ML20153A834

Scenario D-1, Appendix D, Scenario Outline

ML20153A834
Person / Time
Site:	Quad Cities
Issue date:	04/10/2020
From:	NRC/RGN-III
To:	Exelon Generation Co
Roach G
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ML19121A185	List: ML20153A820 ML20153A823 ML20153A826 ML20153A827 ML20153A829 ML20153A830 ML20153A831 ML20153A832 ML20153A833 ML20153A834
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Download: ML20153A834 (4)

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Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario: 2020 NRC Scenario 1 Op-Test No.: ILT 18-1 Examiners: ________________________ Operators:_____________________________

Initial Conditions:

The plant is operating at 100% power, holding load.

Turnover: Reverse Main Condenser flow per QCOP 4400-09.

Critical Tasks:

1. With a primary system discharging into Secondary Containment, isolate Reactor Building ventilation. Time of manual isolation not to exceed 30 minutes from discovery of unisolable HPCI steam leak (EAL entry condition).

2. Perform an RPV Blowdown when two areas are above max safe radiation levels.

QGA 500-1 entry not to exceed 15 minutes after two or more areas of the same parameter are above max safe.

Event Malf. No. Event Event No. Type* Description 1 None BOP Reverse Main Condenser flow N

2 AOPI1514012 BOP 1A EHC pump degrades and standby pump fails to AOAI1564025 C auto-start.

SER0783 LOIL15650PANP 3 RR01A ATC 1A Recirc pump trip / Emergency Power Reduction R / TS 4 NM08A ATC APRM 1 fails to track (stuck at 100%)

C 5 DIFC1064018I2 ATC DFWLC Master Controller failure C

6 HP10 BOP HPCI spurious initiation C / TS 7 HP13 CREW HPCI Steam Line break & Fuel failure CR01 M RPV Blowdown (2 areas above max safe rad levels) 8 HV01 CREW Reactor Building Vents fail to isolate C

Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario: 2020 NRC Scenario 2 Op-Test No.: ILT 18-1 Examiners: ________________________ Operators:_____________________________

Initial Conditions:

The plant is at 40% power with a startup in progress per QCGP 1-1.

Turnover: Start the second Reactor Feed Pump per QCGP 1-1, step F.9.zz.

Critical Tasks:

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

2. 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/LVL TERM/PREVENT)

Event Malf. No. Event Event No. Type* Description 1 None BOP Start the 2nd Reactor Feed Pump N

2 None ATC Raise Reactor Power per QCGP 1-1 R

3 RD01R4631 ATC Uncoupled Control Rod with full insertion C / TS 4 SER1123 SRO 3D ERV Acoustic Monitor failure LOAM102034B4C05 TS LOAM102034B4C03 LOAM102034B4C01 5 SER1487 ATC RFP Vent Fan trip DIHS15707A C 6 MC01C BOP 1C Circulation Water Pump trip C

7 SW07A BOP RBCCW pump degradation / swap RBCCW C pumps 8 MC08 CREW Loss of Main Condenser vacuum / SCRAM M

9 RD13A CREW Full Core Hydraulic ATWS RD13B C

Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario: 2020 NRC Scenario 3 Op-Test No.: ILT 18-1 Examiners: ________________________ Operators:_____________________________

Initial Conditions: 90% Reactor power, 1B RHR pump out of service Turnover: Complete QCOS 5600-08, Turbine Generator Quarterly Testing for the Bypass Valves, then continue load increase to full power.

Critical Tasks:

1. When Torus pressure exceeds 5 psig, INITIATE drywell sprays while in the safe region of the drywell spray initiation limit (DSIL) prior to Drywell temperature exceeding 281°F. (BWROG PC-5.1 INIT DW SPRAY)

2. Given an inability to maintain RPV water level above -59 inches, INHIBIT ADS, to prevent an uncontrolled depressurization IAW QGA 100.

3. Given an inability to maintain RPV water level above -142 inches with an injection source lined-up and running, initiate an emergency depressurization before RPV water level drops to MSCRWL in accordance with QGA 100 and QGA 500-1.

(BWROG RPV-1.1 LOSS HP INJ E/D TAF)

Event Malf. No. Event Event No. Type* Description 1 None BOP QCOS 5600-08, Turbine Generator Quarterly N Testing for BPVs 7-9.

2 RR09A SRO 1A Recirc ASD cell failure/bypass.

TS 3 DIFC10262221 ATC Recirc System MASTER SPEED DEMAND Failure DIFC10262222 C 4 None ATC Raise Reactor power with Recirculation pumps R

5 NM10B ATC RBM Channel 8 fails high I/TS 6 IA01C BOP 1/2 Instrument Air Compressor trip C per QOA 912-1 C-7.

7 MC05 CREW Condensate Pit Flooding / Loss of Condensate/Feed M System / Reactor SCRAM 8 DG04B BOP 1/2 Emergency Diesel Generator to auto-start C failure.

9 RR11A CREW LOCA / RPV Blowdown M

Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario: 2020 NRC Scenario 4 Op-Test No.: ILT 18-1 Examiners: ________________________ Operators:_____________________________

Initial Conditions:

The plant is operating at 100% power.

Turnover: Swap Bus Duct Coolers for Preventive Maintenance.

Critical Tasks:

1. With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron (prior to exceeding 110ºF torus temperature) and/or inserting control rods, to prevent exceeding primary containment design limits.

(BWROG RPV-6.1 ATWS PWR/LVL S/D REACTOR)

2. When Torus pressure cannot be maintained below the Pressure Suppression Pressure Limit initiate an Emergency Depressurization prior to exceeding primary containment design limits.

Event Malf. No. Event Event No. Type* Description 1 NONE BOP Swap Bus Duct Coolers IAW QCOP 5370-02.

N 2 RM05A SRO A Drywell Rad Monitor Upscale Failure TS 3 FW06B ATC 1B RFP Flow Transmitter Downscale Failure I

4 NONE ATC Power Reduction to Secure 1B RFP R

5 PC11B BOP SBGTS Low Flow after Autostart on Refuel Floor C/TS High Radiation.

6 EG07B BOP Degraded Stator Cooling Water Pump C

7 MS04C CREW C Main Steam Line Break Inside the Drywell M

8 RP02B/D ATC Electric ATWS - Failure of RPS Channel B to RP03B C Process Scram Signals RD29 9 DIHS11001S17A BOP Drywell Spray Valves Fail to Operate / Blowdown RH20BR C