ML022890504
| ML022890504 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 07/25/2002 |
| From: | Caniano R, Grobe J Division of Reactor Safety III |
| To: | Skolds J Exelon Generation Co, Exelon Nuclear |
| References | |
| 50-456/02301, 50-457/02301 | |
| Download: ML022890504 (94) | |
Text
FINAL AS-ADMINISTERED SCENARIOS FOR THE BRAIDWOOD INITIAL EXAMINATION - JULY 2002
Simulation Facility Braidwood Scenario No. 1 Operating Test No. 2002 Examiners: Applicant: SRO RO BOP Initial Conditions: IC-21 , 100% power, BOL, equilibrium Xenon, steady state Turnover: 9 3 %power following ramp from 100%. IA CS Pump is OOS for a motor bearing replacement. ID CD/CB pump is OOS for an alignment and vibration problem. Load was reduced from 100% power due to CB pump suction strainer delta-p. Further load reduction is anticipated to allow isolation and flushing of the 1C CB Pump suction strainer.
Event Malf. No. Event Event No. Type* Description Preload RPO1 M RO Failure of RTB A&B to auto AND manual open. (can be opened locally)
SRO IACSpumpOOS CS01A BOP Failure of CS and Phase B to Actuate on Hi-3 Cnmt Press. Train B must be manually started from the MCR FW22D ID CD/CB pump OOS Preload (preload note) C RO 1S8801A will not auto open nor open from the MCB SRO I S18801B will not open automatically. Will open manually from MCB 1 N BOP Ramp down turbine power to 900 Mwe at directed MW/min SRO R RO Lower reactor power using rods and/or boration.
SRO 2 NI09A I RO Power Range N-41 fails high.
SRO 3 FW22B C BOP Trip of 1C CD/CB Pump. Standby CD/CB Pump not available SRO 4 RD09, 1 C RO Automatic rod motion fails at 1 step per minute.
SRO 5 RX03E, 4.8 I BOP Steam Flow Transmitter FT-532 (input to controlling channel) fails high.
SRO 6 RPO2A,B M RO Reactor Trip Breakers fail to open / ATWS BOP SRO 7 THO6 M RO Large Break LOCA inside containment. Leads to high-3 containment BOP pressure SRO 8 (OR) CSO1B C BOP Failure of CS to auto actuate.
-'N')ormal, ttK)eactlvity ýi)nstrument, ýU)omponent, (Mv)ajor Transient Braidwood 2002 NRC Exam Scenario 02-1
SCENARIO OVERVIEW The Unit 1 is at 93% power. ID CD/CB pump is OOS for alignment and vibration problems. IA CS Pump is OOS for a motor bearing replacement. Power was recently decreased from 100% due to CB Pump suction strainer delta-p problems.
-urther load decrease will be required to stop the running CD/CB pump and flush the suction strainer.
Following clearly observable plant response from the reactivity changes, Power Range Nuclear Instrument N-41 will fail high causing a demand for inward rod motion. The crew will diagnose the PR failure and perform actions of 1BwOA INST-1, "NUCLEAR INSTRUMENTATION FAILURE- Attachment A," to defeat the channel and restore Tave=Tref.
The SRO will review TS and direct tripping of the associated bistables.
After completion of the actions specified in iBwOA INST-I the 1C CD/CD pump will trip on overcurrent. The Crew will enter IBwOA SEC-1, "SECONDARY PUMP TRIP", and commence a runback to reduce load to within the capacity of the remaining two CD/CB pumps (-700 Mwe). Rod Control is failed such that any auto rod motion will occur only at 1 step per minute, which is less than the expected minimum rod speed for the temperature transient in progress. The crew may elect to perforn steps of 1BwOA ROD-i, "UNCONTROLLED ROD MOTION", but it is NOT required. Rod Control will be shifted to manual to match Tave and Tref at the new lower value.
Following completion of actions for the CD/CB pump and rapid load reduction, the 1C S/G selected steam flow channel will fail high, resulting in indications of increased steam flow and initial opening of 1C S/G feed reg valve to attempt to match feed flow with steam flow. An equilibrium level should be reached if manual control of the feed reg valve is not expeditiously taken. The crew will perform the actions of 1BwOA INST-2, "FAILED INSTRUMENT CHANNEL Attachment H".
After the unit is stablilzed following the SF channel malfunction, a large break LOCA of 50,000 gpm occurs, increasing to 400,000 gpm over 2 minutes. The size of the LOCA will result in an automatic SI actuation and lead to the discovery of the failure of the reactor to automatically trip. 1BwFR S. 1, "RESPONSE TO NUCLEAR POWER GENERATION /
\TWS" will be entered. After dispatching an operator to locally trip Unit 1 reactor, the reactor trip breakers will be opened only after placing the steam dumps in Off/Reset per step 7 of BwFR S. 1.
Following the safety injection actuation, cold leg injection valves 1S18801A&B will fail to open. 1SI880IB must be opened manually from the MCB.
CS will fail to automatically occur at the high-3 pressure setpoints. Manual action by the crew will be required to actuate train B of CS, either while performing the actions of 1BwEP-0 or the SRO may elect to perform 1BwFR Z.1, "RESPONSE TO HIGH CONTAINMENT PRESSURE" The scenario ends with completion of step 6 in 1BwEP ES-1.3 Critical Tasks
- 1. FR-S. 1 Insert negative reactivity into the core by manually inserting RCCAs before completing step 4 of FR-S. 1
- 2. EP-0--I Manually initiate high head injection flow via 1SI8801B before exiting lBwEP-0
- 2. EP-0--E: Manually actuate at least the minimum required compliment of containment cooling equipment before an extreme (red path) challenge develops to the containment CSF Braidwood 2002 NRC Exam 2 Scenario 02-1
SIMULATOR OPERATOR NOTES:
Simulator Setup:
IC-21, 100% power. Complete the 'ready for training' checklist. Hang YELLOW risk placard.
Ensure Delta I limits and Delta I band are correct for 100% power level.
Decrease Unit load to 1150 MW using turbine load decrease and rods only. Allow to stabilize.
Take IA CS pump OOS. Control switch to PULL OUT. Hang Tag Take ID CD/CD pump OOS. Control switch to PULL OUT. Hang Tag.
Take ID CD/CB pump aux lube oil pump OOS. Control switch to PULL OUT. Hang Tag.
Go to 'Action List' and use the following overrides and malfunctions:
ZLO1SI8801A1 ON ZLO1SI88OlA1 ON (must do both even though they are identical tags to get both indications)
RF ED0531 OPEN (opens breaker for 1SI8801A at 131X1 :F4. When used with the overrides it appears the Valve is closed and energized. If operators are dispatched to de-energize and open this valve, then use the Overrides to de-energize the valve, but do NOT open 1S1880 A.
Turn ON annunciator 1-17-A10, CD PUMP SUCT STRN DP HIGH, PN0991 (ON)
Modify Remote Function:
Rp75 (on SDG RP 15) to OUT. This prevents slave relay K603 from energizing. Components affected are:
1ST8801B will not stroke open on an SI, but can be manually opened from the MCB 1CV8105 will not automatically close, but can be closed manually.
lB AFW pump lube oil pump won't auto start, will not affect this scenario as the AF Pump will still auto start.
Activate the following malfunctions:
RP02A&B Failure of Reactor Trip Breakers to open in Auto and Manual. May be locally opened after steam Dumps are taken to OFF in 1BwFR S. 1 CSO1A 1A CS Pump Fail to Start/ Trip.
Modify the following remote functions (after closing the valves):
ED062A OPEN Breaker forlCS007A ED053M OPEN Breaker for ICS019A ED053A OPEN Breaker for 1CSOOA ED053B OPEN Breaker for ICS009A Modify the following remote function:
RP63 OUT to prevent lB CS pump from starting until 1CSO19B is manually opened.
Insert the following overrides to complete the OOS for the ID CD/CB pump:
ZLO1CBl 13D(l) OFF Open Light OFF ZLO 1CB 113D(2) OFF Close Light OFF 3 Scenario 02-1 Braidwood NRC Exam 2002 NRC Braidwood 2002 Exam 3 Scenario 02-1
Event 1 Load Ramp to 700 MWe Event 2 Power Range Channel N-41 fails high (NI09A, 120)
Insert malfunction to fail power range channel N41 high (NI09A, 120) after clearly observing plant response to reactivity Changes, or at the lead examiners direction.
Perform the following to trip PR channel bistables:
On SDG RX4:
Open Protection Cabinet Door #1 RX020 OPEN OTDT Trip TB41IC CI-124 BS-3 RX013 TRIP OTDTRunback TB41ID C1-124 BS-4 RX135 TRIP Protection Cab #1 Close Door RX020 CLOSE Event 3 Automatic Rod Motion fails at 1 Step per Minute (RD09, 1)
Insert Rod Speed Failure Malfunction (RD09, 1) immediately prior to inserting the CD/CB pump trip Event 4 Trip of 1C CD/CB Pump with standby CD/CB Pump not available (FW22C)
Insert malfunction to trip 1C CD/CB pump (FW22C) after all actions for the failed NI channel have been competed and MW loading has decreased below 1050 MWe Event 5 Steam Flow Transmitter FT-532 (controlling channel) fails high nsert malfunction to fail IC SG controlling steam flow channel, FT-532 HIGH (RX03E, 4.8) on SDG RX16 after bistables for PR channel N-41 are tripped.
Event 6 Reactor Trip Breakers fail to open (ATWS)
The ATWS malfunction(s) are in Pre-load. When directed as a local operator to open the unit 1 reactor trip breakers, wait until after the steam dumps have been placed in OFF/RESET. DELETE malfunctions RP02A and RP02B. Important: If the reactor is still at power after the S/Gs reach 10% wide range level, the RCS pressure will start to rise rapidly above the Pzr Safety setpoints. Use triggers to delete malfunctions RP02A and RP02B when the steam dumps are taken to off. OR open trip breakers if crew transitions to EP-0 at step 6 of FR-S.1 DMF RP02A and B Event 7 Large Break LOCA inside Cnmt. Leads to failure of Hi-3 automatic actuations Insert LBLOCA malfunction (TH06C, 50K to 400K over 2 minutes) inside containment to ensure the Hi-3 containment pressure setpoint is reached. If asked for ETR on IA CS, 2-4 hours is optimistic.
INSTRUCTOR NOTE: As STA, do NOT report on any status until AFTER containment pressure has decreased below 20 psig.
Event 8 Failure of CS to automatically actuate The failure of CS to auto actuate is in the Pre-load. Operators will manually align the CS system for operation.
Braidwood 2002 NRC Exam 4 Scenario 02-1
Scenario No: 02-1 Event No. I Event
Description:
Ramp down turbine and reactor power to 700 Mwe.
Time Position] Applicant's Actions or Behavior CUE Turnover. (Reviews and Load Swing Instruction Sheet may have been initiated in classroom)
US Implement actions of 1BwGP 100-4 , rev 17, step F.1 US Direct load reduction to 700 Mwe at 5 MW/min
"* Initiate load swing instruction sheet, 1BwGP 100-4T2
"* Contact chemistry and HP for load change >15% in one hour 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 "O Effects of previously performed borations "o Boration / Dilution tables
"* Determine required boric acid flow rate
"* Set IFK- 110 BA Flow Control to desired boration rate
"* Set 1FY-01 10 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 (1CV 1OB open, BA Pump running, 1CV 11OA throttles open, BA flow indicated on recorder.
If 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 lCV11OA
"* Close 1CV11OB Comments:
Braidwood 2002 NRC Exam 5 Scenario 02-1
Scenario No: 02-1 Event No. 1 Event
Description:
Ramp down turbine and reactor power to 700 Mwe.
Time Position Applicant's Actions or Behavior BOP Initiate turbine load reduction:
"* Depress LOAD RATE MW/MIN
"* Enter desired value for rate (5 MW/min)
"* Depress REF
"* Enter desired final turbine loading (700 MW)
"* When ready to begin load decrease, depress GO
"* Verify load reduction occuring RO/BOP Monitor reactor power and load decreasse
"* Monitor NI's, Tave, Al, 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 NOTE: Following the required plant response, Event 2 may be started Comments:
Braidwood 2002 NRC Exam 6 Scenario 02-1
Scenario No: 02-1 Event No. 2 Event
Description:
Power Range NI Channel N-41 Fails High Time I Position Applicant's Actions or Behavior CUE: Annunciators:
1-10-A3 PWR RNG HIGH STPT RX TRIP ALERT 1-10-B5 PWR RNG FLUX HIGH ROD STOP 1-10-C3 PWR RNG FLUX RATE RX TRIP ALERT 1-10-C4 PWR RNG CHANNEL DEV Rods moving in response to High Auctioneered Nuclear Power PRNI N41 indications failed high.
RO/SRO Identify/report failure of PRNI N4 1.
US Enter 1BwOA INST-I "NUCLEAR INSTRUMENTATION MALFUNCTION" Attachment A PR Channel Failure, and direct actions.
RO Place Rod Control in MANUAL Check Rod Stop (1 10-B5) Lit BOP Bypass the Rod Stop for Channel N-41 at 1PM07J RO Control Tave - Tref to within 1 degree via manual rod control, boration or turbine loading BOP Check S/G Levels normal and stable Bypass/defeat PR N41 at 1PM07J:
"* Detector Current Comparator (Upper and Lower Section) 0 Power Mismatch Bypass
"* Rod Stop Bypass (if not previously performed)
"* Comparator Channel defeat
"* Remove Control Power Fuses for high and low flux and rate trips.
US/RO Trip Bistables for OTDT Trip and Runback (2 Bistables: TB41 IC and TB41 ID)
Select operable Loop DT recorder When conditons are stable and Tave is within I degree of Tref, return rod control to automatic US Refer to Tech Specs (3.3.1, 3.2.4, TRM 3.3.h)
Request to have risk performance done Notify SM / Maintenance of NI failure Comments:
Braidwood 2002 NRC Exam 7 Scenario 02-1I
Scenario No: 02-1 Event No. 3 &4 Event
Description:
Trip of IC CD/CB Pump. Stby not available. Rod speed fails at 1 spin in auto Time Position Applicant's Actions or Behavior CUE: Annunciators:
1- 17-A9 CD/CB PUMP TRIP 1-17-AIO CD PUMP SUCT STRN DP HIGH 1-17-All CB PUMP SUCT STRN DP HIGH 1-17-Bll CB PUMP DISCH FLOW HIGH Amber pole disagreement light for 1C CD/CB pump breaker.
Increasing flows on running CD/CB pumps.
BOP/US Identify / report trip of running 1C CD/CB pump US Implement 1BwOA SEC- 1, "SECONDARY PUMP TRIP-Attachment B", and direct operator actions:
o Notify chemistry to monitor secondary chemistry due to transient
"* Complete applicable steps of lBwGP 100-4
"* Have risk assessment performed Notify chemistry and HP if power change > 15% in one hour for tech spec and RETS samples BOP Perform actions of 1BwOA SEC-1 as directed by SRO:
"* Check turbine load > 700 Mwe
"* Determine standby CD/CB pump is NOT available
"* Depress Turbine Runback pushbutton
"* Verify turbine load decreasing Verify/Close recirc valve 1CB113C If FW pump flows oscillating: Reduce MFP turbine speed Check alarms NOT LIT/CLEAR:
"* 1-17-B 11 CB PUMP DSCH FLOW HIGH
"* 1-16-El FW PUMP NPSH LOW If either of the above alarms LIT, perform the following:
"* Manually open CP Bypass (1CD210A and 1CD20OB)
"* Verify/CLOSE CD pumps recirc (lCD152)
"* Verify/Open GS Condenser bypass (1CD157A and 1CD157B)
"* Verify HDP discharge valves opening in auto (1HD046A and 1HD046B)
"* Verify CB pump recirc valves closed (1CB1 13A-D)
When load has stabilized and when directed by US, depress turbine runback pushbutton to clear the runback circuit Comments:
Braidwood 2002 NRC Exam 8 Scenario 02-1
Scenario No: 02-1 Event No. 3 &4 Event
Description:
Trip of IC CD/CB Pump. Stby not available. Rod speed fails at 1 spin in auto Time Position Applicant's Actions or Behavior BOP Verify Controls in Automatic and responding correctly to the load decrease:
"* Turbine driven MFPs
"* HD046A and B
"* CB113s
"* CD152
"* CB157A and B
"* Shutdown tripped CD/CB pump per BwOP CD/CB-2 "o Adjust B/D flows and Calorimetric inputs as necessary "o Verify DEHC feedback loops in service (Impulse and MW)
NOTE: At some time during the turbine runback the crew should question the rod control response and discover the rod speed problem. From that time forward they should remain in Manual Rod Control. If they select Auto for rods they should note the rod speed indicator too low for minimum auto rod speed
(<8spm) and return to Manual.
IF BwOA ROD-2 is entered for failure of rods to move the actions start on page 10 CUE: 1-14-Di TAVE CONT DEV HIGH - LIT RO Perform actions of 1BwOA SEC-I as directed by SRO:
"* Verify rod control in Automatic.
"* Initiate Boration as necessary.
"* Maintain Tave and Tref within 3 degrees F While monitoring rod control response, identify the response is inadequate to maintain Tave Tref during the load reduction.
"* Take manual control of rods
"* Manually insert rods to maintain Tave and Tref deviation within acceptable limits.
"* Inform SM of rod control speed failure RO Check PDMS operable as follows:
- 1-10E8 PDMS INOPERABLE not lit
- 1BwOS PDMS-la, PDMS AAR not implemented
- 1-10-D7 PDMS LIMIT NOT EXCEEDED not lit Control delta I near target 1-10-B6 ROD BANK LOW INSERTION LIMIT not lit (if lit, borate as necessary, refer to TS 3.1.6) 1-BP-4.6 LOSS OF TURB LOAD INTLK C7 not lit Comments:
Braidwood 2002 NRC Exam 9 Scenario 02-1 5
Scenario No: 02-1 Event No. 3&4 Event
Description:
Trip of IC CD/CB Pump. Stby not available. Rod speed fails at 1 spm in auto Time Position Applicant's Actions or Behavior If 1BwOA ROD-2 is entered, the actions are below:
US Enter lBwOA ROD-2 and direct actions:
US/RO Perform actions as directed:
- Place Rod Control In MANUAL.
o Stop unnecessary Turbine Load and Boron changes
"* Check Rod Stops NOT Lit:
- PWR RNG FLUX HIGH ROD STOP (1-10-B5)
SIR HIGH FLUX ROD STOP (1-10-A2)
- TURBINE LOW POWER INTLK C-5
- BANK D ROD STOP C-11 (1-10-D5)
"* Check ROD CONT URGENT FAILURE (1-10-C6) NOT Lit.
"* Determine if Rod Control Should be placed in AUTOMATIC:
"* C-5 Not Lit
"* Tave-Tref deviation < 1 degree F.
"* Determine that placing rod control into automatic will result in wrong rod speed response NOTE: When the plant has been stabilized at 700 Mwe, the next event may be inserted Comments:
Braidwood 2002 NRC Exam 10 Scenario 02-1
Scenario No: 02-1 Event No. 5 Event
Description:
Steam Flow Transmitter FT-532 (input to controlling channel) fails high Time I Position Applicant's Actions or Behavior CUE Annunciators:
1-15-C4 SG IC FLOW MISMATCH FW FLOW LOW IFT-532 indication reading high 1FW530 throttling open FW flow increasing SG level increasing above program BOP/US Identify/report steam flow channel FT-532 failure
- Take manual control of 1FW530 and balance feed flow with steam flow to stabilize level as necessary.
US Implement lBwOA INST-2, "OPERATION WITH A FAILED INSTRUENT", Attachment H "STEAMFLOW CHANNEL FAILURE", and direct actions.
BOP Perform actions as directed:
"* Check affected SG levels Normal. IF NOT:
"* Place FRV in Manual
"* Verify adequate FW DP
"* Restore level to a stable condition.
"* Select operable Steam flow channel o Establish Auto level control
- Verify Steam Pressure Channels Normal RO Assist BOP as required to identify failed instrument channel and stabilize SG levels Monitor RCS and stabilize changing parameters resulting from FF/SF imbalance:
"* RCS Tave
"* Pzr Pressure US Inform SM and maintenance of failure.
1 i 1 t
.7 1 Comments:
Braidwood 2002 NRC Exam 11 Scenario 02-1
Scenario No: 02-1 Event No. 6, 7, 8 Event
Description:
Large Break LOCA / ATWS / Failure of CS to actuate Time Position Applicant's Actions or Behavior CUE Large Break LOCA results in lowering inventory and Reactor trip RED FIRST OUT US Implement 1BwEP-0 "REACTOR TRIP OR SI" RO Perform immediate operator actions of 1BwEP-0 Verify the reactor is NOT tripped:
"* Rod bottom lights NOT LIT
"* Reactor trip & bypass breakers NOT open
"* Neutron flux NOT decreasing Manually attempt to trip reactor with both switches at:
"* 1PM05J
"* lPM06J RO Identify/report that reactor trip breakers did not open.
US Transition to 1BwFR-S. 1 "RESPONSE TO NUCLEAR POWER GENERATION/ATWS" o Contact WEC for STA duties CREW Dispatch operator to locally open reactor trip breakers RO Perform immediate operator actions of FR-S. 1:
"* Verify reactor is NOT tripped
"* Rod Bottom lights NOT lit
"* Reactor trip breakers NOT open; Bypass breakers open (not racked in)
"* Neutron flux stable/NOT decreasing from Post Trip.
"* Manually attempt to trip reactor with switch
"* 1PM05J
"* 1PM06J RO Insert control rods at 48 spm in Manual. (Auto is failed to 1 spm)
[CT]
FR-S.I -- C Comments:
Braidwood 2002 NRC Exam 12 Scenario 02-1
Scenario No: 02-1 Event No. 6, 7, 8 Event
Description:
Large Break LOCA / ATWS / Failure of CS to actuate Time Position Applicant's Actions or Behavior BOP Verify turbine trip
"* Turbine throttle valves closed
"* Turbine governor valves closed Check AFW Pumps Running
& AF Pump run lights - Lit RO/BOP Verify Emergency Boration of the RCS is occurring (with SI actuation):
- 1CV112D and E are OPEN 0 1CV1 12B and C are CLOSED
- Both CV Pumps RUNNING Check PZR pressure - Less than 2335 RO BOP Verify Containment Ventilation Isolation
- Group 6 CNMT Vent Isol monitor lights -LIT (Note: US may assign an operator to verify proper ESF Actuations per OAS as time permits.)
RO Verify reactor subcritical
"* PR channels < 5%
"* IR channels SUR < 0 Determine the power is still above 5% and continue with steps of 1BwFR-S. 1.
(NOTE: If the values above are satisfied the crew will transition to 1BwEP-0.
actions for 1BwEP-0 begin on page 15)
BOP Isolate Steam Dumps
- Place steam dump BYPASS INTERLOCK switches to OFF/RESET for both Trains.
(NOTE: Reactor trip breakers will be locally opened after dumps are in OFF/RESET. If S/G WR levels reach 8% before the reactor is tripped, RCS pressure rapidly rises to the Pzr Safety setpoint.)
CREW Check trips have occurred
"* Reactor trip. If NOT - Direct the operator to locally open the trip breakers by depressing the manual trip buttons
"* Turbine trip Comments:
Braidwood 2002 NRC Exam 13 Scenario 02-1
Scenario No: 02-1 Event No. 6, 7, 8 Event
Description:
Large Break LOCA / ATWS / Failure of CS to actuate Time Position Applicant's Actions or Behavior BOP Check SG levels
- Control feed flow to maintain SG levels between 10%Q (31% adverse) and 5 0%
- Reactor Makeup dilution valves ICV 1 A and 1CV 111 B closed
- Verify BTRS Mode Selector in OFF
- Dispatch operator to locally check valves closed per 1BwFR S. 1 step 10c:
- 1CV8841, PW to Emergency boration
- 1CV8435 & 1CV8453 CV chemical mixing tank 0 1AB8629A Recycle evap feed pumps to CENT CHG pumps suction CREW Stop reactivity insertion from RCS cooldown
"* RCS temperature NOT decreasing in uncontrolled manner
"* Note: RCS temperature may be decreasing due to ECCS injection and AF Flow to SGs.
"* SG pressure, none decreasing in uncontrolled manner RO Check CETCs < 1200°F RO Verify reactor subcritical
"* PR channels < 5%
"* IR channels SUR < 0 CREW Transition to Procedure and step in effect. 1BwEP-0, "RX TRIP OR SI".
(Note: Actions of 1BwEP-O continue on next page)
Comments:
Braidwood 2002 NRC Exam 14 Scenario 02-1
Scenario No: 02-1 Event No. 6, 7, 8 Event
Description:
Large Break LOCA / ATWS / Failure of CS to actuate Time Position Applicant's Actions or Behavior RO Perform Immediate Actions of 1BwEP-0 Verify reactor trip
"* Rod bottom lights lit
"* Rx trip and bypass breakers open
"* Flux decreasing 0
BOP Verify Turbine tripped
"* TV's closed
"* GV's closed Verify 4KV ESF Busses energized
"* Bus 141
"* Bus 142 CREW Determine SI is actuated/required
"* SI First Out annunciator Lit (1-1 1-B/C/D/E 1)
"* SI Equipment actuated (SI Pumps running)
Recognize Adverse Containment conditions exist
- Cnmt Pressure >5psig RO/US Trip RCP's per Operator Action Summary
"° CC Water lost to RCP's "o Cnmt Phase B actuated 0 All of the following exist:
- Controlled RCS Cooldown not in progress
- RCS Pressure <1425 psig
"* FW Pumps tripped
"* Isolation monitor lights lit
"* FW discharge valves (1FW002A/B/C) closed RO/US Verify ECCS pumps running:
- CV pumps
[CT] o 1 S1880 lB may be opened at this point while verifying pump alignments EP-0--I 0 SI pumps
- RH pumps Comments:
Braidwood 2002 NRC Exam 15 Scenario 02-1
Scenario No: 02-1 Event No. 6,7,8 Event
Description:
Large Break LOCA / ATWS / Failure of CS to actuate Time Position Applicant's Actions or Behavior BOP/US Verify Containment Conditions:
"o RCFC Accident Mode Lights LIT (Group 2)
"o Phase A Lights LIT (Group 3)
"o Containment Ventilation Lights LIT (Group 6)
BOP/US Verify the following:
- AF Aligned:
- 1A and 1B AFW pumps running
- 1AF013A-H Open
- 1AF005A-H Throttled 0 1A and lB CCW pumps running
- 1A and lB SX pumps running
- MSIVs and B/P Isolated when Cnmt Pressure >8.2 psig or Steam Line Pressure < 640 psig BOP/US Check If Containment Spray required:
- Cnmt pressure > 20 psig
"* Stop All RCPs
"* Group 6 lights NOT lit
"* Phase B lights NOT Lit Identifies/reports 1B CS pump failed to start.
Identifies/reports failure of Phase B actuation/positioning of Phase B valves
- Manually actuates Both switches for CS and Phase B actuation at IPM05J and IPM06J
[CTI
EP-0-E 0 Checks ICS001B open
"* Opens 1CS007B
"* Places lB CS pump TEST switch to TEST
"* Opens ICS019B
"* Returns TEST switch to Normal
- Checks 1CS010B open
Verifies CS Additive flow > 5 gpm (1FI-CS016)
Comments:
Braidwood 2002 NRC Exam 16 Scenario 02-1
Scenario No: 02-1 Event No. 6,7,8 Event
Description:
Large Break LOCA / ATWS / Failure of CS to actuate Time Position Applicant's Actions or Behavior NOTE: At some time CNMT pressure may rise to an ORANGE Path condition (without CS pumps running). If so, performance of 1BwFR Z.1 "RESPONSE TO HIGH CONTAINMENT PRESSURE" may be required. Actions are covered below. CUE will be provided by the STA after monitoring the BwSTs.
US Implement and direct as advised by the STA the actions of 1BwFR-Z. 1, "RESPONSE TO HIGH CONTAINMENT PRESSURE".
BOP Verify Containment Isolations
"* Phase A Group 3 lights lit
"* Cnmt Ventilation Group 6 lights lit Check if Containment Pressure has increased to > 20 psig (1PR-937 or 1PI-CS934 thru 937)
- Stop all RCPs (previously completed)
Verify CS alignment: (previously complete for B Train)
US/BOP Verify Group 6 Phase B Isolation lights lit (previously completed)
Verify RCFCs running in ACCIDENT MODE (Group 2 lights lit).
Verify MS Isolation, MSIVs and B/P closed. (previously completed)
Determine NO SGs are faulted:
"* No Steam Generator pressure decreasing in an uncontrolled manner
"* No Steam Generator completely depressurized Return to step and procedure in effect.
NOTE: Actions below resume from 1BwEP-0.
- 500 >gpm
- Control SG levels 31-50%
- Determine no SG level increasing in an uncontrolled manner Comments:
Braidwood 2002 NRC Exam 17 Scenario 02-1
Scenario No: 02-1 Event No. 6,7,8 Event
Description:
Large Break LOCA / ATWS / Failure of CS to actuate Time Position Applicant's Actions or Behavior RO Verify the following:
[CTI EP-0--I
- Group 2 Cold Leg Injection lights lit - OPEN 1S8801B ECCS Operations:
"* High Head SI flow > 100 gpm
"* RCS pressure < 1700 psig
"* Sl pump flow > 200 gpm
"* RCS pressure < 325 psig
"* RH pump flow > 1000 gpm PZR Porv Relief path available:
"* At least one block valve energized
"* Porv in Auto
"* Associated Block valve open BOP Verify the following:
Main Generator Trip:
"* Output Breakers Open
"* PMG Breaker Open EDGs running
"* 1SX 169A and B Open
"* Dispatch operator for local check of EDG operation Ventilation aligned:
- Control room
- Aux bldg
- Fuel Handling bldg Comments:
Braidwood 2002 NRC Exam 18 Scenario 02-1
Scenario No: 02-1 Event No. 6,7,8 Event
Description:
Large Break LOCA / ATWS / Failure of CS to actuate Time Position Applicant's Actions or Behavior RO Check the following:
PZR PORVs and Sprays Closed RCPs tripped Secondary Pressure Boundaries are Intact:
"* No SG pressure decreasing uncontrollably
"* No SG completely depressurized BOP/US Check SG Tubes Intact:
- NO rads on RM-11 for:
o SJAE/GS Exhauster 1PR27J 0 SG Blowdown 1PR08J o Main Steam Lines 1AR022, and 23 (all MSIV rooms)
CREW Determine RCS is NOT Intact:
"* CNMT ARMs in alert or alarm 1AR014, 011, 012, 021, 022
"* Cnmt Pressure > 3.4 psig
"* Cnmt Floor water level > 5 inches.
Transitions to 1BwEP-1, "LOSS OF REACTOR OR SECONDARY COOLANT".
NOTE: Cooldown from the LOCA may cause entry conditions for 1BwFR-P.1, "RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK", if so the actions are below.
Comments:
Braidwood 2002 NRC Exam 19 Scenario 02-1
Scenario No: 02-1 Event No. 6,7,8 Event
Description:
Large Break LOCA / ATWS / Failure of CS to actuate Time I Position Applicant's Actions or Behavior US Implement and direct actions of lBwFR-P. 1, "RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK" as advised by the STA:
"* Check RCS pressure > 325 psig
"* Return to step and procedure in effect (1 BwEP- 1)
US Enter 1BwEP-1, "LOSS OF REACTOR OR SECONDARY COOLANT" and direct actions.
BOP Determine NO SGs are Faulted:
"* No SG Pressure decreasing uncontrollably
"* No SG completely depressurized Control Intact SG levels to 10% (31 % Adverse) to 50% NR level Check Secondary Radiation levels normal: No evidence of SGTR.
RO Check PZR PORVs and Isolation Valves:
"* PORV Isolation valves open and energized
"* PORVs Closed CREW Check if ECCS flow should be reduced:
US/BOP Check if RH Pumps should be stopped:
"* RESET SI
"* Check RH suction align to RWST
"* Check RCS Pressure < 325 psig. DO NOT STOP RH pumps Determine 4KV ESF busses ENERGIZED (Bus 141 and 142)
"* Determine 4KV Non ESF Busses Energized (bus 143 and 144)
"* Stop 1A and lB EDG and place in standby per BwOP DG-12 DG Shutdown Comments:
Braidwood 2002 NRC Exam 20 Scenario 02-1I
Scenario No: 02-1 EventNo. 6,7,8 Event
Description:
Large Break LOCA / ATWS / Failure of CS to actuate Time Position Applicant's Actions or Behavior CREW Initiate evaluation of plant status
"* Determine Cold Leg Recirc Capability exists Power Available to RH pumps and 1 S1881 1A and B
"* Aux Bldg rads are normal for plant conditions 1/2PR28J and 1/2PR30J, ECCS Cubicle PRMs.
"* Reset Containment Isolation Phase A
"* Place Hydrogen Monitors in service per BwOP PS-9, "POST LOCA H2 MONITORS"
"* Obtain samples: RCS Activity, RCS Boron, Cnmt Atm, Cnmt Sump
"* Contact SM for evaluation to place H2 recombiners in operation.
"* Trip all HDPs
"* Shutdown lB and IC MFP (BwOP FW-2), CD/CB pumps (BwOP CD/CB-2)
"* Shutdown VC Chiller on Non operating Train. Control switch to trip.
US Check next procedure transition:
"* RCS pressure < 325 psig
"* RH pump flow> 1000 gpm
"* Transition to 1BwEP ES-1.3 when RWST level reaches 46%. (recycle to plant evaluation step if RWST level > 46%.
US Implement 1BwEP ES-1.3, "TRANSFER TO COLD LEG RECIRCULATION" when RWST level <
46% and direct actions.
Comments:
Braidwood 2002 NRC Exam 21 Scenario 02-1
Scenario No: 02-1 Event No. 6,7,8 Event
Description:
Large Break LOCA / ATWS / Failure of CS to actuate Time Position Applicant's Actions or Behavior BOP/RO Perform actions of 1BwEP ES-1.3 as directed:
Open CC to RH Hx isolation valves (1CC9412A and 1CC9412B)
Check CC flows to RH Hx > 5000 gpm Verify adequate Containment sump level- 8 inches (13 adverse) 1PI-PC006 or 007 Align RH pump suctions to Cnmt Sumps:
"* Check Both RH pumps running
"* Check Open 1SI8811A and 1SI8811B
"* Close 1S18812A and 1S18812B Check SI and CV pumps in injection mode:
"* SI pumps both running
"* Cold Leg Injection valves (1S1880 lA/B) OPEN Align SI and CV pumps for Cold Leg Recirculation:
"* Dispatch operator to energize 1SI8806 and 1SI8813
"* Verify CV pump lA miniflow isolation valves closed (1CV81 11 and ICV8114)
"* Close SI pump miniflow isolation valves (1 S18814, 1SI8920, and 1S18813 when power restored)
"* Close RH Hx Discharge Cross ties (1RH8716A and B)
"* Open SI and CV pump suction header Cross ties (1SI8807A and B, and 1SI8924)
"* Check 1A RH pump running
"* Open 1CV8804A
"* Check lB RH pump running
"* Open 1SI8804B .
Start ECCS pumps as necessary Reset SI as necessary Isolate RWST from SI and CV pumps
"* Check Open 1CV8804A and/or 1S18804B
"* Close 1S18806 (when power restored)
"* Close and de-energize 1CV1 12D and E.
(NOTE: Scenario may be terminated when reaching step to align CC for Post LOCA recovery)
Align CC for post LOCA Recovery:
"* Establish SX flow to U-0 CC Hx
"* Open 0SX146
"* Open 1SX005 Dispatch operator to adjust SX flow to CC Hxs to maintain the following:
"* CC Hx outlet temperature > 105 degrees F
"* SX motor current < 191 amps Initaite alignment of CC for Post LOCA recovery per BwOP CC-1.
Comme ts:
Braidwood 2002 NRC Exam 22 Scenario 02-1
SHIFT MANAGER TURNOVER Weekday, Today, 2001 ONCOMING SHIFT 2 U 4111 )IA I U UNUIT UMAJOR OOS's
, + ',* ___________________
MODE ............ 1 IA CS Pump Rx Pwr ............ 93 Generator MWe ..... 1150 ID CD/CB Pump Max Load/Power .... 100%
Min Load/Power .... 500 MW Max Ramp Rate ..... 5 MW/Min Desired Delta I ..... Target On-Line Risk ....... Green Boron @ .......... 934 Control RBnk n" ni) 17.r UNI~T0& 1 IN PROGRESS 'UNIT 0 & 1PENDIN 1A CS Pump bearing replacement. Hour 36 of a 7 day Ramp unit I to 700 MW at 5 MW/min in LCOAR. preparation for removing 1C CD/CB pump from service and flushing suction strainer.
ID CD/CB Pump alignment.
Estimated RTS in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 1C CB Pump suction strainer delta-p problems.
Ramped unit from 100% to 1150 MW over last 15 Focus Areas:
minutes using EHC and control rods only.
U Verification Practices U Command and Control Standard for Execution of Critical Steps THINK CONFIGURATION CONTROL and SAFETY!!!
flt trr.trt -- a fl n..tfW "i*L*L A WULt: 1 11Y O*I* FrL I IC21 .doc
SHIFT MANAGER TURNOVER
'NI~4 i l a UNIT 2 AJOR OO's~
,vMODE ............ 1 Rx Pwr ............ 97.6 Generator MWe ..... 1197 Max Load/Power .... 97.6 impulse pressure Min Load/Power .... 700 Max Ramp Rate ..... 5 mw/min Desired Delta I ..... Target On-Line Risk ....... Green Boron @ .......... 1037 Control Bank ....... D@210 LCARENTRE RVOS4 R UNIT 2 MAJOR SURVILNE none Dose INFO: Dose goal for day 10 mr SCHEDUJLE[D ACTIVITY CON~FLIC~T IC21.doc
SHIFT MANAGER TURNOVER T-mod Ul Tm B RVLIS. Jumper Installed on ýC U-1 MPT Disconnect.
I FW009A T-Mod for Hyd Pp Press Sw 1PS-FW1 62.
n if I~l.Y n_4 U0l
/ Q ; In Vý" a i k.,
nýA e'.
r*.I-. I Daily Manning Schedule See sheet for restricted duty personnel and overtime restrictions Oncoming STA Fire Chief Control Room Rounds (GSEP/LER/DVR/ENS)
Material TS Conditioning SFP High Level alarm did not alarm during calibration RWP's / Releases / Precautions / ALARA Infrequent Evolution Activities Lesson learned files L:\shared\opex then ctd F to search SPSO / Division LD Alternate BPO Outside # 815-727-5902/5903 Tie # 8-565-5902/5903 Uni..... 1...o..e..s..
..... mmonComments Air line break at 15/16 heaters, temp repair in place, fix Al F34 U1 FC Cleanup SFP 1HD046A jerky last 30% of travel. Problem on pp swaps U2 FC Cleanup OFFLINE (leak)
Battery 112 cell 32 has floating material in electrolyte, eval'd OK FC Cooling U1 D.O. OOS prevents filling U-I tanks normally, but BwOP DO-6 50K DO Tank empty can be used to fill tanks. T-MOD is installed allowing U-I boiler 125K DO Tank and FRAC Tks Certified ops Aux Steam U-1 ES --*U1 HDT U-0 CC Hx Ul U-0 CC Pump Bus 141 Ul Aux boiler Wet lay-up U2 Aux boiler Wet lay-up SAC / Dryer U1/U0 MUDs U-1 CST CW Makeup Running OA/0B CW Blowdown On Lake Level 5.8' 2AF017A leaking by .3 gpm, AR 990116738 Conference Call Phone Number- 1-800-232-1234 Teleconference S/G sampling lines/valves at HRSS are not correct. Do not folder ID #=472664085 hang OOS on any 2PS181 valves till further notice. Meeting Place 630-663-7120 +code 2PS229A still blows fuse 2PA32J Ckt 9 Duty Team is located @ SITE APPS, NRC Duty list in book CV seal leakage: Substation construction (John Strle) Cell phone 815-351-8472 2A Running 200cc/min shutdown about 6 drops/min 2B Running -12 dpm; S/D- none Cation CardCs AbnormalPositionedCompoent CCNUM EPN - OGNUM EPN Abnormalf~osition
- SM BEEPE[ TURNOVER Shift 1 To 2 Time Now Date Today Offgoing Oncoming IC21 .doc
1BwOSR 0.1-1,2,3 Revision 10 Information Use UNIT ONE - MODES 1, 2, AND 3 SHIFTLY AND DAILY OPERATING SURVEILLANCE DATA SHEET Critical Parameter Data Sheet (Mode 1 and 2)
Unit 1 Date: Todav Time Al/Target Al VCT Highest PR NI PZR Press PZR LvI Hi Tavg/Tref SLevel
. .. Gen Mwe Initial 23:00 -9.68 -9.67 53 100.0 2235 60 1586.0 586.0 1256 RC 0:00 -9.68 ..-9.67 53. 100.0 2235 60 586.0 586.0 1256 RC 1:00 -9.68 -9.67 53 100.0 2235 60 586.0 586.0 1256 RC 2:00 -9.68 -9.67 53 100.0 2235 60 586.0 586.0 1256 RC 3:00 -9.68 -9.67 53 100.0 2235 60 586.0 586.0 1256 RC 4:00 -9.68 -9.67 53 100.0 2235 60 586.0 586.0 1256 RC 5:00 -9.68 -9.67 53 100.0 2235 60 586.0 586.0 1256 RC 6:00 -9.68 -9.67 53 100.0 2235 60 586.0 586.0 1256 RC Unit Supervisor: KH 7:00 -9.68 -9.67 53 100.0 2235 60 586.0 586.0 1256 RC 8:00 9:00 10:00 11:00 12:00 13:00 14:00 Unit Supervisor:
15:00 16:00 17:00 18:00 19:00 20:00 21:00 22:00 Unit Supervisor:
(Final)
IC21
lBwOS NR-I Revision 12 Reference Use UNIT ONE POWER HISTORY HOURLY SURVEILLANCE DATA SHEET DATE FOR WHICH THIS SURVEILLANCE IS BEING PERFORMED: TODAY TIME AVG NUCLEAR TIME AVG NUCLEAR POWER OUTPUT POWER OUTPUT IDEAL ACTUAL IDEAL ACTUAL 0100 0100 100.0 %RTP 1300 %RTP 0200 O0200 100.0 %RTP 1400 '%RTP "0300 -0300 -100.0 %RTP 1500 %RTP 0400 0400 100.0 %RTP 1600 %RTP 0500 0500 100.0 %RTP 1700 "RTP 0600 0600 100.0 %RTP 1800 %RTP 0700 0700 100.0 %RTP 1900 %RTP 0800 %RTP- 2000 %RTP 0900 *%RTP 2100 %RTP 1000 *RTP 2200 %RTP 1100 %RTP 2300 %RTP 1200 %RTP 2400 %RTP TOTAL POWER FOR THE DAY: (Sum of each recorded average Nuclear Power Output)
TOTAL EFPH FOR THE DAY: (Total Power for the day multiplied by 0.01)
PREVIOUS CUMULATIVE EFPH: 2150.177 (Total EFPH to date from previous last run of this surveillance)
EFPH ADJUSTMENT**: Signature:
TOTAL EFPH TO DATE: (TRANSFER to next day's surveillance or next run of this surveillance) 1l "INFO ONLY" copy placed in file (Reviewer).
- MAY ONLY BE MADE AND SIGNED BY THE STATION NUCLEAR ENGINEER OR DESIGNEE. A WRITTEN DESCRIPTION OF THE REASON(S) FOR THE ADJUSTMENT MUST BE ATTACHED.
(Final)
IC21 D-2
Facility: Braidwood Scenario No.: 2 Op-Test No.:
Examiners: Operators: SRO RO BOP Initial Conditions: IC-21; 100% power, BOL, equilibrium Xenon, steady state, lB Diesel Generator OOS, 1C HD pump OOS, U-2 SAC OOS.
Turnover: 100% power, BOL, equilibrium Xenon, steady state. The lB Diesel Generator is OOS for replacement of Turbo Charger. The DG has been OOS for 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> and is expected to be returned to service by the end of the shift. 1C Heater Drain Pump is OOS for motor bearing replacement. Unit 2 SAC is OOS for an oil change and is expected to be returned to service by the end of the shift. The 1B CCW Pump is running for ASME testing. A tube leak being trended on the IC SG has increased over the last hour and has been confirmed at 5 gpm requiring a unit shutdown.
Event Malf. Event 1 Event No. No. Type* Description Preload RF EG09 1B DG OOS MAINT 0 Preload Preload - RO Steam Generator 1C Tube Leak (5 gpm)
TH03C BOP SRO 1 N BOP Reduce Turbine Load for Unit Shutdown due to SG leakage > Tech SRO Spec R RO Lower reactor power using rods and/or boration 2 RX18A I RO IA RCS loop Tcold RTD failed High SRO 3 EG03 C BOP Voltage Regulator malfunction Field Forcing SRO 4 RX06K I BOP Steam Generator 1C controlling level channel 1LT539 Failed High on a SRO 3 sec ramp.
5 CV01A C RO Centrifugal Charging Pump Trip SRO 6 TH03C M RO Steam Generator 1C Tube Rupture (460 gpm)
BOP SRO 7 EDI IA C RO Loss of Instrument Bus 111 coincident with Reactor Trip BOP SRO 8 RF RP84 C RO lB SI Pump fails to start automatically, Manually start an SI pump and RP15D BOP Manually Align train A ECCS for Injection due to failure to auto start SRO from loss of instrument bus 111
"*(N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient Braidwood 2002 NRC Exam Page I Scenario 02-2
SCENARIO 02-2 OVERVIEW The unit is at 100% power, BOL, equilibrium Xenon, steady state. The lB Diesel Generator is OOS for Turbo Charger replacement. The Diesel Generator has been OOS for 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> and is expected to be returned to service by the end of the shift. IC Heater Drain Pump is OOS for motor bearing replacement. Unit 2 SAC is OOS for an oil change and is expected to be returned to service by the end of the shift.
A known steam generator tube leak on the 1C S/G has just been confirmed to have increased beyond that allowed for continued plant operations and a unit shutdown has been ordered at 5 MW/min. A unit shutdown will be commenced in accordance with 1BwOA SEC-8 step 10 and Tech Spec 3.4.13, "Operational Leakage".
Once the ramp has been initiated a failure of the 1A Tcold narrow range RTD instrument high will occur. The US will enter BwOA INST-2 for the failed instrument. The crew should identify the failed Tcold instrument by abnormal rod motion and place rod control in manual. The crew should identify bistables to be tripped within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for the failed RTD channel.
After an adequate power change is observed and the actions for failed RTD are completed, a Voltage Regulator malfunction will result in field forcing. The crew should take the Voltage Regulator to OFF and use the Base Adjuster to reduce Exciter field current to less than 100 amps. The Voltage Regulator should remain OFF and control will be manual operation of the Base Adjuster to control main generator voltage.
After the actions for the Voltage Regulator failure are complete, 1C Steam Generator Level Channel 1LT-539 will fail high causing 1FW530 (IC FRV) to close. The operators will take manual control of the IC FRV and restore feedwater flow to normal. The US will enter BwOA INST-2 and direct actions for failed SG Level channel and establish normal automatic steam generator level control.
After actions are complete for the level channel failure, the 1A CV pump will trip. The operators will perform actions to isolate letdown, then restore charging and restore letdown IAW 1BwOA PRI-15, "LOSS OF NORMAL CHARGING" After the actions are complete for the CV pump trip, the 1C S/G tube leak will increase to 460 gpm requiring a Reactor Trip and Safety Injection. Coincident with the reactor trip and safety injection a fault of instrument bus Ill will result in de-energization of the bus. The crew will enter lBwEP-0 and manually align A train of ECCS due to the de-energized instrument bus. The 1B Safety injection pump will fail to auto start and the crew will take actions to manually start 1A and lB SI pumps.
The US will transition to 1BwEP-3 at step 28 of 1BwEP-0. The crew should take actions of 1BwEP-3 to stabilize the plant by cooling down and depressurizing the RCS.
Completion criteria is the performance of 1BwEP-3 through ECCS termination step 21.
Critical Tasks
- 1. E-3--A: Isolate feedwater flow into and steam flow from the ruptured S/G before transition to ECA-3.1 occurs.
- 2. E-3--B: Establish/maintain RCS temperature so that transition from E-3 does not occur because temperature is either of the following: Too high to maintain minimum required subcooling OR Below the RCS temperature that cause an extreme or severe challenge to the subcriticality and/or the integrity CSF.
Braidwood 2002 NRC Exam Page 2 Scenario 02-2
SCENARIO 2001-3 SIMULATOR OPERATOR NOTES Simulator Setup:
IC-21, 100% power, BOL, equilibrium Xenon, steady state.
Align switches:
lB DG C/S PTL and OOS ACB 1423 PTL and OOS IC HD pump C/S PLT and OOS U-2 SAC C/S PTL and OOS, ensure U-1 SAC running Perform "Ready for Training" checklist.
Swap running CC Pumps - lB in RUN, IA in STANDBY Insert PRELOAD Events:
- RF RP84 - OPEN - Auto start failure of lB SI pump
- IMF RP15D - Auto start failure of lB SI pump
- IMF: TH03C, 5 gpm - SG tube leak in IC SG is intended to force a unit shutdown based on exceeding allowable limits per Tech Specs and the procedure.
Acknowledge RM- 11 Grid 1 alarms Open 1BwOA SEC-8 and place keep through step IOc Event 1 Power reduction.
Event 2 1A RCS loop Tcold narrow range RTD failed high SDG: RXI Malf: RX18A, 630 Initiate event after clearly observing reactivity change/response of plant to requested power ramp and with lead examiners concurrence.
Acknowledge all info passed to the SM, WEC, and maintenance.
SDG RX4, RX2 Cabinet door #1 open RF RP20 OPEN OPDT Trip TB41IG CI-124 BS-I RF RX014 TRIP OPDT Runback TB411H CI-124 BS-2 RF RX136 TRIP OTDT Trip TB411C CI-124 BS-3 RF RXO13 TRIP OTDT Runback TB411D CI-124 BS-4 RF RX135 TRIP Low Tave TB412G CI-121 BS-2 RF RX016 TRIP Lo-Lo Tave TB412D CI-121 BS-1 RF RX015 TRIP Cabinet door #1 Close RF RP20 CLOSE Event 3 Voltage Regulator malfunction Field Forcing.
SDG: EG1 Malf: EG03, 94%
Initiate malfunction after actions are taken for the failed RTD and with lead examiners concurrence.
If asked role play as U-2 admin and/or extra NSO for Unit 2 Main Generator VARs have decreased.
Acknowledge all info passed to the SM, WEC, and maintenance.
NOTE: Failure to take action to reduce exciter field current will result in a generator trip reactor trip.
Braidwood 2002 NRC Exam Page 3 Scenario 02-2
Event 4 SG 1C controlling level channel 1LT-539 fails high.
SDG: RX19 Malf: RX06K, 100%
Initiate malfunction after actions are taken to manually control main generator exciter field current and with lead examiners concurrence.
Use the following to trip bistables for the failed channel Cabinet door #1 open RF RP20 OPEN P14 LB539A C2-753 BS-1 RF RX063 TRIP Lo-2 Rx Trip/AF Pump Start LB539B C2-753 BS-2 RF RX064 TRIP Cabinet door #1 Close RF RP20 CLOSE Event 5 Centrifugal Charging Pump trip SDG: CV5 Malf: CVO1A Initiate this event after actions for SG level channel failuire are completed and with lead examiners concurrrence.
If sent to locally investigate the 1A CV pump and breaker, wait 3 minutes, perform first check, and report no apparent cause at the breaker (bus 141 cub 11).
If sent to check the lB CV pump, wait 3 minutes, perform first check, and report "normal operating conditions".
Acknowledge all info passed to the SM, WEC, and maintenance.
Remote Starts or Stops of the Aux Lube Oil pumps can be accomplished by RF CV76 Event 6 SGTR IC SG. Leakage increases to 460 gpm over 3 minutes.
SDG: TH5 Malf: TH03C, 460 gpm, 180 sec ramp.
Initiate failure after tech specs are investigated for the CV pump and with lead examiners concurrence.
Acknowledge all info passed to the SM, WEC, and chemistry.
Event 7 Loss of Instrument Bus 111 SDG: ED6 Malf: EDIlA Trigger - When Reactor trip breakers are opened The loss of Instrument Bus 111 occurs after the reactor trip and prior to initiation of Safety Injection. This will prevent the auto actuation of Train A ESFAS. The loss of the instrument bus is non-recoverable for the duration of the scenario and probably won't be pursued by the crew. If requested to investigate as NLO wait 3 minutes, perform first check and report that Instrument Bus 111 indicates evidence of electrical damage.
Acknowledge all info passed to the SM, WEC, and maintenance.
Event 8 1B SI pump fails to start automatically. Start and Manually Align train A ECCS for Injection due to failure to auto start from loss of instrument bus 111 Malf: (preload) RP15D RF: (preload) RP84 Acknowledge all info passed to the SM, WEC, and maintenance.
Braidwood 2002 NRC Exam Page 4 Scenario 02-2
Scenario No.: 02-2 Event No.: I Event
Description:
Plant shutdown due to excessive S/G leakage Time Position Applicant's Actions or Behavior CUE: As a result of the excessive steam Generator tube leakage, 1BwOA SEC-8 dictates a power reduction to Hot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of exceeding 150 gpd.
US Implement actions of 1BwGP 100-4 US Direct load reduction to MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> CREW Review applicable Prerequisites, 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 by:
"o Effects of previously performed borations "o Boration Dilution Tables
"* Determine required boric acid flow rate.
"* Set 1FK-1 10 BA Flow Cont to desired boration rate.
"* Set IFY-01 10 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 (CV 10B open, BA pump is running, CV1 10A throttles opens, BA flow on recorder.
OR Batch addition:
"* Open CV1OB.
"* Open CV 1OA.
"* Start BA Transfer pump.
"* When desired amount of BA added, stop BA Transfer pump.
"* Close CV1 1A o Flush BA line.
- Close CV1OB.
Comments:
Braidwood 2002 NRC Exam Page 5 6/18/2002
Scenario No.: 02-2 Event No.: 1 Event
Description:
Plant shutdown due to excessive S/G leakage Time Position Applicant's Actions or Behavior BOP Initiate turbine load reduction:
"* Depress LOAD RATE MW/MIN
"* Enter desired value for rate
"* Depress REF
"* Enter power level 620 MW.
"* When ready to begin load decrease, depress GO
"* Verify load decreases.
RO/BOP Monitor power/load decrease:
- Monitor reactor power, Tave, Al RO During boration:
"* Monitor VCT level
"* Verify RCS boron concentration increasing
"* Monitor BA blender counter
"* Verify boration stops at preset value NOTE: Following clearly observable plant response from the reactivity changes and with lead examiners cue, Event 2 is entered.
Comments:
Braidwood 2002 NRC Exam Page 6 6/18/2002
Scenario No.: 02-2 Event No.: 2 Event
Description:
lA RCS loop Tcold failed high Time I Position [ Applicant's Actions or Behavior CUE Annunciators:
1-14-Dl TAVE CONTROL DEV HIGH 1-14-B 1 OTAT HIGH RX TRIP ALERT I-14-E2 AUCT TAVE HIGH I-14-A5 LOOP 1A AT DEV LOW I-14-B3, C3, D3 LOOP 1B,C,D TAVE DEV LOW Control rods stepping in 1A Tave indication high RO/US Identify /report IA Tave channel failure RO Determine turbine load stable and place rods in Manual.
US Implement 1BwOA INST-2, "OPERATION WITH A FAILED INSTRUMENT CHANNEL" Attachment A and direct operator actions.
RO Verify rod bank select switch in manual RO Manually defeat failed RTD channel:
"* Select failed Tave channel with TAVE DEFEAT switch
"* Select failedAT channel with AT DEFEAT switch RO Select an operable RTD channel to the AT recorder RO Check if rod control can be placed in auto
"* TURBINE LOW POWER INTLK C5 - NOT lit
"* Tave-Tref deviation - Stable and within 1°F
- IF NOT restore Tave-Tref deviation to within 1°F
- Adjust rods
"* Place ROD BANK SELECT switch in AUTO RO Check PZR level
- PZR level NORMAL and STABLE RO/US o Dispatch operator to locally trip bistables for failed channel by placing switches to "TEST" Comments:
Braidwood 2002 NRC Exam Page 7 6/18/2002
Scenario No.: 02-2 Event No.: 2 Event
Description:
lA RCS loop Tcold failed high Time I Position I Applicant's Actions or Behavior RO Check P 12 interlock
- Tave greater than 550'F
. LO-2 TAVE STM DUMP INTLK P12 -NOT LIT BOP Monitor secondary plant parameters as a result of the primary transient Assist RO as requested / directed by US o Coordinate bistable tripping
"* Investigate BwARs
"* Make phone calls as directed by US/RO
"* Provide appropriate peer checks to RO as requested
"* Control Turbine loading as directed by US/RO US Refer to Tech Spec
- 3.3.1 Reactor Trip Instrumentation
- 3.3.2 ESFAS Instrumentation
NOTE: After actions are complete for failed Tave channel and lead examiners concurrence, Event 3 is entered.
Comments:
Braidwood 2002 NRC Exam Page 8 6/18/2002
Scenario No.: 02-2 Event No.: 3 Event
Description:
Voltage Regulator malfunction Field Forcing Time Position I Applicant's Actions or Behavior CUE: Annunciators:
1- 19-B6 GENERATOR FIELD FORCING 1-19-C8 GENERATOR VOLT REG TROUBLE I-19-E8 TGTMS ALARM SETPOINT EXCEEDED Increasing Exciter Field Current BOP Identify/report main generator field forcing.
BOP/US Perform immediate actions of lBwAR 1-19-B6:
- If Voltage Regulator failure is suspected then,
"* SHIFT Voltage Regulator to OFF
"* Using the Base Adjuster, Reduce exciter field current to <100 amps
"* Notify Electric Operations BOP/US Perform subsequent operator actions of 1BwAR 1-19-B6:
0 Refer to BwGP 100-3A6/3A7 for MW and VAR limits with regulator out of service US Inform SM/Electrical Operations of Voltage Regulator failure.
RO Monitor Primary plant response during the secondary transient Assist BOP as difected/requested by US/BOP
"* Determine MW vs VAR loading
"* Investigate BwARs
"* Provided appropriate peer checks to BOP as requested
"* Make phone calls/notifications as directed NOTE: IF Exciter field is NOT reduced far enough Turbine Generator Temperature monitoring System may alarm and the following actions might be required.
CUE: Annunciators:
1-19-E3 TGTMS GEN TEMP TRIP STPT EXCEEDED 1-19-E8 TGTMS GEN TEMP ALARM STPT EXCEEDED US Implement 1BwOA TG-2, "TGTMS TROUBLE" and direct operator actions.
CREW Verify Main Generator operating within limits.
- Refer to lBwGP 100-3A6/3A7 for excitation limits Comments:
Braidwood 2002 NRC Exam Page 9 6/18/2002
Scenario No.: 02-2 Event No.: 3 Event
Description:
Voltage Regulator malfunction Field Forcing Time Position Applicant's Actions or Behavior BOP Dispatch operator to check proper operation of the following turbine generator support systems:
"* Stator water
"* Hydrogen cooling
"* Hydrogen seal oil
"* Exciter cooling
"* Bus duct cooling
"* Turbine oil BOP/US Determine that problem is due to excessive VARs and reduce Exciter field current with Base adjuster to clear condition.
NOTE: When actions are complete for voltage regulator failure and with lead evaluators concurrence, Events 4 is entered Comments:
Braidwood 2002 NRC Exam Page 10 6/18/2002
Scenario No.: 02-2 Event No.: 4 Event
Description:
Steam Generator IC controlling level channel 1LT539 Failed High on a 3 sec ramp Time I Position] Applicant's Actions or Behavior CUE: Annunciators:
1-15-C4, "S/G IC FLOW MISMATCH FW FLOW LOW" 1-15-C8, "S/G IC LVL HI-2 TURB TRIP P-14 ALERT" 1-15-C9, "S/G IC LEVEL DEVIATION HIGH LOW" FRV 1FW530 closing I LT-539 meter indicating full scale Feedwater flow decreasing BOP/US Identify/report failure of 1LT-539 IC SG Narrow Range Level Channel US Implement 1BwOA INST-2, "OPERATION WITH A FAILED INSTRUMENT" Attachment E and direct operator actions.
BOP Take manual control of 1C SG Feedwater Regulating Valve 1FW530 Increase demand to control feedwater flow greater than steam flow to restore level to normal BOP Check affected SG level:
"* SG level normal
- If NOT
"* Place feed reg valve in manual
"* Restore SG level to a stable condition
"* Operable SG level control channel selected
- Select 1LT558 as control BOP Dispatch operator to locally trip bistable for failed channel by placing indicated switches to test I1LT-539 IC SG Narrow Range Level Channel
"* P14 LB539A
"* Lo-2 Rx Trip/AF pump start LB 539B US Determine Status of AMS System to be ok for this failure Comments:
Braidwood 2002 NRC Exam Page I11 6/18/2002
Scenario No.: 02-2 Event No.: 4 Event
Description:
Steam Generator IC controlling level channel 1LT539 Failed High on a 3 sec ramp Time Position Applicant's Actions or Behavior RO Monitor changing primary plant parameters as a result of changing feedwater flows
"* Reactor Power
"* Tave
"* Pzr pressure Assist BOP as directed/requested by US/BOP
"* Provide appropriate peer checks as requested
"* Investigate BwARs
"* Make phone calls/notifications as directed US Refer to Technical Specifications
- 3.3.1 trip bistables within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
- 3.3.2 trip bistables within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
NOTE: After the actions for failed level channel are complete and with lead examiners concurrence, Event 5 is entered.
Comments:
Braidwood 2002 NRC Exam Page 12 6/18/2002
Scenario No.: 02-2 Event No.: 5 Event
Description:
Centrifugal Charging Pump Trip Time Position Applicant's Actions or Behavior CUE Annunciator:
1-9-A3 CHG PUMP TRIP 1-9-D3 CHG LINE FLOW HIGH LOW Charging pump trip indication Loss of seal injection flow indication RO Identify/report trip of the 1A CV pump RO/US Refer to BwAR for charging pump trip for immediate operator actions:
Initiate and direct the actions of 1BwOA PRI-15 "LOSS OF NORMAL CHARGING" Comments:
Braidwood 2002 NRC Exam Page 13 6/18/2002
Scenario No.: 02-2 Event No.: 5 Event
Description:
Centrifugal Charging Pump Trip Time Position Applicant's Actions or Behavior RO Perform actions of 1BwOA PRI-15:
Identify neither CV pump is running
"* Close 1CV8149A,B,C
"* Close 1CV459 and 1CV460 Check VCT suction valves open
- 1CV112B and 1CV112C Monitor and maintain VCT level greater than 20%
Check VCT Temperature High alarm (1-9-C2) not lit Check previously running CV pump was not gas bound o # 1 Seal leakoff flow not fluctuating prior to pump trip 0 CV pump flows not fluctuating prior to the pump trip 0 CV discharge press not fluctuating prior to the pump trip 0 CV pump amps not fluctuating prior to the pump trip Restore normal charging flow "o Check miniflows open 1CV8 110 and 1CV8116 "O Check RCS pressure at NOP Start the standby 1B CV pump Check CV alignment
" 1CV8146 OR 1CV8147 open
"* 1CV8324A OR 1CV8324B open
"* 1CV8105 AND 1CV8106 open
"* Check charging flow established RO/US Refer to BwAR for charging pump trip for subsequent operator actions:
Comments:
Braidwood 2002 NRC Exam Page 14 6/1 8/2002
Scenario No.: 02-2 Event No.: 5 Event
Description:
Centrifugal Charging Pump Trip Time Position Applicant's Actions or Behavior BOP/RO Restore normal letdown flow per 1BwOA ESP-2 "REESTABLISHING CV LETDOWN DURING ABNORMAL CONDITIONS.
"* Verify CLOSED 1CV8149A, B, C, letdown orifice isolation valves
"* Verify CLOSED 1CV459 & 1CV460 letdown line isolation valves
"* Check 1CV8401A letdown Hx isolation valve OPEN
"* Verify 1CV8324A and 1CV8389A regen Hx isol valves OPEN
"* Verify 1CV8152 and 8160 letdown Cnmt Isolation valves OPEN
"* Verify BTRS mode select switch OFF
"* Place 1CV 131 controller in MANUAL at 40% demand
"* Place 1CC130A/B flow controller in MANUAL at 60% demand
"* Check CV flow established- 1CV8105 and 1CV8106 open
"* Throttle 1CV182 and 1CV121 to establish 8-13 gpm seal inj and 100 gpm charging flows
"* Open 1CV459 and 1CV460 if closed
"* Simultaneously perform the follwing:
- Open orifice isolation valves 1CV8149A/B/C for desired flow
- Adjust 1CV131 controller to maintain letdown header pressure at 360 psig and place in AUTO
- Ensure 1CC130A/B controller maintains letdown temperature 90' to 115'F and place in AUTO
- Verify 1PR06J in service RO/US Dispatch operator to investigate cause of 1A CV pump trip.
US Refer to Tech Specs for tripped CV pump.
- 3.5.2 Restore in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
- TRM 3.L.a thru d
- 3.8.1 DG Required Action B.3 declare both CV pumps inop if condition of DG and opposite train CV pump exists for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
US Inform SM/Maint of 1A CV pump trip/status.
NOTE: After the actions for charging pump trip are complete and with lead exminers concurrence, Events 6-8 are entered.
Comments:
Braidwood 2002 NRC Exam Page 15 6/18/2002
Scenario No.: 02-2 Event No.: 6, 7 and 8 Event
Description:
Steam Generator 1C Tube Rupture (460 gpm).(7)
Instrument Bus 111 fault when the reactor is tripped (8) 1B SI Pump fails to start automatically, Manually start an SI pump and Manually Align train A ECCS for Injection due to failure to auto start from loss of instrument bus 111 (9)
Time Position Applicant's Actions or Behavior CUE: Annunciators:
I-12-B4 PZR LEVEL CONT DEV LOW 1-12-Cl PZR PRESS CONT DEV LOW HTRS ON SG blowdown radiation monitor 1PR08J increasing SJAE/Gland Steam Exhauster radiation monitor 1PR 27J increasing Increased charging flow PZR level dropping PZR pressure dropping FW flow/Steam flow mismatch for ID SG CREW Identify/report increase in RCS leakage RO Report inability to maintain PZR level > 17%
US Direct reactor trip and Safety Injection initiation RO Manually trip reactor Manually actuate SI US Implement 1BwEP-0 "REACTOR TRIP OR SAFETY INJECTION" and direct operator actions.
RO Perform immediate operator actions of 1BwEP-0:
Verify reactor trip
"* Rod bottom lights LIT
"* Reactor trip & Bypass breakers open
"* Neutron flux decreasing Comments:
Braidwood 2002 NRC Exam Page 16 6/18/2002
Scenario No.: 02-2 Event No.: 6, 7 and 8 Event
Description:
Steam Generator IC Tube Rupture (460 gpm).(7)
Instrument Bus 111 fault when the reactor is tripped (8) lB SI Pump fails to start automatically, Manually start an SI pump and Manually Align train A ECCS for Injection due to failure to auto start from loss of instrument bus 111 (9)
Time Position Applicant's Actions or Behavior BOP Perform immediate operator actions of 1BwEP-0:
Verify turbine trip
"* Turbine throttle valves closed
"* Turbine governor valves closed BOP Verify power to 4KV busses
"* Bus 141 alive light lit
"* Bus 142 alive light lit CREW Check SI status:
"* SI First OUT annunciator lit (1-1 1-C 1)
"* SI ACTUATED lit (1-BP-4.1)
"* SI Equipment actuated (CV Cold leg injection S18801B open)
Determine SI actuated Identify/report train A ESFAS components did NOT actuate due to instrument bus 111 de-energized.
Actuate SI by taking either SI switch to ACTUATE "o IPM05J "o 1PM06J BOP Verify FW isolated
"* FW pumps tripped
"* FW Isolation Monitor lights lit
"* FW pump discharge valves stroking closed 1FW002A-C RO Verify ECCS pumps running
"* CENT Chg pumps- IA CV pump is unavailable / lB running
"* RH pumps -manually start IA RH pump
[CT] 0 SI pumps - manually start 1A SI pump and/or lB SI pump E-O--I Comments:
Braidwood 2002 NRC Exam Page 17 6/18/2002
Scenario No.: 02-2 Event No.: 6, 7 and 8 Event
Description:
Steam Generator 1 C Tube Rupture (460 gpm).(7)
Instrument Bus 111 fault when the reactor is tripped (8) lB SI Pump fails to start automatically, Manually start an SI pump and Manually Align train A ECCS for Injection due to failure to auto start from loss of instrument bus 111 (9)
Time Position Applicant's Actions or Behavior BOP Verify RCFCs running in Accident Mode Group 2 RCFC Accident Mode Status lights NOT lit Manually align RCFCs in accident mode as necessary:
"* Stop A and C RCFC high speed
"* Close ISX112A and 1SXI14A
"* Open 1SX147A
"* Verify open 1SXO16A and 1SX027A
"* Start A and C RCFCs in low speed BOP Verify Phase A isolation
"* Group 3 Monitor lights NOT lit
"* Manually actuate Phase A
- Close train A valves as required:
"* 1PRO01A
"* 1PR066
"* 1PS228A
"* 1PS228B
"* 1WO006A
"* 1WO020A
"* 1WO056B
"* 1CV8152
"* 1CV8100 1IA065 BOP Verify CNMT Ventilation isolation
- Group 6 Monitor lights lit Comments:
Braidwood 2002 NRC Exam Page 18 6/18/2002
Scenario No.: 02-2 Event No.: 6, 7 and 8 Event
Description:
Steam Generator IC Tube Rupture (460 gpm).(7)
Instrument Bus 111 fault when the reactor is tripped (8) 11B SI Pump fails to start automatically, Manually start an SI pump and Manually Align train A ECCS for Injection due to failure to auto start from loss of instrument bus 111 (9)
Time Position Applicant's Actions or Behavior BOP Verify AF system:
1B AF pumps running Manually start 1A AF pump
"* AF isolation valves open (AF13A-H)
"* AF flow control valves throttled (AF005E-H)
NOTE: The A train AF005A-D will be closed due to loss of instrument bus 111.
Verify CC Pumps running o Manually start 1A CC pump (may have previously started)
Verify SX Pumps running o Manually start 1A SX pump (may have previously started)
Check Main Steamline Isolation NOT required
"* Check SG pressure > 640 psig
"* Check CNMT pressure <8.2 psig BOP Check if CNMT Spray is required
- AF flow > 500 gpm
- SG levels maintained between 10% and 50%
BOP/US Check for NR level NOT increasing in uncontrolled manner Identify/report 1C as ruptured SG.
[CT] If ruptured SG suspected, isolate AF Isol valves:
E-3-A
- 1AF013C
- 1AF013G Comments:
Braidwood 2002 NRC Exam Page 19 6/18/2002
Scenario No.: 02-2 Event No.: 6, 7 and 8 Event
Description:
Steam Generator 1C Tube Rupture (460 gpm).(7)
Instrument Bus 111 fault when the reactor is tripped (8) 1B SI Pump fails to start automatically, Manually start an SI pump and Manually Align train A ECCS for Injection due to failure to auto start from loss of instrument bus 111 (9)
Time Position Applicant's Actions or Behavior RO Verify ECCS valve alignment Group 2 CL Injection monitor lights NOT all lit Manually align train A valves as required:
"* 1CV112B CLOSED
"* ICV112DOPEN
"* 1CV8106 CLOSED
"* 1S18801A OPEN RO Verify ECCS flow:
"* High Head SI flow >100 gpm
"* RCS pressure is NOT <1700 psig RO Check at least ONE PZR PORV relief path available:
"* PORV Isol valves at least one energized
"* PORV relief path at least one available
"* Main Transformer output breakers open
"* OCB 1-8
"* OCB 7-8
"* PMG output breaker open BOP Verify DG running
"* Manually start lA DG (lB DG OOS)
"* SX valve open 1SX169A
"* Dispatch operator locally to check operation Comments:
Braidwood 2002 NRC Exam Page 20 6/18/2002
Scenario No.: 02-2 Event No.: 6, 7 and 8 Event
Description:
Steam Generator IC Tube Rupture (460 gpm).(7)
Instrument Bus 111 fault when the reactor is tripped (8) 1B SI Pump fails to start automatically, Manually start an SI pump and Manually Align train A ECCS for Injection due to failure to auto start from loss of instrument bus 111 (9)
Time Position Applicant's Actions or Behavior BOP Verify Control Room ventilation aligned-for emergency operations:
"* Check RM-II Grid 2 Control Room outside air rad monitors less than alert alarm setpoint.
"* Operating VC train equipment running Train A
"* Supply fan
"* Return fan
"* M/U fan - manually start OA VC M/U fan
"* Chilled water pump
- MCR chiller OA
"* M/U fan outlet damper NOT full closed OVC24Y
"* VC train M/U filter light LIT
"* Operating VC train Charcoal Adsorber aligned for train A
- Place Recirc Charcoal Adsorber selector switch to Adsorb
"* OVC43Y closed
"* OVC21Y open
"* OVC22Y open
"* Control Room pressure greater than +0. 125 inches water on OPDI-VC038 BOP Verify Auxiliary Building ventilation aligned
- Two inaccessible filter plenums aligned
"* PlenumA fan OVA03CB running
"* Damper OVA023Y open
"* Damper 0VA436Y closed
"* Plenum C fan OVA03CE running
"* Damper OVA067Y open
"* Damper OVA052Y closed BOP Verify FHB ventilation aligned
"* Train B fan OVA04CB running
"* OVA055Y open
"* OVA062Y open
"* 0VA435Y closed RO Check PZR spray valves and PORVs
"* Normal spray valves closed
"* PORVs closed Comments:
Braidwood 2002 NRC Exam Page 21 6/18/2002
Scenario No.: 02-2 Event No.: 6, 7 and 8 Event
Description:
Steam Generator 1C Tube Rupture (460 gpm).(7)
Instrument Bus 111 fault when the reactor is tripped (8) 1B SI Pump fails to start automatically, Manually start an SI pump and Manually Align train A ECCS for Injection due to failure to auto start from loss of instrument bus 111 (9)
Time Position Applicant's Actions or Behavior RO Maintain RCS temperature control
- Check RCPs any running 0 Tave Stable or trending to 557 'F RO/US Check status of RCPs and determine RCPs can remain running
- If any running, apply trip criteria "o High Head SI flow >100 gpm on 1FI-917 OR "o SI flow > 200 gpm on 1FI-918/922 "o RCS pressure < 1425 psig BOP Check if SG secondary pressure boundaries are intact
- Check pressure in all SGs
"* No SG pressure decreasing in an uncontrolled manner
"* No SG completely depressurized CREW Identify ruptured SG "o Unexpected rise in NR level on 1C Steam Generator "o Main steamline rad monitors NOT normal for plant conditions on 1C Steam Line "o RT-AR022 Grid 1 4AD322 "o RT-AR023 Grid 1 4AD323 "o High activity for any SG sample CREW Identify/report IC SG as ruptured US Implement 1BwEP-3 "STEAM GENERATOR TUBE RUPTURE" WOG-1C and direct operator actions.
RO/US Check status of RCPs and determine RCPs can remain running
- If any running, apply trip criteria "o High Head SI flow >100 gpm on 1FI-917 OR "o SI flow > 200 gpm on 1FI-918/922 "o RCS pressure < 1425 psig Comments:
Braidwood 2002 NRC Exam Page 22 6/18/2002
Scenario No.: 02-2 Event No.: 6, 7 and 8 Event
Description:
Steam Generator 1C Tube Rupture (460 gpm).(7)
Instrument Bus 111 fault when the reactor is tripped (8) 11B SI Pump fails to start automatically, Manually start an SI pump and Manually Align train A ECCS for Injection due to failure to auto start from loss of instrument bus 111 (9)
Time Position Applicant's Actions or Behavior CREW Identify ruptured SG "o Unexpected rise in NR level "o Main steamline rad monitor "o 1RT-AR022 Grid 1 4AD322 "o 1RT-AR023 Grid I 4AD323 "o High activity for any SG sample Identify/report IC SG as ruptured SG BOP Isolate flow from rupture SG
- Verify closed when SG pressure < 1115 psig
- Verify SG blowdown isolation valves closed
"* ISDO02G
"* 1SDO02H
[CT] 0 Close MSIV and MSIV bypass valves for IC SG E-3--A o Check PORVs on intact SGs available for RCS cooldown BOP/US Check ruptured SG level
[CT]
- Narrow Range >l10%
E-3--A
"* 1AF013C (Close if flow is present indicating leakage past the closed IAF005)
"* 1AF013G BOP Check Rupture SG pressure
- Ruptured SG pressure greater than 320 psig a IfNOT go to 1BwCA 3.1 Comments:
Braidwood 2002 NRC Exam Page 23 6/18/2002
Scenario No.: 02-2 Event No.: 6, 7 and 8 Event
Description:
Steam Generator IC Tube Rupture (460 gpm).(7)
Instrument Bus 111 fault when the reactor is tripped (8) lB SI Pump fails to start automatically, Manually start an SI pump and Manually Align train A ECCS for Injection due to failure to auto start from loss of instrument bus 111 (9)
Time Position Applicant's Actions or Behavior BOP Initiate RCS Cooldown
[CT] a Determine required core exit temperature from table based on current ruptured SG pressure E-3--B o Check PZR pressure < 1930 psig
- PZR LOW PRESS SI BLOCK PERMISSIVE P-11 Lit 0 If NOT continue with procedure until P-Il Lit before blocking STM LINE SI
- Block Steamline Isol SI @ P-11
- Dump Steam to condenser from intact SGs at maximum rate NOTE: After cooldown is intitiated the operators may hold the Steam Dump Interlock switches in Bypass as temperature approaches the P-12 setpoint to prevent interruption of the cooldown.
If the interlock occurs the operator will have to place the main steam pressure controller in manual and at minimum demand, bypass P-12 using both switches and then re-establish the cooldown.
"* 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) when < required temperature BOP Check intact SG levels:
"* Narrow range levels > 10%.
"* Control feed flow to maintain narrow range levels between 10% and 50%.
"* Check narrow range levels not increasing in an uncontrolled manner.
RO Check PZR PORVs and isolation valves
"* Power to PORV Isol valves I1RY8000A
- lRY8000B
"* PORVs closed
"* 1RY455A
"* 1RY456
"* At least ONE PORV Isol valve OPEN "o 1RY8000A "o IRY8000B BOP/RO Reset SI if necessary Comments:
Braidwood 2002 NRC Exam Page 24 6/18/2002
Scenario No.: 02-2 Event No.: 6, 7 and 8 Event
Description:
Steam Generator 1C Tube Rupture (460 gpm).(7)
Instrument Bus 111 fault when the reactor is tripped (8) 1B SI Pump fails to start automatically, Manually start an SI pump and Manually Align train A ECCS for Injection due to failure to auto start from loss of instrument bus 111 (9)
Time Position Applicant's Actions or Behavior BOP Reset CNMT Isolation:
"* Reset CNMT Isolation Phase A.
"* Check SACs - any running
"* Open instrument air CNMT isolation valves.
"* 1IA065
"* 1IA066 BOP Verify all AC busses energized by offsite power BOP Check if RH pumps should be stopped:
"* Suction aligned to RWST
"* RCS pressure greater than 325 psig
"* Stop RH pumps and place in standby RO 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:
- Acceptable per Attachment A and Figure lBwEP 3-2 (+20'F)
Comments:
Braidwood 2002 NRC Exam Page 25 6/18/2002
Scenario No.: 02-2 Event No.: 6, 7 and 8 Event
Description:
Steam Generator 1 C Tube Rupture (460 gpm).(7)
Instrument Bus 111 fault when the reactor is tripped (8) 1B SI Pump fails to start automatically, Manually start an SI pump and Manually Align train A ECCS for Injection due to failure to auto start from loss of instrument bus 111 (9)
Time Position Applicant's Actions or Behavior RO Depressurize RCS using PZR sprays to minimize break flow and refill PZR:
[CT] 0 Normal sprays available E-3--C
- Spray PZR with maximum spray until any of the following are satisfied o BOTH:
"* RCS pressure less than ruptured pressure
"* PZR level greater than 12%
o PZR level greater than 69%
o RCS subcooling NOT acceptable
- Close normal spray valves
- Check PZR Aux spray valve closed Use ONE PZR PORV if normal PZR spray is inadequate RO/BOP Check if ECCS flow should be terminated
"* RCS subcooling acceptable
"* Secondary heat sink o Narrow range level in at least ONE SG >10%
OR o >500 pgm total feed flow to SGs
"* RCS Pressure stable or increasing
"* PZR level >12%
RO/BOP Stop ECCS pumps and place in standby
"* SI pumps
"* All but one CV pump NOTE: The scenario can be terminated once ECCS termination steps are complete with lead examiners concurrence Comments:
Braidwood 2002 NRC Exam Page 26 6/18/2002
SHIFT MANAGER TURNOVER Weekday, Today, 2001 ONCOMING SHIFT 2 I t Z1 U1141 I I A tW A UI UNIT 0 & I MAJOR QOS's UNI 0__1________________
MODE ............ 1 I B Emergency Diesel Rx Pwr ............ 100 Generator Generator MWe ..... 1256 Max Load/Power .... 100% 1C Heater Drain Pump Min Load/Power .... 700 MW Max Ramp Rate ..... 5 MW/Min Desired Delta I ..... Target On-Line Risk ....... Green Boron @ .......... 934 Control Bank ....... D (d 214 3.8.J Loncition B tor 1B EDG 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> ago. Est RTS by end of shift t5wk.)3 ).6.1.1 - ctue in o flours 3.4.13 RCS Leakage - IC Steam Generator at 5 gpm
,UNIT 0 & I IN PROGRESS UNIT 0 & I PENDING lB EDG turbo charger replacement Following step 10.c RNO of 1BwOA SEC-8, Shutdown Unit 1 per 1BwGP 100-4 due to IC HDP bearing replacement increased operational leakage - IC SG.
Shutdown unit to MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> using lB CCW Pump run for ASME Testing 1BwGP 100-4 and 1BwGP 100-4T1, normal plant shutdown.
lBwOA SEC-8 has been in progress and has been performed up to and including step 1O.c Focus Areas:
"* Verification Practices
"* Command and Control Standard for Execution of Critical Steps THINK CONFIGURATION CONTROL and SAFETY!!!
SCH-EDULED ACTIVITY CONFLICT IC21 .doc
SHIFT MANAGER TURNOVER
'INIT 2 STATUS UNIT1 2 MAJOR OOS's
.4ODE ............ 1 A~ n unit Z SAU -z kun change I'~
Rx Pwr ............ 97.6 Generator MWe ..... 1197 Max Load/Power .... 97.6 impulse pressure Min Load/Power .... 700 Max Ramp Rate ..... 5 mw/min Desired Delta I ..... Target On-Line Risk ....... Green Boron @ .......... 1037 Control Bank ....... D@210 LCOAJR EN~TRIES PREVIOUS 48 HRS__ UNIT 2 MAJOR SURVEILLANCES i1coar num" "Affected Equipment" UNIT 2 IN PROGRESS UNIT 2 PENDING Oil change on Unit 2 Station Air Compressor. RTS by end of shift today.
Dose INFO: Dose goal for day 10 mr SCHEDULED ACTIVITY CONFLICT IC21 .doc
SHIFT MANAGER TURNOVER
______________________Administrative emporary Procedures ! Modifications T-mod U1 Tm B RVLIS. Jumper Installed on 4C U-1 MPT Disconnect.
1 FW009A T-Mod for Hyd Pp Press Sw 1 PS-FW1 62. T-mod for drain on 1 B AF casing. Tmod for no disc in 2CC9502B installed.
Daily Orders! Special Op Orders Daily Manning Schedule See sheet for restricted duty personnel and overtime restrictions Oncoming STA Fire Chief Control Room Rounds (GSEP / LER / DVR / ENS)
Material TS Conditioning SFP High Level alarm did not alarm during calibration RWP's / Releases / Precautions / ALARA Infrequent Evolution Activities Lesson learned files L:\shared\opex then ctrl F to search SPSO / Division LD Alternate BPO Outside # 815-727-5902/5903 Tie # 8-565-5902/5903
-Unrit 1 Comments Unit Comhmon Comments Battery 112 cell 32 has floating material in electrolyte, eval'd OK. U1 FC Cleanup SFP DO.0OOS prevents filling U-I tanks normally, but BwOP DO-6 U2 FC Cleanup OFFLINE (leak) can be used to fill tanks. T-MOD is installed allowing U-I boiler FC Cooling Ul ops. 50K DO Tank empty 1AF006A is leaking by from CST. 125K DO Tank and FRAC Tks Certified Aux Steam U-1 ES -->U1 HDT U-0 CC Hx Ul U-0 CC Pump Bus 141 Ul Aux boiler Wet lay-up U2 Aux boiler Wet lay-up SAC / Dryer U1/U0 MUDs U-1 CST CW Makeup Running OA/OB CW Blowdown On Lake Level 5.8' Unit 2 Comments General Comments 2AF017A leaking by .3 gpm, AR 990116738 Conference Call Phone Number- 1-800-232-1234 Telecornference S/G sampling lines/valves at HRSS are not correct. Do not folder ID #=472664085 hang OOS on any 2PS181 valves till further notice. Meeting Place 630-663-7120 +code 2PS229A still blows fuse 2PA32J Ckt 9 Duty Team is located @ SITE APPS, NRC Duty list in book CV seal leakage: Substation construction (John Strle) Cell phone 815-351-8472 2A Running 200cc/min shutdown about 6 drops/min 2B Running -12 dpm; S/D- none Caution Cards Abnormal Positioned Components CCNUM EPN CCNUM EPN AbnormaPosition SM BEEPER TURNOVER Shift 1 To 2 Time Now Date Today Offgoing Oncoming IC21 .doc
BwAP 335-1 T6 Revision 8 Information Use UNIT 1 NSO TURNOVER Weekday, Today, Oncominq Shift 2 1B EDG turbo charger replacement. RTS by end of shift today BwOSR 3.8.1.1 1C Heater Drain Pump bearing replacement Per Step 10.c RNO of 1BwOA SEC-8, shutdown Unit 1 due to RCS operational leakage to MODE 3 within the next 6 1B Component Cooling Water Pump run for ASME Testing hours. IC Steam Generator leakage at 5 gpm 1BwOA SEC-8 is in progress at step 10. Perform a normal plant shutdown using 1 BwGP 100-4 and 1BwGP 100-4T1.
LO1G TERM ADMINISTRATIVE Temporary procedures Temporary alterations New caution cards Unit logbook Unit routine BDPS Icoar in mode 3.
Aux. Electric room access Daily orders Control board walk down LCO/TLCO RETS DEQUIPIAAR 3.8.1 1B EDG 3.4.13 Leakage IC2 L.doc
BwAP 335-1T6 Revision 8 Information Use
________________________ TURNOVER ITEMS ISO SHIFTLY/DAILY SURVEILLANCE z) SSPS CHANNELS/BISTABLES B train SSPS logic ground to chassis ground had higher than expected readings during SSPS, AR written.
- 3) SYS - SAFEGUARDS
- 4) SYS - PRIMARY CC to spent fuel pool hx is at 2800 gpm.
- 5) SYS - BALANCE OF PLANT Spent fuel pool cooling now on Unit 1.
- 6) ALARMS-SER/ANNUNCIATOR
- 7) ALARMS - PROCESS/RM-1 1
- 8) ALARMS - FP/OTHERS
- 9) CHEMISTRY Max flow through condensate polishers at full power is -2000 gpm without causing a low npsh alarm. This is only a guideline and not an absolute value.
- 10) RADIATION PRECAUTIONS
- 11) NUCLEAR INSTRUMENTATION_
- 12) MCB INSTRUMENTATION
- 13) MCB CONTROLLERS
- 14) ELECTRICAL DISTRIBUTION - AC MPT transformer disconnects has bad seat on one phase. Jumper installed, SOC on disconnect - do not operate.
- 15) ELECTRICAL DISTRIBUTION - DC
- 16) EGC STATUS ___
171 RWNP (PPr)'W::"l IP1: AKin QTID INl EFFECT) 1 nvle ,-f DIAI ,.ill D CC- 7 1FVVOO9B has small nitron*.n lI.mk nn I P.*-FWX1
- 1 FW 00l B Ih WV al 'l1/4*1., .*[VPlI nn I %-
Ar* ,^,ir IC21 .doc
Scenario No. 3 Simulation Facility Braidwood Scenario No. 3 Operating Test No. 2002 Examiners: Applicant:
SRO RO BOP Initial Conditions: IC-18, 76% power MOL. Equil. Xe.
Turnover: Steady state with 1A CS Pump OOS for motor bearing replacement and ID CD/CB pump OOS for an alignment and vibration problem. Electric Operations requests Bwd Unit-i increase power to 1250 Mwe @ 3 MW/min to meet grid demand.
Event Malf. No. Event Event No. Type* Description Preload SI12A C RO 1A SI Pump fails to Auto start, can be manually started SIO1B BOP lB SI Pump fails to Auto start, cannot be manually started SRO 1 N BOP Ramp up turbine power to 1250 MWe at directed MW/min.
SRO R RO Raise reactor power using rods and/or dilution SRO 2 RX05, 0 I BOP Main Steam Header Pressure controller (PT-507) fails low 5 min ramp SRO 3 CV17, 0 I RO Volume Control Tank (VCT) level channel 1LT- 112 fails high SRO 4 RX21A I RO PT-455 Controlling Pressurizer Pressure channel fails high SRO 5 MSO4B, 100 C BOP 1MS018B, lB Steam Generator PORV fails open SRO 6 MRF RP61 M RO All MSIV's fail closed at power SRO BOP 7 MS03B/F M RO Pressure surge causes Main Steam Safety valves (2) to stick open, Loop 100 SRO lB BOP 8 FWOO9B C RO FRV-520 fails to close as required on FWI signal. Cannot be manually BOP closed.
9 TH03B M RO SGTL occurs on lB Steam Generator after Steam Generator has reached 600 gpm BOP dry out conditions.
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient Braidwood 2002 NRC Exam Scenario 02-3
SCENARIO OVERVIEW The Unit is at 76% power, MOL, equilibrium xenon. ID CD/CB pump is OOS for alignment and vibration problems. 1A CS Pump is OOS for a motor bearing replacement. Power is to be increased at direction of Electric Operations using iormal procedures. On-Line Risk is YELLOW because of the CS Pump OOS.
Following clearly observable plant response from the reactivity changes, the Main Steam Line pressure controller (PT 507) will fail low, resulting in decreased MFP speed and lowering main feedwater flow to the SGs. The crew should take manual control of MFP speed and adjust /increase MFW to the SGs. The Crew should match steam flow and feed flow and control MFP speed in manual.
After the secondary plant is stabilized, Volume Control Tank (VCT) Lever Controller (LT- 112) will fail high. This will result in diverting letdown flow from the VCT to the Holdup Tank (HUT). The failure of 1LT- 112 level channel will result in the loss of automatic level control and makeup to the VCT.
After actions have been taken to restore normal letdown flow, the controlling Pzr Pressure channel (PT-455) will fail high, causing a Pzr PORV (lRY-455A) and Pzr Spray valves to open, decreasing actual RCS pressure. The RO will diagnose the pressure malfunction from alarms, meter indications, and decreasing Pzr pressure. The RO must close the PORV or PORV block valve to stop the pressure decrease. Manual action will also be required to close the Pzr spray valves which will open due to the master pressure controller demand. The SRO will enter and direct actions of 1BwOP INST-2, Attachment B, "PRESSURIZER PRESSURE CHANNEL FAILURE", to select an operable controlling channel and restore automatic pressurizer pressure control, trip TS bistables, and identify TS Action requirements.
After actions have been completed for the failed Pzr Pressure channel, the lB SG PORV controller will cause the 1B SG PORV to open. RCS Tave will decrease causing control rod motion in the outward direction. The crew will investigate the cause of the temperature decrease and diagnose the inadvertent PORV opening. Emergency closure of the PORV will be available. The PORV may be isolated locally by closure of the manual upstream isolation valve, IMSO19B.
After the unit is stabilized following the open SG PORV, a failed capacitor in Instrument Inverter 111 will generate a spurious Main Steam Line Isolation signal (Bwd LER). All 4 MSIV's will automatically close at power, resulting in a Reactor Trip and Safety Injection. The Crew will enter and perform the immediate actions of 1BwEP-0, "REACTOR TRIP OR SAFETY INJECTION".
The resultant pressure increase following the spurious MSIV closure causes 2 Main Steam Line Safety valves on Loop 1B to open and stick open. The Operators will diagnose a fault on the lB Steam Line while performing the actions of 1BwEP-0 as a faulted steam generator and transition to lBwEP-2, "FAULTED STEAM GENERATOR ISOLATION",
and will take actions to isolate the lB Steam Generator. FRV-520 has failed to close following the Feedwater Isolation signal and the operators will have to take actions of step 4d RNO to manually close the upstream isolation valve, 1FW006B.
Comments:
Braidwood 2002 NRC Exam 2 Scenario 02-3
Once the faulted steam generator has been depressurized and dried out, the pressure delta P will cause a steam generator tube leak of 600gpm on the lB SG. The crew will diagnose this by decreasing RCS pressure and inventory. They must perform the actions of 1BwEP-3, "STEAM GENERATOR TUBE RUPTURE", and finally transition to 1BwCA-3.1, "SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED", when it is noted that the uptured SG pressure is less than 320psig. The Scenario ends with the establishment of RCS Cooldown in 1BwCA-3.1.
Critical Tasks
- 3. ECA-3.1-B Take necessary operator actions to control the RCS cooldown rate at the highest rate achievable but less than 100 degrees F per hour in all RCS cold legs.
SIMULATOR OPERATOR NOTES:
Simulator Setup:
IC-1 8, 76% power. Complete the 'ready for training' checklist. Hang YELLOW risk placard.
Take 1A CS pump OOS. Control switch to PULL OUT. Hang Tag Take ID CD/CD pump OOS. Control switch to PULL OUT. Hang Tag.
Take 1D CD/CB pump aux lube oil pump OOS. Control switch to PULL OUT. Hang Tag.
IOR ZLOlCB113D(1) OFF Open Light OFF
'OR ZLO1CB113D(2) OFF Close Light OFF Setup the following overrides/malfunctions for the IA CS OOS:
IMF CSO1A to fail 1A CS pump from starting MRF ED062A OPEN Breaker for 1CS007A MRF ED053M OPEN Breaker for 1CSO19A MRF ED053A OPEN Breaker for 1CSOO1A MRF ED053B OPEN Breaker for 1CS009A Setup the following overrides/malfunctions:
IMF FW22D to fail ID CD/CB pump from starting IMF S112A 1A SI pump fails to auto start, can be manually started IMF SI01B lB SI pump fails to auto start, cannot be manually started Comments:
Braidwood 2002 NRC Exam Scenario 02-3
Event 1 Power Increase - ramp power from 76% to 100%
As SM acknowledge ramp initiation As RP/HP/Chemistry acknowledge sample requirements for power change >150%in one hour Event 2 Main Steam Pressure Controller PT-507 Failure low SDG: RX22 IMF RX05, 0, 600sec Initiate malfunction after clearly observable reactivity changes/plant response from requested ramp and/or wi concurrence from lead examiner Acknowledge all info passed to SM, WEC, and maintenance Event 3 VCT Level Channel LT-112 Failure High SDG: CV3 IMF CV16, 100 Initiate malfunction after actions for PT-507 have been completed and with concurrence from lead examiner.
Acknowledge all info passed to SM, WEC, and maintenance Event 4 Pzr Pressure Channel PT-455 failure high (2500#)
IMF RX21A, 2500 Initiate malfunctions after actions are complete for LT- 112 failure and with concurrence of lead examiner.
Role Play as U-2 admin/extra NSO to accomplish bistable tripping.
Acknowledge all info passed as SM, WEC, and maintenance.
Perform the following to trip Pressurizer channel bistables:
On SDG RX10:
Open Protection Cabinet Door #1 RX020 OPEN Pzr Press Hi Trip PB455A CI-153 BS-l RX032 TRIP Pzr Press Lo Trip PB455C C1-153 BS-4 RX034 TRIP Pzr Lo Press SI PB455D CI-153 BS-3 RX035 TRIP PzrPress P-11 PB455B CI-153 BS-2 RX033 TRIP On SDG RX4:
OTDT Trip TB41IC CI-124 BS-3 RX013 TRIP OTDTRunback TB41ID CI-124 BS-4 RX135 Protection Cab #1 Close Door RX020 CLOSE Comments:
Braidwood 2002 NRC Exam 4 Scenario 02-3
Event 5 1MS018B, 1B Steam Generator PORV fails open SDG MS4 Initiate after actions are completed for the PT-455 failure and with concurrence of lead examiner.
IMF MS04B, 100, no ramp If dispatched to controller box in AEER, report no obvious problems. If sent to locally close IMS019B, wait 5 minutes, call CR for first check, and close 1MSO19B Acknowledge all info passed to SM, WEC, and maintenance Event 6-8 ARE SIMULTANEOUS EVENTS.
FRV-520 fails to close on FWI signal, MSIV auto closure occurs (all 4 MSIVs), Steam Line Fault outside containment (Loop 1B)
Initiate events after actions are completed for S/G PORV failure and with concurrence of lead examiner.
IOR ZLO1SLFW520, OFF FWI Status light to OFF IOR ZLO1FW5202, ON FRV 520 Open light to ON IMF FW09B, As Is - FRV 520 failure MRF RP61, IN - Closure of all MSIVs IMF MS03B and MS03F, 100 MS Safeties (2) to OPEN Insert malfunctions after actions are completed for PORV failure and with concurrence of lead examiner.
Acknowledge all info passed to SM, WEC, and maintenance Event 9 Steam Generator Tube Rupture, 1B SG, after 1BwEP-2 transition and SG dryout is reached SDG TH6 IMF TH03B, 600gpm, lminute ramp Initiate malfunction after lB SG Wide Range level is <10% and transition has occurred out of 1BwEP-2, and with concurrence of lead examiner Acknowledge all info passed to SM, WEC, and maintenance Comments:
Braidwood 2002 NRC Exam 5 Scenario 02-3
Scenario No: 02-3 Event No. 1 Event
Description:
Raise turbine load and reactor power Time Position I Applicant's Actions or Behavior CUE Turnover information includes request from Electric Operations for an increase in Unit 1 MW to full load (1260 MW) to begin ASAP at 3 MWe/minute.
US Implement actions of 1BwGP 100-3 step 61.
- Initiate load swing instruction sheet (lBwGP 100-4T2 Boration Dilution Boundary Calculation).
o Contact chemistry and Health Physics for load change > 15% in one hr.
- Inform SM of plant Status, and Elec Ops of ramp start.
CREW Review applicable Precautions, Limitations and Actions of 1BwGP 100-3 RO Verify rod position and boron concentration.
Perform reactivity manipulation calculation to determine amount of RCS dilution and expected rod outward movement to maintain Delta I within the limits of BwCB- 1 Fig. 19.
Determine required dilution volume by:
"o Effects of previously performed dilutions.
"o Braidwood Boration Dilution Tables.
Initiate Dilution in accordance with BwOP CV-5:
"* Determine required Primary Water flow rate.
"* Set 1FK- 111 Pw/Total Flow Control to desired dilution rate.
"* Set IFY-0111 Primary Water Control Preset Counter to desired volume.
"* Place MAKE-UP CONT Switch to STOP position.
"* Set MU MODE SELECT Switch to ALT DIL position.
"* Place MAKE-UP CONT Switch to START.
o Verify proper operation of valves (1CV I 1A throttles open, PW flow indicated on recorder).
OR Batch Addition:
- OPEN 1CV110B.
- OPEN 1CV11IA.
When desired amount of Primary Water added:
"* CLOSE 1CV111A.
"* CLOSE 1CVIIOB.
Comments:
Braidwood 2002 NRC Exam 6 Scenario 02-3
Scenario No: 02-3 Event No. 1 Event
Description:
Raise turbine load and reactor power Time Position Applicant's Actions or Behavior BOP Initiate turbine load increase:
"* VERIFY the DEHC IMP IN, SPEED IN, and MW IN half of the pushbuttons are illuminated.
"* DEPRESS the LOAD RATE MW/MIN pushbutton.
"* ENTER the desired load rate (< 3).
"* DEPRESS the ENTER pushbutton.
"* DEPRESS the REF pushbutton.
"* ENTER the desired MW on the REFERENCE DEMAND Window using the numbered pushbuttons (1120).
"* DEPRESS the ENTER pushbutton.
"* DEPRESS the GO pushbutton when directed by the US/RO.
"* VERIFY load begins to increase.
+/- t RO Monitor power increase:
"* Monitor Reactor power, Tave, and Delta I.
"* Verify control rods automatically move to maintain Tave within + 1.0 degree F of Tref.
If Diluting:
a Monitor VCT level.
o Verify RCS boron concentration decreasing.
"* Monitor PW/Total counter.
"* Verify dilution auto stops at preset value.
"* Return Reactor Makeup system to blended flow at current boron concentration.
NOTE: Following clearly observable plant response from the reactivity changes, and with concurrence of the lead examiner, event 2 may be entered.
Comments:
Braidwood 2002 NRC Exam 7 Scenario 02-3
Scenario No: 02-3 Event No. 2 Event
Description:
Main Steam Header Pressure Controller (1 PT-507) Fails low over 5 minutes.
Time Position [ Applicant's Actions or Behavior CUE Annunciators:
1-18-B7 MSR SHELL DRAIN TANK LEVEL HIGH LOW 1-18-A7 MSR SHELL DRAIN TANK EMER DRAIN VALVE OPEN 1-15-A/B/C/D4 SG 1A!B/C/D FLOW MISMATCH FW FLOW LOW I-15-A/B/C/D9 SG IA/B/C/D LEVEL DEVIATION HIGH LOW Indications:
Feed flow indication decreasing Feed Pumps Speed Decreasing SG levels decreasing Feed Reg Valves Position Demand Increasing 1PI-507 Decreasing BOP/US Diagnose/Report decreasing feed pump speed and SG levels as a result of 1PT-507 failing low.
RO Monitor Reactor power and primary parameters.
Refer to BwARs as directed by US.
Assist BOP as directed/necessary.
US Direct actions stabilize the plant and restore normal feedwater conditions:
- Place Master feed pump speed control in Manual and Increase feed pumps speed to increase feed flow.
o Direct flagging of Master Feed pump speed controller, 1PI-507, and Steam Dumps Steam Pressure.
o Review effect offailure with crew with regard to Steam Dumps.
o Inform SM of plant status, and direct WEC to write AR, CR, and get maintenance involved.
BOP Perform actions as directed by US:
"* Place Master feed pump speed control in Manual and Increase feed pumps speed to increase feed flow.
"* Control feed flow to recover SG levels in a controlled manner without over cooling the RCS.
"* Stabilize feed flow/ pump speed to maintain SG levels at -60%.
NOTE: After crew stablilizes SG levels, initiate event 3 Comments:
Braidwood 2002 NRC Exam 8 Scenario 02-3
Scenario No: 02-3 Event No. 3 Event
Description:
Volume Control Tank (VCT) level channel 1LT- 112 fails high Time [Position Applicant's Actions or Behavior CUE Annunciators:
1-9-A2 VCT LEVEL HIGH 1LT 112 CVT Level indication full scale high 1 CVI 12A VCT Inlet valve diverting to the HUT RO/US Identify/report failure of 1LT-CV 112 RO Refer to 1BwAR 1-9-A2 for operator actions Place 1LCV CV-1 12A to the VCT position to restore letdown flow to the VCT via the control switch on IPM05J or using manual on the level controller.
BOP Assist RO as directed by US / requested by RO
"* Investigate BwARs
"* Make phone notifications as directed by US/RO
"* Provide appropriate peer checks as requested by RO Control turbine loading as directed by US CREW Identify loss of auto makeup capabilities to the VCT Identify loss of auto suction swapover to the RWST on low VCT level NOTE: When actions have been completed for the failed VCT level channel, and with the lead examiners concurrence event 4 is entered Comments:
Braidwood 2002 NRC Exam 9 Scenario 02-3
Scenario No: 02-3 Event No. 4 Event
Description:
PT-455 Controlling Pressurizer Pressure Channel fails high Time Position Applicant's Actions or Behavior CUE Annunciators:
1-12-B2 PZR PORV OR SAF VLV OPEN 1-12-C6 PZR PORV DSCH TEMP HIGH 1-12-D2 PZR PRESS CONT DEV HIGH Porv 1RY455A OPEN Position Indicating Light Lit.
IPI-455 Indicating 2500 psig.
Decreasing PZR pressure RO/US Diagnose/Announce PZR Pressure Transmitter failure, 1RY455A and Pzr sprays open:
"* Verify PZR Pressure is decreasing, Identify open PORV and spray valves
"* Close 1RY455A
"* Manually Close spray valves.
US Implement 1BwOA INST-2 "OPERATION WITH A FAILED CHANNEL", ATTACHMENT B, "PZR PRESSURE CHANNEL FAILURE", and direct actions:
"* Get acknowledgements from RO and BOP.
"* Inform SM of plant status, evaluate for GSEP.
"* Direct WEC to write AR, CR, and get maintenance involved.
& Briefs Unit 1 NSO and Unit 2 Admin NSO on Bistable tripping.
Comments:
Braidwood 2002 NRC Exam 10 Scenario 02-3
Scenario No: 02-3 Event No. 4 Event
Description:
PT-455 Controlling Pressurizer Pressure Channel fails high Time Position Applicant's Actions or Behavior RO Perform actions of 1BwOA INST-2 as directed:
""Determine PZR Pressure NOT NORMAL, and take Manual Control to restore Pressure.
"* Determine Operable Channel NOT selected, Place the Master PZR Pressure Controller in Manual, Control PZR Pressure, and Select an Operable Channel.
"* Check PZR Porvs, Spray Valves and Heaters:
- PORVS Closed. If NOT, and PZR Pressure < 2315 psig, manually close PORV (1RY455A).
- PZR Spray Valves NORMAL. If not, then manually control.
- PZR Heaters NORMAL.
"* Check PZR Pressure Control In Auto:
"*1RY455 returned to Auto
" 1RY456 in Auto.
"*Sprays in Auto (after operable channel selected for control).
" Master PZR Pressure Controller in Auto.
"* Select Operable Channels to Recorders:
- PZR Pressure.
o Loop DT.
"* Coordinates Bistable Tripping:
- Places colored dots on bistable, indications, and annunciators.
- Maintains communications with NSO tripping bistables.
RO Ensures the following Bistables are tripped:
"* PB455A
"* PB455C
"* PB455D
"* PB455B
"* TB411C
"* TB411D Checks PZR Pressure > 1930 psig and P-II permissive is NOT Lit (Bypass Permissive 3.3).
US Refers to Tech Specs, and determines the following:
- 3.3.1. Conditions E and K apply - Trip channel within 6 hrs.
- 3.3.2 Condition D applies - Trip channel within 6 hrs.
- 3.3.4 Condition A applies - Restore within 30 days
- 3.4.1 Condition A applies - Restore DNB within 2 hrs.
Comments:
Braidwood 2002 NRC Exam I1I Scenario 02-3
Scenario No: 02-3 Event No. 4 Event
Description:
PT-455 Controlling Pressurizer Pressure Channel fails high Time Position Applicant's Actions or Behavior BOP Perform actions as directed:
"o Assist Unit NSO in monitoring panels and parameters.
"o Investigate BwARs.
"o Make phone calls as directed to WEC and maintenance.
"o Control load ramp NOTE: after completion of all actions and TS determination for the Pzr Instrument failure, and with the concurrence of the lead examiner, the next event may be initiated Comments:
Braidwood 2002 NRC Exam 12 Scenario 02-3
Scenario No: 02-3 Event No. 5 Event
Description:
lB Steam Generator PORV fails open, 1MS018B Time Position Applicant's Actions or Behavior CUE Indications:
RCS Tave decreasing Control rods stepping out Reactor Power increasing Reactor power/ turbine power mismatch increasing Red Porv OPEN position indication light lit.
LVDT meter indication increasing above 0%.
BOP Diagnoses 1B SG PORV OPEN, determines SG pressure is below setpoint (1115 psig) and reports failure to US.
Performs actions directed by US:
"* Take MANUAL control at the M/A Station and attempt to reduce demand.
"* Report MANUAL control has no effect to US.
"* PLACE EMERGENCY CLOSE switch to CLOSE.
o Report/Acknowledge SG lB PORV TROUBLE annunciator (1-15-B 10) as expected alarm.
"o Dispatch operator to AEER to PORV controller box.
"o Dispatch operator to locally isolate 1MS018B by closing 1MS019B.
- Report status to US.
US Diagnose/Acknowledge failure of lB SG PORV OPEN and direct actions:
o Determine SG pressure < PORV setpoint.
"* Attempt MANUAL Control via M/A station to CLOSE PORV.
"* PLACE EMERGENCY CLOSE switch to CLOSE.
o Dispatch operator to isolate PORV by closing 1MS019B.
"* Inform SM of plant status.
"* Order WEC to generate AR, CR, and get maintenance involved for repairs.
"* Refer to Tech Spec 3.7.4. (30 days to restore operability).
o May refer to Tech Spec 3.6.3. (not applicable, porv is in its isolation positon.)
Comments:
Braidwood 2002 NRC Exam 13 Scenario 02-3
Scenario No: 02-3 Event No. 5 Event
Description:
1B Steam Generator PORV fails open, 1MSO18B Time Position Applicant's Actions or Behavior RO Diagnose/Acknowledge failure of 1B SG PORV OPEN.
Monitor Reactor and Primary parameters for effects and expected response:
"* Reactor Power
"* Tave, Delta I and rod motion.
"* Assist as directed by US.
"* Investigate BwARs.
NOTE: After PORV is closed/isolated, TS actions have been identified, and with concurrence with the lead examiner the next event may be initiated.
Comments:
Braidwood 2002 NRC Exam 14 Scenario 02-3
Scenario No: 02-3 Event No. 6 - 9 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI, faulted-ruptured SG Time Position I Applicant's Actions or Behavior CUE Annunciators:
MSIV Closed Steam Flows all 4 Steam Generators decreasing All MSIV position indicators closing/closed CREW Identify closure of MSIVs Initiate a manual reactor trip / respond to an automatic reactor trip US Implement and direct actions of lBwEP-0 "Reactor Trip or Safety Injection" RO Perform Immediate actions of lBwEP-0:
Verify reactor trip
"* Rod bottom lights lit
"* Reactor trip and bypass breakers open
"* Neutron flux decreasing Check SI Status
"* Determines that Pzr pressure is decreasing abnormally
"* Determines Pzr level can not be maintained >4% level
"* Announces automatic SI actuation has occurred
"* Manually actuates SI BOP Perform Immediate actions of lBwEP-0:
Verify Turbine trip
"* All throttle valves closed
"* All governor valves closed Verify 4KV ESF Busses energized
"* Bus 141 bus alive light lit
"* Bus 142 bus alive light lit Comments:
Braidwood 2002 NRC Exam 15 Scenario 02-3
Scenario No: 02-3 Event No. 6- 9 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI, faulted-ruptured SG Time Position Applicant's Actions or Behavior BOP Performs subsequent automatic actions of lBwEP-0, as directed:
Verify FW Isolation:
- FW pumps TRIPPED.
- FW Isolation monitor lights LIT.
- FW pumps discharge valves (1FW002A, B, and C) CLOSED.
- FW Isolation monitor lights NOT ALL LIT
"* Identify failure of FRV-520 to close
"* Attempt manual closure of 1FRV-520
"* Manually close upstream isolation valve 1FW-006B Verify RCFCs Running in Accident Mode:
- Group 2 RCFC Accident Mode status lights LIT.
Verify Cnmt Isolations:
- Cnmt Isolation Phase A:
- Group 3 CNMT Isol monitor lights LIT.
- Cnmt Ventilation Isolation:
- Group 6 CNMT Vent Isol monitor lights LIT.
Verify AF System:
- AF Pumps BOTH RUNNING.
oAF Isol valves (1AFO13A-H) OPEN oAF Flow Control valves (1AF005A-H) THROTTLED.
Verify CC Pumps BOTH RUNNING.
Verify SX Pumps BOTH RUNNING.
Verify all MSIVs are Closed Determine CS DOES NOT need to be actuated:
- CNMT Pressure has remained < 20 psig.
Verify Total AF Flow:
oAF Flow > 500 gpm.
- Control feed flow to maintain narrow range level BETWEEN 10% and 50%.
Comments:
Braidwood 2002 NRC Exam 16 Scenario 02-3
Scenario No: 02-3 Event No. 6- 9 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI, faulted-ruptured SG Time Position Applicant's Actions or Behavior RO Performs subsequent automatic actions of 1BwEP-0, as directed:
o Verify ECCS Pumps Running:
o CV Pumps BOTH RUNNING CT: SI Pumps:
E-0--J.
"o RH Pumps BOTH RUNNING "o Reports SI pump failure to US.
"o Dispatches operators to investigate 1B SI pump and breaker.
RO Performs subsequent actions of lBwEP-0, as directed:
Verify ECCS Valve Alignment:
- Group 2 Cold Leg Injection monitor lights LIT.
Verify ECCS Flow:
200 gpm.
o IF RCS Pressure < 325 psig, THEN verify RH Pump Discharge Flow (1FI-618/619) > 1000 gpm.
Check at Least One PZR PORV Relief Path Available:
oPORV Isol valves (1RY8000A and 1RY8000B) AT LEAST ONE ENERGIZED.
- PORV Relief Path AT LEAST ONE AVAILABLE:
"* PORV inAUTO.
"* Associated isol valve OPEN.
BOP Performs subsequent actions of 1BwEP-0, as directed:
Verify Generator Trip:
- Main Transformer output breakers (OCB 1-8 and OCB7-8) OPEN.
- PMG Output Breaker OPEN.
Verify DGs Running:
- DGs BOTH RUNNING.
- DGs BOTH SX Cooling Valves (1SX169A and 1SX169B) OPEN.
- Dispatch operator to LOCALLY check operation.
Comments:
Braidwood 2002 NRC Exam 17 Scenario 02-3
Scenario No: 02-3 Event No. 6 - 9 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI, faulted-ruptured SG Time Position Applicant's Actions or Behavior BOP Verify Control Room Ventilation Aligned for Emergency Operation:
" Checks RM- 11, Grid 2, OPR31J-OPR34J < high alarm setpoint.
"*Checks operating VC train equipment running:
"* Supply fan
"* Return fan
"* M/U fan
"* Chilled Water pump
"* MCR Chiller
"*Checks Operating VC train dampers aligned:
"* M/U fan outlet damper (OVC024Y/OVC08Y) NOT FULLY CLOSED.
"* VC train M/U Filter Light Lit
- Checks Operating VC Train Charcoal Absorber Aligned:
"* Bypass damper closed (OVC43Y/OVC44Y)
"* Inlet damper Open (OVC21Y/OVC05Y)
"* Outlet Damper Open (OVC22Y/OVC06Y) eControl Room pressure (MCR/TB DP, OPDI-VC038) > +0.125" H20.
BOP Verify Aux Bldg Ventilation Aligned for Emergency Operation:
- Inaccessible Filter Plenums - Only TWO Aligned with Charcoal Absorbers On Line:
"o Plenum A:
"o Fan OVA03CA Running with Flow Control Damper (OVA022Y) Open and Byp Isol Damper (OVA020Y) Closed.
"o Fan OVA03CB Running with Flow Control Damper (OVA023Y) Open and Byp Isol Damper (0VA436Y) Closed.
"o Plenum B:
"o Fan OVA03CC Running with Flow Control Damper (OVA024Y) Open and Byp Isol Damper (OVA021 Y) Closed.
"o Fan OVA03CD Running with Flow Control Damper (OVA025Y) Open and Byp Isol Damper (0VA437Y) Closed.
"o Plenum C:
"o Fan OVA03CE Running with Flow Control Damper (OVA067Y) Open and Byp Isol Damper (OVA052Y) Closed.
"o Fan OVA03CF Running with Flow Control Damper (OVA072Y) Open and Byp Isol Damper (0VA438Y) Closed.
Comments:
Braidwood 2002 NRC Exam 18 Scenario 02-3
Scenario No: 02-3 Event No. 6- 9 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI, faulted-ruptured SG Time Position Applicant's Actions or Behavior BOP Verify FHB Ventilation Aligned for Emergency Operation:
- FHB Charcoal Absorbers -One Train Aligned:
"o Train A:
"* Fan 0VA04CA Running
"* 0VA060Y Charcoal Absorber Inlet Isol Damper- Open.
"* 0VA057Y Filter Flow Control Damper - Open.
"* 0VA051Y Charcoal Absorber Bypass Isolation Damper- Closed.
" Train B:
"* Fan 0VA04CB Running
"* 0VA055Y Charcoal Absorber Inlet Isol Damper - Open.
"* 0VA062Y Filter Flow Control Damper - Open.
"* 0VA435Y Charcoal Absorber Bypass Isolation Damper - Closed.
RO Check PZR Spray Valves and Porvs:
"* Spray valves (1RY455B and 1RY455C) Closed.
"* Porvs: 1RY455A and 1RY456 Closed Attempt to Maintain RCS Temperature Control:
o Maintains> 500 gpm AF flow until at least one SG is 10% (31% Adverse).
Check RCP Status:
"* Determines RCPs RUNNING.
"* Check If RCPS should be Stopped:
- RCS Pressure NOT LESS THAN 1425 psig.
Check Secondary Pressure Boundaries Intact:
- Identify the lB Steam Generator pressure decreasing in a uncontrolled manner US Diagnoses/Announces Faulted Steam Generator, Transitions to 1BwEP-2, "FAULTED STEAM GENERATOR ISOLATION", and directs actions:
"* Gets acknowledgement from RO and BOP.
"* Informs SM of plant status, and evaluates for GSEP.
Comments:
Braidwood 2002 NRC Exam 19 Scenario 02-3
Scenario No: 02-3 Event No. 6,7,8 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI Time Position Applicant's Actions or Behavior BOP Acknowledge transition to 1BwEP-2 and performs actions:
Re-verify all MSIV's closed Check if any Steam Generator secondary pressure boundary is intact:
- Identify 1A, 1C, and 1D steam generator pressures appear stable or increasing Identify lB Steam Generator as faulted 0 Pressure decreasing in an uncontrolled manner and/or completely depressurized BOP Isolate Faulted SG
[CT] 0 1AF013B Closed E-2--A 0 1AFO 13F Closed Check FW to faulted SG isolated
1FW009B Closed I1FW034B Closed IIFW035B Closed I1FW039B Closed 1FW520 NOT Closed I1FW006B closed
- Verify SG PORV on faulted SG closed IMS018B Verify SG blowdown isolation valves on faulted SG - closed
- 1SDO02E
BOP Monitor AF Pump Suction Pressure
- No radiation monitors in alarm indicating steam generator tube rupture Comments:
Braidwood 2002 NRC Exam 20 Scenario 02-3
Scenario No: 02-3 Event No. 6,7,8 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI Time Position Applicant's Actions or Behavior US Diagnoses/Announces transition to 1BwEP-1, "LOSS OF REACTOR OR SECONDARY COOLANT", and directs actions:
"* Gets acknowledgement from RO and BOP.
"* Informs SM of plant status, and evaluates for GSEP.
"* Directs STA to continue monitoring Status Trees.
NOTE: Upon transition to 1BwEP-1 and after 1B SG Wide Range level reaches <10% level, the SGTR on 1B Steam Generator will occur resulting in a faulted / ruptured Steam Generator via the 2 open MS Safety valves on the lB loop CUE Increasing Radiation / Radiation alarms on lB MS Rad Monitors Indicated pressure increase in lB Steam Generator Indicated steam flow from lB Steam Generator Decreasing RCS Pressure and level CREW e Identify increased radiation sensed on the 1B Steam Generator MS Line
"* Identify decreasing RCS pressure and level
"* Identify indicated pressure increase and steam flow on the 1B Steam Generator US Diagnose by use of board indications and/or:
"* Operator Action Summary page of 1BwEP-ifor abnormal secondary radiation
"* Step 4 of 1BwEP-1 for abnormal secondary radiation That 1B SG is faulted and ruptured and make the transition to 1BwEP-3 "STEAM GENERATOR TUBE RUPTURE"
"* Gets acknowledgement from RO and BOP.
"* Informs SM of plant status, and to evaluate for GSEP.
RO Performs actions of 1BwEP-3, "SGTR" as directed:
- Check If RCPS should be Stopped if not previously stopped
"* ECCS Flow > 100 gpm on IFI-917 or SI pump Flow > 200 gpm on 1FI-922.
"* RCS Pressure NOT LESS THAN 1425 psig.
Comments:
Braidwood 2002 NRC Exam 21 Scenario 02-3
Scenario No: 02-3 Event No. 6,7,8 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI Time Position Applicant's Actions or Behavior BOP Performs actions of 1BwEP-3, "SGTR", as directed:
Identify Ruptured SG fom any of the following means:
e Unexpected level rise in lB SG.
eMS Line Rad 1B MSL/ MSIV room NOT NORMAL FOR PLANT CONDITIONS.
- High Activity from 1B SG sample.
e Indicated steam flow and pressure on faulted / isolated steam generator BOP Isolate Flow from lB SG:
"* Verify 1B SG Blowdown isolation valves (ISDO02E and 1SD002F) CLOSED.
"* Verify lB MSIV and Bypass valves CLOSED Determine PORVs on intact Steam Generators are available (1MS018A, 1MS018C, 1MS018D)
US/BOP Identify ruptured Steam Generator level is <10% Narrow Range DO NOT initiate AFW flow to ruptured / faulted Steam Generator Verify AF Isol Valves remain CLOSED
"* 1AF013B
"* IAF013F US Evaluate Ruptured Steam Generator pressure less than 320 psig and transition to 1BwCA-3. 1, "SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED"
"* Gets acknowledgement from RO and BOP.
"* Informs SM of plant status, and to evaluate for GSEP.
RO/BOP: Perform actions of 1BwCA-3.1 as directed:
- Reset SI o Reset Cnmt Isolations (Previously performed)
"* Verify all AC buses Energized
"* Check if CS should be stopped (CS is not initiated)
BOP Perform actions as directed:
"* Check ruptured SG (1B) Narrow Range level< 10%.
"* DOES NOT Initiate feed to lB SG Level.
"* Stop RH pumps if RCS pressure >325 psig, stable or increasing Comments:
Braidwood 2002 NRC Exam 22 Scenario 02-3
Scenario No: 02-3 Event No. 6,7,8 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI Time Position Applicant's Actions or Behavior BOP Perform subsequent actions as directed to initiate plant status evaluation:
"* Check Aux Bldg Rad Trends for both Unit 1 and Unit 2 on RM-Il or HMI:
e Vent Stack effluent 1PR28J, 1PR3OJ, 2PR28J, 2PR30J.
oECCS Pump Cubicles- IPR13J through 1PR18J.
- Grid 4 Aux Bldg Area.
"* Place Hydrogen Monitors in service per BwOP PS-9, POST LOCA CNMT H2 MONITORING SYSTEM OPERATION.
US Perform actions of 1BwCA-3.1:
"* Call Chemistry for samples:
- RCS Activity
- Cnmt Atmosphere
"* Evaluate equipment needed in CC and RH systems to assist in plant recovery.
US Get Concurrence from SM that the Hydrogen Recombiners DO NOT need to be run.
Note: Crew will decide that they have accomplished the Isolation of the Faulted ID SG in accordance with 1BwEP-2, "FAULTED SG ISOLATION" BOP Performs actions as directed to continue in 1BwCA-3.1:
"* Controls Intact SG levels between 10% and 50%. (23% and 5 0 %)
"* Verifies NO INTACT SG level INCREASING IN AN UNCONTROLLED MANNER.
RO Performs actions as directed to continue in 1BwCA-3. 1:
e Determines Cooldown in RCS Cold Legs is NOT LESS THAN 100 Degrees F in any 1 hr period.
CT: o DOES NOT Initiate any further Operator Controlled Cooldown of the RCS if the Cooldown rate in the CA3.1- RCS Cold Legs is > 100 degrees F in any 1 hr.
B.
BOP Check if Subcooled Recovery is appropriate:
"* Determines RWST level is > 67%.
"* Determines 1B SG level < 93%
RO/US Checks RCS Subcooling:
e Determines RCS Subcooling is acceptable by Iconic or Attachment A.
Comments:
Braidwood 2002 NRC Exam 23 Scenario 02-3
Scenario No: 02-3 Event No. 6,7,8 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI Time Position Applicant's Actions or Behavior Scenario is complete at this point or at the Chief examiners discretion I 1.
T I I I t -I-F -I-i f t +/-
r 1 1
1 i i t i f- i Comments:
Braidwood 2002 NRC Exam 24 Scenario 02-3
SHIFT MANAGER TURNOVER Weekday, Today, 2001 ONCOMING SHIFT 2 i ____ -
'UNIT 1 STATUU UNIT 0 & 1 MAJOR QOS's MODE ............ 1 1A Containment Spray Rx Pwr ............ 77 Pump Generator MWe ..... 942 Max Load/Power .... 100% ID CD/CB Pump Min Load/Power .... 700 MW Max Ramp Rate ..... 5 MW/Min Desired Delta I ..... Target On-Line Risk ....... Yellow Boron @ .......... 926 Control Bank ....... D(a) 169
.3.b.b c(onfltlon A hour 36 of 7 day LCOAR a as. I-------- -
UNI I U I IN' F QU t.ýj "liHIT n j i=inPmr-M(
I I A CS Pump motor bearing replacement. Unit 1 load increase to 1250 Mwe to meet load demand @ 3 MW/min per electric operations Alignment on 1D CD/CB Pump. Est. RTS by end of
,hift today Focus Areas:
U Verification Practices U
Command and Control Standard for Execution of Critical Steps THINK CONFIGURATION CONTROL and SAFETY!!!
Zo f1rULL AU
- I IVI *UNtMLIG I IC18.doc
SHIFT MANAGER TURNOVER S fl n Sn F- - -. - - - - - -
iNtl !bIA1U> UNIT 2 MAJOR OOS's
-I
,lODE ............ 1 Rx Pwr ............ 97.6 Generator MWe ..... 1197 Max Load/Power .... 97.6 impulse pressure Min Load/Power .... 700 Max Ramp Rate ..... 5 mw/min Desired Delta I ..... Target On-Line Risk ....... Green Boron @ .......... 1037 Control Bank ....... D@210 ICOAR ENTRIES PREVIOUS 48 HRS UNIT 2 MAJOR SURVEI F LLANCES. . ...
"icoar num" "Affected-Equipment" UNIT 2 IN PROGRESS UNIT 2 PENDING Make sure that equipment such as ladders, fans, hoses, electrical cords either have tags on them, are put away, or notify SM so they can help get responsible persons out.
Safety: Electrical: SH-AA-1 31 Inspecting & Testing Extension Cords and Generators Dose INFO: Dose goal for day 10 mr SCHEDULED ACTIVITY CONFLICT IC18.doc
SHIFT MANAGER TURNOVER T-mod Ul Tm B RVLIS. Jumper Installed on 4C U-1 MPT Disconnect.
1 FW009A T-Mod for Hyd Pp Press Sw I PS-FW1 62. T-mod for drain on 1 B AF casing. Tmod for no disc in 2CC9502B installed Daily Orders / Special Op Orders Daily Manning Schedule See sheet for restricted duty personnel and overtime restrictions Oncoming STA Fire Chief Control Room Rounds (GSEP / LER / DVR / ENS)
Material TS Conditioning SFP High Level alarm did not alarm during calibration RWP's / Releases / Precautions / ALARA Infrequent Evolution Activities Lesson learned files L:\shared\opex then ctrl F to search SPSO / Division LID Alternate BPO Outside # 815-727-5902/5903 Tie # 8-565-5902/5903
- --- U it 1 Commnents Unit Common~ Comments Battery 112 cell 32 has floating material in electrolyte, eval'd OK U1 FC Cleanup SFP D.O. OOS prevents filling U-I tanks normally, but BwOP DO-6 U2 FC Cleanup OFFLINE (leak) can be used to fill tanks. T-MOD is installed allowing U-I boiler FC Cooling Ul ops. 50K DO Tank empty IAF006A is leaking by from CST. 125K DO Tank and FRAC Tks Certified Aux Steam U-1 ES -->U1 HDT U-0 CC Hx Ul U-0 CC Pump Bus 141 U1 Aux boiler Wet lay-up U2 Aux boiler Wet lay-up SAC / Dryer U1/U0 MUDs U-1 CST CW Makeup Running OA/OB CW Blowdown On
,Lake Level 5.8' Unit 2 Comments General Commein-ts 2AF017A leaking by .3 gpm, AR 990116738 Conference Call Phone Number- 1-800-232-1234 Teleconference S/G sampling lines/valves at HRSS are not correct. Do not folder ID #=472664085 hang OOS on any 2PS181 valves till further notice. Meeting Place 630-663-7120 +code 2PS229A still blows fuse 2PA32J Ckt 9 Duty Team is located @ SITE APPS, NRC Duty list in book CV seal leakage: Substation construction (John Strle) Cell phone 815-351-8472 2A Running 200cc/min shutdown about 6 drops/min 2B Running -12 dpm; S/D- none Caution Cards Abnormal Positioned Components CC-NUM _EPN_ C-(CNU-M EPN Abnormalfositon zIVI bI---'It--I I UK-NUVI-E Shift 1 To 2 Time Now Date Today Offgoing Oncoming IC18.doc
SHIFT MANAGER TURNOVER
.OPERATORS CONCERN LIST tl/-K 'IJv 1 U~
IVerify PZR PORV's Open at Setpoint or Open PZR PORV - Spurious SI Concern I97-159 2B CV Pump Monitor seal leakage shiftly - Notify System Engineering if > 0.5 gpm 98-049 UNIT 0 CONTROL ROOM ANNUNCIATORsA I IT it tAnnunciao A rnitor Desciipion *6b nAR#AARD UNIT 1 CONTROL ROOM ANNUNCIATORS LITStts UNIT 2. CONTROL ROOM ANNUNCIATORS LIT Concerns and/or Pending OP-AA-101-301 Evaluations EP' Unit I Resolution IC18.doc
BwAP 335-1 T6 Revision 8 Information Use UNIT 1 NSO TURNOVER Weekday, Today, Oncomina Shift 2 Containment Spray Pump 1A motor bearing replacement Unit 1 load increase to 1250 Mwe per electric operations at 3 MW/min Alignment of 1D CD/CB Pump LONG TERM4 ADMINISTRATIVE Temporary procedures Temporary alterations New caution cards Unit logbook Unit routine BDPS Icoar in mode 3.
Aux. Electric room access Daily orders Control board walk down LCO/TLCO RETS DEQUIP.AAR 3.6.6 1lA CS Pump IC 1.doc
BwAP 335-1T6 Revision 8 Information Use TUR8NOVER ITEMS NSO SHIETLY/DAILY SURVEILLANCE
-) SSPS CHANNELS/BISTABLES B train SSPS logic ground to chassis ground had higher than expected readings during SSPS, AR written.
- 3) SYS - SAFEGUARDS
- 4) SYS - PRIMARY 1. CC to spent fuel pool hx is at 2800 gpm.
- 5) SYS - BALANCE OF PLANT Spent fuel pool cooling now on Unit 1.
- 6) ALARMS-SER/ANNUNCIATOR
- 7) ALARMS - PROCESS/RM-1 1
- 8) ALARMS - FP/OTHERS
- 9) CHEMISTRY Max flow through condensate polishers at full power is -2000 gpm without I causing a low npsh alarm. This is only a guideline and not an absolute value.
- 10) RADIATION PRECAUTIONS
- 11) NUCLEAR INSTRUMENTATION
- 12) MCB INSTRUMENTATION
- 13) MCB CONTROLLERS
- 14) ELECTRICAL DISTRIBUTION - AC MPT transformer disconnects has bad seat on one phase. Jumper installed, SOC on disconnect - do not operate.
- 15) ELECTRICAL DISTRIBUTION - DC
- 16) EGC STATUS
- 17) BWOP_ (PROCEDURE AND STEP IN
- -ECT)
C~OMMENTS 15 gals PW will raise RCS Temps .1 F 1FW009B has small nitrogen leak on 1PS-FW1 65, AR written.
IC18.doc
1BwOS NR-1 Revision 11 Reference Use UNIT ONE POWER HISTORY HOURLY SURVEILLANCE DATA SHEET DATE FOR WHICH THIS SURVEILLANCE IS BEING PERFORMED: TODAY TIME AVG NUCLEAR TIME AVG NUCLEAR POWER OUTPUT POWER OUTPUT IDEAL ACTUAL IDEAL ACTUAL 0100 01001 76.1 %RTP 1300 "%RTP 0200 -02.00-.- 76.1 %-RTP 1400 .%-RTP 0300 0300. 76.1 %RTP 1500 .%RTP 0400 0400 76.1 %RTP 1600 %RTP 0500 0500 76.1 %RTP 1700 %RTP 0600 0600 76.1 %RTP 1800 %RTP 0700 0700 76.1 %RTP 1900* %RTP 0800 %-RTP 2000 %RTP 0900 %RTP 2100 %RTP 1000 %RTP 2200 %RTP 1100 %RTP 2300 %-RTP 1200 .%-RTP 2400 %RTP TOTAL POWER FOR THE DAY: ,(Sum of each recorded average Nuclear.Power Output)
TOTAL EFPH FOR THE DAY: (Total Power for the day multiplied by 0.01)
PREVIOUS CUMULATIVE EFPH: 5750.177 (Total EFPH to date from previous last run of this surveillance)
EFPH ADJUSTMENT**. Signature:
TOTAL EFPH TO DATE: (TRANSFER to next day's surveillance or next run of this surveillance)
El "INFO ONLY" copy placed in file (Reviewer).
- MAY ONLY BE MADE AND SIGNED BY THE STATION NUCLEAR ENGINEER OR DESIGNEE. A WRITTEN DESCRIPTION OF THE REASON(S) FOR THE ADJUSTMENT MUST BE ATTACHED.
(Final)
IC18 D-2
1BwOSR 0.1-1,2,3 Revision 10 Information Use UNIT ONE - MODES 1, 2, AND 3 SHIFTLY AND DAILY OPERATING SURVEILLANCE DATA SHEET Critical Parameter Data Sheet (Mode 1 and 2)
Unit 1 r3*f*. Tnrl*\t TimAI-I-rge AI VCT Highest PZR *,,, ,.4,A Time Al/Target Al veigPR N! Press PZR Lvl Hi Tavg/Tref Gen Mwe Initial 23:00 -2.13 -2.14 49 77.1 2235 51 577.5 577.4 942 RC 0:00 -2.13 -2.14 49 77.1 2235 51 577.5 577.4 942 RC" 1:00 -2.13 -2.14 49 77.1 2235 51 577.5 577.4, 942 RC 2:00 -2.13 -2.14 49 77.1 2235 51 577.5 577.4 942 RC 3:00 -2.13 -2.14 49 77.1 2235 51 577.5 577.4 942 RC 4:00 -2.13 -2.14 49 77.1 2235 51 577.5 577.4 942 RC 5:00 -2.13 -2.14 49 77.1 2235 51 577.5 577.4 942 RC 6:00 -2.13 -2.14 49 77.1 2235 51 577.5 577.4 942 RC Unit Supervisor: KH 7:00 -2.13 -2.14 49 77.1 2235 51 577.5 577.4 942 RC 8:00 9:00 Dae Tnrl 10:00 11:00 12:00 13:00 14:00 Unit Supervisor:
15:00 16:00 17:00 18:00 19:00 20:00 21:00 Unit Supervisor:
(Final)
IC18