IR 05000424/2003301
| ML032450424 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 05/08/2003 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 50-424/03-301, 50-425/03-301 | |
| Download: ML032450424 (51) | |
Text
Final Submittal VOGTLE OP RETAKE EXAM 50-424 & 50-425/2003-301 MAY 8,2003 As Given Simulator Scenarlo wperaror AcIions ES-D-2
Appendix D Scenario Outline Form ES-D-1 Facility: Voqtle Electric Generatina Plant Scenario NO.:^
Examiners:
Operators:
Op-Test No.: 301-2003
FW06 I MT I Feed break inside containment Post I
....-
Automatic Feedwater isolation fails, HV 8801B thermals out when being closed I
I
1 BMDAFW fails to auto start M I I
I I
Scenario ends when primary and secondary plant are stabl * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix 0 Scenario Outline Form ES-D-1 TU02 I,
Main turbine vibration which leadk to lhe requwernent to lower tuhne load. Will cont.nue until crew IS forced to use rods which. at this point wlli not drive CB D This should lead io a manual Rx tri C (Bop)
U Facility: Voatle Electric Generatina Plant Scenario No.: 1 Examiners:
Operators:
Op-Test No.: 301-2003 U
POST MT It It ES02I1 MT ANVS followed by Small Break LOCA
& RC04 I A HHSI pump falls to start, HV-88018 fails to ope Initial Conditions:
Rx Power loo%, EOL, Rod Operability Testing in progress with CB C and D left to d Turnover:
I 4BoVAC Swltchgear Fault-Fault switchgear that feeds HV-8801A (BIT valve)
Tech Spec for SqO. Begin to slowly ramp in RCS leak at Examiners deswetio I1 I
I I
I1
- (N)orrnal, (R)eactivity, (I)nstrument, (C)ornponent, (M)ajor
Facility:
Vogtle Scenario No:
Op-Test No:
Examiners: George Hopper Operators:
Clint Hartfield (SRO)
John Covington (RO surrogate)
Tim Harris (BOP surrogate)
Initial Conditions:
Unit 1 is at 75% Reactor Power at EOL. Power had been held at 70% power to replace HDP #2. The HDP has been returned to service. 1A MDAFWP is out of service. Metal filings were found a pump oil sample. The pump has been tagged to inspect the pump bearings. It has been out of service for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of an expected 56-hour outage. LCO 3.7.5, condition B is in effec Turnover: UOP 12004-C, Power Operation step 4.1.45 has been complete Reactor Power is being held at 75% while temperature and vibration on HDP #2 is being measure OSP 14410-1, Control Rod Operability Test is in progress. The surveillance has been completed for all Shutdown Banks and Control Banks A and 6. You are to complete the surveillance for Control Banks C and Once 14410-1 and HDP monitoring is complete, you are to begin a power ramp to return to 100% power in accordance with 12004-C, step 4.1.4... rev C
Initial Conditions:
Unit 1 is at 75% Reactor Power at EOL. Power had been held at 70% power to replace HDP #2. The HDP has been returned to service. 1A MDAFWP is out of service. Metal filings were found a pump oil sample. The pump has been tagged to inspect the pump bearings. It has been out of service for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of an expected 56-hour outage. LCO 3.7.5, condition B is in effec Turnover:
UOP 12004-C, Power Operation step 4.1.45 has been complete Reactor Power is being held at 75% while temperature and vibration on HDP #2 is being measure OSP 14410-1, Control Rod Operability Test is in progress. The surveillance has been completed for all Shutdown Banks and Control Banks A and B. You are to complete the surveillance for Control Banks C and Once 14410-1 and HDP monitoring is complete, you are to begin a power ramp to return to 100% power in accordance with 12004-C, step 4.1.4 rev C
Event N...
POST MT Action N Malf RD 12H Malf u Event Type*
N MT Event Description Perform OSP 14410-1, Control Rod Operability Tes Control Bank D, rod D4 fails to move during completion of OSP 14410-1, Control Rod Operability Tes Loss of power to 1AB15, IABB, and IABD resulting in a loss of power to BIT isolation valve I-HV-8801A. Tech Spec for SR Main Turbine Vibration leads to the requirement to reduce powe Failure of automatic and manual reactor trip followed by a small break LOC CRITICAL TASK CCP 1AfaiIs to start, IHV 88016 fails to ope CRITICAL TASK
rev C
PREINSERTS:
Initial Conditions:
Ensure Exam Security per 60008-C, EXAMINATION SECURITY PROGRAM 0 Base IC
2 0 Ensure Information Board in Control Room is updated
Shift sign in and reactivity briefing sheets provided 0 RO & BOP Name plates on Panel D
Check EOPs, AOPs, UOPs, SOPS used in the last scenario clear of marks
Correct AFD sheet Select to following QMCB positions:
IPC is Mode 1 0 Check Control Rod Group Step Counters 0 Ensure all QPCP and QHVC recorders running in auto
Place CLEARANCE HOLD TAG on:
Train A MDAFW Discharge valve IHS-5137A CLOSED 0 Train A MDAFW Discharge valve IHS-5139A CLOSED
Train A MDAFW CST #2 Suction valve 1 HS-5119 CLOSED
Place CAUTION TAG for the PRNl HIGH FLUX TRIP SETPOINT AT 90%
0 Place BATP train A in STOP 0 Place BATP train B in AUTO 0 shut down A CCW D Start B ccw
Insert the following ACTIONS:
MALFUNCTIONS:
0 AF 028 Train A MDAFWP trip I 0 ES 01 Failure of the Automatic Reactor Trip 1_______1 0 ES 02 Failure of the Manual Reactor Trip I 0 CV 06A CCP 1A trip ______i 0 RD 12H CBD rod D4 fails to move d
ANN OVERRIDES:
0 None REMOTE:
0 SF 01 Train A SFPC to 00s L SF 02 Train 6 SFPC to inservice _l_l__i OVERRIDE POT:
0 None OVERRIDE METER:
0 None SWITCHES:
Train A MDAFW CST #2 Suction valve 1 HS-5119A CLOSED Train A MDAFW Discharge valve IHS-5137A CLOSED
0 Train A MDAFW Discharge valve IHS-5139A CLOSED I
BIT Isolation Valve 1 HS 8801 B CLOSED OVERRIDE LAMP:
0 Train A MDAFW CST #2 Suction valve IHS-5119A GREEN set DIGITAL VALUE OFF
OFF I
- I Train A MDAFW Discharge valve IHS-5137A GREEN set DIGITAL VALUE 0 Train A MDAFW Discharge valve IHS-5137A WHITE set DIGITAL VALUE OFF 0 Train A MDAFW Discharge valve IHS-5139A GREEN set DIGITAL VALUE OFF 0 Train A MDAFW Discharge valve IHS-5139A WHITE set DIGITAL VALUE OFF I
rev C
OP Test N Scenario N Event N & 2 Event Control Bank D, rod D4 fails to move during completion of OSP Description:
14410-1, Control Rod Operability Tes Time Position Applicants Actions or Behaviors SRO Declare rod D4 untrippable and enter LCO 3.1.4, condition o Request the performance of 14005-1, Shutdown Margin Calculation within 1 h o Be in mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> if the rod cannot be declared trippable RO o Complete OSP 14410-1, Control Rod Operability Test for Control Banks C and D. Identify rod D4 fails to mov BOP o none Crew Initiate maintenance
rev C
OP Test N Scenario N Event N & 2 Event Control Bank D, rod D4 fails to move during completion of OSP Description:
1441 0-1, Control Rod Operability Tes Action Instructions Preloaded I&C reports a blown lift coil fuse. The fuse cannot be replaced until after troubleshooting the circui Notes:..
rev C
OP Test N Scenario N Event N Event Description:
Loss of power to 1AB15, IABB, and IABD resulting in a loss of power to BIT isolation valve 1-HV-8801A. Tech Spec for SR Time Position SRO RO BOP Applicants Actions or Behaviors o Recognize entry into LCO 3.8.9, condition A (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to restore)
Identify loss of power to ECCS valves o Recognize loss of 480v. swgr. 1AB15, MCC IABB and IABD o Reference ARP 17036-1 and Electrical One Line Drawings to determine affected equipment Crew o
rev C
OP Test N Scenario N Event N Event Description:
Action Instructions Malf EL 10G Loss of power to 1AB15, IABB, and IABD resulting in a loss of power to BIT isolation valve 1-HV-8801A. Tech Spec for SR Opens 1AB15-01, supplyto 1AB15 NOTE 5 Notes: IX3D-AA-El6A (1 AB1 5), IX3D-AA-Fl6A (1 ABB), lX3D-AA-FIlNB (IABD). rev C
Description:
Time Position SRO
OP Test N Scenario N Event N Event Main Turbine Vibration leads to reactorlturbine tri Applicants Actions or Behaviors o Direct a reactorlturbine trip as vibration approaches the turbine trip setpoint (12 mil).
RO BOP o Recognize successful the attempt to trip the reactor was not o Reference ATSl computer display to determine alarm was due to turbine vibration o Reference ARP 17020 and SOP 13800 Manually trip the turbine Crew
rev C
OP Test N Scenario N Event N Event Description:
Action Instructions TU 02 Main Turbine Vibration leads to reactorhurbine tri Ramp to 50% over 300 seconds I
Notes:.
1.
rev C
OP Test N Scenario N Event N Event Description:
Time Position Applicants Actions or Behaviors Failure of automatic and manual reactor trip followed by a small break LOCA with no BIT flow availabl SRO o Enter E-0 (19000) Reactor Trip or SI and at step 1 transition to FR-S.1 (19211), ATWT o Direct the BOP to verify AFW pumps running o Direct the RO to emergency borate 0 Direct the RO verify CVI Direct the BOP to maintain AFW flow greater than 1260gpm o Direct someone to isolate all RCS dilution paths Direct the RO to verify RCS temperature stable Direct the RO to verify CETCs are less than 1200°F
rev C
u Transition from FR-S.1 to E-0 step 1 o Direct the BOP to verify power to the I-E busses u Direct the RO to check if SI is actuated o Direct the BOP to verify FWI o Direct the RO to verify SI is aligning and CIA is actuated u Direct the BOP to verify AFW pumps running and SGBD is isolated o Direct the RO to verify ECCS pumps, CCW pumps, and NSCW pumps and Containment Coolers are running o Direct the RO to verify CVI
rev C
SRO o Direct BOP to check MSLl is not required Direct the RO to verify Containment Spray not required o Direct the BOP to verify the EDGs running o Direct the RO to verify ECCS flows o Direct the BOP to verify AFW flow greater than 570gpm or SG level greater than 10%
Direct the RO to verify ECCS alignment is correct Direct the RO to verify RCS temperature stable or trending to 557°F Direct the RO to verify the PORVs, Block Valves, and Pzr spray valves operable o Direct the RO to shut down the RCPs if RCS pressure is less than 1375psig
rev C
SRO P Direct the RO to verify ACCW is in service o Direct the BOP to verify the SG secondary pressure boundaries and the SG tubes are intact o Direct the RO to determine if the RCS is intact and transition to E-I Loss of Reactor or Secondary Coolant (19010)
o Direct the RO to shut down the RCPs if RCS pressure is less than 1375psig o Direct the RO to verify ACCW is in service P Direct the BOP to verify the SG secondary pressure boundaries and the SG tubes are intact Direct the RO to verify the PORVs and Block Valves operable Direct the RO to check ECCS termination criteria
SRO Direct the RO to shutdown the RHR pumps if RCS pressure is greater than 300 psig Direct the BOP to shutdown the EDGs and reenergize the stub busses o Direct the RO to verify Cold Leg Recirc capability o Transition to ES-1.2 Post LOCA Cooldown and Depressurization (1 901 2)
o Direct the RO to Reset SI and CIA o Direct the BOP to establish instrument air to containment Direct the BOP to verify all busses are energized form offsite power o Direct the RO to deenergize the PZR heaters and shutdown the RHR pumps o Direct the RO and BOP to initiate a cooldown
rev C
RO o Attempt to trip the reactor and begin to manually insert control rods o emergency borate o verify CVI o verify RCS temperature stable o verify CETCs are less than 1200°F o verify the reactor is subcritical o check if SI is actuated o verify SI is aligning and CIA is actuated verify ECCS pumps running, identify CCP 1A tripped
rev C
RO o verify CCW pumps, and NSCW pumps and Containment Coolers are running 0 verify CVI D verify Containment Spray not required u verify ECCS flows, identify no BIT flow o verify ECCS alignment is correct, identify the BIT cannot be opened o verify RCS temperature stable or trending to 557°F verify the PORVs, Block Valves, and Pzr spray valves operable u shut down the RCPs if RCS pressure is less than 1375psig o verify ACCW is in service o determine the RCS is not intact and transition to E-I Loss of Reactor or Secondary Coolant (19010)
rev C
RO o shut down the RCPs if RCS pressure is less than 1375psig o verify ACCW is in service verify the PORVs and Block Valves operable o verify the ECCS termination criteria cannot be met shutdown the RHR pumps if RCS pressure is less than 300 psig o verify Cold Leg Recirc capability Reset SI and CIA o deenergize the PZR heaters and shutdown the RHR Pumps o initiate a cooldown
rev C
BOP Trip the turbine P verify AFW pumps running o maintain AFW flow greater than 1260gpm o verify power to the 1 -E busses n verify FWI n verify AFW pumps running and SGBD is isolated o check MSLl is not required n verify the EDGs running Verify AFW flow greater than 570gpm or SG level greater than 10%
Verify the SG secondary pressure boundaries and the SG tubes are intact
rev C
BOP o Verify the SG secondary pressure boundaries and the SG tubes are intact o shutdown the EDGs and reenergize the stub busses o establish instrument air to containment o verify all busses are energized from offsite power o initiate a cooldown Crew o Dispatch operator to open the Reactor Trip Breakers
rev C
-
OP Test N Scenario N Event N Event Failure of automatic and manual reactor trip followed by a small Description:
break LOCA with no BIT flow availabl Action Instructions Malf RC 05D Set severity to 3% after step 7 of S-I (1921 I-C)
I
-.
Notes:
1 If someone was dispatched to locally open the Reactor Trip Breakers, remove Malfunction ES 01 after 4 minute.
1.
rev C
Facility:
Vogtle Scenario No:
Op-Test No:
Examiners:
Operators:
John Covington (SRO surrogate)
George Hopper Clint Hartfield (RO)
Tim Harris (BOP surrogate)
Initial Conditions:
Unit 1 is at 100% Reactor Power at EOL. 1A MDAFWP is out of service. Metal filings were found a pump oil sample. The pump has been tagged to inspect the pump bearings. It has been out of service for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of an expected 56 hour6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> outage. LCO 3.7.5, condition B is in effec Turnover: UOP 12004-C, section 4.3 is currently in effec.
Reduce reactor power to less than 95% in accordance with step 5.3.1.1 of 14540-1. OSP 14540-1, Main Turbine Valve Stroke Test surveillance is due. The quarterly performance is due which requires reactor power to be less than 95%.
AMSAC has been bypassed for a surveillance that is being performed by I&C and engineerin... rev C
Initial Conditions:
Unit 1 is at 100% Reactor Power at EOL. 1A MDAFWP is out of service. Metal filings were found a pump oil sample. The pump has been tagged to inspect the pump bearings. It has been out of service for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of an expected 56 hour6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> outage. LCO 3.7.5, condition B is in effec Turnover:
UOP 12004-C, section 4.3 is currently in effec Reduce reactor power to less than 95% in accordance with step 5.3.1.I of 14540-1. OSP 14540-1, Main Turbine Valve Stroke Test surveillance is due. The quarterly performance is due which requires reactor power to be less than 95%.
AMSAC has been bypassed for a surveillance that is being performed by I&C and engineerin rev C
- vent N...
POST MT Action N nOne TU 19A FW 06C Event Type*
R BOP)
~~
Event Description Reduce reactor power to less than 95% in accordance with step 5.3.1.1 of 14540-1, and then perform section VCT Level Transmitter 1 LT-185 fails high TE-130 fails low resulting in a loss of cooling to CVCS Letdown HX. Requires manual contro ~~~
~
Generator load rejection coincident with Turbine impulse pressure transmitter 1 PT-505 failing hig CRITICAL TASK SG #3 Main Feedwater Line break inside containment Auto CIA fails, 1 HV 8801 B fails to shut, Train B MDAFWP fails to auto start
- 3 -
rev C
.
PREINSERTS:
Initial Conditions:
0 Ensure Exam Security per 60008-C, EXAMINATION SECURITY PROGRAM 0 Base IC
_______I 0 Ensure Information Board in Control Room is updated 0 Shift sign in and reactivity briefing sheets provided 0 RO & BOP Name plates on Panel D 0 Check EOPs, AOPs, UOPs, SOPS used in the last scenario clear of marks 0 Correct AFD sheet Select to following QMCB positions:
0 IPC is Mode 1 0 Check Control Rod Group Step Counters Ensure all QPCP and QHVC recorders running in auto 0 Place Clearance Hold Tag on:
0 Train A MDAFWP IHS-5131A PTL 0 Train A MDAFW Discharge valve IHS-5137A CLOSED 0 Train A MDAFW Discharge valve 1 HS-5139A CLOSED 0 Train A MDAFW CST #2 Suction valve IHS-5119 CLOSED 0 ROD BANK SELECTOR SWITCH selected to IHS-40041 MANUAL 4 -
rev C
Insert the following ACTIONS:
MALFUNCTIONS:
0 AF 02B Train A MDAFWP trip 0 ES 20A Block auto CIA train A 0 ES 20B Block auto CIA train B ANN OVERRIDES:
None REMOTE:
0 None OVERRIDE POT:
None OVERRIDE METER 0 None SWITCHES:
0 Train A MDAFW CST #2 Suction valve IHS-5119A CLOSED 0 Train A MDAFW Discharge valve IHS-5137A CLOSED 0 Train A MDAFW Discharge valve IHS-5139A CLOSED
0 Override N-129 to Demin Position
OVERRIDE LAMP:
D Train A MDAFW CST #2 Suction valve IHS-5119A GREEN set DIGITAL VALUE OFF -
OFF
.I
-______i OFF -
Train A MDAFW Discharge valve IHS-5137A GREEN set DIGITAL VALUE 0 Train A MDAFW Discharge valve IHS-5137A WHITE set DIGITAL VALUE OFF 0 Train A MDAFW Discharge valve IHS-5139A GREEN set DIGITAL VALUE 0 Train A MDAFW Discharge valve IHS-5139A WHITE set DIGITAL VALUE OFF 6 -
rev C
OP Test N Scenario N Event N Event Description:
5.3.1.I of 14540-1 Time Position Applicants Actions or Behaviors Reduce reactor power to less than 95% in accordance with step SRO o Brief crew on power reduction o Direct operators to reduce power to less than 95%
o Refer to UOP 12004-C. Power Operation RO o Borate RCS and insert control rods to maintain T,,
on Program and AFD on Target BOP Reduces turbine load per SOP 13800-1 Crew o None
- 7 -
rev C
OP Test N Scenario N Event N Event Description:
5.3.1.I of 14540- Action Instructions Reduce reactor power to less than 95% in accordance with step Notes:..
OP Test N Scenario N Event N Event VCT Level Transmitter 1 LT-185 fails high Description:
Time Position SRO RO BOP Applicants Actions or Behaviors Initiate maintenance Verify VCT auto makeup starts at 30% on 1 LT-112 o Place 1 -LV-I12A to the VCT position None Crew o Recognize VCT LoLo Level Auto Swap to RWST is inoperabl o Monitor VCT level on Plant Computer 9 -
rev C
OP Test N Scenario N Event N Event Description:
VCT Level Transmitter 1 LT-185 fails high Action Malf CV 12 NOTE 5 Instructions Notes:..
LV-112A modulates to the HUT
- 1 0 -
rev C
OP Test N Scenario N Event N Event Description:
Time Position Applicants Actions or Behaviors TE-130 fails low resulting in a loss of cooling to CVCS Letdown HX and a failure of the automatic demin divert functio SRO a Initiate maintenance RO a Isolate letdown or take manual control of I-TIC-I30 to control letdown temperature less than 115°F o Recognize the Letdown Demin Bypass Valve 1 HS-129 did not automatically divert and then manually place the handswitch to the "VCT" positio o Refer to ARP 17007 ALBFOI o Verify Letdown has diverted around the CVCS demins BOP a None Crew o None
- 11 -
rev C
OP Test N Scenario N Event N Event Description:
TE-130 fails low resulting in a loss of cooling to CVCS Letdown HX and a failure of the automatic demin divert functio Action Instructions Malf CV 04 Notes: I O.
1.
- 1 2 -
rev C
OP Test N Scenario N Event N Event Description:
Time Position Applicants Actions or Behaviors Generator load rejection coincident with Turbine impulse pressure transmitter 1 PT-505 failing hig SRO o Go to AOP 18012-C for the load rejection Go to AOP 18001-C for the turbine impulse pressure fa i I u re RO o Identify effects of 1 PT-505 failure on Rod Control and place rods in manual Insert control rods to restore Tavs/Tref P Adjust RCS boron concentration as necessary to maintain control rods above the insertion limit o Verify P-7 and P-13 status lights are not illuminated
- 13 -
rev C
BOP o Verify Turbine runback is not required o Place turbine load control in STANDBY and verify load stabilizes o Identify 1 PT-505 failure o Place steam dumps in the Steam Pressure Mode n ResetC-7 Crew o Stabilize reactor power, reactor temperature, and turbine load to shut the steam dumps
- 14-rev C
OP Test N Scenario N Event N Event Description:
Action Instructions Malf GE 09 Generator load rejection coincident with Turbine impulse pressure transmitter 1 PT-505 failing hig Set severity to 30% -
Malf TU 19A Set severity to 100% i Notes:
1.
1.
- 15 -
OP Test N Scenario N Event N Event Description:
Time Position Applicants Actions or Behaviors Main Feedwater Line break inside containment SRO o Enter E-0 (19000) Reactor Trip or SI Direct RO verify the reactor is tripped Direct the BOP to verify the turbine is tripped and all 1-E busses are energized o Direct the RO to verify SI is actuated o Direct the BOP to verify FWI o Direct the RO to verify ECCS equipment is aligning Direct RO to actuate CIA o Direct RO and BOP to manually align CIA valves when auto or manual alignment does not occur
- 16-rev C
SRO o Direct the BOP to verify AFW pumps running and SGBD is isolated o Direct the RO to verify ECCS pumps, CCW pumps, NSCW pumps, and Containment Coolers are running o Direct the RO to verify CVI has aligned o Direct the BOP to verify MSLl has actuated Direct the RO to verify Containment Spray is not required o Direct the BOP to verify the EDGs are running Direct the RO to verify ECCS flow Direct the BOP to verify AFW flow greater than 570gpm or SG levels greater than 10% (32%)Direct the RO to verify proper ECCS alignment o Direct the RO to verify RCS temperature trending to 557°F
- 1 7 -
rev C
SRO Direct the RO to verify PORV, Block valve and Pzr Spray valve operability Direct the RO to shutdown the RCPs if RCS pressure is less than 1375psig Direct the RO to verify ACCW is in service o Direct the BOP to verify SG secondary pressure boundaries are not intact Transition to E-2 (19020) Faulted Steam Generator Isolation Direct BOP to verify SG #3 MSlV and BSlV are shut o Direct BOP to verify SG #3 MFlV and BFlV are shut o Direct BOP to isolate AFW to SG # 3 o Direct BOP to verify SG # 3 ARV and SGBD are isolated
- 1 8 -
rev C
SRO Transition to ES-1.I (1901 1) SI Termination if SI Termination Criteria are met, transition to E-I (19010) Loss of Reactor or Secondary Coolant if SI criteria are not me Direct RO to stop RCPs if RCS Pressure is less than 1375psig Q Direct BOP to verify SG #3 is isolated Q Direct BOP to control intact SG levels between 10%(32%) and 65%
o Direct BOP to verify no indications of secondary activity o Direct RO to verify PORV and Block Valve operability Q Transition to ES-1.1 (19011) SI Termination when SI Termination Criteria are met Direct RO to reset SI and CIA o Direct BOP to restore instrument air to containment
- 1 9 -
rev C
SRO Direct RO to shutdown all but 1 CCP and establish normal charging flow pat o Direct the RO to shut the CCP discharge header crosstie valve 1 HV 8438 and start the 1A CCP-20-rev C
RO o verify the reactor is tripped o verify SI is actuated verify ECCS equipment is aligning o attempt to actuate CIA, and manually align when actuation does not occur o verify ECCS pumps, CCW pumps, NSCW pumps, and Containment Coolers are running o verify CVI has aligned o verify Containment Spray is not required shutdown the RCPs if RCS pressure is less than 1375psig verify ECCS flow verify proper ECCS alignment-21 -
rev C
o verify RCS temperature trending to 557°F o verify PORV, Block valve and Pzr Spray valve operability o verify ACCW is in service o stop RCPs if RCS Pressure is less than 1375psig o verify PORV and Block Valve operability o reset SI and CIA o Shutdown all but 1 CCP and establish normal charging flow path o Recognize BIT cannot be isolated because 1 HV 8801 B cannot be shu o Shut the CCP discharge header crosstie valve IHV 8438 and start the 1A CCP
- 22 -
rev C
BOP o verify the turbine is tripped and all I-E busses are energized o verify FWI o manually align CIA valves when auto or manual alignment does not occur o verify AFW pumps running and SGBD is isolated o verify MSLl has actuated o verify the EDGs are running verify AFW flow greater than 570gpm or SG levels greater than 10% (32%)
o verify SG secondary pressure boundaries are not intact verify SG #3 MSlV and BSlV are shut verify SG #3 MFlV and BFlV are shut
- 23 -
rev C
u isolate AFW to SG # 3 o verify SG # 3 ARV and SGBD are isolated o verify SG #3 is isolated u control intact SG levels between 10%(32%) and 65%
u verify no indications of secondary activity R restore instrument air to containment Crew o Recognize Adverse Containment conditions-24-rev C
OP Test N Scenario N Event N Event Description:
Action Instructions Malf FW 06C Main Feedwater Line break inside containment Ramp to 100% in 300 seconds Switches After SI is actuated override BIT Discharge isolation valve 1 HS8801 B OPEN Override lamp When SI flow is being terminated and the the RO places the handswitch for BIT Discharge isolation valve 1 HS8801 B to the CLOSE position, then insert the following LAMPS and the ANN OVERRIDE to simulate the breaker trippin BIT Discharge isolation valve 1HS8801B GREEN set DIGITAL VALUE OFF BIT Discharge isolation valve 1HS8801B RED set DIGITAL VALUE OFF ALB 37 DO1 set to ON ANN OVERRIDE Notes:
1.
1.
25 -
rev C