ML22174A073
| ML22174A073 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 12/20/2019 |
| From: | Randy Baker NRC/RGN-III/DRS/OLB |
| To: | Exelon Generation Co |
| Baker R | |
| Shared Package | |
| ML19121A241 | List: |
| References | |
| Download: ML22174A073 (8) | |
Text
19-1 NRC 1 Page 1 of 2 Simulation Facility:
Braidwood Scenario No.:
NRC 1 Operating Test No.: 19-1 NRC Examiners:
Applicant:
SRO ATC BOP Initial Conditions:
IC-22 Turnover:
Unit 1 is at 100%, steady state, Equilibrium Xenon, MOL. On-line risk is Green. Automatic rod control failed last shift, control rods are in MANUAL. Following turnover, swap WS pumps per BwOP WS-1 & 3 to allow for an oil change next shift on the 0A WS pump and place the 0A WS pump in standby. EOs are briefed and standing by at the LSH.
Event No.
Malf. No.
Event Type*
Event Description Preload IMF RX17A FALSE IMF RX17B FALSE IRF RP35 OUT IRF RP61 OUT IOR ZDI1SI8801A CLS IRF RP75 OUT Automatic rod withdrawal fails Automatic rod insertion fails Prevent auto MSLI (train A)
Prevent auto MSLI (train B)
Prevent 1SI8801A from opening on SI Prevent train B CV/SI valves from auto opening/closing on SI 1
None N-BOP N-SRO Swap WS pumps (start 0B WS pump, shutdown 0A WS pump) 2 IMF CV16 100 I-ATC I-SRO VCT level channel, 1LT-112, fails high 3
IMF CV01A C-ATC C, T-SRO 1A CV pump trip 4
IMF TC14D 0 IMF RX17A FALSE (preload)
IMF RX17B FALSE (preload)
R-ATC R-SRO Governor Valve #4 fails closed with rods in manual control 5
IMF RX18A 630 T-SRO Loop 1A Tave channel fails high 6
IMF TP19A RAISE I-BOP I-SRO Main Generator H2 temperature controller, 1TK-HY001, setpoint fails high 7
IMF TH03D 450 30 IMF FW19D 2 M-ALL SGTR on 1D SG 1D SG feedline break (faulted/ruptured SG) 8 IRF RP35 OUT (preload)
IRF RP61 OUT (preload)
C-ATC C-SRO Prevent auto MSLI (train A)
Prevent auto MSLI (train B) 9 IRF RP75 OUT (preload)
IOR ZDI1SI8801A CLS (preload)
C-ATC C-SRO Prevent train B CV/SI valves from auto opening/closing on SI Prevent 1SI8801A from opening on SI
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient
19-1 NRC 1 Page 2 of 2 SCENARIO OVERVIEW Unit 1 is at 100%, steady state, Equilibrium Xenon, MOL. On-line risk is Green. Automatic rod control failed last shift, control rods are in MANUAL. Following turnover, swap WS pumps per BwOP WS-1 & 3 to allow for an oil change next shift on the 0A WS pump and place the 0A WS pump in standby. EOs are briefed and standing by at the LSH.
After completing shift turnover, the crew will swap WS pumps. The crew will start the 0B WS pump per BwOP WS-1 and then shutdown the 0A WS pump and place it in standby per BwOP WS-3.
After the WS pumps have been swapped, VCT level channel, 1LT-112, will fail high. Letdown flow will divert to the HUT and the ATC must reposition 1CV112A to restore letdown flow to the CV demineralizers. The SRO will enter 1BwOA INST-2.
After the actions for the VCT level channel failure are complete, the 1A CV pump will trip. The ATC will use 1BwPR 1-9-A3 to isolate letdown. The crew will use 1BwOA PRI-15 to start the 1B CV pump and then use 1BwOA ESP-2 to restore letdown. The SRO will enter Tech Spec 3.5.2 Condition A and TRM 3.1.d Condition A.
After the SRO has evaluated Tech Specs for the 1A CV pump trip, Governor Valve (GV) #4 will fail closed with control rods in MANUAL. Turbine load will lower approximately 60 MWe. The ATC will borate the RCS as necessary and/or manually move control rods to restore RCS Tave and Delta I to within their normal band.
After the GV #4 reactivity change is adequately evaluated, the loop 1A Tave channel will fail high (Tcold RTD failure). The SRO will enter 1BwOA INST-2 and enter Tech Spec 3.3.1 Conditions A and E.
After the SRO has evaluated Tech Specs for the loop 1A Tave channel failure, the Main Generator H2 temperature controller, 1TK-HY001, setpoint will fail high. The BOP will take manual control of 1TK-HY001 and will throttle H2 cooling valve, 1WS106, open to lower the Main Generator H2 temperature to a normal value.
After the plant is stabilized from the Main Generator H2 temperature controller failure, a SGTR will occur on the 1D SG followed by a 1D SG feedline break. The BOP will respond to the main steamline rad monitor alarm. The ATC will determine that PZR level is lowering > 2% per minute. The SRO will direct the ATC to manually trip the reactor, verify reactor trip and then insert a manual SI. The SRO will enter 1BwEP-0. One minute after the SGTR, a feedline break inside containment will occur on the 1D SG feedline. After SI actuates, high head SI does NOT automatically align, the ATC must manually open 1SI8801B. The MSIVs will NOT auto close and must be manually closed. The crew will transition to 1BwEP-3. The crew will transition to 1BwEP-2 and isolate AF to the 1D SG. The crew will then transition to 1BwCA-3.1 and perform actions through step 8, check if RH pumps should be stopped.
Scenario completion criteria is when the crew places both RH pumps in standby in 1BwCA-3.1.
Critical Tasks:
(Westinghouse - CT-7) (K/A number - 013 A4.01, Importance - 4.5/4.8)
- 2. Isolate the 1D SG before transition out of 1BwEP-2. (Westinghouse - CT-17)
(K/A Number - APE040 AA1.10, Importance - 4.1/4.1)
19-1 NRC 2 Page 1 of 2 Simulation Facility Braidwood Scenario No.:
NRC 2 Operating Test No.: 19-1 NRC Examiners:
Applicant:
SRO ATC BOP Initial Conditions:
IC-16 Turnover:
Unit 1 is at 53%, steady state, Equilibrium Xenon, MOL. On-line risk is Green. Following turnover, lower reactive load by 1 KV per TSO direction received just prior to turnover.
The BOP will lower reactive load per BwOP MP-23. Unit 2 is in a refueling outage. Early this shift, the load ascension to full power is expected to commence (recent grid emergency conditions have been resolved).
Event No.
Malf. No.
Event Type*
Event Description Preload IMF RH01A IMF CS01A IRF RP63 OUT 1A RH pump trip 1A CS pump trip 1B CS pump auto-start failure 1
None N-BOP N-SRO Lower reactive load by 1 KV 2
IMF RH05D 100 T-SRO RWST level channel, 1LT-933, fails high 3
IMF CV44A RAISE I-ATC I-SRO Letdown HX temperature controller, 1TK-0130, setpoint fails high 4
IMF RX17B FALSE IMF RX17A TRUE C-ATC C-SRO Uncontrolled rod withdrawal 5
IMF NI09B 0 T-SRO PRNI channel N-42 fails low 6
None R-ATC R-SRO Ramp unit to 1120 MWe at 1.6 MWe/minute with rods in manual 7
IMF EG03 90 96 180 C-BOP C-SRO Main Generator voltage regulator failure 8
IMF TH06C 540000 30 M-ALL Large break RCS LOCA 9
IMF RH01A (preload)
C-BOP C-SRO 1A RH pump trip 10 IMF CS01A (preload)
IRF RP63 OUT (preload)
C-BOP C-SRO 1A CS pump trip 1B CS pump auto-start failure
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient
19-1 NRC 2 Page 2 of 2 SCENARIO OVERVIEW Unit 1 is at 53%, steady state, Equilibrium Xenon, MOL. On-line risk is Green. Following turnover, lower reactive load by 1 KV per TSO direction received just prior to turnover. The BOP will lower reactive load per BwOP MP-23. Unit 2 is in a refueling outage. Early this shift, the load ascension to full power is expected to commence (recent grid emergency conditions have been resolved).
After completing shift turnover, the crew will lower reactive load by 1 KV. The crew will lower reactive load by 1 KV per BwOP MP-23.
After lowering reactive load, RWST level channel, 1LT-933, will fail high. The SRO will enter 1BwOA INST-2 and enter Tech Spec 3.3.2 Conditions A and K.
After the SRO has evaluated Tech Specs for the RWST level channel failure, the Letdown HX temperature controller, 1TK-0130, setpoint will fail high. This will cause a high letdown temperature and the crew will respond using BwAR 1-8-C5. The ATC will place 1TK-0130 in manual and restore letdown temperature to normal.
After the Letdown HX temperature controller setpoint failure actions are completed, uncontrolled rod withdrawal will occur. The ATC to respond per 1BwPR 1-10-RD and will place rods in manual to stop the rod withdrawal. The SRO will enter 1BwOA ROD-1. Rods will remain in Manual control for the remainder of the scenario.
After the uncontrolled rod withdrawal actions are completed, PRNI channel N-42 will fail low. The crew will respond to the failure and the SRO enter 1BwOA INST-1. The SRO will enter Tech Spec 3.3.1 Conditions A, D & E. Bistables will not be tripped or bypassed for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> due to a callout to obtain additional NSO support.
After the SRO has evaluated Tech Specs for the PRNI channel failure, the load dispatcher will request that the crew starts the load ramp to full power. The BOP will initially program the turbine to ramp to 1120 MWe at 1.6 MWe/minute per 1BwGP 100-3. The ATC will dilute the RCS to support the load ramp per BwOP CV-5 and/or reposition control rods as required.
After the load ramp reactivity change is adequately evaluated, a Main Generator voltage regulator failure will occur. The BOP will use 1BwPR 1-19-B6 and take the voltage regulator to off and adjust the base adjuster to lower exciter field current. The BOP will then review BwAR 1-19-B6 for subsequent operator actions (i.e., inform TSO, NDO, etc.). NOTE: If the crew takes no action for this failure, a main generator/turbine trip will occur in ~ 3 minutes.
After the plant is stabilized from the Main Generator voltage regulator failure, a large break RCS LOCA will occur. A reactor trip and SI will automatically occur. The SRO will enter 1BwEP-0. The 1A RH pump will trip and neither train of CS will start; the 1B CS pump can be manually started. The crew will transition to 1BwEP-1. Once the RWST level LO-2 annunciator alarms, the crew will transition to 1BwEP ES-1.3 and will align the 1B RH train for cold leg recirculation.
Scenario completion criteria is when the crew aligns 1B RH train for cold leg recirculation.
Critical Tasks:
- 1. Manually lower main generator exciter field current to prevent a main generator/turbine trip. (K/A number - 045 GEN2.1.7, Importance - 4.4/4.7)
(Westinghouse - CT-3) (K/A number - 026 A4.01, Importance - 4.5/4.3)
- 3. Transfer to cold leg recirculation and establish ECCS recirculation flow before RWST level drops to
< 9%. (Westinghouse - CT-36) (K/A number - EPE011 EA1.11, Importance - 4.2/4.2)
19-1 NRC 3 Page 1 of 2 Simulation Facility Braidwood Scenario No.:
NRC 3 Operating Test No.: 19-1 NRC Examiners:
Applicant:
SRO ATC BOP Initial Conditions:
IC-18 Turnover:
Unit 1 is at 75%, steady state, Equilibrium Xenon, MOL. On-line risk is Green. Following turnover, swap 75 gpm letdown orifices per BwOP CV-9 for a PMT after a cracked fuse holder was replaced on 1CV8149C.
Event No.
Malf. No.
Event Type*
Event Description Preload IMF CC02B 151 IMF FW35B IMF RP02A/B IMF RD09 8 Fail 1B CC pump discharge pressure switch 1B HD pump trip Fail RTA & RTB closed Fail auto rod speed at 8 steps/min 1
None N-BOP N-SRO Swap 75 gpm letdown orifices (close 1CV8149B, open 1CV8149C) 2 IMF CC01B IMF CC02B 151 (preload)
C-BOP C, T-SRO 1A CC pump trip with 1B CC pump failure to auto-start 3
IMF TH07 3 C-ATC C-SRO Reactor vessel flange leak 4
IMF FW35A IMF FW35B (preload)
R-ATC R-SRO 1A HD pump trip with 1B HD pump tripped (turbine runback) 5 IMF d9mod4127c2f UNBLKD IMF d9mod4131c2f UNBLKD IMF d8mod131c3f OPEN IMF d8mod142c3f OPEN I-ATC I, T-SRO PZR PORV 1RY456 inadvertently opens (manual closure available) 6 IMF RP02A/B (preload)
IMF TH16C M-ALL 1C RCP trip/ATWS 7
IMF RD09 8 (preload)
I-ATC I-SRO Fail auto rod speed at 8 steps/min 8
IMF MS07C 4 20 M-ALL 1C SG steam break inside Cnmt
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient
19-1 NRC 3 Page 2 of 2 SCENARIO OVERVIEW Unit 1 is at 75%, steady state, Equilibrium Xenon, MOL. On-line risk is Green. Following turnover, swap 75 gpm letdown orifices per BwOP CV-9 for a PMT after a cracked fuse holder was replaced on 1CV8149C.
After completing shift turnover, the crew will swap 75 gpm letdown orifices. The BOP will close 1CV8149B, then open 1CV8149C per BwOP CV-9.
After swapping 75 gpm letdown orifices, 1A CC pump will trip with a 1B CC pump failure to auto-start (failed discharge pressure switch). The BOP will respond per BwAR 1-2-A4 and will manually start the 1B CC pump. The SRO will enter Tech Spec 3.7.7 Condition B (entry is initially made, then exited once the control switch for the 1A CC pump is placed in PULL OUT).
After the SRO has evaluated Tech Specs for the 1A CC pump trip, a reactor vessel flange leak will occur. The ATC will respond per BwAR 1-14-E5 and will close 1RC8032 to stop the leak. The crew will request local leak isolation actions per BwAR 1-14-E5.
After the reactor vessel flange leak actions are completed, a 1A HD pump trip with the 1B HD pump tripped will occur. The standby 1B HD pump will not start and a HD runback will be initiated by the BOP per 1BwPR 1-17-D2. The ATC will borate the RCS during the HD runback. The SRO will enter 1BwOA SEC-1.
After the HD pump trip reactivity change is adequately evaluated, PZR PORV 1RY456 will inadvertently open. The ATC will respond per 1BwPR 1-12-RY and will manually close 1RY456 (or close block valve 1RY8000B). The SRO will enter Tech Spec 3.4.1 Condition A when PZR pressure drops below 2209 psig.
After the SRO has evaluated Tech Specs for the PZR PORV failing open, a 1C RCP trip/ATWS/1C SG steam break inside Cnmt will occur. The 1C RCP will trip and the reactor will not trip manually or automatically. The SRO will initially enter 1BwEP-0, then transition to 1BwFR-S.1. The ATC must manually insert rods with rod speed failed at 8 steps/min and the BOP will initiate an emergency boration.
After the reactor is locally tripped and 1BwFR-S.1 is completed, the crew will transition back to 1BwEP-0 and a 1C SG steam break will occur. After determining that the 1C SG secondary pressure boundary is not intact, the crew will transition to 1BwEP-2 and isolate AF to the 1C SG. The crew will transition to 1BwEP ES-1.1 based on meeting the criteria for reducing ECCS flow.
Scenario completion criteria is the crew establishing charging flow in 1BwEP ES-1.1.
Critical Tasks:
- 1. Close PZR PORV 1RY456 (or close 1RY456 isolation valve 1RY8000B) prior to a reactor trip.
(K/A number - 010 A4.03, Importance - 4.0/3.8)
- 2. Insert negative reactivity into the core by at least manually inserting control rods or initiating emergency boration before completing step 4 of 1BwFR-S.1. (Westinghouse - CT-52) (K/A number -
EPE029 EA1.14, Importance - 4.2/3.9)
- 3. Isolate 1C Steam Generator before transition out of 1BwEP-2.
(Westinghouse - CT-17) (K/A number - APE040 AA1.10, Importance - 4.1/4.1)
19-1 NRC 4 Page 1 of 2 Simulation Facility Braidwood Scenario No.:
NRC 4 Operating Test No.: 19-1 NRC Examiners:
Applicant:
SRO ATC BOP Initial Conditions:
IC-31 Turnover:
Unit 1 is at 90%, steady state, Equilibrium Xenon, BOL. On-line risk is Green. Following turnover, perform a 1C TDFWP PMT per 1BwOS FW-W1, TDFW Pump Stop Valve Surveillance. An EO is briefed and standing by at the 1C TDFW pump.
Event No.
Malf. No.
Event Type*
Event Description Preload IMF FW75 IMF CV32B IRF ED500 1096 Trigger 1 (RP:SI(1).EQ. 1)
IMF CV01A Prevent 1A FW pump auto-start Prevent 1B CV pump auto-start Set AND computer to current AND MWe SI actuation trigger 1A CV pump trip on SI 1
None N-BOP N-SRO Perform a 1C TDFW Pump PMT per 1BwOS FW-W1, TDFW Pump Stop Valve Surveillance 2
IMF CV05inc RAISE I-ATC I-SRO Letdown line pressure controller, 1PK-0131, setpoint fails high 3
IMF CV23A 90 C-ATC C, T-SRO 1A letdown HX tube leak 4
IMF FW02B TRIP IMF FW75 (preload)
C-BOP C-SRO 1C FW pump trip with a 1A FW pump auto-start failure 5
IRF ED500 896 R-ATC R-SRO Advanced Nuclear Dispatch (AND) order to lower load by 200 MWe at 4 MW/minute 6
IMF TH15G 0 T-SRO Loop 1D WR Thot channel fails low 7
IMF TH01.4 60 M-ALL PZR vapor space LOCA 8
IMF CV01A (preload)
IMF CV32B (preload)
C-ATC C-SRO 1A CV pump trip on SI with 1B CV pump auto-start failure
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient
19-1 NRC 4 Page 2 of 2 SCENARIO OVERVIEW Unit 1 is at 90%, steady state, Equilibrium Xenon, BOL. On-line risk is Green. Following turnover, perform a 1C TDFWP PMT per 1BwOS FW-W1, TDFW Pump Stop Valve Surveillance. An EO is briefed and standing by at the 1C TDFW pump.
After completing shift turnover, the crew will perform a 1C TDFW Pump PMT per 1BwOS FW-W1, TDFW Pump Stop Valve Surveillance. The BOP will perform a 1C TDFW pump PMT per 1BwOS FW-W1.
After completing the 1C TDFW Pump Stop Valve Surveillance PMT, the Letdown line pressure controller, 1PK-0131, setpoint will fail high. This will cause a letdown pressure high alarm and high letdown line pressure. The ATC will take manual control of 1PK-0131 per 1BwPR 1-9-LD to restore normal letdown pressure.
After the Letdown line pressure controller setpoint failure actions are completed, a 1A letdown HX tube leak will occur. The crew will identify the leak location as the 1A letdown HX and the SRO will enter 1BwOA PRI-6. The crew will swap to the 1B letdown HX per BwOP CV-22. Letdown will be restored per BwOP CV-17. The SRO will enter Tech Spec 3.4.13 Condition A.
After normal charging and letdown have been restored, a 1C FW pump trip with a 1A FW pump auto-start failure will occur. The BOP will respond per 1BwPR 1-16-A1,B1,C1 (Dual Pump Operation) and will manually start the 1A FW pump (or runback the main turbine). The SRO will enter 1BwOA SEC-1. NOTE: Failure to start the 1A FW pump (or runback the main turbine) would lead to an automatic reactor trip.
After the 1A FW pump is manually started and the plant is stable, an Advanced Nuclear Dispatch (AND) order to lower load by 200 MWe will occur. The AND ramp computer will indicate a ramp to 896 MWe is requested and the crew will call to confirm the ramp. Once the ramp is confirmed, the ramp down to 896 MWe will be commenced at 4 MW/min per the operator aid. The ATC will borate the RCS.
After the load ramp reactivity change is adequately evaluated, the loop 1D WR Thot channel will fail low. The SRO will enter 1BwOA INST-2 and enter Tech Spec 3.3.4 Condition A.
After the SRO has evaluated Tech Specs for the WR Thot channel failure, a PZR vapor space LOCA will occur. The ATC will respond to the PZR vapor space LOCA and will insert a manual reactor trip and SI. The SRO will enter 1BwEP-0. The ATC will manually start the 1B CV pump with the 1A CV pump tripped and trip the RCPs when the RCP trip criteria are met. The crew will then transition to 1BwEP-1.
Scenario completion criteria is crew entry into 1BwEP ES-1.2.
Critical Tasks:
- 1. Manually start the 1A FW pump (or runback the main turbine) prior to a reactor trip.
(K/A number - 059 A2.07, Importance - 3.0/3.3)
- 2. Manually start 1B CV pump before transition out of 1BwEP-0.
(Westinghouse - CT-6) (K/A number - 006 A4.07, Importance - 4.4/4.4)
100 gpm or SI pump discharge flow > 200 gpm) prior to transition out of 1BwEP-1.
(Westinghouse - CT-16) (K/A Number - EPE009 EA1.09, Importance - 3.6/3.6)