ML22139A308

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Retake Scenario 1 and 2 ES-D-1s
ML22139A308
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 07/24/2019
From: Randy Baker
NRC/RGN-III/DRS/OLB
To:
Exelon Generation Co
Baker R
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ML19161A059 List:
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Download: ML22139A308 (8)
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Quad Cities 2019-301 NRC EXAM Scenario 1

Exelon Nuclear

2019-301 ILT NRC Exam Scenario

Scenario Number:

NRC Scenario 1

Revision Number: 00

Date: 05/28/2019

Developed by:

Instructor Date

Validated by:

SME or Instructor Date

Reviewed by:

Operations Facility Representative Date

Approved by:

Training Department Date

Quad Cities 2019-301 NRC EXAM Scenario 1 Appendix D Scenario Outline Form ES-D-1

Facility: Quad Cities Scenario: 2019-301 NRC Scenario 1 Op-Test No.: ILT 19-301 Examiners: ________________________ Operators:_____________________________

Initial Conditions:

The plant is operating at 80% power with Drywell Spray Valve 23A is inoperable, Day 2 of a 7-Day of TLCO 3.6.a Condition a. 2A SW Pump and 1B EHC Pump are OOS.

Turnover: Start the third RFP. Return to full power.

Event Malf. No. Event Event No. Type* Description 1 None BOP Start a third Reactor Feed Pump IAW QOP 3200- 03 N

2 None ATC Normal Power up IAW REMA R

3 RM05B SRO B Drywell Rad Monitor Upscale Failure TS TS 4 ED08Q SRO MCC 30 Feed Breaker trip on overcurrent TS TS 5 MC08 ATC Loss of Main Turbine Vacuum/ Emergency Power C Reduction 6 RR10A BOP Slow Recirc Leak resulting in a Scram C

7 RR10A Crew High Drywell Pressure results in entry into QGA 100 M and 200.

8 HP11 BOP HPCI fails to initiate automatically. BOP must start C HPCI manually.

9 DIHS11001S17B Crew Div 2 Drywell Spray valves fail to open, Emergency M Depressurization per QGA 500- 1 when PSP exceeded 10 Crew Reference leg flashing results in entry into QGA 500-M 4

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

ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 7 BOP Normal: E1 Malfunction(s) after EOP (1-2): E8, 9 ATC Reactivity (1 per set): E2 Abnormal Events (2-4): E5, 6 BOP I/C (4 per set): E6, E8 Major Transient(s) /E-Plan entry (1-2): E7 ATC I/C (4 per set): E5 EOPs (1-2): QGA 100, 200 SRO-I I/C (4 per set inc 2 as ATC):

EOP Contingencies (0500-4 - 2): QGA 500-1, E5, 6, 8 Critical Tasks (2-3): 2 SRO Tech Spec (2 per set): E3, 4 ALL Major Transients (2 per set) E6

Quad Cities 2019-301 NRC EXAM Scenario 1

SUMMARY

  • Initial Conditions:

Drywell Spray Valve 23A is inoperable, Day 2 of a 7-Day LCO 2A SW Pump is OOS 1B EHC Pump is OOS

  • Event 1: The BOP will start a third Reactor Feed Pump IAW QOP 3200 -03.
  • Event 2: Raise Reactor Power using REMA.
  • Event 4: MCC 30 Feed Breaker trips. Report from EO is that the breaker tripped on overcurrent. SRO enters TS 3.7.9.A.
  • Event 5: An air leak will result in lowering Main Condenser Vacuum. The crew performs QOA 3300- 02 and Emergency Power Reduction. Prompt action by Equipment Operators to re-fill a loop seal line will stabilize Main Condenser Vacuum.
  • Event 6: A Recirc leak will develop in the Drywell causing Drywell Pressure to rise resulting in BOP performing actions of QCOA 201- 01. Drywell pressure will stabilize when the 7th drywell cooler is started
  • Event 7: Recirc Leak will become larger causing drywell pressure to rise at a greater rate. When Drywell Pressure reaches scram criteria, ATC will SCRAM the Reactor. All three Reactor Feed Pumps will trip when the Scram has been inserted. SRO will enter QGA 100 and 200.
  • Event 8: HPCI will fail to start automatically at 2.5# drywell pressure. BOP must start HPCI manually IAW QCOP 2300- 06.
  • Event 9: When Division 2 Containment Spray valves cannot be opened, the crew must Blowdown per QGA 200 and 500- 1, in order to avoid exceeding Pressure Suppression Pressure (PSP).
  • After Blowdown has commenced, the drywell will reach saturation conditions. The SRO will enter QGA 500-4 and flood the RPV to the Main Steam Lines.
  • Approximate Run Time: 1.5 Hours

Quad Cities 2019-301 NRC EXAM Scenario 1

CRITICAL TASKS:

Critical Task #1 When Drywell temperature CANNOT be maintained < 280 F OR Torus pressure CANNOT be maintained < the Pressure Suppression Pressure Limit, (PSP),

INITIATE an Emergency Depressurization..

Critical Task #2: When RPV Level cannot be determined, flood the RPV to the elevation of the Main Steam Lines.

Quad Cities 2019-301 NRC EXAM Scenario 2

Exelon Nuclear

2019-301ILT NRCExam Scenario

Scenario Number:

NRC Scenario 2

Revision Number: 00

Date: 05/28/2019

Developed by:

Instructor Date

Validated by:

SME or Instructor Date

Reviewed by:

Operations Facility Representative Date

Approved by:

Training Department Date

Quad Cities 2019-301 NRC EXAMScenario 2

Appendix D Scenario Outline Form ES-D-1

Facility: Quad Cities Scenario No. 2019 -301 NRC Scenario 2 Op-Test No. ILT 19-301 Examiners: ________________________ Operators:_____________________________

Initial Conditions:

A normal plant shutdown is in progress currently at 75 % power.

Turnover: Reduce Recirc Flow to Lower Reactor power.

Event Malf. No. Event Event No. Type* Description 1 None ATCR Reduce Recirc Flow to Lower Reactor power.

2 SER1494 Feed Pump Vent Fan degraded.

AOTI324087 ATC C

3 FW01A ATC 1A RFP trips with the standby RFP failing to auto-FW02 C start. ATC will start the 1C RFP per QCOA 3200-01 4 BOP Stuck open relief valve (QCOA 0203- 01) and AD01D AD07D C Reactor Scram

5 RD13A Crew Hydraulic ATWS. Crew Takes actions per QGA 101 M to control reactor power, level and pressure.

6 RD27C ATC Running CRD pump trips. ATC takes actions to start C standby CRD pump

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 5 BOP Normal:

Malfunction(s) after EOP (1-2): E6 ATC Reactivity (1 per set): E1 Abnormal Events (2-4): E2, 3, 4 BOP I/C (4 per set): E4 Major Transient(s) /E-Plan entry (1-2): E5 ATC I/C (4 per set): E2, 3, 6 EOPs (1-2): QGA 100 SRO-I I/C (4 per set inc 2 as ATC): E2, 3, 4, 6 EOP Contingencies (0- 2): QGA 101 SRO Tech Spec (2 per set):

Critical Tasks (2-3): 3 ALL Major Transients (2 per set) E5

Quad Cities 2019-301 NRC EXAMScenario 2

SUMMARY

  • Initial Conditions:

o The plant is operating at 75%.

o Relief valve 3D Tailpipe Temperature is elevated and rising 1 °F/Day.

  • Event 1: The SRO and ATC reduce Recirc Flow to Lower Reactor power.
  • Event 2: A Reactor Feed Pump vent fan will become degraded, requiring a shift to the alternate fan after receiving high temp alarms.
  • Event 3. 1A RFP trips with a failure of 1C RFP auto-starting. ATC will take actions per QCOA 3200- 01 to start the 1C RFP and perform Emergency Power Reduction if necessary to maintain RWL.
  • Event 4: The D Relief Valve will actuate and stick open. The crew responds per QCOA 0203- 01 and scram the reactor prior to exceeding 95° F Torus Water Temperature. The Relief valve will close after the ATWS.
  • Event 5: When the ATC inserts a manual scram no control rods will insert. The crew will recognize they are in a hydraulic ATWS and enter QGA 100, RPV Control and then they will rapidly transition to QGA 101 RPV Control (ATWS). The crew will attempt to insert control rods per QCOP 0300- 28, but they will have little success beyond driving individual driving rods. The SRO will enter the Level/Power Control section of QGA 101 and lower reactor level to control reactor power.
  • Event 6: After entry into QGA 101, the running CRD pump will trip. ATC will take actions per QCOA 0300- 01 to start the standby CRD pump.
  • Approximate Run Time: 1 Hour

Quad Cities 2019-301 NRC EXAMScenario 2 CRITICAL TASKS:

Critical task #1: With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron (prior to exceeding 110°F torus temperature) and/or inserting control rods, to prevent exceeding primary containment design limits. (BWROG RPV-6.1 ATWS PWR/LVL S/D REACTOR)

Critical task #2: With a reactor scram required and the reactor not shutdown, and conditions for ADS blowdown are met, INHIBIT ADS to prevent an uncontrolled RPV depressurization, to prevent causing a significant power excursion. (BWR RPV-6.2 ATWS PWR/LVL INHIBIT ADS)

Critical task #3: During an ATWS with conditions met to perform power/level control, TERMINATE AND PREVENT INJECTION, with the exception of boron, CRD and RCIC into the RPV until conditions are met to re-establish injection.

(BWROG RPV-6.3 PWR/LVL TERM/PREVENT)

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