ML20153A834
| ML20153A834 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 04/10/2020 |
| From: | NRC/RGN-III |
| To: | Exelon Generation Co |
| Roach G | |
| Shared Package | |
| ML19121A185 | List: |
| References | |
| Download: ML20153A834 (4) | |
Text
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 No.
Malf. No.
Event Type*
Event Description 1
None BOP N
Reverse Main Condenser flow 2
AOPI1514012 AOAI1564025 SER0783 LOIL15650PANP BOP C
1A EHC pump degrades and standby pump fails to auto-start.
3 RR01A ATC R / TS 1A Recirc pump trip / Emergency Power Reduction 4
NM08A ATC C
APRM 1 fails to track (stuck at 100%)
5 DIFC1064018I2 ATC C
DFWLC Master Controller failure 6
HP10 BOP C / TS HPCI spurious initiation 7
HP13 CR01 CREW M
HPCI Steam Line break & Fuel failure RPV Blowdown (2 areas above max safe rad levels) 8 HV01 CREW C
Reactor Building Vents fail to isolate
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 No.
Malf. No.
Event Type*
Event Description 1
None BOP N
Start the 2nd Reactor Feed Pump 2
None ATC R
Raise Reactor Power per QCGP 1-1 3
RD01R4631 ATC C / TS Uncoupled Control Rod with full insertion 4
SER1123 LOAM102034B4C05 LOAM102034B4C03 LOAM102034B4C01 SRO TS 3D ERV Acoustic Monitor failure 5
SER1487 DIHS15707A ATC C
RFP Vent Fan trip 6
MC01C BOP C
1C Circulation Water Pump trip 7
SW07A BOP C
RBCCW pump degradation / swap RBCCW pumps 8
MC08 CREW M
Loss of Main Condenser vacuum / SCRAM 9
RD13A RD13B CREW C
Full Core Hydraulic ATWS
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 No.
Malf. No.
Event Type*
Event Description 1
None BOP N
QCOS 5600-08, Turbine Generator Quarterly Testing for BPVs 7-9.
2 RR09A SRO TS 1A Recirc ASD cell failure/bypass.
3 DIFC10262221 DIFC10262222 ATC C
Recirc System MASTER SPEED DEMAND Failure 4
None ATC R
Raise Reactor power with Recirculation pumps 5
NM10B ATC I/TS RBM Channel 8 fails high 6
IA01C BOP C
1/2 Instrument Air Compressor trip per QOA 912-1 C-7.
7 MC05 CREW M
Condensate Pit Flooding / Loss of Condensate/Feed System / Reactor SCRAM 8
DG04B BOP C
1/2 Emergency Diesel Generator to auto-start failure.
9 RR11A CREW 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 No.
Malf. No.
Event Type*
Event Description 1
NONE BOP N
Swap Bus Duct Coolers IAW QCOP 5370-02.
2 RM05A SRO TS A Drywell Rad Monitor Upscale Failure 3
FW06B ATC I
1B RFP Flow Transmitter Downscale Failure 4
NONE ATC R
Power Reduction to Secure 1B RFP 5
PC11B BOP C/TS SBGTS Low Flow after Autostart on Refuel Floor High Radiation.
6 EG07B BOP C
Degraded Stator Cooling Water Pump 7
MS04C CREW M
C Main Steam Line Break Inside the Drywell 8
RP02B/D RP03B RD29 ATC C
Electric ATWS - Failure of RPS Channel B to Process Scram Signals 9
DIHS11001S17A RH20BR BOP C
Drywell Spray Valves Fail to Operate / Blowdown