ML042190230
| ML042190230 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 07/12/2004 |
| From: | Lanksbury R NRC/RGN-III/DRS/OLB |
| To: | Cameron R Exelon Generation Co |
| References | |
| 50-456/04-301, 50-457/04-301 | |
| Download: ML042190230 (32) | |
Text
Braidwood NRC 04-1 Page 1 Simulation Facility Braidwood Scenario No.:
NRC 04-1 Operating Test No.:
2004301 Examiners:
Applicant:
__Surrogate____________
BOP LOSS OF HEAT SINK Initial Conditions:
IC-21 Turnover: 100% power, BOL, equilibrium Xenon, steady state. PRT Gas sampling in progress. 1B CV pump is running. 0 CC pump is aligned to Bus 142. Unit 2 SAC is tagged out due to high vibration problems, Diesel Backup air compressor will be on site tomorrow. 1B AF pump was tagged out for turbocharger replacement (TS 3.7.5 condition A was entered 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> ago), a test run has just failed. Unit 1 shutdown has been ordered by the OCC. On line risk status is YELLOW.
Event No.
Malf. No.
Event Type*
Event Description Preload IMF FW43 IMF RP01 IRF CC07 RI IRF CC42 RO IRF RP52 OUT IOR ZDI1IA065 OPEN IOR ZDI1IA066 OPEN IOR ZDI1RY8026 OPEN IOR ZDI1AF01PB PTL IOR ZLO1AF01PBC OFF IOR ZDI2SA01C PTL 1A AF pp Fail to start Failure of automatic Reactor Trip 0 CC pump aligned to bus 142 K606 Failure Cont Isolation Valves 1RY8026 failed open 1B AF pp OOS Unit 2 SAC OOS 1
NONE R(RO, US)
N(BOP)
IMF RX21A 1700 I(RO, US)
PZR press channel 1PT455 fails low 3
IOR ZDI0WO01PB PTL C(BOP, US) 0B VC Chill Water pump trip (This event was run concurrently with Event 1 during the examination.)
4 IMF CV23A 30 C(ALL) 30 GPM 1A Letdown HX leak 5, 6, & 7 Remote Remote Remote IMF ED05A Preload Preload, IMF MS07B 4 IRF FW150 REMOVED IRF FW151 REMOVED IRF FW149 START M (ALL)
C (RO, US)
C/M (ALL) 6.9KV bus 156 Faults Rx does not auto trip, manual Rx Trip will work.
1A AF pump fails to start. Loss of Heat Sink, 1B MS Line Faults inside containment 30 seconds after pump trip.
Remove fuses Defeat FW isolation A Train Remove fuses Defeat FW isolation B Train Starts S/U Feedwater pump Aux Oil Pump 8
Preload, CAEPs NRC 04-1 EVENT 7 and 7A C(ALL)
K606 fails to operate Cont Isolation valves fail to auto close, 1RY8026 cannot be closed from the control room
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient
Braidwood NRC 04-1 Page 2 SCENARIO OVERVIEW 100% power, BOL, equilibrium Xenon, steady state. PRT Gas sampling in progress. 1B CV pump is running. 0 CC pump is aligned to Bus 142. Unit 2 SAC is tagged out due to high vibration problems, Diesel Backup air compressor will be on site tomorrow. 1B AF pump was tagged out for turbocharger replacement (TS 3.7.5 condition A was entered 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> ago), a test run has just failed. Unit 1 shutdown has been ordered by the OCC. On line risk status is YELLOW.
About 30 minutes into the scenario, the crew should commence a power decrease at 3-6mw/min (4.5 ideally).
About 40 minutes into the scenario the controlling PZR pressure channel 1PT455 will fail low, the RO should identify the failure and take manual control of the PZR pressure master controller. US should enter 1BwOA INST 2. TSs 3.3.1 conditions A, E, and K, 3.3.2 conditions A and D, and 3.3.4 condition A should be entered.
About 60 minutes into the scenario, 0B VC Chill Water pump will trip. Local operator will identify that the breaker is tripped. US should enter TS 3.7.11 Cond A. ORAM should be evaluated. Extra Unit 2 NSO will swap VC trains.
About 65 minutes into the scenario, a 30 gpm tube leak will occur in the 1A Letdown Hx. High Radiation in the CC system will provide the initial indication. High CC surge tank level will occur, 1BwOA PRI-6 CC System Malfunction will be entered. RO should be able to identify the leak due to reduced letdown flow. Upon identification US should order letdown isolated. 1A Letdown HX CC side should be isolated and 1B letdown HX placed in service. TS 3.4.13 condition A should be entered and exited due to identified leakage.
About 90 minutes into the scenario, 6.9KV bus 159 will fault. A red first out will annunciate implying a reactor trip is warranted due to RCP low flow above P-8, however the reactor trip signal will not automatically open the reactor trip breakers. The RO should identify the red first out and immediately initiate a reactor trip. 30 seconds after the 1B RCP trip, 1B MS line will fault inside containment. An auto SI and Main Steam Isolation will occur (Manual operation is possible). 1A AF pump will fail to start. 1BwEP-0 will be entered, and at step 15 the crew will transition to 1BwFR-H.1 due to the failure of the 1A AF pump (pump seizure) and the unavailability of the 1B AF pump and S/G levels less than 31% NR. Failure of both valves in the PRT to Waste gas sampling system containment penetration will require manual closure of 1RY8025. The inside containment valve (1RY8026) will fail in mid position. The outside containment isolation (1RY8025) will stay open due to slave relay failure until manually closed.
Completion Criteria: Scenario will end when FW flow is obtained from the U1 Startup Feedwater pump.
Critical Tasks
- 1. E - A: Manually trip the reactor from the control room before reaching RCS pressure of 2335 psig and all S/Gs <10% WR level. Failure to trip the reactor at this point would make bleed and feed ineffective.
- 2. E - O: Close containment isolation valves such that at least one valve is closed on each critical phase-A penetration before the end of the scenario. (1RY8025 must be manually closed)
- 3. FR-H.1 - - A: Establish feedwater flow into at least one SG before RCS bleed and feed is required (<43% Wide range on all 3 intact S/G levels). NOTE: In this scenario if the manual reactor trip is delayed greater than 1 minute this critical task may not be applicable since bleed and feed may be required upon entry to 1BwFR H.1.
--OR--
FR-H.1 - - B: Establish bleed and feed before PORVs open automatically. Bleed and feed must be established before the PORVs open due to a loss of RCS HEAT SINK. NOTE: In this scenario, it is expected that RCS pressure may rise to the PORV setpoint(s) due to CV pump injection following an SI, however for this critical task to be considered not met, RCS heat up must have caused the PZR PORVs to open (This will generally not occur until the S/Gs have dried out). On the Braidwood simulator for this set, Core Exit Thermocouples above 600°F without bleed and feed established (no CV injection, RCPs running, full spray flow) were required to cause the first PORV to open.
Braidwood NRC 04-1 Page 3 SIMULATOR OPERATOR NOTES:
Simulator Setup:
Completed Reset to IC 21, reset rods, and allow simulator to run Place 1B AF pump and Unit 2 SAC in PTL and place Danger tags on the control switches Open 1RY8025 Start 1B CV pp, shutdown 1A.
Place 141 C/S for 0CC pump in PTL, place 142 C/S for 0CC pump in NAT, IRF CC07 RI, CC42 RO Run CAEP on disk for NRC 04-1 SETUP PRELOAD or enter preload items manually Place yellow at risk placard. Ensure ORAM updated.
Ensure Delta I limits and Delta I band are correct for 100% power.
Ensure turnover sheets, GP flowchart, REMA and Load swing instruction sheet are filled out.
Event 1: Power Decrease at 4.5 Mw/min Acknowledge Ramp as load dispatcher.
Event 2: Insert IMF RX21A 1700 for 1PT455 failing low when requested by examiner. As SM acknowledge the failure, LCO 3.3.1 conditions A, E, K and 3.3.2 conditions A, and D, and 3.3.4 condition A should be entered. Acknowledge WRs and CR/IR requests.
Ensure phone is used when tripping bistables (NOT radio).
IRF RP20 OPEN to open protection cabinet 1 door IRF RX032 TRIP for PB455A C1-153 BS-1 Hi Press Rx Trip IRF RX034 TRIP for PB455C C1-153 BS-4 Low Press Rx Trip IRF RX035 TRIP for PB455D C1-153 BS-3 Pzr Lo Press SI IRF RX033 TRIP for PB455B C1-153 BS-2 P-11 IRF RX013 TRIP for TB411C C1-124 BS-5 OT DT Rx Trip IRF RX135 TRIP for TB411D C1-124 BS-4 OT DT Runback IRF RP20 CLOSE to close protection cabinet 1 Event 3: Insert IOR ZDI0WO01PB PTL to trip the 0B VC chill water pump when requested by examiner. If dispatched as local operator report back that the pump breaker is tripped, if breaker closure is attempted report that breaker will not stay closed. As SM acknowledge entry into TS 3.7.11 Cond A. Report back to US that U2 assist NSO will swap VC trains. To swap VC trains: stop 0B VC supply and return fans, place 0B MCR chiller in PTL. Start 0A VC supply, then 0A VC Return, start 0A VC Chill Water pump.
Prior to the starting chiller inform US, that 0A VC chiller trouble is expected and start 0A VC chiller. Be ready to acknowledge alarm, report alarm as expected. When chiller actually starts inform US that 0A VC train is running. IRF HV01 RESET will clear Chiller trouble annunciator when chill water temperature is low enough (10 minutes later).
Event 4: Insert IMF CV23A 30 when requested by examiner.
Acknowledge entry as SM into 1BwOA PRI-6, E-Plan eval request TS 3.4.13 cond A should be entered and exited due to identified leakage.
When dispatched as NLO to isolate the 1A Letdown Hx place IRF CC40 0 (SIM DIAG CC6)and IRF CC37 0 to close 1CC9452B and 1CC9452A.
To place the 1B letdown HX in service IRF CC39 100 (SIM DIAG CC6) (1CC9452C). Acknowledge CC problems as SM Issue request. If requested to drain Unit 1 CC surge tank insert IRF CC15 100 SIM DIAG CC2 (1CC2020B). When draining is complete (U1 CC surge tank at 56%) IRF CC15 0.
Events 5, 6, 7, 8: Insert IMF ED05A to trip 6.9 KV bus 156 when requested by examiner. 30 seconds later insert IMF MS07B 4 to fault 1B MS line in containment. Failure of Rx trip, Slave relay for 1RY8025, 1RY8026 stuck open, and 1A AF pump failing to start are preloaded. RUN CAEPs: NRC 04-1 EVENT 7 and 7A immediately after SI initiation. (These simulate air operated valves in containment failing normally). If asked: Bus 156 is damaged, UAT feeder breaker door is blown open, no fire. AF pump status:
report that 1B AF pump is taken apart (turbocharger has been removed), 1A AF pump is seized. When requested to remove fuses FU 24 and 27 in 1PA27J and 28J: IRF FW150 REMOVED and IRF FW151 REMOVED. To start the SU feed water pump Aux Oil pump IRF FW149 START
`
Comments:
Braidwood NRC 04-1 Page 4 Scenario No:
NRC 04-1 Event No.
1 Event
Description:
Power decrease at 4.5 Mw/min Time Position Applicants Actions or Behavior CUE o Turnover/Load reduction brief.
CREW Review applicable Precautions, Limitations and Actions of 1BwGP 100-4 Participate in shutdown brief.
US Implement actions of 1BwGP 100-4 US Direct load reduction to 620 Mwe at 3-6 MW/min (4.5 Mw/min is expected)
Refers to GP flowchart 1BwGP 100-4T1/2 RO Verify rod position and boron concentration:
Initiate boration, if required. (BwOP CV-6):
Determine required boric acid volume
° ReMa Form (This is the preferred method.)
° Effects of previously performed borations
° Boration / Dilution tables Determine required boric acid flow rate Automatic method:
- Set 1FK-110 BA Flow Control to desired boration rate
- Set 1FY-0110 BA Blender Preset Counter to desired volume.
- Place MAKE-UP MODE CONT SWITCH to STOP position
- Set MU MODE SELECT to BOR position
- Place MAKE-UP MODE CONT Switch to START
- Verify proper operation of valves and BA transfer pump (1CV110B open, BA Pump running, 1CV110A throttles open, BA flow indicated on recorder.)
OR Batch addition of BA:
- Open 1CV110B
- Open 1CV110A
- Start the BA Transfer pump
- When desired amount of BA has been added, Stop the BA Transfer Pump
- Close 1CV110A
- Close 1CV110B o May flush boron by opening 1CV111A for 5-20 gallons.
Comments:
Braidwood NRC 04-1 Page 5 Scenario No:
NRC 04-1 Event No.
1 (cont)
Event
Description:
Power decrease at 4.5 Mw/min Time Position Applicants Actions or Behavior BOP Initiate turbine load reduction:
o May Place Turbine in MW IN Depress LOAD RATE MW/MIN Enter desired value for rate (4.5 MW/min)
Depress REF Enter desired final turbine loading (620 MW)
When ready to begin load decrease, depress GO Verify load reduction occurring RO/
BOP Monitor reactor power and load decrease Monitor NIs, Tave, I, Pzr press/level Monitor Mwe, turb loading, EHC RO During Boration:
Monitor VCT Level and pressure Monitor BA boric acid counter and flow Verify boration stops at preset value After a measurable response and with lead examiners concurrence, initiate the next event:
Comments:
Braidwood NRC 04-1 Page 6 Scenario No:
NRC 04-1 Event No.
2 Event
Description:
1PT455 fails low IMF RX21A 1700 Time Position Applicants Actions or Behavior CUE Annunciators:
1-12-A1 PZR LOW RX TRIP STPT ALERT 1-12-B1 PZR PRESS LOW 1-12-C1 PZR PRESS CONT DEV LOW HTRS ON 1-10-C5 OT DT HIGH ROD STOP C-3 1-14-B1 OT DT HIGH RX TRIP ALERT 1PI-455A indicates 1700 psig
- Master pressure controller 1PK-455A output fails low, spray valves close, all PZR heaters on.
RO Identifies 1PI-455A indicates low.
Informs US.
Takes manual control of 1PK-455A, raises output in manual to stabilize RCS pressure rise.
(examinee may wait for direction by US)
Selects operable channel for controlling channel (when directed by US).
Selects operable channel for PZR press and OT DT recorders (when directed by US).
Returns PZR press control to auto (when directed by US) and PZR pressure approximately stable at 2235 psig.
Coordinates bistable tripping with NSOs in AEER.
BOP/RO
- References BwARs.
US Enters 1BwOA INST-2 Attachment B Notifies SM of 1BwOA INST-2 entry:
Communicates 1PT455 failed low Requests SM evaluate for Emergency Plan conditions o Asks for WR and CR/IR Requests additional NSOs for bistable tripping Directs actions in BwOA o Directs BOP to Stop ramp Briefs RO and additional NSOs on bistable tripping Determines LCO 3.3.1 conditions A, E, K, 3.3.2 conditions A, D, and 3.3.4 condition A should be entered.
Informs SM of TS entries.
o May restart ramp.
RO/Add RO and additional NSO coordinate to Trip the following bistables in protection cabinet 1:
Comments:
Braidwood NRC 04-1 Page 7 Scenario No:
NRC 04-1 Event No.
2 Event
Description:
1PT455 fails low IMF RX21A 1700 Time Position Applicants Actions or Behavior NSOs IRF RP20 OPEN to open protection cabinet 1 door IRF RX032 TRIP for PB455A C1-153 BS-1 Hi Press Rx Trip IRF RX034 TRIP for PB455C C1-153 BS-4 Low Press Rx Trip IRF RX035 TRIP for PB455D C1-153 BS-3 Pzr Lo Press SI IRF RX033 TRIP for PB455B C1-153 BS-2 P-11 IRF RX013 TRIP for TB411C C1-124 BS-5 OT DT Rx Trip IRF RX135 TRIP for TB411D C1-124 BS-4 OT DT Runback IRF RP20 CLOSE to close protection cabinet 1 With lead examiners concurrence, enter next event.
Comments:
Braidwood NRC 04-1 Page 8 Scenario No:
NRC 04-1 Event No.
3 Event
Description:
OB VC chill water pump trips Time Position Applicants Actions or Behavior CUE Annunciator:
0-33-C6 MCR CHLR Unit Trouble BOP
- Refers to BwAR
- Identifies 0B Chill water pump tripped
- Informs US US
- Acknowledges 0B chill water pump trip.
- Directs local investigation of pump.
- Determines TS 3.7.11 Cond A is applicable.
- Directs VC trains be swapped
- Informs SM:
0B VC Chill Water pump trip TS entry Requests WR and CR/Issue.
- Directs On Line Risk Assessment.
o May stop Turbine ramp, & restart.
With lead examiners concurrence, enter next event.
Comments:
Braidwood NRC 04-1 Page 9 Scenario No:
NRC 04-1 Event No.
4 Event
Description:
1A CV letdown Hx Leak IMF CV23A 30 Time Position Applicants Actions or Behavior CUE Annunciators:
1-2-A5 CC SURGE TANK LEVEL HIGH LOW 1PR09J CC rad monitor in Alarm on RM-11 Rising Unit 1CC Surge Tank Level Lowered letdown flow rate on 1FI-132 Lowering VCT level CC surge tank vent valve, 1CC017, closed BOP
- Checks CC surge tank level rising.
- Identifies reduced letdown flowrate o Identifies lowering VCT level o Isolates Letdown o Diverts letdown to RHUT o Restores letdown when 1A HX isolated and CC aligned to 1B US
- Implements 1BwOA PRI-6 "COMPONENT COOLING MALFUNCTION" Att. A
- Informs SM of Emergency plan evaluation, requests WR and CR/IR o TS 3.4.13 condition A should be entered and exited (once A letdown HX is isolated) due to excessive identified leakage.
- May stop and restart ramp BOP
- Checks CC surge tank level rising (when directed)
US
- Transitions to attachment B BOP/RO Check for leakage from RCP thermal barriers:
Verifies 1-7-E4 is not lit.
No seal injection flow abnormally high.
Isolate CC System Inleakage Verifies 1PR09J or 0PR09J in alarm on RM-11 Notifies chemistry to sample CC system for activity Locate inleakage from 1A Letdown Heat Exchanger.
US One of the following will be performed:
Comments:
Braidwood NRC 04-1 Page 10 Scenario No:
NRC 04-1 Event No.
4 Event
Description:
1A CV letdown Hx Leak IMF CV23A 30 Time Position Applicants Actions or Behavior o May direct letdown be isolated or o May direct swapping of in-service Letdown Hx with letdown in service o May direct 1CV112A be placed in Divert
- Determine from P&IDs that 1CC9452A and B must be closed. Directs these valves be closed.
o May direct 1CV8467A be closed
- Informs SM of 1A letdown Hx problem, CR and AR/IR o Inform MM Dept. of the 1A Letdown HX failure o Notify Rad Protection of elevated radiation levels in the CC system
- IF letdown isolated, directs normal or excess letdown be restored RO/BOP Isolates letdown (IF directed)
Closes 1CV8149A, B, and C o May close 1CV459 and 460 Swaps in-service letdown heat exchangers (per procedure) IF directed.
Opens 1CV8401B, closes 1CV8401A Asks NLO to open 1CC9452D
- Restores letdown or excess letdown (if isolated) as directed.
With lead examiners concurrence, enter next event.
Comments:
Braidwood NRC 04-1 Page 11 Scenario No:
NRC 04-1 Event No.
5-8 Event
Description:
Loss of Heat Sink.
Time Position Applicants Actions or Behavior RO E - A (SIM OPERATOR: After ensuring preloads are set, insert IMF ED05A, 156 Trip. 30 seconds later, regardless of Reactor Trip status insert IMF MS07B 4 to fault 1B MS line in containment.
Immediately following SI actuation RUN CAEPs: NRC 04-1 Event 7 and 7A to simulate IA valves in containment failing normally. Do NOT silence back panel alarms until after RO has performed Cont Isolation steps.)
Performs Immediate Actions of 1BwEP-0, Reactor Trip or SI:
Notes Red First Out: RCP LOW FLOW ABOVE P8 RX TRIP.
Initiates manual Reactor Trip.
Verify Reactor Trip:
- All Rod Bottom Lights Lit.
- Reactor Trip and Bypass Breakers Open.
- Neutron Flux Decreasing.
o May determine SI is required, and manually actuates SI.
o May determine MS is required, manually actuates MS isolation.
US
- Directs actions of 1BwEP-0 Reactor Trip or SI BOP Performs Immediate Actions of 1BwEP-0:
Verify Turbine Trip:
- Verify all Turbine Throttle Valves are closed.
- Verify all Turbine Governor Valves are closed.
Verify Power to 4KV ESF Buses:
- Buses 141 and 142 Bus Alive Lights both LIT.
RO Performs Immediate Actions of 1BwEP-0, Reactor Trip or SI:
US
- FW Pumps Tripped.
- FW Isolation Monitor Lights LIT.
- FW Pump Discharge Valves (1FW002A, B, C) Closed.
(Examiner NOTE: At this point BOP will silence RM-11 and proceed to back panels to silence alarms and will remain unavailable until RO has performed Cont Isolation steps. If BOP is directed to return, BOP will attempt to steer RO toward his own panel by stating that he will close 1RE9160B and 1RE9170 on 1PM11J when Containment isolation step is directed by US)
Comments:
Braidwood NRC 04-1 Page 12 Scenario No:
NRC 04-1 Event No.
5-8 Event
Description:
Loss of Heat Sink.
Time Position Applicants Actions or Behavior
- Both CV pumps.
- Both RH pumps.
- Both SI pumps.
[CT]
E - O Verify RCFCs running in Accident Mode:
- Group 2 RCFC Accident Mode status lights lit.
Verify Cnmt Isolation Phase A:
- Group 3 Cnmt Isol monitor lights are not all lit:
RE9169B, RE9170, RY8025, RY8026, RY8033.
- Manually closes 1RE9169B, 1RE9170, 1RY8025, 1RY8033, attempts to manually close 1RY8026
- 1RY8025 must be manually closed to meet critical task, closure attempt on 1RY8026 should be made. (Examiner NOTE: BOP may assist anytime after this is done.)
Verify Cnmt Ventilation Isolation:
- Group 6 Cnmt Vent Isol monitor lights lit.
BOP US BOP/RO Verify AF system:
- Reports Neither AFW pump is running.
o 1AF013A through D all Open o 1AF005A through D all Throttled/Open.
- Directs personnel check on AF pump status
- Verify 1A and 1B CC pumps are running.
- Verify 1A and 1B SX pumps are running.
Check Main Steamline Isolation Not Required:
Reports 1B S/G pressure is less than 640 psig or Containment pressure is greater than 8.2 psig.
Verifies all MSIVs and all MSIV Bypass valves are closed. (May use Bistable status lights or direct valve indication)
BOP/RO Check if CS is required:
- Reports Containment Pressure has exceeded 20 psig and CS is required. (Examiner NOTE:
CS may not be actuated when this step is reached initially. CS will actuate approx 5 minutes
Comments:
Braidwood NRC 04-1 Page 13 Scenario No:
NRC 04-1 Event No.
5-8 Event
Description:
Loss of Heat Sink.
Time Position Applicants Actions or Behavior after steam line faults)
US Transitions to 1BwFR H.1, Loss of Secondary Heat Sink, from 1BwEP-0, due to No AFW flow and low inventory levels in all SGs
- Announces procedure transition and asks for peer check from RO/BOP
- Informs SM of plant Status, procedure entry and that Emergency Plan evaluation is required
- Directs actions of 1BwFR-H.1, Loss of Secondary Heat Sink Note: Upon entry into 1BwFR-H.1, if at any time the Operator Action Summary page item for Bleed and Feed Initiation is met the Crew may immediately go to step 13 of 1BwFR-H.1. If this occurs go to page 15 RO Check if Secondary Heat Sink is Required, Check Cent CHG Pump Status:
- Checks RCS pressure and temperature
- Checks CV pump status (both running)
BOP/RO Check if feed and bleed is required:
- Verifies Wide range S/G levels are greater than 43%
- Verifies RCS pressure is greater than 2335 psig due to loss of heat sink Note: If Bleed and Feed Initiation is required, the Crew may immediately go to step 13 of 1BwFR-H.1. If this occurs go to page 15 BOP US BOP Attempts to establish AF flow Verifies 1SD002A-H closed, 1SD005A-D closed.
Reviews attachment B prior to feeding S/Gs AF PUMP SX SUCT VLS ARMED NOT lit.
Comments:
Braidwood NRC 04-1 Page 14 Scenario No:
NRC 04-1 Event No.
5-8 Event
Description:
Loss of Heat Sink.
Time Position Applicants Actions or Behavior 1AF004A and B both OPEN.
Note: US should have directed closure of 1AF013B and F and should not be directing that these valves are verified open.
1AF013A, C, D, E, G, H all OPEN 1AF005A, C, D, E, G, H all OPEN Neither AF pump is running.
Dispatches operator to attempt to start AF pumps, US may after reading this step decide that this is not appropriate based on reports by field operators on AF pump status.
Verifies AF flow is NOT greater than 500 gpm.
Verify all RCPs stopped. (RCPs should have been stopped earlier due to high containment pressure)
BOP/RO US Prepare FW System for Restoration Check CD/CB pumps at least one running.
Place FW REG valves, bypass valves, tempering flow control valves in manual at zero demand Checks FW isolation Aux relay lights lit Checks SI is actuated.
Dispatches operator to pull fuses in 1PA27J and 1PA28J.
Opens 1FW035A, C, D when FW actuated lights are clear.
Verifies SU feedwater pump or 1A FW pp is available Verifies CD/CB pumps running.
Checks BUS 159 energized.
Dispatches operator to start SU feedwater pump aux oil pump.
Opens discharge valve for SU feedwater pump Verifies SU Recirc Valve Open Verifies Main FW pump Recirc Valves Closed.
Starts the SU feedwater pump US
- Verifies Attachment B has been reviewed
- Directs BOP/RO to feed at least two S/Gs (NOT 1B), may direct all three be fed.
BOP FR-H.1 -
- A:
Feeds at least two Non dry S/Gs (B S/G should not be fed, all others may be fed at max rate available with tempering lines) Feed lines should not be voided, e.g. has not been greater than 75minutes since feed has been isolated.
Comments:
Braidwood NRC 04-1 Page 15 Scenario No:
NRC 04-1 Event No.
5-8 Event
Description:
Loss of Heat Sink.
Time Position Applicants Actions or Behavior Once Feed is initiated to intact S/Gs: END SCENARIO.
RO NOTE: These steps are only performed if Feed and Bleed is initiated.
Establish RCS Feed Path:
RO FR-H.1 -
- B:
Verify RCS Feed Path:
Checks that a CV or SI pump are running (All four are running.)
Checks group 2 cold leg injection alignment.
Establish RCS Bleed Path:
Verifies PORV block valves energized and open.
Opens both PZR PORVs.
Verify Adequate RCS Bleed Path:
Verifies both PZR PORVs and Block Valves Open.
US
BOP/RO Reset SI if Necessary:
END SCENARIO. (Scenario cannot go farther due to overrides necessary to cause 1RY8026 to fail open.
EAL CALL: FS1 Due to potential loss of Fission Product and RCS Barriers. (Entry into 1BwFR-H.1)
Braidwood NRC 04-2.
Page 1 Simulation Facility Braidwood Scenario No.:
NRC 04-2 Operating Test No.:
2004301 Examiners:
Applicant:
__Surrogate____________
BOP ATWS/ Tube Rupture Initial Conditions:
IC-16 Turnover: 52% Steady State MOL, 1B FW pp turbine rebuilding in progress, 1A SI pump tagged (TS 3.5.2 cond A was entered 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago) to replace oil cooler, expected back tomorrow. RCS activity is elevated (below TS limits for continuous operation). National security threat level has just been raised to Orange due to a non-specific threat against a United States nuclear plant. System Power has requested an 80 Mw reduction in Unit 1 Load as soon as possible. Chemistry has requested the Unit 1 Cation bed be placed in-service for 25 minutes. A NLO is being briefed by the WEC on placing the Cation bed in service and will contact the U1 control room when ready. On line risk status is YELLOW.
Event No.
Malf. No.
Event Type*
Event Description Preload IMF RP02A IMF RP02B IOR ZDI1SI01PA PTL IRF MS69 0 IRF MS71 0 IRF FW025 0 IOR ZDI1FW002B CLS IOR ZDI1FW012B CLS IOR ZDI1FW01PBA PTL IOR ZDI1FW01PBB PTL IOR ZDI1FW01PPC PTL IOR ZLO1ES095A2 OFF IOR ZLO1ES095A1 ON IOR ZDI1FW01PBE STOP RTA fails to operate RTB fails to operate 1A SI pump OOS 1B FW pp OOS 1
NONE R(RO, US)
N(BOP)
IMF RM02U I(US) 1PR11J (Cont Atmos Rad Monitor) Fails 3
IMF RX10A 0 I(ALL) 1PT505 failure 4
IMF RX13A 100 I(RO, US) 1LT459 fails High 5, 6, 7 IMF RD09 0 IOR ZDI1MS001D CLS Preload I(RO, US)
C(BOP, US)
M(ALL)
Rod speed fails to zero 1D MSIV fails closed ATWS 8
IMF TH03A 400 M(ALL)
Tube Rupture 1A S/G
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient
Braidwood NRC 04-2 Page 2 SCENARIO OVERVIEW 52% Steady State MOL, 1B FW pp turbine rebuilding in progress, 1A SI pump tagged (TS 3.5.2 cond A was entered 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago) to replace oil cooler, expected back tomorrow. RCS activity is elevated (below TS limits for continuous operation). National security threat level has just been raised to Orange due to a non-specific threat against a United States nuclear plant. System Power has requested an 80 Mw reduction in Unit 1 Load as soon as possible. Chemistry has requested the Unit 1 Cation bed be placed in-service for 25 minutes. A NLO is being briefed by the WEC on placing the Cation bed in service and will contact the U1 control room when ready. On line risk status is YELLOW.
About 30 minutes into the scenario, the crew should commence a power decrease at 2 mw/min.
About 35 minutes into the scenario, 1PR11J will fail, the BOP should refer to the BwAR, US should enter TS 3.4.15 Cond B.
About 45 minutes into the scenario 1PT505 will fail low, the RO should take manual control of rods after verifying turbine load stable. 1BwOA INST-2 should be entered. TS 3.3.1 conditions A and P should be entered. Rods must be returned to Auto before continuing.
About 60 minutes into the scenario 1LT459 will fail High. Charging flow will drop to minimum. Upon RO diagnosis, US should direct the Master PZR level/1CV121 controller be placed in manual and enter 1BwOA INST-2.
TS 3.3.1 conditions A and K should be entered.
About 75 minutes into the scenario 1D MSIV will fail closed, BOP or RO may diagnose, US should order reactor trip.
RO will attempt to trip from both panels and declare ATWS, RO will be forced to manually insert rods due to failure of automatic rod speed. As soon as RO begins manual rod insertion (and immediate actions are completed) RTA will open automatically. At RCS pressure peak 1A S/G will rupture (400 gpm). Crew should identify leak due to rad monitors, RCS, and S/G level response.
Completion criteria occurs when step 17 of 1BwEP-3 is completed (S/G and RCS pressure are equalized).
Critical Tasks
- 1. FR-S.1 - - C Insert negative reactivity into the core by at least one of the following methods before completing the immediate-action steps of FR-S.1:
De-energize the control rod drive MG sets Insert RCCAs Establish emergency boration flow to the RCS
- 2. E - A: Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs.
Braidwood NRC 04-2 Page 3 SIMULATOR OPERATOR NOTES:
Simulator Setup:
Completed Reset to IC-16, reset rods, and allow simulator to run.
Place 1A SI pump in PTL and place a Danger Tag on the control switch.
Shutdown the 1B FW Pump, place danger tags on the 1B FW pump controls. Dot appropriate alarms.
Run CAEP on disk for NRC 04-2 SETUP PRELOAD or enter preload items manually.
Place yellow at risk placard. Update ORAM.
Ensure Delta I limits and Delta I band are correct for 52% power.
Ensure turnover sheets, REMA, and Load swing instruction sheet are filled out.
Event 1: Power Decrease at 2 Mw/min Event 2: Insert IMF RM02U to fail 1PR11J. As SM acknowledge the failure, LCO 3.4.15, Cond B Entry, WR and CR/IR. As RP report back that 1PR11J Logic Selector has been placed in bypass (when requested). Report back as RP that the 1PR11J pump appears broken. Acknowledge request as RP to take U1 containment air samples.
Event 3: Insert IMF RX10A 0 for 1PT505 failing Low. As SM acknowledge the failure, LCO 3.3.1 Conditions A and P, On Line Risk assessment, WRs and CR/IR requests. IRF RP20 OPEN to open protection set 1 door, IRF RX143 TRIP to trip (BS-1 C1-742) bistable, IRF RP20 CLOSE to shut protection set 1 door. IMF PN0470 ON will simulate OPERATING BYPASS (SW-12) to TIP 1, IRF RX149 TRIP will place the OPERATING BYPASS SWITCH TEST INPUT (SW11) to TEST-TRIP,. Do not continue until Rods are returned to AUTO.
Event 4: Insert IMF RX13A 100 to fail 1LT459 High. As SM acknowledge the failure, LCO 3.3.1 Conditions A and K should be entered, WRs and CR/IR requests. IRF RP20 OPEN to open protection set 1 door. Insert RX029 TRIP to trip bistable LB459A (BS-1), IRF RP20 CLOSE.
Events 5-8: Insert the following on one trigger IMF RD09 0 and IOR ZDI1MS001D CLS to fail rod speed and close the 1D MSIV. The ATWS is preloaded. When RCS pressure peaks, insert IMF TH03A 400 to rupture the 1A S/G.
Delete DMF RP02A when the immediate actions of 1BwFR-S.1 are complete. If RTA does not automatically open insert IRF RP01 TRIP. If dispatched as NLO report back that RTA was already open and delete DMF RP02B, IRF RP02 TRIP to open RTB. As SM acknowledge entry into 1BwFR-S.1, 1BwEP-0, and 1BwEP-3, Emergency Plan evaluations, and STA request.
Comments:
Braidwood NRC 04-2 Page 4 Scenario No:
NRC 04-2 Event No.
1 Event
Description:
Power decrease at 2 Mw/min to 535 Mwe Time Position Applicants Actions or Behavior CUE o Turnover. (Reviews and Load Swing Instruction Sheet may have been initiated in classroom) o If asked, Nuclear Engineering does not have a beacon prediction (ReMa) available for the down power.
US Implement actions of 1BwGP 100-4 US Direct load reduction to 535 Mwe at 2 MW/min:
Initiate load swing instruction sheet, 1BwGP 100-4T2 CREW Review applicable Precautions, Limitations and Actions of 1BwGP 100-4 RO Verify rod position and boron concentration:
Initiate boration, if required. (BwOP CV-6):
Determine required boric acid volume
° Effects of previously performed borations
° Boration / Dilution tables Determine required boric acid flow rate Automatic method:
- Set 1FK-110 BA Flow Control to desired boration rate
- Set 1FY-0110 BA Blender Preset Counter to desired volume.
- Place MAKE-UP MODE CONT SWITCH to STOP position
- Set MU MODE SELECT to BOR position
- Place MAKE-UP MODE CONT Switch to START
- Verify proper operation of valves and BA transfer pump (1CV110B open, BA Pump running, 1CV110A throttles open, BA flow indicated on recorder.)
OR Batch addition of BA:
- Open 1CV110B
- Open 1CV110A
- Start the BA Transfer pump
- When desired amount of BA has been added, Stop the BA Transfer Pump
- Close 1CV110A
- Close 1CV110B
Comments:
Braidwood NRC 04-2 Page 5 Scenario No:
NRC 04-2 Event No.
1 (cont)
Event
Description:
Power decrease at 2 Mw/min to 535Mwe Time Position Applicants Actions or Behavior BOP Initiate turbine load reduction:
Depress LOAD RATE MW/MIN Enter desired value for rate (2 MW/min)
Depress REF Enter desired final turbine loading (US may elect to go to 620 MWe first vice 535 MWe)
When ready to begin load decrease, depress GO Verify load reduction occurring RO/
BOP Monitor reactor power and load decrease:
Monitor NIs, Tave, I, Pzr press/level Monitor Mwe, turb loading, EHC RO During Boration:
Monitor VCT Level and pressure Verify RCS boron concentration increasing Monitor BA blender counter Verify boration stops at preset value After a measurable response and with lead examiners concurrence, initiate the next event.
Comments:
Braidwood NRC 04-2 Page 6 Scenario No:
NRC 04-2 Event No.
2 Event
Description:
1PR11J (Cont Atmos Rad Monitor) Fails IMF RM02U Time Position Applicants Actions or Behavior CUE
- RM-11 ALARM BOP Identifies 1PR11J has failed due to loss of sample flow Refers to BwAR Dispatches RP to check CASP panel. (Report back that 1PR039, 1PR041, 1PR043, 1PR044, 1PR035 are closed)
Informs RP to locally place 1PR11J Logic selector switch in bypass (SIM OPERATOR NOTE: Report back as RP that the pump appears broken)
Refers to BwOP AR/PR-11, BwOP AR/PR-11A-5 Informs RP to take Containment samples Informs US to consult TS 3.4.15 US
- Determines TS 3.4.15 condition B is applicable
- Informs SM, requests WR and CR/IR, engineering support o Fills out LCOAR paperwork After a measurable response and with lead examiners concurrence, initiate the next event.
Comments:
Braidwood NRC 04-2 Page 7 Scenario No:
NRC 04-2 Event No.
3 Event
Description:
1PT505 fails low IMF RX10A 0 Time Position Applicants Actions or Behavior CUE Annunciators:
(1-14-D1) TAVE CONT DEV HIGH (1-12-D1) PZR PRESS CONT DEV LOW HTRS ON Annunciator Rods stepping in at 72 steps/min RO
- Recognizes 1PT505 has failed
- Informs US
- Places rods in Manual o Informs US if DNB tech spec met
- Defeats 1PT505 when directed BOP
- Places steam dumps in steam pressure mode when directed US o Directs Load Ramp placed in HOLD. May direct Rods stepped out.
- Acknowledges 1PT505 failure
- Enters 1BwOA INST-2 attachment D
- Directs actions per BwOA
- Enters Tech Spec 3.4.1 (DNB), if required
- Briefs RO and spare NSOs for bistable tripping (SIM OPERATOR NOTE:
IRF RP20 OPEN to open protection set 1 door IRF RX143 TRIP to trip (BS-1 C1-742) bistable IRF RP20 CLOSE to shut protection set 1 door)
IMF PN0470 ON will simulate OPERATING BYPASS (SW-12) to TIP 1 IRF RX149 TRIP will place the OPERATING BYPASS SWITCH TEST INPUT (SW11) to TEST-TRIP After a measurable response and with lead examiners concurrence, initiate the next event.
Comments:
Braidwood NRC 04-2 Page 8 Scenario No:
NRC 04-2 Event No.
4 Event
Description:
1LT459 fails High. IMF RX13A 100 Time Position Applicants Actions or Behavior CUE Annunciators:
(1-12-A3) PZR LEVEL HIGH RX TRIP STPT ALERT (1-12-C1) PZR PRESS CONT DEV LOW HTRS ON (1-12-C3) PZR LEVEL CONT DEV HIGH HTRS ON (1-9-D3) CHG LINE FLOW HIGH LOW Charging flow control CV-121 throttles closed to decrease flow RO/US Identify/report failed PZR level channel:
LT-459 US Implement BwOA INST-2, Attachment C and direct operator action.
Informs SM, requests WR & CR/IR.
RO/US Check PZR Level:
Verify level normal (60%)
If NOT take manual control of either the master level controller (LK-459) OR CV121 controller (FK-121) and increase charging flow to normal while maintaining RCP seal injection flow within required limits.
Select Operable Channel on LEVEL CHANNEL SELECTOR by placing to 461/460 position (when directed).
Verify Channel 460 or 461 selected on PZR level recorder. (when directed)
US Enters TS 3.3.1 Cond A & K Briefs RO and spare NSOs for bistable tripping.
(SIM OPERATOR NOTE:
Insert IRF RP20 OPEN to open protection set 1 door.
Insert IRF RX029 TRIP to trip bistable LB459A (BS-1)
Insert IRF RP20 CLOSE to close protection set 1 door.)
After a measurable response and with lead examiners concurrence, initiate the next event.
Comments:
Braidwood NRC 04-2 Page 9 Scenario No:
NRC 04-2 Event No.
5-8 Event
Description:
Rod speed fails to zero, 1D MSIV fails closed, ATWS, 1A S/G SGTR. IMF RD09 0, IOR ZDI1MS001D CLS, IMF TH03A 400 Time Position Applicants Actions or Behavior CUE Annunciators:
1-15-E8 MSIV NOT FULL OPEN 1-15-D3 S/G 1D FLOW MISMATCH STM FLOW LOW 1-1-A5 MSIV NOT FULL OPEN 1-1-E5 MSIV 1D HYD/PNEU PRESS HIGH LOW (SIM OPERATOR NOTE: Insert IMF RD09 0, ZDI1MS001D CLS on one trigger, when RCS pressure peaks (after Main Turbine Trip) insert IMF TH03A 400)
CREW Identify closure of 1D MSIV Determine that a Reactor Trip is required RO
[CT]
FR-S.1
- - C Performs immediate actions of 1BwFR-S.1 ATWS:
Manually attempts reactor trip from 1PM05J and 1PM06J RX Trip Switches Determines rods should be auto inserting but are NOT moving Manually inserts control rods Dispatches operator to locally trip Unit 1 Reactor Trip Breakers US Announces ATWS, enters, and directs actions of 1BwFR-S.1:
Informs SM, requests Emergency Plan evaluation Requests STA to monitor Status Trees (SIM OPERATOR NOTE: delete malfunction DMF RP02A and insert IRF RP01 TRIP (if necessary) when immediate actions of 1BwFR-S.1 are complete. When dispatched as NLO, delete DMF RP02B and insert IRF RP02 to trip, report that U1 RTA was already open)
BOP Performs immediate actions of 1BwFR-S.1 ATWS:
Trips Turbine Verifies AF pumps running RO Initiates emergency boration:
Checks CV pump running Opens 1CV8104 Starts Boric Acid Transfer pump Checks emergency boration flow greater than 30 gpm Checks charging flow greater than 30 gpm Checks PZR pressure less than 2335 psig BOP Verifies Containment Vent Isolation RO Verifies Reactor Subcritical
Comments:
Braidwood NRC 04-2 Page 10 Scenario No:
NRC 04-2 Event No.
5-8 Event
Description:
Rod speed fails to zero, 1D MSIV fails closed, ATWS, 1A S/G SGTR. IMF RD09 0, IOR ZDI1MS001D CLS, IMF TH03A 400 Time Position Applicants Actions or Behavior PR channels Less than 5%
IR channels have a negative startup rate US Transitions to 1BwEP-0:
Asks for peer check (from RO/BOP)
Informs SM, requests Emergency Plan evaluation RO Verifies Reactor Trip:
Rod bottom lights - ALL Lit Reactor trip and bypass breakers open o If RTB still closed re-initiates trip Neutron flux - Dropping BOP Verifies Turbine Trip:
All turbine throttle valves CLOSED All turbine governor valves CLOSED Verify Power to 4KV ESF Busses:
- Both ESF busses energized CUE CREW 1A Steam generator tube rupture. (This malfunction was placed when RCS pressure peaked) 1A S/G level rising RCS pressure dropping PZR level dropping Main Steam line rad monitors in alarm Check SI Status: (Examiner NOTE: The crew may have manually Safety Injected based on previous indications or an automatic SI may have occurred)
Check SI actuated.
Check if SI required:
- Check PZR pressure
- Check steam line pressure
- Check containment pressure
- Check PZR level. (RO should determine that PZR level and pressure cannot be maintained)
FW pumps tripped (all three)
FW Isolation monitor lights lit FW pps disch vlvs, 1FW002A and C closed (or going closed, 2B is already closed).
Both CV
Comments:
Braidwood NRC 04-2 Page 11 Scenario No:
NRC 04-2 Event No.
5-8 Event
Description:
Rod speed fails to zero, 1D MSIV fails closed, ATWS, 1A S/G SGTR. IMF RD09 0, IOR ZDI1MS001D CLS, IMF TH03A 400 Time Position Applicants Actions or Behavior RO/
BOP Both RH 1B SI pump (1A is OOS)
BOP Verify RCFC Accident Mode lights lit Verify Phase A isolation - Group 3 monitor lights lit Verify CNMT Ventilation isolation - Group 6 CNMT Vent Isol monitor lights lit Verify AF system:
AF pumps both running AF isolation valves open 1AF13A-H AF flow control valves throttled 1AF005A-H Verify both CC pumps running Verify both SX pumps running RO/
BOP Check/verify Main Steamline Isolation not required:
All S/G pressures > 640 psig CNMT pressure < 8.2 psig BOP/
CNMT pressure remained < 20 psig Verify Total AF flow:
AF flow > 500 gpm SG levels maintained Check status of S/G NR levels o SG levels NOT increasing in an uncontrolled manner, then continue o IF 1A S/G is determined to be increasing in an uncontrolled manner, THEN
- Close 1AF013A and E RO/
BOP Verify ECCS valve alignment:
- Determine Group 2 Cold Leg Injection monitor lights are lit Verify ECCS flow HHSI flow >100 gpm RCS pressure NOT <1700 psig RO Check at least ONE PZR PORV relief path available:
PORV isol valves - (Both) ENERGIZED PORV relief paths - (Both) AVAILABLE and in AUTO
- (Both) Isolation valves open
Comments:
Braidwood NRC 04-2 Page 12 Scenario No:
NRC 04-2 Event No.
5-8 Event
Description:
Rod speed fails to zero, 1D MSIV fails closed, ATWS, 1A S/G SGTR. IMF RD09 0, IOR ZDI1MS001D CLS, IMF TH03A 400 Time Position Applicants Actions or Behavior BOP Verify Generator Trip:
OCB 1-8 and 7-8 open PMG output breaker open BOP Verify both DGs running:
SX valves open 1SX169A/B Dispatch operator locally to check operation Examiners note: US and RO will continue in 1BwEP-0 while BOP is performing the next 3 ventilation steps:
BOP Verify Control Room ventilation aligned for emergency operations:
Dispatch NLO to trip VV, VL and VW fans Operating VC train equipment running:
Supply fan Return fan M/U fan Chilled water pump Verify MCR chiller 0B running Operating VC train dampers:
M/U fan outlet damper NOT full closed 0VC08Y VC train M/U filter light LIT 0VC09Y open 0VC313Y closed Operating VC train Charcoal Adsorber aligned for train B 0VC44Y closed 0VC05Y open 0VC06Y open
- Control Room pressure greater than +0.125 inches water on 0PDI-VC038 BOP Verify Auxiliary Building ventilation aligned:
Two inaccessible filter plenums aligned Plenum A fan 0VA03CB running Damper 0VA023Y open Damper 0VA436Y closed
Comments:
Braidwood NRC 04-2 Page 13 Scenario No:
NRC 04-2 Event No.
5-8 Event
Description:
Rod speed fails to zero, 1D MSIV fails closed, ATWS, 1A S/G SGTR. IMF RD09 0, IOR ZDI1MS001D CLS, IMF TH03A 400 Time Position Applicants Actions or Behavior Plenum C fan 0VA03CF running Damper 0VA072Y open
Train B fan 0VA04CB running:
0VA055Y open 0VA062Y open
Normal spray valves closed 1RY455B and 1RY455C PORVs closed:
1RY455A 1RY456 RO Maintain RCS temperature control:
Check RCPs running Verify RCS average temperature stable at or trending to 557°F RO Check if RCPs should be stopped:
Any RCPs running Check if trip criteria applies:
o HHSI flow >100 gpm OR o SI pump discharge flow >200 gpm RCS pressure < 1425 psig
- Trip RCPs if controlled cooldown NOT in progress and above criteria met BOP/
RO Check if SG secondary pressure boundaries are intact:
Check pressure in all SGs:
None decreasing in an uncontrolled manner None completely depressurized CREW Determine S/G tubes are NOT intact:
RM-11 Rad Monitor ALERT/HI RAD Alarms o 1PR08J SG Blowdown o 1PR27J SJAE/GS o 1AR 22/23 1A Mainsteam Line
Comments:
Braidwood NRC 04-2 Page 14 Scenario No:
NRC 04-2 Event No.
5-8 Event
Description:
Rod speed fails to zero, 1D MSIV fails closed, ATWS, 1A S/G SGTR. IMF RD09 0, IOR ZDI1MS001D CLS, IMF TH03A 400 Time Position Applicants Actions or Behavior US/RO Transitions to 1BwEP-3, STEAM GENERATOR TUBE RUPTURE, has RO/BOP perform peer check.
US Notifies SM of plant status and procedure entry Requests evaluation of Emergency Plan conditions Enter/Implement 1BwEP-3 and direct operator actions of 1BwEP-3 RO Check Status of RCPs:
All RCPs running High Head SI Flow >100 gpm RCS Pressure >1425 psig (RCP Trip criteria NOT met)
CREW
[CT]
E-3--A Identify ruptured SG 1A Unexpected rise in S/G Level 1A 1A Mainsteam line rad monitor NOT NORMAL for plant conditions Isolate ruptured SG:
o Verify SG PORV 1MS018A in AUTO o Verify closed when SG pressure < 1115 psig o US informs SM to dispatch environs teams o Verify SG blowdown isolation valves closed o 1SD002A o 1SD002B Close MSIV and MSIV bypass valves for 1A SG o Check PORVs on intact (1B, 1C, & 1D) SGs available for RCS cooldown o Check ruptured SG level:
o Narrow Range >10%
Verify/close 1A SG AF isol valves 1AF013A (should have been closed in 1BwEP-0) 1AF013E (should have been closed in 1BwEP-0)
BOP Check Ruptured SG pressure:
Determine required core exit temperature from table based on current ruptured SG pressure Check PZR pressure < 1930 psig PZR LOW PRESS SI BLOCK PERMISSIVE P-11 Lit If NOT continue with procedure until P-11 Lit before blocking STM LINE SI
Comments:
Braidwood NRC 04-2 Page 15 Scenario No:
NRC 04-2 Event No.
5-8 Event
Description:
Rod speed fails to zero, 1D MSIV fails closed, ATWS, 1A S/G SGTR. IMF RD09 0, IOR ZDI1MS001D CLS, IMF TH03A 400 Time Position Applicants Actions or Behavior RO BOP BOP Block Steamline Isol SI Place STM LINE SI BLOCK switches to BLOCK for train A and B (when P-11 reached)
Dump Steam to condenser from intact SGs at maximum rate Check average of ten highest CETCs less than required temperature If NOT continue with procedure and stop cooldown when less than required temperature Stop RCS cooldown (continuous action in effect)
Narrow range levels > 10%
Control feed flow to maintain narrow range levels between 23% and 50%
Check narrow range levels not increasing in an uncontrolled manner RO Check PZR PORVs and isolation valves:
Power to PORV Isol valves 1RY8000A, 1RY8000B PORV closed 1RY455A and 1RY456 closed At least ONE PORV Isol valve OPEN Both are open 1RY8000A, B BOP/RO Reset SI:
Depress both SI Reset P/Bs Verify SI ACTUATED permissive light not lit Verify AUTO SI BLOCKED lit BOP Reset CNMT Isolation:
Reset CNMT Isolation Phase A Check SACs - any running Open instrument air CNMT isolation valves:
1IA065 1IA066 Verify All Ac busses energized:
- 141, 142, 143, 144, 156, 157, 158, 159
Comments:
Braidwood NRC 04-2 Page 16 Scenario No:
NRC 04-2 Event No.
5-8 Event
Description:
Rod speed fails to zero, 1D MSIV fails closed, ATWS, 1A S/G SGTR. IMF RD09 0, IOR ZDI1MS001D CLS, IMF TH03A 400 Time Position Applicants Actions or Behavior Check if RH pumps should be stopped:
RH pump suction aligned to RWST RCS pressure greater than 325 psig Stops both RH pumps RO/
BOP Check if RCS cooldown should be stopped:
Check average of ten highest CETCs less than required temperature If NOT then do NOT proceed until required temperature achieved Stop RCS cooldown Maintain average of ten highest CETCs less than required temperature BOP Check ruptured SG pressure:
Stable or increasing RO/US Check RCS subcooling:
Acceptable per Attachment A and Figure 1BwEP 3-2 (+20°F)
RO/US Depressurize RCS Using PZR spray to minimize break flow and refill PZR:
- Determine Normal PZR Spray is available
- Spray PZR with maximum available spray until any of the following conditions -
satisfied:
Both
- PZR level greater than 12%
Comments:
Braidwood NRC 04-2 Page 17 Scenario No:
NRC 04-2 Event No.
5-8 Event
Description:
Rod speed fails to zero, 1D MSIV fails closed, ATWS, 1A S/G SGTR. IMF RD09 0, IOR ZDI1MS001D CLS, IMF TH03A 400 Time Position Applicants Actions or Behavior
- PZR level greater than 69%
- RCS subcooling not acceptable
- Transition to step 17 since spray flow will not be adequate Depressurize RCS using PZR PORVs Verify one PZR PORV available (both are available)
Open on PZR PORV until above conditions are met Closes both spray valves and PZR PORV once 1A S/G and RCS pressure are equalized and PZR level is greater than 12%
Note: At this point the scenario may be terminated EAL CALL: MS3 Auto and manual Trip not successful.