ML23160A191
| ML23160A191 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 03/16/2023 |
| From: | Constellation Energy Generation |
| To: | NRC/RGN-III |
| Gregory Roach | |
| Shared Package | |
| ML22007A047 | List: |
| References | |
| Download: ML23160A191 (1) | |
Text
Form 3.3-1 Scenario Outline This would be Dresdens choice to be the spare scenario.
Facility:
Dresden Scenario #: ILT-N-1 (Spare scenario)
Scenario Source:
Site developed Op. Test #: 2023-301 Examiners:
Applicants/
Operators:
Initial Conditions:
Unit 2 is at 100% power 2A EHC Pump is OOS Turnover:
Branch dP is reading ~27 feet of water and it has been determined that Circ Water Flow through the Main Condenser shall be reversed. Once flow has been reversed, exercise CRDs A-06, D-09, and N-08 per DOS 0300-01 Critical Tasks:
RPV-1.1 - If the RPV level trend is not reversible, initiate RPV blowdown with the minimum number of available ADS valves when RPV water level is between the Top-of-Active Fuel and the Minimum Steam Cooling RPV Water Level or within 2 1/2 minutes after TAF is reached, whichever is later.
RPV-1.5 - Per DEOP 100 or DEOP 0400-06 (as applicable), with the automatic ADS timer initiated, inhibit ADS before an automatic actuation occurs.
Event No.
Malf. No.
Event Type*
Event Description 1
None N
BOP (New) CIRC WATER - Reversing Circ Water Flow Through Main Condenser 2
RODD09ST C
ATC (New) CRD - Control Rod, Stuck and Requires Higher Pressure to Move 3
RLMRFBP C
ATC (New) FW - Recirc Runback, due to loss of RFP 4
RMARMPFAILF(1)
RMARMPFAILD(1)
VRMISO42A VRMISO42B MRGFPB I/
MC/TS BOP /
CRS (New) PRM - RB Fuel Pool Channel B Rad detector fails upscale causing RB Vent to isolate with failure of 2 isolation dampers to close; CRS will reference Tech Specs 5
HDD3103C2 HDD3103S2 R
ATC (New) FEEDWTER HEATING - HP Heater Trip (Reactivity move) 6 ICTUBLK C/TS BOP/
((New) LPCI - Isolable leak on 2A LPCI Pump Suction Piping, spraying onto the 2A and 2B LPCI Pump Motors 7
F41 M
CREW MANUAL SCRAM - Recirc leak in Drywell 8
RLMFAFC RLMFBFC FLMFFC HPPMGDG M
CREW (New) FWLC - Loss of all Feedwater Reg Valves HPCI degraded EMERGENCY DEPRESSURIZE - On lowering RPV water level
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control
- (New) - Event not used on previous 2 NRC Exams, (Pre) - Event used on previous 2 NRC Exams
Form 3.3-1 Scenario Outline Facility:
Dresden Scenario #: ILT-N-2 Scenario Source:
Site developed Op. Test #: 2023-301 Examiners:
Applicants/
Operators:
Initial Conditions:
Unit 2 in MODE 2 ~5% power. DGP 01-01 in progress Turnover:
Crew will swap Service Water pumps due to abnormal noises in running pump.
DGP 01-01 Step G.45 is being performed.
Critical Tasks:
PC-1.1 - While executing DEOP 200-1, when drywell pressure exceeds 11 psig and only if operating within the safe region of the drywell spray initiation limit (DSIL), initiate drywell sprays within 6 minutes of exceeding 11 psig while in an ATWS condition.
PC-1.2 - After initiating drywell sprays per the primary containment pressure or temperature legs of DEOP 200-1, terminate drywell sprays before drywell pressure drops to < 0 psig.
Event No.
Malf. No.
Event Type*
Event Description 1
None N
BOP (New) SERVICE WATER - Swap Service Water pumps 2
None R
ATC REACTIVITY - Raise Power with Rods (To get 2 Bypass valves open) 3 RODJ07DO C, TS ATC/
BOP/
K40 C, TS BOP/
CRS (New) AUX POWER - Trip of Bus 28 5
FWSACBV C,
MC ATC (PRE) HVAC - RFP Vent Fan, Trips Due to Overcurrent; failure of standby fan to auto start 6
F41 M
CREW (PRE) SLOW LEAK - Steam leak in Drywell 7
I21 M
CREW LEAK WORSENS - Leak worsens, Manual Scram, Electrical ATWS (ARI Unsuccessful)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control
- (New) - Event not used on previous 2 NRC Exams, (Pre) - Event used on previous 2 NRC Exams
Form 3.3-1 Scenario Outline Facility:
Dresden Scenario #: ILT-N-3 Scenario Source:
Site developed Op. Test #: 2023-301 Examiners:
Applicants/
Operators:
Initial Conditions:
Unit 2 in MODE 1 90% power.
APRM #6 is OOS due to faulty power supply.
Turnover:
Torus Cooling was running to support a HPCI run and can now be secured.
Critical Tasks:
SC-1.1 - While executing DEOP 300-1, before any critical area(s) reach their respective maximum safe operating values with an unisolable primary system discharging into the respective area(s),
manually scram the reactor.
SC-1.2 - While executing DEOP 300-1, when more than one critical area reaches their respective maximum safe operating values for the same parameter with an unisolable primary system discharging into the respective area(s), perform a complete RPV blowdown per DEOP 100 within 10 minutes of exceeding the same max safe parameter in multiple areas.
Event No.
Malf. No.
Event Type*
Event Description #
1 None N
BOP (New) LPCI - Secure Torus Cooling 2
RDPPATRP C, TS ATC /
CRS (Pre) CRD - CRD Pump Trip 3a SER1633 E230 C
BOP (New) AUX POWER - Main Power Transformer High Temperature 3b R
ATC REACTIVITY MOVE - Lowering power to unload MPT 4
NII12POT NIA2POT B12 I, MC, TS ATC /
CRS (New) NI - APRM Fails upscale with no half scram and one APRM already out 5
T50 T52 C,
MC BOP (Pre) GENERATOR - Stator Water Cooling Pump Trip with failure of Standby to start 6
HPRMBRKP HPGP4RLY M
CREW (New) MANUAL SCRAM - Unisolable steam leak in HPCI Room 7
Supplemental CAEP M
CREW (New) EMERGENCY DEPRESSURIZE - On 2 Areas Above Max Safe Radiation Levels Due To HPCI Steam Line Leak into the HPCI Room 8
ADS3BBN C
BOP (New) MAIN STEAM - Failure of ERV to open during Emergency Depressurization
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control
- (New) - Event not used on previous 2 NRC Exams, (Pre) - Event used on previous 2 NRC Exams
Form 3.3-1 Scenario Outline Facility:
Dresden Scenario #: ILT-N-4 Scenario Source:
Site developed Op. Test #: 2023-301 Examiners:
Applicants/
Operators:
Initial Conditions:
Unit 2 in MODE 1 81% power.
Turnover:
Swap EHC pumps.
Critical Tasks:
RPV-4.1 - When RPV water level cannot be determined by multiple direct or indirect indications as defined by DEOP 0010-10, enter DEOP 400-1, RPV Flooding, before adequate core cooling is lost as indicated by a rise in Drywell radiation levels.
RPV-4.2 - Following blowdown per DEOP 400-1 during non-ATWS RPV Flooding, maximize injection and do not divert available RPV injection flow paths until the RPV is flooded to the Main Steam Lines.
Event No.
Malf. No.
Event Type*
Event Description 1
None N
BOP (New) EHC - Swap EHC pumps 2
B15 NVM100BP I, TS, MC ATC /
CRS (New) NBI - MR Level Instrument Fails with Partial Half Scram 3
None C, TS BOP/
CRS (New) ISO COND - Iso Condenser tube leak; CRS will reference Tech Specs 4a K50 K07 C,
MC BOP (New) - TURBINE AUX - Loss Of Hydrogen Seal Oil, With Failure Of ESOP To Start 4b R
ATC (New) - Lower Reactor Power to meet turbine loading requirements with loss of seal oil 5
NONE C
BOP (New) - INST AIR - Compressor, Swap Due To Oil Leak 6
RR02A C
ATC (Pre) RECIRC - Recirc Pump Speed Controller Failure 7
NVMNRALP M
CREW (New) NBI - Narrow Range Level Reference Leg Leak, Slow rise in DW Pressure, Manual Scram 8
NVMMRALP NVML29AP NVM106AP/BP NVML112P M
CREW (Pre) Loss of Level Indication - RPV Flooding
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control
- (New) - Event not used on previous 2 NRC Exams, (Pre) - Event used on previous 2 NRC Exams