Note: Several steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.
BOP Responds to ARP 1-AR-M3B A-3.
BOP Places HS-46-9A 1A MFP RESET/TRIP to TRIP.
SRO Transitions to AOP-S.01, Section 2.4 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 5 Page 36 of 64 Event
Description:
1A MFW Pump Oil Leak Time Position Applicant's Actions or Behavior SRO Directs actions of AOP-S.01, Section 2.4 BOP BOP BOP BOP Crew Performs a Crew Brief as time allows.
Crew Notifications should be addressed as applicable if not specifically addressed by the procedure or in the crew brief. Operations Management - Typically Shift Manager.
Maintenance Personnel - Typically Maintenance Shift Supervisor (MSS). (Note: Maintenance notification may be delegated to the Shift Manager). Lead Examiner may cue the next event when desired.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 6, 7, 8 Page 37 of 64 Event
Description:
- 1 S/G SGTR/#1 S/G ADV Fail Open Time Position Applicant's Actions or Behavior Simulator Operator: When directed, initiate Event 6 Indications available: RCS pressure lowering rapidly Numerous radiation monitor alarms RCS pressure lowering. #1 SG Level increasing Examiner Note: The following steps come from AOP-R.01, STEAM GENERATOR TUBE LEAK and may be performed as the SGTL degrades.
ATC ATC If pressurizer level is still dropping, places HS-FCV-62-72, FCV-62-73 CLOSED, and FCV-62-74 to CLOSE. (If not already performed.)
ATC May place HS-62-108A 1A Charging Pump to START.
SRO Transitions to E-0. Reactor Trip or Safety Injection Examiner Note: following IOA performance, prior to Steps 1-4 immediate action verification, ATC/BOP surveys MCBs for any expected automatic system response that failed to occur. Upon discovery, they may take manual action(s) to align plant systems as expected for the event in progress. (Ref. EPM-4, Prudent Operator Actions)
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 6, 7, 8 Page 38 of 64 Event
Description:
- 1 S/G SGTR/#1 S/G ADV Fail Open Time Position Applicant's Actions or Behavior Examiner Note: MONITOR status trees, the crew will implement status tree monitoring via ICS. When a RED or ORANGE path status tree is observed, the SRO will designate one of the Board operators (typically the BOP) to verify status tree conditions using 1-FR-0, UNIT 1 STATUS TREES. Once verified, the SRO should direct the crew to transition to the appropriate RED and/or ORANGE path procedure(s). CREW Performs the first four steps of E-0 unprompted.
ATC Manually trips the Reactor ATC Manually initiates Safety Injection.
SRO Directs performance of E-0, Reactor Trip Or Safety Injection.
ATC BOP CRITICAL TASK BOP Places HS-47-24 Turbine Trip to TRIP.
BOP ATC BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 6, 7, 8 Page 39 of 64 Event
Description:
- 1 S/G SGTR/#1 S/G ADV Fail Open Time Position Applicant's Actions or Behavior SRO/ATC Continue with the performance of E-0 REACTOR TRIP OR SAFETY INJECTION BOP Performs ES-0.5, Equipment Verifications go to page 49 for details SRO Addresses foldout page.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 6, 7, 8 Page 40 of 64 Event
Description:
- 1 S/G SGTR/#1 S/G ADV Fail Open Time Position Applicant's Actions or Behavior ATC ATC/BOP Manually controls AFW flow to maintain total AFW flow greater than 440 gpm until S/G are greater than 10% NR in at least 1 S/G.
ATC Examiner Note: The crew may take action using the Foldout Page (FOP) to isolate the #1 Steam Generator now. ATC/BOP Places HS-1-4A, 1-11A, 1-22A and 1-29A MSIV's to CLOSE.
Critical Task ATC/BOP Places HS-3 164A 1A-A AFP LCV to S/G #1 to RAMP CLOSE until valve indicates closed.
Critical Task ATC/BOP Places HS-3 174A S/G 1 Turbine AFP LCV to CLOSE and PTL.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 6, 7, 8 Page 41 of 64 Event
Description:
- 1 S/G SGTR/#1 S/G ADV Fail Open Time Position Applicant's Actions or Behavior ATC ATC/BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 6, 7, 8 Page 42 of 64 Event
Description:
- 1 S/G SGTR/#1 S/G ADV Fail Open Time Position Applicant's Actions or Behavior ATC/BOP Manually controls AFW flow to maintain total AFW flow greater than 440 gpm and less than 600 gpm until at least one S/G level is greater than 10% NR.
ATC ATC Examiner Note: MONITOR status trees, the crew will implement status tree monitoring via SPDS. When a RED or ORANGE path status tree is observed, the SRO will designate one of the Board operators (typically the BOP) to verify status tree conditions using 1-FR-0, UNIT 1 STATUS TREES. Once verified, the SRO should direct the crew to transition to the appropriate RED and/or ORANGE path procedure(s).
SRO Transitions to E-2 FAULTED STEAM GENERATOR ISOLATION SRO Directs actions from E-2 FAULTED STEAM GENERATOR ISOLATION Critical Task ATC/BOP Places HS-1-4A, 1-11A, 1-22A and 1-29A MSIV's to CLOSE. (If not already performed.)
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 6, 7, 8 Page 43 of 64 Event
Description:
- 1 S/G SGTR/#1 S/G ADV Fail Open Time Position Applicant's Actions or Behavior CREW Identifies #1 S/G is faulted.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 6, 7, 8 Page 44 of 64 Event
Description:
- 1 S/G SGTR/#1 S/G ADV Fail Open Time Position Applicant's Actions or Behavior Critical Task ATC/BOP Places HS-3 164A 1A-A AFP LCV to S/G #1 to RAMP CLOSE until valve indicates closed. (If not already performed.)
Critical Task ATC/BOP Places HS-3 174A S/G 1 Turbine AFP LCV to CLOSE and PTL. (If not already performed.)
ATC/BOP ATC/BOP Places HS-1-15A TDAFWP steam supply from S/G #1 to CLOSE and HS-1-16A TDAFWP steam supply from S/G #4 to OPEN. (If not already performed.)
SRO SRO determines S/G #1 is ruptured and transitions to E-3, Steam Generator Tube Rupture. SRO Direct performance of E-3, Steam Generator Tube Rupture SRO Addresses foldout page, see next page for details.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 6, 7, 8 Page 45 of 64 Event
Description:
- 1 S/G SGTR/#1 S/G ADV Fail Open
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 6, 7, 8 Page 46 of 64 Event
Description:
- 1 S/G SGTR/#1 S/G ADV Fail Open Time Position Applicant's Actions or Behavior ATC ATC Crew CREW Determines SG 1 IS RUPTURED
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 6, 7, 8 Page 47 of 64 Event
Description:
- 1 S/G SGTR/#1 S/G ADV Fail Open Time Position Applicant's Actions or Behavior ATC/BOP ATC/BOP Places PIC-1-6A setpoint to 87% ATC/BOP SRO Determines SG 1 IS RUPTURED ATC/BOP Places HS-1-15A TDAFWP steam supply from S/G #1 to CLOSE and HS-1-16A TDAFWP steam supply from S/G #4 to OPEN. (If not already performed.)
ATC/BOP ATC/BOP Critical Task ATC/BOP Places HS-1-4A MSIV to CLOSE (If not already performed.)
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 2013-301 Scenario # 1 Event # 6, 7, 8 Page 48 of 64 Event
Description:
- 1 S/G SGTR/#1 S/G ADV Fail Open Time Position Applicant's Actions or Behavior ATC/BOP Critical Task ATC/BOP Places HS-3 164A 1A-A AFP LCV to S/G #1 to RAMP CLOSE until valve indicates closed. (If not already performed.)
Critical Task ATC/BOP Places HS-3 174A S/G 1 Turbine AFP LCV to CLOSE and PTL. (If not already performed.)
ATC/BOP SRO Examiner Note: If #1 S/G is NOT 550 psig or below go to page 55 for additional E-3 steps. Scenario may be terminated when the SRO transitions to ECA-3.1or earlier, at discretion of Lead Examiner Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # ES-0.5 Page 49 of 64 Event
Description:
Equipment Verifications Time Position Applicant's Actions or Behavior ES-0.5 Actions BOP BOP BOP BOP BOP BOP BOP BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # ES-0.5 Page 50 of 64 Event
Description:
Equipment Verifications Time Position Applicant's Actions or Behavior BOP BOP BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # ES-0.5 Page 51 of 64 Event
Description:
Equipment Verifications Time Position Applicant's Actions or Behavior BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # ES-0.5 Page 52 of 64 Event
Description:
Equipment Verifications Time Position Applicant's Actions or Behavior BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # ES-0.5 Page 53 of 64 Event
Description:
Equipment Verifications Time Position Applicant's Actions or Behavior BOP BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # ES-0.5 Page 54 of 64 Event
Description:
Equipment Verifications Time Position Applicant's Actions or Behavior BOP BOP BOP BOP BOP BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # Critical Task Page 55 of 64 Event
Description:
E-3 Steps if #1 S/G Pressure is Above 550 psig.
Time Position Applicant's Actions or Behavior E-3 Actions if ECA-3.1 is NOT entered.
ATC/BOP SRO/ATC Determine target cooldown temperature of approx 420 to 430 deg F.
BOP Places HS-63-135A and 135B LO STM LINE PRESS SIS BLOCK to BLOCK, as required.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # Critical Task Page 56 of 64 Event
Description:
E-3 Steps if #1 S/G Pressure is Above 550 psig.
Time Position Applicant's Actions or Behavior BOP Raises output on PIC-1-13A, 24A, and 31A ATM Relief Control to open three ATM Relief Valves.
CRITICAL TASK BOP Reduces output on PIC-1-13A, 24A, and 31A ATM Relief Control to 0 when target temperature is reached.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # Critical Task Page 57 of 64 Event
Description:
E-3 Steps if #1 S/G Pressure is Above 550 psig.
Time Position Applicant's Actions or Behavior ATC ATC ATC Depresses HS-63-134A and 134B SIS RESET TRAIN A & B BOP ATC ATC Depresses HS-30-63D and 63E Phase A Isol Reset Train A & Train B Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # Critical Task Page 58 of 64 Event
Description:
E-3 Steps if #1 S/G Pressure is Above 550 psig.
Time Position Applicant's Actions or Behavior ATC ATC Places HS-74-10A and 20A RHR Pumps 1A and 1B to STOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # Critical Task Page 59 of 64 Event
Description:
E-3 Steps if #1 S/G Pressure is Above 550 psig.
Time Position Applicant's Actions or Behavior BOP CRITICAL TASK BOP Reduces output on PIC-1-13A, 24A, and 31A ATM Relief Control to 0 when target temperature is reached.
BOP ATC Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # Critical Task Page 60 of 64 Event
Description:
E-3 Steps if #1 S/G Pressure is Above 550 psig.
Time Position Applicant's Actions or Behavior
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # Critical Task Page 61 of 64 Event
Description:
E-3 Steps if #1 S/G Pressure is Above 550 psig.
Time Position Applicant's Actions or Behavior ATC Places PIC-68-340A PZR PRESSURE CONTROL to MANUAL and raises output. ATC Reduces PIC-68-340A PZR PRESSURE CONTROL output when depressurization criteria is met.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # Critical Task Page 62 of 64 Event
Description:
E-3 Steps if #1 S/G Pressure is Above 550 psig.
Time Position Applicant's Actions or Behavior ATC ATC ATC Places HS-63-10A and 15A SI Pump 1A and 1B to STOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # Critical Task Page 63 of 64 Event
Description:
E-3 Steps if #1 S/G Pressure is Above 550 psig.
Time Position Applicant's Actions or Behavior ATC ATC Places HS-63-39A and 40A CCPIT inlet isolation valves to CLOSE ATC Places HS-63-25A and 26A CCPIT outlet isolation valves to CLOSE Scenario may be terminated when the CCPIT is isolated or earlier, at discretion of Lead Examiner.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 1 Event # Critical Task Page 64 of 64 Event
Description:
Critical Tasks Critical Tasks: Critical Task Statement 1 Manually trip the main turbine prior to the completion of E-0.
2 Isolate AFW flow into the ruptured (#1) SG by closing FCV-3-164 and 3-174 before a transition to ECA-3.1 occurs.
As required. Establish cooldown and maintain RCS temperature so that transition from E3 does not occur because the RCS temperature causes an extreme (red-path) or a severe (orange-path) challenge to the subcriticality and/or the integrity CSF. (As required.)
Appendix D Scenario Outline Form ES-D-1 Facility: Sequoyah Scenario No.: 3 Op Test No.: 2013-301 Examiners: Operators: Initial Conditions: Unit 1 is in MODE 2, ~4% Reactor Power, A Main Feedwater Pump I/S Turnover: Continue Plant Startup. Currently at 0-GO-4, Section 5.1 Step 4. Place Feed Regulating valves in AUTO, then increase power to 13-15%. D RCW pump is OOS for maintenance. PT-3-1A is in Maintenance Bypass Target CTs: Manually initiate a Phase B isolation prior to completing ES-0.5 step 13. Isolate AFW Flow to #4 Steam Generator Prior to completing E-2 step 4.
Event No. Malf. No. Event Type* Event Description 1. N/A R-ATC Continue Power Increase from ~4%. 1.a N/A N-BOP/SRO Place feed Reg Valves in AUTO using 0-GO-4.Section 5.1 Step 4. 2. IMF NI04B I-ATC/SRO TS-SRO IR Channel N-36 fails higher than normal, the crew will place N36 Level Trip switch in BYPASS using AOP-I.01. The SRO will address Tech Specs and enter LCO 3.3.1.1 Action 3b and 3.3.3.7, Action 1a. 3. IMF CC11A Pre-insert IMF CC21B C-BOP/SRO The 1A Thermal Barrier Booster Pump breaker trips and the 1B Thermal Barrier Booster Pump fails to AUTO Start. The BOP manually starts the 1B Thermal Barrier Booster Pump using the ARP and AOP M.03, LOSS OF COMPONENT COOLING WATER. 4. RX31AUTO C-ATC/SRO TS-SRO PIC-68-340A Pressurizer Master Controller fails with maximum output. The ATC will take manual control of PIC-68-340 to close the Pressurizer Spray valves and energize Pressurizer heaters. The SRO will address Tech Specs and enter LCO 3.2.5 action. 5. IMF SI11D TS-SRO RWST level indicator LT-63-53 fails low, the crew will respond using AOP-I.09 RWST LEVEL INSTRUMENT MALFUNCTION. The SRO will address Tech Specs and enter LCO 3.3.1.1 Action 18. 6. FW23A M-All A Feed line break will develop on the #4 Steam Generator inside containment, the crew will initiate a Reactor Trip and Safety Injection and transitions to E-0. 7. Pre-insert RP07 C-ATC During the performance of E-0, the Hi-Hi Containment pressure logic to initiate Phase B containment isolation fails. The ATC will manually initiate a Phase B using prudent operator actions. 8. Pre-insert ZDIHS6523A C-BOP The EGTS fans fail to AUTO-START, the BOP will manually start the EGTS fans using Prudent Operator Actions or guidance from ES-0.5. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline 2013-301 Scenario 3 Summary EVENT 1 - The crew will assume the shift, place the feed reg valves in AUTO using 0-GO-4.Section 5.1 Step 4 and continue the power increase.
EVENT 2 - When directed by the lead examiner, IR Channel N-36 fails higher than normal, the crew will place N36 Level Trip switch in BYPASS using AOP-I.01 NUCLEAR INSTRUMENT MALFUNCTION. The SRO will enter LCO 3.3.1.1 Action 3b and LCO 3.3.3.7, Action 1a.
EVENT 3 - When directed by the lead examiner, the 1A Thermal Barrier Booster Pump breaker trips and the 1B Thermal Barrier Booster Pump fails to AUTO Start. The BOP manually starts the 1B Thermal Barrier Booster Pump using the ARP and AOP M.03, LOSS OF COMPONENT COOLING WATER.
EVENT 4 - When directed by the lead examiner, PIC-68-340A Pressurizer Master Controller fails with maximum output. The ATC will take manual control of PIC-68-340 to close the Pressurizer Spray valves and energize Pressurizer heaters. The SRO will address Tech Specs and enter LCO 3.2.5 action.
EVENT 5 - When directed by the lead examiner, RWST level indicator LT-63-53 fails low, the crew will respond using AOP-I.09 RWST LEVEL INSTRUMENT MALFUNCTION. The SRO will address Tech Specs and enter LCO 3.3.1.1 Action 18.
EVENT 6 - When directed by the lead examiner, a Feed line break will develop on the #4 Steam Generator inside containment, the crew will initiate a Reactor Trip and Safety Injection and transitions to E-0 REACTOR TRIP OR SAFETY INJECTION. The crew will transition to E-2, FAULTED STEAM GENERATOR ISOLATION and ultimately ES-1.1, SI TERMINATION. When status tree monitoring commences, the crew will identify an orange path condition and implement FR-Z.1 for High Containment Pressure.
EVENT 7 - During the performance of E-0, the Hi-Hi Containment pressure logic to initiate Phase B containment isolation fails. The ATC will manually initiate a Phase B using prudent operator actions.
EVENT 8 - During performance of the EOP's, the EGTS fans fail to AUTO-START, the BOP will manually start the EGTS fans using Prudent Operator Actions or guidance in ES-0.5, EQUIPMENT VERIFICATIONS. The scenario terminates as directed by the Lead Examiner upon transition to ES-1.1, SI TERMINATION.
EOP flow: E-0, FR-Z.1, E-2, ES-1.1
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 1 Page 1 of 48 Event
Description:
Raise plant power to 13-15% RTP Time Position Applicant's Actions or Behavior Booth Operator: No action required for event 1 Examiner Note:
The crew will shift Feed Reg Valves to AUTO using 0-GO-4, Section 5.1 Actions To Be Performed Prior To Raising Reactor Power.
BOP BOP Depresses AUTO pushbutton for FIC-3-35, 48, 90 and 103.
SRO Direct a load increase in accordance with 0-GO-4, Reactor Power Ascension To Between 13% And 15% RTP, Section 5.2, and 0-SO-62-7 Boron Concentration Control, Section 6.1 or Section 6.2.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 1 Page 2 of 48 Event
Description:
Raise plant power to 13-15% RTP Time Position Applicant's Actions or Behavior CREW Examiner Note:
The following Steps are from 0-SO-62-7 Boron Concentration Control, Section 6.2, Dilute Examiner Note: Dilutions will be performed based on the Reactor Engineering provided Reactivity Spreadsheet; based on 0-GO-4 Notes, recommended dilution rate is 50 to 75 gallon batches every 12 to 15 minutes for a steady power increase. During subsequent power escalation, large volume dilutions will be divided evenly over each hour as determined by the crew [i.e.: one-third, one-quarter of the volume over each hour's period (e.g.: ~60 gallons, 4 times per hour for 240 gallons for the first hour)]. ATC [1] ENSURE unit is NOT in a Tech Spec or TRM action that prohibits positive reactivity additions.
[C.1] NOTE: HUT level increase of 1% is equal to 1380 gallons (TI-28 fig. 34).
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 1 Page 3 of 48 Event
Description:
Raise plant power to 13-15% RTP Time Position Applicant's Actions or Behavior ATC [2] ENSURE sufficient capacity available in the HUT selected to receive expected amounts of CVCS letdown: (N/A if not used)
HUT LEVEL INITIALS A ___________
% ___________
B ___________
% ___________
ATC [3] ENSURE makeup system is aligned for AUTO operation in accordance with Section 5.1. ATC [4] RECORD the quantity of dilution water required to achieve desired boron concentration using Appendix D. (N/A for minor power changes)
NOTE Due to eyeball interpolation the verified calculation may slightly differ from the initial calculation. The following si gnoff indicates that any differences in the two results have been discussed and are close enough to be considered
validated.
ATC [5] PERFORM Appendix I Independent Verification of Calculation for Amount of Boric Acid or Primary Water. (N/A if App. D was performed by SRO to verify
data from Rx Engineering) (Step not required provided in shift turnover package)
ATC [6] PLACE [HS-62-140A], Boric Acid Supply to Blender Flow Control Switch to the STOP position.
ATC [7] PLACE [HS-62-140B], CVCS Makeup Selector Switch to the DILUTE position.
ATC [8] ENSURE [HS-62-140D], Boric Acid Valve to the Blender is CLOSED (Green light is LIT). ATC [9] SET [FQ-62-142], Batch Integrator for the desired quantity NOTE 4 Primary Water Flow Controller
[FC-62-142] receives its reference signal (70 gpm) from setpoint potentiometer (dial indicator) located on panel M-6. A setpoint of 35% corresponds to a 70 gpm primary water flow rate ATC [10] ADJUST [FC-62-142], Primary Makeup Water Flow Controller for the desired flow rate ATC [11] PLACE [HS-62-140A], Boric Acid Supply to Blender Flow Control Switch to the START position. ATC [12] VERIFY the following;
[a] Inlet to top of VCT
[FCV-62-128]
is OPEN. [b] Primary Water flow by
[FI-62-142A]
OR [FQ-62-142]
.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 1 Page 4 of 48 Event
Description:
Raise plant power to 13-15% RTP Time Position Applicant's Actions or Behavior NOTE Alternate dilution in small amounts is acceptable on a regular basis, provided no significant changes in seal water temperature or seal leakoff are indicated. Batches of 5 to 10 gallons may be added through FCV-62-144 on a frequency not to exceed once per 30 minutes. ICS points for No. 1 seal leakoffs and seal water temperatures on the RCPs should be monitored during and after dilution.
ATC [13] IF primary water addition to the bottom of the VCT [FCV-62-144]
is desired, THEN ATC [a] CLOSE [FCV-62-128]
with [HS-62-128]. ATC [b] OPEN [FCV-62-144]
with [HS-62-144]. ATC [c] VERIFY Primary Water flow by
[FI-62-142A]
OR [FQ-62-142]. NOTE 5 It may take approximately 15 minutes before any changes to reactivity are indicated on nuclear instrumentati on or RCS temperature indication. ATC [14] MONITOR nuclear instrumentation and reactor coolant temperature to ensure the proper response from dilution.
ATC [15] IF [LI-62-129], Volume Control Tank Level, increases to 63 percent, THEN ENSURE [LCV-62-118], Volume Control Tank Divert Valve OPENS to divert excess water to the Holdup Tanks.
ATC [16] WHEN dilution is complete, THEN ATC [a] PLACE [HS-62-140A], Boric Acid to Blender Flow Control Switch to the STOP position. ATC [b] IF [FCV-62-144]
was previously OPENED , THEN CLOSE
[FCV-62-144]
with [HS-62-144]. ATC [c] VERIFY no primary water flow on either
[FI-62-142A]
OR [FQ-62-142]. ATC [d] ENSURE
[FCV-62-128]
is CLOSED ATC [17] IF power increase in progress and additional dilutions will be required, THEN use this table to re-perform steps
[4] through [18] (next page)
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 1 Page 5 of 48 Event
Description:
Raise plant power to 13-15% RTP
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 1 Page 6 of 48 Event
Description:
Raise plant power to 13-15% RTP Time Position Applicant's Actions or Behavior ATC [19] REALIGN the blender controls for AUTO makeup to the CVCS in accordance with Section 5.1.
ATC [20] ENSURE dilution(s) is logged in Unit Narrative Log.
NOTE 6 Sample may be obtained at normal RCS sample intervals provided the unit is at power and the unit response following the dilution is as expected.
ATC [21] IF RCS boron sample is required, THEN NOTIFY Chem Lab to obtain RCS boron sample.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 1 Page 7 of 48 Event
Description:
Raise plant power to 13-15% RTP Time Position Applicant's Actions or Behavior 0-GO-4, Section 5.2 Reactor Power Ascension To Between 13% And 15% RTP Examiner Note:
Crew will coordinate control rod withdrawal and dilutions based on the Reactor Engineering provided Reactivity Spreadsheet and would coordinate rod withdrawal and dilutions observing the guidance of Step 3 NOTES above on page 2.
Examiner Note: Mode change call is made using Loop T indications on the MCB and ICS, not NIs; NIs may be referred to during the MODE change determination Refer to 0-GO-4 Section 3.1, Precaution C, specifically bullets 2 & 3 (below):
ATC [4] WHEN reactor power is above 5%, THEN LOG Mode 1 entry in the Unit Narrative Log.
SRO ATC would be monitoring the mode change; any crew member may make the initial identification however the SRO should announce transition to MODE 1 based on Loop T indication. Normally, both MCB and ICS indications are reviewed for MODE transition verification. Crew member replaces the MODE 2 sign with MODE 1 sign on 1-M-4 under the clock.
BOP Examiner Note: According to turnover information, the crew will not prepare for nor perform MT roll; Step 6 is N/A for this exam.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 1 Page 8 of 48 Event
Description:
Raise plant power to 13-15% RTP Time Position Applicant's Actions or Behavior N/A [6] IF Turbine Roll in parallel with power increase is desired, THEN PERFORM Section 5.3 in parallel with the remainder of this section.
ATC [7] IF the intermediate range rod stop setpoint is reached before P-10 energizes, THEN [7.1] STOP the power escalation.
[7.2] CONTACT Reactor Engineering to evaluate power range calibration.
[C.3] When the crew has sufficiently raised power the Lead examiner may proceed to Event 2.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 1 Page 9 of 48 Event
Description:
Raise plant power to 13-15% RTP Examiner note: The following 4 pages are the guidance for maintaining S/G levels using the DCS (Digital Feed Control) and may or may not be used.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 1 Page 10 of 48 Event
Description:
Raise plant power to 13-15% RTP
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 1 Page 11 of 48 Event
Description:
Raise plant power to 13-15% RTP
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 1 Page 12 of 48 Event
Description:
Raise plant power to 13-15% RTP
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 2 Page 13 of 48 Event
Description:
IR Channel B Instrument N-36 Fails Time Position Applicant's Actions or Behavior At 6% NI power during a control rod withdrawal, direct the Simulator Operator to initiate Event 2 IR Channel N-36 Fails.
Indications available: 4B B2 IPRS NIS Intermediate Range HI FLUX LVL ROD WITHDRAWAL STOP Control Rod motion stops, if in progress. Intermediate Range Instrument N-36 is greater than N-35 Examiner Note: Several steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.
ATC Responds to alarm using ARP 1-AR-M4B, B2 SRO Transitions to AOP-I.01, Nuclear Instrument Malfunction.
SRO Directs actions using AOP-I.01, Nuclear Instrument Malfunction.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 2 Page 14 of 48 Event
Description:
IR Channel B Instrument N-36 Fails Time Position Applicant's Actions or Behavior SRO SRO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 2 Page 15 of 48 Event
Description:
IR Channel B Instrument N-36 Fails Time Position Applicant's Actions or Behavior
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 2 Page 16 of 48 Event
Description:
IR Channel B Instrument N-36 Fails Time Position Applicant's Actions or Behavior SRO Enters LCO 3.3.1.1 Action 3 and 3.3.3.7, Action 1.
ATC ATC ATC ATC ATC Places N-36 Trip Level Bypass switch to BYPASS.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 2 Page 17 of 48 Event
Description:
IR Channel B Instrument N-36 Fails Time Position Applicant's Actions or Behavior Crew Performs a Crew Brief as time allows.
Crew Notifications should be addressed as applicable if not specifically addressed by the procedure or in the crew brief. Operations Management - Typically Shift Manager.
Maintenance Personnel - Typically Maintenance Shift Supervisor (MSS).
(Note: Maintenance notification may be delegated to the Shift Manager).
Lead Examiner may cue next event when N-36 Trip Level switch has been placed in bypass.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 3 Page 18 of 48 Event
Description:
1A Thermal Barrier Booster Pump Breaker Trips Time Position Applicant's Actions or Behavior Direct the Simulator Operator to initiate Event 3, 1A Thermal Barrier Booster Pump Trip Indications available: 0-M-27-B-A Annunciators: 0-XA-27-B-A Window B-1: RC PUMPS THRM BARRIER RETURN HEADER FLOW LOW 0-XA-27-B-A Window B-2: RC PUMP 1 BARRIER Outlet FLOW LOW 0-XA-27-B-A Window B-3: RC PUMP 2 BARRIER Outlet FLOW LOW 0-XA-27-B-A Window B-4: RC PUMP 3 BARRIER Outlet FLOW LOW 0-XA-27-B-A Window B-5: RC PUMP 4 BARRIER Outlet FLOW LOW BOP Responds to ARP 0-AR-M27B-A B-1.
BOP May place HS-70-130A Thermal Barrier Booster Pump 1B-B to START and HS-70-131A Thermal Barrier Booster Pump 1A-A to STOP based on prudent operator actions.
Examiner Note: Several steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.
SRO Transitions to AOP-M.03 Loss Of Component Cooling Water section 2.2 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 3 Page 19 of 48 Event
Description:
1A Thermal Barrier Booster Pump Breaker Trips Time Position Applicant's Actions or Behavior BOP BOP Places HS-70-131A Thermal Barrier Booster Pump 1A-A to STOP PTL.
BOP BOP BOP Places HS-70-130A Thermal Barrier Booster Pump 1B-B to START if not already done.
BOP BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 3 Page 20 of 48 Event
Description:
1A Thermal Barrier Booster Pump Breaker Trips Time Position Applicant's Actions or Behavior BOP SRO BOP SRO Crew Performs a Crew Brief as time allows.
Crew Notifications should be addressed as applicable if not specifically addressed by the procedure or in the crew brief. Operations Management - Typically Shift Manager.
Maintenance Personnel - Typically Maintenance Shift Supervisor (MSS). (Note: Maintenance notification may be delegated to the Shift Manager). Evaluator Note: Proceed to the next event when ready
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 4 Page 21 of 48 Event
Description:
Pressurizer Master Controller Fails With Maximum Output Time Position Applicant's Actions or Behavior Direct the Simulator Operator to initiate Event 4 Pressurizer Master Controller Fails With Maximum Output Alarms 1-M-5 5A B-3 "PS 68 340F/G PRESSURIZER PRESS ABOVE REF SET POINT" Indications 1-M-4 RCS Pressurizer Main Spray Valves OPEN 1-PI-68-334, 323, 322 RCS PZR PRESS indicators decreasing Time Position Applicant's Actions or Behavior Examiner Note: Several steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.
ATC Responds to alarm using ARP 1-AR-M5A, B3 ATC Places PIC-68-340A, Master Pressure Controller in MANUAL and lowers output. OR Places PZR Spray controllers PIC-68-340D (Loop 1) and PIC-68-340B (Loop 2) and lowers output. Using immediate operator actions (IOAs)
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 4 Page 22 of 48 Event
Description:
Pressurizer Master Controller Fails With Maximum Output Time Position Applicant's Actions or Behavior SRO Transitions to AOP-I.04 Pressurizer Instrument And Control Malfunctions.
SRO ATC Places Master Pressure Controller in MANUAL OR Spray controllers PIC-68-340D (Loop 1) and PIC-68-340B (Loop 2) in MANUAL if not already performed during IOA's.
ATC ATC May energize additional Pressurizer heaters.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 4 Page 23 of 48 Event
Description:
Pressurizer Master Controller Fails With Maximum Output Time Position Applicant's Actions or Behavior ATC ATC ATC ATC ATC Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 4 Page 24 of 48 Event
Description:
Pressurizer Master Controller Fails With Maximum Output Time Position Applicant's Actions or Behavior ATC SRO SRO Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 4 Page 25 of 48 Event
Description:
Pressurizer Master Controller Fails With Maximum Output Time Position Applicant's Actions or Behavior SRO If in MODE 1 enters LCO 3.2.5 Action if Pressurizer Pressure decreases to less than 2220 psia.
ATC ATC Maintains RCS Pressure control with PIC-68-340 or Pressurizer Spray valves in MANUAL. Lead Examiner may cue next event when Pressurizer Pressure control is established in MANUAL and Tech Specs are identified.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 5 Page 26 of 48 Event
Description:
RWST Level Indicator Fails Low Time Position Applicant's Actions or Behavior Direct the Simulator Operator to initiate Event 5 RWST level indicator LT-63-53 fails low.
Alarms 6E, E-3 "LS-63-50A RWST LVL LO" 6E, E4 "LS-63-50B RWST LVL LO-LO" Indications 1-M-6 LI-63-53 indicates 0.
Time Position Applicant's Actions or Behavior Examiner Note: Several steps, notes, and cautions in the Annunciator response procedure do not apply to this failure. Only those that are applicable are listed in this event guide.
ATC Responds to alarm using ARP 1-AR-M6E, E3 SRO Transitions to AOP-I.09 RWST LEVEL INSTRUMENT MALFUNCTION.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 5 Page 27 of 48 Event
Description:
RWST Level Indicator Fails Low Time Position Applicant's Actions or Behavior SRO Enters LCO 3.3.2.1 Action 18.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 5 Page 28 of 48 Event
Description:
RWST Level Indicator Fails Low Time Position Applicant's Actions or Behavior SRO SRO Lead Examiner may cue next event when Tech Specs are identified.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 6, 7, 8 Page 29 of 48 Event
Description:
- 4 SG FWLB Inside Cont/Failure of Phase B/EGTS Auto Start Failure Time Position Applicant's Actions or Behavior Simulator Operator: When directed, initiate Event 6 #4 Steam Generator Feed Line Break Inside Containment. Indications available: Annunicators: 1-M-6 6B, C-6, "CONTAINMENT HI-HI PRESSURE SPRAY ACTUATION" 6E, C-6 "ZS-61-186 ICE CONDENSER LOWER INLET DOOR OPEN" Indicators: 1-M-4 SG-4 FW INLET FLOW increasing SG-4 NR LEVEL: decreasing level SRO Transitions to E-0 and Direct Immediate Operator Actions (IOAs) Examiner Note: following IOA performance, prior to Steps 1-4 immediate action verification, ATC/BOP surveys MCBs for any expected automatic system response that failed to occur. Upon discovery, they may take manual action(s) to align plant systems as expected for the event in progress. (Ref. EPM-4, Prudent Operator Actions) CREW Performs the first four steps of E-0 unprompted.
SRO Directs performance of E-0 ATC Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 6, 7, 8 Page 30 of 48 Event
Description:
- 4 SG FWLB Inside Cont/Failure of Phase B/EGTS Auto Start Failure Time Position Applicant's Actions or Behavior BOP BOP ATC CRITICAL TASK BOP Places HS-30-64A and 64B Phase B and CNTMT Vent Isol to ACTUATE BOP SRO/ATC Continue with the performance of E-0 REACTOR TRIP OR SAFETY INJECTION BOP Performs ES-0.5, Equipment Verifications go to page 41 for details SRO Addresses foldout page, see next page for details.
ATC Places HS 68-8A, 31A, 50A, and 73A RCP's to STOP based on FOP criteria.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 6, 7, 8 Page 31 of 48 Event
Description:
- 4 SG FWLB Inside Cont/Failure of Phase B/EGTS Auto Start Failure
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 6, 7, 8 Page 32 of 48 Event
Description:
- 4 SG FWLB Inside Cont/Failure of Phase B/EGTS Auto Start Failure Time Position Applicant's Actions or Behavior CRITICAL TASK ATC/BOP Places HS-3-161A, AFP 1B-B LCV to SG-4 to ACC RESET then CLOSE Places HS-3-175A, SG-4 Turbine AFP LCV to CLOSE and PTL.
ATC ATC/BOP Manually controls AFW flow to maintain total AFW flow greater than 440 gpm until S/G are greater than 10% NR in at least 1 S/G. (25% ADV) NR.
ATC Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 6, 7, 8 Page 33 of 48 Event
Description:
- 4 SG FWLB Inside Cont/Failure of Phase B/EGTS Auto Start Failure Time Position Applicant's Actions or Behavior ATC ATC Places HS 68-8A, 31A, 50A, and 73A RCP's to STOP (If not already performed.).
ATC/BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 6, 7, 8 Page 34 of 48 Event
Description:
- 4 SG FWLB Inside Cont/Failure of Phase B/EGTS Auto Start Failure Time Position Applicant's Actions or Behavior ATC/BOP Manually controls AFW flow to maintain total AFW flow greater than 440 gpm and less than 600 gpm until at least one S/G level is greater than 10% NR. ATC ATC Examiner Note: MONITOR status trees, the crew will implement status tree monitoring via ICS. When a RED or ORANGE path status tree is observed, the SRO will designate one of the Board operators (typically the BOP) to verify status tree conditions using 1-FR-0, UNIT 1 STATUS TREES. Once verified, the SRO should direct the crew to transition to the appropriate RED and/or ORANGE path procedure(s). When a RED Path for Containment is evident on ICS, the SRO will transition to FR-Z.1, go to page 41 for details. SRO Transitions to E-2, Faulted Steam Generator Isolation.
ATC Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 6, 7, 8 Page 35 of 48 Event
Description:
- 4 SG FWLB Inside Cont/Failure of Phase B/EGTS Auto Start Failure Time Position Applicant's Actions or Behavior BOP SRO SRO Identifies #4 S/G as faulted.
BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 6, 7, 8 Page 36 of 48 Event
Description:
- 4 SG FWLB Inside Cont/Failure of Phase B/EGTS Auto Start Failure Time Position Applicant's Actions or Behavior BOP CRITICAL TASK ATC/BOP Places HS-3-161A, AFP 1B-B LCV to SG-4 to ACC RESET then CLOSE Places HS-3-175A, SG-4 Turbine AFP LCV to CLOSE and PTL. If not already performed.
BOP BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 6, 7, 8 Page 37 of 48 Event
Description:
- 4 SG FWLB Inside Cont/Failure of Phase B/EGTS Auto Start Failure Time Position Applicant's Actions or Behavior BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 6, 7, 8 Page 38 of 48 Event
Description:
- 4 SG FWLB Inside Cont/Failure of Phase B/EGTS Auto Start Failure Time Position Applicant's Actions or Behavior ATC SRO Transitions to ES-1.1, SI TERMINATION. Scenario may be terminated when the SRO transitions to ES-1.1 or earlier, at discretion of Lead Examiner.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 5, 6, 7 Page 39 of 48 Event
Description:
- 4 Steam Generator FWLB IS Cont/Failure of Phase B/Failure of EGTS Auto Start.
Time Position Applicant's Actions or Behavior FR-Z.1 Actions ATC/BOP ATC/BOP ATC/BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # 5, 6, 7 Page 40 of 48 Event
Description:
- 4 Steam Generator FWLB IS Cont/Failure of Phase B/Failure of EGTS Auto Start.
Time Position Applicant's Actions or Behavior ATC/BOP SRO Transitions to E-2 (go to page 34).
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # ES-0.5 Page 41 of 48 Event
Description:
Equipment Verifications Time Position Applicant's Actions or Behavior ES-0.5 Actions BOP BOP BOP BOP BOP BOP Places 0-HS-65-23A EGTS Fan A and 0-HS-65-42A EGTS Fan B to START BOP BOP BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # ES-0.5 Page 42 of 48 Event
Description:
Equipment Verifications Time Position Applicant's Actions or Behavior BOP BOP BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # ES-0.5 Page 43 of 48 Event
Description:
Equipment Verifications Time Position Applicant's Actions or Behavior BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # ES-0.5 Page 44 of 48 Event
Description:
Equipment Verifications Time Position Applicant's Actions or Behavior BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # ES-0.5 Page 45 of 48 Event
Description:
Equipment Verifications Time Position Applicant's Actions or Behavior CRITICAL TASK BOP Places HS-30-64A and 64B Phase B and CNTMT Vent Isol to ACTUATE BOP BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # ES-0.5 Page 46 of 48 Event
Description:
Equipment Verifications Time Position Applicant's Actions or Behavior BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # ES-0.5 Page 47 of 48 Event
Description:
Equipment Verifications Time Position Applicant's Actions or Behavior BOP BOP BOP BOP BOP Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC 2013-301 Scenario # 3 Event # Critical Task Page 48 of 48 Event
Description:
Critical Task Critical Tasks: Critical Task Statement 1. Manually initiate a Phase B isolation prior to completing ES-0.5 step 13. 2. Isolate AFW Flow to #4 Steam Generator Prior to completing E-2 step 4.