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{{#Wiki_filter:Simulation Facility Braidwood | {{#Wiki_filter:Simulation Facility Braidwood Scenario Operating Test No.: 15-1 NRC No.: | ||
NRC 1 Examiners: ______________________ Applicant: _____________________ SRO | |||
______________________ | ______________________ _____________________ ATC | ||
Applicant: | ______________________ _____________________ BOP Initial Conditions: IC-21 Turnover: Unit 1 is at 100% power, steady state, equilibrium xenon, BOL. Following completion of turnover, the Shift Manager requests that the BOP swap the 0A & 0B WS pumps per BwOP WS-1 and WS-3 in preparation for surveillance testing on Unit 2. | ||
_____________________ | Event Malf. No. Event Event No. Type* Description Preload Trgset 1 ZLO1HSMP025(3) == 0 Trg 1 IMF ED04A Offsite power is lost on the main generator trip 1 None N-BOP, Swap WS pumps US 2 IMF NI08H 500 10 I-ATC, US PR NI N-44 fails high TS-US 3 IMF RX03C 4.8 I-BOP, US 1B SG steam flow, 1FT-522, fails high 4 IMF CV05 600 5 C-ATC, Letdown line pressure controller 1PK-131 output US fails low 5 IOR ZDI1WO01PA TRIP C-BOP, 1A Containment Chilled Water Pump trip US 6 TH03B 5 60 TS-US 1B SG Tube Leak 7 None R-ATC, 1BwOA SEC-8 Fast Ramp US 8 IMF TH03B 550 M-ALL 1B SGTR 9 Preload C-ALL Offsite power is lost on the main generator trip (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient | ||
_____________________ | |||
_____________________ | |||
IC-21 Turnover: Unit 1 is at 100% power, steady state, equilibrium xenon, BOL. Following completion of turnover, | |||
-131 output fails low 5 IOR ZDI1WO01PA TRIP C-BOP, | |||
SCENARIO OVERVIEW Unit 1 is at 100% power, steady state, equilibrium xenon, BOL. Following completion of turnover, the Shift Manager requests that the BOP swap the 0A & 0B WS pumps per BwOP WS-1 and WS-3 in preparation for surveillance testing on Unit 2. | |||
After completing shift turnover and relief, the BOP will swap the 0A & 0B WS pumps in accordance with BwOP WS | After completing shift turnover and relief, the BOP will swap the 0A & 0B WS pumps in accordance with BwOP WS-1 and WS-3. The 0B WS pump will be started and the 0A WS pump will be placed in standby. | ||
-1 and WS-3. The 0B WS pump will be started and the 0A WS pump will be placed in standby. After swapping WS pumps , a failure of power range N | After swapping WS pumps, a failure of power range N-44 lower detector will occur. The crew will take actions per hard card 1BwPR 1-10-RD & 1BwOA INST-1 NUCLEAR INSTRUMENTATION MALFUNCTION including defeating the channel functions. Technical Specifications 3.3.1 Conditions A, D & E apply. | ||
-44 lower detector will occur. The crew will take actions per hard card 1BwPR 1-10-RD & 1BwOA INST | After the Power Range failure is addressed, a failure of 1FT-522, 1B SG steam flow channel, will occur. The crew will take actions per hard card 1BwPR 1-15-SG & 1BwOA INST-2 OPERATION WITH FAILED INSTRUMENT CHANNEL and perform required actions. The crew will swap to an operable steam flow channel. | ||
-1 | After completion of steam flow failure actions, letdown pressure controller, 1PK-131, output will fail low. The letdown pressure control valve, 1CV131, will close and letdown pressure will rise lifting the letdown line relief valve. The ATC will take manual control of letdown pressure controller per hard card 1BwPR 1-9-LD and restore letdown pressure. The crew may isolate letdown due to the lifting letdown relief valve. If letdown is isolated, it will be restored per BwOP CV-17. | ||
-522 , 1B SG steam flow channel | After the 1PK-131 controller failure is addressed, the 1A Containment Chilled Water pump will trip resulting in a trip of the 1A Containment Chiller. The crew will start the standby 1B Chilled Water pump and Chiller per BwOP VP-1 after receiving a report that the 1A Chilled Water pump motor appears damaged. Containment pressure and temperature will slowly rise as a result of the loss of Containment Cooling. The US should reference Tech Spec 3.6.4 and 3.6.5 and place a priority to start the standby Cnmt Chiller. | ||
, will occur. The crew will take actions per hard card 1BwPR 1-15-SG & 1BwOA INST-2 | After the Containment Chilled Water malfunction has been addressed, a 1B Steam Generator Tube Leak will be initiated. The crew will implement 1BwOA SEC-8 STEAM GENERATOR TUBE LEAK. The crew should determine from the estimated leak size that a fast ramp to remove the unit from power is required and make preparations to ramp the unit off line using 1BwGP 100-4, POWER DESCENSION or 1BwOA PWR-1 POWER REDUCTION. Technical Specifications 3.4.13 Condition B applies. | ||
After completion of steam flow failure actions , letdown pressure controller | After the SGTL has been addressed and the crew has ramped the unit sufficiently for a reactivity manipulation, the 1B SGTL will degrade to a 550 gpm Steam Generator Tube Rupture. The crew will implement 1BwEP-0 REACTOR TRIP OR SAFETY INJECTION. The crew will transition to 1BwEP-3 SGTR. | ||
, 1PK-131 , output will fail low. The letdown pressure control valve, 1CV131, will close and letdown pressure will rise lifting the letdown line relief valve. The ATC will take manual control of letdown pressure controller per hard card 1BwPR 1-9-LD and restore letdown pressure. The crew may isolate letdown due to the lifting letdown relief valve. If letdown is isolated, it will be restored per BwOP CV | The scenario is complete when the crew has terminated high head injection and established normal charging flow in 1BwEP-3. | ||
-17. After the 1PK | Critical Tasks | ||
-131 controller failure is addressed | : 1. Identify the 1B SG as the ruptured SG and isolate prior to a transition to 1BwCA-3.1 is required. | ||
, the 1A Containment Chilled Water pump will trip resulting in a trip of the 1A Containment Chiller. The crew will start the standby 1B Chilled Water pump and Chiller per BwOP VP | (Westinghouse - CT-18) (K/A number - EPE038EA1.32 importance 4.6/4.7) | ||
-1 after receiving a report that the 1A Chilled Water pump motor appears damaged. Containment pressure and temperature will slowly rise as a result of the loss of Containment Cooling. The US should reference Tech Spec 3.6.4 and 3.6.5 and place a priority to start the standby Cnmt Chiller. After the Containment Chilled Water malfunction has been addressed, a 1B Steam Generator Tube Leak will be initiated. The crew will implement 1BwOA SEC | : 2. Depressurize RCS to restore RCS inventory prior to 1B SG PORV or safety valve water release. | ||
-8 | (Westinghouse - CT-20) (K/A number - EPE038EA1.04 importance 4.3/4.1) 151 NRC 1 Page 2 | ||
-4, POWER DESCENSION or 1BwOA PWR-1 | |||
. | |||
-0 | |||
-3 | |||
-3. Critical Tasks | |||
: 1. Identify the | |||
-3.1 is required. | |||
(Westinghouse - CT-18) (K/A number | |||
- EPE038EA1.32 importance 4.6/4.7) | |||
: 2. Depressurize RCS to restore RCS inventory prior to | |||
(Westinghouse | |||
- CT-20) (K/A number | |||
SIMULATOR SETUP GUIDE | |||
. | * Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST. | ||
* Establish the conditions of IC-21, 100% power, steady state, equilibrium xenon. | |||
* Complete items on Simulator Ready for Training Checklist. | |||
* Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario. | |||
* Place simulator in RUN (allow simulator to run during board walk down and turnover). | |||
* Verify/place 0A and 0C VA plenums in service, 0B VA plenum in standby. | |||
* Verify RM-11 on Grid 1. | |||
* Monitor ruptured S/G status by using SimView file - SGTR. | |||
* Run caep 151 NRC 1 SETUP from disk and verify the following actuate: | |||
* Trgset 1 ZLO1HSMP025(3) == 0 | |||
* Trg 1 IMF ED04A | |||
* Provide examinees with turnover sheets. | |||
* Verify SER and RM-11 printers are clear of data. | |||
* Set Leak Tracker Program PPC point U9050 = 1.25 gpd. | |||
151 NRC 1 Page 3 | |||
Event 2: | INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Swap WS pumps. | ||
If dispatched as EO to observe WS pump swap, report 0B WS pump is ready for start, the pump has stable operating parameters once running. The stopped WS pump is not rotating backwards. Acknowledge the need to complete steps for aligning chemical injection. | |||
Event 2: Power Range N-44 fails high. | |||
Insert IMF NI08H 500 10 to fail N-44 lower detector high over 10 seconds. | Insert IMF NI08H 500 10 to fail N-44 lower detector high over 10 seconds. | ||
Acknowledge as SM | Acknowledge as SM, entry into Tech Spec 3.3.1 Conditions A, D & E. | ||
, entry into Tech Spec 3.3.1 Conditions A, D & E. | Acknowledge as SM, request for writing IR, performing on-line risk assessment and making appropriate notifications. | ||
Acknowledge as SM | |||
, request for writing IR, performing on-line risk assessment and making appropriate notifications. | |||
As SM, if requested for support for bypassing bistables in AEER, report that AEER bistables are not to be bypassed until work analyst and NSO support can be obtained (in approx. 2 hours) and that the abnormal operating procedure should be continued. | As SM, if requested for support for bypassing bistables in AEER, report that AEER bistables are not to be bypassed until work analyst and NSO support can be obtained (in approx. 2 hours) and that the abnormal operating procedure should be continued. | ||
ENSURE CONTROL RODS IN AUTO PRIOR TO INSERTING EVENT 3. | ENSURE CONTROL RODS IN AUTO PRIOR TO INSERTING EVENT 3. | ||
Event 3: Steam Flow detector 1FT | Event 3: Steam Flow detector 1FT-522 fails high. | ||
-522 fails high. Insert IMF RX03C 4.8 to fail 1B SG steam flow detector, 1FT | Insert IMF RX03C 4.8 to fail 1B SG steam flow detector, 1FT-522, high. | ||
-522, high. | As SM, acknowledge failure of 1FT-522, and requests for on-line risk assessment, maintenance support, and IR initiation. | ||
As SM, acknowledge failure of 1FT | |||
-522, and requests for on | |||
-line risk assessment, maintenance support, and IR initiation. | |||
As SM, acknowledge request for personnel notifications. | As SM, acknowledge request for personnel notifications. | ||
Event 4: | Event 4: Letdown line pressure controller 1PK-131 output fails low. | ||
-131 output fails low. | |||
Insert IMF CV05 600 5 to fail 1CV131 controller to 600 psig over 5 seconds. | Insert IMF CV05 600 5 to fail 1CV131 controller to 600 psig over 5 seconds. | ||
If dispatched as EO to investigate 1PT | If dispatched as EO to investigate 1PT-131, wait three minutes and report no visible damage to 1PT-131. | ||
-131, wait three minutes and report no visible damage to 1PT | If dispatched as EO to align excess letdown to the top of the VCT, insert the following: | ||
-131. If dispatched as EO to align excess letdown to the top of the VCT, insert the following: | * MRF CV26remf 100 to open 1CV8482. | ||
MRF CV26remf 100 to open 1CV8482. | * MRF CV27 0 to close 1CV8484. | ||
MRF CV27 0 to close 1CV8484. | Acknowledge as SM, the 1PK-131 failure, on-line risk assessment, requests for maintenance support, and IR requests. | ||
Acknowledge as SM | 151 NRC 1 Page 4 | ||
, the 1PK-131 failure, on | |||
-line risk assessment, requests for maintenance support, and IR requests. | |||
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 5: 1A Containment Chilled Water pump trip. | |||
Insert IOR ZDI1WO01PA TRIP to trip the 1A Containment Chilled Water pump. | |||
After the 1A Chilled Water pump is tripped, DELETE override DOR ZDI1WO01PA | After the 1A Chilled Water pump is tripped, DELETE override DOR ZDI1WO01PA. | ||
. | If dispatched as EO to investigate 1A Chilled Water pump breaker, wait 2 minutes and report the breaker tripped free. The 1A Cnmt Chiller breaker is open with NO flags. | ||
If dispatched as EO to investigate 1A Chilled Water pump breaker, wait 2 minutes and report the breaker tripped free. | |||
The 1A Cnmt Chiller breaker is open with NO flags. | |||
If dispatched as EO to investigate 1A Chilled Water pump, wait 3 minutes and report the pump motor smells acrid and there is a haze above the motor (no fire). Cause of 1A Containment Chiller trip is EVAP LOW WATER FLOW. | If dispatched as EO to investigate 1A Chilled Water pump, wait 3 minutes and report the pump motor smells acrid and there is a haze above the motor (no fire). Cause of 1A Containment Chiller trip is EVAP LOW WATER FLOW. | ||
If asked as EO | If asked as EO, report 1TIS-WO018 reads 44oF. | ||
, report 1TIS | As SM, acknowledge the trip of 1A Containment Chilled Water pump and Chiller, on-line risk assessment, maintenance support, and IR initiation. | ||
-WO018 reads | If asked direct the crew to start the 1B Chiller remotely from the MCR rather than locally. (reason is to limit time frame to restore Containment cooling). | ||
-line risk assessment, maintenance support, and IR initiation. | As EO, provide local operator actions for starting the 1B Containment Chilled Water Pump and Chiller (BwOP VP-1): | ||
If asked direct the crew to start the 1B Chiller remotely from the MCR rather than locally | * (step F.2) As EO, Oil Heater Breaker is on. If contacted as WEC supervisor, the WEC is tracking 1B Chiller Oil Heater energization time. | ||
. (reason is to limit time frame to restore Containment cooling). | * (step F.5) Pump suction pressure is 22 psig. WO Expansion Tank level is 55%. | ||
As EO, provide local operator actions for starting the 1B Containment Chilled Water Pump and Chiller (BwOP VP-1): | * (step F.7) 1WO005B is throttled. 1FIS-WO027 indicates 3000 gpm. | ||
(step F.5) Pump suction pressure is 22 psig. WO Expansion Tank level is 55%. | * (step F.8) Chiller Oil level is 50% in sightglass. | ||
(step F.7) 1WO005B is throttled. 1FIS | * (step F.9) Lamp test was satisfactory for all light bulbs. | ||
-WO027 indicates 3000 gpm. | * (step F.10) Chiller oil temperature is in band and Low Oil Temp alarm NOT lit locally. | ||
(step F.8) | * (step F.11) Electrical Demand Selector is in the 60% demand position. | ||
(step F.9) Lamp test was satisfactory for all light bulbs. | * (step F.12) LCD on the purge control unit displays ADAPTIVE mode. | ||
(step F.10) Chiller oil temperature is in band and Low Oil Temp alarm NOT lit locally. | * (step F.13) RESET pushbutton has been depressed for 2 seconds, no trip lights lit. | ||
(step F. | * (step F.15) IF asked to start the Chiller locally, report that the Local/Remote transfer switch is physically stuck in the REMOTE position (the intent is for the MCR to start the chiller per step F.16). | ||
(step F. | * (step F.16) Report that as EO you are standing by the 1B Containment Chiller ready for a remote start (START/STOP Switch is in STOP; Local/Remote switch is in REMOTE). | ||
(step F. | * (step F.17) The Program Timer Light at the Local Control Panel is lit. | ||
(step F. | * Report that you will complete the remaining local steps (F.18 - F.30). | ||
(step F.17) The Program Timer Light at the Local Control Panel is lit. | 151 NRC 1 Page 5 | ||
Report that you will complete the remaining local steps (F. | |||
151 NRC 1 Page | |||
Insert IMF TH03B 8 gpm initial to 9 gpm final over 30 minutes | INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 6: 1B SG tube leak. | ||
- | Insert IMF TH03B 8 gpm initial to 9 gpm final over 30 minutes - 1B SGTL at 8 gpm to 9 gpm over 30 minutes. | ||
Acknowledge as SM | If called as Chemistry for 1B S/G sample, wait 15 minutes and report the estimated 1B S/G leakrate at 5 gpm. | ||
, procedure transitions , Tech Spec 3.4.13 | If called as Chemistry a second time for 1B S/G sample, wait 10 minutes and report the estimated 1B S/G leakrate at 5 gpm. | ||
Event 7: | Acknowledge as SM, procedure transitions, Tech Spec 3.4.13 Condition B entry, E Plan evaluation. | ||
Event 7: Fast ramp of unit off line. | |||
To reset the SG blowdown panel trouble alarm, use the following: | To reset the SG blowdown panel trouble alarm, use the following: | ||
Insert IRF WD14 RESET As SM , acknowledge fast ramp requirement. | Insert IRF WD14 RESET As SM, acknowledge fast ramp requirement. | ||
Acknowledge as Generation Dispatch | Acknowledge as Generation Dispatch, the initiation of ramp. | ||
, the initiation of ramp | Event 8: 1B SGTR. | ||
Insert IMF TH03B 550 to initiate a 550 gpm tube rupture in the 1B SG. | |||
: procedure transitions, E Plan evaluations, and STA request. | Acknowledge as SM: procedure transitions, E Plan evaluations, and STA request. | ||
If asked, use SimView to close 1FW002A | If asked, use SimView to close 1FW002A-C (in SimView, set FWV1FW002A/B/C = 0). | ||
-C (in SimView, set | If asked, status of SAT 142-1 after sudden pressure trip, wait 2 minutes, then report deluge has initiated, NO fire exists. | ||
If asked, status of SAT 142 | |||
-1 after sudden pressure trip, wait 2 minutes, then report deluge has initiated, NO fire exists. | |||
Run CAE DrainCCSurge.cae if requested to isolate WM makeup and drain the CC surge tank. | Run CAE DrainCCSurge.cae if requested to isolate WM makeup and drain the CC surge tank. | ||
151 NRC 1 Page 6 | |||
Scenario NRC 1 Event 1 No: No. | |||
Event Swap WS pumps | |||
== | |||
Description:== | |||
== Description:== | |||
Time Position Applicants Actions or Behavior CUE | |||
-ESSENTIAL SERVICE WATER SYSTEM | * From turnover, swap 0A & 0B WS pumps per BwOP WS-1 STARTUP AND OPERATION OF THE NON-ESSENTIAL SERVICE WATER SYSTEM and BwOP WS-3 SHUTDOWN OF A NON-ESSENTIAL SERVICE WATER PUMP. | ||
US | |||
-ESSENTIAL SERVICE WATER PUMP. | * Direct BOP to perform BwOP WS-1 and BwOP WS-3. | ||
BOP Refer to BwOP WS-1, step 3. | |||
-3. BOP Refer to BwOP WS-1, step 3. | * Direct EO to verify proper 0B WS pump bearing oil levels. | ||
* Direct EO to perform Att. A to flush/clean 0B WS pump strainer. | |||
Direct EO to perform Att. A to flush/clean 0B WS pump strainer. | * Direct EO to verify/open 0WS002B, 0B WS pump discharge valve. | ||
Direct EO to verify/open 0WS002B, 0B WS pump discharge valve. | * Start 0B WS pump at 0PM01J. | ||
Start 0B WS pump at 0PM01J. Check for normal pump parameters. | * Check for normal pump parameters. | ||
Direct EO to OPEN 0CFX401, 0B WS pump chem injection isolation valve. | * Direct EO to OPEN 0CFX401, 0B WS pump chem injection isolation valve. | ||
Refer to BwOP WS | Refer to BwOP WS-3 (ALL 3 WS pumps are running). | ||
-3 (ALL 3 WS pumps are running). | * Direct EO to close 0CFX400, 0A WS pump chem injection isolation valve. | ||
Direct EO to close 0CFX400, 0A WS pump chem injection isolation valve. | * Place the 0A WS pump control switch in PULL OUT at 0PM01J. | ||
Place the 0A WS pump control switch in PULL OUT at 0PM01J. | * Direct EO to verify that the 0A WS pump shaft stops rotating. | ||
Direct EO to verify that the 0A WS pump shaft stops rotating. | * Direct EO to verify proper 0A WS pump bearing oil levels. | ||
Direct EO to verify proper 0A WS pump bearing oil levels. | * Direct EO to verify/open 0WS002A, 0A WS pump discharge valve. | ||
Direct EO to verify/open 0WS002A, 0A WS pump discharge valve. | * Place the 0A WS pump control switch in AFTER TRIP. | ||
Place the 0A WS pump control switch in AFTER TRIP. | * Check 0A WS pump stop light ON. | ||
Check 0A WS pump stop light ON. | * Direct EO to complete BwOP WS-3 step F.6 actions at Lake Screen House. | ||
Direct EO to complete BwOP WS | * Inform US that the WS pump swap is complete. | ||
-3 step F.6 actions at Lake Screen House. | US | ||
Inform US that the WS pump swap is complete. US | * Acknowledge report of WS pump swap. | ||
o Notify SM that WS pump swap is complete. | o Notify SM that WS pump swap is complete. | ||
ATC o Monitor remainder of | ATC o Monitor remainder of MCBs. | ||
EXAMINERS NOTE: After BwOP WS-1 & WS-3 are complete and with Lead Examiners concurrence, enter next event. | |||
Comments: | |||
151 NRC 1 Page 7 | |||
Scenario NRC 1 Event 2 No: No. | |||
Event Power Range N-44 fails high. | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior CUE | |||
* Annunciator PWR RNG FLUX RATE RX TRIP ALERT (1-10-C3) | |||
* Annunciator PWR RNG CHANNEL DEV (1-10-C4) | |||
Time Position | * Annunciator PWR RNG LOWER DET FLUX DEV HIGH (1-10-B4) | ||
* Control rod inward motion. | |||
-44 failing high. | ATC | ||
Verify turbine load stable, then place control rods in manual (may use hard card 1BwPR 1-10-RD). o Reference BwARs as time permits. | * Determine PR channel N-44 failing high. | ||
CREW | * Verify turbine load stable, then place control rods in manual (may use hard card 1BwPR 1-10-RD). | ||
-1 | o Reference BwARs as time permits. | ||
US | CREW | ||
-1 | * Identify entry conditions for 1BwOA INST-1 NUCLEAR INSTRUMENTATION MALFUNCTION. | ||
, | US | ||
Notify SM of PR N | * Implement 1BwOA INST-1 NUCLEAR INSTRUMENTATION MALFUNCTION, Attachment A "PR CHANNEL FAILURE" and direct operator action. | ||
-44 failure. | * Notify SM of PR N-44 failure. | ||
Notify SM to evaluate for Emergency Plan. ATC | * Notify SM to evaluate for Emergency Plan. | ||
Rod bank select switch in manual (performed previously). | ATC | ||
Check for rod stop. | * Check rod control status. | ||
Annunciator PWR RNG FLUX HIGH ROD STOP (1 B5) - LIT. Place rod stop bypass switch to N | * Rod bank select switch in manual (performed previously). | ||
-44 at 1PM07J. | * Check for rod stop. | ||
ATC | * Annunciator PWR RNG FLUX HIGH ROD STOP (1-10-B5) - LIT. | ||
BOP | |||
* Place rod stop bypass switch to N-44 at 1PM07J. | |||
ATC | |||
* Verify TAVE - TREF stable & within 1°F. If NOT, restore TAVE - TREF to within 1°F: | |||
o Withdraw control rods. | |||
o Adjust RCS boron concentration. | o Adjust RCS boron concentration. | ||
o Adjust turbine load. | o Adjust turbine load. | ||
BOP | BOP | ||
BOP | * Check SG levels normal and stable. | ||
N-44 upper section detector current comparator. | BOP | ||
N-44 lower section detector current comparator. | * Bypass/defeat PR channel functions at 1PM07J: | ||
N-44 power mismatch bypass. | * N-44 upper section detector current comparator. | ||
o N-44 rod stop bypass (performed | * N-44 lower section detector current comparator. | ||
* N-44 power mismatch bypass. | |||
o N-44 rod stop bypass (performed previously). | |||
* N-44 comparator channel defeat. | |||
Comments: | |||
151 NRC 1 Page 8 | |||
Scenario NRC 1 Event 2 No: No. | |||
Event Power Range N-44 fails high. | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior BOP | |||
* Reset flux rate trip alarm for N-44 at 1PM07J. | |||
BOP | |||
Time Position | * Place computer points in test: | ||
BOP | * N0047 | ||
N0047 | * N0048 | ||
N0052A | * U1143 | ||
US o As directed by the Shift Manager: | * Delete computer point from scan: | ||
* N0052A | |||
* Place N44 input to DEH in Test. | |||
US o As directed by the Shift Manager: | |||
o Locally bypass bistables for affected channel. | o Locally bypass bistables for affected channel. | ||
o Trip bistables for affected PR channel | o Trip bistables for affected PR channel. | ||
BOP o Locally bypass bistables for failed NI protection channel functions. | |||
Access failed NI protection panel. | * Access failed NI protection panel. | ||
Verify bypass enable key lock switch is in normal. | * Verify bypass enable key lock switch is in normal. | ||
Verify following individual bypass function switches in normal and bypass LEDs off: | * Verify following individual bypass function switches in normal and bypass LEDs off: | ||
-LOW | * SWITCH #2 P10 PERMISSIVE | ||
-HIGH | * SWITCH #3 POSITIVE RATE TRIP | ||
Non-safety breaker ON. | * SWITCH #4 OVER POWER TRIP-LOW | ||
Safety breaker ON. | * SWITCH #5 OVER POWER TRIP-HIGH | ||
Insert key in bypass enable key lock and turn key to BYPASS position. Verify bypass enable LED is lit. | * SWTICH #6 OVER POWER ROD STOP | ||
Place bypass function switches in bypass and verify bypass LEDs are lit. | * SWITCH #7 P8 PERMISSIVE | ||
SWITCH #2 P10 PERMISSIVE SWITCH #3 POSITIVE RATE TRIP SWITCH #4 OVER POWER TRIP | * Energize failed channel bypass panel by pressing both breaker to on. | ||
-LOW | * Non-safety breaker ON. | ||
-HIGH | * Safety breaker ON. | ||
* Insert key in bypass enable key lock and turn key to BYPASS position. | |||
* Verify bypass enable LED is lit. | |||
* Place bypass function switches in bypass and verify bypass LEDs are lit. | |||
* SWITCH #2 P10 PERMISSIVE | |||
* SWITCH #3 POSITIVE RATE TRIP | |||
* SWITCH #4 OVER POWER TRIP-LOW | |||
* SWITCH #5 OVER POWER TRIP-HIGH | |||
* SWTICH #6 OVER POWER ROD STOP | |||
* SWITCH #7 P8 PERMISSIVE Comments: | |||
151 NRC 1 Page 9 | |||
Scenario NRC 1 Event 2 No: No. | |||
Event Power Range N-44 fails high. | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior o Locally bypass AEER bistables for PR N-44 to bypass. | |||
ATC | |||
* Select operable channel (other than 1D) to loop T recorder. | |||
Time Position | ATC | ||
-44 to bypass | * Check if rod control can be placed in auto. | ||
* C-5 not lit. | |||
ATC | * TAVE - TREF stable and within 1°F. | ||
C-5 not lit. | * Place control rods in auto. | ||
US | |||
US | * Determine Tech Spec 3.3.1 Conditions A, D, and E are applicable. | ||
o Enter/exit Tech Spec 3.4.1 if PZR pressure dropped below 2209 psig during auto rod steps. Contact SM to perform risk assessment, initiate IR, evaluate reactivity screening, make notifications and contact appropriate personnel to investigate/correct instrument failure. | o Enter/exit Tech Spec 3.4.1 if PZR pressure dropped below 2209 psig during auto rod steps. | ||
* Contact SM to perform risk assessment, initiate IR, evaluate reactivity screening, make notifications and contact appropriate personnel to investigate/correct instrument failure. | |||
EXAMINERS NOTE: (1) After the actions for PRNI N-44 are complete and with Lead Examiners concurrence, enter next event. | |||
(2) Ensure rods are back in AUTO prior to inserting the next event. | (2) Ensure rods are back in AUTO prior to inserting the next event. | ||
Comments: | |||
151 NRC 1 Page 10 | |||
Scenario NRC 1 Event 3 No: No. | |||
Event Steam flow detector, 1FT-522, failure | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior CUE | |||
* Annunciator S/G 1B FLOW MISMATCH FW FLOW LOW (1-15-B4) | |||
* 1FI-522A steam flow indicator fails high. | |||
* 1B SG level meters, 1LI-527/528/529/557, indicate rising level. | |||
/G 1B FLOW MISMATCH FW FLOW LOW (1 B4) | o Annunciator S/G 1B LEVEL DEVIATION HIGH LOW (1-15-B9) | ||
1B SG level meters, 1LI-527/528/529/557 , indicate rising level. | BOP | ||
o Annunciator S | * Determine 1FT-522 failed high. | ||
/G 1B LEVEL DEVIATION HIGH LOW (1 B9) | * Place 1B FRV (1FW520) in manual and restore SG level per hard card 1BwPR 1 SG. | ||
-522 failed high. Place 1B FRV (1FW520) in manual and restore SG level per hard | * Place master feed pump speed control in manual. | ||
Select operable steam flow channel. | * Select operable steam flow channel. | ||
o Reference BwARs.as time permits. | o Reference BwARs.as time permits. | ||
CREW | CREW | ||
-2 | * Identify entry conditions for 1BwOA INST-2 OPERATION WITH FAILED INSTRUMENT CHANNEL. | ||
US | US | ||
Request SM evaluation of Emergency Plan conditions. | * Notify SM of plant status and procedure entry. | ||
Enter/implement 1BwOA INST | * Request SM evaluation of Emergency Plan conditions. | ||
-2 | * Enter/implement 1BwOA INST-2 OPERATION WITH FAILED INSTRUMENT CHANNEL, Attachment H, STEAM FLOW CHANNEL FAILURE and direct operator actions of 1BwOA INST-2. | ||
-2. BOP | BOP | ||
-2). o If SG level abnormal: | * Stabilize 1B SG level (actions to stabilize per hard card 1BwPR 1-15-SG initially, then 1BwOA INST-2). | ||
o If SG level abnormal: | |||
o Control 1B FRV (1FW520) in manual. | o Control 1B FRV (1FW520) in manual. | ||
o Place master feed pump speed control in manual. | o Place master feed pump speed control in manual. | ||
o Verify adequate feedwater DP (1BwGP 100 | o Verify adequate feedwater DP (1BwGP 100-3A9). | ||
-3A9). o Restore SG level(s). Select operable steam flow channel (1BwPR 1-15-SG action): | o Restore SG level(s). | ||
Verify steam pressure channels normal. | * Select operable steam flow channel (1BwPR 1-15-SG action): | ||
BOP o Ramp 5 MW down at 5 MW/minute (may be performed based on crew discretion). | * Establish/verify automatic SG level control. | ||
* Verify steam pressure channels normal. | |||
BOP o Ramp 5 MW down at 5 MW/minute (may be performed based on crew discretion). | |||
Comments: | |||
151 NRC 1 Page 11 | |||
Scenario NRC 1 Event 3 No: No. | |||
Event Steam flow detector, 1FT-522, failure | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior EXAMINERS NOTE: 1BwOA PRI-16 RESPONSE TO OVERPOWER CONDITION may also be used to lower Rx power below 100%. | |||
CREW | |||
* Check reactor power <100%: | |||
* PPC 10 min. calorimetric. | |||
* Computer point (U0923) | |||
* NIs. | |||
US | |||
* Notify SM/maintenance to investigate/correct the failed steam flow channel: | |||
* Determine Tech Specs are NOT applicable. | |||
* Contact SM to perform risk assessment, initiate IR, reactivity screening, notify QNE and contact maintenance to investigate/correct instrument failure. | |||
EXAMINERS NOTE: After the actions for the steam flow failure are complete and with Lead Examiners concurrence, insert next event. | |||
Comments: | |||
151 NRC 1 Page 12 | |||
Scenario NRC 1 Event 4 No: No. | |||
Event 1PK-131 output fails low | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior CUE | |||
* Annunciator LTDWN HX OUTLT PRESS HIGH (1-8-B5) | |||
* 1FI-132, letdown line flow, lowering. | |||
* 1PI-131, letdown line pressure, rising. | |||
o Annunciator LP LTDWN RLF TEMP HIGH (1-9-B1) | |||
1PI-131, letdown line pressure, rising. | ATC | ||
o Annunciator LP LTDWN RLF TEMP HIGH (1 B1) | * Recognize 1PK-131 failed. | ||
-131 failed. | * Place 1PK-131 in manual and adjust letdown pressure to pre-failed value per hard card 1BwPR 1-9-LD at 1PM05J. | ||
Place 1PK-131 in manual and adjust letdown pressure to pre | |||
-failed value per hard card 1BwPR 1-9-LD at 1PM05J. | |||
o Refer to BwARs as time permits. | o Refer to BwARs as time permits. | ||
US | US | ||
-131 and returns letdown pressure to normal. Inform SM of 1PK | * Direct/ensure ATC takes manual control of 1PK-131 and returns letdown pressure to normal. | ||
-131 failure. | * Inform SM of 1PK-131 failure. | ||
o Direct ATC to isolate letdown. | o Direct ATC to isolate letdown. | ||
ATC Perform the following at 1PM05J: | ATC Perform the following at 1PM05J: | ||
Maintain letdown flow and pressure by operating 1PK | * Maintain letdown flow and pressure by operating 1PK-131 in manual. | ||
-131 in manual. | o May take manual control of 1TK-130. | ||
o May take manual control of 1TK | US | ||
-130. US | * Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure. | ||
EXAMINERS NOTE: (1) The crew may elect to isolate letdown based on letdown relief valve lifting. Following letdown isolation, the crew may elect to establish excess letdown or re-establish normal letdown. The steps for restoring normal letdown are in italics below. | |||
, the crew may elect to establish excess letdown or re | (2) The crew may use hard card 1BwPR 1-9-LD to isolate letdown. | ||
-establish normal letdown. The steps for restoring normal letdown are in italics below. | BOP o Establish normal letdown per BwOP CV-17: | ||
(2) The crew may | o Verify/close 1CV8149A/B/C. | ||
BOP o Establish normal letdown per BwOP CV | o Verify CC aligned to letdown HX (was previously aligned). | ||
-17: o Verify/close 1CV8149A/B/C. | |||
o Verify CC aligned to letdown | |||
o Place 1CV131 controller in manual at 40% demand. | o Place 1CV131 controller in manual at 40% demand. | ||
o Place 1CC130 controller in manual at 60% demand. | o Place 1CC130 controller in manual at 60% demand. | ||
Comments: | |||
151 NRC 1 Page 13 | |||
Scenario NRC 1 Event 4 No: No. | |||
Event 1PK-131 output fails low | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior o Verify/open 1CV8152/8160. | |||
o Verify/open 1CV459/460. | |||
o Verify/open 1CV8324A & 1CV8389A. | |||
o Verify/open 1CV459/460. | o Verify/open 1CV381B (BTRS Mode Selector Switch OFF light LIT). | ||
o Verify/open 1CV8324A & 1CV8389A. | o Verify/close 1CV381A (BTRS Mode Selector Switch OFF light LIT). | ||
o Verify/open 1CV381B (BTRS Mode Selector Switch OFF light LIT). | o Verify/open 1CV8401A. | ||
o Verify/close 1CV381A (BTRS Mode Selector Switch OFF light LIT). | o Verify/close 1CV8145. | ||
o Verify/open 1CV8401A. | o Verify/open 1CV8147. | ||
o Verify/close 1CV8145. | o Open 1CV8105/8106. | ||
o Verify/open 1CV8147. | o Adjust charging flow to approx. 100 gpm w/seal injection 8-10 gpm per RCP. | ||
o Open 1CV8105/8106. | o Open 1CV8149A/B/C and control 1CV131 to maintain letdown pressure 360-380 psig. | ||
o Adjust charging flow to approx. 100 gpm w/seal injection 8 | o Control 1CC130 controller to maintain letdown temperature 90-115°F. | ||
-10 gpm per RCP. | o Place controllers in auto. | ||
o Open 1CV8149A/B/C and control 1CV131 to maintain letdown pressure 360 | |||
-380 psig. o Control 1CC130 controller to maintain letdown temperature 90 | |||
-115 F. o Place controllers in auto. | |||
o Verify 1PR06J in service. | o Verify 1PR06J in service. | ||
o Verify proper operation of RMCS during VCT makeup. | o Verify proper operation of RMCS during VCT makeup. | ||
o Proper flow indicated on PW/Total Flow (1FT | o Proper flow indicated on PW/Total Flow (1FT-0111) and Boric Acid Flow (1FT-0110). | ||
-0111) and Boric Acid Flow (1FT | o Restore PZR level to program. | ||
-0110). o Restore PZR level to program. | |||
The steps for establishing excess letdown are in italics below. | The steps for establishing excess letdown are in italics below. | ||
BOP o Establish excess letdown per BwOP CV | BOP o Establish excess letdown per BwOP CV-15 EXCESS LETDOWN OPERATIONS. | ||
-15 | o Prerequisite if excess letdown is placed in service, reactor power is maintained less than or equal to 99.8%. | ||
o Verify open 1CV8100/8112. | |||
, reactor power is maintained less than or equal to 99.8%. | o Open 1CC9437A/B. | ||
o Verify open 1CV8100/8112. o Open 1CC9437A/B. | |||
o Verify/closed 1CV123. | o Verify/closed 1CV123. | ||
o Verify 1CV8143 C/S in VCT position. | o Verify 1CV8143 C/S in VCT position. | ||
o Open 1RC8037A/B/C/D. | o Open 1RC8037A/B/C/D. | ||
o Open 1CV8153A(B). | o Open 1CV8153A(B). | ||
o Slowly open 1CV123 while | o Slowly open 1CV123 while maintaining excess letdown outlet temperature <165F. | ||
EXAMINERS NOTE: After the actions for the 1PK-131 failure are complete and with Lead Examiners concurrence, insert next event. | |||
Comments: | |||
151 NRC 1 Page 14 | |||
Scenario NRC 1 Event 5 No: No. | |||
Event 1A Containment Chilled Water pump trip | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior CUE | |||
* Annunciator CNMT CHLR UNIT TROUBLE (0-33-D3) | |||
* 1A Containment Chiller trip light - LIT. | |||
* 1A Chilled Water pump trip light - LIT. | |||
US o Direct BOP to respond to BwAR 0-33-D3. | |||
* Direct BOP to start 1B Containment Chilled Water Pump and Chiller. | |||
* Notify SM of 1A Cnmt Chilled Water pump failure. | |||
o Evaluate Containment conditions against Tech Specs 3.6.4 and 3.6.5. | |||
o Notify SM to evaluate for Emergency Plan. | |||
BOP | |||
* Determine 1A Cnmt Chiller and Chilled Water pump tripped. | |||
* Reference BwAR 0-33-D3 (dispatch EO to Cnmt Chiller/Chilled Water pump). | |||
o Place 1A Chilled Water Pump/Chiller C/S in PTL. | |||
* Start 1B Containment Chilled Water Pump and Chiller per BwOP VP-1. | |||
BOP BwOP VP-1 Actions: | |||
* Direct EO to locally energize oil heaters and notifies WEC to track energization time of heaters-verify heaters energized for 1B VP chiller. | |||
* Verify OPEN: | |||
* 1SX112B, Cnmt Chiller SX Inlet Vlv. | |||
* 1SX114B, Cnmt Chiller SX Outlet Vlv. | |||
* 1SX147B, Cnmt Chiller SX Bypass Vlv. | |||
* 1SX016B, RCFC SX Supply Vlv @ 1PM06J. | |||
* 1SX027B, RCFC SX Return Vlv @ 1PM06J. | |||
* Verify OPEN @ 1PM06J: | |||
* 1WO006B, 1B + 1D Chill Wtr Inlet Cnmt Isol Vlv. | |||
* 1WO020B, 1B + 1D Chill Wtr Outlet Cnmt Isol Vlv. | |||
* 1WO056B, 1B + 1D Chill Wtr Outlet Cnmt Isol Vlv. | |||
* Direct local EO to perform steps F.5 (verify Pump suction pressure and Expansion Tank level). | |||
* Start 1WO01PB, Chilled Water Pump. | |||
* Direct EO to locally complete BwOP VP-1 steps F.7 - F.13. | |||
* Verify/place 1B Byp Isol Vlv 1SX147B in AUTO at 0PM02J. | |||
* Start the 1B Containment Chiller from the MCR: | |||
Comments: | |||
151 NRC 1 Page 15 | |||
Scenario NRC 1 Event 5 No: No. | |||
Event 1A Containment Chilled Water pump trip | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior | |||
* Direct EO to locally verify START/STOP switch in STOP and Local/Remote switch in Remote and is prepared to record initial data locally. | |||
* Place 1WO01CB, Chiller 1B Control Switch, at 0PM02J to AFTER CLOSE. | |||
* Direct EO to locally complete steps F.17 to F.30. | |||
US | |||
Place 1WO01CB, Chiller 1B Control Switch, at 0PM02J to AFTER CLOSE. | * Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure. | ||
Direct EO to locally complete steps F. | EXAMINERS NOTE: After the actions for the Containment Chilled Water pump trip are complete and with Lead Examiners concurrence, insert next event. | ||
Comments: | |||
Comments: | 151 NRC 1 Page 16 | ||
Scenario NRC 1 Event 6 No: No. | |||
Event 1B SG Tube Leak | |||
== Description:== | == | ||
Description:== | |||
Time Position Applicants Actions or Behavior CUE | |||
o SG BLDN - 1PR08J. o SJAE/GLAND STEAM EXHAUST | * RM-11 Secondary rad monitor alarms/levels rising: | ||
- 1PR027J. o 1B MAIN STEAM LINE | o SG BLDN - 1PR08J. | ||
- 1AR022J/23J. | o SJAE/GLAND STEAM EXHAUST - 1PR027J. | ||
o 1B MAIN STEAM LINE - 1AR022J/23J. | |||
o PZR level dropping. | o PZR level dropping. | ||
o PZR pressure dropping. | o PZR pressure dropping. | ||
o Charging/letdown mismatch. BOP o Refer to BwAR 1-1PR27J for operator actions. | o Charging/letdown mismatch. | ||
o Refer to BwAR 1-1PR08J for operator actions. | BOP o Refer to BwAR 1-1PR27J for operator actions. | ||
o Refer to BwAR 1-1AR22/23J for operator actions. | o Refer to BwAR 1-1PR08J for operator actions. | ||
CREW | o Refer to BwAR 1-1AR22/23J for operator actions. | ||
US | CREW | ||
Request SM evaluation of Emergency Plan conditions. | * Identify entry conditions for 1BwOA SEC-8 STEAM GENERATOR TUBE LEAK. | ||
Notify SM of SG leakage. | US | ||
ATC | * Implement 1BwOA SEC-8 and direct operator actions. | ||
o PZR pressure | * Request SM evaluation of Emergency Plan conditions. | ||
< 1829 psig. | * Notify SM of SG leakage. | ||
o Steamline pressure | ATC | ||
< 640 psig. o CNMT pressure | * Check SI Status: | ||
> 3.4 psig. Maintain PZR level: | o PZR pressure < 1829 psig. | ||
Throttle 1CV121 & 1CV182 as necessary. | o Steamline pressure < 640 psig. | ||
Check PZR level stable or rising. | o CNMT pressure > 3.4 psig. | ||
* Maintain PZR level: | |||
* Throttle 1CV121 & 1CV182 as necessary. | |||
* Check PZR level stable or rising. | |||
o If PZR level lowering, reduce letdown flow to 75 gpm. | o If PZR level lowering, reduce letdown flow to 75 gpm. | ||
ATC | ATC | ||
Verify makeup is adequate to maintain VCT level. | * Monitor VCT level. | ||
US | * Verify makeup is adequate to maintain VCT level. | ||
Dispatch operators to perform BwOP MS-13 | US | ||
Comments: | * Minimize Secondary Contamination. | ||
* Dispatch operators to perform BwOP MS-13 OPERATION WITH SG TUBE LEAKAGE. | |||
Comments: | |||
151 NRC 1 Page 17 | |||
Scenario NRC 1 Event 6 No: No. | |||
Event 1B SG Tube Leak | |||
== Description:== | == | ||
Description:== | |||
Time Position Applicants Actions or Behavior US | |||
CREW | * Notify RP to monitor rad levels and quantify release. | ||
Trend Main Steam Line monitors. | CREW | ||
o Dropping | * Identify leaking SG (1B). | ||
* Trend Main Steam Line monitors. | |||
o Dropping feed flow with stable SG level. | |||
o Unexpected rise in any NR SG level. | o Unexpected rise in any NR SG level. | ||
o Chemistry reports high activity via sample or N | o Chemistry reports high activity via sample or N-16 monitor. | ||
-16 monitor. | CREW | ||
CREW | * Determine SG tube leak rate. | ||
Estimate leak rate. | * Estimate leak rate. | ||
o Computer point U9052 or SG Leak Tracker Program on PPC. o Charging/letdown/RCP leakoff flow balance. | o Computer point U9052 or SG Leak Tracker Program on PPC. | ||
o Charging/letdown/RCP leakoff flow balance. | |||
o Change in VCT level. | o Change in VCT level. | ||
o Grab sample. | o Grab sample. | ||
o 1BwOS SG-1 SG , Pri to Sec Leakage Estimation. | o 1BwOS SG-1 SG, Pri to Sec Leakage Estimation. | ||
Check total RCS to secondary leak rate | * Check total RCS to secondary leak rate > 10 gpm - NO. | ||
* Perform 1BwOSR 3.4.13.1 while continuing with 1BwOA SEC-8. | |||
-8. Check 1PR27J, SJAE rad monitor, operable. | * Check 1PR27J, SJAE rad monitor, operable. | ||
Trend SG leakrate. | * Trend SG leakrate. | ||
Notify Chemistry to sample SGs. | * Notify Chemistry to sample SGs. | ||
Check PPC point U9052 responding to plant conditions ( | * Check PPC point U9052 responding to plant conditions (1PR08J/N-16 rad monitors). | ||
Determine if a shutdown is required. | * Trend leakrate every 15 minutes. | ||
SG leakrate | * Determine if a shutdown is required. | ||
< 100 gpd - NO - GO TO step 9. | * SG leakrate < 100 gpd - NO - GO TO step 9. | ||
CREW | CREW | ||
- TREND in the same direction. | * Confirm SG leak rate (step 9). | ||
* At least 2 independent indications - TREND in the same direction. | |||
o Main steam line radiation monitors. | o Main steam line radiation monitors. | ||
o SJAE/GS Exhaust radiation monitor. | o SJAE/GS Exhaust radiation monitor. | ||
o SG Blowdown radiation monitor. | o SG Blowdown radiation monitor. | ||
o N-16 radiation monitors. | o N-16 radiation monitors. | ||
Comments: | |||
151 NRC 1 Page 18 | |||
Scenario NRC 1 Event 6 No: No. | |||
Event 1B SG Tube Leak | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior CREW | |||
* Initiate Unit Shutdown. | |||
* Check leak rate < 100 gpd - NO. | |||
Check leak rate < 100 gpd | * Reduce power to < 50% within 1 hour (Rapid Power Reduction - 1BwGP 100-4T3). | ||
- NO. Reduce power to < 50% within 1 hour (Rapid Power Reduction | o Shutdown Unit to MODE 3 within 2 hours of reaching 50% power. Continue shutdown using 1BwGP 100-4 and 5. | ||
- 1BwGP 100-4T3). o Shutdown Unit to MODE 3 within 2 hours of reaching 50% power. | US | ||
Continue shutdown using 1BwGP 100 | * Determine Tech Spec 3.4.13 Condition B applies. | ||
-4 and 5. US | EXAMINERS NOTE: At this point, the crew should begin preparations for shutting down the unit. The remaining actions of 1BwOA SEC-8 would be performed after the reactor is shutdown, if an SI does NOT actuate. | ||
EXAMINERS NOTE: The fast ramp due to the SG tube leak is event 7. See the following pages. | |||
, the crew should begin preparations for shutting down the unit. | Comments: | ||
The remaining actions of 1BwOA SEC | 151 NRC 1 Page 19 | ||
-8 would be performed after the reactor is shutdown, if an SI does NOT actuate. | |||
Comments: | |||
Scenario NRC 1 Event 7 No: No. | |||
Event 1BwOA SEC-8 Fast Ramp | |||
== Description:== | == | ||
Description:== | |||
Time Position Applicants Actions or Behavior CUE | |||
-8, a fast ramp load drop is required. | * Determine from 1BwOA SEC-8, a fast ramp load drop is required. | ||
US | US o Perform pre-job brief per HU-AA-1211 PRE-JOB, HEIGHTENED LEVEL OF AWARENESS, INFREQUENT PLANT ACTIVITY, AND POST JOB BRIEFINGS for load ramp. | ||
-job brief per HU | o Perform pre-job brief using the Emergent Ramp Reactivity Summary Sheet (under the NSO desk glass) for load ramp. | ||
-AA-1211 | |||
o Perform pre | |||
-job brief using the Emergent Ramp Reactivity Summary Sheet (under the NSO desk glass) for load ramp. | |||
o Inform SM of the 1BwOA SEC-8 fast ramp. | o Inform SM of the 1BwOA SEC-8 fast ramp. | ||
CREW | CREW | ||
-8 Fast Ramp reactivity plan. | * Review Operator Aid for 1BwOA SEC-8 Fast Ramp reactivity plan. | ||
Review applicable Prerequisites, Precautions, and Limitations and Actions of 1BwGP 100-4. | * Review applicable Prerequisites, Precautions, and Limitations and Actions of 1BwGP 100-4. | ||
EXAMINERS NOTE: The following step may be repeated as necessary to borate the RCS during the power descension. | |||
Perform the following at 1PM05J: | ATC BwOP CV-6 Attachment A, borate in automatic, via hard card. Perform the following at 1PM05J: | ||
Verify rod position and boron concentration. | * Verify rod position and boron concentration. | ||
Determine required boric acid volume. | * Determine required boric acid volume. | ||
o Refer to operator aid for required boric acid addition. | o Refer to operator aid for required boric acid addition. | ||
Determine desired boric acid flow rate. | * Determine desired boric acid flow rate. | ||
Perform the following at 1PM05J: | * Perform the following at 1PM05J: | ||
o Turn on PZR backup heaters (as required). | o Turn on PZR backup heaters (as required). | ||
Set 1FK-110 BA Flow | * Set 1FK-110 BA Flow Controller to desired boration rate. | ||
Set 1FY-0110 BA Blender Predet Counter to desired volume. | * Set 1FY-0110 BA Blender Predet Counter to desired volume. | ||
Place MAKE | * Place MAKE-UP MODE CONT SWITCH to STOP position. | ||
-UP MODE CONT SWITCH to STOP position. Place MODE SELECT SWITCH to BORATE position. | * Place MODE SELECT SWITCH to BORATE position. | ||
Place MAKE | * Place MAKE-UP MODE CONT SWITCH to START. | ||
-UP MODE CONT SWITCH to START. | * Verify proper operation of valves and BA transfer pump (1CV110B open, Boric Acid Transfer Pump running, 1CV110A throttles open, proper BA flow indicated on recorder). | ||
Verify proper operation of valves and BA transfer pump (1CV110B open, Boric Acid Transfer Pump running, 1CV110A throttles open, proper BA flow indicated on recorder). o If desired, adjust 1LK | o If desired, adjust 1LK-112, VCT level controller, setpoint to control VCT level. | ||
-112, VCT level controller, setpoint to control VCT level. | * When desired boration achieved, place RMCS M/U CONT switch to STOP. | ||
When desired boration achieved, place RMCS M/U CONT switch to STOP. | * Verify 1CV110B closed, 1CV110A closed and Boric Acid Transfer Pump stopped. | ||
Verify 1CV110B closed, 1CV110A closed and Boric Acid Transfer Pump stopped. | OR Comments: | ||
OR Comments: | 151 NRC 1 Page 20 | ||
Scenario NRC 1 Event 7 No: No. | |||
Event 1BwOA SEC-8 Fast Ramp | |||
== Description:== | == | ||
Description:== | |||
Time Position Applicants Actions or Behavior BwOP CV-6 Attachment A, batch boration, via hard card. Perform the following at 1PM05J: | |||
Perform the following at 1PM05J: o Turn on PZR backup heaters (as required). | o Turn on PZR backup heaters (as required). | ||
Open 1CV110B. | * Open 1CV110B. | ||
Open 1CV110A. | * Open 1CV110A. | ||
Start the BA Transfer pump. | * Start the BA Transfer pump. | ||
o If desired, adjust 1LK | o If desired, adjust 1LK-112, VCT level controller, setpoint to control VCT level. | ||
-112, VCT level controller, setpoint to control VCT level. | * When desired amount of BA has been added, stop the BA Transfer Pump. | ||
When desired amount of BA has been added, stop the BA Transfer Pump. | * Close 1CV110A. | ||
Close 1CV110A. | * Close 1CV110B. | ||
Close 1CV110B. | o Adjust 1LK-112, VCT level controller, setpoint to desired value. | ||
o Adjust 1LK | * Place 1CV110A/B to AUTO. | ||
-112, VCT level controller, setpoint to desired value. | * Record boration in Unit log. | ||
Place 1CV110A/B to AUTO. | * Perform BwOP CV-7 to return RMCS to automatic. | ||
Record boration in Unit log. | BOP | ||
Perform BwOP CV | * Lower turbine load at 1PM02J or OWS drop 210 by performing the following: | ||
-7 to return RMCS to automatic. | * Select SETPOINT. | ||
BOP | * Enter desired MWs into REF DEMAND window. | ||
Select SETPOINT. | * Select ENTER. | ||
Enter desired | * Verify correct value in REFERENCE DEMAND window. | ||
Select ENTER. | * Enter desired MW/min into the RATE window. | ||
Verify correct value in REFERENCE DEMAND window. | * Select ENTER. | ||
Enter desired MW/min into the RATE window. | * Select EXIT. | ||
Select ENTER. Select EXIT. | * Select GO/HOLD. | ||
Select GO/HOLD. | * Verify GO/HOLD button illuminates. | ||
Verify GO/HOLD button illuminates. | * Verify HOLD illuminated RED. | ||
Verify HOLD illuminated RED. | * Inform crew of pending ramp with an UPDATE. | ||
Inform crew of pending ramp with an UPDATE. | * Select GO. | ||
Select GO. | * Verify GO illuminates RED. | ||
Verify GO illuminates RED. | * Verify main turbine load begins to lower. | ||
Verify main turbine load begins to lower. | ATC | ||
ATC | * Monitor reactor power and turbine load lowering. | ||
Monitor NIs, Tave, I, | * Monitor NIs, Tave, I, PZR pressure/level at 1PM05J. | ||
Monitor MWe and DEHC system response at 1PM02J or OWS drop 210. | * Monitor MWe and DEHC system response at 1PM02J or OWS drop 210. | ||
During boration, monitor the following at 1PM05J and PPC: | * During boration, monitor the following at 1PM05J and PPC: | ||
o Monitor VCT level. | o Monitor VCT level. | ||
Comments: | |||
151 NRC 1 Page 21 | |||
Scenario NRC 1 Event 7 No: No. | |||
Event 1BwOA SEC-8 Fast Ramp | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior o Monitor BA predet counter. | |||
o Verify boration auto stops at preset value. | |||
o Return Reactor Makeup Control System to automatic at current boron concentration. | |||
o Verify boration auto stops at preset value. | EXAMINERS NOTE: The crew may use 1BwOA PWR-1 POWER REDUCTION as the guidance to perform the fast ramp. Steps in italics below. | ||
o Return Reactor Makeup Control System to automatic at current boron concentration. | CREW 1BwOA PWR-1 POWER REDUCTION | ||
* Request SM evaluation of Emergency Plan conditions. | |||
-1 | * Perform a reactivity summary brief. | ||
* Check control rods in auto. | |||
CREW 1BwOA PWR-1 | * Energize PZR backup heaters, as necessary. | ||
Perform a reactivity summary brief. | * Perform boration, as time permits, prior to the ramp per the following: | ||
Check control rods in auto. | o Borate per Op Aid guidance. | ||
Energize PZR backup heaters, as necessary. | |||
Perform boration, as time permits, prior to the ramp per the following: o Borate per Op Aid guidance. | |||
o As directed by the SM/designee. | o As directed by the SM/designee. | ||
Program/start ramp not to exceed 60 mw/min with DEHC in auto (DEHC graphic 5501): | * Program/start ramp not to exceed 60 mw/min with DEHC in auto (DEHC graphic 5501): | ||
ENTER desired load into REF DEMAND window. | * SELECT setpoint. | ||
SELECT LEFT ENTER. | * ENTER desired load into REF DEMAND window. | ||
VERIFY the correct value appears in the REFERENCE DEMAND window. | * SELECT LEFT ENTER. | ||
ENTER desired MW/MIN ramp rate into the RATE window. | * VERIFY the correct value appears in the REFERENCE DEMAND window. | ||
Verify the correct value appears in the RATE window. | * ENTER desired MW/MIN ramp rate into the RATE window. | ||
SELECT RIGHT ENTER. | * Verify the correct value appears in the RATE window. | ||
Notify Control Room team of the pending ramp. | * SELECT RIGHT ENTER. | ||
SELECT GO/HOLD. | * Notify Control Room team of the pending ramp. | ||
VERIFY GO/HOLD illuminates orange | * SELECT GO/HOLD. | ||
* VERIFY GO/HOLD illuminates orange. | |||
SELECT GO. | * VERIFY HOLD indicator illuminates red. | ||
VERIFY GO indicator illuminates red while the main turbine ramps. | * SELECT GO. | ||
VERIFY main turbine load begins to drop. | * VERIFY GO indicator illuminates red while the main turbine ramps. | ||
Notify TSO. | * VERIFY main turbine load begins to drop. | ||
Check PZR pressure controlling at or trending to 2235 psig. | * Notify TSO. | ||
Check PZR level controlling at or trending to program level. | * Check PZR pressure controlling at or trending to 2235 psig. | ||
* Check PZR level controlling at or trending to program level. | |||
Comments: | |||
151 NRC 1 Page 22 | |||
Scenario NRC 1 Event 7 No: No. | |||
Event 1BwOA SEC-8 Fast Ramp | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior | |||
* Maintain Tave within 4°F of Tref. | |||
* Check SG NR level. | |||
* Notify Chemistry and RP of ramp in progress | |||
* Notify SM to perform risk assessment, initiate IR, reactivity screening, notify QNE and notify other personnel. | |||
EXAMINERS NOTE: After measurable change in power (approx. 10 min.) and with Lead Examiners concurrence, insert next event. | |||
Comments: | |||
151 NRC 1 Page 23 | |||
Scenario NRC 1 Event 8&9 No: No. | |||
& | Event 1B SGTR, Loss of Offsite Power | ||
== | |||
Description:== | |||
151 NRC 1 Page 24 | Time Position Applicants Actions or Behavior CUE | ||
* RM-11 Secondary rad monitor alarms/levels rising. | |||
o SJAE/GLAND STEAM EXHAUSTER - 1PR027J. | |||
o 1B/1C MAIN STEAM LINE - 1AR022J/23J. | |||
* PZR level dropping. | |||
* PZR pressure dropping. | |||
* Charging/letdown mismatch. | |||
CREW Identify entry conditions for 1BwEP-0 REACTOR TRIP OR SAFETY INJECTION. | |||
ATC | |||
* Insert manual reactor trip and actuate SI as directed. | |||
US | |||
* Notify SM of plant status and procedure entry. | |||
* Request SM evaluation of Emergency Plan conditions. | |||
* Enter/implement 1BwEP-0 and direct operator actions of 1BwEP-0 to establish the following conditions: | |||
ATC Perform immediate operator actions of 1BwEP-0 at 1PM05J: | |||
* Verify reactor trip: | |||
* Rod bottom lights - ALL LIT. | |||
* Reactor trip & Bypass breakers - OPEN. | |||
* Neutron flux - DROPPING. | |||
BOP Perform immediate operator actions of 1BwEP-0 at 1PM02J: | |||
* Verify turbine trip: | |||
* All Turbine throttle valves - CLOSED. | |||
* All Turbine governor valves - CLOSED. | |||
BOP Perform immediate operator actions of 1BwEP-0 at 1PM01J: | |||
* Verify power to 4KV busses: | |||
* ESF Buses - BOTH ENERGIZED. | |||
CREW Perform immediate operator actions of 1BwEP-0 at 1PM05J: | |||
* Check SI Status: | |||
Comments: | |||
151 NRC 1 Page 24 | |||
Scenario NRC 1 Event 8&9 No: No. | |||
Event 1B SGTR, Loss of Offsite Power | |||
== | |||
Description:== | |||
Comments: | Time Position Applicants Actions or Behavior | ||
* SI First OUT annunciator - LIT. | |||
* SI ACTUATED Permissive Light - LIT. | |||
* SI Equipment - AUTOMATICALLY ACTUATED: | |||
o Either SI pump - RUNNING. | |||
o Either CV pump to cold leg isolation valve OPEN - 1SI8801A/B. | |||
* Manually actuate SI at 1PM05J & 1PM06J. | |||
US Direct BOP to perform Attachment B of 1BwEP-0. | |||
EXAMINERS NOTE: US and ATC will continue in 1BwEP-0 while BOP is performing Attachment B. | |||
BOP 1BwEP-0 ATTACHMENT B: | |||
* Verify FW isolated at 1PM04J. | |||
* FW pumps - TRIPPED. | |||
* FW isolation monitor lights - LIT (lights de-energized). | |||
* FW pumps discharge valves - CLOSED (or going closed) 1FW002A-C (lights de-energized). | |||
* Verify DGs running at 1PM01J: | |||
* DGs - BOTH RUNNING. | |||
* 1SX169A/B OPEN. | |||
* Dispatch operator to monitor DGs operation. | |||
* Verify Generator Trip at 1PM01J: | |||
* OCB 1-8 and 7-8 open. | |||
* PMG output breaker open. | |||
* Verify Control Room ventilation aligned for emergency operations at 0PM02J: | |||
* VC Rad Monitors - loss of power (dispatch EO to locally verify VV/VL/VW fans tripped). | |||
* Operating VC train equipment - RUNNING. | |||
* 0B Supply fan | |||
* 0B Return fan | |||
* 0B M/U fan | |||
* 0B Chilled water pump | |||
* 0B Chiller | |||
* Operating VC train dampers - ALIGNED. | |||
* M/U fan outlet damper - 0VC08Y NOT FULLY CLOSED. | |||
* 0B VC train M/U filter light - LIT. | |||
Comments: | |||
151 NRC 1 Page 25 | |||
Scenario NRC 1 Event 8&9 No: No. | |||
Event 1B SGTR, Loss of Offsite Power | |||
== Description:== | == | ||
Description:== | |||
Time Position Applicants Actions or Behavior | |||
- | * 0VC09Y - OPEN. | ||
- | * 0VC313Y - CLOSED. | ||
- | * Operating VC train Charcoal Absorber aligned for train B. | ||
* 0VC44Y - CLOSED. | |||
- | * 0VC05Y - OPEN. | ||
- | * 0VC06Y - OPEN. | ||
* Control Room pressure greater than +0.125 inches water on 0PDI-VC038 (meter de-energized, dispatch EO to perform BwOP VC-14). | |||
- | * Verify Auxiliary Building ventilation aligned for emergency operations at 0PM02J: | ||
* Two inaccessible filter plenums aligned. | |||
* Plenum A: | |||
: | * 0VA03CB - RUNNING. | ||
* 0VA023Y - OPEN. | |||
- | * 0VA436Y - CLOSED. | ||
- | * Plenum C: | ||
* 0VA03CF - RUNNING. | |||
- | * 0VA072Y - OPEN. | ||
- | * 0VA438Y - CLOSED. | ||
- | * Verify FHB ventilation aligned for emergency operation at 0PM02J: | ||
Verify | * 0VA04CB - RUNNING. | ||
* 0VA055Y - OPEN. | |||
* 0VA062Y - OPEN. | |||
* 0VA435Y - CLOSED. | |||
* Trip all running HD pumps (no power). | |||
* Initiate periodic monitoring of Spent Fuel Cooling. | |||
Verify | * Notify US Attachment B complete/manual actions taken. | ||
ATC | |||
- | * Verify ECCS pumps running at 1PM05J/1PM06J: | ||
- RUNNING. | * BOTH CV pumps - RUNNING. | ||
- | * BOTH RH pumps - RUNNING. | ||
* BOTH SI pumps - RUNNING. | |||
ATC | |||
* Verify the following at 1PM06J: | |||
Comments: | * RCFCs running in accident mode. | ||
* Group 2 RCFC accident mode status light lit. | |||
* CNMT Phase A valves closed. | |||
Comments: | |||
151 NRC 1 Page 26 | |||
Scenario NRC 1 Event 8&9 No: No. | |||
Event 1B SGTR, Loss of Offsite Power | |||
== Description:== | == | ||
Description:== | |||
Time Position Applicants Actions or Behavior ATC | |||
* Perform the following at 1PM06J: | |||
* Verify Cnmt Vent isolation: | |||
- | * Group 6 Cnmt Vent Isol monitor lights - LIT. | ||
* Verify AF system: | |||
* BOTH AF pumps - RUNNING. | |||
* AF isolation valves - 1AF13A-H OPEN. | |||
* AF flow control valves - 1AF005A-D throttled OPEN. | |||
* Verify CC pumps running: | |||
* BOTH CC pumps - RUNNING. | |||
- | * Verify SX pumps running: | ||
* BOTH SX pumps - RUNNING. | |||
- | ATC | ||
* Check if Main Steamlines Should Be Isolated: | |||
. | * S/G pressures > 640 psig at 1PM04J. | ||
* CNMT pressure < 8.2 psig at 1PM06J. | |||
. | ATC | ||
Comments: | * Check if CS is required: | ||
* CNMT pressure remained < 20 psig. | |||
ATC | |||
* Verify total AF flow: | |||
* AF flow > 500 gpm. | |||
Identify the 1B SG as the ruptured SG and isolate prior to a transition to 1BwCA-3.1 is required. (Westinghouse - CT-18) (K/A number - EPE038EA1.32 importance 4.6/4.7) | |||
* If 1B SG NR level > 10% and rising in an uncontrolled manner, then: | |||
[CT-18] | |||
* CLOSE 1AF013B. | |||
[CT-18] | |||
* CLOSE 1AF013F. | |||
* Set 1AF005B and 1AF005F pot demand = 0%. | |||
ATC | |||
* Verify ECCS valve alignment: | |||
* Group 2 cold leg injection monitor lights lit. | |||
* Verify ECCS flow: | |||
* High head SI flow >100 gpm (1FI-917). | |||
ATC | |||
* Check PZR PORVs and spray valves: | |||
* PORVs CLOSED. | |||
* PORV isolation valves - BOTH ENERGIZED. | |||
* PORV relief paths - PORVs in AUTO, PORV isolation valves OPEN. | |||
* Normal spray valves CLOSED (valve position lights de-energized). | |||
Comments: | |||
151 NRC 1 Page 27 | |||
Scenario NRC 1 Event 8&9 No: No. | |||
Event 1B SGTR, Loss of Offsite Power | |||
== Description:== | == | ||
Description:== | |||
Time Position Applicants Actions or Behavior ATC | |||
* Check RCS temperatures: | |||
* RCPs - NONE running. | |||
- | * Tcold at or trending to 557°F. | ||
o Throttle AF to control cooldown. | |||
- | ATC | ||
* Verify RCPs running (ALL RCPs de-energized). | |||
BOP | |||
* Check if SG secondary boundaries are intact: | |||
* Verify NO SG depressurizing in an uncontrolled manner or completely depressurized. | |||
- | BOP | ||
* Check if SG tubes are intact: | |||
* 1PR27J and 1B MS line indicate ABNORMAL rads. | |||
CREW Identify entry conditions for 1BwEP-3 STEAM GENERATOR TUBE RUPTURE. | |||
US | |||
* Notify SM of plant status and procedure entry. | |||
* Request SM evaluation of Emergency Plan conditions. | |||
-3.1 is required. | * Request STA evaluation of status trees. | ||
- CT-18) (K/A number | US | ||
- EPE038EA1.32 importance 4.6/4.7) | * Enter/implement 1BwEP-3 STEAM GENERATOR TUBE RUPTURE, and direct operator actions of 1BwEP-3 to establish the following conditions: | ||
ATC | |||
* Check status of RCPs: | |||
* RCPs - none running. | |||
* Identify ruptured SG 1B. | |||
- | BOP | ||
* 1B Main steam line rad monitor ABNORMAL for plant conditions. | |||
- | * 1B SG level rising uncontrollably. | ||
* Isolate ruptured SG. | |||
* Verify 1MS018B CLOSED. | |||
* Verify 1SD002E & F CLOSED. | |||
Identify the 1B SG as the ruptured SG and isolate prior to a transition to 1BwCA-3.1 is required. (Westinghouse - CT-18) (K/A number - EPE038EA1.32 importance 4.6/4.7) | |||
[CT-18] | |||
* CLOSE MSIV and MSIV bypass valve for 1B SG. | |||
* Check ruptured SG level - Narrow Range > 10%. | |||
[CT-18] | |||
* CLOSE 1AF013B&F - may have already been closed in 1BwEP-0. | |||
* Set 1AF005B and 1AF005F pot demand = 0% - may have already been performed in 1BwEP-0. | |||
Comments: | |||
151 NRC 1 Page 28 | |||
Scenario NRC 1 Event 8&9 No: No. | |||
Event 1B SGTR, Loss of Offsite Power | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior BOP | |||
* Check ruptured SG pressure > 320 psig. | |||
US | |||
* Specify RCS temperature to which the RCS must be cooled down to allow depressurization of the RCS to ruptured SG pressure. | |||
BOP | |||
* Dump steam at maximum rate via: | |||
* Intact SG PORVs. | |||
ATC | |||
* Block MS Isolation after P-11 reached. | |||
US | |||
* Dispatch EO with keys to 1SI101A/B. | |||
BOP | |||
* Check intact SG levels. | |||
* Control Aux feed flow to maintain intact SG levels between 30% and 50%. | |||
ATC | |||
* Check PZR PORVs and ISOL Valves: | |||
* PORV isolation valves - Both ENERGIZED. | |||
* PORVs CLOSED. | |||
* PORV isolation valves OPEN. | |||
BOP | |||
* Reset SI | |||
* Depress BOTH SI Reset Pushbuttons at 1PM06J. | |||
* Verify SI ACTUATED PERMISSIVE light NOT lit at 1PM05J (no power). | |||
* Verify AUTO SI BLOCKED PERMISSIVE light lit at 1PM05J (no power). | |||
BOP | |||
* Reset Phase A. | |||
* Depress BOTH Phase A Reset Pushbuttons at 1PM06J. | |||
BOP | |||
* Restore IA to Cnmt. | |||
* Check a station air compressor is running at 0PM01J. | |||
* OPEN 1IA065 and 1IA066 at 1PM11J. | |||
BOP | |||
* Check if RH pumps should be stopped. | |||
* Check RCS pressure > 325 psig. | |||
* Stop BOTH RH pumps and place in standby. | |||
BOP | |||
* Check if RCS cooldown should be stopped: | |||
* Check CETCs < required temperature. | |||
* Reduce steam flow from intact SG PORVs. | |||
* Maintain CETCs < required temperature. | |||
* Check ruptured SG pressure stable or rising. | |||
* Check RCS subcooling acceptable. | |||
Comments: | |||
151 NRC 1 Page 29 | |||
1 | Scenario NRC 1 Event 8&9 No: No. | ||
Event 1B SGTR, Loss of Offsite Power | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior ATC | |||
* Depressurize RCS to refill PZR (normal PZR spray NOT available). | |||
Depressurize RCS to restore RCS inventory prior to 1B SG PORV or safety valve water release. (Westinghouse - CT-20) (K/A number - EPE038EA1.04 importance 4.3/4.1) | |||
[CT-20] | |||
* OPEN 1 PZR PORV at 1PM05J until any of the following are met: | |||
o RCS press < ruptured SG press and PZR level > 14%. | |||
o PZR level > 68%. | |||
o RCS subcooling is unacceptable. | |||
[CT-20] | |||
* CLOSE 1 PZR PORV at 1PM05J. | |||
* Check RCS pressure rising. | |||
ATC | |||
* Check if ECCS flow should be terminated. | |||
* Check subcooling acceptable. | |||
* Check Aux feed flow >500 gpm OR NR level in >1 intact SG >10% level. | |||
* Check RCS pressure stable or rising. | |||
* Check PZR level >14%. | |||
* Stop ECCS pumps. | |||
BOP | |||
* Stop both SI pumps ATC | |||
* Stop 1 CV pump (place control switch to PULL OUT). | |||
BOP | |||
* Terminate high-head ECCS & establish charging flow. | |||
* Depress BOTH SI recirc sump reset pushbuttons at 1PM06J. | |||
ATC | |||
* Depress BOTH CV pump recirc valve reset pushbuttons at 1PM05J. | |||
* Verify CV pump recirc valves OPEN at 1PM05J: | |||
* 1CV8110, 1CV8111, 1CV8114 & 1CV8116. | |||
ATC | |||
* CLOSE 1SI8801A & B at 1PM05J. | |||
* Place 1CV182 controller demand at 0%. | |||
* OPEN 1CV8105 & 1CV8106 at 1PM05J. | |||
* Adjust 1CV121 and 1CV182 to maintain desired charging and seal injection flow. | |||
EXAMINERS NOTE: (1) All critical tasks are complete at this point; the scenario may be terminated at Lead Examiners discretion. | |||
Depressurize RCS to restore RCS inventory prior to 1B SG PORV or safety valve water release. | |||
- CT-20) (K/A number | |||
o RCS press < ruptured SG press and PZR level > 14 | |||
%. o PZR level > 68% | |||
>1 intact SG >10% level. Check RCS pressure stable or rising. Check | |||
BOP | |||
-head ECCS & establish charging flow | |||
1CV8110, 1CV8111, 1CV8114 & | |||
1CV8116. ATC | |||
%. OPEN 1CV8105 & | |||
1CV8106 at 1PM05J. Adjust 1CV121 and 1CV182 to maintain desired charging and seal injection flow. | |||
(2) The following steps address the second RCS depressurization. | (2) The following steps address the second RCS depressurization. | ||
Comments: | |||
151 NRC 1 Page 30 | |||
Scenario NRC 1 Event 8&9 No: No. | |||
Event 1B SGTR, Loss of Offsite Power | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior ATC | |||
* Control charging to maintain PZR Level stable. | |||
* Verify ECCS flow not required: | |||
* Subcooling acceptable. | |||
* PZR level > 14%. | |||
* Check RMCS: | |||
Subcooling acceptable | * Makeup set for automatic control (no power). | ||
* Check if letdown can be established: | |||
* PZR level > 27%. | |||
Makeup set for automatic control (no power). | BOP | ||
Check if letdown can be established: | * BOP establishes letdown per 1BwOA ESP-2. | ||
PZR level > 27% | ATC | ||
* Adjust charging and letdown to maintain subcooling and avoid SG overfill. | |||
-2. Adjust charging and letdown to maintain subcooling and avoid SG overfill | ATC Align Cent Chg pump suction to VCT: | ||
* Check VCT level > 37%. | |||
Check VCT level > 37 | * Check VCT pressure 15-65 psig. | ||
%. Check VCT pressure 15 | * Open 1CV112B and 1CV112C. | ||
-65 psig. Open 1CV112B and 1CV112C | * Close 1CV112D and 1CV112E. | ||
* Check 1CV8804A - closed. | |||
* Check SI and cent chg pumps suction header crosstie valves: | |||
- closed. Check SI and cent chg pumps suction header crosstie valves: | o 1SI8807A and B - closed; or o 1SI8924 - closed | ||
o 1SI8807A and B | * Check if SI Accumulators should be isolated: | ||
- closed; or o 1SI8924 - closed | * RCS pressure < 800 psig - NO - continue with step 29. | ||
RCS pressure < 800 psig | * Control RCS pressure and charging flow to minimize RCS to Secondary Leakage: | ||
- NO - continue with step 29. Control RCS pressure and charging flow to minimize RCS to Secondary Leakage: | o PZR level < 27% and 1B SG level rising: raise charging flow and depressurize RCS using a PZR PORV. | ||
o PZR level < 27% and | o PZR level 27-50% and 1B SG level rising: depressurize RCS using a PZR PORV. | ||
o PZR level 27 | o PZR level 50-68% and 1B SG level rising: depressurize RCS using a PZR PORV and reduce charging flow. | ||
-50% and | o PZR level >68% and 1B SG level rising: reduce charging flow. | ||
o PZR level 50 | EXAMINERS NOTE: Terminate the scenario at Lead Examiners discretion. | ||
-68% and | |||
o PZR level >68% and | |||
(Final) | (Final) | ||
Comments: | |||
151 NRC 1 Page 31 | |||
1C MSIV failed open 1D MSIV failed open 1A CS pump fails to start K643 1B CS slave relay fails to actuate 1 None N-BOP, US Lower reactive load 1 KV. 2 IMF RX10A 0 15 I-ATC, US | Simulation Facility Braidwood Scenario Operating Test No.: 15-1 NRC No.: | ||
, 1PT-505 , fails | NRC 2 Examiners: ______________________ Applicant: ____________________ SRO | ||
, 1LT-539 , fails low 5 IMF FW35A | ______________________ ____________________ RO | ||
______________________ ____________________ BOP Initial Conditions: IC-31 Turnover: Unit 1 is operating at 90% power, steady state, equilibrium xenon, BOL. Online risk is green. | |||
Following completion of turnover, coordinate with Unit 2 and lower total station reactive load by a total of 2 KV in accordance with BwOP MP-23. The 1B HD pump was taken out of service 3 days ago and will NOT be returned to service for an additional 5 days. | |||
Event Malf. No. Event Event No. Type* Description Preload IMF MS01A 100 1A MSIV failed open IMF MS01B 100 1B MSIV failed open IMF MS01C 100 1C MSIV failed open IMF MS01D 100 1D MSIV failed open IMF CS01A 1A CS pump fails to start IRF RP63 OUT K643 1B CS slave relay fails to actuate 1 None N-BOP, US Lower reactive load 1 KV. | |||
2 IMF RX10A 0 15 I-ATC, US Turbine impulse pressure channel, 1PT-505, TS-US fails low 3 IMF CV10 0 30 I-ATC, US 1CV121 controller failure low 4 IMF RX06K 0 15 I-BOP, US 1C SG NR level transmitter, 1LT-539, fails low TS-US 5 IMF FW35A C-BOP, US 1A Heater Drain Pump trip 6 None R-ATC, US Turbine runback (only 1 HD pump running) 7 IMF MS07C 4 M-ALL Uncontrolled depressurization of all SGs 8 Preload C-ALL Failure of both CS trains to start automatically | |||
*(N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient | |||
SCENARIO OVERVIEW Unit 1 is operating at 90% power, steady state, equilibrium xenon, BOL. Online risk is green. Following completion of turnover, coordinate with Unit 2 and lower total station reactive load by a total of 2 KV in accordance with BwOP MP-23. The 1B HD pump was taken out of service 3 days ago and will NOT be returned to service for an additional 5 days. | |||
-23. The 1B HD pump was taken out of service 3 days ago and will NOT be returned to service for an additional 5 days. | After completing shift turnover and relief, the BOP will lower Unit 1 reactive load 1 KV in accordance with BwOP MP-23. | ||
After completing shift turnover and relief, the BOP will lower Unit 1 reactive load 1 KV in accordance with BwOP MP | After lowering reactive load, First Stage Turbine Impulse Pressure channel, 1PT-505, will fail low. After the crew diagnoses the failure of 1PT-505, the ATC will take manual control of rods after verifying turbine load stable. Initial ATC response is per hard card 1BwPR 1-10-RD, followed by entry into 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL, ATTACHMENT D. Tech Spec 3.3.1 Conditions A and P will be entered. The ATC will return rod control to automatic after verifying Tave and Tref are stable and within 1°F. | ||
-23. After lowering reactive load, First Stage Turbine Impulse Pressure channel | After the 1PT-505 failure is addressed, 1CV121, Charging Pump Flow Control Valve Controller 1FK-121, will fail to 0% demand. The 1CV121 valve will fully close and pressurizer level will drop. The crew will take actions to stabilize the plant by taking manual control of the 1FK-121 controller and restore charging flow. | ||
, 1PT-505 , will fail low. After the crew | After the 1FK-121 failure has been addressed, 1C SG NR level transmitter, 1LT-539, will fail low. | ||
-505, the ATC will take manual control of rods after verifying turbine load stable. Initial ATC response is per hard card 1BwPR 1-10-RD, followed by entry into 1BwOA INST | 1FW530, Feedwater Regulating Valve, will open and 1C SG level will rise. The BOP will take manual control of 1C SG level per hard card 1BwPR 1-15-SG and stabilize 1C SG level. 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL, ATTACHMENT E, will be entered. The BOP will restore 1C SG level control to automatic after 1C SG level is restored to normal and an operable 1C SG NR level controlling channel is selected. Tech Specs 3.3.1 Conditions A and E and 3.3.2 Conditions A and D are applicable. | ||
-2 | After the 1LT-539 failure has been addressed, 1A Heater Drain Pump will trip. 1BwOA SEC-1 SECONDARY PUMP TRIP, ATTACHMENT C, will be entered. The BOP will initiate a turbine load reduction to 780 MW at 20 MW/minute. The ATC will borate the RCS as necessary during the load reduction. | ||
As the crew is reducing load to address the 1A HD pump trip, a large steam break will occur on the 1C MS line. When containment pressure reaches 20 psig, Phase B actuates but the CS pumps do not start. | |||
-121 , will fail to 0% demand. | The crew should manually realign train B CS valves which will start the 1B CS pump. Operators should transition to 1BwEP-2 FAULTED STEAM GENERATOR ISOLATION and recognize that the MSIVs have failed to close and that an uncontrolled depressurization of all SGs is in progress. The crew will transition to 1BwCA-2.1 UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS where they will throttle AF flow to the SGs. Entry into 1BwFR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK will be required when the crew throttles AF flow to 45 gpm per SG; however, a note in 1BwFR-H.1 directs that the procedure should NOT be performed. The crew will continue in 1BwCA-2.1. | ||
The 1CV121 valve will fully close and pressurizer level will drop. | Completion criteria is stopping the RH pumps in 1BwCA-2.1. | ||
The crew will take actions to stabilize the plant by taking manual | Critical Tasks | ||
-121 controller and restore charging flow. | : 1. Manually actuate one train of containment spray prior to transition out of 1BwEP-0. | ||
After the 1FK-121 failure has been addressed , 1C SG NR level transmitter | (Westinghouse - CT-3) (K/A number - 013000A4.01 importance - 4.5/4.8) | ||
, 1LT-539 , will fail low. 1FW530, Feedwater Regulating Valve, will open and 1C SG level will rise. The BOP will take manual control of 1C SG level per hard card | : 2. Manually control AF flowrate to 45 gpm for each SG before orange path in integrity occurs. | ||
-2 | (Westinghouse - CT-33) (K/A number - EPEE12EA1.3 importance - 3.4/3.9) 151 NRC 2 Page 2 | ||
-539 failure has been addressed | |||
, 1A Heater Drain Pump will trip. 1BwOA SEC | |||
-1 | |||
As the crew is reducing load to address the 1A HD pump trip , a | |||
-H.1 | |||
-H.1 directs that the procedure should NOT be performed. | |||
The crew will continue in 1BwCA | |||
-2.1. Completion criteria is stopping the RH pumps in 1BwCA | |||
-2.1. Critical Tasks | |||
: 1. Manually actuate one train of containment spray prior to transition out of 1BwEP | |||
-0. | |||
- CT-3) (K/A number | |||
- 013000A4.01 | |||
(Westinghouse | |||
- CT-33) (K/A number | |||
- EPEE12EA1.3 importance | |||
- 3.4/3.9) 151 | |||
Establish the conditions of IC | SIMULATOR SETUP GUIDE | ||
-31 , 90% power, steady state, equilibrium xenon, BOL. | * Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST. | ||
Verify/place OA & OC VA plenums in service, 0B VA plenum in standby. | * Establish the conditions of IC-31, 90% power, steady state, equilibrium xenon, BOL. | ||
Ensure main generator VARS approx. 230 MVARs out. | * Verify/place OA & OC VA plenums in service, 0B VA plenum in standby. | ||
Complete items on Simulator Ready for Training Checklist. | * Ensure main generator VARS approx. 230 MVARs out. | ||
* Complete items on Simulator Ready for Training Checklist. | |||
* Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario. | |||
* Place simulator in RUN and allow simulator to run during board walk down and turnover. | |||
* Run caep 151 NRC 2 SETUP from disk and verify the following actuate: | |||
* IMF MS01A 100 | |||
* IMF MS01B 100 | |||
* IMF MS01C 100 | |||
* IMF MS01D 100 | |||
* IMF CS01A | |||
* IRF RP63 OUT | |||
* Verify SER and RM-11 printers are clear of data. | |||
* Place the 1B HD pump C/S in PULL OUT and place the 1B HD pump OOS. | |||
* Provide students with turnover sheets, and a copy of BwOP MP-23. | |||
151 NRC 2 Page 3 | |||
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Lower total station reactive load 2 KV. | |||
Acknowledge as Shift Manager the start and completion of procedure. | |||
Acknowledge as Unit 2, the need to lower Unit 2 reactive load by 1 KV (50 MVARs). | |||
Acknowledge as Unit 2 | |||
, the need to lower Unit 2 reactive load by 1 KV (50 MVARs). | |||
If asked, eGPM website is down. | If asked, eGPM website is down. | ||
If asked, lowering reactive load has been logged per BwOP MP | If asked, lowering reactive load has been logged per BwOP MP-23. | ||
-23. If contacted, acknowledge as a generation dispatcher (Kerry Koch) completion of reactive load adjustment. | If contacted, acknowledge as a generation dispatcher (Kerry Koch) completion of reactive load adjustment. | ||
Event 2: Turbine Impulse Pressure channel 1PT-505 failed low. | |||
Event 2: | Insert IMF RX10A 0 15 to fail 1PT-505 low over 15 seconds. | ||
-505 failed low | As SM, acknowledge the failure, 1BwOA INST-2 entry, request for E Plan evaluation, LCO 3.3.1 Conditions A | ||
. | & P entry, and requests for on-line risk assessment, maintenance support, and IR initiation. | ||
Insert IMF RX10A 0 15 to fail 1PT | As SM, if requested support for tripping bistable in AEER, report that AEER bistable is not to be tripped until work analyst and NSO support can be obtained (in approx. 2 hours) and that the abnormal operating procedure should be continued. | ||
-505 low over 15 seconds. | |||
As SM, acknowledge the failure, 1BwOA INST | |||
-2 entry, request for E Plan evaluation, LCO 3.3.1 Conditions A & P entry, and requests for | |||
As SM, if requested support for tripping bistable in AEER, report that AEER bistable is not to be tripped until work analyst and NSO support can be obtained (in approx. 2 hours) and that the abnormal operating procedure should be continued. | |||
As an extra NSO, if asked, report/perform the following concerning AMS: | As an extra NSO, if asked, report/perform the following concerning AMS: | ||
Initially: Operating Bypass switch (SW12) is in OFF. | * Initially: Operating Bypass switch (SW12) is in OFF. | ||
Operating Bypass switch (SW12) to TIP 1: perform the following: | * Operating Bypass switch (SW12) to TIP 1: perform the following: | ||
IMF | * IMF PN0470 ON to turn on annunciator 1-18-E11. | ||
-TRIP: perform the following: | * Operating Bypass Test Input (SW11) to TEST-TRIP: perform the following: | ||
IRF RX149 TRIP to trip AMS C | * IRF RX149 TRIP to trip AMS C-20 for 1PT-505. | ||
-20 for 1PT | Event 3: 1FK121 Controller failure. | ||
-505. Event 3: | Insert IMF CV10 0 30 to fail 1CV121 closed over 30 seconds. | ||
If dispatched as EO to investigate, wait two minutes and report no visible damage to 1CV121 valve. 1CV121 appears to be failed closed and responding correctly in manual (if asked for feedback to manual operations). | |||
If dispatched as EO to investigate, wait two minutes and report no visible damage to 1CV121 valve. 1CV121 appears to be failed closed and responding correctly in manual (if asked for feedback to manual operations). Acknowledge as Shift Manager the failure, request for maintenance support, and IR request. | Acknowledge as Shift Manager the failure, request for maintenance support, and IR request. | ||
151 NRC 2 Page 4 | |||
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 4: 1C SG NR level transmitter 1LT-539 fails low. | |||
-539 fails low. | Insert IMF RX06K 0 15 to fail 1LT-539 low over a 15 second period. | ||
Acknowledge as Shift Manager the failure, 1BwOA INST-2 entry, LCOAR entry, on-line risk assessment, EAL evaluation, request for maintenance support, and IR request. | |||
Insert IMF RX06K 0 15 to fail 1LT | |||
-539 low over a 15 second period. | |||
Acknowledge as Shift Manager the failure, 1BwOA INST-2 entry, LCOAR entry, on | |||
-line risk assessment, EAL evaluation, request for maintenance support, and IR request. | |||
Acknowledge as Shift Manager on line risk assessment, request for IR, evaluation for reactivity screening, QNE and personnel notifications, and evaluation of return to full power operation. | Acknowledge as Shift Manager on line risk assessment, request for IR, evaluation for reactivity screening, QNE and personnel notifications, and evaluation of return to full power operation. | ||
If lead examiner desires the bistable bypassed, participate in brief and perform the following: | If lead examiner desires the bistable bypassed, participate in brief and perform the following: | ||
To bypass the required bistables, participate in brief and perform the following (SDG RX19): | |||
* As extra NSO contact Unit 1 (X2209). | |||
* Insert the following: | |||
* MRF RP20 OPEN (open protection cabinet #1 door). | |||
* IRF RX063A BYPASS (Bypass LB 539A). | |||
* IRF RX063B BYPASS (Bypass LB 539B). | |||
* MRF RP20 CLOSE (close protection cabinet #1 door). | |||
Event 5: 1A Heater Drain Pump trip. | |||
Insert IMF FW35A As SM, acknowledge the failure, 1BwOA SEC-1 entry, request for E Plan evaluation, and requests for on line risk assessment, maintenance support, and IR initiation. | |||
If dispatched as EO, wait 2 minutes, then report 1A Heater Drain pump has a ground overcurrent flag at breaker cubicle. If asked, the 1A HD pump has no issues locally. | |||
If dispatched to the 1B HD pump breaker, wait 2 minutes, then report that the breaker appears to be damaged. The breaker is not fully in the cubicle and the frame appears bent. If asked, the 1B HD pump has no issues locally. | |||
Event 6: Turbine runback (only 1 HD pump running). | |||
As SM acknowledge the turbine runback. | |||
Acknowledge as Generation Dispatch, the initiation of ramp. | |||
151 NRC 2 Page 5 | |||
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 7/8: Uncontrolled depressurization of ALL SGs; Auto SI and CS failures. | |||
Insert IMF MS07C 4 to initiate a 4 Mlb/hr steam break on the 1C SG. | |||
Acknowledge as SM procedure changes, E Plan evaluations, and STA request. | Acknowledge as SM procedure changes, E Plan evaluations, and STA request. | ||
After STA requested, as STA report CSF status: | After STA requested, as STA report CSF status: Red Path on heat sink when AF throttled to 45 gpm per SG, orange on integrity if RCS cold leg temperature < 240°F. | ||
If dispatched as EO to investigate 1A CS pump, wait 3 minutes, then report ground overcurrent flag at breaker cubicle. | If dispatched as EO to investigate 1A CS pump, wait 3 minutes, then report ground overcurrent flag at breaker cubicle. | ||
151 NRC 2 Page 6 | |||
151 NRC 2 Page | |||
Scenario NRC 2 Event 1 No: No. | |||
Event Lower reactive load 1 KV on Unit 1 (U-2 will also lower 1 KV) | |||
== Description:== | == | ||
Description:== | |||
Time Position Applicants Actions or Behavior CUE | |||
* From turnover, lower total station reactive load 2 KV in accordance with BwOP MP-23 ADJUSTING REACTIVE LOAD. | |||
Time Position | US Direct BOP to perform BwOP MP-23. | ||
EXAMINERS NOTE: (1) The limitation and action associated with BwOP MP-23 of logging the reactive load change has been logged. | |||
-23. | (2) Adjusting the reactive load 1 KV correlates to 50 MVARS on 1VI-MP006. | ||
-23 of logging the reactive load change has been logged. | BOP | ||
(2) Adjusting the reactive load 1 KV correlates to 50 MVARS on 1VI | * Refer to BwOP MP-23. | ||
-MP006. BOP | * Verify MVAR change will not exceed Generator Capability Curve in 1BwGP 100-3A6. | ||
-23. Verify MVAR change will not exceed Generator Capability Curve in 1BwGP 100 | * Monitor PPC point Q2801 (preferred), 1VI-MP006, main generator output VARS, and switchyard bus voltage during the MVARs adjustment. | ||
-3A6. Monitor PPC point Q2801 (preferred), 1VI | * Perform the following at 1PM01J: | ||
-MP006, main generator output VARS, and switchyard bus voltage during the MVARs adjustment. | * Contact Unit 2 and coordinate lowering total station reactive load by 2 KV. | ||
Perform the following at 1PM01J: | * Place volt adjust C/S to lower (may be done intermittently). | ||
Contact Unit 2 and coordinate lowering total station reactive load by 2 KV. | * Release volt adjust C/S when Q2801 has dropped 50 MVARS (1 KV). | ||
Place volt adjust C/S to lower (may be done intermittently) | o Inform US BwOP MP-23 is complete. | ||
US | |||
-23 is complete. | * Acknowledge report. | ||
US | |||
o Notify SM that BwOP MP-23 is complete. | o Notify SM that BwOP MP-23 is complete. | ||
o Notify Generation Dispatch that BwOP MP-23 is complete. | o Notify Generation Dispatch that BwOP MP-23 is complete. | ||
ATC o Peer check actions of BOP. | ATC o Peer check actions of BOP. | ||
o Monitor remainder of MCBs. | o Monitor remainder of MCBs. | ||
EXAMINERS NOTE: After BwOP MP-23 is complete and with Lead Examiners concurrence, enter next event. | |||
-23 is complete and with | Comments: | ||
151 NRC 2 Page 7 | |||
Scenario NRC 2 Event 2 No: No. | |||
Event Turbine Impulse Pressure Channel, 1PT-505, failed low | |||
== Description:== | == | ||
Description:== | |||
Time Position Applicants Actions or Behavior CUE | |||
* Annunciator TAVE CONT DEV HIGH (1-14-D1) | |||
Control rod inward motion | * 1PI-505, First Stage Pressure, lowering. | ||
* Control rod inward motion. | |||
* 1TR-0412, Auct Tave/Tref recorder, Tref indication lowering. | |||
* 1SI-412, Rod Speed, indicates 72 step per minute. | |||
-505 has failed low | ATC | ||
* Recognize 1PT-505 has failed low. | |||
* Report failure to US. | |||
Check turbine load stable. | * Review hard card 1BwPR 1-10-RD and take the following actions: | ||
Place rod control in manual. | * Check turbine load stable. | ||
Check rods NOT moving. | * Place rod control in manual. | ||
o Refer to BwARs as time permits | * Check rods NOT moving. | ||
o Refer to BwARs as time permits. | |||
-2 | BOP | ||
* Verifies turbine load stable. | |||
CREW | |||
* Identify entry conditions for 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL. | |||
-2 "OPERATION WITH A FAILED INSTRUMENT | US | ||
-2 to establish the following conditions: | * Notify SM of plant status and procedure entry. | ||
Direct ATC to place rod control in manual (previously performed). | * Request SM to evaluate Emergency Plan conditions. | ||
o If | * Implement 1BwOA INST-2 "OPERATION WITH A FAILED INSTRUMENT CHANNEL," | ||
BOP | ATTACHMENT D "TURBINE IMPULSE PRESSURE CHANNEL FAILURE" and direct operator actions of 1BwOA INST-2 to establish the following conditions: | ||
* Direct ATC to place rod control in manual (previously performed). | |||
o If PZR pressure drops below 2209 psig, enter Tech Spec 3.4.1 Condition A until pressure is > 2209 psig. | |||
BOP | |||
* Restore steam dumps: | |||
* Check C-7 NOT lit. | |||
100%. BOP | * Place 1PK-507 in manual. | ||
-505. | * Lower 1PK-507 demand to 0%. | ||
* Place steam dump mode select switch to STM PRESS mode. | |||
* Place 1PK-507 in auto. | |||
* Check Reactor Power <100%. | |||
BOP | |||
* Place Turbine Impulse Pressure Defeat Switch, 1PS505Z, to DEFEAT P-505. | |||
Comments: | Comments: | ||
151 NRC 2 Page | 151 NRC 2 Page 8 | ||
Scenario NRC 2 Event 2 No: No. | |||
Event Turbine Impulse Pressure Channel, 1PT-505, failed low | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior ATC | |||
* Check if rod control can be placed in auto: | |||
* C5 NOT lit. | |||
* Tave/Tref stable and within 1°F (check T0494 or 1TR-0412). | |||
o If control rods need to be adjusted to restore Tave - Tref within 1°F, perform the following: | |||
o Obtain SM concurrence for reactivity change. | |||
o Adjust Tave - Tref within 1°F using control rods, or o Adjust Tave - Tref within 1°F by dilution/load drop. | |||
* Place rod control in auto. | |||
ATC | |||
* Check P13 interlock: | |||
* Turbine power > 10% - P13 NOT lit. | |||
o Trip bistables (bistables will NOT be tripped at this time). | |||
BOP | |||
* Check status of AMS: | |||
* Operating Bypass switch (SW12) at 1PA54J - OFF. | |||
* Locally trip AMS bistable at 1PA54J - C-20. | |||
US | |||
* Determine Tech Spec 3.3.1 Conditions A and P are applicable. | |||
* Contact SM to perform risk assessment, initiate IR, perform reactivity screening, notify QNE and contact personnel to investigate/correct instrument failure. | |||
EXAMINERS NOTE: After the above actions by the US and with Lead Examiners concurrence, insert next event. | |||
Comments: | Comments: | ||
151 NRC 2 Page | 151 NRC 2 Page 9 | ||
== Description:== | Scenario NRC 2 Event 3 No: No. | ||
Event 1CV121 controller fails low in auto | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior CUE | |||
Charging flow, 1FI-121A , lowering. PZR level , 1LI-459A/460A/461 | * Annunciator CHG LINE FLOW HIGH LOW (1-9-D3) | ||
, lowering. ATC | * Annunciator REGEN HX LTDWN TEMP HIGH (1-9-A1) | ||
Determine loss of charging flow. | * Annunciator RCP SEAL WTR INJ FLOW LOW (1-7-B2) | ||
Identify 1FK-121 is failing low. | * 1FK-121 controller output failed low. | ||
Report failure to US. | * Charging flow, 1FI-121A, lowering. | ||
ATC | * PZR level, 1LI-459A/460A/461, lowering. | ||
Place 1FK-121, 1CV121 Controller, in manual. | ATC | ||
Raise demand on 1FK | * Perform the following at 1PM05J: | ||
-121. Monitor charging flow and pressurizer level and return level to normal. | * Determine loss of charging flow. | ||
Maintain charging flow by operating 1FK | * Identify 1FK-121 is failing low. | ||
-121 in manual. | * Report failure to US. | ||
ATC o Reference BwARs as time permits. | ATC | ||
o If required, isolate letdown per BwAR or use hard card 1BwPR 1 LD: o Close 1CV8149A-C. o Close 1CV459/460. | * Perform the following at 1PM05J: | ||
* Place 1FK-121, 1CV121 Controller, in manual. | |||
* Raise demand on 1FK-121. | |||
* Monitor charging flow and pressurizer level and return level to normal. | |||
* Maintain charging flow by operating 1FK-121 in manual. | |||
ATC o Reference BwARs as time permits. | |||
o If required, isolate letdown per BwAR or use hard card 1BwPR 1-9-LD: | |||
o Close 1CV8149A-C. | |||
o Close 1CV459/460. | |||
o Adjust 1CV121 and 1CV182, as required. | o Adjust 1CV121 and 1CV182, as required. | ||
o Close 1CV8105/1CV8106. | o Close 1CV8105/1CV8106. | ||
Recognize 1FK | * Recognize 1FK-121 output failed low. | ||
-121 output failed low. | |||
o Dispatch operator to investigate cause of failure. | o Dispatch operator to investigate cause of failure. | ||
EXAMINERS NOTE: THE CREW MAY ELECT TO ENTER 1BwOA PRI-15 LOSS OF NORMAL CHARGING. SEE NEXT PAGE FOR ACTIONS OF 1BwOA PRI-15. | |||
-15 | US o Direct actions of 1BwOA PRI-15 (see note above). | ||
* Direct/ensure ATC takes manual control of 1FK-121 and returns charging flow to normal. | |||
-15 (see note above | o Inform SM of FK-121 failure. | ||
). Direct/ensure ATC takes manual control of 1FK | US | ||
-121 and returns charging flow to normal. o Inform SM of FK | * Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure. | ||
-121 failure. | US o IF PZR pressure drops below 2209 psig, enter Tech Spec 3.4.1 Condition A. | ||
US | |||
US o IF PZR pressure drops below 2209 psig, enter Tech Spec 3.4.1 Condition A. | |||
Comments: | Comments: | ||
151 NRC 2 Page | 151 NRC 2 Page 10 | ||
Scenario NRC 2 Event 3 No: No. | |||
Event 1CV121 controller fails low in auto | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior ATC 1BwOA PRI-15 ACTIONS (APPLICABLE IF CREW ENTERS THE PROCEDURE): | |||
o Status of Cent Chg Pumps (one running). | o Status of Cent Chg Pumps (one running). | ||
o Check Cent Chg pump parameters (none fluctuating). | o Check Cent Chg pump parameters (none fluctuating). | ||
Line 1,184: | Line 1,288: | ||
o Either 1CV8146 or 1CV8147 Open (one open). | o Either 1CV8146 or 1CV8147 Open (one open). | ||
o 1CV8324A or 1CV8324B Open (one open). | o 1CV8324A or 1CV8324B Open (one open). | ||
o BOTH 1CV8105 and 1CV8106 Open (if previously closed, crew re | o BOTH 1CV8105 and 1CV8106 Open (if previously closed, crew re-opens valves). | ||
-opens valves). o Check charging flow established (established). o Check normal letdown isolated (if previously isolated, crew implements 1BwOA ESP-2 to re-establish normal letdown). | o Check charging flow established (established). | ||
BOP o Check normal letdown isolated (if previously isolated, crew implements 1BwOA ESP-2 to re-establish normal letdown). | |||
o Notify SM to perform risk evaluation, initiate IR and make external notifications. | o Notify SM to perform risk evaluation, initiate IR and make external notifications. | ||
o Evaluate Tech Specs/TRM (none applicable). | o Evaluate Tech Specs/TRM (none applicable). | ||
o Return to procedure and step in effect. | o Return to procedure and step in effect. | ||
BOP 1BwOA ESP-2 ACTIONS (APPLICABLE IF CREW ISOLATED LETDOWN) in 1BwOA PRI-15: o Restore normal letdown using 1BwOA ESP | BOP 1BwOA ESP-2 ACTIONS (APPLICABLE IF CREW ISOLATED LETDOWN) in 1BwOA PRI-15: | ||
-2 | o Restore normal letdown using 1BwOA ESP-2 REESTABLISHING LETDOWN DURING ABNORMAL CONDITIONS as directed by performing the following at 1PM05J: | ||
o Close letdown orifice isolation valves (1CV8149A-C). | |||
-C). o Close letdown line isolation valves (1CV459 and 1CV460). | o Close letdown line isolation valves (1CV459 and 1CV460). | ||
o Verify either 1CV8401A or B open. | o Verify either 1CV8401A or B open. | ||
o Open | o Open 1CV8324A and 1CV8389A. | ||
o Letdown CNMT isolation valves 1CV8152 and 1CV8160 open. | |||
o BTRS Mode Selector switch OFF light LIT. | o BTRS Mode Selector switch OFF light LIT. | ||
o Place 1CV131 controller in manual at 40% demand. | o Place 1CV131 controller in manual at 40% demand. | ||
o Place 1CC130 controller in manual at 60% demand. | o Place 1CC130 controller in manual at 60% demand. | ||
o 1CV8105/1CV8106 open. | o 1CV8105/1CV8106 open. | ||
o Adjust 1CV121 and 1CV182 to establish at least 100 gpm charging with seal injection 8 | o Adjust 1CV121 and 1CV182 to establish at least 100 gpm charging with seal injection 8-13 gpm per RCP. | ||
-13 gpm per RCP. | o Open 1CV459 and 1CV460. | ||
o Open 1CV459 and 1CV460. o Re-establish 120 gpm letdown flow by opening appropriate orifice isolation valves (1CV8149A and either 1CV8149B or C). | o Re-establish 120 gpm letdown flow by opening appropriate orifice isolation valves (1CV8149A and either 1CV8149B or C). | ||
o Adjust 1CV131 and 1CC130 to restore letdown to 360 psig and 90 | o Adjust 1CV131 and 1CC130 to restore letdown to 360 psig and 90-115oF. | ||
- | o Place controllers in auto when desired (1CV131 and 1CC130). | ||
o Verify 1PR06J restored (RM | o Verify 1PR06J restored (RM-11). | ||
-11). o Return to procedure and step in effect. | o Return to procedure and step in effect. | ||
Comments: | Comments: | ||
151 NRC 2 Page | 151 NRC 2 Page 11 | ||
Scenario NRC 2 Event 3 No: No. | |||
Event 1CV121 controller fails low in auto | |||
== | |||
: | Description:== | ||
Time Position Applicants Actions or Behavior BOP 1BwOP CV-17 ACTIONS (APPLICABLE IF CREW ISOLATED LETDOWN): | |||
o Perform the following at 1PM05J to establish normal letdown flow through the 1A letdown heat exchanger in accordance with BwOP CV-17 ESTABLISHING AND SECURING NORMAL AND RH LETDOWN FLOW (N/A if excess letdown established): | |||
* Verify/close 1CV8149A, B, & C, letdown orifice isolation valves. | |||
o Contact operators to locally verity CC locally aligned to 1A letdown HX. | |||
* Place 1PK-131, letdown line pressure controller, in manual and raise demand to 40%. | |||
* Place 1CC-130A, letdown HX outlet temperature controller, in manual and raise demand to 60%. | |||
* Open 1CV8152 & 1CV8160, letdown line CNMT isolation valves. | |||
* Open 1CV459 & 1CV460, letdown line isolation valves. | |||
* Open 1CV8324A, charging to regen HX 1A isolation valve. | |||
* Open 1CV8389A, letdown to regen HX 1A isolation valve. | |||
* Verify OFF light is lit above BTRS mode selector C/S (signifies that 1CV381B is OPEN & 1CV381A is CLOSED. | |||
* Verify/open 1CV8401A, letdown HX 1A inlet valve. | |||
* Verify/closed 1CV8145, PZR aux spray valve. | |||
* Verify/open 1CV8147, charging to loop 1A isolation valve. | |||
* Open 1CV8105 & 1CV8106, charging line CNMT isolation valves. | |||
* Control 1FK-121, CV pumps flow control valve, in manual to raise letdown flow to 100 gpm while concurrently adjusting 1CV182, charging header backpressure control valve, to control RCP seal injection 8-13 gpm per RCP. | |||
* Open 1CV8149A/B/C, letdown orifice isolation valves, as necessary to establish desired letdown flow while concurrently and controlling 1PK-131, letdown line pressure controller, in manual to maintain letdown pressure 360-380 psig. | |||
* Control 1CC130A, letdown HX outlet temperature controller, in manual to maintain letdown temperature 90-115°F. | |||
* Place 1FK-121, 1PK-131 & 1CC130A in auto. | |||
* Verify 1PR06J in service at the RM-11 console. | |||
EXAMINERS NOTE: After the crew restores charging flow and with Lead Examiners concurrence, insert next event. | |||
Comments: | Comments: | ||
151 NRC 2 Page | 151 NRC 2 Page 12 | ||
== Description:== | Scenario NRC 2 Event 4 No: No. | ||
Event 1C SG NR level transmitter, 1LT-539, fails low | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior CUE | |||
* Annunciator S/G 1C LEVEL DEVIATION HIGH LOW (1-15-C9) | |||
-2 RX TRIP ALERT (1-15-C5) | * Annunciator S/G 1C LVL LO-2 RX TRIP ALERT (1-15-C5) | ||
BOP | * SG 1C feed flow and NR level rising. | ||
Identify 1LI | BOP | ||
-539 indicates lowering SG NR level at 1PM04J. | * Determine SG 1C feed flow and/or NR level rising at 1PM04J. | ||
Review hard card 1BwPR 1 | * Identify 1LI-539 indicates lowering SG NR level at 1PM04J. | ||
- | * Review hard card 1BwPR 1-15-SG and performs the following actions: | ||
Place 1C FRV controller in manual. | * Place 1C FRV controller in manual. | ||
Restore 1C SG level to pre | * Restore 1C SG level to pre-failed value. | ||
-failed value. | * Determine failed input channel. | ||
Determine failed input channel. | * Verify/select operable channel (L-558). | ||
Verify/select operable channel (L | o Refer to BwARs as time permits. | ||
-558). o Refer to BwARs as time permits. | CREW | ||
CREW | * Identify entry conditions for 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL. | ||
-2 | US | ||
* Notify Shift Manager of SG level channel failure. | |||
Implement 1BwOA INST | * Implement 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL, ATTACHMENT E NARROW RANGE SG LEVEL CHANNEL FAILURE, and direct operator actions of 1BwOA INST-2 to establish the following conditions: | ||
-2 | BOP | ||
-2 to establish the following conditions: | * Stabilize 1C SG level at 1PM04J (actions performed previously). | ||
BOP | |||
o Place 1FK-530, FW Reg Valve 1FW530 controller, in manual. | o Place 1FK-530, FW Reg Valve 1FW530 controller, in manual. | ||
o Lower demand on 1FK | o Lower demand on 1FK-530 sufficiently to lower FW flow to restore 1C SG level. | ||
-530 sufficiently to lower FW flow to restore 1C SG level. | o Operate 1FK-530 in manual to stabilize 1C SG level in the normal operating band. | ||
o Operate 1FK | o Select an operable channel (L-558). | ||
-530 in manual to stabilize 1C SG level in the normal operating band. | * Establish automatic level control by placing 1FK-530 in auto when SG level restored to program level. | ||
o Select an operable channel (L-558). Establish automatic level control by placing 1FK | ATC | ||
-530 in auto when SG level restored to program level. | * Perform the following: | ||
ATC | * Check Rx power < 100% - Monitor reactor power at 1PM05J/PPC. | ||
Check Rx power < 100% | * Assist US by making notifications. | ||
- Monitor reactor power at 1PM05J/PPC. | |||
Assist US by making notifications. | |||
o Refer to BwARs as time permits. | o Refer to BwARs as time permits. | ||
EXAMINERS NOTE: The following steps will be performed if the Lead Examiner desires to observe bypassing bistables. | |||
Comments: | Comments: | ||
151 NRC 2 Page | 151 NRC 2 Page 13 | ||
Scenario NRC 2 Event 4 No: No. | |||
Event 1C SG NR level transmitter, 1LT-539, fails low | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior US o Perform pre-job brief per HU-AA-1211 for bistable bypassing. | |||
o Complete 1BwOL 3.3.1/3.3.2, Attachment A, INSTRUMENT CONDITION TRACKING LOG. | |||
BOP o Locally bypass bistables for 1C SG level channel 1LT-539 by placing in BYPASS/ | |||
BOP verifies correct bistable operation: | |||
o P-14/LO-2 Rx Trip/AF Pump Start. | |||
US | |||
* Determine AMS channel NOT affected. | |||
* Determine Tech Spec 3.3.1 Conditions A and E are applicable. | |||
* Determine Tech Spec 3.3.2 Conditions A and D are applicable. | |||
* Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure, and make other notifications. | |||
EXAMINERS NOTE: After the above actions by the US and with Lead Examiners concurrence, insert next event. | |||
Comments: | Comments: | ||
151 NRC 2 Page | 151 NRC 2 Page 14 | ||
Scenario NRC 2 Event 5&6 No: No. | |||
Event 1A Heater Drain Pump Trip | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior CUE | |||
* Annunciator HD PUMP TRIP (1-17-D2) | |||
* HD Tank level rising. | |||
* HD pump discharge valves opening. | |||
BOP | |||
* Recognize 1A HD pump tripped. | |||
o Refer to BwAR 1-17-D2 as time permits. | |||
* Report failure to US. | |||
* Recognize only one HD pump running. | |||
CREW | |||
* Identify entry conditions for 1BwOA SEC-1 SECONDARY PUMP TRIP. | |||
US | |||
* Acknowledge 1A HD pump trip. | |||
* Implement 1BwOA SEC-1 SECONDARY PUMP TRIP, ATTACHMENT C "HD PUMP TRIP" and direct operator actions of 1BwOA SEC-1 to establish the following conditions: | |||
* Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct failure. | |||
* Notify SM of the HD runback. | |||
BOP | |||
* Recognize standby HD pump NOT AVAILABLE. | |||
* Check HD pump status. | |||
* ONLY 1C HD pump running. | |||
* Initiate turbine load reduction to 780 MW at 20 MW/min. | |||
* Initiate HD runback on OWS graphic 5512. | |||
* Verify turbine load lowering. | |||
BOP | |||
* Check HD Tank level: | |||
* Level > 72% and rising. | |||
* Maintain HD tank level: | |||
o Verify 1HD046A &B opening in AUTO. | |||
o Open 1CB113A-D. | |||
o Manually open 1HD117, HD tank overflow valve. | |||
* Check 1HD117, HD tank overflow valve, in auto and closed. | |||
o Lower turbine load as necessary to close 1HD117 (load ramp in progress). | |||
* Check 1C HD pump parameters: | |||
* 1C HD pump amps < 168 amps. | |||
* 1C HD pump flow < 2950 KLB/HR. | |||
o Lower turbine load as necessary to restore 1C HD pump parameters. | |||
* Deactivate turbine runback. | |||
Comments: | Comments: | ||
151 NRC 2 Page | 151 NRC 2 Page 15 | ||
== Description:== | Scenario NRC 2 Event 5&6 No: No. | ||
Event 1A Heater Drain Pump Trip | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior ATC | |||
* Check PDMS operable: | |||
-1A not implemented | * Annunciator PDMS INOPERABLE not lit (1-10-E8). | ||
* 1BwOS PDMS-1A not implemented. | |||
* Annunciator PDMS LIMIT EXCEEDED not lit (1-10-D7). | |||
ATC | |||
* Control I near target. | |||
ATC | * Operate control rods in manual to restore I near target. | ||
* Monitor RCS parameters: | |||
o Determine from Op Aid (ramp starts from 90%). Borate in Automatic (BwOP CV-6 hard card): | o If PZR pressure lowers < 2209 psig, notify US to enter Tech Spec 3.4.1, RCS DNB Limits, Condition A. | ||
ATC | |||
* Initiate RCS boration. | |||
* Determine required boric acid volume. | |||
o Determine from Op Aid (ramp starts from 90%). | |||
Borate in Automatic (BwOP CV-6 hard card): | |||
o Turn on PZR backup heaters to equalize boron concentration. | o Turn on PZR backup heaters to equalize boron concentration. | ||
Set 1FY-0110 BA Blender Predet Counter to desired value. Set 1FK-110 BA Flow Control to desired boration rate Place MAKE | * Set 1FY-0110 BA Blender Predet Counter to desired value. | ||
-UP MODE CONT SWITCH to STOP position. | * Set 1FK-110 BA Flow Control to desired boration rate | ||
Place MODE SELECT SWITCH to BORATE position. | * Place MAKE-UP MODE CONT SWITCH to STOP position. | ||
Place MAKE | * Place MODE SELECT SWITCH to BORATE position. | ||
-UP MODE CONT SWITCH to START. | * Place MAKE-UP MODE CONT SWITCH to START. | ||
Verify the following occurs: | * Verify the following occurs: | ||
1CV110B opens. | * 1CV110B opens. | ||
1CV110A opens. | * 1CV110A opens. | ||
BA pump starts. | * BA pump starts. | ||
Proper BA flow on recorder 1FR | * Proper BA flow on recorder 1FR-110. | ||
-110. When desired boration is achieved, place MAKE-UP MODE CONT SWITCH to STOP. Verify the following occurs: | * When desired boration is achieved, place MAKE-UP MODE CONT SWITCH to STOP. | ||
1CV110B closes. | * Verify the following occurs: | ||
1CV110A closes. | * 1CV110B closes. | ||
BA pump stops. | * 1CV110A closes. | ||
Record time and amount of BA addition. | * BA pump stops. | ||
Perform BwOP CV | * Record time and amount of BA addition. | ||
-7 to return RMCS to AUTO following the final boration. | * Perform BwOP CV-7 to return RMCS to AUTO following the final boration. | ||
OR Comments: | OR Comments: | ||
151 NRC 2 Page | 151 NRC 2 Page 16 | ||
== Description:== | Scenario NRC 2 Event 5&6 No: No. | ||
Event 1A Heater Drain Pump Trip | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior Batch addition of Boric Acid (BwOP CV-6 hard card): | |||
o Turn on PZR backup heaters to equalize boron concentration. | o Turn on PZR backup heaters to equalize boron concentration. | ||
o Momentarily depress RESET pushbutton on BA Flow totalizer. | o Momentarily depress RESET pushbutton on BA Flow totalizer. | ||
Open 1CV110B | * Open 1CV110B. | ||
* Open 1CV110A. | |||
* Start the BA Transfer Pump. | |||
-112 setpoint to desired value. | o If desired, control VCL level by adjusting 1LK-112 setpoint to desired value. | ||
When desired amount of BA has been added, stop the BA Transfer Pump | * When desired amount of BA has been added, stop the BA Transfer Pump. | ||
* Close 1CV110A. | |||
* Close 1CV110B. | |||
* Verify VCT level/pressure at desired value and adjust 1LK-112 setpoint to desired corresponding level setpoint. | |||
-112 setpoint to desired corresponding level setpoint. | * Place 1CV110A/1CV110B in AUTO. | ||
Place 1CV110A/1CV110B in AUTO. Record time and amount of BA addition. | * Record time and amount of BA addition. | ||
Perform BwOP CV | * Perform BwOP CV-7 to return RMCS to AUTO following the final boration. | ||
-7 to return RMCS to AUTO following the final boration. | o May flush boric acid lines per BwOP CV-6 step. F.5. | ||
o May flush boric acid lines per BwOP CV | BOP | ||
-6 step. F.5. | * Verify running CB pump recirc valves in auto | ||
BOP | * 1CB113A-D on running pumps. | ||
* Dispatch operators to perform BwOP HD-2 for 1A HD pump. | |||
-2 for 1A HD pump | * Shutdown 4th CD/CB pump (if started during procedure performance). | ||
US | |||
* Notify Chemistry to monitor secondary plant chemistry. | |||
* Notify SM to perform risk assessment. | |||
* Check reactor power change > 15% in one hour: | |||
o Notify Chemistry to perform Tech Spec 3.4.16 sampling. | |||
o Notify Rad Protection to perform RETS 12.4.1.A sampling. | |||
-2 rod insertion limit | o Determine Tech Spec 3.1.6 Condition A entry required if control rods below LO-2 rod insertion limit. | ||
o Determine Tech Spec 3.4.1 Condition A entry if PZR pressure lowers < 2209 psig. | |||
EXAMINERS NOTE: After the above actions are complete by the US and with Lead Examiners concurrence, insert next event. | |||
Comments: | |||
151 NRC 2 Page 17 | |||
Scenario NRC 2 Event 7, 8 No: No. | |||
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs, failure of both | |||
== | |||
Description:== | |||
CS trains to automatically actuate Time Position Applicants Actions or Behavior CUE | |||
* Annunciator CNMT PRESS HIGH SI/RX TRIP (1-11-E1) | |||
* All SG pressures dropping. | |||
* RCS Tave dropping. | |||
* Rx Trip breakers open. | |||
US | |||
* Notify SM of plant status and procedure entry. | |||
* Request SM evaluation of Emergency Plan conditions. | |||
* Enter/implement 1BwEP-0 and direct operator actions of 1BwEP-0. | |||
ATC Perform immediate operator actions of 1BwEP-0 at 1PM05J: | |||
* Verify reactor trip: | |||
* Rod bottom lights - ALL LIT. | |||
* Reactor trip & Bypass breakers - OPEN. | |||
* Neutron flux - DROPPING. | |||
BOP Perform immediate operator actions of 1BwEP-0 at 1PM02J: | |||
* Verify turbine trip: | |||
* All Turbine throttle valves - CLOSED. | |||
* All Turbine governor valves - CLOSED. | |||
BOP Perform immediate operator actions of 1BwEP-0 at 1PM01J: | |||
* Verify power to 4KV busses: | |||
* ESF Buses - BOTH ENERGIZED. | |||
ATC Perform immediate operator actions of 1BwEP-0 at 1PM05J: | |||
* Check SI status: | |||
o SI First OUT annunciator - Annunciator CNMT PRESS HIGH SI/RX TRIP (1 E1) LIT. | |||
o SI ACTUATED Permissive Light - LIT. | |||
o SI Equipment - AUTOMATICALLY ACTUATED: | |||
o Either SI pump - RUNNING. | |||
o Either CV pump to cold leg isolation valve OPEN - 1SI8801A/B. | |||
* Manually actuate SI from 1PM05J and 1PM06J. | |||
US Direct BOP to perform Attachment B of 1BwEP-0. | |||
EXAMINERS NOTE: US and ATC will continue in 1BwEP-0 while BOP is performing Attachment B. | |||
Comments: | Comments: | ||
151 NRC 2 Page 18 | 151 NRC 2 Page 18 | ||
== Description:== | Scenario NRC 2 Event 7, 8 No: No. | ||
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs, failure of both | |||
== | |||
Description:== | |||
CS trains to automatically actuate Time Position Applicants Actions or Behavior BOP 1BwEP-0 ATTACHMENT B: | |||
Verify FW isolated at 1PM04J: | |||
* FW pumps - TRIPPED. | |||
* FW isolation monitor lights - LIT. | |||
* FW pumps discharge valves - CLOSED (or going closed) 1FW002A-C. | |||
* Verify DGs running at 1PM01J: | |||
* DGs - BOTH RUNNING. | |||
* 1SX169A/B OPEN. | |||
* Dispatch operator to monitor DGs operation. | |||
* Verify Generator Trip at 1PM01J: | |||
* OCB 1-8 and 7-8 open. | |||
* PMG output breaker open. | |||
* Verify Control Room ventilation aligned for emergency operations at 0PM02J: | |||
* VC Rad Monitors - LESS THAN HIGH ALARM SETPOINT. | |||
* Operating VC train equipment - RUNNING. | |||
* 0B Supply fan | |||
* 0B Return fan | |||
* 0B M/U fan | |||
* 0B Chilled water pump | |||
* 0B Chiller | |||
* Operating VC train dampers - ALIGNED. | |||
* M/U fan outlet damper - 0VC08Y NOT FULLY CLOSED. | |||
* 0B VC train M/U filter light - LIT. | |||
* 0VC09Y - OPEN. | |||
* 0VC313Y - CLOSED. | |||
* Operating VC train Charcoal Absorber aligned for train B. | |||
* 0VC44Y - CLOSED. | |||
* 0VC05Y - OPEN. | |||
* 0VC06Y - OPEN. | |||
* Control Room pressure greater than +0.125 inches water on 0PDI-VC038. | |||
* Verify Auxiliary Building ventilation aligned for emergency operations at 0PM02J: | |||
* Two inaccessible filter plenums aligned. | |||
* Plenum A: | |||
* 0VA03CB - RUNNING. | |||
* 0VA023Y - OPEN. | |||
* 0VA436Y - CLOSED. | |||
* Plenum C: | |||
* 0VA03CF RUNNING. | |||
* 0VA072Y - OPEN. | |||
Comments: | |||
151 NRC 2 Page 19 | |||
Steam leak inside containment/uncontrolled depressurization of ALL SGs, failure of both | Scenario NRC 2 Event 7, 8 No: No. | ||
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs, failure of both | |||
== | |||
Description:== | |||
CS trains to automatically actuate Time Position Applicants Actions or Behavior | |||
* 0VA438Y - CLOSED. | |||
* Verify FHB ventilation aligned for emergency operation at 0PM02J: | |||
* 0VA04CB - RUNNING. | |||
* 0VA055Y - OPEN. | |||
* 0VA062Y - OPEN. | |||
* 0VA435Y - CLOSED. | |||
* Trip 1C HD pump. | |||
* Initiate periodic monitoring of Spent Fuel Cooling. | |||
* Notify US Attachment B complete/manual actions taken. | |||
ATC | |||
* Verify ECCS pumps running at 1PM05J/1PM06J: | |||
* BOTH CV pumps - RUNNING. | |||
* BOTH RH pumps - RUNNING. | |||
* BOTH SI pumps - RUNNING. | |||
ATC | |||
* Perform the following at 1PM06J: | |||
* RCFCs running in accident mode. | |||
* Group 2 RCFC accident mode status light lit. | |||
* CNMT Phase A valves closed. | |||
EXAMINERS NOTE: RCPs may be stopped by the crew any time after recognizing that Phase B isolation has occurred. | |||
ATC Perform the following at 1PM06J: | |||
* Verify Cnmt Vent isolation: | |||
* Group 6 Cnmt Vent Isol monitor lights - LIT. | |||
* Verify AF system: | |||
* BOTH AF pumps - RUNNING. | |||
* AF isolation valves - 1AF13A-H OPEN. | |||
* AF flow control valves - 1AF005A-D throttled OPEN. | |||
* Verify CC pumps running: | |||
* BOTH CC pumps - RUNNING. | |||
* Verify SX pumps running: | |||
* BOTH SX pumps - RUNNING. | |||
ATC | |||
* Check if Main Steamlines Should Be Isolated: | |||
* CNMT pressure > 8.2 psig OR SG pressure <640 psig. | |||
* Verify MS isolation: | |||
* MSIVs are open. | |||
Comments: | Comments: | ||
151 NRC 2 Page | 151 NRC 2 Page 20 | ||
Scenario NRC 2 Event 7, 8 No: No. | |||
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs, failure of both | |||
== | |||
Description:== | |||
CS trains to automatically actuate Time Position Applicants Actions or Behavior | |||
* Manually actuate MS isolation. | |||
* ALL MSIVs remain open. | |||
* Place control switches to close for ALL MSIVs (ALL MSIVs remain open). | |||
CREW o Determine and announce containment is adverse when containment pressure rises above 5 psig. | |||
ATC | |||
* Check if CS is required | |||
* CNMT pressure > 20 psig. | |||
* Group 6 CS monitor lights - NOT ALL LIT. | |||
* Manually actuate CS and Phase B Isolation. | |||
* Group 6 CS monitor lights remain - NOT ALL LIT, GO TO Attachment C. | |||
US | |||
* Implement 1BwEP-0, ATTACHMENT C MANUAL CS ACTUATION. | |||
- | |||
Comments: | Comments: | ||
151 NRC 2 Page | 151 NRC 2 Page 21 | ||
Scenario NRC 2 Event 7, 8 No: No. | |||
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs, failure of both | |||
== | |||
Description:== | |||
. | CS trains to automatically actuate Time Position Applicants Actions or Behavior 1BwEP-0, ATTACHMENT C MANUAL CS ACTUATION EXAMINERS NOTE: The examinees will also attempt to align the A train of CS, however only the B train will properly align and start the 1B CS pump as outlined below. | ||
. | ATC | ||
* Check CS valve alignment: | |||
* Check 1CS001A/B - OPEN. | |||
* Check 1CS007A/B - OPEN: | |||
Manually actuate one train of containment spray prior to transition out of 1BwEP-0. | |||
(Westinghouse - CT-3) (K/A number - 013000A4.01 importance - 4.5/4.8) | |||
* 1CS007A - OPEN. | |||
ATC | [CT-3] | ||
* Manually open 1CS007B. | |||
Group 6 | * Check 1CS019A/B - OPEN. | ||
- LIT. Verify | * 1CS007A open. | ||
[CT-3] | |||
* Place 1B CS pump test switch in test. | |||
- | [CT-3] | ||
- | * Manually open 1CS019B. | ||
Verify | * Place 1B CS pump test switch in normal | ||
* Check 1CS010A/B - OPEN. | |||
* Check CS pumps - AT LEAST ONE RUNNING: | |||
- | * 1B CS pump running. | ||
o Place 1A CS pump in PTL. | |||
US | |||
* Return to 1BwEP-0 main body, step 14.c. | |||
ATC | |||
* Check if CS is required: | |||
* Group 6 phase B monitor lights - ALL LIT. | |||
* Verify/stop all RCPs (may have been performed previously). | |||
* Check CS eductor suction flow - 1FI-CS014 > 15 gpm. | |||
* Check CS eductor additive flow - 1FI-CS016 > 5 gpm. | |||
BOP | |||
* Verify total AF flow: | |||
* AF flow > 500 gpm. | |||
* Check S/G NR levels - NOT rising in an uncontrolled manner. | |||
ATC | |||
* Verify ECCS valve alignment: | |||
* Group 2 Cold Leg Injection monitor lights required for injection - LIT. | |||
Comments: | Comments: | ||
151 NRC 2 Page | 151 NRC 2 Page 22 | ||
Scenario NRC 2 Event 7, 8 No: No. | |||
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs, failure of both | |||
== | |||
. | Description:== | ||
. | CS trains to automatically actuate Time Position Applicants Actions or Behavior ATC | ||
. | * Verify ECCS flow: | ||
ATC | * High head SI flow >100 gpm (1FI-917). | ||
. | * RCS pressure < 1700 psig. | ||
- | * SI pump discharge flows > 200 gpm. | ||
. | * RCS pressure > 325 psig. | ||
. | ATC | ||
. | * Check PZR PORVs and spray valves: | ||
- | * PORVs CLOSED. | ||
. | * PORV isolation valves - BOTH ENERGIZED. | ||
* PORV relief paths - BOTH PORVs in AUTO, PORV isolation valves OPEN. | |||
* Normal spray valves CLOSED. | |||
ATC | |||
* Check RCS temperatures: | |||
* RCPs - NONE RUNNING. | |||
* RCS Tcold temperatures are NOT stable at or trending to 557F. | |||
* Stop dumping steam | |||
* Throttle AF flow while maintaining > 500 gpm. | |||
* MSIVs open - verify closed (will not close). | |||
o Crew may throttle AF flow to 45 gpm per SG. | |||
ATC | |||
* Check status of RCPs: | |||
* RCPs - NONE RUNNING. | |||
CREW Check if SG secondary boundaries are intact: | |||
* Check NO SG depressurizing uncontrollably or completely depressurized. | |||
* ALL SG pressures dropping in an uncontrolled manner. | |||
CREW Transition to 1BwEP-2 FAULTED STEAM GENERATOR ISOLATION. | |||
Comments: | Comments: | ||
151 NRC 2 Page | 151 NRC 2 Page 23 | ||
Scenario NRC 2 Event 7 No: No. | |||
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs | |||
== Description:== | == | ||
Description:== | |||
Time Position Applicants Actions or Behavior 1BwEP-2 FAULTED STEAM GENERATOR ISOLATION US | |||
* Notify SM of plant status and procedure entry. | |||
* Request SM evaluation of Emergency Plan conditions. | |||
* Request STA evaluation of status trees. | |||
* Enter/implement 1BwEP-2 and direct operator actions of 1BwEP-2 to establish the following conditions: | |||
BOP | |||
/ | * Check Main Steamline Isolation: | ||
- | * ALL MSIVs remain open (manual MS line isolation previously attempted). | ||
CREW | |||
* Check if any SG secondary pressure boundary intact: | |||
* No SG pressure stable or rising. | |||
* ALL SGs depressurizing in an uncontrolled manner. | |||
* GO TO 1BwCA-2.1 UNCONTROLLED DEPRESSURIZATION OF ALL SGs. | |||
CREW Transition to 1BwCA-2.1 UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS. | |||
: | |||
: | |||
. | |||
. | |||
- | |||
Comments: | Comments: | ||
151 NRC 2 Page | 151 NRC 2 Page 24 | ||
== Description:== | Scenario NRC 2 Event 7 No: No. | ||
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior 1BwCA-2.1 UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS US | |||
: | * Notify SM of plant status and procedure entry. | ||
- | * Request SM evaluation of Emergency Plan conditions. | ||
. | * Enter/implement 1BwCA-2.1 and direct operator actions of 1BwCA-2.1 to establish the following conditions: | ||
BOP | |||
* Check secondary pressure boundary: | |||
- | * MSIVs open - attempt to close (previously attempted). | ||
* MSIV bypass valves - CLOSED. | |||
- | * SG PORVs - CLOSED. | ||
* Check FW isolation monitor lights - LIT. | |||
* Check 1SD002A-H - CLOSED. | |||
. | * Check 1SD005A-D - CLOSED. | ||
. | EXAMINERS NOTE: Throttling AF flow to 45 gpm per SG will result in a red path on the heat sink status tree and require a transition to 1BwFR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK. 1BwFR-H.1 will be entered and immediately exited due to operator action lowering AF flow to < 500 gpm. | ||
BOP | |||
. | * Control feed flow to minimize RCS cooldown. | ||
. | * Check cooldown rate in RCS cold legs < 100 F in any 1 hour period - NO. | ||
Manually control AF flowrate to 45 gpm for each SG before orange path in integrity occurs. (Westinghouse - CT-33) (K/A number - EPEE12EA1.3 importance - 3.4/3.9) | |||
[CT-33] | |||
. | * Throttle AF flow to 45 gpm per SG. | ||
- | * Check RCS hot leg temperatures - Stable or dropping. | ||
. | * Check RCPs - NONE RUNNING. | ||
* Check PZR PORVs and Isolation Valves: | |||
* PORV Isolation Valves - BOTH energized. | |||
* PORVs - BOTH closed. | |||
* PORV Isolation Valves - BOTH open. | |||
BOP | |||
* Check Secondary Radiation: | |||
* Reset Phase A. | |||
* Open 1SD005A-D. | |||
* Request Chemistry to periodically sample all SGs for activity. | |||
* Check secondary radiation trends on RM-11 or PPC - ALL normal. | |||
Comments: | Comments: | ||
151 NRC 2 Page | 151 NRC 2 Page 25 | ||
Scenario NRC 2 Event 7 No: No. | |||
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs | |||
== Description:== | == | ||
Description:== | |||
Time Position Applicants Actions or Behavior BOP | |||
* Check if RH Pumps Should be Stopped: | |||
* RH pumps - BOTH running with suction on RWST. | |||
* If RCS pressure > 325 psig and pressure is stable or rising, reset SI and stop RH pumps/place in standby. | |||
EXAMINERS NOTE: Terminate the scenario at Lead Examiners discretion. | |||
(Final) | |||
: | |||
- | |||
. | |||
Comments: | Comments: | ||
151 NRC 2 Page 26 | 151 NRC 2 Page 26 | ||
Simulation Facility Braidwood Scenario Operating Test No.: 151 NRC No.: | |||
NRC 3 Examiners: ______________________ Applicant: ____________________ SRO | |||
______________________ ____________________ ATC | |||
______________________ ____________________ BOP Initial Conditions: IC-21 Turnover: Unit 1 is operating at 100% power, steady state, equilibrium xenon, BOL. 1B CW pump is OOS for motor inspection. Automatic Rod Control is failed (rod speed programmer failure). | |||
Rods are in MANUAL. IMD troubleshooting will commence in 3-4 hours. Following completion of turnover, the crew is to perform 1BwOS EH-M1 UNIT 1 PUMP OPERABILITY SURVEILLANCE, using the preferred method of depressing and holding the MCB pushbutton. An Equipment Operator has been briefed and is standing by at the Unit 1 EH skid. | |||
Event Malf. No. Event Event No. Type Description Preload IMF RX17 0 Rod speed programmer failure IOR ZDI1CW01PB PTL 1B CW pump OOS IMF FW44 1A AF pump fails to start IMF FW43 1B AF pump fails to start IMF SI12B 1B SI pump fails to automatically start IRF RP30 OUT Phase A slave failure IRF RP56 OUT Phase A slave failure trgset 1 ZLO52BRKA(2) == 1 IMF FW19C 3.5 (1 0) 1C feedline break inside Cnmt when reactor trips IMF CV01B (1 0) 1B CV pump trips when reactor trips 1 None N-BOP, Perform 1BwOS EH-M1 US 2 IMF RX04E 0 120 I-BOP, Feed Flow channel, 1FT530, fails low US 3 IMF CV29A 100 C-ATC, 1A CV pump shaft shear US TS-US 4 IMF SW01A C-BOP, 1A SX Pump Trip US TS-US 5 IMF RX15 2195 I-ATC, Master Pressurizer Pressure Controller output US fails to 2195 psig (0% demand) 6 IMF FW36 500 scfm to 120 R-ATC, Condenser vacuum leak requiring load reduction scfm over 600 seconds US 7 IMF CV03 Boric acid transfer pump trip 8 IMF RP09A M-ALL Inadvertent FWI Feed line break inside containment 9 Preload C-ALL 1B CV pump trip when reactor trips 10 Preload M-ALL Loss of heat sink (1A/1B AF pumps tripped) | |||
*(N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient 151 NRC 3 | |||
SCENARIO OVERVIEW Unit 1 is operating at 100% power, steady state, equilibrium xenon, BOL. 1B CW pump is OOS for motor inspection. Automatic Rod Control is failed (rod speed programmer failure). Rods are in MANUAL. IMD troubleshooting will commence in 3-4 hours. Following completion of turnover, the crew is to perform 1BwOS EH-M1 UNIT 1 PUMP OPERABILITY SURVEILLANCE, using the preferred method of depressing and holding the MCB pushbutton. An Equipment Operator has been briefed and is standing by at the Unit 1 EH skid. | |||
After completing shift turnover and relief, the BOP will perform 1BwOS EH-M1 UNIT 1 PUMP OPERABILITY SURVEILLANCE. | |||
After completing the surveillance, feed flow channel, 1FT-530, will fail low resulting in rising feed flow and opening of 1FW530, 1C S/G Feed Reg Valve, to match feed flow with steam flow. The BOP will diagnose the failure and take manual control of 1FW530 to restore 1C SG level. The US will enter 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL - ATTACHMENT G. The crew will take actions per hard card 1BwPR 1-15-SG & 1BwOA INST-2 and perform appropriate actions. The crew will swap to an operable feed flow channel. | |||
After addressing the failed feed flow channel, the 1A CV pump shaft shear will occur. The crew will implement 1BwOA PRI-15 LOSS OF NORMAL CHARGING. The crew will start the 1B CV pump to restore normal charging. Technical Specifications 3.5.2 Condition A and TRM 3.1.d Condition A apply. | |||
After the charging pump failure is addressed, the 1A Essential Service Water (SX) pump will trip due to an overcurrent condition. The crew will take actions per hard card 1BwPR 1-2-A1 to start the 1B SX pump. The crew MAY enter 1BwOA PRI-8, ESSENTIAL SERVICE WATER MALFUNCTION. Tech Specs 3.7.8 Condition A applies. The 1A SX pump will remain unavailable for the rest of the scenario. | |||
-4 hours. Following completion of turnover, the crew is to perform 1BwOS EH-M1 | |||
After completing shift turnover and relief, the BOP will perform 1BwOS EH | |||
-M1 | |||
, 1FT-530 , will fail low resulting in rising feed flow and opening of 1FW530, 1C S/G Feed Reg Valve | |||
, to match feed flow with steam flow. The BOP will diagnose the failure and take manual control of 1FW530 to restore 1C SG level. The US will enter 1BwOA INST-2 | |||
- ATTACHMENT G. | |||
After addressing the failed feed flow channel, the 1A CV pump shaft shear will | |||
-15 | |||
After the charging pump failure is addressed, the 1A Essential Service Water (SX) pump will trip due to an overcurrent condition. The crew will take actions per hard card 1BwPR 1 A1 to start the 1B SX pump. The crew MAY enter 1BwOA PRI | |||
-8, ESSENTIAL SERVICE WATER MALFUNCTION. Tech Specs 3.7.8 Condition A applies. The 1A SX pump will remain unavailable for the rest of the scenario. | |||
After the 1A SX pump trip is addressed, the master pressurizer pressure controller output will fail to 2195 psig (0% demand) in automatic. The RO will identify the failure and take manual control to restore pressurizer pressure. | After the 1A SX pump trip is addressed, the master pressurizer pressure controller output will fail to 2195 psig (0% demand) in automatic. The RO will identify the failure and take manual control to restore pressurizer pressure. | ||
After the master pressurizer pressure controller failure has been addressed, an air leak will develop in the main condenser. The crew will enter 1BwOA SEC-3 | After the master pressurizer pressure controller failure has been addressed, an air leak will develop in the main condenser. The crew will enter 1BwOA SEC-3 LOSS OF CONDENSER VACUUM, dispatch operators to locate the leak and contact Engineering to evaluate the leakage. With the 1B CW pump OOS; the crew will be required to commence a ramp down of Unit 1 to stabilize the loss of vacuum. | ||
dispatch operators to locate the leak and contact Engineering to evaluate the leakage. | |||
With the 1B CW pump OOS; the crew will be required to commence a ramp down of Unit 1 to stabilize the loss of vacuum. | |||
During the ramp, the boric acid transfer pump will trip during the first boration. The common boric acid pump will not be available and the ATC will have to continue the ramp with rods only. | During the ramp, the boric acid transfer pump will trip during the first boration. The common boric acid pump will not be available and the ATC will have to continue the ramp with rods only. | ||
After a sufficient reactivity manipulation has occurred | After a sufficient reactivity manipulation has occurred, an inadvertent FWI occurs. When the crew manually trips the reactor, a feed line break on the 1C SG inside containment will occur. The 1B CV pump trips when the reactor trips. The crew will enter 1BwEP-0 to stabilize the plant and SI will actuate. The 1B SI pump fails to auto start and must be manually started. The 1A and 1B AF pumps will not start resulting in a transition to 1BwFR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK at step 15 of 1BwEP- | ||
, an inadvertent FWI occurs. When the crew manually trips the reactor, a feed line break on the 1C SG inside containment will occur. The 1B CV pump trips when the reactor trips. | : 0. Bleed and feed will be required due to NO CV pumps running. | ||
The crew will enter 1BwEP | Completion criteria is establishing bleed and feed during the loss of heat sink. | ||
-0 to stabilize the plant and SI will actuate. The 1B SI pump fails to auto start and must be manually started. The 1A and 1B AF | |||
-H.1 | |||
Critical Tasks | Critical Tasks | ||
: 1. Close containment isolation valves such that at least one valve is closed on each Phase A penetration before the end of the scenario. | : 1. Close containment isolation valves such that at least one valve is closed on each Phase A penetration before the end of the scenario. (Westinghouse CT-11) (K/A number APE069AA1.01 importance 3.5/3.7) | ||
-11) (K/A number | : 2. Initiate RCS bleed and feed so that the RCS depressurizes sufficiently for SI pump injection to occur. | ||
-46) (K/A number EPEE05EA1.1 importance 4.1/4.0) | (Westinghouse CT-46) (K/A number EPEE05EA1.1 importance 4.1/4.0) 151 NRC 3 Page 2 | ||
151 NRC 3 Page | |||
Complete items on Simulator Ready for Training Checklist. | SIMULATOR SETUP GUIDE | ||
* Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST. | |||
* Establish the conditions of IC-21, 100% power, steady state, equilibrium xenon, BOL OR use the IC written below. | |||
* Verify/place OA & OC VA plenums in service, 0B VA plenum in standby. | |||
* Place ROD BANK SELECT switch in MANUAL. | |||
* Place YELLOW on-line risk sign on 1PM05J. | |||
* Update PARAGON to BOL with RODS in MANUAL. | |||
* Complete items on Simulator Ready for Training Checklist. | |||
* Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario. | |||
* Place simulator in RUN (allow simulator to run during board walk down and turnover). | |||
* Place 1B CW pump C/S in PTL, after 1CW001B is full closed, then run CAE. | |||
* Hang OOS card on 1B CW pump. | |||
* Run caep 151 NRC 3 SETUP from disk and verify the following actuate: | |||
* IMF RX17 0 | |||
* IOR ZDI1CW01PB PTL | |||
* IMF FW44 | |||
* IMF FW43 | |||
* IMF SI12B | |||
* IRF RP30 OUT | |||
* IRF RP56 OUT | |||
* trgset 1 ZLO52BRKA(2) == 1 | |||
* IMF FW19C 3.5 (1 0) | |||
* IMF CV01B (1 0) | |||
* After main generator load stabilizes, write an IC to allow the scenario to be used again. | |||
* Provide students with turnover sheets. | |||
151 NRC 3 Page 3 | |||
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Perform 1BwOS EH-M1. | |||
When requested, as Equipment Operator, report you are standing by at the Unit 1 EH skid. Report the following data as EH pumps are started and stopped: | |||
* EH system temperature is 110°F. | |||
* EH system pressure is 1970 psig with ONE EH pump running. | |||
* EH system pressure is 1985 psig with TWO EH pumps running. | |||
-M1. When requested, as Equipment Operator | |||
, report you are standing by at the Unit 1 EH skid. Report the following data as EH pumps are started and stopped: | |||
EH system temperature is 110 F. EH system pressure is 1970 psig with ONE EH pump running. | |||
EH system pressure is 1985 psig with TWO EH pumps running. | |||
If requested, as Field Supervisor report you are providing direct supervision in the field for production risk. | If requested, as Field Supervisor report you are providing direct supervision in the field for production risk. | ||
Acknowledge as Shift Manager, the start and completion of procedure. | |||
Acknowledge as Shift Manager, the start and completion of procedure. Event 2: Feed flow channel , 1FT-530 , fails low. Insert IMF RX04E 0 120 to fail 1FT | Event 2: Feed flow channel, 1FT-530, fails low. | ||
-530 low over 120 seconds. | Insert IMF RX04E 0 120 to fail 1FT-530 low over 120 seconds. | ||
As SM, acknowledge the failure, requests for on | As SM, acknowledge the failure, requests for on-line risk assessment, maintenance support, and IR initiation. | ||
-line risk assessment, maintenance support, and IR initiation. | Event 3: 1A CV pump shaft shear. | ||
Event 3: | Insert IMF CV29A 100 for 1A CV pump shaft shear. | ||
If dispatched as Equipment Operator to 1A CV pump and/or pump breaker, wait three minutes and report 1A CV pump appears shaft is sheared. | If dispatched as Equipment Operator to 1A CV pump and/or pump breaker, wait three minutes and report 1A CV pump appears shaft is sheared. | ||
If dispatched as Equipment Operator to check for a good start on the 1B CV pump , report that the 1B CV pump had a good start. | If dispatched as Equipment Operator to check for a good start on the 1B CV pump, report that the 1B CV pump had a good start. | ||
Acknowledge as Shift Manager the failure, LCOAR entry, on | Acknowledge as Shift Manager the failure, LCOAR entry, on-line risk assessment, EAL evaluation, request for maintenance support, and IR request. | ||
-line risk assessment, EAL evaluation, request for maintenance support, and IR request. | 151 NRC 3 Page 4 | ||
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 4: 1A SX pump trip. | |||
Insert IMF SW01A for 1A SX pump trip. | |||
If dispatched as EO to investigate 1A SX pump breaker, wait 2 minutes and report phase A overcurrent flag on 1A SX pump breaker cubicle (Bus 141, cubicle 2). | If dispatched as EO to investigate 1A SX pump breaker, wait 2 minutes and report phase A overcurrent flag on 1A SX pump breaker cubicle (Bus 141, cubicle 2). | ||
If dispatched as EO to investigate 1A SX pump, wait 3 minutes and report no damage visible at pump and pump is NOT rotating backwards. Report 1B SX pump is running with normal parameters if dispatched to check 1B SX pump. | If dispatched as EO to investigate 1A SX pump, wait 3 minutes and report no damage visible at pump and pump is NOT rotating backwards. Report 1B SX pump is running with normal parameters if dispatched to check 1B SX pump. | ||
If contacted as Unit 2 to swap Unit 2 SX pumps for chem. feed alignment, acknowledge request. | If contacted as Unit 2 to swap Unit 2 SX pumps for chem. feed alignment, acknowledge request. | ||
If contacted as Rad Waste Operator, report no abnormal Aux Building sump indications. | If contacted as Rad Waste Operator, report no abnormal Aux Building sump indications. | ||
If contacted as EO to check the containment chiller report chiller tripped on high evaporator pressure from a loss of SX. Chiller checks out ok for a restart. | If contacted as EO to check the containment chiller report chiller tripped on high evaporator pressure from a loss of SX. Chiller checks out ok for a restart. | ||
As SM, acknowledge the trip of 1A SX pump, Tech Spec 3.7.8 Condition A entry, and requests for on | As SM, acknowledge the trip of 1A SX pump, Tech Spec 3.7.8 Condition A entry, and requests for on-line risk assessment, maintenance support, and IR initiation. | ||
-line risk assessment, maintenance support, and IR initiation. | |||
Event 5: Master Pressurizer Pressure Controller fails to 2195 psig (0% demand). | Event 5: Master Pressurizer Pressure Controller fails to 2195 psig (0% demand). | ||
Insert IMF | Insert IMF RX15 2195 to fail the master pressurizer pressure controller output low. | ||
. | 151 NRC 3 Page 5 | ||
151 NRC 3 Page | |||
Event 6: Lowering condenser vacuum requiring load drop. | |||
Insert IMF FW36 500 SCFM lowering to 120 SCFM over 600 seconds. | |||
-line risk assessment, maintenance support, and IR initiation. | As SM, acknowledge 1BwOA SEC-3 entry, request for E Plan evaluation, load ramp and requests for on-line risk assessment, maintenance support, and IR initiation. | ||
If contacted as Engineering to evaluate lowering vacuum, inform the unit supervisor that an Engineer is evaluating the Unit 1 lowering condenser vacuum. | If contacted as Engineering to evaluate lowering vacuum, inform the unit supervisor that an Engineer is evaluating the Unit 1 lowering condenser vacuum. | ||
Acknowledge dispatch of EOs to investigate the lowering condenser vacuum. After approximately 10 minutes , report the sound of air leak coming from under the | Acknowledge dispatch of EOs to investigate the lowering condenser vacuum. After approximately 10 minutes, report the sound of air leak coming from under the 1C LP turbine. | ||
Monitor the crew for the first boration and insert Event 7 during the first boration. | Monitor the crew for the first boration and insert Event 7 during the first boration. | ||
If contacted as Reactor Engineering, acknowledge the ramp being performed with rods only. If asked for permission to ramp or for guidance to ramp with rods only | If contacted as Reactor Engineering, acknowledge the ramp being performed with rods only. If asked for permission to ramp or for guidance to ramp with rods only. Inform Unit 1 you will develop a plan to recover to the desired rod alignment once the transient is over and boric acid is restored. | ||
. Inform Unit 1 you will develop a plan to recover to the desired rod alignment once the transient is over and boric acid is restored. | Once the ramp has commenced, monitor condenser pressure in SimView (YCP2205/06/07) to ensure a ramp is required, but vacuum doesnt degrade to the reactor trip set point. Adjust MF FW36 severity as required. | ||
Once the ramp has commenced | Event 7: Trip of the unit 1 boric acid pump. | ||
, monitor condenser pressure in SimView (YCP2205/06/07) to ensure a ramp is required, but vacuum | Once the first boration has been started: | ||
Adjust MF FW36 severity as required. | Insert IMF CV03 to trip the boric acid transfer pump. | ||
Event 7: | As SM, acknowledge loss of Unit 1 boric acid pump and requests for on-line risk assessment, maintenance support, and IR initiation. | ||
As the EO, report that the boric acid pump is hot to the touch and an acrid odor is in the air. There is no fire and the breaker is tripped free. | |||
-line risk assessment, maintenance support, and IR initiation. | As the Field Supervisor or EO, acknowledge the need to swap to the Unit 0 boric acid pump on Unit 1 per BwOP AB-23 step F.1. After 3 minutes, call to report the power cord for the Unit 0 AB pump is damaged and not usable. | ||
As the EO , report that the boric acid pump is hot to the touch and an acrid odor is in the air. There is no fire and the breaker is tripped free. | |||
As the Field Supervisor or | |||
After 3 minutes | |||
, call to report the power cord for the Unit 0 AB pump is damaged and not usable. | |||
If contacted as Unit 2, acknowledge the request for use of the Unit 2 boric acid transfer pump and inform Unit 1 it will be 30 to 60 minutes before it will be available. | If contacted as Unit 2, acknowledge the request for use of the Unit 2 boric acid transfer pump and inform Unit 1 it will be 30 to 60 minutes before it will be available. | ||
151 NRC 3 Page 6 | |||
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 8: Inadvertent Feed Water Isolation. | |||
Insert IMF RP09A. | |||
Event 9/10: Feed line break in containment / Loss of Heat Sink | Event 9/10: Feed line break in containment / Loss of Heat Sink / CV pump trip. | ||
Acknowledge as SM procedure transitions, E Plan evaluations, and STA request. | |||
After STA requested, as STA report CSF status - Red path on heat sink (until feed flow established). | |||
Yellow on heat sink once feed flow established, Yellow on inventory when vessel head voids due to bleed and feed. | |||
After STA requested, as STA report CSF status | If dispatched as EO, report 1B CV pump has phase C overcurrent flag. | ||
- Red path on heat sink (until feed flow established). Yellow on heat sink once feed flow established, Yellow on inventory when vessel head voids due to bleed and feed. If dispatched as EO, report 1B CV pump has phase C overcurrent flag. | |||
If dispatched as EO, report 1A AF pump has a ground overcurrent flag and motor damage. | If dispatched as EO, report 1A AF pump has a ground overcurrent flag and motor damage. | ||
If dispatched as EO, report 1B AF pump has large lube oil leak and engine damage. | If dispatched as EO, report 1B AF pump has large lube oil leak and engine damage. | ||
Acknowledge as U | Acknowledge as U-2 NSO, the request to remove FW isolation fuses; then insert the following: | ||
-2 NSO, the request to remove FW isolation fuses | * MRF FW150 REMOVED | ||
; then insert the following: | * MRF FW151 REMOVED | ||
MRF FW150 REMOVED MRF FW151 REMOVED MRF RP78 REMOVED MRF RP79 REMOVED Acknowledge as EO to start startup FW pump aux oil pump and insert the following: | * MRF RP78 REMOVED | ||
MRF FW149 START | * MRF RP79 REMOVED Acknowledge as EO to start startup FW pump aux oil pump and insert the following: | ||
* MRF FW149 START 151 NRC 3 Page 7 | |||
Scenario NRC 3 Event 1 No: No. | |||
Event Perform 1BwOS EH-M1 | |||
== Description:== | == Description:== | ||
Time Position Applicants Actions or Behavior CUE | |||
* From turnover, perform 1BwOS EH-M1 UNIT 1 PUMP OPERABILITY SURVEILLANCE. | |||
-M1 | US | ||
* Direct BOP to perform 1BwOS EH-M1. | |||
-M1. BOP | BOP | ||
-M1. Record initial data on Data Sheet D | * Refer to 1BwOS EH-M1. | ||
-2. Notify Equipment Operator at EH skid of pending 1B EH pump start | * Record initial data on Data Sheet D-2. | ||
* Notify Equipment Operator at EH skid of pending 1B EH pump start. | |||
* At 1PM02J, depress EH PP LO PRESS AUTO START TEST (20/MPT) pushbutton. | |||
o Equipment Operator locally verifies 1B EH pump started. | o Equipment Operator locally verifies 1B EH pump started. | ||
Perform the following at 1PM02J: | * Perform the following at 1PM02J: | ||
Verify annunciator 1 B15, EH SYSTEM TROUBLE, remained clear. | * Verify annunciator 1-18-B15, EH SYSTEM TROUBLE, remained clear. | ||
Place 1B EH pump C/S in AFTER CLOSE. | * Place 1B EH pump C/S in AFTER CLOSE. | ||
Notify Equipment Operator at EH skid of pending 1A EH pump shutdown | * Notify Equipment Operator at EH skid of pending 1A EH pump shutdown. | ||
* At 1PM02J, place 1A EH pump C/S in AFTER TRIP. | |||
Equipment Operator locally verify EH pressure 1950 | * Equipment Operator locally verify EH pressure 1950 +/- 50 psig. | ||
* Notify Equipment Operator at EH skid of pending 1A EH pump start. | |||
* At 1PM02J, depress EH PP LO PRESS AUTO START TEST (20/MPT) pushbutton. | |||
Perform the following at 1PM02J: | o Equipment Operator locally verifies 1A EH pump started. | ||
Verify annunciator 1 B15, EH SYSTEM TROUBLE, remained clear. | * Perform the following at 1PM02J: | ||
Place 1A EH pump C/S in AFTER TRIP. | * Verify annunciator 1-18-B15, EH SYSTEM TROUBLE, remained clear. | ||
Equipment Operator locally verifies EH pressure 1950 | * Place 1A EH pump C/S in AFTER TRIP. | ||
-2. Inform US that 1BwOS EH-M1 complete. | * Equipment Operator locally verifies EH pressure 1950 +/- 50 psig. | ||
US | * Record as left data on Data Sheet D-2. | ||
* Inform US that 1BwOS EH-M1 complete. | |||
US | |||
* Acknowledge report of surveillance completion. | |||
o Notify SM that 1BwOS EH-M1 is complete. | o Notify SM that 1BwOS EH-M1 is complete. | ||
EXAMINERS NOTE: After 1BwOS EH-M1 is complete and with Lead Examiners concurrence, enter next event. | |||
-M1 is complete and with Lead | Comments: | ||
151 NRC 3 Page 8 | |||
Comments: | |||
Scenario NRC 3 Event 2 No: No. | |||
Event Feed flow channel, 1FT-530, fails low | |||
== Description:== | == Description:== | ||
Time Position Applicants Actions or Behavior CUE | |||
* Annunciator S/G 1C FLOW MISMATCH FW FLOW LOW (1-15-C4) | |||
/G 1C FLOW MISMATCH FW FLOW LOW (1 C4) | * Annunciator S/G 1C LEVEL DEVIATION HIGH/LOW (1-15-C9) | ||
/G 1C LEVEL DEVIATION HIGH/LOW (1 C9) | * 1C SG NR levels rising. | ||
-530. Place 1C FRV (1FW530) in manual and restore SG level per 1BwPR 1 SG. o Reference BwARs as time permits. | * FW flow rising on feed flow meter, 1FI-531A. | ||
ATC o Reference BwARs as time permits. | BOP | ||
CREW | * Identify/report failure of 1FT-530. | ||
-2 | * Place 1C FRV (1FW530) in manual and restore SG level per 1BwPR 1-15-SG. | ||
o Reference BwARs as time permits. | |||
Request SM evaluation of Emergency Plan conditions. | ATC o Reference BwARs as time permits. | ||
Enter/implement 1BwOA INST | CREW | ||
-2 | * Identify entry conditions for 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL. | ||
-2 to establish the following conditions: | US | ||
BOP | * Notify SM of plant status and procedure entry. | ||
Control 1C FRV (1FW530) in manual. | * Request SM evaluation of Emergency Plan conditions. | ||
Restore SG level to stable condition. | * Enter/implement 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL, ATTACHMENT G FEEDWATER FLOW CHANNEL FAILURE and direct operator actions of 1BwOA INST-2 to establish the following conditions: | ||
Select operable feed flow channel (1BwPR 1 SG action). | BOP | ||
Establish/verify automatic SG level control. | * Stabilize 1C SG level (actions to stabilize per 1BwPR 1-15-SG initially, then 1BwOA INST-2). | ||
Check reactor power <100% (if > 100 | * If SG level abnormal: | ||
%, reduce turbine load | * Control 1C FRV (1FW530) in manual. | ||
): | * Restore SG level to stable condition. | ||
* Select operable feed flow channel (1BwPR 1-15-SG action). | |||
1HD046A & B position normal. | * Establish/verify automatic SG level control. | ||
* Check reactor power <100% (if > 100%, reduce turbine load): | |||
* PPC 10 min. calorimetric. | |||
* Computer point (U0923). | |||
* NIs. | |||
* Check HD system operation: | |||
* 1HD046A & B position normal. | |||
Comments: | |||
151 NRC 3 Page 9 | |||
Scenario NRC 3 Event 2 No: No. | |||
Event Feed flow channel, 1FT-530, fails low | |||
== Description:== | == Description:== | ||
Time Position Applicants Actions or Behavior US | |||
* Notify SM/maintenance to investigate/correct the failed feed flow channel: | |||
Determines Tech Specs are NOT applicable. | * Determines Tech Specs are NOT applicable. | ||
Contact SM to perform risk assessment, initiate IR, reactivity screening, notify QNE and contact maintenance to investigate/correct instrument failure. | * Contact SM to perform risk assessment, initiate IR, reactivity screening, notify QNE and contact maintenance to investigate/correct instrument failure. | ||
Contact SM to make appropriate personnel notifications. | * Contact SM to make appropriate personnel notifications. | ||
EXAMINERS NOTE: After the feed flow channel failure actions are complete and with Lead Examiners concurrence, enter next event. | |||
Comments: | |||
151 NRC 3 Page 10 | |||
Scenario NRC 3 Event 3 No: No. | |||
Event 1A CV pump shaft shear | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior CUE | |||
* Annunciator CHG LINE FLOW HIGH/LOW (1-9-D3) | |||
* Annunciator RCP SEAL WATER INJ FLOW LOW (1-7-B2) | |||
Low amps on the 1A CV pump. | * Annunciator REGEN HX LTDWN TEMP HIGH (1-9-A1) | ||
ATC | * PZR level lowering. | ||
Report failure to US. | * Low amps on the 1A CV pump. | ||
o May isolate letdown per BwAR 1 A1, hard card 1BwPR 1-9-LD or 1BwOA | ATC | ||
CREW | * Identify 1A CV pump has low amps at 1PM05J. | ||
o Identify entry conditions for 1BwOA PRI | * Report failure to US. | ||
-15 | o May isolate letdown per BwAR 1-9-A1, hard card 1BwPR 1-9-LD or 1BwOA PRI-15 Operator Action Summary page by closing 1CV8149A/B/C and 1CV459/460. | ||
CREW | |||
US Enter 1BwOA PRI | * Reference BwARs as time permits. | ||
-15 to start 1B CV pump. | o Identify entry conditions for 1BwOA PRI-15 LOSS OF NORMAL CHARGING. | ||
Notify Shift Manager of plant status and procedure entry. | * Dispatch operator to investigate cause of 1A CV pump low amps. | ||
Request SM evaluation of Emergency Plan conditions. | US Enter 1BwOA PRI-15 to start 1B CV pump. | ||
Implement 1BwOA PRI | * Notify Shift Manager of plant status and procedure entry. | ||
-15 and direct operator actions of 1BwOA PRI | * Request SM evaluation of Emergency Plan conditions. | ||
-15 to establish the following conditions: | * Implement 1BwOA PRI-15 and direct operator actions of 1BwOA PRI-15 to establish the following conditions: | ||
o Enter Tech Spec 3.4.1 Condition A if PZR pressure < 2209 psig. | o Enter Tech Spec 3.4.1 Condition A if PZR pressure < 2209 psig. | ||
EXAMINERS NOTE: Crew may stop the 1A CV pump due to abnormal indications. | |||
ATC | ATC Perform the following at 1PM05J: | ||
Check CV pump status: | * Check CV pump status: | ||
o If one CV pump is running (CV pump may or may not be tripped before entering the 1BwOA PRI-15). Check CV pump parameters any fluctuating | o If one CV pump is running (CV pump may or may not be tripped before entering the 1BwOA PRI-15). | ||
- | * Check CV pump parameters any fluctuating - NO. | ||
-120A is less than RCS pressure: | * CV pump discharge pressure on 1PI-120A is less than RCS pressure: | ||
Place 1CV121 controller to manual. | * Place 1CV121 controller to manual. | ||
Place 1A CV pump C/S in PULL OUT. | * Place 1A CV pump C/S in PULL OUT. | ||
Start 1B CV pump. | * Start 1B CV pump. | ||
Place 1CV121 controller in auto (if desired) | * Place 1CV121 controller in auto (if desired). | ||
OR ATC o If NEITHER CV pump is running. | |||
Place 1A CV pump C/S in PULL OUT. | * Place 1A CV pump C/S in PULL OUT. | ||
Isolate normal letdown: | * Isolate normal letdown: | ||
Comments: | |||
151 NRC 3 Page 11 | |||
Scenario NRC 3 Event 3 No: No. | |||
Event 1A CV pump shaft shear | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior | |||
* CLOSE 1CV8149A, B & C, letdown orifice isolation valves. | |||
* CLOSE 1CV459 & 1CV460, letdown isolation valves. | |||
* Check VCT status: | |||
* Check 1CV112B & 1CV112C, VCT suction valves, OPEN. | |||
* Maintain VCT level greater than 20%. | |||
Check VCT status: | |||
Check 1CV112B & 1CV112C, VCT suction valves, OPEN. | |||
Maintain VCT level greater than 20%. | |||
o Operate RMCS in automatic or manual to maintain VCT level > 20%. | o Operate RMCS in automatic or manual to maintain VCT level > 20%. | ||
Check annunciator 1 C2, VCT TEMP HIGH | * Check annunciator 1-9-C2, VCT TEMP HIGH - NOT lit. | ||
- NOT lit. o Acknowledge RM | o Acknowledge RM-11 alarm caused by isolating flow to 1PR06J, Gross Failed Fuel Monitor. | ||
-11 alarm caused by isolating flow to 1PR06J, Gross Failed Fuel Monitor. Perform the following at 1PM05J: | ATC Perform the following at 1PM05J: | ||
Check for gas binding of previously running CV pump by verifying the following trends NOT fluctuating prior to pump trip (may use PPC trends): | * Check for gas binding of previously running CV pump by verifying the following trends NOT fluctuating prior to pump trip (may use PPC trends): | ||
RCP #1 seal leak off flows. | * RCP #1 seal leak off flows. | ||
CV pump flow. | * CV pump flow. | ||
CV pump discharge pressure. | * CV pump discharge pressure. | ||
CV pump amps. | * CV pump amps. | ||
Restore charging flow: | * Restore charging flow: | ||
Check 1CV8110 & 1CV8116, 1B CV pump miniflow isolation valves | * Check 1CV8110 & 1CV8116, 1B CV pump miniflow isolation valves - OPEN. | ||
- OPEN. Check RCS pressure approximately 2235 psig. | * Check RCS pressure approximately 2235 psig. | ||
Start 1B CV pump. | * Start 1B CV pump. | ||
ATC | ATC | ||
Verify | * Check CV System Alignment: | ||
- OPEN. Verify 1CV8324A, charging to regen HX 1A isolation valve | * Verify 1CV8147, charging to RC 1A loop isolation valve - OPEN. | ||
- OPEN. Verify/open 1CV8105 and 1CV8106, charging line CNMT isolation valves. | * Verify 1CV8324A, charging to regen HX 1A isolation valve - OPEN. | ||
Check charging flow established (charging flow may be at minimum for RCP seal injection due to letdown isolation). | * Verify/open 1CV8105 and 1CV8106, charging line CNMT isolation valves. | ||
Determine normal letdown is isolated (restore letdown, see next page). | * Check charging flow established (charging flow may be at minimum for RCP seal injection due to letdown isolation). | ||
* Determine normal letdown is isolated (restore letdown, see next page). | |||
o Monitor RMCS during automatic VCT makeup: | o Monitor RMCS during automatic VCT makeup: | ||
o Proper flow on PW/Total Flow (1FT | o Proper flow on PW/Total Flow (1FT-0111) and Boric Acid Flow (1FT-0110) on recorder 1FR-0110. | ||
-0111) and Boric Acid Flow (1FT | CREW | ||
-0110) on recorder 1FR | * Identify entry conditions for 1BwOA ESP-2 REESTABLISHING CV LETDOWN DURING ABNORMAL CONDITIONS. | ||
-0110. | US | ||
-2 | * Notify Shift Manager of plant status and procedure entry. | ||
* Implement 1BwOA ESP-2 REESTABLISHING CV LETDOWN DURING ABNORMAL CONDITIONS, and direct operator actions of 1BwOA ESP-2 to establish the following conditions: | |||
Implement 1BwOA ESP | Comments: | ||
-2 | 151 NRC 3 Page 12 | ||
-2 to establish the following conditions: | |||
Scenario NRC 3 Event 3 No: No. | |||
Event 1A CV pump shaft shear | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior BOP Restore normal letdown using 1BwOA ESP-2 as directed by performing the following at 1PM05J: | |||
* Check letdown isolated: | |||
* Verify 1CV8149A, B, & C, letdown orifice isolation valves - CLOSED. | |||
* Verify 1CV459 & 1CV460, letdown line isolation valves - CLOSED. | |||
* Check letdown flow path: | |||
* Verify 1CV8401A, letdown HX 1A isolation valve - OPEN. | |||
* Verify 1CV8324A, charging to regen HX 1A isolation valve - OPEN. | |||
* Verify 1CV8389A, letdown to regen HX 1A isolation valve - OPEN. | |||
* Verify 1CV8152 & 1CV8160, letdown line CNMT isolation valves - OPEN. | |||
* Verify BTRS mode select switch OFF light - LIT. | |||
* Align letdown controllers: | |||
* Place 1PK-131, letdown line pressure controller, in MANUAL and raise demand to 40%. | |||
* Place 1CC130A, letdown HX outlet temperature controller, in MANUAL and raise demand to 60%. | |||
* Verify charging flow established: | |||
* Verify 1CV8105 and 1CV8106, charging line CNMT isolation valves - OPEN. | |||
* Throttle 1CV182, charging header backpressure control valve, to establish 8-13 gpm RCP seal injection flow. | |||
* Place 1FK-121, in manual and operate 1FK-121 in manual to establish > 100 gpm charging flow on 1FI-121A. | |||
* Establish letdown flow: | |||
* OPEN 1CV459 & 1CV460, letdown line isolation valves. | |||
* OPEN 1CV8149A/B/C, letdown orifice isolation valves, as necessary to establish 120 gpm letdown flow. | |||
* Lower demand on 1PK-131, letdown line pressure controller, to raise letdown pressure to approximately 360 psig on 1PI-131. | |||
* Operate 1FK-121 in manual to restore PZR level to normal operating band and maintain 8-13 gpm RCP seal injection flow. | |||
* Lower demand on 1CC130A, to control letdown temperature between 90° to 115°F on 1TI-130. | |||
* Place 1PK-131, letdown line pressure controller, in AUTO. | |||
* Place 1CC130A, letdown HX outlet temperature controller, in AUTO. | |||
* At the RM-11, verify 1PR06J rad monitor status is GREEN. | |||
Comments: | |||
151 NRC 3 Page 13 | |||
1A CV pump shaft shear | Scenario NRC 3 Event 3 No: No. | ||
Event 1A CV pump shaft shear | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior US | |||
* Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure. | |||
* Determine Tech Spec 3.5.2 Condition A is applicable. | |||
* Determine TRM 3.1.d Condition A is applicable. | |||
EXAMINERS NOTE: After the 1A CV pump shaft shear actions are complete and with Lead Examiners concurrence, enter next event. | |||
Determine Tech Spec 3.5.2 Condition A is applicable. | Comments: | ||
Determine TRM 3.1.d Condition A is applicable. | 151 NRC 3 Page 14 | ||
Comments: | |||
Scenario NRC 3 Event 4 No: No. | |||
Event 1A Essential Service Water (SX) pump trip | |||
== Description:== | == | ||
Description:== | |||
Time Position Applicants Actions or Behavior EXAMINERS NOTE: The crew will start the standby SX pump per hard card 1BwPR 1-2-A1, BwAR 1-2-A1 OR MAY elect to enter 1BwOA PRI-8 ESSENTIAL SERVICE WATER MALFUNCTION to address the 1A SX pump trip. Actions for 1BwOA PRI-8 start in italics below. | |||
-8 | CUE | ||
-8 start in italics below. | * Annunciator SX PUMP TRIP (1-2-A1) | ||
CUE | * Annunciator SX PUMP DSCH HDR PRESS LOW (1-2-A2) | ||
- LIT. BOP | * 1A SX pump trip light - LIT. | ||
Use hard card 1BwPR 1 A1 to perform the following actions: | BOP | ||
Start the standby (1B) SX pump (1SX001B/16B/27B must be open to allow a manual pump start). | * Determine 1A SX pump tripped. | ||
Place 1B SX pump control switch to start and hold until the lube oil pressure interlock is met and 1B SX pump starts. | * Use hard card 1BwPR 1-2-A1 to perform the following actions: | ||
BOP | * Start the standby (1B) SX pump (1SX001B/16B/27B must be open to allow a manual pump start). | ||
Verify 1B SX pump started. | * Place 1B SX pump control switch to start and hold until the lube oil pressure interlock is met and 1B SX pump starts. | ||
Verify voltage on ALL 3 phases on 4KV bus > 3990 volts. | BOP | ||
If SX flow cannot be restored, enter 1BwOA PRI | * Reference BwAR 1-2-A1, SX PUMP TRIP: | ||
-8 | * Verify 1B SX pump started. | ||
* Verify voltage on ALL 3 phases on 4KV bus > 3990 volts. | |||
o Refer to BwOP SX | * If SX flow cannot be restored, enter 1BwOA PRI-8 ESSENTIAL SERVICE WATER MALFUNCTION. | ||
-1/2. o Verify annunciator SX PUMP DSCH HDR PRESS LOW (1 A2) is NOT LIT. | o Place 1A SX pump C/S in PTL. | ||
o Restart the 1A containment chiller. | o Refer to BwOP SX-1/2. | ||
ATC o Refer to BwARs as time permits. | o Verify annunciator SX PUMP DSCH HDR PRESS LOW (1-2-A2) is NOT LIT. | ||
o Dispatch EO to 1A & 1B SX pumps. | o Restart the 1A containment chiller. | ||
US | ATC o Refer to BwARs as time permits. | ||
Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct failure. | o Dispatch EO to 1A & 1B SX pumps. | ||
o Inform Unit 2 to swap SX pumps for proper Chem Feed alignment. | US | ||
CREW 1BwOA PRI-8 | * Determine Tech Spec 3.7.8 Condition A is applicable. | ||
-8 | * Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct failure. | ||
o Inform Unit 2 to swap SX pumps for proper Chem Feed alignment. | |||
CREW 1BwOA PRI-8 ESSENTIAL SERVICE WATER MALFUNCTION o Identify entry conditions for 1BwOA PRI-8 ESSENTIAL SERVICE WATER MALFUNCTION. | |||
o Dispatch operators to investigate status of 1A SX pump and breaker. | o Dispatch operators to investigate status of 1A SX pump and breaker. | ||
Comments: | |||
151 NRC 3 Page 15 | |||
Scenario NRC 3 Event 4 No: No. | |||
Event 1A Essential Service Water (SX) pump trip | |||
== | |||
Description:== | |||
== Description:== | |||
Time Position Applicants Actions or Behavior US o Notify SM of plant status and procedure entry. | |||
o Request SM evaluation of Emergency Plan conditions. | o Request SM evaluation of Emergency Plan conditions. | ||
o Enter/implement 1BwOA PRI | o Enter/implement 1BwOA PRI-8 and direct operator actions to establish the following conditions: | ||
-8 and direct operator actions to establish the following conditions: | CREW o Check for excessive leakage in Aux Building: | ||
CREW | o Contact Radwaste to monitor Aux Building sumps. | ||
o Annunciator SX PUMP SUCT VLV PIT LEVEL HIGH (1 D2) - NOT LIT. BOP o Check status of SX pumps at 1PM06J: | o Annunciator SX PUMP SUCT VLV PIT LEVEL HIGH (1-2-D2) - NOT LIT. | ||
BOP o Check status of SX pumps at 1PM06J: | |||
o Start 1B SX pump if not already running. | o Start 1B SX pump if not already running. | ||
o Check status of SX system at 1PM06J: | o Check status of SX system at 1PM06J: | ||
o Annunciator SX PUMP SUCT PRESS LOW (1 C1) - NOT LIT. o Annunciator SX STRN DP HIGH (1 C2) - NOT LIT. o Annunciator SX PUMP DSCH HDR PRESS LOW (1 A2) - NOT LIT. o Annunciator SX PUMP DSCH HDR TEMP HIGH LOW (1-2-B2) - NOT LIT. o 1A SX pump NOT rotating backwards. | o Annunciator SX PUMP SUCT PRESS LOW (1-2-C1) - NOT LIT. | ||
o Check for SX leakage into containment at 1PM06J: | o Annunciator SX STRN DP HIGH (1-2-C2) - NOT LIT. | ||
o Annunciator CNMT DRAIN LEAK DETECT FLOW HIGH (1 A2) - NOT LIT. o Check CC outlet temperatures < | o Annunciator SX PUMP DSCH HDR PRESS LOW (1-2-A2) - NOT LIT. | ||
-674, 0TI-675). o Check RCP cooling at 1PM05J: | o Annunciator SX PUMP DSCH HDR TEMP HIGH LOW (1-2-B2) - NOT LIT. | ||
o Annunciator RCP THERM BARR CC WTR TEMP HIGH (1 E3) - NOT LIT. o Annunciator RCP BRNG CC WTR TEMP HIGH (1 E5) - NOT LIT. US o Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure. o Determine Tech Spec 3.7.8 Condition A is applicable. | o 1A SX pump NOT rotating backwards. | ||
o Check for SX leakage into containment at 1PM06J: | |||
o Annunciator CNMT DRAIN LEAK DETECT FLOW HIGH (1-1-A2) - NOT LIT. | |||
o Check CC outlet temperatures < 105°F at 1PM06J (1TI-674, 0TI-675). | |||
o Check RCP cooling at 1PM05J: | |||
o Annunciator RCP THERM BARR CC WTR TEMP HIGH (1-7-E3) - NOT LIT. | |||
o Annunciator RCP BRNG CC WTR TEMP HIGH (1-7-E5) - NOT LIT. | |||
US o Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure. | |||
o Determine Tech Spec 3.7.8 Condition A is applicable. | |||
EXAMINERS NOTE: After the actions for the 1A SX pump trip are complete and with Lead Examiners concurrence, insert next event. | |||
Comments: | |||
151 NRC 3 Page 16 | |||
Scenario NRC 3 Event 5 No: No. | |||
Event Master pressurizer pressure controller output fails to 2195 psig (0% demand) | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior CUE | |||
* Annunciator PZR PRESS CONT DEV LOW HTRS ON (1-12-C1) | |||
* PZR pressure, 1PI-455A/456/457/458, rising. | |||
Time Position | * Master PZR pressure controller demand at 0%. | ||
, 1PI-455A/456/457/458 | ATC | ||
, rising. Master PZR pressure controller demand at 0%. ATC | * Identify/report failure of Master pressurizer pressure controller. | ||
Perform actions per BwAR 1 C1: | * Perform actions per BwAR 1-12-C1: | ||
Verify PZR spray valves closed. | * Monitor PZR pressure and level channels. | ||
Check PZR heaters for proper operation. | * Verify PZR spray valves closed. | ||
Take manual control to restore PZR pressure - place 1PK-455A in manual and raise demand prior to PZR PORVs automatically opening. | * Check PZR heaters for proper operation. | ||
Control PZR pressure manually throughout scenario. | * Take manual control to restore PZR pressure - place 1PK-455A in manual and raise demand prior to PZR PORVs automatically opening. | ||
* Control PZR pressure manually throughout scenario. | |||
- 15 psig). CREW o Refer to other BwARs as time permits. | EXAMINERS NOTE: The crew should establish a normal pressure control band to maintain (approximately 2235 psig +/- 15 psig). | ||
US o | CREW o Refer to other BwARs as time permits. | ||
Notify SM of plant status and the need for maintenance assistance. | US o Enter Tech Spec 3.4.1 Condition A if PZR pressure drops below 2209 psig. | ||
* Notify SM of plant status and the need for maintenance assistance. | |||
Comments: | EXAMINERS NOTE: After the actions for the Master Pressurizer Pressure Controller failure are complete and with Lead Examiners concurrence, insert next event. | ||
Comments: | |||
151 NRC 3 Page 17 | |||
Scenario NRC 3 Event 6&7 No: No. | |||
Event | |||
== Description:== | == Description:== | ||
Lowering condenser vacuum requires load to be lowered with rods only due to boric acid transfer pump trip and common boric acid pump unavailable Time Position Applicants Actions or Behavior CUE | |||
* Annunciator SECONDARY SAMPLING PANEL/SINK TROUBLE (1-1-B7) | |||
* Exhaust hood, 1PI-ES043/46/49, (condenser pressure) rising/degrading. | |||
* Annunciator CNDSR VACUUM LOW (1-18-D4) | |||
BOP | |||
* Recommend entry to 1BwOA SEC-3 LOSS OF CONDENSER VACUUM. | |||
US | |||
* Direct actions of 1BwOA SEC-3. | |||
* Notify Shift Manager of plant status and procedure entry. | |||
* Request SM evaluation of Emergency Plan conditions. | |||
* Notify Engineering to track condenser pressure. | |||
BOP | |||
* Check CW system: | |||
* CW flow normal - NO. | |||
* 1B CW pump discharge valve closed. | |||
* 1A/1C CW pump discharge valves open. | |||
* With condenser pressure rising, perform the following to reduce turbine load to stabilize condenser pressure (use U-1 Contingency ReMAs Op Aid for guidance): | |||
* Select SETPOINT. | |||
* Set REFERENCE DEMAND: | |||
* Select REF DEMAND. | |||
* Enter desired value. | |||
* Select left ENTER. | |||
* Set LOAD RATE: | |||
* Select RATE. | |||
* Enter desired rate. | |||
* Select right ENTER. | |||
* Initiate ramp: | |||
* Select GO/HOLD. | |||
* Select GO. | |||
BOP | |||
* Monitor condenser pressure: | |||
* Check Figure 1BwOA SEC-3-1 for acceptable operation. | |||
* Check condenser pressure > 5.5 HgA. | |||
* Check DEHC - MW OUT SELECTED. | |||
ATC | |||
* Prepare reactivity plan to recommend to US for ramp (use U-1 Contingency ReMAs Op Aid for guidance). | |||
Comments: | |||
151 NRC 3 Page 18 | |||
Scenario NRC 3 Event 6&7 No: No. | |||
Event | |||
== Description:== | == Description:== | ||
Lowering condenser vacuum requires load to be lowered with rods only due to boric acid transfer pump trip and common boric acid pump unavailable Time Position Applicants Actions or Behavior | |||
Lowering condenser vacuum requires load to be lowered with rods only due to boric acid transfer pump trip and common boric acid pump unavailable Time Position | * Determine required boric acid volume. | ||
Borate in Automatic (BwOP CV-6 hard card): | Borate in Automatic (BwOP CV-6 hard card): | ||
o Turn on PZR backup heaters to equalize boron concentration. | o Turn on PZR backup heaters to equalize boron concentration. | ||
Set 1FY-0110 BA Blender Predet Counter to desired value. | * Set 1FY-0110 BA Blender Predet Counter to desired value. | ||
Set 1FK-110 BA Flow Control to desired boration rate Place MAKE | * Set 1FK-110 BA Flow Control to desired boration rate | ||
-UP MODE CONT SWITCH to STOP position. | * Place MAKE-UP MODE CONT SWITCH to STOP position. | ||
Place MODE SELECT SWITCH to BORATE position. | * Place MODE SELECT SWITCH to BORATE position. | ||
Place MAKE | * Place MAKE-UP MODE CONT SWITCH to START. | ||
-UP MODE CONT SWITCH to START. | * Verify the following occurs: | ||
Verify the following occurs: | * 1CV110B opens. | ||
1CV110B opens. | * 1CV110A opens. | ||
1CV110A opens. | * BA pump starts. | ||
BA pump starts. | * Proper BA flow on recorder 1FR-110. | ||
Proper BA flow on recorder 1FR | * When desired boration is achieved, place MAKE-UP MODE CONT SWITCH to STOP. | ||
-110. When desired boration is achieved, place MAKE | * Verify the following occurs: | ||
-UP MODE CONT SWITCH to STOP. Verify the following occurs: | * 1CV110B closes. | ||
1CV110B closes. | * 1CV110A closes. | ||
1CV110A closes. | * BA pump stops. | ||
BA pump stops. | * Record time and amount of BA addition. | ||
Record time and amount of BA addition. | * Perform BwOP CV-7 to return RMCS to AUTO following the final boration. | ||
Perform BwOP CV | OR Batch addition of Boric Acid (BwOP CV-6 hard card): | ||
-7 to return RMCS to AUTO following the final boration. | |||
OR Batch addition of Boric Acid (BwOP CV | |||
-6 hard card): | |||
o Turn on PZR backup heaters to equalize boron concentration. | o Turn on PZR backup heaters to equalize boron concentration. | ||
o Momentarily depress RESET pushbutton on BA Flow totalizer. | o Momentarily depress RESET pushbutton on BA Flow totalizer. | ||
Open 1CV110B. | * Open 1CV110B. | ||
Open 1CV110A. | * Open 1CV110A. | ||
Start the BA Transfer Pump. | * Start the BA Transfer Pump. | ||
o If desired, control VCL level by adjusting 1LK | o If desired, control VCL level by adjusting 1LK-112 setpoint to desired value. | ||
-112 setpoint to desired value. | * When desired amount of BA has been added, stop the BA Transfer Pump | ||
When desired amount of BA has been added, stop the BA Transfer Pump Close 1CV110A | * Close 1CV110A. | ||
* Close 1CV110B. | |||
* Verify VCT level/pressure at desired value and adjust 1LK-112 setpoint to desired corresponding level setpoint. | |||
-112 setpoint to desired corresponding level setpoint. | * Place 1CV110A/1CV110B in AUTO. | ||
Place 1CV110A/1CV110B in AUTO. | * Record time and amount of BA addition. | ||
Record time and amount of BA addition. | * Perform BwOP CV-7 to return RMCS to AUTO following the final boration. | ||
Perform BwOP CV | o May flush boric acid lines per BwOP CV-6 step. F.5. | ||
-7 to return RMCS to AUTO following the final boration. | * When the U-1 boric acid transfer pump trips, attempt to align to the U-0 boric acid Comments: | ||
o May flush boric acid lines per BwOP CV | 151 NRC 3 Page 19 | ||
-6 step. F.5. | |||
When the U | |||
-1 boric acid transfer pump trips, attempt to align to the U | |||
-0 boric acid Comments: | |||
Scenario NRC 3 Event 6&7 No: No. | |||
Event | |||
== Description:== | == Description:== | ||
Lowering condenser vacuum requires load to be lowered with rods only due to boric acid transfer pump trip and common boric acid pump unavailable Time Position Applicants Actions or Behavior transfer pump. | |||
* After the U-1 boric transfer pump trip, continue load ramp on rods only. | |||
BOP | |||
* Bypass CP demins: | |||
* Open 1CD210A/B. | |||
* Restore condenser vacuum: | |||
o Start at least one hogging vacuum pump. | |||
o Place 2nd set of air ejectors in-service. | |||
* Check condenser pressure: | |||
* Acceptable per Figure 1BwOA SEC-3-1. | |||
* Condenser pressure stable or dropping. | |||
* Check C-9 bypass permissive light - NOT LIT. | |||
* Identify and isolate leak. | |||
US | |||
* Request Chemistry to check dissolved oxygen levels. | |||
* Determine condenser status. | |||
* Contact SM to perform risk assessment, initiate IR, reactivity screening and contact maintenance to investigate/correct instrument failure. | |||
EXAMINERS NOTE: After an acceptable load ramp has occurred and with Lead Examiners concurrence, insert next event. | |||
Comments: | |||
151 NRC 3 Page 20 | |||
Scenario NRC 3 Event 8 No: No. | |||
Event Inadvertent FWI & feed line break inside containment | |||
== Description:== | |||
. | |||
Comments: | Time Position Applicants Actions or Behavior CUE | ||
* Annunciator FWIV NOT FULL OPEN (1-1-A4) (1-15-E7) | |||
* FWI monitor lights - ALL lit. | |||
CREW | |||
* Recognize a FWI has occurred and conditions requiring a manual reactor trip exist. | |||
US | |||
* Direct a manual Rx trip. | |||
* Notify SM of plant status and procedure entry. | |||
* Request SM evaluation of Emergency Plan conditions. | |||
* Implement 1BwEP-0 "REACTOR TRIP OR SI. | |||
* Direct operator actions of 1BwEP-0 to establish the following conditions: | |||
ATC Perform immediate operator actions of 1BwEP-0 at 1PM05J: | |||
* Verify reactor trip: | |||
* Rod bottom lights - ALL LIT. | |||
* Reactor trip & Bypass breakers - OPEN. | |||
* Neutron flux - DROPPING. | |||
BOP Perform immediate operator actions of 1BwEP-0 at 1PM02J or OWS drop 210: | |||
* Verify turbine trip: | |||
* All Turbine throttle valves - CLOSED. | |||
* All Turbine governor valves - CLOSED. | |||
BOP Perform immediate operator actions of 1BwEP-0 at 1PM01J: | |||
* Verify power to 4KV busses: | |||
* ESF Buses - BOTH ENERGIZED. | |||
CREW Perform immediate operator actions of 1BwEP-0 at 1PM05J: | |||
* Check SI Status (Cnmt pressure SI/1C SG pressure cannot be maintained > 640 psig). | |||
* SI First OUT annunciator - LIT. | |||
* SI ACTUATED Permissive Light - LIT. | |||
* SI Equipment - AUTOMATICALLY ACTUATED: | |||
o Either SI pump - RUNNING. | |||
o Either CV pump to cold leg isolation valve OPEN - 1SI8801A/B. | |||
* Manually actuate SI at 1PM05J & 1PM06J. | |||
Comments: | |||
151 NRC 3 Page 21 | |||
Scenario NRC 3 Event 9 & 10 No: No. | |||
Event Feed line break inside containment & loss of heat sink/1B CV pump trip | |||
== Description:== | == Description:== | ||
Time Position Applicants Actions or Behavior EXAMINERS NOTE: Per the 1BwEP-0 Operator Action Summary page, RCP trip criteria is applicable throughout the performance of 1BwEP-0. The crew may trip RCPs whenever the criteria of RCS pressure <1425 psig AND high head SI flow | |||
>100 gpm are recognized. | |||
EXAMINERS NOTE: US and ATC will continue in 1BwEP-0 while BOP is performing Attachment B. | |||
BOP 1BwEP-0 ATTACHMENT B: | |||
* Verify FW isolated at 1PM04J: | |||
* FW pumps - TRIPPED. | |||
* FW isolation monitor lights - LIT. | |||
-0 | * FW pumps discharge valves - CLOSED (or going closed) 1FW002A-C. | ||
* Verify DGs running at 1PM01J: | |||
* DGs - BOTH RUNNING. | |||
* 1SX169A/B OPEN. | |||
* Dispatch operator locally to check operation. | |||
- | * Verify Generator Trip at 1PM01J: | ||
- | * OCB 1-8 and 7-8 open. | ||
- | * PMG output breaker open. | ||
* Verify Control Room ventilation aligned for emergency operations at 0PM02J: | |||
* VC Rad Monitors - LESS THAN HIGH ALARM SETPOINT. | |||
- | * Operating VC train equipment - RUNNING. | ||
* 0B Supply fan | |||
* 0B Return fan | |||
Verify | * 0B M/U fan | ||
* 0B Chilled water pump | |||
- | * 0B Chiller | ||
* Operating VC train dampers - ALIGNED. | |||
- | * M/U fan outlet damper - 0VC08Y NOT FULLY CLOSED. | ||
* 0B VC train M/U filter light - LIT. | |||
- LIT. | * 0VC09Y - OPEN. | ||
* 0VC313Y - CLOSED. | |||
- | * Operating VC train Charcoal Absorber aligned for train B. | ||
* 0VC44Y - CLOSED. | |||
- | * 0VC05Y - OPEN. | ||
- | * 0VC06Y - OPEN. | ||
* Control Room pressure greater than +0.125 inches water on 0PDI-VC038. | |||
Comments: | |||
151 NRC 3 Page 22 | |||
Scenario NRC 3 Event 9 & 10 No: No. | |||
Event Feed line break inside containment & loss of heat sink/1B CV pump trip | |||
== Description:== | |||
Time Position Applicants Actions or Behavior | |||
* Verify Auxiliary Building ventilation aligned for emergency operations at 0PM02J: | |||
Two inaccessible filter plenums aligned. | * Two inaccessible filter plenums aligned. | ||
Plenum A: | * Plenum A: | ||
0VA04CB - RUNNING. 0VA055Y - OPEN. 0VA062Y - OPEN. 0VA435Y - | * 0VA03CB - RUNNING. | ||
* 0VA023Y - OPEN. | |||
* 0VA436Y - CLOSED. | |||
ATC | * Plenum C: | ||
* 0VA03CF - RUNNING. | |||
* 0VA072Y - OPEN. | |||
* 0VA438Y - CLOSED. | |||
* Verify FHB ventilation aligned for emergency operation at 0PM02J: | |||
* 0VA04CB - RUNNING. | |||
* 0VA055Y - OPEN. | |||
* 0VA062Y - OPEN. | |||
* 0VA435Y - CLOSED. | |||
* Secure all running HD pumps. | |||
* Initiate periodic monitoring of Spent Fuel Cooling. | |||
* Notify US Attachment B complete/manual actions taken. | |||
ATC | |||
* Verify ECCS pumps running at 1PM05J/1PM06J: | |||
* BOTH CV pumps - NONE RUNNING (1B tripped). | |||
* BOTH RH pumps - RUNNING. | |||
* SI pumps - 1A SI pump RUNNING. | |||
* Manually START 1B SI pump. | |||
* Verify the following at 1PM06J: | |||
* RCFCs running in accident mode. | |||
* Group 2 RCFC accident mode status light lit. | |||
* CNMT Phase A valves closed - NO. | |||
* Manually actuate Phase A. | |||
Close containment isolation valves such that at least one valve is closed on each Phase A penetration before the end of the scenario. (Westinghouse CT-11) (K/A number APE069AA1.01 importance 3.5/3.7) | |||
[CT-11] | |||
* Manually close 1CV8100 and/or 1CV8112. | |||
* Manually close the following valves: | |||
* 1FP010 | |||
* 1CV8152/8160 | |||
* 1IA065/066 | |||
* 1PS228A, 228B, 229A & 229B | |||
* 1PR001A/B Comments: | |||
151 NRC 3 Page 23 | |||
Scenario NRC 3 Event 9 & 10 No: No. | |||
Event Feed line break inside containment & loss of heat sink/1B CV pump trip | |||
== Description:== | |||
Time Position Applicants Actions or Behavior | |||
* Verify Cnmt Vent isolation: | |||
* Group 6 Cnmt Vent Isol monitor lights - LIT. | |||
Verify Cnmt Vent isolation: | * Verify AF system: | ||
Group 6 Cnmt Vent Isol monitor lights | * AF pumps - Neither RUNNING. | ||
- LIT. Verify AF system: | * Attempt manual start of BOTH AF pumps. | ||
AF pumps - Neither RUNNING. Attempt manual start of BOTH AF pumps. | |||
o Dispatch EO to BOTH AF pumps. | o Dispatch EO to BOTH AF pumps. | ||
AF isolation valves | * AF isolation valves - 1AF13A-H OPEN. | ||
- 1AF13A-H OPEN. AF flow control valves | * AF flow control valves - 1AF005A-D OPEN. | ||
- 1AF005A-D OPEN. Verify CC pumps running: | * Verify CC pumps running: | ||
BOTH CC pumps | * BOTH CC pumps - RUNNING. | ||
- RUNNING. Verify SX pumps running: | * Verify SX pumps running: | ||
BOTH SX pumps | * BOTH SX pumps - RUNNING. | ||
- RUNNING. ATC | ATC | ||
1C S/G pressure < 640 psig at 1PM04J. | * Check if Main Steamlines Should Be Isolated: | ||
CNMT pressure > 8.2 psig at 1PM06J. | * 1C S/G pressure < 640 psig at 1PM04J. | ||
Verify MSIV & MSIV bypass valves | * CNMT pressure > 8.2 psig at 1PM06J. | ||
- CLOSED. CREW | * Verify MSIV & MSIV bypass valves - CLOSED. | ||
ATC | CREW | ||
* Determine and announce containment is adverse when containment pressure rises above 5 psig. | |||
AF flow < 500 gpm | ATC | ||
* Check if CS is required. | |||
(attempt to start AF pumps previously performed). | * CNMT pressure remained < 20 psig. | ||
o May CLOSE | BOP | ||
-H.1 | * Verify total AF flow: | ||
Comments: | * AF flow < 500 gpm. | ||
* Check SG levels < 31% (attempt to start AF pumps previously performed). | |||
o May CLOSE 1AF013C & 1AF013G to isolate CST gravity flow to 1C SG feed line break. | |||
CREW Identify entry conditions for 1BwFR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK. | |||
Comments: | |||
151 NRC 3 Page 24 | |||
Scenario NRC 3 Event 10 No: No. | |||
Event Feed line break inside containment/loss of heat sink | |||
== Description:== | == Description:== | ||
Time Position Applicants Actions or Behavior 1BwFR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK US | |||
* Notify SM of plant status and procedure entry. | |||
* Request SM evaluation of Emergency Plan conditions. | |||
* Request STA evaluation of status trees. | |||
-H.1 and direct operator actions of 1BwFR | * Enter/implement 1BwFR-H.1 and direct operator actions of 1BwFR-H.1 to establish the following conditions: | ||
-H.1 to establish the following conditions | ATC | ||
* Check if secondary heat sink is required: | |||
* RCS pressure > intact SG pressure. | |||
* RCS temperature > 350°F. | |||
ATC | |||
* Check CV pump status: | |||
* CV pumps - NONE RUNNING. | |||
* STOP all RCPs. | |||
* GO TO step 14 (bleed and feed). | |||
ATC | |||
- LIT. ATC | * Establish RCS feed path: | ||
* Actuate SI. | |||
- 1RY8000A & 1RY8000B energized & open | BOP | ||
* Verify RCS feed path: | |||
-46) (K/A number EPEE05EA1.1 importance 4.1/4.0) | * BOTH SI pumps - RUNNING. | ||
* Group 2 cold leg injection monitor lights required for operating ECCS pumps - LIT. | |||
ATC | |||
- BOTH OPEN. | * Establish RCS bleed path: | ||
* PORV isolation valves - 1RY8000A & 1RY8000B energized & open. | |||
Initiate RCS bleed and feed so that the RCS depressurizes sufficiently for SI pump injection to occur. (Westinghouse CT-46) (K/A number EPEE05EA1.1 importance 4.1/4.0) | |||
[CT-46] | |||
* Open BOTH PZR PORVs (1RY455A & 1RY456). | |||
ATC | |||
* Verify adequate RCS bleed path: | |||
* PZR PORVs - BOTH OPEN. | |||
* PORV isolation valves - BOTH OPEN. | |||
EXAMINERS NOTE: (1) All critical tasks are complete at this point; the scenario may be terminated at Lead Examiners discretion. | |||
(2) The following steps address restoring feedwater to the SGs. | (2) The following steps address restoring feedwater to the SGs. | ||
Comments: | |||
151 NRC 3 Page 25 | |||
Scenario NRC 3 Event 10 No: No. | |||
Event Feed line break inside containment/loss of heat sink | |||
== Description:== | == Description:== | ||
Time Position Applicants Actions or Behavior BOP | |||
* Verify ESF equipment actuations. | |||
-0 have been performed. | * Check if ESF actuation verification steps of 1BwEP-0 have been performed. | ||
CREW | CREW | ||
* Maintain RCS heat removal: | |||
* Maintain ECCS flow. | |||
- BOTH OPEN. BOP | * Maintain PZR PORVs - BOTH OPEN. | ||
Depress BOTH SI Reset Pushbuttons at 1PM06J. | BOP | ||
Verify SI ACTUATED PERMISSIVE light NOT lit at 1PM05J. | * Reset SI, if necessary: | ||
Verify AUTO SI BLOCKED PERMISSIVE light LIT at 1PM05J. | * Depress BOTH SI Reset Pushbuttons at 1PM06J. | ||
Reset Cnmt isolation | * Verify SI ACTUATED PERMISSIVE light NOT lit at 1PM05J. | ||
* Verify AUTO SI BLOCKED PERMISSIVE light LIT at 1PM05J. | |||
* Reset Cnmt isolation: | |||
* Reset Phase A. | |||
Open 1IA065 and 1IA066. | * Establish IA to Cnmt: | ||
BOP | * Verify any SAC running. | ||
* Open 1IA065 and 1IA066. | |||
BOP | |||
* Check if CS should be stopped: | |||
* CS pumps - NONE RUNNING. | |||
ATC | |||
* Verify cold leg recirc capability: | |||
-H. Prior to initiating feed flow, review Attachment B | * BOTH RH pumps - RUNNING. | ||
* 1SI8811A/B valve position lights - ENERGIZED. | |||
- OPEN. Check AF pumps | BOP | ||
- NONE RUNNING (1A AF pump has ground overcurrent flag and motor damage; 1B AF pump has large lube oil leak and engine damage). | * Try to establish AF to at least one SG: | ||
AF isolation valves, 1AF013A-H - OPEN. AF flow control valves, 1AF005A-H - THROTTLED/OPEN | * Check blowdown isolation and sample valves closed: | ||
* 1SD005A-D & 1SD002A-H. | |||
- NOT ESTABLISHED | * Prior to initiating feed flow, review Attachment B. | ||
. | * Check annunciator AF PUMP SX SUCT VLVS ARMED (1-3-E7) - NOT LIT. | ||
* Check 1AF004A & B - OPEN. | |||
Comments: | * Check AF pumps - NONE RUNNING (1A AF pump has ground overcurrent flag and motor damage; 1B AF pump has large lube oil leak and engine damage). | ||
* AF isolation valves, 1AF013A-H - OPEN. | |||
* AF flow control valves, 1AF005A-H - THROTTLED/OPEN. | |||
* Check AF flow - NOT ESTABLISHED. | |||
Comments: | |||
151 NRC 3 Page 26 | |||
Scenario NRC 3 Event 10 No: No. | |||
Event Feed line break inside containment/loss of heat sink | |||
== Description:== | == Description:== | ||
Time Position Applicants Actions or Behavior BOP | |||
* Prepare FW system for restoration: | |||
- at least ONE | * Check CD/CB pumps - at least ONE RUNNING. | ||
* Place FW valves in manual at 0% demand. | |||
* 1FW510-540. | |||
* 1FW510A-540A. | |||
* 1FW034A-D. | |||
BOP | |||
* Defeat FW isolation: | |||
- at least TWO RUNNING | * Dispatch U-2 NSO to remove FW isolation fuses. | ||
* FW isolation fuses FU-24 and FU-27 removed at: | |||
* 1PA27J. | |||
* 1PA28J. | |||
- 1FW076 (place C/S in modulate) | BOP | ||
* Establish main FW flow to at least one SG: | |||
- 1FW012A, B & C | * Open 1FW035A/B/D. | ||
* Check FW pumps available. | |||
* Check CD/CB pumps - at least TWO RUNNING. | |||
* Prepare startup FW pump for operation: | |||
* Check Bus 159 - ENERGIZED. | |||
* Locally start aux oil pump. | |||
: Terminate the scenario at Lead | * Open startup FW pump discharge valve - 1FW059. | ||
* Open startup FW pump recirc valve - 1FW076 (place C/S in modulate). | |||
* Close main FW pump recirc valves - 1FW012A, B & C. | |||
* Start startup FW pump. | |||
US | |||
* Prior to initiating FW flow, review Attachment B. | |||
BOP | |||
* Establish main FW flow to at least one SG: | |||
* Throttle 1FW034A/B/D to desired flowrate. | |||
* Maintain hotwell level > 7 inches. | |||
* Check SG WR levels rising. | |||
EXAMINERS NOTE: Terminate the scenario at Lead Examiners discretion. | |||
(Final) | (Final) | ||
Comments: | |||
151 NRC 3 Page 27 | |||
1B SGTR when 1B SG pressure | Simulation Facility Braidwood Scenario Operating Test No.: 151 NRC No.: | ||
< 600 psig 1 TRGSET 3 | NRC 4 Examiners: ______________________ Applicant: _____________________ SRO | ||
______________________ _____________________ ATC | |||
______________________ _____________________ BOP Initial Conditions: IC-16 Turnover: Unit 1 is at 53% power, steady state, equilibrium xenon, MOL. Online risk is green. Following completion of turnover, the crew will perform 1BwOSR 3.7.4.1 MAIN STEAM SYSTEM ISOLATION 1MS018A/B/C/D VALVE TRAVEL AND INDICATION 18 MONTH SURVEILLANCE. Once the surveillance is complete, the SM has directed ramping Unit 1 to 938 MW at 3 MW/min. | |||
2 None R-ATC, US Raise power from | Event Malf. No. Event Event No. Type* Description IMF CV32B 1B CV pump auto start failure TRGSET 1 1A CV pump trip on 1A SI pump start ZLO1SI01PA(3) = = 1 IMF CV01A (1 0) 1A CV pump trips on 1A SI pump start TRGSET 2 ZAO1PI524A < 0.46 IMF TH03B (2 10) 600 60 1B SGTR when 1B SG pressure < 600 psig 1 TRGSET 3 N-BOP, US 1BwOSR 3.7.4.1, 1MS018A/B/C/D Surv with ZAO1PKMS042A > 0.90 TS-US 1MS018B valve failure. | ||
The 1B SG PORV , 1MS018B, will fail the test due to a broken hydraulic line when the valve is stroked open. | IMF PB2411 (3 0) ON IMF PB2412 (3 0) ON IOR ZLO1MS018B2 (3 0) ON IOR ZLO1MS018B1 (3 0) ON IOR ZAO1ZIMS010 (3 0) 90 TRGSET 2 "ZDI1MS018B == 0" TRG 2 "DOR ZAO1ZIMS010" 2 None R-ATC, US Raise power from 53% to 938 MW 3 IMF TH10B 100 15 C-ATC, US 1RY455C spray valve fails open in auto 4 IMF RX13A 0 C-ATC, US PZR level channel, 1LT-459, fails low TS-US 5 IMF RX29B 100 30 I-BOP, US 1FW520 controller fails high in auto 6 IMF FW17 10 30 I-BOP, US HD Tank level controller failure in auto 7 IOR ZDI1MS001B CLS M-ALL 1B MSIV fails closed causing 1B SG safety IMF MS03B 100 valves to stick open IMF MS03F 100 IMF MS03J 100 8 Preload C-ALL 1A CV pump trips/1B CV pump fails to auto start 9 Preload M-ALL 1B SGTR (600 gpm) (faulted and ruptured SG) | ||
The Unit Supervisor will enter Tech Spec 3.7.4 Condition A and Tech Spec 3.6.3 Condition C. 1MS019B will remain closed to comply with TS 3.6.3 Condition C. 1MS018B will remain unavailable for the remainder of the scenario. | *(N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient | ||
The crew should inform the SM following the 1MS018B failure. | |||
After the 1MS018B failure has been addressed, the crew will commence a ramp to 938 MW at 3 MW/min. After a measurable change in power, 1PK-455C , Pressurizer Spray Valve controller | SCENARIO OVERVIEW Unit 1 is at 53% power, steady state, equilibrium xenon, MOL. Online risk is green. Following completion of turnover, the crew will perform 1BwOSR 3.7.4.1 MAIN STEAM SYSTEM ISOLATION 1MS018A/B/C/D VALVE TRAVEL AND INDICATION 18 MONTH SURVEILLANCE. Once the surveillance is complete, the SM has directed ramping Unit 1 to 938 MW at 3 MW/min. | ||
, will fail to 100% demand position. | After completing shift turnover and relief, the BOP performs 1BwOSR 3.7.4.1. The 1B SG PORV, 1MS018B, will fail the test due to a broken hydraulic line when the valve is stroked open. The Unit Supervisor will enter Tech Spec 3.7.4 Condition A and Tech Spec 3.6.3 Condition C. 1MS019B will remain closed to comply with TS 3.6.3 Condition C. 1MS018B will remain unavailable for the remainder of the scenario. The crew should inform the SM following the 1MS018B failure. | ||
1RY455C will fail full open and pressurizer pressure will drop. | After the 1MS018B failure has been addressed, the crew will commence a ramp to 938 MW at 3 MW/min. | ||
The ATC will take manual control of 1PK | After a measurable change in power, 1PK-455C, Pressurizer Spray Valve controller, will fail to 100% | ||
-455C per hard card 1BwPR 1-12-RY and lower demand to close the pressurizer spray valve. | demand position. 1RY455C will fail full open and pressurizer pressure will drop. The ATC will take manual control of 1PK-455C per hard card 1BwPR 1-12-RY and lower demand to close the pressurizer spray valve. | ||
Tech Spec 3.4.1 Condition A will apply if pressurizer pressure drops below 2209 psig. | Tech Spec 3.4.1 Condition A will apply if pressurizer pressure drops below 2209 psig. | ||
After the 1PK | After the 1PK-455C failure has been addressed, the controlling PZR level channel, 1LT-459, will fail low. | ||
-455C failure has been addressed, the controlling PZR level channel, 1LT | The crew will implement 1BwOA INST-2 and take actions to restore PZR level control and stabilize plant conditions. Technical Specification 3.3.1 Conditions A and K apply (Tech Spec 3.3.3 and 3.3.4 for Accident Monitoring and Remote Shutdown Panel minimum channel requirements are still met). | ||
-459 , will fail low. The crew will implement 1BwOA INST | After the failed PZR level channel has been addressed, 1FK-520, Feed Reg Valve 1FW520 Controller, will fail to 100% demand. 1FW520, 1B FRV, will fully open and 1B SG level will rise. The crew will take actions per hard card 1BwPR 1-15-SG to stabilize the plant by taking manual control of the 1B FRV controller. | ||
-2 and take actions to restore PZR level control and stabilize plant conditions. Technical Specification 3.3.1 Conditions A and K apply (Tech Spec 3.3.3 and 3.3.4 for Accident Monitoring and Remote Shutdown Panel minimum channel requirements are still met). | After the 1FK-520 failure is addressed, Heater Drain Tank (HDT) Level Controller, 1LK-HD009A, will fail to 0% demand. The 1HD046A/B valves will throttle close and HDT level will rise. The BOP will take actions to stabilize the plant by taking manual control of the 1LK-HD009A controller. | ||
After the failed PZR level channel has been addressed, 1FK-520, Feed Reg Valve 1FW520 Controller, will fail to 100% demand. | After the HDT Level Controller failure is addressed, the 1B MSIV fails closed causing three SG safety valves on the 1B SG to stick open resulting in a faulted SG. SG pressure will drop and a manual reactor trip will be required. The crew will implement 1BwEP-0 REACTOR TRIP OR SAFETY INJECTION. When safety injection is actuated, the 1A CV pump will trip. The 1B CV pump must be manually started to establish high head ECCS flow. After determining 1B SG secondary pressure boundary is not intact, the crew will transition to 1BwEP-2 FAULTED STEAM GENERATOR ISOLATION. When 1B SG pressure drops to 600 psig, a SGTR will occur on the 1B SG, causing a faulted/ruptured SG. The crew will complete isolation of 1B SG and transition to 1BwEP-3 STEAM GENERATOR TUBE RUPTURE based on secondary radiation trends on the 1B SG. In addition, the crew will recognize 1B SG pressure does not drop to zero and lowering pressurizer level/pressure will indicate a SGTR (alternate indications). After determining the ruptured SG pressure is less than 320 psig, the crew will transition 1BwCA-3.1 SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. | ||
Completion criteria is completion of step 8 to stop the RH pumps in 1BwCA-3.1. | |||
The crew will take actions per hard card 1BwPR 1-15-SG to stabilize the plant by taking manual control of the 1B FRV controller. | Critical Tasks | ||
After the 1FK | : 1. Manually start the 1B CV pump prior to completion of step 6 of 1BwEP-0. | ||
- | (Westinghouse - CT-6) (K/A number - 013000A4.01 importance 4.5/4.8) | ||
The 1HD046A/B valves will throttle close and HDT level will rise. | : 2. Isolate 1B Steam Generator prior to completing step 4 of 1BwEP-2. | ||
The BOP will take actions to stabilize the plant by taking manual control of the 1LK | (Westinghouse - CT-18) (K/A number - APE040AA1.10 importance 4.1/4.1) 151 NRC 4 Page 2 | ||
-HD009A controller. | |||
After the HDT Level Controller failure is addressed, the 1B MSIV fails closed causing three SG safety valves on the 1B SG to stick open resulting in a faulted SG. SG pressure will drop and a manual reactor trip will be required. The crew will implement 1BwEP | |||
-0 | |||
, the crew will transition to 1BwEP | |||
-2 | |||
The crew will complete isolation of 1B SG and transition to 1BwEP | |||
-3 | |||
In addition, the crew will recognize 1B SG pressure does not drop to zero and lowering pressurizer level/pressure will indicate a SGTR (alternate indications). After determining the ruptured SG pressure is less than 320 psig, the crew will transition 1BwCA | |||
-3.1 | |||
- SUBCOOLED RECOVERY DESIRED. | |||
: 1. Manually start the 1B CV pump prior to completion of step 6 of 1BwEP | |||
-0. | |||
- CT-6) (K/A number | |||
- 013000A4.01 importance 4.5/4.8) | |||
-2. | |||
- CT-18) (K/A number | |||
- APE040AA1.10 importance 4.1/4.1) 151 NRC 4 Page | |||
151 NRC 4 Page | SIMULATOR SETUP GUIDE | ||
. | * Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST. | ||
* Establish the conditions of IC-16, 53% power, steady state, equilibrium xenon. | |||
* Verify/place 0A and 0C VA plenums in service, 0B VA plenum in standby. | |||
* Complete items on Simulator Ready for Training Checklist. | |||
* Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario. | |||
* Place simulator in RUN (allow simulator to run during board walk down and turnover). | |||
* Run caep 151 NRC 4 SETUP from disk and verify the following actuate: | |||
* IMF CV32B | |||
* TRGSET 1 ZLO1SI01PA(3) = = 1 | |||
* IMF CV01A (1 0) | |||
* TRGSET 2 ZAO1PI524A < 0.46 | |||
* IMF TH03B (2 10) 600 60 | |||
* See EVENT 1 and run the event 1 cae during simulator setup. | |||
* Provide examinees with turnover sheets. | |||
151 NRC 4 Page 3 | |||
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: 1BwOSR 3.7.4.1 with 1MS018B valve failure (Tech Spec). | |||
Run caep 151 NRC 4 EVENT 1 from disk and verify the following actuate: | Run caep 151 NRC 4 EVENT 1 from disk and verify the following actuate: | ||
TRGSET 3 | * TRGSET 3 ZAO1PKMS042A > 0.90 | ||
* IMF PB2411 (3 0) ON | |||
* IMF PB2412 (3 0) ON | |||
, report you are standing by at the 1MS018B/C valves. Report the following as an EO when prompted: | * IOR ZLO1MS018B2 (3 0) ON | ||
* IOR ZLO1MS018B1 (3 0) ON | |||
* IOR ZAO1ZIMS010 (3 0) 90 | |||
* TRGSET 4 "ZDI1MS018B == 0" | |||
* TRG 4 "DOR ZAO1ZIMS010" When requested, as Equipment Operator, report you are standing by at the 1MS018B/C valves. | |||
Report the following as an EO when prompted: AS FOUND position for 1MS019A/B/C/D is OPEN. | |||
When requested to close 1MS019A/B/C/D insert the following: | When requested to close 1MS019A/B/C/D insert the following: | ||
IRF MS51 0 for 1MS019A. IRF MS52 0 for 1MS019B. IRF MS53 0 for 1MS019C. IRF MS54 0 for 1MS019D. As SM acknowledge the failure of 1MS018B, LCO 3.6.3, Condition C and LCO 3.7.4, Condition A entry, and requests for on | * IRF MS51 0 for 1MS019A. | ||
-line risk assessment, maintenance support and IR initiation. | * IRF MS52 0 for 1MS019B. | ||
If asked, 1BwOSR 3.6.3.5.MS | * IRF MS53 0 for 1MS019C. | ||
-1 is NOT required to be performed. | * IRF MS54 0 for 1MS019D. | ||
As SM acknowledge the failure of 1MS018B, LCO 3.6.3, Condition C and LCO 3.7.4, Condition A entry, and requests for on-line risk assessment, maintenance support and IR initiation. If asked, 1BwOSR 3.6.3.5.MS-1 is NOT required to be performed. | |||
If asked, as EO, report 1MS018B has a broken hydraulic line and a small puddle of hydraulic fluid is present beneath the valve. The hydraulic pump is running. If asked 1MS018B is 90% open locally. | If asked, as EO, report 1MS018B has a broken hydraulic line and a small puddle of hydraulic fluid is present beneath the valve. The hydraulic pump is running. If asked 1MS018B is 90% open locally. | ||
After the BOP takes the 1MS018B C/S to CLOSE, if asked as the EO, report 1MS018B is 90% open & its hydraulic pump is NOT running. | After the BOP takes the 1MS018B C/S to CLOSE, if asked as the EO, report 1MS018B is 90% open & its hydraulic pump is NOT running. | ||
As WEC supervisor, acknowledge request for EST for 1MS018B C/S, if EST is requested. | As WEC supervisor, acknowledge request for EST for 1MS018B C/S, if EST is requested. | ||
Event 2: | Event 2: Raise power to 938 MW at 3 MW/min. | ||
If ramp is not commenced immediately after the Tech Spec entry | If ramp is not commenced immediately after the Tech Spec entry, call as TSO and request status of Unit 1 ramp to 938 MW. | ||
, call as TSO and request status of Unit 1 ramp to 938 MW. | Acknowledge as Chemistry/Rad Protection requests for samples (if required). | ||
Acknowledge as Chemistry/ | Acknowledge as Generation Dispatch the initiation of the ramp. | ||
Acknowledge as Generation Dispatch the initiation of the ramp. | 151 NRC 4 Page 4 | ||
151 NRC 4 Page | |||
Event 3: 1PK-455C Pressurizer Spray Valve Controller failure. | INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 3: 1PK-455C Pressurizer Spray Valve Controller failure. | ||
Insert IMF TH10B 100 15 to fail 1RY455C controller to 100% demand over 15 seconds. | Insert IMF TH10B 100 15 to fail 1RY455C controller to 100% demand over 15 seconds. | ||
As SM, acknowledge the failure, LCO 3.4.1 Condition A entry and exit (if applicable), and requests for maintenance support, and IR initiation. | As SM, acknowledge the failure, LCO 3.4.1 Condition A entry and exit (if applicable), and requests for maintenance support, and IR initiation. | ||
Events 4: PZR level channel 1LT-459 fails low. | |||
Events 4: | Insert IMF RX13A 0 to fail 1LT-459 low. | ||
-459 fails low. | As SM, if support requested for bypassing the bistable in AEER, report that AEER bistable is not to be bypassed until work analyst and NSO support can be obtained (in approx. 2 hours) and that the abnormal operating procedure should be continued. | ||
Insert IMF RX13A 0 to fail 1LT | Acknowledge as Shift Manager the failure, LCOAR entry, on-line risk assessment, EAL evaluation, request for maintenance support, and IR request. | ||
-459 low. As SM, if support requested for bypassing the bistable in AEER, report that AEER bistable is not to be bypassed until work analyst and NSO support can be obtained (in approx. 2 hours) and that the abnormal operating procedure should be continued. | Event 5: 1FW520 controller fails high in auto. | ||
Acknowledge as Shift Manager the failure, LCOAR entry, on | Insert IMF RX29B 100 30 to fail 1FK-520 controller to 100% demand over 30 seconds. | ||
-line risk assessment, EAL evaluation, request for maintenance support, and IR request. | If dispatched as EO to investigate, wait one minute and report no visible damage to 1FW520. 1FW520 appears to be responding correctly in manual (if asked for feedback to manual ops). | ||
Event 5: 1FW520 controller fails high in auto | |||
- | |||
If dispatched as EO to investigate, wait one minute and report no visible damage to | |||
Acknowledge as Shift Manager the failure, request for maintenance support, and IR request. | Acknowledge as Shift Manager the failure, request for maintenance support, and IR request. | ||
Event 6: HDT Level controller failure. Insert IMF FW17 0 30 to fail the controller to 0% demand over 30 seconds. | Event 6: HDT Level controller failure. | ||
If dispatched as EO to investigate, wait one minute and report no visible damage to 1HD046A or B valves. Report local operation/position of 1HD046A/B the same as MCR indication (if asked for feedback to manual valve | Insert IMF FW17 0 30 to fail the controller to 0% demand over 30 seconds. | ||
If dispatched as EO to investigate, wait one minute and report no visible damage to 1HD046A or B valves. | |||
Report local operation/position of 1HD046A/B the same as MCR indication (if asked for feedback to manual valve operation). | |||
Report local HD tank level same as MCR indication. | |||
If dispatched as EO to investigate HDT rupture disk, report it is intact. | If dispatched as EO to investigate HDT rupture disk, report it is intact. | ||
151 NRC 4 Page 5 | |||
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 7: 1B SG Safety valves stick open when 1B MSIV fails closed. | |||
Run caep 151 NRC 4 EVENT 7 from disk and verify the following actuate: | |||
Event 7: | |||
IOR ZDI1MS001B CLS IMF MS03B 100 IMF MS03F 100 IMF MS03J 100 After faulted SG is diagnosed by crew OR two minutes after malfunction is inserted, report as security, steam flow from 1B/1C MSIV room safety valve tailpipes. | IOR ZDI1MS001B CLS IMF MS03B 100 IMF MS03F 100 IMF MS03J 100 After faulted SG is diagnosed by crew OR two minutes after malfunction is inserted, report as security, steam flow from 1B/1C MSIV room safety valve tailpipes. | ||
Acknowledge as SM procedure changes, Emergency Plan evaluations, and STA request. | Acknowledge as SM procedure changes, Emergency Plan evaluations, and STA request. | ||
Event 8: | Event 8: 1A CV pump trips/1B CV pump fails to auto start (preload). | ||
Verify that the 1A CV pump trips when the 1A SI pump starts. | |||
If dispatched as EO to investigate 1A CV pump, report ground overcurrent flag at breaker cubicle. | If dispatched as EO to investigate 1A CV pump, report ground overcurrent flag at breaker cubicle. | ||
Event 9: | Event 9: Faulted/ruptured 1B SG (preload). | ||
Verify that MF TH03B inserts when 1B SG pressure drops below 600 psig. | |||
Acknowledge as SM procedure changes, Emergency Plan evaluations, and STA request. | Acknowledge as SM procedure changes, Emergency Plan evaluations, and STA request. | ||
After STA requested, as STA report CSF status. | After STA requested, as STA report CSF status. | ||
151 NRC 4 Page 6 | |||
Scenario NRC 4 Event 1 No: No. | |||
Event Perform 1BwOSR 3.7.4.1 MAIN STEAM SYSTEM ISOLATION 1MS018A/B/C/D VALVE | |||
== Description:== | == | ||
Description:== | |||
TRAVEL AND INDICATION 18 MONTH SURVEILLANCE Time Position Applicants Actions or Behavior CUE From turnover, perform 1BwOSR 3.7.4.1. | |||
US | |||
US | * Direct BOP to perform 1BwOSR 3.7.4.1. | ||
BOP | BOP | ||
Verify/initial step 1, initial conditions. | * Refer to 1BwOSR 3.7.4.1. | ||
Contact the EO at 1MS019B for initial position and record initial valve | * Verify/initial step 1, initial conditions. | ||
* Contact the EO at 1MS019B for initial position and record initial valve positions. | |||
OPEN 1MS018B at 1PM04J. | * Direct the EO to close 1MS019B. | ||
Respond to Annunciator S/G 1B PORV TROUBLE (1 B10) alarm. | * OPEN 1MS018B at 1PM04J. | ||
Identify/report trouble alarm on 1MS018B. | * Respond to Annunciator S/G 1B PORV TROUBLE (1-15-B10) alarm. | ||
Refer to BwAR 1 B10. Contact operator at 1MS018B for valve status. | * Identify/report trouble alarm on 1MS018B. | ||
* Refer to BwAR 1-15-B10. | |||
* Contact operator at 1MS018B for valve status. | |||
o Place 1MS018B C/S in close to stop hydraulic pump. | o Place 1MS018B C/S in close to stop hydraulic pump. | ||
o Request Equipment Status Tag for 1MS018B C/S & 1MS019B hand wheel. | o Request Equipment Status Tag for 1MS018B C/S & 1MS019B hand wheel. | ||
US | US | ||
Identify entry conditions for Tech Spec 3.6.3 Condition C. | * Identify entry conditions for Tech Spec 3.7.4 Condition A. | ||
* Identify entry conditions for Tech Spec 3.6.3 Condition C. | |||
o Direct operator to maintain 1MS019B closed. | o Direct operator to maintain 1MS019B closed. | ||
o Inform SM of 1MS018B status, Tech Spec status, request IR, | o Inform SM of 1MS018B status, Tech Spec status, request IR, on-line risk assessment, maintenance support, and clearance order/EST for 1MS019B. | ||
EXAMINERS NOTE: (1) After the actions for 1MS018B failure are complete and with Lead Examiners concurrence, enter next event. | |||
(2) 1B S/G PORV LVDT meter de-energizes when its control switch is placed in close. | (2) 1B S/G PORV LVDT meter de-energizes when its control switch is placed in close. | ||
Comments: | Comments: | ||
151 NRC 4 Page 7 | |||
Scenario NRC 4 Event 2 No: No. | |||
Event Raise power to 938 MW at 3 MW/min | |||
== Description:== | == | ||
Description:== | |||
Time Position Applicants Actions or Behavior CUE | |||
US | * If ramp is not commenced immediately after suspending the surveillance, call from TSO to request the status of the Unit 1 power ascension. | ||
-3. o Perform pre | US | ||
-job brief per HU | * Acknowledge request to raise load to 938 MW at 3 MW/min. | ||
-AA-1211 | * Implement actions of 1BwGP 100-3. | ||
US | o Perform pre-job brief per HU-AA-1211 PRE-JOB, HEIGHTENED LEVEL OF AWARENESS, INFREQUENT PLANT ACTIVITY, AND POST JOB BRIEFINGS for load ramp. | ||
-4T2. CREW o Review applicable Precautions, and Limitations and Actions (may have been done in PJB prior to starting scenario). o May energize PZR heaters. | US | ||
ATC | * Direct raising load to 938 MW at 3 MW/min. | ||
Initiate dilution per BwOP CV | o Initiate Load Swing Instruction Sheet, 1BwGP 100-4T2. | ||
-5. Determine required PW volume from ReMA. o Dilute in automatic (PREFERRED) | CREW o Review applicable Precautions, and Limitations and Actions (may have been done in PJB prior to starting scenario). | ||
o May energize PZR heaters. | |||
- | ATC | ||
o Adjust setpoint on 1FK | * Verify rod position and boron concentration. | ||
-111 to desired PW flowrate. | * Initiate dilution per BwOP CV-5. | ||
o Set 1FY-0111 PW Control Predet Counter | * Determine required PW volume from ReMA. | ||
, to desired PW volume. | o Dilute in automatic (PREFERRED): | ||
o Control VCT level by adjusting 1LK | o Determine required PW flowrate. | ||
-112 setpoint or manually controlling 1LK | o Note as found setpoint on 1FK-111, PW Total Flow Controller Pot. | ||
-112. o Place MAKE | o Adjust setpoint on 1FK-111 to desired PW flowrate. | ||
-UP CONT SWITCH to STOP position. | o Set 1FY-0111 PW Control Predet Counter, to desired PW volume. | ||
o Set MODE SELECT to DIL/ALT DIL position. | o Control VCT level by adjusting 1LK-112 setpoint or manually controlling 1LK-112. | ||
o Place MAKE | o Place MAKE-UP CONT SWITCH to STOP position. | ||
-UP CONT SWITCH to START. o Verify proper operation of valves and PW makeup pump (1CV111B open, 1CV111A throttled, 1CV110B open (ALT DIL only), PW pump running, proper PW flow on recorder). | o Set MODE SELECT to DIL/ALT DIL position. | ||
o When desired dilution completed, place MAKE | o Place MAKE-UP CONT SWITCH to START. | ||
-UP CONT SWITCH to STOP position. o Verify the following (1CV111B close, 1CV111A close, 1CV110B close, PW pump remains running). | o Verify proper operation of valves and PW makeup pump (1CV111B open, 1CV111A throttled, 1CV110B open (ALT DIL only), PW pump running, proper PW flow on recorder). | ||
OR | o When desired dilution completed, place MAKE-UP CONT SWITCH to STOP position. | ||
-112 setpoint or manually controlling 1LK | o Verify the following (1CV111B close, 1CV111A close, 1CV110B close, PW pump remains running). | ||
-112. o Reset PW Total Flow Totalizer to ZERO. | OR ATC o Batch dilution: | ||
o Control VCT level by adjusting 1LK-112 setpoint or manually controlling 1LK-112. | |||
o Reset PW Total Flow Totalizer to ZERO. | |||
Comments: | |||
151 NRC 4 Page 8 | |||
Scenario NRC 4 Event 2 No: No. | |||
Event Raise power to 938 MW at 3 MW/min | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior o Open 1CV111B, if desired to dilute to VCT upper nozzle. | |||
o Open 1CV110B, if desired to dilute to VCT outlet. | |||
o Open 1CV111A. | |||
o Open 1CV110B, if desired to dilute to VCT outlet. | o When desired amount of primary water added: | ||
o Open 1CV111A. | |||
o When desired amount of primary water added: | |||
o Close 1CV111A and verify/place control switch to AUTO. | o Close 1CV111A and verify/place control switch to AUTO. | ||
o Close 1CV110B and verify/place control switch to AUTO. | o Close 1CV110B and verify/place control switch to AUTO. | ||
o Close 1CV111B and verify/place control switch to AUTO. | o Close 1CV111B and verify/place control switch to AUTO. | ||
BOP | BOP | ||
Select SETPOINT. | * Raise turbine load at 1PM02J or OWS drop 210 by performing the following: | ||
Enter 938 MW into REF DEMAND window. | * Select SETPOINT. | ||
Select left ENTER. Verify correct value appears in REF DEMAND window. | * Enter 938 MW into REF DEMAND window. | ||
Enter 3 MW/min into the RATE window. | * Select left ENTER. | ||
Select right ENTER. Select EXIT. | * Verify correct value appears in REF DEMAND window. | ||
o Notify Control room team of pending ramp. | * Enter 3 MW/min into the RATE window. | ||
Select GO/HOLD. | * Select right ENTER. | ||
Verify GO/HOLD illuminates orange. | * Select EXIT. | ||
Verify HOLD | o Notify Control room team of pending ramp. | ||
Verify GO illuminates RED while the main turbine ramps. | * Select GO/HOLD. | ||
Verify main turbine load begins to rise. | * Verify GO/HOLD illuminates orange. | ||
ATC | * Verify HOLD illuminates RED. | ||
Monitor NIs, Tave, I, | * Select GO. | ||
Monitor MW and DEHC system response at 1PM02J or OWS drop 210. | * Verify GO illuminates RED while the main turbine ramps. | ||
During dilution, monitor the following at 1PM05J or PPC: | * Verify main turbine load begins to rise. | ||
VCT level. | ATC | ||
RCS Tave. o PW/Total flow predet counter responding correctly. | * Monitor reactor power and load ascension: | ||
* Monitor NIs, Tave, I, PZR pressure/level at 1PM05J or PPC. | |||
* Monitor MW and DEHC system response at 1PM02J or OWS drop 210. | |||
* During dilution, monitor the following at 1PM05J or PPC: | |||
* VCT level. | |||
* RCS Tave. | |||
o PW/Total flow predet counter responding correctly. | |||
o Verify dilution auto stops at preset value. | o Verify dilution auto stops at preset value. | ||
o Return Reactor Makeup Control System to automatic. | o Return Reactor Makeup Control System to automatic. | ||
o Perform periodic control rod steps to maintain Tave and Delta I within boundaries. | o Perform periodic control rod steps to maintain Tave and Delta I within boundaries. | ||
EXAMINERS NOTE: After measurable change in power and with Lead Examiners concurrence, enter next event. | |||
Comments: | |||
151 NRC 4 Page 9 | |||
Scenario NRC 4 Event 3 No: No. | |||
Event 1PK-455C, Pressurizer Spray Valve controller, fails to 100% demand | |||
== Description:== | == Description:== | ||
Time Position Applicants Actions or Behavior CUE | |||
* 1RY455C valve position lights indicate full open. | |||
Pressurizer pressure dropping. | * Pressurizer pressure dropping. | ||
Master Pressurizer Pressure Controller demand dropping. | * Master Pressurizer Pressure Controller demand dropping. | ||
o Annunciator PZR PRESS CONT DEV LOW HTRS ON (1 C1) | o Annunciator PZR PRESS CONT DEV LOW HTRS ON (1-12-C1) | ||
Perform the following actions per hard card 1BwPR 1 RY: | ATC | ||
* Identify failure/report alarm on 1PM05J. | |||
-failed value). | * Perform the following actions per hard card 1BwPR 1-12-RY: | ||
BOP o Refer to BwARs as time permits. | * Place 1PK-455C in manual. | ||
* Lower demand to close 1RY455C (adjust PZR pressure to pre-failed value). | |||
BOP o Refer to BwARs as time permits. | |||
o Hold load ramp, if requested. | o Hold load ramp, if requested. | ||
US | US | ||
o Identify entry condition for Tech Spec 3.4.1 Condition A if RCS pressure drops below 2209 psig. o Identify exit condition for Tech Spec 3.4.1 Condition A. | * Direct operator to close 1RY455C. | ||
o May hold load ramp (if in progress) | o Identify entry condition for Tech Spec 3.4.1 Condition A if RCS pressure drops below 2209 psig. | ||
o Identify exit condition for Tech Spec 3.4.1 Condition A. | |||
-455C failure, Tech Spec status, request IR, | o May hold load ramp (if in progress). | ||
NOTE: | US o Inform SM of 1PK-455C failure, Tech Spec status, request IR, on-line risk assessment and maintenance support. | ||
-455C failure are complete and with | NOTE: After the actions for 1PK-455C failure are complete and with Lead Examiners concurrence, enter next event. | ||
Comments: | |||
151 NRC 4 Page 10 | |||
Scenario NRC 4 Event 4 No: No. | |||
Event PZR level channel, 1LT-459, fails low | |||
== Description:== | == Description:== | ||
Time Position Applicants Actions or Behavior CUE | |||
* Annunciator PZR LVL LOW HTRS OFF LTDWN SECURED (1-12-A4) | |||
Identify 1LI | * Annunciator PZR HTR TRIP (1-12-A5) | ||
- | * Annunciator PZR LEVEL CONT DEV LOW (1-12-B4) | ||
Report failure to US. | * PZR level, 1LI-459A/461, and charging flow rising. | ||
Perform the following at 1PM05J: | ATC | ||
Place 1CV121 controller (1FK-121) or 1LK | * Determine PZR level and/or charging header flow rising at 1PM05J. | ||
-459 in manual and control PZR level (minimize charging). | * Identify 1LI-459A is failed low. | ||
Verify automatic actions occurred (letdown isolated, heaters tripped off). | * Report failure to US. | ||
o Reference BwARs as time permits. | * Perform the following at 1PM05J: | ||
CREW | * Place 1CV121 controller (1FK-121) or 1LK-459 in manual and control PZR level (minimize charging). | ||
-2 | * Verify automatic actions occurred (letdown isolated, heaters tripped off). | ||
o Reference BwARs as time permits. | |||
Request SM evaluation of Emergency Plan conditions. | CREW | ||
Implement 1BwOA INST | * Identify entry conditions for 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL. | ||
-2 | US | ||
-2 to establish the following conditions: | * Notify Shift Manager of plant status and procedure entry. | ||
o May hold load ramp (if in progress). | * Request SM evaluation of Emergency Plan conditions. | ||
ATC | * Implement 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL, ATTACHMENT C PRESSURIZER LEVEL CHANNEL FAILURE, and direct operator actions of 1BwOA INST-2 to establish the following conditions: | ||
PZR level normal - NO. Manually restore PZR level using 1LK | o May hold load ramp (if in progress). | ||
-459 or 1FK | ATC | ||
-121. Select operable PZR level control channel: | * Check PZR level at 1PM05J: | ||
Place PZR level control select C/S to CH 461/460 position. Select operable PZR level channel for PZR level recorder at 1PM05J: | * PZR level normal - NO. | ||
Verify PZR level channel to recorder select switch in CH-460 or CH-461 position. Check letdown and PZR heaters at 1PM05J: | * Manually restore PZR level using 1LK-459 or 1FK-121. | ||
Check PZR level > 17% on 1LI | * Select operable PZR level control channel: | ||
- | * Place PZR level control select C/S to CH 461/460 position. | ||
* Select operable PZR level channel for PZR level recorder at 1PM05J: | |||
-2 actions are Comments: | * Verify PZR level channel to recorder select switch in CH-460 or CH-461 position. | ||
* Check letdown and PZR heaters at 1PM05J: | |||
* Check PZR level > 17% on 1LI-460A & 1LI-461. | |||
* Check letdown flow established - NO, letdown isolated (1BwOA ESP-2 actions are Comments: | |||
151 NRC 4 Page 11 | |||
Scenario NRC 4 Event 4 No: No. | |||
Event PZR level channel, 1LT-459, fails low | |||
== Description:== | == Description:== | ||
Time Position Applicants Actions or Behavior on the next page). | |||
* Check PZR heaters normal: | |||
Check PZR heaters normal: | * PZR heaters available in auto. | ||
Check PZR level control in auto at 1PM05J: | * Check PZR level control in auto at 1PM05J: | ||
1LK-459, Master PZR level controller. | * Verify/place the following components in AUTO: | ||
1FK-121, CV pumps flow control valve. | * 1LK-459, Master PZR level controller. | ||
BOP 1BwOA ESP-2 | * 1FK-121, CV pumps flow control valve. | ||
-2 as directed by performing the following at 1PM05J: | BOP 1BwOA ESP-2 REESTABLISHING CV LETDOWN DURING ABNORMAL CONDITIONS Restore normal letdown using 1BwOA ESP-2 as directed by performing the following at 1PM05J: | ||
Verify 1CV8149A, B, & C, letdown orifice isolation valves | * Check letdown isolated: | ||
- CLOSED. Verify 1CV459 & 1CV460, letdown line isolation valves | * Verify 1CV8149A, B, & C, letdown orifice isolation valves - CLOSED. | ||
- CLOSED. Check letdown flow path: | * Verify 1CV459 & 1CV460, letdown line isolation valves - CLOSED. | ||
Verify 1CV8401A, letdown HX 1A isolation valve | * Check letdown flow path: | ||
- OPEN. Verify 1CV8324A, charging to regen HX 1A isolation valve | * Verify 1CV8401A, letdown HX 1A isolation valve - OPEN. | ||
- OPEN. Verify 1CV8389A, letdown to regen HX 1A isolation valve | * Verify 1CV8324A, charging to regen HX 1A isolation valve - OPEN. | ||
- OPEN. Verify 1CV8152 & 1CV8160, letdown line CNMT isolation valves | * Verify 1CV8389A, letdown to regen HX 1A isolation valve - OPEN. | ||
- OPEN. Verify BTRS mode select switch OFF light - LIT. Align letdown controllers: | * Verify 1CV8152 & 1CV8160, letdown line CNMT isolation valves - OPEN. | ||
Place 1PK-131, letdown line pressure controller, in MANUAL and raise demand to 40%. Place 1CC130A, letdown HX outlet temperature controller, in MANUAL and raise demand to 60%. | * Verify BTRS mode select switch OFF light - LIT. | ||
Verify charging flow established: | * Align letdown controllers: | ||
Verify 1CV8105 and 1CV8106, charging line CNMT isolation valves | * Place 1PK-131, letdown line pressure controller, in MANUAL and raise demand to 40%. | ||
- OPEN. Throttle 1CV182, charging header backpressure control valve, to establish 8 | * Place 1CC130A, letdown HX outlet temperature controller, in MANUAL and raise demand to 60%. | ||
-13 gpm RCP seal injection flow. | * Verify charging flow established: | ||
Place 1FK-121, in manual and operate 1FK | * Verify 1CV8105 and 1CV8106, charging line CNMT isolation valves - OPEN. | ||
-121 in manual to establish | * Throttle 1CV182, charging header backpressure control valve, to establish 8-13 gpm RCP seal injection flow. | ||
> 100 gpm charging flow on 1FI | * Place 1FK-121, in manual and operate 1FK-121 in manual to establish > 100 gpm charging flow on 1FI-121A. | ||
-121A. Establish letdown flow: | * Establish letdown flow: | ||
OPEN 1CV459 & 1CV460, letdown line isolation valves | * OPEN 1CV459 & 1CV460, letdown line isolation valves. | ||
* OPEN 1CV8149A/B/C, letdown orifice isolation valves, as necessary to establish 120 gpm letdown flow. | |||
Lower demand on 1PK | * Lower demand on 1PK-131, letdown line pressure controller, to raise letdown pressure to approximately 360 psig on 1PI-131. | ||
-131, letdown line pressure controller, to raise letdown pressure to approximately 360 psig on 1PI | * Operate 1FK-121 in manual to restore PZR level to normal operating band and Comments: | ||
-131. Operate 1FK | 151 NRC 4 Page 12 | ||
-121 in manual to restore PZR level to normal operating band and Comments: | |||
Scenario NRC 4 Event 4 No: No. | |||
Event PZR level channel, 1LT-459, fails low | |||
== Description:== | == Description:== | ||
Time Position Applicants Actions or Behavior maintain 8-13 gpm RCP seal injection flow. | |||
* Lower demand on 1CC130A to control letdown temperature between 90° to 115°F on 1TI-130. | |||
-13 gpm RCP seal injection flow. | * Place 1PK-131, letdown line pressure controller, in AUTO. | ||
Lower demand on 1CC130A to control letdown temperature | * Place 1CC130A, letdown HX outlet temperature controller, in AUTO. | ||
Place 1CC130A, letdown HX outlet temperature controller, in AUTO. | * At the RM-11, verify 1PR06J rad monitor status is GREEN. | ||
At the RM-11, verify 1PR06J rad monitor status is GREEN. | US | ||
US | * Determine Tech Spec 3.3.1 Conditions A and K are applicable. | ||
o Determine Tech Spec 3.3.3 and 3.3.4 are NOT applicable | o Determine Tech Spec 3.3.3 and 3.3.4 are NOT applicable - minimum channels operable requirement is met. | ||
- minimum channels operable requirement is met. | * Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure. | ||
Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure. | EXAMINERS NOTE: After the actions for the pressurizer level channel failure are complete and with Lead Examiners concurrence, insert next event. | ||
Comments: | |||
151 NRC 4 Page 13 | |||
Scenario NRC 4 Event 5 No: No. | |||
Event | |||
== Description:== | == Description:== | ||
1FW520 (1B FRV) controller fails high in auto Time Position Applicants Actions or Behavior CUE | |||
* Annunciator S/G 1B FLOW MISMATCH STM FLOW LOW (1-15-B3) | |||
* 1FK-520 controller output failed high. | |||
* Feed flow rising on FW flow meters, 1FI-520A/521A. | |||
* 1B SG level rising on SG level meters, 1LI-527/528/529/557. | |||
BOP | |||
* Determine 1B SG level rising. | |||
* Perform the following per hard card 1BwPR 1-15-SG at 1PM04J: | |||
* Place 1FK-520 in manual. | |||
* Restore 1B SG level to pre-failed value. | |||
* Determine that 1B FRV controller failed in auto. | |||
* Maintain 1B SG level by operating 1FK-520 in manual. | |||
* Report failure to US. | |||
CREW | |||
* Recognize 1FK-520 output failed high. | |||
o Reference BwARs as time permits. | |||
US | |||
* Direct/ensure BOP takes manual control of 1FK-520 and returns 1B SG level to normal. | |||
* Inform SM of 1FK-520 failure. | |||
o May hold load ramp (if in progress). | |||
US o Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct controller failure. | |||
CREW o Crew may elect to base load 1FW520 and place 1FW520A in automatic per 1BwGP 100-3 Limitation E.4.g or BwOP FW-30. | |||
EXAMINERS NOTE: After the actions for the 1FW520 controller failure are complete and with Lead Examiners concurrence, insert next event. | |||
Comments: | |||
151 NRC 4 Page 14 | |||
Scenario NRC 4 Event 6 No: No. | |||
Event | |||
== Description:== | == Description:== | ||
HD Tank Level Controller Failure Time Position Applicants Actions or Behavior CUE | |||
HD Tank Level Controller Failure Time Position | * HD tank level controller, 1LK-HD009A, output failed to 0%. | ||
-HD009A, output failed to 0%. Lowering HD pump | * Lowering HD pump flows on 1FI-HD004/6. | ||
-HD009. Annunciator HD TANK LEVEL HIGH LOW (1-17-E4) | * Rising HD tank level on 1LI-HD009. | ||
-HD009A output failed low (0%). US | * Annunciator HD TANK LEVEL HIGH LOW (1-17-E4) | ||
-HD009A and restore HD | CREW | ||
Place 1LK-HD009A, HD Tank Level Controller, in manual. | * Recognize 1LK-HD009A output failed low (0%). | ||
Raise demand on 1LK | US | ||
-HD009A. Monitor HDT level and control 1HD046A/B position to restore HD Tank level to normal. Maintain HD Tank level by operating 1LK | * Direct/ensure BOP takes manual control of 1LK-HD009A and restore HD Tank level to normal. | ||
-HD009A in manual. | * Inform SM of HD Tank level controller failure. | ||
BOP | |||
* Perform the following at 1PM03J: | |||
* Place 1LK-HD009A, HD Tank Level Controller, in manual. | |||
* Raise demand on 1LK-HD009A. | |||
* Monitor HDT level and control 1HD046A/B position to restore HD Tank level to normal. | |||
* Maintain HD Tank level by operating 1LK-HD009A in manual. | |||
o Dispatch EO to 1HD046A/B valves. | o Dispatch EO to 1HD046A/B valves. | ||
US o Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure. | US o Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure. | ||
ATC o | ATC o Review BwARs as time permits. | ||
EXAMINERS NOTE: After the actions for the HD tank level controller failure are complete and with Lead Examiners concurrence, insert next event. | |||
Comments: | |||
151 NRC 4 Page 15 | |||
Scenario NRC 4 Event 7&8 No: No. | |||
Event 1B MSIV closes causing1B SG safety valves to stick open, 1A CV pump trips/1B CV | |||
== | |||
Description:== | |||
== Description:== | pump fails to auto start Time Position Applicants Actions or Behavior CUE | ||
* 1B MSIV indicates closed. | |||
* Annunciator S/G 1B FLOW MISMATCH FW FLOW LOW (1-15-B4) | |||
Annunciator S/G 1B FLOW MISMATCH FW FLOW LOW (1 B4) | * PZR pressure lowering. | ||
Turbine MW output lowering. | * Turbine MW output lowering. | ||
ATC | ATC | ||
Initiate a manual SI. | * Recommend/initiate a manual reactor trip. | ||
CREW | * Initiate a manual SI. | ||
CREW | |||
* Recognize indications of faulted SG. | |||
o Dispatch operators to look for steam leak. | o Dispatch operators to look for steam leak. | ||
o When report is received that 1B SG safeties are open, recognize that SG pressure is below safety valve lift setpoint | o When report is received that 1B SG safeties are open, recognize that SG pressure is below safety valve lift setpoint. | ||
US | |||
Implement 1BwEP | * Direct a manual Rx trip. | ||
-0 "REACTOR TRIP OR SI. | * Implement 1BwEP-0 "REACTOR TRIP OR SI. | ||
Notify SM of plant status and procedure entry. | * Notify SM of plant status and procedure entry. | ||
Request SM evaluation of Emergency Plan conditions. | * Request SM evaluation of Emergency Plan conditions. | ||
Direct operator actions of 1BwEP | * Direct operator actions of 1BwEP-0 to establish the following conditions: | ||
-0 to establish the following conditions: | ATC Perform immediate operator actions of 1BwEP-0 at 1PM05J: | ||
ATC Perform immediate operator actions of 1BwEP | * Verify reactor trip: | ||
-0 at 1PM05J: | * Rod bottom lights - ALL LIT. | ||
Verify reactor trip: | * Reactor trip & Bypass breakers - OPEN. | ||
Rod bottom lights | * Neutron flux - DROPPING. | ||
- ALL LIT. Reactor trip & Bypass breakers | BOP Perform immediate operator actions of 1BwEP-0 at 1PM02J: | ||
- OPEN. Neutron flux | * Verify turbine trip: | ||
- DROPPING. BOP Perform immediate operator actions of 1BwEP | * All Turbine throttle valves - CLOSED. | ||
-0 at 1PM02J: | * All Turbine governor valves - CLOSED. | ||
Verify turbine trip: | BOP Perform immediate operator actions of 1BwEP-0 at 1PM01J: | ||
- CLOSED. All Turbine governor valves | * Verify power to 4KV busses: | ||
- CLOSED. BOP Perform immediate operator actions of 1BwEP | * ESF Buses - BOTH ENERGIZED (141 & 142). | ||
-0 at 1PM01J: | Comments: | ||
Verify power to 4KV busses: | 151 NRC 4 Page 16 | ||
ESF Buses | |||
- BOTH ENERGIZED (141 & 142). | |||
Comments: | |||
151 NRC 4 Page | |||
Scenario NRC 4 Event 7&8 No: No. | |||
Event 1B MSIV closes causing1B SG safety valves to stick open, 1A CV pump trips/1B CV | |||
== | |||
, | Description:== | ||
Manually actuate SI from 1PM05J and 1PM06J. | pump fails to auto start Time Position Applicants Actions or Behavior CREW Recognize and respond to conditions requiring a Safety Injection in accordance with 1BwEP-0 REACTOR TRIP OR SAFETY INJECTION, step 4: | ||
CREW | * SG pressure cannot be maintained > 640 psig. | ||
o SI First OUT annunciator | * Manually actuate SI from 1PM05J and 1PM06J. | ||
- LIT. o SI ACTUATED Permissive Light | CREW | ||
- LIT. o SI Equipment | * Check SI Status: | ||
- AUTOMATICALLY ACTUATED. | o SI First OUT annunciator - LIT. | ||
o Either SI pumps - RUNNING. o Either CV pump to cold leg isolation valve OPEN | o SI ACTUATED Permissive Light - LIT. | ||
- 1SI8801A/B. | o SI Equipment - AUTOMATICALLY ACTUATED. | ||
CREW o May choose to isolate 1B SG immediately due to possible personnel safety considerations. | o Either SI pumps - RUNNING. | ||
o Either CV pump to cold leg isolation valve OPEN - 1SI8801A/B. | |||
CREW o May choose to isolate 1B SG immediately due to possible personnel safety considerations. | |||
o Isolate AF to 1B SG - CLOSE 1AF013B/F. | o Isolate AF to 1B SG - CLOSE 1AF013B/F. | ||
o Actuate Main Steam Isolation. | o Actuate Main Steam Isolation. | ||
US | US | ||
-0. | * Direct BOP to perform Attachment B of 1BwEP-0. | ||
-0 while BOP is performing Attachment B. | EXAMINERS NOTE: US and ATC will continue in 1BwEP-0 while BOP is performing Attachment B. | ||
BOP 1BwEP-0 ATTACHMENT B: | BOP 1BwEP-0 ATTACHMENT B: | ||
Verify FW isolated at 1PM04J: | * Verify FW isolated at 1PM04J: | ||
FW pumps - TRIPPED. FW isolation monitor lights | * FW pumps - TRIPPED. | ||
- LIT. FW pumps discharge valves | * FW isolation monitor lights - LIT. | ||
- CLOSED (or going closed) 1FW002A | * FW pumps discharge valves - CLOSED (or going closed) 1FW002A-C. | ||
-C. Verify DGs running at 1PM01J: | * Verify DGs running at 1PM01J: | ||
DGs - BOTH RUNNING 1SX169A/B OPEN. | * DGs - BOTH RUNNING | ||
Dispatch operator locally to check operation. | * 1SX169A/B OPEN. | ||
Verify Generator Trip at 1PM01J: | * Dispatch operator locally to check operation. | ||
OCB 1-8 and 7-8 open. PMG output breaker open. | * Verify Generator Trip at 1PM01J: | ||
Verify Control Room ventilation aligned for emergency operations at 0PM02J: | * OCB 1-8 and 7-8 open. | ||
VC Rad Monitors | * PMG output breaker open. | ||
- LESS THAN HIGH ALARM SETPOINT. | * Verify Control Room ventilation aligned for emergency operations at 0PM02J: | ||
Operating VC train equipment | * VC Rad Monitors - LESS THAN HIGH ALARM SETPOINT. | ||
- RUNNING. 0B Supply fan. | * Operating VC train equipment - RUNNING. | ||
0B Return fan. | * 0B Supply fan. | ||
0B M/U fan. | * 0B Return fan. | ||
0B Chilled water pump. | * 0B M/U fan. | ||
0B Chiller. | * 0B Chilled water pump. | ||
* 0B Chiller. | |||
Comments: | |||
151 NRC 4 Page 17 | |||
Scenario NRC 4 Event 7&8 No: No. | |||
Event 1B MSIV closes causing1B SG safety valves to stick open, 1A CV pump trips/1B CV | |||
151 NRC 4 Page 18 | == | ||
Description:== | |||
pump fails to auto start Time Position Applicants Actions or Behavior | |||
* Operating VC train dampers - ALIGNED. | |||
* M/U fan outlet damper - 0VC08Y NOT FULLY CLOSED. | |||
* 0B VC train M/U filter light - LIT. | |||
* 0VC09Y - OPEN. | |||
* 0VC313Y - CLOSED. | |||
* Operating VC train Charcoal Absorber aligned for train B. | |||
* 0VC44Y - CLOSED. | |||
* 0VC05Y - OPEN. | |||
* 0VC06Y - OPEN. | |||
* Control Room pressure greater than +0.125 inches water on 0PDI-VC038. | |||
* Verify Auxiliary Building ventilation aligned for emergency operations at 0PM02J: | |||
* Two inaccessible filter plenums aligned. | |||
* Plenum A: | |||
* 0VA03CB - RUNNING. | |||
* 0VA023Y - OPEN. | |||
* 0VA436Y - CLOSED. | |||
* Plenum C: | |||
* 0VA03CF RUNNING. | |||
* 0VA072Y - OPEN. | |||
* 0VA438Y - CLOSED. | |||
* Verify FHB ventilation aligned for emergency operation at 0PM02J: | |||
* 0VA04CB - RUNNING | |||
* 0VA055Y - OPEN. | |||
* 0VA062Y - OPEN. | |||
* 0VA435Y - CLOSED. | |||
* Secure all running HD pumps. | |||
* Initiate periodic monitoring of Spent Fuel Cooling. | |||
* Notify US Attachment B complete/manual actions taken. | |||
ATC | |||
* Verify ECCS pumps running: | |||
* CV pumps - NONE RUNNING. | |||
Manually start the 1B CV pump prior to completion of step 6 of 1BwEP-0. | |||
(Westinghouse - CT-6) (K/A number - 013000A4.01 importance 4.5/4.8) | |||
[CT-6] | |||
* Manually start the 1B CV pump. | |||
* Both RH pumps - RUNNING. | |||
* Both SI pumps - RUNNING. | |||
Comments: | |||
151 NRC 4 Page 18 | |||
Scenario NRC 4 Event 7&8 No: No. | |||
Event 1B MSIV closes causing1B SG safety valves to stick open, 1A CV pump trips/1B CV | |||
== | |||
Description:== | |||
- | pump fails to auto start Time Position Applicants Actions or Behavior ATC | ||
* Verify RCFCs running in Accident Mode. | |||
- LIT. | * Group 2 RCFC Accident Mode lights - LIT. | ||
* Verify Phase A isolation. | |||
* Group 3 Cnmt Isol monitor lights - LIT. | |||
* Verify Cnmt Vent isolation. | |||
* Group 6 Cnmt Vent Isol monitor lights - LIT. | |||
* Verify AF system: | |||
* BOTH AF pumps - RUNNING. | |||
* AF isolation valves - 1Af013A-H OPEN. | |||
* AF flow control valves - 1AF005A-H throttled OPEN. | |||
* Verify CC pumps running: | |||
* BOTH CC pumps - RUNNING. | |||
* Verify SX pumps running: | |||
* BOTH SX pumps - RUNNING. | |||
ATC | ATC | ||
* Check if Main Steamlines Should Be Isolated: | |||
* Check SG pressures: | |||
o SG pressures > 640 psig - continue in 1BwEP-0. | |||
-0. | * SG pressures < 640 psig - verify MSIVs and MSIV bypass valves closed. | ||
- | * CNMT pressure < 8.2 psig. | ||
ATC | |||
* Check if CS is required. | |||
* CNMT pressure remained < 20 psig. | |||
- | BOP | ||
* Verify total AF flow: | |||
Comments: | * AF flow > 500 gpm. | ||
* Check S/G NR levels - NOT rising in an uncontrolled manner. | |||
ATC | |||
* Verify ECCS valve alignment: | |||
* Group 2 Cold Leg Injection monitor lights required for injection - LIT. | |||
* Verify ECCS flow: | |||
* High head SI flow >100 gpm (1FI-917). | |||
* RCS pressure < 1700 psig. | |||
* SI pump discharge flows > 200 gpm. | |||
* RCS pressure < 325 psig. | |||
Comments: | |||
151 NRC 4 Page 19 | |||
Scenario NRC 4 Event 7&8 No: No. | |||
Event 1B MSIV closes causing1B SG safety valves to stick open, 1A CV pump trips/1B CV | |||
== Description:== | == | ||
Description:== | |||
pump fails to auto start Time Position Applicants Actions or Behavior ATC | |||
* Check PZR PORVs and spray valves: | |||
* PORVs CLOSED. | |||
* PORV isolation valves - BOTH ENERGIZED. | |||
* PORV relief paths - BOTH PORVs in AUTO, PORV isolation valves OPEN. | |||
* Normal spray valves CLOSED. | |||
ATC | |||
* Check RCS temperatures: | |||
o ANY RCP running. | |||
* RCS Tave stable at or trending to 557°F - NO. | |||
o Throttle AF flow. | |||
o Isolate AF flow to 1B SG. | |||
o NO RCPs running. | |||
* RCS cold leg temperature stable at or trending to 557°F - NO. | |||
o Throttle AF flow. | |||
PORV isolation valves - BOTH ENERGIZED. | |||
PORV relief paths | |||
- BOTH PORVs in AUTO, PORV isolation valves OPEN. | |||
Normal spray valves CLOSED. | |||
ATC | |||
o | |||
RCS Tave stable at or trending to 557°F | |||
o Isolate AF flow to 1B SG. o NO RCPs running. | |||
RCS cold leg temperature stable at or trending to 557°F | |||
- NO. o Throttle AF flow. | |||
o Isolate AF flow to 1B SG. | o Isolate AF flow to 1B SG. | ||
ATC | ATC | ||
* Check status of RCPs: | |||
o RCS pressure > 1425 psig | * ALL RCPs - RUNNING. | ||
- continue in 1BwEP | * Check RCP trip criteria. | ||
-0. o RCS pressure < 1425 psig: | o RCS pressure > 1425 psig - continue in 1BwEP-0. | ||
Verify high head injection flow (1FI | o RCS pressure < 1425 psig: | ||
-917) > 100 gpm. | * Verify high head injection flow (1FI-917) > 100 gpm. | ||
Trip ALL RCPs. BOP | * Trip ALL RCPs. | ||
Check NO SG depressurizing uncontrollably or completely depressurized. | BOP | ||
1B SG pressure dropping in an uncontrolled manner. | * Check if SG secondary pressure boundaries are intact: | ||
CREW Transition to 1BwEP | * Check NO SG depressurizing uncontrollably or completely depressurized. | ||
-2 | * 1B SG pressure dropping in an uncontrolled manner. | ||
CREW Transition to 1BwEP-2 FAULTED STEAM GENERATOR ISOLATION. | |||
Comments: | Comments: | ||
151 NRC 4 Page 20 | |||
Scenario NRC 4 Event 9 No: No. | |||
Event 1B SGTR (600 gpm), faulted/ruptured 1B SG | |||
== Description:== | == | ||
Description:== | |||
Time Position Applicants Actions or Behavior 1BwEP-2 FAULTED STEAM GENERATOR ISOLATION US | |||
Request SM evaluation of Emergency Plan conditions. | * Notify SM of plant status and procedure entry. | ||
Request STA evaluation of status trees. | * Request SM evaluation of Emergency Plan conditions. | ||
Enter/implement 1BwEP | * Request STA evaluation of status trees. | ||
-2 and direct operator actions of 1BwEP | * Enter/implement 1BwEP-2 and direct operator actions of 1BwEP-2 to establish the following conditions: | ||
-2 to establish the following conditions: | BOP | ||
BOP | * Check MS isolation: | ||
All MSIVs and bypass valves | * All MSIVs and bypass valves - CLOSED. | ||
- CLOSED. BOP | BOP | ||
1A, 1C & 1D SG pressures stable. | * Check if any SG secondary pressure boundary is intact: | ||
CREW | * 1A, 1C & 1D SG pressures stable. | ||
1B SG pressure lowering in an uncontrolled manner (1B SG indicates steam flow with its MSIV and MSIV bypass valve closed). | CREW | ||
BOP | * Identify faulted SG: | ||
Isolate 1B Steam Generator prior to completing step 4 of 1BwEP | * 1B SG pressure lowering in an uncontrolled manner (1B SG indicates steam flow with its MSIV and MSIV bypass valve closed). | ||
-2. (Westinghouse | BOP | ||
- CT-18) (K/A number | * Isolate 1B Steam Generator: | ||
- APE040AA1.10 importance 4.1/4.1) | Isolate 1B Steam Generator prior to completing step 4 of 1BwEP-2. | ||
(Westinghouse - CT-18) (K/A number - APE040AA1.10 importance 4.1/4.1) | |||
-0. Check FW to faulted SG isolated ( | [CT-18] | ||
Verify 1MS018B closed. | * Verify/Close 1AF013B & F - may have been closed at step 15 of 1BwEP-0. | ||
Verify 1SD002E & F closed. | * Check FW to faulted SG isolated (2nd row of FWI monitor lights LIT). | ||
Verify 1SD005C closed. | * Verify 1MS018B closed. | ||
BOP | * Verify 1SD002E & F closed. | ||
Reset Phase A at 1PM06J. | * Verify 1SD005C closed. | ||
OPEN 1SD005A | BOP | ||
-D at 1PM11J. | * Check AF Pump Suction Pressure: | ||
Request Chemistry to periodically sample | * Annunciator AF PUMP SX SUCT VLVS ARMED (1-3-E7) - NOT LIT. | ||
1B Main Steam Line radiation abnormal on PPC or RM | BOP | ||
-11. CREW Transition to 1BwEP | * Check Secondary Radiation: | ||
-3 | * Reset Phase A at 1PM06J. | ||
* OPEN 1SD005A-D at 1PM11J. | |||
Comments: | * Request Chemistry to periodically sample SGs for activity. | ||
* Check secondary radiation trends: | |||
* 1B Main Steam Line radiation abnormal on PPC or RM-11. | |||
CREW Transition to 1BwEP-3 STEAM GENERATOR TUBE RUPTURE. | |||
Comments: | |||
151 NRC 4 Page 21 | |||
Scenario NRC 4 Event 9 No: No. | |||
Event 1B SGTR (600 gpm), faulted/ruptured 1B SG | |||
== Description:== | == | ||
Description:== | |||
Time Position Applicants Actions or Behavior 1BwEP-3 STEAM GENERATOR TUBE RUPTURE US | |||
Request SM evaluation of Emergency Plan conditions. | * Notify SM of plant status and procedure entry. | ||
Enter/implement 1BwEP | * Request SM evaluation of Emergency Plan conditions. | ||
-3 and direct operator actions of 1BwEP | * Enter/implement 1BwEP-3 and direct operator actions of 1BwEP-3 to establish the following conditions: | ||
-3 to establish the following conditions: | ATC | ||
ATC | * Check Status of RCPs: | ||
RCPs - NONE running | * RCPs - NONE running - tripped earlier when RCP trip criteria met. | ||
- tripped earlier when RCP trip criteria met. | BOP | ||
BOP | * Identify ruptured SG 1B: | ||
1B Main steam line rad | * 1B Main steam line rad monitors ABNORMAL for plant conditions. | ||
Isolate flow from ruptured SG: | * Isolate flow from ruptured SG: | ||
Verify 1MS018B in auto and closed. | * Verify 1MS018B in auto and closed. (C/S may be in CLOSE, 1MS018B failed 90% | ||
(C/S may be in CLOSE, 1MS018B failed 90% open, 1MS019B closed). | open, 1MS019B closed). | ||
Verify 1SD002E & F CLOSED. | * Verify 1SD002E & F CLOSED. | ||
Verify MSIV and MSIV bypass valve for 1B SG CLOSED | * Verify MSIV and MSIV bypass valve for 1B SG CLOSED. | ||
* Check ruptured SG level - Narrow Range level < 10%: | |||
- Narrow Range level < 10%: | * Do not feed 1B SG per Caution prior to step. | ||
o Verify/close 1AF013B & F | o Verify/close 1AF013B & F - previously closed in 1BwEP-0 OR 1BwEP-2. | ||
- previously closed in 1BwEP | * Set 1AF005B and 1AF005F pot demand = 0%. | ||
-0 OR 1BwEP | CREW | ||
-2. Set 1AF005B and 1AF005F pot demand = 0%. | * Determine ruptured SG pressure < 320 psig. | ||
CREW | Transition to 1BwCA-3.1 SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. | ||
-3.1 | US | ||
- SUBCOOLED RECOVERY DESIRED. | * Notify SM of plant status and procedure entry. | ||
US | * Request SM evaluation of Emergency Plan conditions. | ||
Request SM evaluation of Emergency Plan conditions. | * Enter/implement 1BwCA-3.1 and direct operator actions of 1BwCA-3.1 to establish the following conditions: | ||
Enter/implement 1BwCA | BOP | ||
-3.1 and direct operator actions of 1BwCA | * Reset SI: | ||
-3.1 to establish the following conditions: | * Depress both SI reset pushbuttons. | ||
BOP Reset SI: | * Verify SI actuated permissive light - NOT LIT. | ||
Verify SI actuated permissive light | * Verify auto SI blocked permissive light - LIT. | ||
- NOT LIT. Verify auto SI blocked permissive light | * Reset CNMT isolation/establish IA to containment: | ||
- LIT. Reset CNMT isolation/establish IA to containment | o Reset Phase A (performed in 1BwEP-2). | ||
* Check a station air compressor is running at 0PM01J. | |||
-2). Check a station air compressor is running at 0PM01J. | * OPEN 1IA065 and 1IA066 at 1PM11J. | ||
OPEN 1IA065 and 1IA066 at 1PM11J. | Comments: | ||
151 NRC 4 Page 22 | |||
Scenario NRC 4 Event 9 No: No. | |||
Event 1B SGTR (600 gpm), faulted/ruptured 1B SG | |||
== | |||
Description:== | |||
Time Position Applicants Actions or Behavior BOP | |||
* Verify all AC buses energized by offsite power: | |||
* All 4 KV ESF buses energized. | |||
All 4 KV ESF buses energized. | * All 4 KV non-ESF buses energized. | ||
All 4 KV non-ESF buses energized. | * All 6.9 KV buses energized. | ||
All 6.9 KV buses energized. | * De-energize PZR Heaters: | ||
De-energize PZR Heaters: | * Place all B/U heaters contactors to OFF. | ||
Place all B/U heaters contactors to OFF. | * Place variable heater control switch in AFTER TRIP. | ||
Place variable heater control switch in AFTER TRIP. | o Consult with SM (TSC) for recommended minimum PZR level to keep PZR heaters covered. | ||
o Consult with SM (TSC) for recommended minimum PZR level to keep PZR heaters covered. Check if CS should be stopped: | * Check if CS should be stopped: | ||
CS pumps - NONE running. | * CS pumps - NONE running. | ||
Check ruptured SG level: | * Check ruptured SG level: | ||
1B SG NR level < 10% | * 1B SG NR level < 10% - do not feed 1B SG per Caution prior to step. | ||
- do not feed 1B SG per Caution prior to step. | * Check if RH pumps should be stopped: | ||
Check if RH pumps should be stopped: | * 1SI8812A & B open (aligned to RWST). | ||
1SI8812A & B open (aligned to RWST). | * RCS pressure > 325 psig and stable/rising. | ||
RCS pressure > 325 psig and stable/rising. o Stop both RH pumps and place in standby (if conditions met). | o Stop both RH pumps and place in standby (if conditions met). | ||
EXAMINERS NOTE: Terminate the scenario at Lead Examiners discretion. | |||
(Final)}} | (Final) | ||
Comments: | |||
151 NRC 4 Page 23}} |
Latest revision as of 13:33, 30 October 2019
ML16307A199 | |
Person / Time | |
---|---|
Site: | Braidwood ![]() |
Issue date: | 09/21/2016 |
From: | Walton R NRC/RGN-III/DRS/OLB |
To: | |
Shared Package | |
ML16306A161 | List: |
References | |
Download: ML16307A199 (107) | |
Text
Simulation Facility Braidwood Scenario Operating Test No.: 15-1 NRC No.:
NRC 1 Examiners: ______________________ Applicant: _____________________ SRO
______________________ _____________________ ATC
______________________ _____________________ BOP Initial Conditions: IC-21 Turnover: Unit 1 is at 100% power, steady state, equilibrium xenon, BOL. Following completion of turnover, the Shift Manager requests that the BOP swap the 0A & 0B WS pumps per BwOP WS-1 and WS-3 in preparation for surveillance testing on Unit 2.
Event Malf. No. Event Event No. Type* Description Preload Trgset 1 ZLO1HSMP025(3) == 0 Trg 1 IMF ED04A Offsite power is lost on the main generator trip 1 None N-BOP, Swap WS pumps US 2 IMF NI08H 500 10 I-ATC, US PR NI N-44 fails high TS-US 3 IMF RX03C 4.8 I-BOP, US 1B SG steam flow, 1FT-522, fails high 4 IMF CV05 600 5 C-ATC, Letdown line pressure controller 1PK-131 output US fails low 5 IOR ZDI1WO01PA TRIP C-BOP, 1A Containment Chilled Water Pump trip US 6 TH03B 5 60 TS-US 1B SG Tube Leak 7 None R-ATC, 1BwOA SEC-8 Fast Ramp US 8 IMF TH03B 550 M-ALL 1B SGTR 9 Preload C-ALL Offsite power is lost on the main generator trip (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient
SCENARIO OVERVIEW Unit 1 is at 100% power, steady state, equilibrium xenon, BOL. Following completion of turnover, the Shift Manager requests that the BOP swap the 0A & 0B WS pumps per BwOP WS-1 and WS-3 in preparation for surveillance testing on Unit 2.
After completing shift turnover and relief, the BOP will swap the 0A & 0B WS pumps in accordance with BwOP WS-1 and WS-3. The 0B WS pump will be started and the 0A WS pump will be placed in standby.
After swapping WS pumps, a failure of power range N-44 lower detector will occur. The crew will take actions per hard card 1BwPR 1-10-RD & 1BwOA INST-1 NUCLEAR INSTRUMENTATION MALFUNCTION including defeating the channel functions. Technical Specifications 3.3.1 Conditions A, D & E apply.
After the Power Range failure is addressed, a failure of 1FT-522, 1B SG steam flow channel, will occur. The crew will take actions per hard card 1BwPR 1-15-SG & 1BwOA INST-2 OPERATION WITH FAILED INSTRUMENT CHANNEL and perform required actions. The crew will swap to an operable steam flow channel.
After completion of steam flow failure actions, letdown pressure controller, 1PK-131, output will fail low. The letdown pressure control valve, 1CV131, will close and letdown pressure will rise lifting the letdown line relief valve. The ATC will take manual control of letdown pressure controller per hard card 1BwPR 1-9-LD and restore letdown pressure. The crew may isolate letdown due to the lifting letdown relief valve. If letdown is isolated, it will be restored per BwOP CV-17.
After the 1PK-131 controller failure is addressed, the 1A Containment Chilled Water pump will trip resulting in a trip of the 1A Containment Chiller. The crew will start the standby 1B Chilled Water pump and Chiller per BwOP VP-1 after receiving a report that the 1A Chilled Water pump motor appears damaged. Containment pressure and temperature will slowly rise as a result of the loss of Containment Cooling. The US should reference Tech Spec 3.6.4 and 3.6.5 and place a priority to start the standby Cnmt Chiller.
After the Containment Chilled Water malfunction has been addressed, a 1B Steam Generator Tube Leak will be initiated. The crew will implement 1BwOA SEC-8 STEAM GENERATOR TUBE LEAK. The crew should determine from the estimated leak size that a fast ramp to remove the unit from power is required and make preparations to ramp the unit off line using 1BwGP 100-4, POWER DESCENSION or 1BwOA PWR-1 POWER REDUCTION. Technical Specifications 3.4.13 Condition B applies.
After the SGTL has been addressed and the crew has ramped the unit sufficiently for a reactivity manipulation, the 1B SGTL will degrade to a 550 gpm Steam Generator Tube Rupture. The crew will implement 1BwEP-0 REACTOR TRIP OR SAFETY INJECTION. The crew will transition to 1BwEP-3 SGTR.
The scenario is complete when the crew has terminated high head injection and established normal charging flow in 1BwEP-3.
Critical Tasks
- 1. Identify the 1B SG as the ruptured SG and isolate prior to a transition to 1BwCA-3.1 is required.
(Westinghouse - CT-18) (K/A number - EPE038EA1.32 importance 4.6/4.7)
(Westinghouse - CT-20) (K/A number - EPE038EA1.04 importance 4.3/4.1) 151 NRC 1 Page 2
SIMULATOR SETUP GUIDE
- Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.
- Establish the conditions of IC-21, 100% power, steady state, equilibrium xenon.
- Complete items on Simulator Ready for Training Checklist.
- Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario.
- Place simulator in RUN (allow simulator to run during board walk down and turnover).
- Verify RM-11 on Grid 1.
- Monitor ruptured S/G status by using SimView file - SGTR.
- Run caep 151 NRC 1 SETUP from disk and verify the following actuate:
- Trgset 1 ZLO1HSMP025(3) == 0
- Trg 1 IMF ED04A
- Provide examinees with turnover sheets.
- Verify SER and RM-11 printers are clear of data.
- Set Leak Tracker Program PPC point U9050 = 1.25 gpd.
151 NRC 1 Page 3
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Swap WS pumps.
If dispatched as EO to observe WS pump swap, report 0B WS pump is ready for start, the pump has stable operating parameters once running. The stopped WS pump is not rotating backwards. Acknowledge the need to complete steps for aligning chemical injection.
Event 2: Power Range N-44 fails high.
Insert IMF NI08H 500 10 to fail N-44 lower detector high over 10 seconds.
Acknowledge as SM, entry into Tech Spec 3.3.1 Conditions A, D & E.
Acknowledge as SM, request for writing IR, performing on-line risk assessment and making appropriate notifications.
As SM, if requested for support for bypassing bistables in AEER, report that AEER bistables are not to be bypassed until work analyst and NSO support can be obtained (in approx. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) and that the abnormal operating procedure should be continued.
ENSURE CONTROL RODS IN AUTO PRIOR TO INSERTING EVENT 3.
Event 3: Steam Flow detector 1FT-522 fails high.
Insert IMF RX03C 4.8 to fail 1B SG steam flow detector, 1FT-522, high.
As SM, acknowledge failure of 1FT-522, and requests for on-line risk assessment, maintenance support, and IR initiation.
As SM, acknowledge request for personnel notifications.
Event 4: Letdown line pressure controller 1PK-131 output fails low.
Insert IMF CV05 600 5 to fail 1CV131 controller to 600 psig over 5 seconds.
If dispatched as EO to investigate 1PT-131, wait three minutes and report no visible damage to 1PT-131.
If dispatched as EO to align excess letdown to the top of the VCT, insert the following:
- MRF CV26remf 100 to open 1CV8482.
- MRF CV27 0 to close 1CV8484.
Acknowledge as SM, the 1PK-131 failure, on-line risk assessment, requests for maintenance support, and IR requests.
151 NRC 1 Page 4
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 5: 1A Containment Chilled Water pump trip.
Insert IOR ZDI1WO01PA TRIP to trip the 1A Containment Chilled Water pump.
After the 1A Chilled Water pump is tripped, DELETE override DOR ZDI1WO01PA.
If dispatched as EO to investigate 1A Chilled Water pump breaker, wait 2 minutes and report the breaker tripped free. The 1A Cnmt Chiller breaker is open with NO flags.
If dispatched as EO to investigate 1A Chilled Water pump, wait 3 minutes and report the pump motor smells acrid and there is a haze above the motor (no fire). Cause of 1A Containment Chiller trip is EVAP LOW WATER FLOW.
If asked as EO, report 1TIS-WO018 reads 44oF.
As SM, acknowledge the trip of 1A Containment Chilled Water pump and Chiller, on-line risk assessment, maintenance support, and IR initiation.
If asked direct the crew to start the 1B Chiller remotely from the MCR rather than locally. (reason is to limit time frame to restore Containment cooling).
As EO, provide local operator actions for starting the 1B Containment Chilled Water Pump and Chiller (BwOP VP-1):
- (step F.2) As EO, Oil Heater Breaker is on. If contacted as WEC supervisor, the WEC is tracking 1B Chiller Oil Heater energization time.
- (step F.5) Pump suction pressure is 22 psig. WO Expansion Tank level is 55%.
- (step F.7) 1WO005B is throttled. 1FIS-WO027 indicates 3000 gpm.
- (step F.8) Chiller Oil level is 50% in sightglass.
- (step F.9) Lamp test was satisfactory for all light bulbs.
- (step F.10) Chiller oil temperature is in band and Low Oil Temp alarm NOT lit locally.
- (step F.11) Electrical Demand Selector is in the 60% demand position.
- (step F.12) LCD on the purge control unit displays ADAPTIVE mode.
- (step F.13) RESET pushbutton has been depressed for 2 seconds, no trip lights lit.
- (step F.15) IF asked to start the Chiller locally, report that the Local/Remote transfer switch is physically stuck in the REMOTE position (the intent is for the MCR to start the chiller per step F.16).
- (step F.16) Report that as EO you are standing by the 1B Containment Chiller ready for a remote start (START/STOP Switch is in STOP; Local/Remote switch is in REMOTE).
- (step F.17) The Program Timer Light at the Local Control Panel is lit.
- Report that you will complete the remaining local steps (F.18 - F.30).
151 NRC 1 Page 5
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 6: 1B SG tube leak.
Insert IMF TH03B 8 gpm initial to 9 gpm final over 30 minutes - 1B SGTL at 8 gpm to 9 gpm over 30 minutes.
If called as Chemistry for 1B S/G sample, wait 15 minutes and report the estimated 1B S/G leakrate at 5 gpm.
If called as Chemistry a second time for 1B S/G sample, wait 10 minutes and report the estimated 1B S/G leakrate at 5 gpm.
Acknowledge as SM, procedure transitions, Tech Spec 3.4.13 Condition B entry, E Plan evaluation.
Event 7: Fast ramp of unit off line.
To reset the SG blowdown panel trouble alarm, use the following:
Insert IRF WD14 RESET As SM, acknowledge fast ramp requirement.
Acknowledge as Generation Dispatch, the initiation of ramp.
Event 8: 1B SGTR.
Insert IMF TH03B 550 to initiate a 550 gpm tube rupture in the 1B SG.
Acknowledge as SM: procedure transitions, E Plan evaluations, and STA request.
If asked, use SimView to close 1FW002A-C (in SimView, set FWV1FW002A/B/C = 0).
If asked, status of SAT 142-1 after sudden pressure trip, wait 2 minutes, then report deluge has initiated, NO fire exists.
Run CAE DrainCCSurge.cae if requested to isolate WM makeup and drain the CC surge tank.
151 NRC 1 Page 6
Scenario NRC 1 Event 1 No: No.
Event Swap WS pumps
==
Description:==
Time Position Applicants Actions or Behavior CUE
- From turnover, swap 0A & 0B WS pumps per BwOP WS-1 STARTUP AND OPERATION OF THE NON-ESSENTIAL SERVICE WATER SYSTEM and BwOP WS-3 SHUTDOWN OF A NON-ESSENTIAL SERVICE WATER PUMP.
US
- Direct BOP to perform BwOP WS-1 and BwOP WS-3.
BOP Refer to BwOP WS-1, step 3.
- Direct EO to verify proper 0B WS pump bearing oil levels.
- Direct EO to perform Att. A to flush/clean 0B WS pump strainer.
- Direct EO to verify/open 0WS002B, 0B WS pump discharge valve.
- Start 0B WS pump at 0PM01J.
- Check for normal pump parameters.
- Direct EO to OPEN 0CFX401, 0B WS pump chem injection isolation valve.
Refer to BwOP WS-3 (ALL 3 WS pumps are running).
- Direct EO to close 0CFX400, 0A WS pump chem injection isolation valve.
- Place the 0A WS pump control switch in PULL OUT at 0PM01J.
- Direct EO to verify that the 0A WS pump shaft stops rotating.
- Direct EO to verify proper 0A WS pump bearing oil levels.
- Direct EO to verify/open 0WS002A, 0A WS pump discharge valve.
- Place the 0A WS pump control switch in AFTER TRIP.
- Check 0A WS pump stop light ON.
- Direct EO to complete BwOP WS-3 step F.6 actions at Lake Screen House.
- Inform US that the WS pump swap is complete.
US
- Acknowledge report of WS pump swap.
o Notify SM that WS pump swap is complete.
ATC o Monitor remainder of MCBs.
EXAMINERS NOTE: After BwOP WS-1 & WS-3 are complete and with Lead Examiners concurrence, enter next event.
Comments:
151 NRC 1 Page 7
Scenario NRC 1 Event 2 No: No.
Event Power Range N-44 fails high.
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator PWR RNG FLUX RATE RX TRIP ALERT (1-10-C3)
- Annunciator PWR RNG CHANNEL DEV (1-10-C4)
- Annunciator PWR RNG LOWER DET FLUX DEV HIGH (1-10-B4)
- Control rod inward motion.
- Determine PR channel N-44 failing high.
- Verify turbine load stable, then place control rods in manual (may use hard card 1BwPR 1-10-RD).
o Reference BwARs as time permits.
CREW
- Identify entry conditions for 1BwOA INST-1 NUCLEAR INSTRUMENTATION MALFUNCTION.
US
- Implement 1BwOA INST-1 NUCLEAR INSTRUMENTATION MALFUNCTION, Attachment A "PR CHANNEL FAILURE" and direct operator action.
- Notify SM of PR N-44 failure.
- Notify SM to evaluate for Emergency Plan.
- Check rod control status.
- Rod bank select switch in manual (performed previously).
- Check for rod stop.
- Annunciator PWR RNG FLUX HIGH ROD STOP (1-10-B5) - LIT.
- Place rod stop bypass switch to N-44 at 1PM07J.
- Verify TAVE - TREF stable & within 1°F. If NOT, restore TAVE - TREF to within 1°F:
o Withdraw control rods.
o Adjust RCS boron concentration.
o Adjust turbine load.
- Check SG levels normal and stable.
- Bypass/defeat PR channel functions at 1PM07J:
- N-44 upper section detector current comparator.
- N-44 lower section detector current comparator.
- N-44 power mismatch bypass.
o N-44 rod stop bypass (performed previously).
- N-44 comparator channel defeat.
Comments:
151 NRC 1 Page 8
Scenario NRC 1 Event 2 No: No.
Event Power Range N-44 fails high.
==
Description:==
Time Position Applicants Actions or Behavior BOP
- Reset flux rate trip alarm for N-44 at 1PM07J.
- Place computer points in test:
- N0047
- N0048
- U1143
- Delete computer point from scan:
- N0052A
- Place N44 input to DEH in Test.
US o As directed by the Shift Manager:
o Locally bypass bistables for affected channel.
o Trip bistables for affected PR channel.
BOP o Locally bypass bistables for failed NI protection channel functions.
- Access failed NI protection panel.
- Verify bypass enable key lock switch is in normal.
- Verify following individual bypass function switches in normal and bypass LEDs off:
- SWITCH #2 P10 PERMISSIVE
- SWITCH #3 POSITIVE RATE TRIP
- SWITCH #4 OVER POWER TRIP-LOW
- SWITCH #5 OVER POWER TRIP-HIGH
- SWTICH #6 OVER POWER ROD STOP
- SWITCH #7 P8 PERMISSIVE
- Energize failed channel bypass panel by pressing both breaker to on.
- Non-safety breaker ON.
- Safety breaker ON.
- Insert key in bypass enable key lock and turn key to BYPASS position.
- Verify bypass enable LED is lit.
- Place bypass function switches in bypass and verify bypass LEDs are lit.
- SWITCH #2 P10 PERMISSIVE
- SWITCH #3 POSITIVE RATE TRIP
- SWITCH #4 OVER POWER TRIP-LOW
- SWITCH #5 OVER POWER TRIP-HIGH
- SWTICH #6 OVER POWER ROD STOP
- SWITCH #7 P8 PERMISSIVE Comments:
151 NRC 1 Page 9
Scenario NRC 1 Event 2 No: No.
Event Power Range N-44 fails high.
==
Description:==
Time Position Applicants Actions or Behavior o Locally bypass AEER bistables for PR N-44 to bypass.
- Select operable channel (other than 1D) to loop T recorder.
- Check if rod control can be placed in auto.
- C-5 not lit.
- TAVE - TREF stable and within 1°F.
- Place control rods in auto.
US
- Determine Tech Spec 3.3.1 Conditions A, D, and E are applicable.
o Enter/exit Tech Spec 3.4.1 if PZR pressure dropped below 2209 psig during auto rod steps.
- Contact SM to perform risk assessment, initiate IR, evaluate reactivity screening, make notifications and contact appropriate personnel to investigate/correct instrument failure.
EXAMINERS NOTE: (1) After the actions for PRNI N-44 are complete and with Lead Examiners concurrence, enter next event.
(2) Ensure rods are back in AUTO prior to inserting the next event.
Comments:
151 NRC 1 Page 10
Scenario NRC 1 Event 3 No: No.
Event Steam flow detector, 1FT-522, failure
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator S/G 1B FLOW MISMATCH FW FLOW LOW (1-15-B4)
- 1FI-522A steam flow indicator fails high.
o Annunciator S/G 1B LEVEL DEVIATION HIGH LOW (1-15-B9)
- Determine 1FT-522 failed high.
- Place master feed pump speed control in manual.
- Select operable steam flow channel.
o Reference BwARs.as time permits.
CREW
- Identify entry conditions for 1BwOA INST-2 OPERATION WITH FAILED INSTRUMENT CHANNEL.
US
- Notify SM of plant status and procedure entry.
- Request SM evaluation of Emergency Plan conditions.
- Enter/implement 1BwOA INST-2 OPERATION WITH FAILED INSTRUMENT CHANNEL, Attachment H, STEAM FLOW CHANNEL FAILURE and direct operator actions of 1BwOA INST-2.
- Stabilize 1B SG level (actions to stabilize per hard card 1BwPR 1-15-SG initially, then 1BwOA INST-2).
o If SG level abnormal:
o Control 1B FRV (1FW520) in manual.
o Place master feed pump speed control in manual.
o Verify adequate feedwater DP (1BwGP 100-3A9).
o Restore SG level(s).
- Select operable steam flow channel (1BwPR 1-15-SG action):
- Establish/verify automatic SG level control.
- Verify steam pressure channels normal.
BOP o Ramp 5 MW down at 5 MW/minute (may be performed based on crew discretion).
Comments:
151 NRC 1 Page 11
Scenario NRC 1 Event 3 No: No.
Event Steam flow detector, 1FT-522, failure
==
Description:==
Time Position Applicants Actions or Behavior EXAMINERS NOTE: 1BwOA PRI-16 RESPONSE TO OVERPOWER CONDITION may also be used to lower Rx power below 100%.
CREW
- Check reactor power <100%:
- PPC 10 min. calorimetric.
- Computer point (U0923)
- NIs.
US
- Notify SM/maintenance to investigate/correct the failed steam flow channel:
- Determine Tech Specs are NOT applicable.
- Contact SM to perform risk assessment, initiate IR, reactivity screening, notify QNE and contact maintenance to investigate/correct instrument failure.
EXAMINERS NOTE: After the actions for the steam flow failure are complete and with Lead Examiners concurrence, insert next event.
Comments:
151 NRC 1 Page 12
Scenario NRC 1 Event 4 No: No.
Event 1PK-131 output fails low
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator LTDWN HX OUTLT PRESS HIGH (1-8-B5)
- 1FI-132, letdown line flow, lowering.
- 1PI-131, letdown line pressure, rising.
o Annunciator LP LTDWN RLF TEMP HIGH (1-9-B1)
- Recognize 1PK-131 failed.
- Place 1PK-131 in manual and adjust letdown pressure to pre-failed value per hard card 1BwPR 1-9-LD at 1PM05J.
o Refer to BwARs as time permits.
US
o Direct ATC to isolate letdown.
ATC Perform the following at 1PM05J:
- Maintain letdown flow and pressure by operating 1PK-131 in manual.
o May take manual control of 1TK-130.
US
- Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.
EXAMINERS NOTE: (1) The crew may elect to isolate letdown based on letdown relief valve lifting. Following letdown isolation, the crew may elect to establish excess letdown or re-establish normal letdown. The steps for restoring normal letdown are in italics below.
(2) The crew may use hard card 1BwPR 1-9-LD to isolate letdown.
BOP o Establish normal letdown per BwOP CV-17:
o Verify/close 1CV8149A/B/C.
o Verify CC aligned to letdown HX (was previously aligned).
o Place 1CV131 controller in manual at 40% demand.
o Place 1CC130 controller in manual at 60% demand.
Comments:
151 NRC 1 Page 13
Scenario NRC 1 Event 4 No: No.
Event 1PK-131 output fails low
==
Description:==
Time Position Applicants Actions or Behavior o Verify/open 1CV8152/8160.
o Verify/open 1CV459/460.
o Verify/open 1CV8324A & 1CV8389A.
o Verify/open 1CV381B (BTRS Mode Selector Switch OFF light LIT).
o Verify/close 1CV381A (BTRS Mode Selector Switch OFF light LIT).
o Verify/open 1CV8401A.
o Verify/close 1CV8145.
o Verify/open 1CV8147.
o Open 1CV8105/8106.
o Adjust charging flow to approx. 100 gpm w/seal injection 8-10 gpm per RCP.
o Open 1CV8149A/B/C and control 1CV131 to maintain letdown pressure 360-380 psig.
o Control 1CC130 controller to maintain letdown temperature 90-115°F.
o Place controllers in auto.
o Verify 1PR06J in service.
o Verify proper operation of RMCS during VCT makeup.
o Proper flow indicated on PW/Total Flow (1FT-0111) and Boric Acid Flow (1FT-0110).
o Restore PZR level to program.
The steps for establishing excess letdown are in italics below.
BOP o Establish excess letdown per BwOP CV-15 EXCESS LETDOWN OPERATIONS.
o Prerequisite if excess letdown is placed in service, reactor power is maintained less than or equal to 99.8%.
o Verify open 1CV8100/8112.
o Open 1CC9437A/B.
o Verify/closed 1CV123.
o Verify 1CV8143 C/S in VCT position.
o Open 1RC8037A/B/C/D.
o Open 1CV8153A(B).
o Slowly open 1CV123 while maintaining excess letdown outlet temperature <165F.
EXAMINERS NOTE: After the actions for the 1PK-131 failure are complete and with Lead Examiners concurrence, insert next event.
Comments:
151 NRC 1 Page 14
Scenario NRC 1 Event 5 No: No.
Event 1A Containment Chilled Water pump trip
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator CNMT CHLR UNIT TROUBLE (0-33-D3)
- 1A Containment Chiller trip light - LIT.
- 1A Chilled Water pump trip light - LIT.
US o Direct BOP to respond to BwAR 0-33-D3.
- Direct BOP to start 1B Containment Chilled Water Pump and Chiller.
- Notify SM of 1A Cnmt Chilled Water pump failure.
o Evaluate Containment conditions against Tech Specs 3.6.4 and 3.6.5.
o Notify SM to evaluate for Emergency Plan.
- Determine 1A Cnmt Chiller and Chilled Water pump tripped.
- Reference BwAR 0-33-D3 (dispatch EO to Cnmt Chiller/Chilled Water pump).
o Place 1A Chilled Water Pump/Chiller C/S in PTL.
- Start 1B Containment Chilled Water Pump and Chiller per BwOP VP-1.
BOP BwOP VP-1 Actions:
- Direct EO to locally energize oil heaters and notifies WEC to track energization time of heaters-verify heaters energized for 1B VP chiller.
- Verify OPEN:
- 1SX112B, Cnmt Chiller SX Inlet Vlv.
- 1SX114B, Cnmt Chiller SX Outlet Vlv.
- 1SX147B, Cnmt Chiller SX Bypass Vlv.
- Verify OPEN @ 1PM06J:
- 1WO006B, 1B + 1D Chill Wtr Inlet Cnmt Isol Vlv.
- 1WO020B, 1B + 1D Chill Wtr Outlet Cnmt Isol Vlv.
- 1WO056B, 1B + 1D Chill Wtr Outlet Cnmt Isol Vlv.
- Direct local EO to perform steps F.5 (verify Pump suction pressure and Expansion Tank level).
- Start 1WO01PB, Chilled Water Pump.
- Direct EO to locally complete BwOP VP-1 steps F.7 - F.13.
- Verify/place 1B Byp Isol Vlv 1SX147B in AUTO at 0PM02J.
- Start the 1B Containment Chiller from the MCR:
Comments:
151 NRC 1 Page 15
Scenario NRC 1 Event 5 No: No.
Event 1A Containment Chilled Water pump trip
==
Description:==
Time Position Applicants Actions or Behavior
- Direct EO to locally verify START/STOP switch in STOP and Local/Remote switch in Remote and is prepared to record initial data locally.
- Place 1WO01CB, Chiller 1B Control Switch, at 0PM02J to AFTER CLOSE.
- Direct EO to locally complete steps F.17 to F.30.
US
- Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.
EXAMINERS NOTE: After the actions for the Containment Chilled Water pump trip are complete and with Lead Examiners concurrence, insert next event.
Comments:
151 NRC 1 Page 16
Scenario NRC 1 Event 6 No: No.
Event 1B SG Tube Leak
==
Description:==
Time Position Applicants Actions or Behavior CUE
- RM-11 Secondary rad monitor alarms/levels rising:
o SG BLDN - 1PR08J.
o SJAE/GLAND STEAM EXHAUST - 1PR027J.
o 1B MAIN STEAM LINE - 1AR022J/23J.
o PZR level dropping.
o PZR pressure dropping.
o Charging/letdown mismatch.
BOP o Refer to BwAR 1-1PR27J for operator actions.
o Refer to BwAR 1-1PR08J for operator actions.
o Refer to BwAR 1-1AR22/23J for operator actions.
CREW
- Identify entry conditions for 1BwOA SEC-8 STEAM GENERATOR TUBE LEAK.
US
- Implement 1BwOA SEC-8 and direct operator actions.
- Request SM evaluation of Emergency Plan conditions.
- Check SI Status:
o PZR pressure < 1829 psig.
o Steamline pressure < 640 psig.
o CNMT pressure > 3.4 psig.
- Maintain PZR level:
- Throttle 1CV121 & 1CV182 as necessary.
- Check PZR level stable or rising.
o If PZR level lowering, reduce letdown flow to 75 gpm.
- Monitor VCT level.
- Verify makeup is adequate to maintain VCT level.
US
- Minimize Secondary Contamination.
- Dispatch operators to perform BwOP MS-13 OPERATION WITH SG TUBE LEAKAGE.
Comments:
151 NRC 1 Page 17
Scenario NRC 1 Event 6 No: No.
Event 1B SG Tube Leak
==
Description:==
Time Position Applicants Actions or Behavior US
- Notify RP to monitor rad levels and quantify release.
CREW
- Identify leaking SG (1B).
- Trend Main Steam Line monitors.
o Dropping feed flow with stable SG level.
o Unexpected rise in any NR SG level.
o Chemistry reports high activity via sample or N-16 monitor.
CREW
- Determine SG tube leak rate.
- Estimate leak rate.
o Computer point U9052 or SG Leak Tracker Program on PPC.
o Charging/letdown/RCP leakoff flow balance.
o Change in VCT level.
o Grab sample.
o 1BwOS SG-1 SG, Pri to Sec Leakage Estimation.
- Check total RCS to secondary leak rate > 10 gpm - NO.
- Perform 1BwOSR 3.4.13.1 while continuing with 1BwOA SEC-8.
- Trend SG leakrate.
- Notify Chemistry to sample SGs.
- Check PPC point U9052 responding to plant conditions (1PR08J/N-16 rad monitors).
- Trend leakrate every 15 minutes.
- Determine if a shutdown is required.
- SG leakrate < 100 gpd - NO - GO TO step 9.
CREW
- Confirm SG leak rate (step 9).
- At least 2 independent indications - TREND in the same direction.
o Main steam line radiation monitors.
o SJAE/GS Exhaust radiation monitor.
o SG Blowdown radiation monitor.
o N-16 radiation monitors.
Comments:
151 NRC 1 Page 18
Scenario NRC 1 Event 6 No: No.
Event 1B SG Tube Leak
==
Description:==
Time Position Applicants Actions or Behavior CREW
- Initiate Unit Shutdown.
- Check leak rate < 100 gpd - NO.
- Reduce power to < 50% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (Rapid Power Reduction - 1BwGP 100-4T3).
o Shutdown Unit to MODE 3 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of reaching 50% power. Continue shutdown using 1BwGP 100-4 and 5.
US
- Determine Tech Spec 3.4.13 Condition B applies.
EXAMINERS NOTE: At this point, the crew should begin preparations for shutting down the unit. The remaining actions of 1BwOA SEC-8 would be performed after the reactor is shutdown, if an SI does NOT actuate.
EXAMINERS NOTE: The fast ramp due to the SG tube leak is event 7. See the following pages.
Comments:
151 NRC 1 Page 19
Scenario NRC 1 Event 7 No: No.
Event 1BwOA SEC-8 Fast Ramp
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Determine from 1BwOA SEC-8, a fast ramp load drop is required.
US o Perform pre-job brief per HU-AA-1211 PRE-JOB, HEIGHTENED LEVEL OF AWARENESS, INFREQUENT PLANT ACTIVITY, AND POST JOB BRIEFINGS for load ramp.
o Perform pre-job brief using the Emergent Ramp Reactivity Summary Sheet (under the NSO desk glass) for load ramp.
o Inform SM of the 1BwOA SEC-8 fast ramp.
CREW
- Review Operator Aid for 1BwOA SEC-8 Fast Ramp reactivity plan.
- Review applicable Prerequisites, Precautions, and Limitations and Actions of 1BwGP 100-4.
EXAMINERS NOTE: The following step may be repeated as necessary to borate the RCS during the power descension.
ATC BwOP CV-6 Attachment A, borate in automatic, via hard card. Perform the following at 1PM05J:
- Verify rod position and boron concentration.
- Determine required boric acid volume.
o Refer to operator aid for required boric acid addition.
- Determine desired boric acid flow rate.
- Perform the following at 1PM05J:
o Turn on PZR backup heaters (as required).
- Set 1FK-110 BA Flow Controller to desired boration rate.
- Set 1FY-0110 BA Blender Predet Counter to desired volume.
- Place MAKE-UP MODE CONT SWITCH to STOP position.
- Place MODE SELECT SWITCH to BORATE position.
- Place MAKE-UP MODE CONT SWITCH to START.
- Verify proper operation of valves and BA transfer pump (1CV110B open, Boric Acid Transfer Pump running, 1CV110A throttles open, proper BA flow indicated on recorder).
o If desired, adjust 1LK-112, VCT level controller, setpoint to control VCT level.
- When desired boration achieved, place RMCS M/U CONT switch to STOP.
- Verify 1CV110B closed, 1CV110A closed and Boric Acid Transfer Pump stopped.
OR Comments:
151 NRC 1 Page 20
Scenario NRC 1 Event 7 No: No.
Event 1BwOA SEC-8 Fast Ramp
==
Description:==
Time Position Applicants Actions or Behavior BwOP CV-6 Attachment A, batch boration, via hard card. Perform the following at 1PM05J:
o Turn on PZR backup heaters (as required).
- Open 1CV110B.
- Open 1CV110A.
- Start the BA Transfer pump.
o If desired, adjust 1LK-112, VCT level controller, setpoint to control VCT level.
- When desired amount of BA has been added, stop the BA Transfer Pump.
- Close 1CV110A.
- Close 1CV110B.
o Adjust 1LK-112, VCT level controller, setpoint to desired value.
- Place 1CV110A/B to AUTO.
- Record boration in Unit log.
- Perform BwOP CV-7 to return RMCS to automatic.
- Lower turbine load at 1PM02J or OWS drop 210 by performing the following:
- Select SETPOINT.
- Enter desired MWs into REF DEMAND window.
- Select ENTER.
- Verify correct value in REFERENCE DEMAND window.
- Enter desired MW/min into the RATE window.
- Select ENTER.
- Select EXIT.
- Select GO/HOLD.
- Verify GO/HOLD button illuminates.
- Verify HOLD illuminated RED.
- Inform crew of pending ramp with an UPDATE.
- Select GO.
- Verify GO illuminates RED.
- Verify main turbine load begins to lower.
- Monitor reactor power and turbine load lowering.
- Monitor NIs, Tave, I, PZR pressure/level at 1PM05J.
- Monitor MWe and DEHC system response at 1PM02J or OWS drop 210.
- During boration, monitor the following at 1PM05J and PPC:
o Monitor VCT level.
Comments:
151 NRC 1 Page 21
Scenario NRC 1 Event 7 No: No.
Event 1BwOA SEC-8 Fast Ramp
==
Description:==
Time Position Applicants Actions or Behavior o Monitor BA predet counter.
o Verify boration auto stops at preset value.
o Return Reactor Makeup Control System to automatic at current boron concentration.
EXAMINERS NOTE: The crew may use 1BwOA PWR-1 POWER REDUCTION as the guidance to perform the fast ramp. Steps in italics below.
CREW 1BwOA PWR-1 POWER REDUCTION
- Request SM evaluation of Emergency Plan conditions.
- Perform a reactivity summary brief.
- Check control rods in auto.
- Energize PZR backup heaters, as necessary.
- Perform boration, as time permits, prior to the ramp per the following:
o Borate per Op Aid guidance.
o As directed by the SM/designee.
- SELECT setpoint.
- ENTER desired load into REF DEMAND window.
- SELECT LEFT ENTER.
- VERIFY the correct value appears in the REFERENCE DEMAND window.
- ENTER desired MW/MIN ramp rate into the RATE window.
- Verify the correct value appears in the RATE window.
- SELECT RIGHT ENTER.
- Notify Control Room team of the pending ramp.
- SELECT GO/HOLD.
- VERIFY GO/HOLD illuminates orange.
- VERIFY HOLD indicator illuminates red.
- SELECT GO.
- VERIFY GO indicator illuminates red while the main turbine ramps.
- VERIFY main turbine load begins to drop.
- Notify TSO.
- Check PZR pressure controlling at or trending to 2235 psig.
- Check PZR level controlling at or trending to program level.
Comments:
151 NRC 1 Page 22
Scenario NRC 1 Event 7 No: No.
Event 1BwOA SEC-8 Fast Ramp
==
Description:==
Time Position Applicants Actions or Behavior
- Maintain Tave within 4°F of Tref.
- Check SG NR level.
- Notify Chemistry and RP of ramp in progress
- Notify SM to perform risk assessment, initiate IR, reactivity screening, notify QNE and notify other personnel.
EXAMINERS NOTE: After measurable change in power (approx. 10 min.) and with Lead Examiners concurrence, insert next event.
Comments:
151 NRC 1 Page 23
Scenario NRC 1 Event 8&9 No: No.
Event 1B SGTR, Loss of Offsite Power
==
Description:==
Time Position Applicants Actions or Behavior CUE
- RM-11 Secondary rad monitor alarms/levels rising.
o SJAE/GLAND STEAM EXHAUSTER - 1PR027J.
o 1B/1C MAIN STEAM LINE - 1AR022J/23J.
- PZR level dropping.
- PZR pressure dropping.
- Charging/letdown mismatch.
CREW Identify entry conditions for 1BwEP-0 REACTOR TRIP OR SAFETY INJECTION.
- Insert manual reactor trip and actuate SI as directed.
US
- Notify SM of plant status and procedure entry.
- Request SM evaluation of Emergency Plan conditions.
- Enter/implement 1BwEP-0 and direct operator actions of 1BwEP-0 to establish the following conditions:
ATC Perform immediate operator actions of 1BwEP-0 at 1PM05J:
- Verify reactor trip:
- Rod bottom lights - ALL LIT.
- Reactor trip & Bypass breakers - OPEN.
- Neutron flux - DROPPING.
BOP Perform immediate operator actions of 1BwEP-0 at 1PM02J:
- Verify turbine trip:
- All Turbine throttle valves - CLOSED.
- All Turbine governor valves - CLOSED.
BOP Perform immediate operator actions of 1BwEP-0 at 1PM01J:
- Verify power to 4KV busses:
- ESF Buses - BOTH ENERGIZED.
CREW Perform immediate operator actions of 1BwEP-0 at 1PM05J:
- Check SI Status:
Comments:
151 NRC 1 Page 24
Scenario NRC 1 Event 8&9 No: No.
Event 1B SGTR, Loss of Offsite Power
==
Description:==
Time Position Applicants Actions or Behavior
- SI First OUT annunciator - LIT.
- SI ACTUATED Permissive Light - LIT.
- SI Equipment - AUTOMATICALLY ACTUATED:
o Either SI pump - RUNNING.
o Either CV pump to cold leg isolation valve OPEN - 1SI8801A/B.
- Manually actuate SI at 1PM05J & 1PM06J.
US Direct BOP to perform Attachment B of 1BwEP-0.
EXAMINERS NOTE: US and ATC will continue in 1BwEP-0 while BOP is performing Attachment B.
- Verify FW isolated at 1PM04J.
- FW pumps - TRIPPED.
- FW isolation monitor lights - LIT (lights de-energized).
- FW pumps discharge valves - CLOSED (or going closed) 1FW002A-C (lights de-energized).
- Verify DGs running at 1PM01J:
- DGs - BOTH RUNNING.
- 1SX169A/B OPEN.
- Dispatch operator to monitor DGs operation.
- Verify Generator Trip at 1PM01J:
- OCB 1-8 and 7-8 open.
- PMG output breaker open.
- Verify Control Room ventilation aligned for emergency operations at 0PM02J:
- Operating VC train equipment - RUNNING.
- 0B Supply fan
- 0B Return fan
- 0B M/U fan
- 0B Chilled water pump
- 0B Chiller
- M/U fan outlet damper - 0VC08Y NOT FULLY CLOSED.
- 0B VC train M/U filter light - LIT.
Comments:
151 NRC 1 Page 25
Scenario NRC 1 Event 8&9 No: No.
Event 1B SGTR, Loss of Offsite Power
==
Description:==
Time Position Applicants Actions or Behavior
- 0VC09Y - OPEN.
- 0VC313Y - CLOSED.
- Operating VC train Charcoal Absorber aligned for train B.
- 0VC44Y - CLOSED.
- 0VC05Y - OPEN.
- 0VC06Y - OPEN.
- Control Room pressure greater than +0.125 inches water on 0PDI-VC038 (meter de-energized, dispatch EO to perform BwOP VC-14).
- Verify Auxiliary Building ventilation aligned for emergency operations at 0PM02J:
- Two inaccessible filter plenums aligned.
- Plenum A:
- 0VA03CB - RUNNING.
- 0VA023Y - OPEN.
- 0VA436Y - CLOSED.
- Plenum C:
- 0VA03CF - RUNNING.
- 0VA072Y - OPEN.
- 0VA438Y - CLOSED.
- Verify FHB ventilation aligned for emergency operation at 0PM02J:
- 0VA04CB - RUNNING.
- 0VA055Y - OPEN.
- 0VA062Y - OPEN.
- 0VA435Y - CLOSED.
- Trip all running HD pumps (no power).
- Initiate periodic monitoring of Spent Fuel Cooling.
- Notify US Attachment B complete/manual actions taken.
- Verify ECCS pumps running at 1PM05J/1PM06J:
- BOTH CV pumps - RUNNING.
- BOTH RH pumps - RUNNING.
- BOTH SI pumps - RUNNING.
- Verify the following at 1PM06J:
- RCFCs running in accident mode.
- Group 2 RCFC accident mode status light lit.
- CNMT Phase A valves closed.
Comments:
151 NRC 1 Page 26
Scenario NRC 1 Event 8&9 No: No.
Event 1B SGTR, Loss of Offsite Power
==
Description:==
Time Position Applicants Actions or Behavior ATC
- Perform the following at 1PM06J:
- Verify Cnmt Vent isolation:
- Group 6 Cnmt Vent Isol monitor lights - LIT.
- Verify AF system:
- BOTH AF pumps - RUNNING.
- AF flow control valves - 1AF005A-D throttled OPEN.
- Verify CC pumps running:
- BOTH CC pumps - RUNNING.
- Verify SX pumps running:
- BOTH SX pumps - RUNNING.
- Check if Main Steamlines Should Be Isolated:
- S/G pressures > 640 psig at 1PM04J.
- CNMT pressure < 8.2 psig at 1PM06J.
- Check if CS is required:
- CNMT pressure remained < 20 psig.
- Verify total AF flow:
- AF flow > 500 gpm.
Identify the 1B SG as the ruptured SG and isolate prior to a transition to 1BwCA-3.1 is required. (Westinghouse - CT-18) (K/A number - EPE038EA1.32 importance 4.6/4.7)
- If 1B SG NR level > 10% and rising in an uncontrolled manner, then:
[CT-18]
- CLOSE 1AF013B.
[CT-18]
- CLOSE 1AF013F.
- Set 1AF005B and 1AF005F pot demand = 0%.
- Verify ECCS valve alignment:
- Group 2 cold leg injection monitor lights lit.
- Verify ECCS flow:
- Check PZR PORVs and spray valves:
- PORVs CLOSED.
- PORV isolation valves - BOTH ENERGIZED.
- Normal spray valves CLOSED (valve position lights de-energized).
Comments:
151 NRC 1 Page 27
Scenario NRC 1 Event 8&9 No: No.
Event 1B SGTR, Loss of Offsite Power
==
Description:==
Time Position Applicants Actions or Behavior ATC
- Check RCS temperatures:
- RCPs - NONE running.
- Tcold at or trending to 557°F.
o Throttle AF to control cooldown.
- Check if SG secondary boundaries are intact:
- Verify NO SG depressurizing in an uncontrolled manner or completely depressurized.
- Check if SG tubes are intact:
- 1PR27J and 1B MS line indicate ABNORMAL rads.
CREW Identify entry conditions for 1BwEP-3 STEAM GENERATOR TUBE RUPTURE.
US
- Notify SM of plant status and procedure entry.
- Request SM evaluation of Emergency Plan conditions.
- Request STA evaluation of status trees.
US
- Enter/implement 1BwEP-3 STEAM GENERATOR TUBE RUPTURE, and direct operator actions of 1BwEP-3 to establish the following conditions:
- Check status of RCPs:
- RCPs - none running.
- Identify ruptured SG 1B.
- 1B Main steam line rad monitor ABNORMAL for plant conditions.
- 1B SG level rising uncontrollably.
- Isolate ruptured SG.
- Verify 1MS018B CLOSED.
- Verify 1SD002E & F CLOSED.
Identify the 1B SG as the ruptured SG and isolate prior to a transition to 1BwCA-3.1 is required. (Westinghouse - CT-18) (K/A number - EPE038EA1.32 importance 4.6/4.7)
[CT-18]
- Check ruptured SG level - Narrow Range > 10%.
[CT-18]
- CLOSE 1AF013B&F - may have already been closed in 1BwEP-0.
- Set 1AF005B and 1AF005F pot demand = 0% - may have already been performed in 1BwEP-0.
Comments:
151 NRC 1 Page 28
Scenario NRC 1 Event 8&9 No: No.
Event 1B SGTR, Loss of Offsite Power
==
Description:==
Time Position Applicants Actions or Behavior BOP
- Check ruptured SG pressure > 320 psig.
US
- Specify RCS temperature to which the RCS must be cooled down to allow depressurization of the RCS to ruptured SG pressure.
- Dump steam at maximum rate via:
- Block MS Isolation after P-11 reached.
US
- Dispatch EO with keys to 1SI101A/B.
- Check intact SG levels.
- Control Aux feed flow to maintain intact SG levels between 30% and 50%.
- Check PZR PORVs and ISOL Valves:
- PORV isolation valves - Both ENERGIZED.
- PORVs CLOSED.
- PORV isolation valves OPEN.
- Reset SI
- Depress BOTH SI Reset Pushbuttons at 1PM06J.
- Verify SI ACTUATED PERMISSIVE light NOT lit at 1PM05J (no power).
- Verify AUTO SI BLOCKED PERMISSIVE light lit at 1PM05J (no power).
- Reset Phase A.
- Depress BOTH Phase A Reset Pushbuttons at 1PM06J.
- Restore IA to Cnmt.
- Check a station air compressor is running at 0PM01J.
- OPEN 1IA065 and 1IA066 at 1PM11J.
- Check if RH pumps should be stopped.
- Check RCS pressure > 325 psig.
- Stop BOTH RH pumps and place in standby.
- Check if RCS cooldown should be stopped:
- Check CETCs < required temperature.
- Maintain CETCs < required temperature.
- Check ruptured SG pressure stable or rising.
- Check RCS subcooling acceptable.
Comments:
151 NRC 1 Page 29
Scenario NRC 1 Event 8&9 No: No.
Event 1B SGTR, Loss of Offsite Power
==
Description:==
Time Position Applicants Actions or Behavior ATC
- Depressurize RCS to refill PZR (normal PZR spray NOT available).
Depressurize RCS to restore RCS inventory prior to 1B SG PORV or safety valve water release. (Westinghouse - CT-20) (K/A number - EPE038EA1.04 importance 4.3/4.1)
[CT-20]
- OPEN 1 PZR PORV at 1PM05J until any of the following are met:
o RCS press < ruptured SG press and PZR level > 14%.
o PZR level > 68%.
o RCS subcooling is unacceptable.
[CT-20]
- CLOSE 1 PZR PORV at 1PM05J.
- Check RCS pressure rising.
- Check if ECCS flow should be terminated.
- Check subcooling acceptable.
- Check RCS pressure stable or rising.
- Check PZR level >14%.
- Stop ECCS pumps.
- Stop 1 CV pump (place control switch to PULL OUT).
- Terminate high-head ECCS & establish charging flow.
- Depress BOTH CV pump recirc valve reset pushbuttons at 1PM05J.
- Verify CV pump recirc valves OPEN at 1PM05J:
- 1CV8110, 1CV8111, 1CV8114 & 1CV8116.
- CLOSE 1SI8801A & B at 1PM05J.
- Place 1CV182 controller demand at 0%.
- OPEN 1CV8105 & 1CV8106 at 1PM05J.
- Adjust 1CV121 and 1CV182 to maintain desired charging and seal injection flow.
EXAMINERS NOTE: (1) All critical tasks are complete at this point; the scenario may be terminated at Lead Examiners discretion.
(2) The following steps address the second RCS depressurization.
Comments:
151 NRC 1 Page 30
Scenario NRC 1 Event 8&9 No: No.
Event 1B SGTR, Loss of Offsite Power
==
Description:==
Time Position Applicants Actions or Behavior ATC
- Control charging to maintain PZR Level stable.
- Verify ECCS flow not required:
- Subcooling acceptable.
- PZR level > 14%.
- Check RMCS:
- Makeup set for automatic control (no power).
- Check if letdown can be established:
- PZR level > 27%.
- Adjust charging and letdown to maintain subcooling and avoid SG overfill.
ATC Align Cent Chg pump suction to VCT:
- Check VCT level > 37%.
- Check VCT pressure 15-65 psig.
- Open 1CV112B and 1CV112C.
- Close 1CV112D and 1CV112E.
- Check 1CV8804A - closed.
o 1SI8807A and B - closed; or o 1SI8924 - closed
- Check if SI Accumulators should be isolated:
- RCS pressure < 800 psig - NO - continue with step 29.
o PZR level < 27% and 1B SG level rising: raise charging flow and depressurize RCS using a PZR PORV.
o PZR level 27-50% and 1B SG level rising: depressurize RCS using a PZR PORV.
o PZR level 50-68% and 1B SG level rising: depressurize RCS using a PZR PORV and reduce charging flow.
o PZR level >68% and 1B SG level rising: reduce charging flow.
EXAMINERS NOTE: Terminate the scenario at Lead Examiners discretion.
(Final)
Comments:
151 NRC 1 Page 31
Simulation Facility Braidwood Scenario Operating Test No.: 15-1 NRC No.:
NRC 2 Examiners: ______________________ Applicant: ____________________ SRO
______________________ ____________________ RO
______________________ ____________________ BOP Initial Conditions: IC-31 Turnover: Unit 1 is operating at 90% power, steady state, equilibrium xenon, BOL. Online risk is green.
Following completion of turnover, coordinate with Unit 2 and lower total station reactive load by a total of 2 KV in accordance with BwOP MP-23. The 1B HD pump was taken out of service 3 days ago and will NOT be returned to service for an additional 5 days.
Event Malf. No. Event Event No. Type* Description Preload IMF MS01A 100 1A MSIV failed open IMF MS01B 100 1B MSIV failed open IMF MS01C 100 1C MSIV failed open IMF MS01D 100 1D MSIV failed open IMF CS01A 1A CS pump fails to start IRF RP63 OUT K643 1B CS slave relay fails to actuate 1 None N-BOP, US Lower reactive load 1 KV.
2 IMF RX10A 0 15 I-ATC, US Turbine impulse pressure channel, 1PT-505, TS-US fails low 3 IMF CV10 0 30 I-ATC, US 1CV121 controller failure low 4 IMF RX06K 0 15 I-BOP, US 1C SG NR level transmitter, 1LT-539, fails low TS-US 5 IMF FW35A C-BOP, US 1A Heater Drain Pump trip 6 None R-ATC, US Turbine runback (only 1 HD pump running) 7 IMF MS07C 4 M-ALL Uncontrolled depressurization of all SGs 8 Preload C-ALL Failure of both CS trains to start automatically
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient
SCENARIO OVERVIEW Unit 1 is operating at 90% power, steady state, equilibrium xenon, BOL. Online risk is green. Following completion of turnover, coordinate with Unit 2 and lower total station reactive load by a total of 2 KV in accordance with BwOP MP-23. The 1B HD pump was taken out of service 3 days ago and will NOT be returned to service for an additional 5 days.
After completing shift turnover and relief, the BOP will lower Unit 1 reactive load 1 KV in accordance with BwOP MP-23.
After lowering reactive load, First Stage Turbine Impulse Pressure channel, 1PT-505, will fail low. After the crew diagnoses the failure of 1PT-505, the ATC will take manual control of rods after verifying turbine load stable. Initial ATC response is per hard card 1BwPR 1-10-RD, followed by entry into 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL, ATTACHMENT D. Tech Spec 3.3.1 Conditions A and P will be entered. The ATC will return rod control to automatic after verifying Tave and Tref are stable and within 1°F.
After the 1PT-505 failure is addressed, 1CV121, Charging Pump Flow Control Valve Controller 1FK-121, will fail to 0% demand. The 1CV121 valve will fully close and pressurizer level will drop. The crew will take actions to stabilize the plant by taking manual control of the 1FK-121 controller and restore charging flow.
After the 1FK-121 failure has been addressed, 1C SG NR level transmitter, 1LT-539, will fail low.
1FW530, Feedwater Regulating Valve, will open and 1C SG level will rise. The BOP will take manual control of 1C SG level per hard card 1BwPR 1-15-SG and stabilize 1C SG level. 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL, ATTACHMENT E, will be entered. The BOP will restore 1C SG level control to automatic after 1C SG level is restored to normal and an operable 1C SG NR level controlling channel is selected. Tech Specs 3.3.1 Conditions A and E and 3.3.2 Conditions A and D are applicable.
After the 1LT-539 failure has been addressed, 1A Heater Drain Pump will trip. 1BwOA SEC-1 SECONDARY PUMP TRIP, ATTACHMENT C, will be entered. The BOP will initiate a turbine load reduction to 780 MW at 20 MW/minute. The ATC will borate the RCS as necessary during the load reduction.
As the crew is reducing load to address the 1A HD pump trip, a large steam break will occur on the 1C MS line. When containment pressure reaches 20 psig, Phase B actuates but the CS pumps do not start.
The crew should manually realign train B CS valves which will start the 1B CS pump. Operators should transition to 1BwEP-2 FAULTED STEAM GENERATOR ISOLATION and recognize that the MSIVs have failed to close and that an uncontrolled depressurization of all SGs is in progress. The crew will transition to 1BwCA-2.1 UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS where they will throttle AF flow to the SGs. Entry into 1BwFR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK will be required when the crew throttles AF flow to 45 gpm per SG; however, a note in 1BwFR-H.1 directs that the procedure should NOT be performed. The crew will continue in 1BwCA-2.1.
Completion criteria is stopping the RH pumps in 1BwCA-2.1.
Critical Tasks
- 1. Manually actuate one train of containment spray prior to transition out of 1BwEP-0.
(Westinghouse - CT-3) (K/A number - 013000A4.01 importance - 4.5/4.8)
(Westinghouse - CT-33) (K/A number - EPEE12EA1.3 importance - 3.4/3.9) 151 NRC 2 Page 2
SIMULATOR SETUP GUIDE
- Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.
- Establish the conditions of IC-31, 90% power, steady state, equilibrium xenon, BOL.
- Ensure main generator VARS approx. 230 MVARs out.
- Complete items on Simulator Ready for Training Checklist.
- Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario.
- Place simulator in RUN and allow simulator to run during board walk down and turnover.
- Run caep 151 NRC 2 SETUP from disk and verify the following actuate:
- IMF MS01A 100
- IMF MS01B 100
- IMF MS01C 100
- IMF MS01D 100
- IMF CS01A
- IRF RP63 OUT
- Verify SER and RM-11 printers are clear of data.
- Place the 1B HD pump C/S in PULL OUT and place the 1B HD pump OOS.
- Provide students with turnover sheets, and a copy of BwOP MP-23.
151 NRC 2 Page 3
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Lower total station reactive load 2 KV.
Acknowledge as Shift Manager the start and completion of procedure.
Acknowledge as Unit 2, the need to lower Unit 2 reactive load by 1 KV (50 MVARs).
If asked, eGPM website is down.
If asked, lowering reactive load has been logged per BwOP MP-23.
If contacted, acknowledge as a generation dispatcher (Kerry Koch) completion of reactive load adjustment.
Event 2: Turbine Impulse Pressure channel 1PT-505 failed low.
Insert IMF RX10A 0 15 to fail 1PT-505 low over 15 seconds.
As SM, acknowledge the failure, 1BwOA INST-2 entry, request for E Plan evaluation, LCO 3.3.1 Conditions A
& P entry, and requests for on-line risk assessment, maintenance support, and IR initiation.
As SM, if requested support for tripping bistable in AEER, report that AEER bistable is not to be tripped until work analyst and NSO support can be obtained (in approx. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) and that the abnormal operating procedure should be continued.
As an extra NSO, if asked, report/perform the following concerning AMS:
- Initially: Operating Bypass switch (SW12) is in OFF.
- Operating Bypass switch (SW12) to TIP 1: perform the following:
- IMF PN0470 ON to turn on annunciator 1-18-E11.
- Operating Bypass Test Input (SW11) to TEST-TRIP: perform the following:
Event 3: 1FK121 Controller failure.
Insert IMF CV10 0 30 to fail 1CV121 closed over 30 seconds.
If dispatched as EO to investigate, wait two minutes and report no visible damage to 1CV121 valve. 1CV121 appears to be failed closed and responding correctly in manual (if asked for feedback to manual operations).
Acknowledge as Shift Manager the failure, request for maintenance support, and IR request.
151 NRC 2 Page 4
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 4: 1C SG NR level transmitter 1LT-539 fails low.
Insert IMF RX06K 0 15 to fail 1LT-539 low over a 15 second period.
Acknowledge as Shift Manager the failure, 1BwOA INST-2 entry, LCOAR entry, on-line risk assessment, EAL evaluation, request for maintenance support, and IR request.
Acknowledge as Shift Manager on line risk assessment, request for IR, evaluation for reactivity screening, QNE and personnel notifications, and evaluation of return to full power operation.
If lead examiner desires the bistable bypassed, participate in brief and perform the following:
To bypass the required bistables, participate in brief and perform the following (SDG RX19):
- As extra NSO contact Unit 1 (X2209).
- Insert the following:
- MRF RP20 OPEN (open protection cabinet #1 door).
- IRF RX063A BYPASS (Bypass LB 539A).
- IRF RX063B BYPASS (Bypass LB 539B).
- MRF RP20 CLOSE (close protection cabinet #1 door).
Event 5: 1A Heater Drain Pump trip.
Insert IMF FW35A As SM, acknowledge the failure, 1BwOA SEC-1 entry, request for E Plan evaluation, and requests for on line risk assessment, maintenance support, and IR initiation.
If dispatched as EO, wait 2 minutes, then report 1A Heater Drain pump has a ground overcurrent flag at breaker cubicle. If asked, the 1A HD pump has no issues locally.
If dispatched to the 1B HD pump breaker, wait 2 minutes, then report that the breaker appears to be damaged. The breaker is not fully in the cubicle and the frame appears bent. If asked, the 1B HD pump has no issues locally.
Event 6: Turbine runback (only 1 HD pump running).
As SM acknowledge the turbine runback.
Acknowledge as Generation Dispatch, the initiation of ramp.
151 NRC 2 Page 5
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 7/8: Uncontrolled depressurization of ALL SGs; Auto SI and CS failures.
Insert IMF MS07C 4 to initiate a 4 Mlb/hr steam break on the 1C SG.
Acknowledge as SM procedure changes, E Plan evaluations, and STA request.
After STA requested, as STA report CSF status: Red Path on heat sink when AF throttled to 45 gpm per SG, orange on integrity if RCS cold leg temperature < 240°F.
If dispatched as EO to investigate 1A CS pump, wait 3 minutes, then report ground overcurrent flag at breaker cubicle.
151 NRC 2 Page 6
Scenario NRC 2 Event 1 No: No.
Event Lower reactive load 1 KV on Unit 1 (U-2 will also lower 1 KV)
==
Description:==
Time Position Applicants Actions or Behavior CUE
- From turnover, lower total station reactive load 2 KV in accordance with BwOP MP-23 ADJUSTING REACTIVE LOAD.
US Direct BOP to perform BwOP MP-23.
EXAMINERS NOTE: (1) The limitation and action associated with BwOP MP-23 of logging the reactive load change has been logged.
(2) Adjusting the reactive load 1 KV correlates to 50 MVARS on 1VI-MP006.
- Refer to BwOP MP-23.
- Verify MVAR change will not exceed Generator Capability Curve in 1BwGP 100-3A6.
- Monitor PPC point Q2801 (preferred), 1VI-MP006, main generator output VARS, and switchyard bus voltage during the MVARs adjustment.
- Perform the following at 1PM01J:
- Contact Unit 2 and coordinate lowering total station reactive load by 2 KV.
- Place volt adjust C/S to lower (may be done intermittently).
- Release volt adjust C/S when Q2801 has dropped 50 MVARS (1 KV).
o Inform US BwOP MP-23 is complete.
US
- Acknowledge report.
o Notify SM that BwOP MP-23 is complete.
o Notify Generation Dispatch that BwOP MP-23 is complete.
ATC o Peer check actions of BOP.
o Monitor remainder of MCBs.
EXAMINERS NOTE: After BwOP MP-23 is complete and with Lead Examiners concurrence, enter next event.
Comments:
151 NRC 2 Page 7
Scenario NRC 2 Event 2 No: No.
Event Turbine Impulse Pressure Channel, 1PT-505, failed low
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator TAVE CONT DEV HIGH (1-14-D1)
- 1PI-505, First Stage Pressure, lowering.
- Control rod inward motion.
- 1TR-0412, Auct Tave/Tref recorder, Tref indication lowering.
- 1SI-412, Rod Speed, indicates 72 step per minute.
- Recognize 1PT-505 has failed low.
- Report failure to US.
- Review hard card 1BwPR 1-10-RD and take the following actions:
- Check turbine load stable.
- Place rod control in manual.
- Check rods NOT moving.
o Refer to BwARs as time permits.
- Verifies turbine load stable.
CREW
- Identify entry conditions for 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL.
US
- Notify SM of plant status and procedure entry.
- Request SM to evaluate Emergency Plan conditions.
- Implement 1BwOA INST-2 "OPERATION WITH A FAILED INSTRUMENT CHANNEL,"
ATTACHMENT D "TURBINE IMPULSE PRESSURE CHANNEL FAILURE" and direct operator actions of 1BwOA INST-2 to establish the following conditions:
- Direct ATC to place rod control in manual (previously performed).
o If PZR pressure drops below 2209 psig, enter Tech Spec 3.4.1 Condition A until pressure is > 2209 psig.
- Restore steam dumps:
- Check C-7 NOT lit.
- Place 1PK-507 in manual.
- Lower 1PK-507 demand to 0%.
- Place steam dump mode select switch to STM PRESS mode.
- Place 1PK-507 in auto.
- Check Reactor Power <100%.
- Place Turbine Impulse Pressure Defeat Switch, 1PS505Z, to DEFEAT P-505.
Comments:
151 NRC 2 Page 8
Scenario NRC 2 Event 2 No: No.
Event Turbine Impulse Pressure Channel, 1PT-505, failed low
==
Description:==
Time Position Applicants Actions or Behavior ATC
- Check if rod control can be placed in auto:
- C5 NOT lit.
- Tave/Tref stable and within 1°F (check T0494 or 1TR-0412).
o If control rods need to be adjusted to restore Tave - Tref within 1°F, perform the following:
o Obtain SM concurrence for reactivity change.
o Adjust Tave - Tref within 1°F using control rods, or o Adjust Tave - Tref within 1°F by dilution/load drop.
- Place rod control in auto.
- Check P13 interlock:
- Turbine power > 10% - P13 NOT lit.
o Trip bistables (bistables will NOT be tripped at this time).
- Check status of AMS:
- Operating Bypass switch (SW12) at 1PA54J - OFF.
- Locally trip AMS bistable at 1PA54J - C-20.
US
- Determine Tech Spec 3.3.1 Conditions A and P are applicable.
- Contact SM to perform risk assessment, initiate IR, perform reactivity screening, notify QNE and contact personnel to investigate/correct instrument failure.
EXAMINERS NOTE: After the above actions by the US and with Lead Examiners concurrence, insert next event.
Comments:
151 NRC 2 Page 9
Scenario NRC 2 Event 3 No: No.
Event 1CV121 controller fails low in auto
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator CHG LINE FLOW HIGH LOW (1-9-D3)
- Annunciator REGEN HX LTDWN TEMP HIGH (1-9-A1)
- Annunciator RCP SEAL WTR INJ FLOW LOW (1-7-B2)
- 1FK-121 controller output failed low.
- Charging flow, 1FI-121A, lowering.
- PZR level, 1LI-459A/460A/461, lowering.
- Perform the following at 1PM05J:
- Determine loss of charging flow.
- Identify 1FK-121 is failing low.
- Report failure to US.
- Perform the following at 1PM05J:
- Place 1FK-121, 1CV121 Controller, in manual.
- Raise demand on 1FK-121.
- Monitor charging flow and pressurizer level and return level to normal.
- Maintain charging flow by operating 1FK-121 in manual.
ATC o Reference BwARs as time permits.
o If required, isolate letdown per BwAR or use hard card 1BwPR 1-9-LD:
o Close 1CV8149A-C.
o Close 1CV459/460.
o Adjust 1CV121 and 1CV182, as required.
o Close 1CV8105/1CV8106.
- Recognize 1FK-121 output failed low.
o Dispatch operator to investigate cause of failure.
EXAMINERS NOTE: THE CREW MAY ELECT TO ENTER 1BwOA PRI-15 LOSS OF NORMAL CHARGING. SEE NEXT PAGE FOR ACTIONS OF 1BwOA PRI-15.
US o Direct actions of 1BwOA PRI-15 (see note above).
o Inform SM of FK-121 failure.
US
- Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.
US o IF PZR pressure drops below 2209 psig, enter Tech Spec 3.4.1 Condition A.
Comments:
151 NRC 2 Page 10
Scenario NRC 2 Event 3 No: No.
Event 1CV121 controller fails low in auto
==
Description:==
Time Position Applicants Actions or Behavior ATC 1BwOA PRI-15 ACTIONS (APPLICABLE IF CREW ENTERS THE PROCEDURE):
o Status of Cent Chg Pumps (one running).
o Check Cent Chg pump parameters (none fluctuating).
o If 1PI-120A less than RCS pressure:
o Place 1CV121 in manual (at this point, the ATC is likely to determine the controller was failed in automatic).
o Place affected Cent Chg pump in Pull Out.
o Start the standby Cent Chg pump.
o Place 1CV121 in auto if desired (crew should keep the controller in manual).
o Check CV System Alignment:
o Either 1CV8146 or 1CV8147 Open (one open).
o 1CV8324A or 1CV8324B Open (one open).
o BOTH 1CV8105 and 1CV8106 Open (if previously closed, crew re-opens valves).
o Check charging flow established (established).
BOP o Check normal letdown isolated (if previously isolated, crew implements 1BwOA ESP-2 to re-establish normal letdown).
o Notify SM to perform risk evaluation, initiate IR and make external notifications.
o Evaluate Tech Specs/TRM (none applicable).
o Return to procedure and step in effect.
BOP 1BwOA ESP-2 ACTIONS (APPLICABLE IF CREW ISOLATED LETDOWN) in 1BwOA PRI-15:
o Restore normal letdown using 1BwOA ESP-2 REESTABLISHING LETDOWN DURING ABNORMAL CONDITIONS as directed by performing the following at 1PM05J:
o Close letdown orifice isolation valves (1CV8149A-C).
o Close letdown line isolation valves (1CV459 and 1CV460).
o Verify either 1CV8401A or B open.
o Open 1CV8324A and 1CV8389A.
o Letdown CNMT isolation valves 1CV8152 and 1CV8160 open.
o BTRS Mode Selector switch OFF light LIT.
o Place 1CV131 controller in manual at 40% demand.
o Place 1CC130 controller in manual at 60% demand.
o 1CV8105/1CV8106 open.
o Adjust 1CV121 and 1CV182 to establish at least 100 gpm charging with seal injection 8-13 gpm per RCP.
o Open 1CV459 and 1CV460.
o Re-establish 120 gpm letdown flow by opening appropriate orifice isolation valves (1CV8149A and either 1CV8149B or C).
o Adjust 1CV131 and 1CC130 to restore letdown to 360 psig and 90-115oF.
o Place controllers in auto when desired (1CV131 and 1CC130).
o Verify 1PR06J restored (RM-11).
o Return to procedure and step in effect.
Comments:
151 NRC 2 Page 11
Scenario NRC 2 Event 3 No: No.
Event 1CV121 controller fails low in auto
==
Description:==
Time Position Applicants Actions or Behavior BOP 1BwOP CV-17 ACTIONS (APPLICABLE IF CREW ISOLATED LETDOWN):
o Perform the following at 1PM05J to establish normal letdown flow through the 1A letdown heat exchanger in accordance with BwOP CV-17 ESTABLISHING AND SECURING NORMAL AND RH LETDOWN FLOW (N/A if excess letdown established):
- Verify/close 1CV8149A, B, & C, letdown orifice isolation valves.
o Contact operators to locally verity CC locally aligned to 1A letdown HX.
- Place 1PK-131, letdown line pressure controller, in manual and raise demand to 40%.
- Open 1CV8152 & 1CV8160, letdown line CNMT isolation valves.
- Open 1CV459 & 1CV460, letdown line isolation valves.
- Open 1CV8324A, charging to regen HX 1A isolation valve.
- Open 1CV8389A, letdown to regen HX 1A isolation valve.
- Verify OFF light is lit above BTRS mode selector C/S (signifies that 1CV381B is OPEN & 1CV381A is CLOSED.
- Verify/open 1CV8401A, letdown HX 1A inlet valve.
- Verify/closed 1CV8145, PZR aux spray valve.
- Verify/open 1CV8147, charging to loop 1A isolation valve.
- Open 1CV8105 & 1CV8106, charging line CNMT isolation valves.
- Control 1FK-121, CV pumps flow control valve, in manual to raise letdown flow to 100 gpm while concurrently adjusting 1CV182, charging header backpressure control valve, to control RCP seal injection 8-13 gpm per RCP.
- Open 1CV8149A/B/C, letdown orifice isolation valves, as necessary to establish desired letdown flow while concurrently and controlling 1PK-131, letdown line pressure controller, in manual to maintain letdown pressure 360-380 psig.
- Control 1CC130A, letdown HX outlet temperature controller, in manual to maintain letdown temperature 90-115°F.
- Verify 1PR06J in service at the RM-11 console.
EXAMINERS NOTE: After the crew restores charging flow and with Lead Examiners concurrence, insert next event.
Comments:
151 NRC 2 Page 12
Scenario NRC 2 Event 4 No: No.
Event 1C SG NR level transmitter, 1LT-539, fails low
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator S/G 1C LEVEL DEVIATION HIGH LOW (1-15-C9)
- Annunciator S/G 1C LVL LO-2 RX TRIP ALERT (1-15-C5)
- SG 1C feed flow and NR level rising.
- Determine SG 1C feed flow and/or NR level rising at 1PM04J.
- Review hard card 1BwPR 1-15-SG and performs the following actions:
- Place 1C FRV controller in manual.
- Restore 1C SG level to pre-failed value.
- Determine failed input channel.
o Refer to BwARs as time permits.
CREW
- Identify entry conditions for 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL.
US
- Notify Shift Manager of SG level channel failure.
- Implement 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL, ATTACHMENT E NARROW RANGE SG LEVEL CHANNEL FAILURE, and direct operator actions of 1BwOA INST-2 to establish the following conditions:
- Stabilize 1C SG level at 1PM04J (actions performed previously).
o Place 1FK-530, FW Reg Valve 1FW530 controller, in manual.
o Lower demand on 1FK-530 sufficiently to lower FW flow to restore 1C SG level.
o Operate 1FK-530 in manual to stabilize 1C SG level in the normal operating band.
o Select an operable channel (L-558).
- Establish automatic level control by placing 1FK-530 in auto when SG level restored to program level.
- Perform the following:
- Check Rx power < 100% - Monitor reactor power at 1PM05J/PPC.
- Assist US by making notifications.
o Refer to BwARs as time permits.
EXAMINERS NOTE: The following steps will be performed if the Lead Examiner desires to observe bypassing bistables.
Comments:
151 NRC 2 Page 13
Scenario NRC 2 Event 4 No: No.
Event 1C SG NR level transmitter, 1LT-539, fails low
==
Description:==
Time Position Applicants Actions or Behavior US o Perform pre-job brief per HU-AA-1211 for bistable bypassing.
o Complete 1BwOL 3.3.1/3.3.2, Attachment A, INSTRUMENT CONDITION TRACKING LOG.
BOP o Locally bypass bistables for 1C SG level channel 1LT-539 by placing in BYPASS/
BOP verifies correct bistable operation:
o P-14/LO-2 Rx Trip/AF Pump Start.
US
- Determine AMS channel NOT affected.
- Determine Tech Spec 3.3.1 Conditions A and E are applicable.
- Determine Tech Spec 3.3.2 Conditions A and D are applicable.
- Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure, and make other notifications.
EXAMINERS NOTE: After the above actions by the US and with Lead Examiners concurrence, insert next event.
Comments:
151 NRC 2 Page 14
Scenario NRC 2 Event 5&6 No: No.
Event 1A Heater Drain Pump Trip
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator HD PUMP TRIP (1-17-D2)
- HD Tank level rising.
- HD pump discharge valves opening.
- Recognize 1A HD pump tripped.
o Refer to BwAR 1-17-D2 as time permits.
- Report failure to US.
- Recognize only one HD pump running.
CREW
- Identify entry conditions for 1BwOA SEC-1 SECONDARY PUMP TRIP.
US
- Acknowledge 1A HD pump trip.
- Implement 1BwOA SEC-1 SECONDARY PUMP TRIP, ATTACHMENT C "HD PUMP TRIP" and direct operator actions of 1BwOA SEC-1 to establish the following conditions:
- Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct failure.
- Notify SM of the HD runback.
- Recognize standby HD pump NOT AVAILABLE.
- Check HD pump status.
- ONLY 1C HD pump running.
- Initiate turbine load reduction to 780 MW at 20 MW/min.
- Initiate HD runback on OWS graphic 5512.
- Verify turbine load lowering.
- Check HD Tank level:
- Level > 72% and rising.
- Maintain HD tank level:
o Verify 1HD046A &B opening in AUTO.
o Open 1CB113A-D.
o Manually open 1HD117, HD tank overflow valve.
- Check 1HD117, HD tank overflow valve, in auto and closed.
o Lower turbine load as necessary to close 1HD117 (load ramp in progress).
- Check 1C HD pump parameters:
- 1C HD pump amps < 168 amps.
- 1C HD pump flow < 2950 KLB/HR.
o Lower turbine load as necessary to restore 1C HD pump parameters.
- Deactivate turbine runback.
Comments:
151 NRC 2 Page 15
Scenario NRC 2 Event 5&6 No: No.
Event 1A Heater Drain Pump Trip
==
Description:==
Time Position Applicants Actions or Behavior ATC
- Check PDMS operable:
- Annunciator PDMS INOPERABLE not lit (1-10-E8).
- 1BwOS PDMS-1A not implemented.
- Annunciator PDMS LIMIT EXCEEDED not lit (1-10-D7).
- Control I near target.
- Operate control rods in manual to restore I near target.
- Monitor RCS parameters:
o If PZR pressure lowers < 2209 psig, notify US to enter Tech Spec 3.4.1, RCS DNB Limits, Condition A.
- Initiate RCS boration.
- Determine required boric acid volume.
o Determine from Op Aid (ramp starts from 90%).
Borate in Automatic (BwOP CV-6 hard card):
o Turn on PZR backup heaters to equalize boron concentration.
- Set 1FY-0110 BA Blender Predet Counter to desired value.
- Set 1FK-110 BA Flow Control to desired boration rate
- Place MAKE-UP MODE CONT SWITCH to STOP position.
- Place MODE SELECT SWITCH to BORATE position.
- Place MAKE-UP MODE CONT SWITCH to START.
- Verify the following occurs:
- 1CV110B opens.
- 1CV110A opens.
- BA pump starts.
- Proper BA flow on recorder 1FR-110.
- When desired boration is achieved, place MAKE-UP MODE CONT SWITCH to STOP.
- Verify the following occurs:
- 1CV110B closes.
- 1CV110A closes.
- BA pump stops.
- Record time and amount of BA addition.
- Perform BwOP CV-7 to return RMCS to AUTO following the final boration.
OR Comments:
151 NRC 2 Page 16
Scenario NRC 2 Event 5&6 No: No.
Event 1A Heater Drain Pump Trip
==
Description:==
Time Position Applicants Actions or Behavior Batch addition of Boric Acid (BwOP CV-6 hard card):
o Turn on PZR backup heaters to equalize boron concentration.
o Momentarily depress RESET pushbutton on BA Flow totalizer.
- Open 1CV110B.
- Open 1CV110A.
- Start the BA Transfer Pump.
o If desired, control VCL level by adjusting 1LK-112 setpoint to desired value.
- When desired amount of BA has been added, stop the BA Transfer Pump.
- Close 1CV110A.
- Close 1CV110B.
- Verify VCT level/pressure at desired value and adjust 1LK-112 setpoint to desired corresponding level setpoint.
- Place 1CV110A/1CV110B in AUTO.
- Record time and amount of BA addition.
- Perform BwOP CV-7 to return RMCS to AUTO following the final boration.
o May flush boric acid lines per BwOP CV-6 step. F.5.
- Verify running CB pump recirc valves in auto
- 1CB113A-D on running pumps.
- Dispatch operators to perform BwOP HD-2 for 1A HD pump.
- Shutdown 4th CD/CB pump (if started during procedure performance).
US
- Notify Chemistry to monitor secondary plant chemistry.
- Notify SM to perform risk assessment.
- Check reactor power change > 15% in one hour:
o Notify Chemistry to perform Tech Spec 3.4.16 sampling.
o Notify Rad Protection to perform RETS 12.4.1.A sampling.
o Determine Tech Spec 3.1.6 Condition A entry required if control rods below LO-2 rod insertion limit.
o Determine Tech Spec 3.4.1 Condition A entry if PZR pressure lowers < 2209 psig.
EXAMINERS NOTE: After the above actions are complete by the US and with Lead Examiners concurrence, insert next event.
Comments:
151 NRC 2 Page 17
Scenario NRC 2 Event 7, 8 No: No.
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs, failure of both
==
Description:==
CS trains to automatically actuate Time Position Applicants Actions or Behavior CUE
- Annunciator CNMT PRESS HIGH SI/RX TRIP (1-11-E1)
- All SG pressures dropping.
- RCS Tave dropping.
- Rx Trip breakers open.
US
- Notify SM of plant status and procedure entry.
- Request SM evaluation of Emergency Plan conditions.
ATC Perform immediate operator actions of 1BwEP-0 at 1PM05J:
- Verify reactor trip:
- Rod bottom lights - ALL LIT.
- Reactor trip & Bypass breakers - OPEN.
- Neutron flux - DROPPING.
BOP Perform immediate operator actions of 1BwEP-0 at 1PM02J:
- Verify turbine trip:
- All Turbine throttle valves - CLOSED.
- All Turbine governor valves - CLOSED.
BOP Perform immediate operator actions of 1BwEP-0 at 1PM01J:
- Verify power to 4KV busses:
- ESF Buses - BOTH ENERGIZED.
ATC Perform immediate operator actions of 1BwEP-0 at 1PM05J:
- Check SI status:
o SI First OUT annunciator - Annunciator CNMT PRESS HIGH SI/RX TRIP (1 E1) LIT.
o SI ACTUATED Permissive Light - LIT.
o SI Equipment - AUTOMATICALLY ACTUATED:
o Either SI pump - RUNNING.
o Either CV pump to cold leg isolation valve OPEN - 1SI8801A/B.
- Manually actuate SI from 1PM05J and 1PM06J.
US Direct BOP to perform Attachment B of 1BwEP-0.
EXAMINERS NOTE: US and ATC will continue in 1BwEP-0 while BOP is performing Attachment B.
Comments:
151 NRC 2 Page 18
Scenario NRC 2 Event 7, 8 No: No.
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs, failure of both
==
Description:==
CS trains to automatically actuate Time Position Applicants Actions or Behavior BOP 1BwEP-0 ATTACHMENT B:
Verify FW isolated at 1PM04J:
- FW pumps - TRIPPED.
- FW isolation monitor lights - LIT.
- FW pumps discharge valves - CLOSED (or going closed) 1FW002A-C.
- Verify DGs running at 1PM01J:
- DGs - BOTH RUNNING.
- 1SX169A/B OPEN.
- Dispatch operator to monitor DGs operation.
- Verify Generator Trip at 1PM01J:
- OCB 1-8 and 7-8 open.
- PMG output breaker open.
- Verify Control Room ventilation aligned for emergency operations at 0PM02J:
- VC Rad Monitors - LESS THAN HIGH ALARM SETPOINT.
- Operating VC train equipment - RUNNING.
- 0B Supply fan
- 0B Return fan
- 0B M/U fan
- 0B Chilled water pump
- 0B Chiller
- M/U fan outlet damper - 0VC08Y NOT FULLY CLOSED.
- 0B VC train M/U filter light - LIT.
- 0VC09Y - OPEN.
- 0VC313Y - CLOSED.
- Operating VC train Charcoal Absorber aligned for train B.
- 0VC44Y - CLOSED.
- 0VC05Y - OPEN.
- 0VC06Y - OPEN.
- Control Room pressure greater than +0.125 inches water on 0PDI-VC038.
- Verify Auxiliary Building ventilation aligned for emergency operations at 0PM02J:
- Two inaccessible filter plenums aligned.
- Plenum A:
- 0VA03CB - RUNNING.
- 0VA023Y - OPEN.
- 0VA436Y - CLOSED.
- Plenum C:
- 0VA03CF RUNNING.
- 0VA072Y - OPEN.
Comments:
151 NRC 2 Page 19
Scenario NRC 2 Event 7, 8 No: No.
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs, failure of both
==
Description:==
CS trains to automatically actuate Time Position Applicants Actions or Behavior
- 0VA438Y - CLOSED.
- Verify FHB ventilation aligned for emergency operation at 0PM02J:
- 0VA04CB - RUNNING.
- 0VA055Y - OPEN.
- 0VA062Y - OPEN.
- 0VA435Y - CLOSED.
- Trip 1C HD pump.
- Initiate periodic monitoring of Spent Fuel Cooling.
- Notify US Attachment B complete/manual actions taken.
- Verify ECCS pumps running at 1PM05J/1PM06J:
- BOTH CV pumps - RUNNING.
- BOTH RH pumps - RUNNING.
- BOTH SI pumps - RUNNING.
- Perform the following at 1PM06J:
- RCFCs running in accident mode.
- Group 2 RCFC accident mode status light lit.
- CNMT Phase A valves closed.
EXAMINERS NOTE: RCPs may be stopped by the crew any time after recognizing that Phase B isolation has occurred.
ATC Perform the following at 1PM06J:
- Verify Cnmt Vent isolation:
- Group 6 Cnmt Vent Isol monitor lights - LIT.
- Verify AF system:
- BOTH AF pumps - RUNNING.
- AF flow control valves - 1AF005A-D throttled OPEN.
- Verify CC pumps running:
- BOTH CC pumps - RUNNING.
- Verify SX pumps running:
- BOTH SX pumps - RUNNING.
- Check if Main Steamlines Should Be Isolated:
- Verify MS isolation:
- MSIVs are open.
Comments:
151 NRC 2 Page 20
Scenario NRC 2 Event 7, 8 No: No.
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs, failure of both
==
Description:==
CS trains to automatically actuate Time Position Applicants Actions or Behavior
- Manually actuate MS isolation.
- ALL MSIVs remain open.
CREW o Determine and announce containment is adverse when containment pressure rises above 5 psig.
- Check if CS is required
- CNMT pressure > 20 psig.
- Group 6 CS monitor lights - NOT ALL LIT.
- Manually actuate CS and Phase B Isolation.
- Group 6 CS monitor lights remain - NOT ALL LIT, GO TO Attachment C.
US
Comments:
151 NRC 2 Page 21
Scenario NRC 2 Event 7, 8 No: No.
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs, failure of both
==
Description:==
CS trains to automatically actuate Time Position Applicants Actions or Behavior 1BwEP-0, ATTACHMENT C MANUAL CS ACTUATION EXAMINERS NOTE: The examinees will also attempt to align the A train of CS, however only the B train will properly align and start the 1B CS pump as outlined below.
- Check CS valve alignment:
- Check 1CS001A/B - OPEN.
- Check 1CS007A/B - OPEN:
Manually actuate one train of containment spray prior to transition out of 1BwEP-0.
(Westinghouse - CT-3) (K/A number - 013000A4.01 importance - 4.5/4.8)
- 1CS007A - OPEN.
[CT-3]
- Manually open 1CS007B.
- Check 1CS019A/B - OPEN.
- 1CS007A open.
[CT-3]
- Place 1B CS pump test switch in test.
[CT-3]
- Manually open 1CS019B.
- Place 1B CS pump test switch in normal
- Check 1CS010A/B - OPEN.
- Check CS pumps - AT LEAST ONE RUNNING:
- 1B CS pump running.
US
- Return to 1BwEP-0 main body, step 14.c.
- Check if CS is required:
- Group 6 phase B monitor lights - ALL LIT.
- Verify/stop all RCPs (may have been performed previously).
- Verify total AF flow:
- AF flow > 500 gpm.
- Check S/G NR levels - NOT rising in an uncontrolled manner.
- Verify ECCS valve alignment:
- Group 2 Cold Leg Injection monitor lights required for injection - LIT.
Comments:
151 NRC 2 Page 22
Scenario NRC 2 Event 7, 8 No: No.
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs, failure of both
==
Description:==
CS trains to automatically actuate Time Position Applicants Actions or Behavior ATC
- Verify ECCS flow:
- RCS pressure < 1700 psig.
- SI pump discharge flows > 200 gpm.
- RCS pressure > 325 psig.
- Check PZR PORVs and spray valves:
- PORVs CLOSED.
- PORV isolation valves - BOTH ENERGIZED.
- Normal spray valves CLOSED.
- Check RCS temperatures:
- RCPs - NONE RUNNING.
- RCS Tcold temperatures are NOT stable at or trending to 557F.
- Stop dumping steam
- Throttle AF flow while maintaining > 500 gpm.
- MSIVs open - verify closed (will not close).
o Crew may throttle AF flow to 45 gpm per SG.
- Check status of RCPs:
- RCPs - NONE RUNNING.
CREW Check if SG secondary boundaries are intact:
- Check NO SG depressurizing uncontrollably or completely depressurized.
- ALL SG pressures dropping in an uncontrolled manner.
CREW Transition to 1BwEP-2 FAULTED STEAM GENERATOR ISOLATION.
Comments:
151 NRC 2 Page 23
Scenario NRC 2 Event 7 No: No.
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs
==
Description:==
Time Position Applicants Actions or Behavior 1BwEP-2 FAULTED STEAM GENERATOR ISOLATION US
- Notify SM of plant status and procedure entry.
- Request SM evaluation of Emergency Plan conditions.
- Request STA evaluation of status trees.
- Enter/implement 1BwEP-2 and direct operator actions of 1BwEP-2 to establish the following conditions:
- Check Main Steamline Isolation:
- ALL MSIVs remain open (manual MS line isolation previously attempted).
CREW
- Check if any SG secondary pressure boundary intact:
- No SG pressure stable or rising.
- ALL SGs depressurizing in an uncontrolled manner.
CREW Transition to 1BwCA-2.1 UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS.
Comments:
151 NRC 2 Page 24
Scenario NRC 2 Event 7 No: No.
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs
==
Description:==
Time Position Applicants Actions or Behavior 1BwCA-2.1 UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS US
- Notify SM of plant status and procedure entry.
- Request SM evaluation of Emergency Plan conditions.
- Enter/implement 1BwCA-2.1 and direct operator actions of 1BwCA-2.1 to establish the following conditions:
- Check secondary pressure boundary:
- MSIVs open - attempt to close (previously attempted).
- MSIV bypass valves - CLOSED.
- Check FW isolation monitor lights - LIT.
- Check 1SD002A-H - CLOSED.
- Check 1SD005A-D - CLOSED.
EXAMINERS NOTE: Throttling AF flow to 45 gpm per SG will result in a red path on the heat sink status tree and require a transition to 1BwFR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK. 1BwFR-H.1 will be entered and immediately exited due to operator action lowering AF flow to < 500 gpm.
- Control feed flow to minimize RCS cooldown.
- Check cooldown rate in RCS cold legs < 100 F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period - NO.
Manually control AF flowrate to 45 gpm for each SG before orange path in integrity occurs. (Westinghouse - CT-33) (K/A number - EPEE12EA1.3 importance - 3.4/3.9)
[CT-33]
- Check RCS hot leg temperatures - Stable or dropping.
- Check RCPs - NONE RUNNING.
- Check PZR PORVs and Isolation Valves:
- PORV Isolation Valves - BOTH energized.
- PORVs - BOTH closed.
- PORV Isolation Valves - BOTH open.
- Check Secondary Radiation:
- Reset Phase A.
- Open 1SD005A-D.
- Request Chemistry to periodically sample all SGs for activity.
- Check secondary radiation trends on RM-11 or PPC - ALL normal.
Comments:
151 NRC 2 Page 25
Scenario NRC 2 Event 7 No: No.
Event Steam leak inside containment/uncontrolled depressurization of ALL SGs
==
Description:==
Time Position Applicants Actions or Behavior BOP
- Check if RH Pumps Should be Stopped:
- RH pumps - BOTH running with suction on RWST.
- If RCS pressure > 325 psig and pressure is stable or rising, reset SI and stop RH pumps/place in standby.
EXAMINERS NOTE: Terminate the scenario at Lead Examiners discretion.
(Final)
Comments:
151 NRC 2 Page 26
Simulation Facility Braidwood Scenario Operating Test No.: 151 NRC No.:
NRC 3 Examiners: ______________________ Applicant: ____________________ SRO
______________________ ____________________ ATC
______________________ ____________________ BOP Initial Conditions: IC-21 Turnover: Unit 1 is operating at 100% power, steady state, equilibrium xenon, BOL. 1B CW pump is OOS for motor inspection. Automatic Rod Control is failed (rod speed programmer failure).
Rods are in MANUAL. IMD troubleshooting will commence in 3-4 hours. Following completion of turnover, the crew is to perform 1BwOS EH-M1 UNIT 1 PUMP OPERABILITY SURVEILLANCE, using the preferred method of depressing and holding the MCB pushbutton. An Equipment Operator has been briefed and is standing by at the Unit 1 EH skid.
Event Malf. No. Event Event No. Type Description Preload IMF RX17 0 Rod speed programmer failure IOR ZDI1CW01PB PTL 1B CW pump OOS IMF FW44 1A AF pump fails to start IMF FW43 1B AF pump fails to start IMF SI12B 1B SI pump fails to automatically start IRF RP30 OUT Phase A slave failure IRF RP56 OUT Phase A slave failure trgset 1 ZLO52BRKA(2) == 1 IMF FW19C 3.5 (1 0) 1C feedline break inside Cnmt when reactor trips IMF CV01B (1 0) 1B CV pump trips when reactor trips 1 None N-BOP, Perform 1BwOS EH-M1 US 2 IMF RX04E 0 120 I-BOP, Feed Flow channel, 1FT530, fails low US 3 IMF CV29A 100 C-ATC, 1A CV pump shaft shear US TS-US 4 IMF SW01A C-BOP, 1A SX Pump Trip US TS-US 5 IMF RX15 2195 I-ATC, Master Pressurizer Pressure Controller output US fails to 2195 psig (0% demand) 6 IMF FW36 500 scfm to 120 R-ATC, Condenser vacuum leak requiring load reduction scfm over 600 seconds US 7 IMF CV03 Boric acid transfer pump trip 8 IMF RP09A M-ALL Inadvertent FWI Feed line break inside containment 9 Preload C-ALL 1B CV pump trip when reactor trips 10 Preload M-ALL Loss of heat sink (1A/1B AF pumps tripped)
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient 151 NRC 3
SCENARIO OVERVIEW Unit 1 is operating at 100% power, steady state, equilibrium xenon, BOL. 1B CW pump is OOS for motor inspection. Automatic Rod Control is failed (rod speed programmer failure). Rods are in MANUAL. IMD troubleshooting will commence in 3-4 hours. Following completion of turnover, the crew is to perform 1BwOS EH-M1 UNIT 1 PUMP OPERABILITY SURVEILLANCE, using the preferred method of depressing and holding the MCB pushbutton. An Equipment Operator has been briefed and is standing by at the Unit 1 EH skid.
After completing shift turnover and relief, the BOP will perform 1BwOS EH-M1 UNIT 1 PUMP OPERABILITY SURVEILLANCE.
After completing the surveillance, feed flow channel, 1FT-530, will fail low resulting in rising feed flow and opening of 1FW530, 1C S/G Feed Reg Valve, to match feed flow with steam flow. The BOP will diagnose the failure and take manual control of 1FW530 to restore 1C SG level. The US will enter 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL - ATTACHMENT G. The crew will take actions per hard card 1BwPR 1-15-SG & 1BwOA INST-2 and perform appropriate actions. The crew will swap to an operable feed flow channel.
After addressing the failed feed flow channel, the 1A CV pump shaft shear will occur. The crew will implement 1BwOA PRI-15 LOSS OF NORMAL CHARGING. The crew will start the 1B CV pump to restore normal charging. Technical Specifications 3.5.2 Condition A and TRM 3.1.d Condition A apply.
After the charging pump failure is addressed, the 1A Essential Service Water (SX) pump will trip due to an overcurrent condition. The crew will take actions per hard card 1BwPR 1-2-A1 to start the 1B SX pump. The crew MAY enter 1BwOA PRI-8, ESSENTIAL SERVICE WATER MALFUNCTION. Tech Specs 3.7.8 Condition A applies. The 1A SX pump will remain unavailable for the rest of the scenario.
After the 1A SX pump trip is addressed, the master pressurizer pressure controller output will fail to 2195 psig (0% demand) in automatic. The RO will identify the failure and take manual control to restore pressurizer pressure.
After the master pressurizer pressure controller failure has been addressed, an air leak will develop in the main condenser. The crew will enter 1BwOA SEC-3 LOSS OF CONDENSER VACUUM, dispatch operators to locate the leak and contact Engineering to evaluate the leakage. With the 1B CW pump OOS; the crew will be required to commence a ramp down of Unit 1 to stabilize the loss of vacuum.
During the ramp, the boric acid transfer pump will trip during the first boration. The common boric acid pump will not be available and the ATC will have to continue the ramp with rods only.
After a sufficient reactivity manipulation has occurred, an inadvertent FWI occurs. When the crew manually trips the reactor, a feed line break on the 1C SG inside containment will occur. The 1B CV pump trips when the reactor trips. The crew will enter 1BwEP-0 to stabilize the plant and SI will actuate. The 1B SI pump fails to auto start and must be manually started. The 1A and 1B AF pumps will not start resulting in a transition to 1BwFR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK at step 15 of 1BwEP-
- 0. Bleed and feed will be required due to NO CV pumps running.
Completion criteria is establishing bleed and feed during the loss of heat sink.
Critical Tasks
- 1. Close containment isolation valves such that at least one valve is closed on each Phase A penetration before the end of the scenario. (Westinghouse CT-11) (K/A number APE069AA1.01 importance 3.5/3.7)
- 2. Initiate RCS bleed and feed so that the RCS depressurizes sufficiently for SI pump injection to occur.
(Westinghouse CT-46) (K/A number EPEE05EA1.1 importance 4.1/4.0) 151 NRC 3 Page 2
SIMULATOR SETUP GUIDE
- Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.
- Establish the conditions of IC-21, 100% power, steady state, equilibrium xenon, BOL OR use the IC written below.
- Place ROD BANK SELECT switch in MANUAL.
- Place YELLOW on-line risk sign on 1PM05J.
- Update PARAGON to BOL with RODS in MANUAL.
- Complete items on Simulator Ready for Training Checklist.
- Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario.
- Place simulator in RUN (allow simulator to run during board walk down and turnover).
- Place 1B CW pump C/S in PTL, after 1CW001B is full closed, then run CAE.
- Hang OOS card on 1B CW pump.
- Run caep 151 NRC 3 SETUP from disk and verify the following actuate:
- IMF RX17 0
- IOR ZDI1CW01PB PTL
- IMF FW44
- IMF FW43
- IMF SI12B
- IRF RP30 OUT
- IRF RP56 OUT
- trgset 1 ZLO52BRKA(2) == 1
- IMF FW19C 3.5 (1 0)
- IMF CV01B (1 0)
- After main generator load stabilizes, write an IC to allow the scenario to be used again.
- Provide students with turnover sheets.
151 NRC 3 Page 3
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Perform 1BwOS EH-M1.
When requested, as Equipment Operator, report you are standing by at the Unit 1 EH skid. Report the following data as EH pumps are started and stopped:
- EH system temperature is 110°F.
- EH system pressure is 1970 psig with ONE EH pump running.
- EH system pressure is 1985 psig with TWO EH pumps running.
If requested, as Field Supervisor report you are providing direct supervision in the field for production risk.
Acknowledge as Shift Manager, the start and completion of procedure.
Event 2: Feed flow channel, 1FT-530, fails low.
Insert IMF RX04E 0 120 to fail 1FT-530 low over 120 seconds.
As SM, acknowledge the failure, requests for on-line risk assessment, maintenance support, and IR initiation.
Event 3: 1A CV pump shaft shear.
Insert IMF CV29A 100 for 1A CV pump shaft shear.
If dispatched as Equipment Operator to 1A CV pump and/or pump breaker, wait three minutes and report 1A CV pump appears shaft is sheared.
If dispatched as Equipment Operator to check for a good start on the 1B CV pump, report that the 1B CV pump had a good start.
Acknowledge as Shift Manager the failure, LCOAR entry, on-line risk assessment, EAL evaluation, request for maintenance support, and IR request.
151 NRC 3 Page 4
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 4: 1A SX pump trip.
Insert IMF SW01A for 1A SX pump trip.
If dispatched as EO to investigate 1A SX pump breaker, wait 2 minutes and report phase A overcurrent flag on 1A SX pump breaker cubicle (Bus 141, cubicle 2).
If dispatched as EO to investigate 1A SX pump, wait 3 minutes and report no damage visible at pump and pump is NOT rotating backwards. Report 1B SX pump is running with normal parameters if dispatched to check 1B SX pump.
If contacted as Unit 2 to swap Unit 2 SX pumps for chem. feed alignment, acknowledge request.
If contacted as Rad Waste Operator, report no abnormal Aux Building sump indications.
If contacted as EO to check the containment chiller report chiller tripped on high evaporator pressure from a loss of SX. Chiller checks out ok for a restart.
As SM, acknowledge the trip of 1A SX pump, Tech Spec 3.7.8 Condition A entry, and requests for on-line risk assessment, maintenance support, and IR initiation.
Event 5: Master Pressurizer Pressure Controller fails to 2195 psig (0% demand).
Insert IMF RX15 2195 to fail the master pressurizer pressure controller output low.
151 NRC 3 Page 5
Event 6: Lowering condenser vacuum requiring load drop.
Insert IMF FW36 500 SCFM lowering to 120 SCFM over 600 seconds.
As SM, acknowledge 1BwOA SEC-3 entry, request for E Plan evaluation, load ramp and requests for on-line risk assessment, maintenance support, and IR initiation.
If contacted as Engineering to evaluate lowering vacuum, inform the unit supervisor that an Engineer is evaluating the Unit 1 lowering condenser vacuum.
Acknowledge dispatch of EOs to investigate the lowering condenser vacuum. After approximately 10 minutes, report the sound of air leak coming from under the 1C LP turbine.
Monitor the crew for the first boration and insert Event 7 during the first boration.
If contacted as Reactor Engineering, acknowledge the ramp being performed with rods only. If asked for permission to ramp or for guidance to ramp with rods only. Inform Unit 1 you will develop a plan to recover to the desired rod alignment once the transient is over and boric acid is restored.
Once the ramp has commenced, monitor condenser pressure in SimView (YCP2205/06/07) to ensure a ramp is required, but vacuum doesnt degrade to the reactor trip set point. Adjust MF FW36 severity as required.
Event 7: Trip of the unit 1 boric acid pump.
Once the first boration has been started:
Insert IMF CV03 to trip the boric acid transfer pump.
As SM, acknowledge loss of Unit 1 boric acid pump and requests for on-line risk assessment, maintenance support, and IR initiation.
As the EO, report that the boric acid pump is hot to the touch and an acrid odor is in the air. There is no fire and the breaker is tripped free.
As the Field Supervisor or EO, acknowledge the need to swap to the Unit 0 boric acid pump on Unit 1 per BwOP AB-23 step F.1. After 3 minutes, call to report the power cord for the Unit 0 AB pump is damaged and not usable.
If contacted as Unit 2, acknowledge the request for use of the Unit 2 boric acid transfer pump and inform Unit 1 it will be 30 to 60 minutes before it will be available.
151 NRC 3 Page 6
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 8: Inadvertent Feed Water Isolation.
Insert IMF RP09A.
Event 9/10: Feed line break in containment / Loss of Heat Sink / CV pump trip.
Acknowledge as SM procedure transitions, E Plan evaluations, and STA request.
After STA requested, as STA report CSF status - Red path on heat sink (until feed flow established).
Yellow on heat sink once feed flow established, Yellow on inventory when vessel head voids due to bleed and feed.
If dispatched as EO, report 1B CV pump has phase C overcurrent flag.
If dispatched as EO, report 1A AF pump has a ground overcurrent flag and motor damage.
If dispatched as EO, report 1B AF pump has large lube oil leak and engine damage.
Acknowledge as U-2 NSO, the request to remove FW isolation fuses; then insert the following:
- MRF FW150 REMOVED
- MRF FW151 REMOVED
- MRF RP78 REMOVED
- MRF FW149 START 151 NRC 3 Page 7
Scenario NRC 3 Event 1 No: No.
Event Perform 1BwOS EH-M1
Description:
Time Position Applicants Actions or Behavior CUE
- From turnover, perform 1BwOS EH-M1 UNIT 1 PUMP OPERABILITY SURVEILLANCE.
US
- Direct BOP to perform 1BwOS EH-M1.
- Refer to 1BwOS EH-M1.
- Record initial data on Data Sheet D-2.
- Notify Equipment Operator at EH skid of pending 1B EH pump start.
- At 1PM02J, depress EH PP LO PRESS AUTO START TEST (20/MPT) pushbutton.
o Equipment Operator locally verifies 1B EH pump started.
- Perform the following at 1PM02J:
- Verify annunciator 1-18-B15, EH SYSTEM TROUBLE, remained clear.
- Place 1B EH pump C/S in AFTER CLOSE.
- Notify Equipment Operator at EH skid of pending 1A EH pump shutdown.
- At 1PM02J, place 1A EH pump C/S in AFTER TRIP.
- Equipment Operator locally verify EH pressure 1950 +/- 50 psig.
- Notify Equipment Operator at EH skid of pending 1A EH pump start.
- At 1PM02J, depress EH PP LO PRESS AUTO START TEST (20/MPT) pushbutton.
o Equipment Operator locally verifies 1A EH pump started.
- Perform the following at 1PM02J:
- Verify annunciator 1-18-B15, EH SYSTEM TROUBLE, remained clear.
- Place 1A EH pump C/S in AFTER TRIP.
- Equipment Operator locally verifies EH pressure 1950 +/- 50 psig.
- Record as left data on Data Sheet D-2.
- Inform US that 1BwOS EH-M1 complete.
US
- Acknowledge report of surveillance completion.
o Notify SM that 1BwOS EH-M1 is complete.
EXAMINERS NOTE: After 1BwOS EH-M1 is complete and with Lead Examiners concurrence, enter next event.
Comments:
151 NRC 3 Page 8
Scenario NRC 3 Event 2 No: No.
Event Feed flow channel, 1FT-530, fails low
Description:
Time Position Applicants Actions or Behavior CUE
- Annunciator S/G 1C FLOW MISMATCH FW FLOW LOW (1-15-C4)
- Annunciator S/G 1C LEVEL DEVIATION HIGH/LOW (1-15-C9)
- 1C SG NR levels rising.
- Identify/report failure of 1FT-530.
o Reference BwARs as time permits.
ATC o Reference BwARs as time permits.
CREW
- Identify entry conditions for 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL.
US
- Notify SM of plant status and procedure entry.
- Request SM evaluation of Emergency Plan conditions.
- Enter/implement 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL, ATTACHMENT G FEEDWATER FLOW CHANNEL FAILURE and direct operator actions of 1BwOA INST-2 to establish the following conditions:
- Stabilize 1C SG level (actions to stabilize per 1BwPR 1-15-SG initially, then 1BwOA INST-2).
- If SG level abnormal:
- Control 1C FRV (1FW530) in manual.
- Restore SG level to stable condition.
- Select operable feed flow channel (1BwPR 1-15-SG action).
- Establish/verify automatic SG level control.
- Check reactor power <100% (if > 100%, reduce turbine load):
- PPC 10 min. calorimetric.
- Computer point (U0923).
- NIs.
- Check HD system operation:
- 1HD046A & B position normal.
Comments:
151 NRC 3 Page 9
Scenario NRC 3 Event 2 No: No.
Event Feed flow channel, 1FT-530, fails low
Description:
Time Position Applicants Actions or Behavior US
- Notify SM/maintenance to investigate/correct the failed feed flow channel:
- Determines Tech Specs are NOT applicable.
- Contact SM to perform risk assessment, initiate IR, reactivity screening, notify QNE and contact maintenance to investigate/correct instrument failure.
- Contact SM to make appropriate personnel notifications.
EXAMINERS NOTE: After the feed flow channel failure actions are complete and with Lead Examiners concurrence, enter next event.
Comments:
151 NRC 3 Page 10
Scenario NRC 3 Event 3 No: No.
Event 1A CV pump shaft shear
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator CHG LINE FLOW HIGH/LOW (1-9-D3)
- Annunciator RCP SEAL WATER INJ FLOW LOW (1-7-B2)
- Annunciator REGEN HX LTDWN TEMP HIGH (1-9-A1)
- PZR level lowering.
- Low amps on the 1A CV pump.
- Identify 1A CV pump has low amps at 1PM05J.
- Report failure to US.
o May isolate letdown per BwAR 1-9-A1, hard card 1BwPR 1-9-LD or 1BwOA PRI-15 Operator Action Summary page by closing 1CV8149A/B/C and 1CV459/460.
CREW
- Reference BwARs as time permits.
o Identify entry conditions for 1BwOA PRI-15 LOSS OF NORMAL CHARGING.
- Dispatch operator to investigate cause of 1A CV pump low amps.
US Enter 1BwOA PRI-15 to start 1B CV pump.
- Notify Shift Manager of plant status and procedure entry.
- Request SM evaluation of Emergency Plan conditions.
- Implement 1BwOA PRI-15 and direct operator actions of 1BwOA PRI-15 to establish the following conditions:
o Enter Tech Spec 3.4.1 Condition A if PZR pressure < 2209 psig.
EXAMINERS NOTE: Crew may stop the 1A CV pump due to abnormal indications.
ATC Perform the following at 1PM05J:
- Check CV pump status:
o If one CV pump is running (CV pump may or may not be tripped before entering the 1BwOA PRI-15).
- Check CV pump parameters any fluctuating - NO.
- Place 1CV121 controller to manual.
- Place 1A CV pump C/S in PULL OUT.
- Start 1B CV pump.
- Place 1CV121 controller in auto (if desired).
OR ATC o If NEITHER CV pump is running.
- Place 1A CV pump C/S in PULL OUT.
- Isolate normal letdown:
Comments:
151 NRC 3 Page 11
Scenario NRC 3 Event 3 No: No.
Event 1A CV pump shaft shear
==
Description:==
Time Position Applicants Actions or Behavior
- CLOSE 1CV8149A, B & C, letdown orifice isolation valves.
- CLOSE 1CV459 & 1CV460, letdown isolation valves.
- Check VCT status:
- Check 1CV112B & 1CV112C, VCT suction valves, OPEN.
- Maintain VCT level greater than 20%.
o Operate RMCS in automatic or manual to maintain VCT level > 20%.
- Check annunciator 1-9-C2, VCT TEMP HIGH - NOT lit.
o Acknowledge RM-11 alarm caused by isolating flow to 1PR06J, Gross Failed Fuel Monitor.
ATC Perform the following at 1PM05J:
- Check for gas binding of previously running CV pump by verifying the following trends NOT fluctuating prior to pump trip (may use PPC trends):
- RCP #1 seal leak off flows.
- CV pump flow.
- CV pump discharge pressure.
- CV pump amps.
- Restore charging flow:
- Check 1CV8110 & 1CV8116, 1B CV pump miniflow isolation valves - OPEN.
- Check RCS pressure approximately 2235 psig.
- Start 1B CV pump.
- Check CV System Alignment:
- Verify 1CV8147, charging to RC 1A loop isolation valve - OPEN.
- Verify 1CV8324A, charging to regen HX 1A isolation valve - OPEN.
- Verify/open 1CV8105 and 1CV8106, charging line CNMT isolation valves.
- Check charging flow established (charging flow may be at minimum for RCP seal injection due to letdown isolation).
- Determine normal letdown is isolated (restore letdown, see next page).
o Monitor RMCS during automatic VCT makeup:
o Proper flow on PW/Total Flow (1FT-0111) and Boric Acid Flow (1FT-0110) on recorder 1FR-0110.
CREW
- Identify entry conditions for 1BwOA ESP-2 REESTABLISHING CV LETDOWN DURING ABNORMAL CONDITIONS.
US
- Notify Shift Manager of plant status and procedure entry.
- Implement 1BwOA ESP-2 REESTABLISHING CV LETDOWN DURING ABNORMAL CONDITIONS, and direct operator actions of 1BwOA ESP-2 to establish the following conditions:
Comments:
151 NRC 3 Page 12
Scenario NRC 3 Event 3 No: No.
Event 1A CV pump shaft shear
==
Description:==
Time Position Applicants Actions or Behavior BOP Restore normal letdown using 1BwOA ESP-2 as directed by performing the following at 1PM05J:
- Check letdown isolated:
- Verify 1CV8149A, B, & C, letdown orifice isolation valves - CLOSED.
- Verify 1CV459 & 1CV460, letdown line isolation valves - CLOSED.
- Check letdown flow path:
- Verify 1CV8401A, letdown HX 1A isolation valve - OPEN.
- Verify 1CV8324A, charging to regen HX 1A isolation valve - OPEN.
- Verify 1CV8389A, letdown to regen HX 1A isolation valve - OPEN.
- Verify 1CV8152 & 1CV8160, letdown line CNMT isolation valves - OPEN.
- Verify BTRS mode select switch OFF light - LIT.
- Align letdown controllers:
- Place 1PK-131, letdown line pressure controller, in MANUAL and raise demand to 40%.
- Place 1CC130A, letdown HX outlet temperature controller, in MANUAL and raise demand to 60%.
- Verify charging flow established:
- Verify 1CV8105 and 1CV8106, charging line CNMT isolation valves - OPEN.
- Throttle 1CV182, charging header backpressure control valve, to establish 8-13 gpm RCP seal injection flow.
- Place 1FK-121, in manual and operate 1FK-121 in manual to establish > 100 gpm charging flow on 1FI-121A.
- Establish letdown flow:
- OPEN 1CV459 & 1CV460, letdown line isolation valves.
- OPEN 1CV8149A/B/C, letdown orifice isolation valves, as necessary to establish 120 gpm letdown flow.
- Lower demand on 1PK-131, letdown line pressure controller, to raise letdown pressure to approximately 360 psig on 1PI-131.
- Operate 1FK-121 in manual to restore PZR level to normal operating band and maintain 8-13 gpm RCP seal injection flow.
- Lower demand on 1CC130A, to control letdown temperature between 90° to 115°F on 1TI-130.
- Place 1PK-131, letdown line pressure controller, in AUTO.
- Place 1CC130A, letdown HX outlet temperature controller, in AUTO.
- At the RM-11, verify 1PR06J rad monitor status is GREEN.
Comments:
151 NRC 3 Page 13
Scenario NRC 3 Event 3 No: No.
Event 1A CV pump shaft shear
==
Description:==
Time Position Applicants Actions or Behavior US
- Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.
- Determine Tech Spec 3.5.2 Condition A is applicable.
- Determine TRM 3.1.d Condition A is applicable.
EXAMINERS NOTE: After the 1A CV pump shaft shear actions are complete and with Lead Examiners concurrence, enter next event.
Comments:
151 NRC 3 Page 14
Scenario NRC 3 Event 4 No: No.
Event 1A Essential Service Water (SX) pump trip
==
Description:==
Time Position Applicants Actions or Behavior EXAMINERS NOTE: The crew will start the standby SX pump per hard card 1BwPR 1-2-A1, BwAR 1-2-A1 OR MAY elect to enter 1BwOA PRI-8 ESSENTIAL SERVICE WATER MALFUNCTION to address the 1A SX pump trip. Actions for 1BwOA PRI-8 start in italics below.
CUE
- Annunciator SX PUMP TRIP (1-2-A1)
- Annunciator SX PUMP DSCH HDR PRESS LOW (1-2-A2)
- 1A SX pump trip light - LIT.
- Determine 1A SX pump tripped.
- Use hard card 1BwPR 1-2-A1 to perform the following actions:
- Start the standby (1B) SX pump (1SX001B/16B/27B must be open to allow a manual pump start).
- Place 1B SX pump control switch to start and hold until the lube oil pressure interlock is met and 1B SX pump starts.
- Reference BwAR 1-2-A1, SX PUMP TRIP:
- Verify 1B SX pump started.
- Verify voltage on ALL 3 phases on 4KV bus > 3990 volts.
- If SX flow cannot be restored, enter 1BwOA PRI-8 ESSENTIAL SERVICE WATER MALFUNCTION.
o Place 1A SX pump C/S in PTL.
o Refer to BwOP SX-1/2.
o Verify annunciator SX PUMP DSCH HDR PRESS LOW (1-2-A2) is NOT LIT.
o Restart the 1A containment chiller.
ATC o Refer to BwARs as time permits.
o Dispatch EO to 1A & 1B SX pumps.
US
- Determine Tech Spec 3.7.8 Condition A is applicable.
- Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct failure.
o Inform Unit 2 to swap SX pumps for proper Chem Feed alignment.
CREW 1BwOA PRI-8 ESSENTIAL SERVICE WATER MALFUNCTION o Identify entry conditions for 1BwOA PRI-8 ESSENTIAL SERVICE WATER MALFUNCTION.
o Dispatch operators to investigate status of 1A SX pump and breaker.
Comments:
151 NRC 3 Page 15
Scenario NRC 3 Event 4 No: No.
Event 1A Essential Service Water (SX) pump trip
==
Description:==
Time Position Applicants Actions or Behavior US o Notify SM of plant status and procedure entry.
o Request SM evaluation of Emergency Plan conditions.
o Enter/implement 1BwOA PRI-8 and direct operator actions to establish the following conditions:
CREW o Check for excessive leakage in Aux Building:
o Contact Radwaste to monitor Aux Building sumps.
o Annunciator SX PUMP SUCT VLV PIT LEVEL HIGH (1-2-D2) - NOT LIT.
BOP o Check status of SX pumps at 1PM06J:
o Start 1B SX pump if not already running.
o Check status of SX system at 1PM06J:
o Annunciator SX PUMP SUCT PRESS LOW (1-2-C1) - NOT LIT.
o Annunciator SX STRN DP HIGH (1-2-C2) - NOT LIT.
o Annunciator SX PUMP DSCH HDR PRESS LOW (1-2-A2) - NOT LIT.
o Annunciator SX PUMP DSCH HDR TEMP HIGH LOW (1-2-B2) - NOT LIT.
o 1A SX pump NOT rotating backwards.
o Check for SX leakage into containment at 1PM06J:
o Annunciator CNMT DRAIN LEAK DETECT FLOW HIGH (1-1-A2) - NOT LIT.
o Check CC outlet temperatures < 105°F at 1PM06J (1TI-674, 0TI-675).
o Check RCP cooling at 1PM05J:
o Annunciator RCP THERM BARR CC WTR TEMP HIGH (1-7-E3) - NOT LIT.
o Annunciator RCP BRNG CC WTR TEMP HIGH (1-7-E5) - NOT LIT.
US o Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.
o Determine Tech Spec 3.7.8 Condition A is applicable.
EXAMINERS NOTE: After the actions for the 1A SX pump trip are complete and with Lead Examiners concurrence, insert next event.
Comments:
151 NRC 3 Page 16
Scenario NRC 3 Event 5 No: No.
Event Master pressurizer pressure controller output fails to 2195 psig (0% demand)
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator PZR PRESS CONT DEV LOW HTRS ON (1-12-C1)
- PZR pressure, 1PI-455A/456/457/458, rising.
- Master PZR pressure controller demand at 0%.
- Identify/report failure of Master pressurizer pressure controller.
- Perform actions per BwAR 1-12-C1:
- Monitor PZR pressure and level channels.
- Verify PZR spray valves closed.
- Check PZR heaters for proper operation.
- Take manual control to restore PZR pressure - place 1PK-455A in manual and raise demand prior to PZR PORVs automatically opening.
- Control PZR pressure manually throughout scenario.
EXAMINERS NOTE: The crew should establish a normal pressure control band to maintain (approximately 2235 psig +/- 15 psig).
CREW o Refer to other BwARs as time permits.
US o Enter Tech Spec 3.4.1 Condition A if PZR pressure drops below 2209 psig.
- Notify SM of plant status and the need for maintenance assistance.
EXAMINERS NOTE: After the actions for the Master Pressurizer Pressure Controller failure are complete and with Lead Examiners concurrence, insert next event.
Comments:
151 NRC 3 Page 17
Scenario NRC 3 Event 6&7 No: No.
Event
Description:
Lowering condenser vacuum requires load to be lowered with rods only due to boric acid transfer pump trip and common boric acid pump unavailable Time Position Applicants Actions or Behavior CUE
- Annunciator SECONDARY SAMPLING PANEL/SINK TROUBLE (1-1-B7)
- Exhaust hood, 1PI-ES043/46/49, (condenser pressure) rising/degrading.
- Annunciator CNDSR VACUUM LOW (1-18-D4)
- Recommend entry to 1BwOA SEC-3 LOSS OF CONDENSER VACUUM.
US
- Direct actions of 1BwOA SEC-3.
- Notify Shift Manager of plant status and procedure entry.
- Request SM evaluation of Emergency Plan conditions.
- Notify Engineering to track condenser pressure.
- Check CW system:
- CW flow normal - NO.
- 1B CW pump discharge valve closed.
- 1A/1C CW pump discharge valves open.
- With condenser pressure rising, perform the following to reduce turbine load to stabilize condenser pressure (use U-1 Contingency ReMAs Op Aid for guidance):
- Select SETPOINT.
- Set REFERENCE DEMAND:
- Select REF DEMAND.
- Enter desired value.
- Select left ENTER.
- Set LOAD RATE:
- Select RATE.
- Enter desired rate.
- Select right ENTER.
- Initiate ramp:
- Select GO/HOLD.
- Select GO.
- Monitor condenser pressure:
- Check Figure 1BwOA SEC-3-1 for acceptable operation.
- Check condenser pressure > 5.5 HgA.
- Prepare reactivity plan to recommend to US for ramp (use U-1 Contingency ReMAs Op Aid for guidance).
Comments:
151 NRC 3 Page 18
Scenario NRC 3 Event 6&7 No: No.
Event
Description:
Lowering condenser vacuum requires load to be lowered with rods only due to boric acid transfer pump trip and common boric acid pump unavailable Time Position Applicants Actions or Behavior
- Determine required boric acid volume.
Borate in Automatic (BwOP CV-6 hard card):
o Turn on PZR backup heaters to equalize boron concentration.
- Set 1FY-0110 BA Blender Predet Counter to desired value.
- Set 1FK-110 BA Flow Control to desired boration rate
- Place MAKE-UP MODE CONT SWITCH to STOP position.
- Place MODE SELECT SWITCH to BORATE position.
- Place MAKE-UP MODE CONT SWITCH to START.
- Verify the following occurs:
- 1CV110B opens.
- 1CV110A opens.
- BA pump starts.
- Proper BA flow on recorder 1FR-110.
- When desired boration is achieved, place MAKE-UP MODE CONT SWITCH to STOP.
- Verify the following occurs:
- 1CV110B closes.
- 1CV110A closes.
- BA pump stops.
- Record time and amount of BA addition.
- Perform BwOP CV-7 to return RMCS to AUTO following the final boration.
OR Batch addition of Boric Acid (BwOP CV-6 hard card):
o Turn on PZR backup heaters to equalize boron concentration.
o Momentarily depress RESET pushbutton on BA Flow totalizer.
- Open 1CV110B.
- Open 1CV110A.
- Start the BA Transfer Pump.
o If desired, control VCL level by adjusting 1LK-112 setpoint to desired value.
- When desired amount of BA has been added, stop the BA Transfer Pump
- Close 1CV110A.
- Close 1CV110B.
- Verify VCT level/pressure at desired value and adjust 1LK-112 setpoint to desired corresponding level setpoint.
- Place 1CV110A/1CV110B in AUTO.
- Record time and amount of BA addition.
- Perform BwOP CV-7 to return RMCS to AUTO following the final boration.
o May flush boric acid lines per BwOP CV-6 step. F.5.
- When the U-1 boric acid transfer pump trips, attempt to align to the U-0 boric acid Comments:
151 NRC 3 Page 19
Scenario NRC 3 Event 6&7 No: No.
Event
Description:
Lowering condenser vacuum requires load to be lowered with rods only due to boric acid transfer pump trip and common boric acid pump unavailable Time Position Applicants Actions or Behavior transfer pump.
- After the U-1 boric transfer pump trip, continue load ramp on rods only.
- Bypass CP demins:
- Open 1CD210A/B.
- Restore condenser vacuum:
o Start at least one hogging vacuum pump.
o Place 2nd set of air ejectors in-service.
- Check condenser pressure:
- Acceptable per Figure 1BwOA SEC-3-1.
- Condenser pressure stable or dropping.
- Check C-9 bypass permissive light - NOT LIT.
- Identify and isolate leak.
US
- Request Chemistry to check dissolved oxygen levels.
- Determine condenser status.
- Contact SM to perform risk assessment, initiate IR, reactivity screening and contact maintenance to investigate/correct instrument failure.
EXAMINERS NOTE: After an acceptable load ramp has occurred and with Lead Examiners concurrence, insert next event.
Comments:
151 NRC 3 Page 20
Scenario NRC 3 Event 8 No: No.
Event Inadvertent FWI & feed line break inside containment
Description:
Time Position Applicants Actions or Behavior CUE
- Annunciator FWIV NOT FULL OPEN (1-1-A4) (1-15-E7)
- FWI monitor lights - ALL lit.
CREW
- Recognize a FWI has occurred and conditions requiring a manual reactor trip exist.
US
- Direct a manual Rx trip.
- Notify SM of plant status and procedure entry.
- Request SM evaluation of Emergency Plan conditions.
- Implement 1BwEP-0 "REACTOR TRIP OR SI.
- Direct operator actions of 1BwEP-0 to establish the following conditions:
ATC Perform immediate operator actions of 1BwEP-0 at 1PM05J:
- Verify reactor trip:
- Rod bottom lights - ALL LIT.
- Reactor trip & Bypass breakers - OPEN.
- Neutron flux - DROPPING.
BOP Perform immediate operator actions of 1BwEP-0 at 1PM02J or OWS drop 210:
- Verify turbine trip:
- All Turbine throttle valves - CLOSED.
- All Turbine governor valves - CLOSED.
BOP Perform immediate operator actions of 1BwEP-0 at 1PM01J:
- Verify power to 4KV busses:
- ESF Buses - BOTH ENERGIZED.
CREW Perform immediate operator actions of 1BwEP-0 at 1PM05J:
- SI First OUT annunciator - LIT.
- SI ACTUATED Permissive Light - LIT.
- SI Equipment - AUTOMATICALLY ACTUATED:
o Either SI pump - RUNNING.
o Either CV pump to cold leg isolation valve OPEN - 1SI8801A/B.
- Manually actuate SI at 1PM05J & 1PM06J.
Comments:
151 NRC 3 Page 21
Scenario NRC 3 Event 9 & 10 No: No.
Event Feed line break inside containment & loss of heat sink/1B CV pump trip
Description:
Time Position Applicants Actions or Behavior EXAMINERS NOTE: Per the 1BwEP-0 Operator Action Summary page, RCP trip criteria is applicable throughout the performance of 1BwEP-0. The crew may trip RCPs whenever the criteria of RCS pressure <1425 psig AND high head SI flow
>100 gpm are recognized.
EXAMINERS NOTE: US and ATC will continue in 1BwEP-0 while BOP is performing Attachment B.
- Verify FW isolated at 1PM04J:
- FW pumps - TRIPPED.
- FW isolation monitor lights - LIT.
- FW pumps discharge valves - CLOSED (or going closed) 1FW002A-C.
- Verify DGs running at 1PM01J:
- DGs - BOTH RUNNING.
- 1SX169A/B OPEN.
- Dispatch operator locally to check operation.
- Verify Generator Trip at 1PM01J:
- OCB 1-8 and 7-8 open.
- PMG output breaker open.
- Verify Control Room ventilation aligned for emergency operations at 0PM02J:
- VC Rad Monitors - LESS THAN HIGH ALARM SETPOINT.
- Operating VC train equipment - RUNNING.
- 0B Supply fan
- 0B Return fan
- 0B M/U fan
- 0B Chilled water pump
- 0B Chiller
- M/U fan outlet damper - 0VC08Y NOT FULLY CLOSED.
- 0B VC train M/U filter light - LIT.
- 0VC09Y - OPEN.
- 0VC313Y - CLOSED.
- Operating VC train Charcoal Absorber aligned for train B.
- 0VC44Y - CLOSED.
- 0VC05Y - OPEN.
- 0VC06Y - OPEN.
- Control Room pressure greater than +0.125 inches water on 0PDI-VC038.
Comments:
151 NRC 3 Page 22
Scenario NRC 3 Event 9 & 10 No: No.
Event Feed line break inside containment & loss of heat sink/1B CV pump trip
Description:
Time Position Applicants Actions or Behavior
- Verify Auxiliary Building ventilation aligned for emergency operations at 0PM02J:
- Two inaccessible filter plenums aligned.
- Plenum A:
- 0VA03CB - RUNNING.
- 0VA023Y - OPEN.
- 0VA436Y - CLOSED.
- Plenum C:
- 0VA03CF - RUNNING.
- 0VA072Y - OPEN.
- 0VA438Y - CLOSED.
- Verify FHB ventilation aligned for emergency operation at 0PM02J:
- 0VA04CB - RUNNING.
- 0VA055Y - OPEN.
- 0VA062Y - OPEN.
- 0VA435Y - CLOSED.
- Secure all running HD pumps.
- Initiate periodic monitoring of Spent Fuel Cooling.
- Notify US Attachment B complete/manual actions taken.
- Verify ECCS pumps running at 1PM05J/1PM06J:
- BOTH CV pumps - NONE RUNNING (1B tripped).
- BOTH RH pumps - RUNNING.
- Manually START 1B SI pump.
- Verify the following at 1PM06J:
- RCFCs running in accident mode.
- Group 2 RCFC accident mode status light lit.
- CNMT Phase A valves closed - NO.
- Manually actuate Phase A.
Close containment isolation valves such that at least one valve is closed on each Phase A penetration before the end of the scenario. (Westinghouse CT-11) (K/A number APE069AA1.01 importance 3.5/3.7)
[CT-11]
- Manually close 1CV8100 and/or 1CV8112.
- Manually close the following valves:
- 1FP010
- 1CV8152/8160
- 1IA065/066
- 1PS228A, 228B, 229A & 229B
- 1PR001A/B Comments:
151 NRC 3 Page 23
Scenario NRC 3 Event 9 & 10 No: No.
Event Feed line break inside containment & loss of heat sink/1B CV pump trip
Description:
Time Position Applicants Actions or Behavior
- Verify Cnmt Vent isolation:
- Group 6 Cnmt Vent Isol monitor lights - LIT.
- Verify AF system:
- AF pumps - Neither RUNNING.
- Attempt manual start of BOTH AF pumps.
o Dispatch EO to BOTH AF pumps.
- AF flow control valves - 1AF005A-D OPEN.
- Verify CC pumps running:
- BOTH CC pumps - RUNNING.
- Verify SX pumps running:
- BOTH SX pumps - RUNNING.
- Check if Main Steamlines Should Be Isolated:
- 1C S/G pressure < 640 psig at 1PM04J.
- CNMT pressure > 8.2 psig at 1PM06J.
CREW
- Determine and announce containment is adverse when containment pressure rises above 5 psig.
- Check if CS is required.
- CNMT pressure remained < 20 psig.
- Verify total AF flow:
- AF flow < 500 gpm.
o May CLOSE 1AF013C & 1AF013G to isolate CST gravity flow to 1C SG feed line break.
CREW Identify entry conditions for 1BwFR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK.
Comments:
151 NRC 3 Page 24
Scenario NRC 3 Event 10 No: No.
Event Feed line break inside containment/loss of heat sink
Description:
Time Position Applicants Actions or Behavior 1BwFR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK US
- Notify SM of plant status and procedure entry.
- Request SM evaluation of Emergency Plan conditions.
- Request STA evaluation of status trees.
- Enter/implement 1BwFR-H.1 and direct operator actions of 1BwFR-H.1 to establish the following conditions:
- Check if secondary heat sink is required:
- RCS temperature > 350°F.
- Check CV pump status:
- CV pumps - NONE RUNNING.
- STOP all RCPs.
- GO TO step 14 (bleed and feed).
- Establish RCS feed path:
- Actuate SI.
- Verify RCS feed path:
- BOTH SI pumps - RUNNING.
- Group 2 cold leg injection monitor lights required for operating ECCS pumps - LIT.
- Establish RCS bleed path:
- PORV isolation valves - 1RY8000A & 1RY8000B energized & open.
Initiate RCS bleed and feed so that the RCS depressurizes sufficiently for SI pump injection to occur. (Westinghouse CT-46) (K/A number EPEE05EA1.1 importance 4.1/4.0)
[CT-46]
- Open BOTH PZR PORVs (1RY455A & 1RY456).
- Verify adequate RCS bleed path:
- PZR PORVs - BOTH OPEN.
- PORV isolation valves - BOTH OPEN.
EXAMINERS NOTE: (1) All critical tasks are complete at this point; the scenario may be terminated at Lead Examiners discretion.
(2) The following steps address restoring feedwater to the SGs.
Comments:
151 NRC 3 Page 25
Scenario NRC 3 Event 10 No: No.
Event Feed line break inside containment/loss of heat sink
Description:
Time Position Applicants Actions or Behavior BOP
- Verify ESF equipment actuations.
CREW
- Maintain RCS heat removal:
- Maintain ECCS flow.
- Maintain PZR PORVs - BOTH OPEN.
- Reset SI, if necessary:
- Depress BOTH SI Reset Pushbuttons at 1PM06J.
- Verify SI ACTUATED PERMISSIVE light NOT lit at 1PM05J.
- Verify AUTO SI BLOCKED PERMISSIVE light LIT at 1PM05J.
- Reset Cnmt isolation:
- Reset Phase A.
- Establish IA to Cnmt:
- Verify any SAC running.
- Open 1IA065 and 1IA066.
- Check if CS should be stopped:
- CS pumps - NONE RUNNING.
- Verify cold leg recirc capability:
- BOTH RH pumps - RUNNING.
- 1SI8811A/B valve position lights - ENERGIZED.
- Try to establish AF to at least one SG:
- Check blowdown isolation and sample valves closed:
- 1SD005A-D & 1SD002A-H.
- Prior to initiating feed flow, review Attachment B.
- Check annunciator AF PUMP SX SUCT VLVS ARMED (1-3-E7) - NOT LIT.
- Check 1AF004A & B - OPEN.
- Check AF pumps - NONE RUNNING (1A AF pump has ground overcurrent flag and motor damage; 1B AF pump has large lube oil leak and engine damage).
- AF isolation valves, 1AF013A-H - OPEN.
- AF flow control valves, 1AF005A-H - THROTTLED/OPEN.
- Check AF flow - NOT ESTABLISHED.
Comments:
151 NRC 3 Page 26
Scenario NRC 3 Event 10 No: No.
Event Feed line break inside containment/loss of heat sink
Description:
Time Position Applicants Actions or Behavior BOP
- Prepare FW system for restoration:
- Check CD/CB pumps - at least ONE RUNNING.
- Place FW valves in manual at 0% demand.
- 1FW510A-540A.
- 1FW034A-D.
- Defeat FW isolation:
- Dispatch U-2 NSO to remove FW isolation fuses.
- FW isolation fuses FU-24 and FU-27 removed at:
- 1PA27J.
- 1PA28J.
- Establish main FW flow to at least one SG:
- Open 1FW035A/B/D.
- Check FW pumps available.
- Check CD/CB pumps - at least TWO RUNNING.
- Prepare startup FW pump for operation:
- Check Bus 159 - ENERGIZED.
- Locally start aux oil pump.
- Open startup FW pump discharge valve - 1FW059.
- Open startup FW pump recirc valve - 1FW076 (place C/S in modulate).
- Close main FW pump recirc valves - 1FW012A, B & C.
- Start startup FW pump.
US
- Prior to initiating FW flow, review Attachment B.
- Establish main FW flow to at least one SG:
- Throttle 1FW034A/B/D to desired flowrate.
- Maintain hotwell level > 7 inches.
EXAMINERS NOTE: Terminate the scenario at Lead Examiners discretion.
(Final)
Comments:
151 NRC 3 Page 27
Simulation Facility Braidwood Scenario Operating Test No.: 151 NRC No.:
NRC 4 Examiners: ______________________ Applicant: _____________________ SRO
______________________ _____________________ ATC
______________________ _____________________ BOP Initial Conditions: IC-16 Turnover: Unit 1 is at 53% power, steady state, equilibrium xenon, MOL. Online risk is green. Following completion of turnover, the crew will perform 1BwOSR 3.7.4.1 MAIN STEAM SYSTEM ISOLATION 1MS018A/B/C/D VALVE TRAVEL AND INDICATION 18 MONTH SURVEILLANCE. Once the surveillance is complete, the SM has directed ramping Unit 1 to 938 MW at 3 MW/min.
Event Malf. No. Event Event No. Type* Description IMF CV32B 1B CV pump auto start failure TRGSET 1 1A CV pump trip on 1A SI pump start ZLO1SI01PA(3) = = 1 IMF CV01A (1 0) 1A CV pump trips on 1A SI pump start TRGSET 2 ZAO1PI524A < 0.46 IMF TH03B (2 10) 600 60 1B SGTR when 1B SG pressure < 600 psig 1 TRGSET 3 N-BOP, US 1BwOSR 3.7.4.1, 1MS018A/B/C/D Surv with ZAO1PKMS042A > 0.90 TS-US 1MS018B valve failure.
IMF PB2411 (3 0) ON IMF PB2412 (3 0) ON IOR ZLO1MS018B2 (3 0) ON IOR ZLO1MS018B1 (3 0) ON IOR ZAO1ZIMS010 (3 0) 90 TRGSET 2 "ZDI1MS018B == 0" TRG 2 "DOR ZAO1ZIMS010" 2 None R-ATC, US Raise power from 53% to 938 MW 3 IMF TH10B 100 15 C-ATC, US 1RY455C spray valve fails open in auto 4 IMF RX13A 0 C-ATC, US PZR level channel, 1LT-459, fails low TS-US 5 IMF RX29B 100 30 I-BOP, US 1FW520 controller fails high in auto 6 IMF FW17 10 30 I-BOP, US HD Tank level controller failure in auto 7 IOR ZDI1MS001B CLS M-ALL 1B MSIV fails closed causing 1B SG safety IMF MS03B 100 valves to stick open IMF MS03F 100 IMF MS03J 100 8 Preload C-ALL 1A CV pump trips/1B CV pump fails to auto start 9 Preload M-ALL 1B SGTR (600 gpm) (faulted and ruptured SG)
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient
SCENARIO OVERVIEW Unit 1 is at 53% power, steady state, equilibrium xenon, MOL. Online risk is green. Following completion of turnover, the crew will perform 1BwOSR 3.7.4.1 MAIN STEAM SYSTEM ISOLATION 1MS018A/B/C/D VALVE TRAVEL AND INDICATION 18 MONTH SURVEILLANCE. Once the surveillance is complete, the SM has directed ramping Unit 1 to 938 MW at 3 MW/min.
After completing shift turnover and relief, the BOP performs 1BwOSR 3.7.4.1. The 1B SG PORV, 1MS018B, will fail the test due to a broken hydraulic line when the valve is stroked open. The Unit Supervisor will enter Tech Spec 3.7.4 Condition A and Tech Spec 3.6.3 Condition C. 1MS019B will remain closed to comply with TS 3.6.3 Condition C. 1MS018B will remain unavailable for the remainder of the scenario. The crew should inform the SM following the 1MS018B failure.
After the 1MS018B failure has been addressed, the crew will commence a ramp to 938 MW at 3 MW/min.
After a measurable change in power, 1PK-455C, Pressurizer Spray Valve controller, will fail to 100%
demand position. 1RY455C will fail full open and pressurizer pressure will drop. The ATC will take manual control of 1PK-455C per hard card 1BwPR 1-12-RY and lower demand to close the pressurizer spray valve.
Tech Spec 3.4.1 Condition A will apply if pressurizer pressure drops below 2209 psig.
After the 1PK-455C failure has been addressed, the controlling PZR level channel, 1LT-459, will fail low.
The crew will implement 1BwOA INST-2 and take actions to restore PZR level control and stabilize plant conditions. Technical Specification 3.3.1 Conditions A and K apply (Tech Spec 3.3.3 and 3.3.4 for Accident Monitoring and Remote Shutdown Panel minimum channel requirements are still met).
After the failed PZR level channel has been addressed, 1FK-520, Feed Reg Valve 1FW520 Controller, will fail to 100% demand. 1FW520, 1B FRV, will fully open and 1B SG level will rise. The crew will take actions per hard card 1BwPR 1-15-SG to stabilize the plant by taking manual control of the 1B FRV controller.
After the 1FK-520 failure is addressed, Heater Drain Tank (HDT) Level Controller, 1LK-HD009A, will fail to 0% demand. The 1HD046A/B valves will throttle close and HDT level will rise. The BOP will take actions to stabilize the plant by taking manual control of the 1LK-HD009A controller.
After the HDT Level Controller failure is addressed, the 1B MSIV fails closed causing three SG safety valves on the 1B SG to stick open resulting in a faulted SG. SG pressure will drop and a manual reactor trip will be required. The crew will implement 1BwEP-0 REACTOR TRIP OR SAFETY INJECTION. When safety injection is actuated, the 1A CV pump will trip. The 1B CV pump must be manually started to establish high head ECCS flow. After determining 1B SG secondary pressure boundary is not intact, the crew will transition to 1BwEP-2 FAULTED STEAM GENERATOR ISOLATION. When 1B SG pressure drops to 600 psig, a SGTR will occur on the 1B SG, causing a faulted/ruptured SG. The crew will complete isolation of 1B SG and transition to 1BwEP-3 STEAM GENERATOR TUBE RUPTURE based on secondary radiation trends on the 1B SG. In addition, the crew will recognize 1B SG pressure does not drop to zero and lowering pressurizer level/pressure will indicate a SGTR (alternate indications). After determining the ruptured SG pressure is less than 320 psig, the crew will transition 1BwCA-3.1 SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED.
Completion criteria is completion of step 8 to stop the RH pumps in 1BwCA-3.1.
Critical Tasks
- 1. Manually start the 1B CV pump prior to completion of step 6 of 1BwEP-0.
(Westinghouse - CT-6) (K/A number - 013000A4.01 importance 4.5/4.8)
- 2. Isolate 1B Steam Generator prior to completing step 4 of 1BwEP-2.
(Westinghouse - CT-18) (K/A number - APE040AA1.10 importance 4.1/4.1) 151 NRC 4 Page 2
SIMULATOR SETUP GUIDE
- Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.
- Establish the conditions of IC-16, 53% power, steady state, equilibrium xenon.
- Complete items on Simulator Ready for Training Checklist.
- Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario.
- Place simulator in RUN (allow simulator to run during board walk down and turnover).
- Run caep 151 NRC 4 SETUP from disk and verify the following actuate:
- IMF CV32B
- TRGSET 1 ZLO1SI01PA(3) = = 1
- IMF CV01A (1 0)
- TRGSET 2 ZAO1PI524A < 0.46
- IMF TH03B (2 10) 600 60
- See EVENT 1 and run the event 1 cae during simulator setup.
- Provide examinees with turnover sheets.
151 NRC 4 Page 3
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: 1BwOSR 3.7.4.1 with 1MS018B valve failure (Tech Spec).
Run caep 151 NRC 4 EVENT 1 from disk and verify the following actuate:
- TRGSET 3 ZAO1PKMS042A > 0.90
- IMF PB2411 (3 0) ON
- IMF PB2412 (3 0) ON
- IOR ZLO1MS018B2 (3 0) ON
- IOR ZLO1MS018B1 (3 0) ON
- IOR ZAO1ZIMS010 (3 0) 90
- TRGSET 4 "ZDI1MS018B == 0"
- TRG 4 "DOR ZAO1ZIMS010" When requested, as Equipment Operator, report you are standing by at the 1MS018B/C valves.
Report the following as an EO when prompted: AS FOUND position for 1MS019A/B/C/D is OPEN.
When requested to close 1MS019A/B/C/D insert the following:
- IRF MS51 0 for 1MS019A.
- IRF MS52 0 for 1MS019B.
- IRF MS53 0 for 1MS019C.
- IRF MS54 0 for 1MS019D.
As SM acknowledge the failure of 1MS018B, LCO 3.6.3, Condition C and LCO 3.7.4, Condition A entry, and requests for on-line risk assessment, maintenance support and IR initiation. If asked, 1BwOSR 3.6.3.5.MS-1 is NOT required to be performed.
If asked, as EO, report 1MS018B has a broken hydraulic line and a small puddle of hydraulic fluid is present beneath the valve. The hydraulic pump is running. If asked 1MS018B is 90% open locally.
After the BOP takes the 1MS018B C/S to CLOSE, if asked as the EO, report 1MS018B is 90% open & its hydraulic pump is NOT running.
As WEC supervisor, acknowledge request for EST for 1MS018B C/S, if EST is requested.
Event 2: Raise power to 938 MW at 3 MW/min.
If ramp is not commenced immediately after the Tech Spec entry, call as TSO and request status of Unit 1 ramp to 938 MW.
Acknowledge as Chemistry/Rad Protection requests for samples (if required).
Acknowledge as Generation Dispatch the initiation of the ramp.
151 NRC 4 Page 4
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 3: 1PK-455C Pressurizer Spray Valve Controller failure.
Insert IMF TH10B 100 15 to fail 1RY455C controller to 100% demand over 15 seconds.
As SM, acknowledge the failure, LCO 3.4.1 Condition A entry and exit (if applicable), and requests for maintenance support, and IR initiation.
Events 4: PZR level channel 1LT-459 fails low.
Insert IMF RX13A 0 to fail 1LT-459 low.
As SM, if support requested for bypassing the bistable in AEER, report that AEER bistable is not to be bypassed until work analyst and NSO support can be obtained (in approx. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) and that the abnormal operating procedure should be continued.
Acknowledge as Shift Manager the failure, LCOAR entry, on-line risk assessment, EAL evaluation, request for maintenance support, and IR request.
Event 5: 1FW520 controller fails high in auto.
Insert IMF RX29B 100 30 to fail 1FK-520 controller to 100% demand over 30 seconds.
If dispatched as EO to investigate, wait one minute and report no visible damage to 1FW520. 1FW520 appears to be responding correctly in manual (if asked for feedback to manual ops).
Acknowledge as Shift Manager the failure, request for maintenance support, and IR request.
Event 6: HDT Level controller failure.
Insert IMF FW17 0 30 to fail the controller to 0% demand over 30 seconds.
If dispatched as EO to investigate, wait one minute and report no visible damage to 1HD046A or B valves.
Report local operation/position of 1HD046A/B the same as MCR indication (if asked for feedback to manual valve operation).
Report local HD tank level same as MCR indication.
If dispatched as EO to investigate HDT rupture disk, report it is intact.
151 NRC 4 Page 5
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 7: 1B SG Safety valves stick open when 1B MSIV fails closed.
Run caep 151 NRC 4 EVENT 7 from disk and verify the following actuate:
IOR ZDI1MS001B CLS IMF MS03B 100 IMF MS03F 100 IMF MS03J 100 After faulted SG is diagnosed by crew OR two minutes after malfunction is inserted, report as security, steam flow from 1B/1C MSIV room safety valve tailpipes.
Acknowledge as SM procedure changes, Emergency Plan evaluations, and STA request.
Event 8: 1A CV pump trips/1B CV pump fails to auto start (preload).
Verify that the 1A CV pump trips when the 1A SI pump starts.
If dispatched as EO to investigate 1A CV pump, report ground overcurrent flag at breaker cubicle.
Event 9: Faulted/ruptured 1B SG (preload).
Verify that MF TH03B inserts when 1B SG pressure drops below 600 psig.
Acknowledge as SM procedure changes, Emergency Plan evaluations, and STA request.
After STA requested, as STA report CSF status.
151 NRC 4 Page 6
Scenario NRC 4 Event 1 No: No.
Event Perform 1BwOSR 3.7.4.1 MAIN STEAM SYSTEM ISOLATION 1MS018A/B/C/D VALVE
==
Description:==
TRAVEL AND INDICATION 18 MONTH SURVEILLANCE Time Position Applicants Actions or Behavior CUE From turnover, perform 1BwOSR 3.7.4.1.
US
- Direct BOP to perform 1BwOSR 3.7.4.1.
- Refer to 1BwOSR 3.7.4.1.
- Verify/initial step 1, initial conditions.
- Contact the EO at 1MS019B for initial position and record initial valve positions.
- Direct the EO to close 1MS019B.
- OPEN 1MS018B at 1PM04J.
- Respond to Annunciator S/G 1B PORV TROUBLE (1-15-B10) alarm.
- Identify/report trouble alarm on 1MS018B.
- Refer to BwAR 1-15-B10.
- Contact operator at 1MS018B for valve status.
o Place 1MS018B C/S in close to stop hydraulic pump.
o Request Equipment Status Tag for 1MS018B C/S & 1MS019B hand wheel.
US
- Identify entry conditions for Tech Spec 3.7.4 Condition A.
- Identify entry conditions for Tech Spec 3.6.3 Condition C.
o Direct operator to maintain 1MS019B closed.
o Inform SM of 1MS018B status, Tech Spec status, request IR, on-line risk assessment, maintenance support, and clearance order/EST for 1MS019B.
EXAMINERS NOTE: (1) After the actions for 1MS018B failure are complete and with Lead Examiners concurrence, enter next event.
(2) 1B S/G PORV LVDT meter de-energizes when its control switch is placed in close.
Comments:
151 NRC 4 Page 7
Scenario NRC 4 Event 2 No: No.
Event Raise power to 938 MW at 3 MW/min
==
Description:==
Time Position Applicants Actions or Behavior CUE
- If ramp is not commenced immediately after suspending the surveillance, call from TSO to request the status of the Unit 1 power ascension.
US
- Acknowledge request to raise load to 938 MW at 3 MW/min.
- Implement actions of 1BwGP 100-3.
o Perform pre-job brief per HU-AA-1211 PRE-JOB, HEIGHTENED LEVEL OF AWARENESS, INFREQUENT PLANT ACTIVITY, AND POST JOB BRIEFINGS for load ramp.
US
- Direct raising load to 938 MW at 3 MW/min.
o Initiate Load Swing Instruction Sheet, 1BwGP 100-4T2.
CREW o Review applicable Precautions, and Limitations and Actions (may have been done in PJB prior to starting scenario).
o May energize PZR heaters.
- Verify rod position and boron concentration.
- Initiate dilution per BwOP CV-5.
- Determine required PW volume from ReMA.
o Dilute in automatic (PREFERRED):
o Determine required PW flowrate.
o Note as found setpoint on 1FK-111, PW Total Flow Controller Pot.
o Adjust setpoint on 1FK-111 to desired PW flowrate.
o Set 1FY-0111 PW Control Predet Counter, to desired PW volume.
o Control VCT level by adjusting 1LK-112 setpoint or manually controlling 1LK-112.
o Place MAKE-UP CONT SWITCH to STOP position.
o Set MODE SELECT to DIL/ALT DIL position.
o Place MAKE-UP CONT SWITCH to START.
o Verify proper operation of valves and PW makeup pump (1CV111B open, 1CV111A throttled, 1CV110B open (ALT DIL only), PW pump running, proper PW flow on recorder).
o When desired dilution completed, place MAKE-UP CONT SWITCH to STOP position.
o Verify the following (1CV111B close, 1CV111A close, 1CV110B close, PW pump remains running).
o Control VCT level by adjusting 1LK-112 setpoint or manually controlling 1LK-112.
o Reset PW Total Flow Totalizer to ZERO.
Comments:
151 NRC 4 Page 8
Scenario NRC 4 Event 2 No: No.
Event Raise power to 938 MW at 3 MW/min
==
Description:==
Time Position Applicants Actions or Behavior o Open 1CV111B, if desired to dilute to VCT upper nozzle.
o Open 1CV110B, if desired to dilute to VCT outlet.
o Open 1CV111A.
o When desired amount of primary water added:
o Close 1CV111A and verify/place control switch to AUTO.
o Close 1CV110B and verify/place control switch to AUTO.
o Close 1CV111B and verify/place control switch to AUTO.
- Raise turbine load at 1PM02J or OWS drop 210 by performing the following:
- Select SETPOINT.
- Enter 938 MW into REF DEMAND window.
- Select left ENTER.
- Verify correct value appears in REF DEMAND window.
- Enter 3 MW/min into the RATE window.
- Select right ENTER.
- Select EXIT.
o Notify Control room team of pending ramp.
- Select GO/HOLD.
- Verify GO/HOLD illuminates orange.
- Verify HOLD illuminates RED.
- Select GO.
- Verify GO illuminates RED while the main turbine ramps.
- Verify main turbine load begins to rise.
- Monitor reactor power and load ascension:
- Monitor NIs, Tave, I, PZR pressure/level at 1PM05J or PPC.
- During dilution, monitor the following at 1PM05J or PPC:
- VCT level.
- RCS Tave.
o PW/Total flow predet counter responding correctly.
o Verify dilution auto stops at preset value.
o Return Reactor Makeup Control System to automatic.
o Perform periodic control rod steps to maintain Tave and Delta I within boundaries.
EXAMINERS NOTE: After measurable change in power and with Lead Examiners concurrence, enter next event.
Comments:
151 NRC 4 Page 9
Scenario NRC 4 Event 3 No: No.
Event 1PK-455C, Pressurizer Spray Valve controller, fails to 100% demand
Description:
Time Position Applicants Actions or Behavior CUE
- 1RY455C valve position lights indicate full open.
- Pressurizer pressure dropping.
- Master Pressurizer Pressure Controller demand dropping.
o Annunciator PZR PRESS CONT DEV LOW HTRS ON (1-12-C1)
- Identify failure/report alarm on 1PM05J.
- Perform the following actions per hard card 1BwPR 1-12-RY:
- Place 1PK-455C in manual.
- Lower demand to close 1RY455C (adjust PZR pressure to pre-failed value).
BOP o Refer to BwARs as time permits.
o Hold load ramp, if requested.
US
- Direct operator to close 1RY455C.
o Identify entry condition for Tech Spec 3.4.1 Condition A if RCS pressure drops below 2209 psig.
o Identify exit condition for Tech Spec 3.4.1 Condition A.
o May hold load ramp (if in progress).
US o Inform SM of 1PK-455C failure, Tech Spec status, request IR, on-line risk assessment and maintenance support.
NOTE: After the actions for 1PK-455C failure are complete and with Lead Examiners concurrence, enter next event.
Comments:
151 NRC 4 Page 10
Scenario NRC 4 Event 4 No: No.
Event PZR level channel, 1LT-459, fails low
Description:
Time Position Applicants Actions or Behavior CUE
- Annunciator PZR LVL LOW HTRS OFF LTDWN SECURED (1-12-A4)
- Annunciator PZR HTR TRIP (1-12-A5)
- Annunciator PZR LEVEL CONT DEV LOW (1-12-B4)
- PZR level, 1LI-459A/461, and charging flow rising.
- Determine PZR level and/or charging header flow rising at 1PM05J.
- Identify 1LI-459A is failed low.
- Report failure to US.
- Perform the following at 1PM05J:
- Verify automatic actions occurred (letdown isolated, heaters tripped off).
o Reference BwARs as time permits.
CREW
- Identify entry conditions for 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL.
US
- Notify Shift Manager of plant status and procedure entry.
- Request SM evaluation of Emergency Plan conditions.
- Implement 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL, ATTACHMENT C PRESSURIZER LEVEL CHANNEL FAILURE, and direct operator actions of 1BwOA INST-2 to establish the following conditions:
o May hold load ramp (if in progress).
- Check PZR level at 1PM05J:
- PZR level normal - NO.
- Select operable PZR level control channel:
- Place PZR level control select C/S to CH 461/460 position.
- Select operable PZR level channel for PZR level recorder at 1PM05J:
- Check letdown and PZR heaters at 1PM05J:
- Check letdown flow established - NO, letdown isolated (1BwOA ESP-2 actions are Comments:
151 NRC 4 Page 11
Scenario NRC 4 Event 4 No: No.
Event PZR level channel, 1LT-459, fails low
Description:
Time Position Applicants Actions or Behavior on the next page).
- Check PZR heaters normal:
- PZR heaters available in auto.
- Check PZR level control in auto at 1PM05J:
- Verify/place the following components in AUTO:
- 1LK-459, Master PZR level controller.
- 1FK-121, CV pumps flow control valve.
BOP 1BwOA ESP-2 REESTABLISHING CV LETDOWN DURING ABNORMAL CONDITIONS Restore normal letdown using 1BwOA ESP-2 as directed by performing the following at 1PM05J:
- Check letdown isolated:
- Verify 1CV8149A, B, & C, letdown orifice isolation valves - CLOSED.
- Verify 1CV459 & 1CV460, letdown line isolation valves - CLOSED.
- Check letdown flow path:
- Verify 1CV8401A, letdown HX 1A isolation valve - OPEN.
- Verify 1CV8324A, charging to regen HX 1A isolation valve - OPEN.
- Verify 1CV8389A, letdown to regen HX 1A isolation valve - OPEN.
- Verify 1CV8152 & 1CV8160, letdown line CNMT isolation valves - OPEN.
- Verify BTRS mode select switch OFF light - LIT.
- Align letdown controllers:
- Place 1PK-131, letdown line pressure controller, in MANUAL and raise demand to 40%.
- Place 1CC130A, letdown HX outlet temperature controller, in MANUAL and raise demand to 60%.
- Verify charging flow established:
- Verify 1CV8105 and 1CV8106, charging line CNMT isolation valves - OPEN.
- Throttle 1CV182, charging header backpressure control valve, to establish 8-13 gpm RCP seal injection flow.
- Place 1FK-121, in manual and operate 1FK-121 in manual to establish > 100 gpm charging flow on 1FI-121A.
- Establish letdown flow:
- OPEN 1CV459 & 1CV460, letdown line isolation valves.
- OPEN 1CV8149A/B/C, letdown orifice isolation valves, as necessary to establish 120 gpm letdown flow.
- Lower demand on 1PK-131, letdown line pressure controller, to raise letdown pressure to approximately 360 psig on 1PI-131.
- Operate 1FK-121 in manual to restore PZR level to normal operating band and Comments:
151 NRC 4 Page 12
Scenario NRC 4 Event 4 No: No.
Event PZR level channel, 1LT-459, fails low
Description:
Time Position Applicants Actions or Behavior maintain 8-13 gpm RCP seal injection flow.
- Lower demand on 1CC130A to control letdown temperature between 90° to 115°F on 1TI-130.
- Place 1PK-131, letdown line pressure controller, in AUTO.
- Place 1CC130A, letdown HX outlet temperature controller, in AUTO.
- At the RM-11, verify 1PR06J rad monitor status is GREEN.
US
- Determine Tech Spec 3.3.1 Conditions A and K are applicable.
o Determine Tech Spec 3.3.3 and 3.3.4 are NOT applicable - minimum channels operable requirement is met.
- Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.
EXAMINERS NOTE: After the actions for the pressurizer level channel failure are complete and with Lead Examiners concurrence, insert next event.
Comments:
151 NRC 4 Page 13
Scenario NRC 4 Event 5 No: No.
Event
Description:
1FW520 (1B FRV) controller fails high in auto Time Position Applicants Actions or Behavior CUE
- Annunciator S/G 1B FLOW MISMATCH STM FLOW LOW (1-15-B3)
- 1FK-520 controller output failed high.
- Determine 1B SG level rising.
- Perform the following per hard card 1BwPR 1-15-SG at 1PM04J:
- Place 1FK-520 in manual.
- Restore 1B SG level to pre-failed value.
- Determine that 1B FRV controller failed in auto.
- Report failure to US.
CREW
- Recognize 1FK-520 output failed high.
o Reference BwARs as time permits.
US
o May hold load ramp (if in progress).
US o Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct controller failure.
CREW o Crew may elect to base load 1FW520 and place 1FW520A in automatic per 1BwGP 100-3 Limitation E.4.g or BwOP FW-30.
EXAMINERS NOTE: After the actions for the 1FW520 controller failure are complete and with Lead Examiners concurrence, insert next event.
Comments:
151 NRC 4 Page 14
Scenario NRC 4 Event 6 No: No.
Event
Description:
HD Tank Level Controller Failure Time Position Applicants Actions or Behavior CUE
- HD tank level controller, 1LK-HD009A, output failed to 0%.
- Lowering HD pump flows on 1FI-HD004/6.
- Rising HD tank level on 1LI-HD009.
- Annunciator HD TANK LEVEL HIGH LOW (1-17-E4)
CREW
- Recognize 1LK-HD009A output failed low (0%).
US
- Direct/ensure BOP takes manual control of 1LK-HD009A and restore HD Tank level to normal.
- Inform SM of HD Tank level controller failure.
- Perform the following at 1PM03J:
- Place 1LK-HD009A, HD Tank Level Controller, in manual.
- Raise demand on 1LK-HD009A.
- Monitor HDT level and control 1HD046A/B position to restore HD Tank level to normal.
- Maintain HD Tank level by operating 1LK-HD009A in manual.
o Dispatch EO to 1HD046A/B valves.
US o Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.
ATC o Review BwARs as time permits.
EXAMINERS NOTE: After the actions for the HD tank level controller failure are complete and with Lead Examiners concurrence, insert next event.
Comments:
151 NRC 4 Page 15
Scenario NRC 4 Event 7&8 No: No.
Event 1B MSIV closes causing1B SG safety valves to stick open, 1A CV pump trips/1B CV
==
Description:==
pump fails to auto start Time Position Applicants Actions or Behavior CUE
- 1B MSIV indicates closed.
- Annunciator S/G 1B FLOW MISMATCH FW FLOW LOW (1-15-B4)
- PZR pressure lowering.
- Turbine MW output lowering.
- Recommend/initiate a manual reactor trip.
- Initiate a manual SI.
CREW
- Recognize indications of faulted SG.
o Dispatch operators to look for steam leak.
o When report is received that 1B SG safeties are open, recognize that SG pressure is below safety valve lift setpoint.
US
- Direct a manual Rx trip.
- Implement 1BwEP-0 "REACTOR TRIP OR SI.
- Notify SM of plant status and procedure entry.
- Request SM evaluation of Emergency Plan conditions.
- Direct operator actions of 1BwEP-0 to establish the following conditions:
ATC Perform immediate operator actions of 1BwEP-0 at 1PM05J:
- Verify reactor trip:
- Rod bottom lights - ALL LIT.
- Reactor trip & Bypass breakers - OPEN.
- Neutron flux - DROPPING.
BOP Perform immediate operator actions of 1BwEP-0 at 1PM02J:
- Verify turbine trip:
- All Turbine throttle valves - CLOSED.
- All Turbine governor valves - CLOSED.
BOP Perform immediate operator actions of 1BwEP-0 at 1PM01J:
- Verify power to 4KV busses:
- ESF Buses - BOTH ENERGIZED (141 & 142).
Comments:
151 NRC 4 Page 16
Scenario NRC 4 Event 7&8 No: No.
Event 1B MSIV closes causing1B SG safety valves to stick open, 1A CV pump trips/1B CV
==
Description:==
pump fails to auto start Time Position Applicants Actions or Behavior CREW Recognize and respond to conditions requiring a Safety Injection in accordance with 1BwEP-0 REACTOR TRIP OR SAFETY INJECTION, step 4:
- SG pressure cannot be maintained > 640 psig.
- Manually actuate SI from 1PM05J and 1PM06J.
CREW
- Check SI Status:
o SI First OUT annunciator - LIT.
o SI ACTUATED Permissive Light - LIT.
o SI Equipment - AUTOMATICALLY ACTUATED.
o Either SI pumps - RUNNING.
o Either CV pump to cold leg isolation valve OPEN - 1SI8801A/B.
CREW o May choose to isolate 1B SG immediately due to possible personnel safety considerations.
o Isolate AF to 1B SG - CLOSE 1AF013B/F.
o Actuate Main Steam Isolation.
US
EXAMINERS NOTE: US and ATC will continue in 1BwEP-0 while BOP is performing Attachment B.
- Verify FW isolated at 1PM04J:
- FW pumps - TRIPPED.
- FW isolation monitor lights - LIT.
- FW pumps discharge valves - CLOSED (or going closed) 1FW002A-C.
- Verify DGs running at 1PM01J:
- DGs - BOTH RUNNING
- 1SX169A/B OPEN.
- Dispatch operator locally to check operation.
- Verify Generator Trip at 1PM01J:
- OCB 1-8 and 7-8 open.
- PMG output breaker open.
- Verify Control Room ventilation aligned for emergency operations at 0PM02J:
- VC Rad Monitors - LESS THAN HIGH ALARM SETPOINT.
- Operating VC train equipment - RUNNING.
- 0B Supply fan.
- 0B Return fan.
- 0B M/U fan.
- 0B Chilled water pump.
- 0B Chiller.
Comments:
151 NRC 4 Page 17
Scenario NRC 4 Event 7&8 No: No.
Event 1B MSIV closes causing1B SG safety valves to stick open, 1A CV pump trips/1B CV
==
Description:==
pump fails to auto start Time Position Applicants Actions or Behavior
- M/U fan outlet damper - 0VC08Y NOT FULLY CLOSED.
- 0B VC train M/U filter light - LIT.
- 0VC09Y - OPEN.
- 0VC313Y - CLOSED.
- Operating VC train Charcoal Absorber aligned for train B.
- 0VC44Y - CLOSED.
- 0VC05Y - OPEN.
- 0VC06Y - OPEN.
- Control Room pressure greater than +0.125 inches water on 0PDI-VC038.
- Verify Auxiliary Building ventilation aligned for emergency operations at 0PM02J:
- Two inaccessible filter plenums aligned.
- Plenum A:
- 0VA03CB - RUNNING.
- 0VA023Y - OPEN.
- 0VA436Y - CLOSED.
- Plenum C:
- 0VA03CF RUNNING.
- 0VA072Y - OPEN.
- 0VA438Y - CLOSED.
- Verify FHB ventilation aligned for emergency operation at 0PM02J:
- 0VA04CB - RUNNING
- 0VA055Y - OPEN.
- 0VA062Y - OPEN.
- 0VA435Y - CLOSED.
- Secure all running HD pumps.
- Initiate periodic monitoring of Spent Fuel Cooling.
- Notify US Attachment B complete/manual actions taken.
- Verify ECCS pumps running:
- CV pumps - NONE RUNNING.
Manually start the 1B CV pump prior to completion of step 6 of 1BwEP-0.
(Westinghouse - CT-6) (K/A number - 013000A4.01 importance 4.5/4.8)
[CT-6]
- Manually start the 1B CV pump.
- Both RH pumps - RUNNING.
- Both SI pumps - RUNNING.
Comments:
151 NRC 4 Page 18
Scenario NRC 4 Event 7&8 No: No.
Event 1B MSIV closes causing1B SG safety valves to stick open, 1A CV pump trips/1B CV
==
Description:==
pump fails to auto start Time Position Applicants Actions or Behavior ATC
- Verify RCFCs running in Accident Mode.
- Group 2 RCFC Accident Mode lights - LIT.
- Verify Phase A isolation.
- Group 3 Cnmt Isol monitor lights - LIT.
- Verify Cnmt Vent isolation.
- Group 6 Cnmt Vent Isol monitor lights - LIT.
- Verify AF system:
- BOTH AF pumps - RUNNING.
- AF isolation valves - 1Af013A-H OPEN.
- AF flow control valves - 1AF005A-H throttled OPEN.
- Verify CC pumps running:
- BOTH CC pumps - RUNNING.
- Verify SX pumps running:
- BOTH SX pumps - RUNNING.
- Check if Main Steamlines Should Be Isolated:
- Check SG pressures:
o SG pressures > 640 psig - continue in 1BwEP-0.
- CNMT pressure < 8.2 psig.
- Check if CS is required.
- CNMT pressure remained < 20 psig.
- Verify total AF flow:
- AF flow > 500 gpm.
- Check S/G NR levels - NOT rising in an uncontrolled manner.
- Verify ECCS valve alignment:
- Group 2 Cold Leg Injection monitor lights required for injection - LIT.
- Verify ECCS flow:
- RCS pressure < 1700 psig.
- SI pump discharge flows > 200 gpm.
- RCS pressure < 325 psig.
Comments:
151 NRC 4 Page 19
Scenario NRC 4 Event 7&8 No: No.
Event 1B MSIV closes causing1B SG safety valves to stick open, 1A CV pump trips/1B CV
==
Description:==
pump fails to auto start Time Position Applicants Actions or Behavior ATC
- Check PZR PORVs and spray valves:
- PORVs CLOSED.
- PORV isolation valves - BOTH ENERGIZED.
- Normal spray valves CLOSED.
- Check RCS temperatures:
o ANY RCP running.
- RCS Tave stable at or trending to 557°F - NO.
o Throttle AF flow.
o NO RCPs running.
- RCS cold leg temperature stable at or trending to 557°F - NO.
o Throttle AF flow.
- Check status of RCPs:
- ALL RCPs - RUNNING.
- Check RCP trip criteria.
o RCS pressure > 1425 psig - continue in 1BwEP-0.
o RCS pressure < 1425 psig:
- Verify high head injection flow (1FI-917) > 100 gpm.
- Trip ALL RCPs.
- Check if SG secondary pressure boundaries are intact:
- Check NO SG depressurizing uncontrollably or completely depressurized.
- 1B SG pressure dropping in an uncontrolled manner.
CREW Transition to 1BwEP-2 FAULTED STEAM GENERATOR ISOLATION.
Comments:
151 NRC 4 Page 20
Scenario NRC 4 Event 9 No: No.
Event 1B SGTR (600 gpm), faulted/ruptured 1B SG
==
Description:==
Time Position Applicants Actions or Behavior 1BwEP-2 FAULTED STEAM GENERATOR ISOLATION US
- Notify SM of plant status and procedure entry.
- Request SM evaluation of Emergency Plan conditions.
- Request STA evaluation of status trees.
- Enter/implement 1BwEP-2 and direct operator actions of 1BwEP-2 to establish the following conditions:
- Check MS isolation:
- All MSIVs and bypass valves - CLOSED.
- Check if any SG secondary pressure boundary is intact:
- 1A, 1C & 1D SG pressures stable.
CREW
- Identify faulted SG:
- 1B SG pressure lowering in an uncontrolled manner (1B SG indicates steam flow with its MSIV and MSIV bypass valve closed).
- Isolate 1B Steam Generator:
Isolate 1B Steam Generator prior to completing step 4 of 1BwEP-2.
(Westinghouse - CT-18) (K/A number - APE040AA1.10 importance 4.1/4.1)
[CT-18]
- Verify/Close 1AF013B & F - may have been closed at step 15 of 1BwEP-0.
- Verify 1MS018B closed.
- Verify 1SD002E & F closed.
- Verify 1SD005C closed.
- Check AF Pump Suction Pressure:
- Annunciator AF PUMP SX SUCT VLVS ARMED (1-3-E7) - NOT LIT.
- Check Secondary Radiation:
- Reset Phase A at 1PM06J.
- OPEN 1SD005A-D at 1PM11J.
- Request Chemistry to periodically sample SGs for activity.
- Check secondary radiation trends:
- 1B Main Steam Line radiation abnormal on PPC or RM-11.
CREW Transition to 1BwEP-3 STEAM GENERATOR TUBE RUPTURE.
Comments:
151 NRC 4 Page 21
Scenario NRC 4 Event 9 No: No.
Event 1B SGTR (600 gpm), faulted/ruptured 1B SG
==
Description:==
Time Position Applicants Actions or Behavior 1BwEP-3 STEAM GENERATOR TUBE RUPTURE US
- Notify SM of plant status and procedure entry.
- Request SM evaluation of Emergency Plan conditions.
- Enter/implement 1BwEP-3 and direct operator actions of 1BwEP-3 to establish the following conditions:
- Check Status of RCPs:
- Identify ruptured SG 1B:
- 1B Main steam line rad monitors ABNORMAL for plant conditions.
- Isolate flow from ruptured SG:
- Verify 1MS018B in auto and closed. (C/S may be in CLOSE, 1MS018B failed 90%
open, 1MS019B closed).
- Verify 1SD002E & F CLOSED.
- Check ruptured SG level - Narrow Range level < 10%:
- Do not feed 1B SG per Caution prior to step.
o Verify/close 1AF013B & F - previously closed in 1BwEP-0 OR 1BwEP-2.
- Set 1AF005B and 1AF005F pot demand = 0%.
CREW
- Determine ruptured SG pressure < 320 psig.
Transition to 1BwCA-3.1 SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED.
US
- Notify SM of plant status and procedure entry.
- Request SM evaluation of Emergency Plan conditions.
- Enter/implement 1BwCA-3.1 and direct operator actions of 1BwCA-3.1 to establish the following conditions:
- Reset SI:
- Depress both SI reset pushbuttons.
- Verify SI actuated permissive light - NOT LIT.
- Verify auto SI blocked permissive light - LIT.
o Reset Phase A (performed in 1BwEP-2).
- Check a station air compressor is running at 0PM01J.
- OPEN 1IA065 and 1IA066 at 1PM11J.
Comments:
151 NRC 4 Page 22
Scenario NRC 4 Event 9 No: No.
Event 1B SGTR (600 gpm), faulted/ruptured 1B SG
==
Description:==
Time Position Applicants Actions or Behavior BOP
- Verify all AC buses energized by offsite power:
- All 4 KV non-ESF buses energized.
- All 6.9 KV buses energized.
- De-energize PZR Heaters:
- Place all B/U heaters contactors to OFF.
- Place variable heater control switch in AFTER TRIP.
o Consult with SM (TSC) for recommended minimum PZR level to keep PZR heaters covered.
- Check if CS should be stopped:
- CS pumps - NONE running.
- Check ruptured SG level:
- Check if RH pumps should be stopped:
- 1SI8812A & B open (aligned to RWST).
- RCS pressure > 325 psig and stable/rising.
o Stop both RH pumps and place in standby (if conditions met).
EXAMINERS NOTE: Terminate the scenario at Lead Examiners discretion.
(Final)
Comments:
151 NRC 4 Page 23