ML030920375
| ML030920375 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 03/10/2003 |
| From: | Bollinger S Detroit Edison |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 50-341/03-301, ES-D-1 50-341/03-301 | |
| Download: ML030920375 (25) | |
Text
NUREG 1021, Rev.8, Supplement 1 Appendix D Scenario Outline Form ES-D-1 Facility: Fermi 2 Scenario No. 1 Op-Test No: 2003-301 Examiners:
Operators:
Initial Conditions: IC-14, MOL 65% Reactor Power.
NOTE: The Pre-job Briefing for 24.206.01 is to be conducted by the crew prior to entering the simulator. (suggested time 30 minutes prior to beginning the scenario). RHR will be placed in Torus Cooling by the previous shift in preparation for the RCIC run.
Event No.
Malf. No.
Event Type*
Event Description 1
N/A R(RO)
N (SRO)
Withdraw Control Rods to the target rod pattern.
2 VO 1300 I(RO)
APRM Channel 1 Failure (130%)
3 MF 142 C(RO)
Control Rod 06-31 Uncoupled 4
N/A N(BOP)
Perform 24.206.01 section 5.1
- 5 MF 3656 MF 3657 C(BOP)
Pressure Regulator Failure N001A(0 #)
Pressure Regulator Failure N001B(0 #)
6 MF 14 M
Main Steam Line C Rupture in the Drywell (3%)
6 VO 177 VO 178 C
Div 1 (2) RHR DW Spray Otbd Iso Vlv, Fail as is at 0%
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor The inservice pressure regulator will be failed downscale.
NUREG 1021, Rev.8, Supplement 1 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.: 2003-301 Scenario No.: 1 Event No.: 1 Page 1 of 2 Event
Description:
Change Reactor Power using control rods.
Time Position Applicant's Actions or Behavior 0 min SRO Conduct a (Short) Briefing on pulling rods to increase reactor power in accordance with 23.623.
+5 min RO NOTE: The Post LPSP pull sheet for Group 10-1 being withdrawn from 20-48 will be provided to the crew prior to rod withdrawal.
Begin to withdrawal control rods to increase reactor power in accordance with 23.623:
Place rod select power in ON Select control rod to be withdrawn Position rod IAW the rod pull sheets (perform rod coupling check on rods withdrawn to position 48)
When rod movement is complete for the selected control rod, select another rod for movement or turn rod select power to OFF.
Conducts coupling check for rods withdrawn to position 48 in accordance with 23.623 Attachment 2.
NOTE: During rod motion at this power level, a RBM Upscale alarm may occur. If it occurs, use the following CUE:
CUE: When requested, wait a couple of minutes and then respond as the STA/SNE. State that you have run a fast case Thermal Limits verification and they are satisfactory to allow renulling RBM.
Respond to Annunciator 3D109 RBM Upscale/Inop Notify Station Nuclear Engineer Verify Reactor Core Thermal Limits within limits.
Verify Control Rods are in accordance with the Rod Pull Sheet.
Check the LPRMs of selected control rod for local power change.
If Thermal Limits are satisfactory, Renull RBM by deselecting the selected control rod, and either select a different control rod or the original rod.
NUREG 1021, Rev.8, Supplement 1 Op-Test No.: 2003-301 Scenario No.: 1 Event No.: 1 Page 2 of 2 Event
Description:
Change Reactor Power using control rods.
SRO/
When Reactor power reaches 65% direct placing Recirc A & B Flow Limiter 2/3 Defeat Switch to NORMAL in accordance with 23.138.01, section 6.1.
RO When Reactor power reaches 65% place the Recirc A & B Flow Limiter 2/3 Defeat Switch to NORMAL in accordance with 23.138.01, section 6.1.
NUREG 1021, Rev.8, Supplement 1 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.: 2003-301 Scenario No.: 1 Event No.: 2 Page 1 of 1
Event
Description:
APRM Channel 1 Upscale (Insert during the third rod movement)
Time Position Applicant's Actions or Behavior
+10 min SRO Responds to APRM #3 Upscale Annunciator 3D97, 3D113, 3D101, & 3D102 Refers to TS 3.3.1.1 RPS Instrumentation Refers to TRM 3.3.2.1 Control Rod Block Instrumentation Directs RO to bypass APRM #3 in accordance with 23.605.
Directs Crew to resume power increase.
RO Respond to annunciator 3D97 APRM Neutron Flux Upscale Trip, 3D101APRM Simulated Thermal Power Upscale Trip, 3D102 APRM Simulated Thermal Power Upscale & 3D113 Control Rod Withdrawal Block Stop control rods movement, investigate cause.
Identifies APRM #3 Upscale.
Bypass APRM #3 in accordance with 23.605, when directed.
Resume power increase when directed.
BOP Respond to annunciator 3D97 APRM Neutron Flux Upscale Trip Notify extra licensed operator to go to the Relay Room and check the condition of the APRM.
BOOTH OPERATOR ACTION: Four minutes after requested, respond as the extra licensed operator that APRM #1 mode switch is in the OPERATE position and is pegged upscale.
After APRM 1 is bypassed report that the blue BYPASSED LED is on for APRM !.
NUREG 1021, Rev.8, Supplement 1 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.: 2003-301 Scenario No.: 1 Event No.: 3 Page 1 of 1
Event
Description:
06-31Uncoupled Control Rod (This is the fourth rod selected)
Time Position Applicant's Actions or Behavior 15 min RO During performance of the rod coupling check in accordance with 23.623, Attachment 2, respond to 3D76, CONTROL ROD OVERTRAVEL, and 3D80 CONTROL ROD DRIFT alarm.
+15 min SRO After verifying an actual control rod over travel has occurred, enter 20.106.02 "Uncoupled/Dropped Control Rod (From Reactor Core)."
Direct actions for Subsequent Actions Condition C Control Rod uncoupled.
C.1 Direct SNE to evaluate effect on Control Rod Pattern.
C.2 Direct RO to Attempt to re-couple rod:
- a. Insert Control Rod in notch mode until nuclear instrumentation indicates Control Rod is inserting.
- b. Obtain permission from SM and SNE to withdraw Control Rod.
- c. Fully withdraw Control Rod in notch mode while observing nuclear instrumentation response.
- d. Perform a coupling check (23.106).
- e. Position Control Rod as directed by SNE.
- f. Reset the CONTROL ROD DRIFT alarm.
BOP Booth Operator Action: The booth operator will delete the uncoupled control rod malfunction after the over travel rod has been notched in to position 46.
The AOP is exited after the control rod is repositioned to position 48 and the coupling check is satisfactory
NUREG 1021, Rev.8, Supplement 1 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.: 2003-301 Scenario No.: 1 Event No.: 4 Page 1 of 2
Event
Description:
Perform RCIC full flow surveillance test per 24.206.01 Time Position Applicant's Actions or Behavior 20 min SRO The CRS gives permission for the BOP to perform RCIC full flow test per 24.206.01.
NOTE: The Pre-job Briefing for 24.206.01 was to have been conducted by the crew prior to entering the simulator. (suggested time 30 minutes prior to beginning the scenario) 20 min BOP A short review of the surveillance precautions and limitations and overview of the upcoming actions may be made by the Panel Operator. The following actions are performed by the BOP operator:
- 1. Verify T4100-B021, Div 1 CS Pumps Room Cooler, in RUN
- 2. Perform the following at COP H11-P805:
- a. Verify P1100-F606, CST Common Rtrn Iso Valve, OPEN.
- b. Verify P1100-F610, CRT Common Rtrn Iso Valve, CLOSED.
3.Verify or place E41-F011, Pressure Controller in AUTO.
- 4. Place E41-F011Selector switch in OPER
- 5. Verify E41-F011 CLOSED.
- 6. Open E5150-F022.
- 7. Start Barometric Condenser Vacuum Pump.
- 8. Record an initial set of Suppression Chamber water temperature readings from T23-R800, Torus Water Temperature Rec, on.
- 9. Record reactor pressure & RCIC turbine inlet steam pressure and verify pressure parameters meet acceptable limits.
BOOTH OPERATOR ACTION: The booth operator will follow along in a copy of 24.206.01 and provide the communications from the field expected from the Nuclear Operator at the RCIC Pump.
- 10. Select E41-F011 Valve Position and Pressure Permissive.
- a. At H11-P602, adjust E41-K820, E41-F011 Ctrlr, to set valve position opening setpoint to about 20% open (s display).
- b. At H11-P602, adjust E41-K820, E41-F011 Ctrlr, to set discharge pressure setpoint to 250 psi (Y-display).
- 11. During RCIC Turbine operation, at five minute record average Suppression Chamber water temperature and verify it is less than or equal to 105°F.
- 12. Make an announcement that the RCIC System will be operated and that personnel in the Torus room should stay clear of the northeast Torus area where the rupture disks are located.
- 13. Open E5150-F046 and measure stroke time
NUREG 1021, Rev.8, Supplement 1
- 14. Verify E5150-F046, goes full open.
NUREG 1021, Rev.8, Supplement 1 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.: 2003-301 Scenario No.: 1 Event No.: 4 Page 2 of 2
Event
Description:
Perform RCIC full flow surveillance test per 24.206.01 Time Position Applicant's Actions or Behavior RO The RO will monitor reactor power, pressure, level and Turbine load during the performance of the RCIC test.
- 15. Manually start RCIC System as follows:
a.Open E5150-F095 b.15 seconds after opening E5150-F095, open E5150-F045 and measure its stroke time.
16.Verify RCIC Turbine starts and speed increases.
17.Verify E41-F011 strokes open to approximately 20% after pump discharge pressure exceeds 250 psig
- 18. Verify the following:
- 19. E5150-F019, RCIC Min Flow Vlv, auto opens, and auto closes when required 20.If necessary after RCIC Turbine Speed is steady:
- a. Adjust E41-F011 Ctrlr, (S-display) to establish a discharge pressure between Rx Pressure plus 100 psi and Rx Pressure plus 150 psi as.
b.Record E41-F011 valve position
- 21. Record RCIC discharge pressure and flow BOOTH OPERATOR ACTION: The booth operator will step the scenario at the discretion of the Lead Examiner some point after RCIC has been started
NUREG 1021, Rev.8, Supplement 1 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.: 2003-301 Scenario No.: 1 Event No.: 5 Page 1 of 2
Event
Description:
Respond to a Pressure Regulator fails low in accordance with 20.109.02.
Time Position Applicant's Actions or Behavior 40 min BOP The operator reports Pressure Regulator in control transfers to backup Pressure Regulator and notes that Pressure Regulator Fault and/or Pressure Regulator Unhealthy white lights on (H11-P804) and responds to ARP 4D91, ELECTRIC GOVERNOR TROUBLE 40 min SRO The SRO enters AOP 20.109.02 for Pressure Regulator signal failed low when this condition is recognized by the failed Pressure Regulator being the present backup as indicated by the white Regulator No 1(2) pushbuttons being off (H11-P804). Actions for Condition B are directed as follows:
40 min BOP Verify the following:
Backup Pressure Regulator takes control.
Indicated Pressure Regulator Setpoints are the same as before the failure.
Indicated Pressure controlling ~ 3.5 psi higher.
BOP Return Pressure Setpoint to value prior to failure by:
- a. Depress Regulator No. 1(2) pushbutton for Pressure Regulator in control.
- b. Depress Pressure Controls LOWER pushbutton to lower Regulator Pressure Setpoint.
c.
Verify Reactor Pressure returns to value prior to Regulator failure.
BOP SRO Direct an operator to go to the Relay Room In Reactor Pressure Controller Cubicle 1, Side 1, check alarm indications on Pressure Alarm Module, Unit 1102.
C.2 Booth Operator role play: Acting as the individual sent to the relay room to investigate the pressure regulator, wait about 4 minutes and report that after Depressing the Lamp Test push-buttons, all (3) Alarm Module alarm lights are functional. After another 30 seconds report a Pressure Steam Discrepancy. AND Pressure Reference Error.
NUREG 1021, Rev.8, Supplement 1 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.: 2003-301 Scenario No.: 1 Event No.: 5 Page 2 of 2
Event
Description:
Respond to a Pressure Regulator fails low in accordance with 20.109.02.
Time Position Applicant's Actions or Behavior 50 min SRO/BOP Direct Disabling the failed Pressure Regulator by removing (Reactor Pressure Controller Cubicle 1, Side 3):
Regulator No 1 failed:A12 circuit card located in Unit 1304.
OR Regulator No 2 failed:A12 circuit card located in Unit 1305.
55 min SRO Inform the crew that with a Failed Pressure Regulator AND Reactor Power between 25% and 90%, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> actions are required to either:
Raise Reactor Power to > 90% (22.000.03).
OR Lower Reactor Power to < 25% (22.000.03).
This is to comply with Technical Specification Section 3.2.2, Minimum Critical Power Ratio (MCPR).
NUREG 1021, Rev.8, Supplement 1 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.: 2003-301 Scenario No.: 1 Event No.: 6 Page 1 of 2
Event
Description:
Respond to a small steam leak in the Drywell.
Time Position Applicant's Actions or Behavior 60 min SRO CT Responds to annunciator 3D81 Primary Containment Pressure High/Low Direct RO/BOP to verify Primary Containment pressure.
Direct RO to place the Mode Switch to Shutdown (SCRAM) prior to 1.68 psig and enter AOP 20.000.21 Reactor Scram.
Direct Scram Reports.
Enter EOP Sheet 1, RPV Control, & Sheet 2, Primary Containment Control, due to high drywell pressure Direct verifying ECCS Actuations and isolations using 29.ESP.01 Direct placing RHR in Torus Cooling in accordance with 23.205.
Direct Confirm Reactor Scram Direct Tripping RR Pumps Direct to Restore and keep RPV Level 173 to 214 Direct placing RHR in Torus Spray prior to Drywell pressure reaching 9 psig in accordance with 23.205.
RO Responds to annunciator 3D81 Primary Containment Pressure High/Low Compare Pri. Cont. Pressures to ensure they are consistent with the annunciator setpoint value, using multiple indications.
Place the Mode Switch to Shutdown and enter 20.000.21 Reactor Scram Executes Scram Report Performs the following actions of EOP sht. 1, RPV Control, & 2, Primary Containment Control, as directed.
Confirm Reactor Scram and all rods full in Perform verification of initiation of EECW.
Perform verification of isolation of EECW to Drywell.
Restore Cooling to CRD.
Shutdown RR Pumps.
Verify ECCS Actuations and Isolations using 29.ESP.01
NUREG 1021, Rev.8, Supplement 1 Start RHR Loop in Torus Cooling in accordance with 23.205.
Places RHR in Torus Spray in accordance with 23.205
NUREG 1021, Rev.8, Supplement 1 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.: 2003-301 Scenario No.: 1 Event No.: 6 Page 2 of 2
Event
Description:
Respond to a small steam leak in the Drywell.
Time Position Applicant's Actions or Behavior 52 min BOP Responds to annunciator 3D81 Primary Containment Pressure High/Low Executes Scram Report.
Performs the following actions of EOP sheet 1, RPV Control, & 2, Primary Containment Control, as directed.
Restore and keep RPV Level 173 to 214.
Maintain Reactor Pressure less than 1093 using bypass valves and SRVs Perform verification of initiation of EECW.
Perform verification of isolation of EECW to Drywell.
Restore Cooling to CRD.
Verify ECCS Actuations and Isolations using 29.ESP.01 Start RHR Loop in Torus Cooling in accordance with 23.205.
Places RHR in Torus Spray in accordance with 23.205 SRO Directs placing RHR in DW Spray in accordance with 23.205.
BOP Informs SRO that Div 1 (2) RHR DW Spray Otbd Iso Vlv, (E1150-F016A (B)), will not operate.
Booth operator: After the first division of RHR DW Spray isolation valve fails to open, delete the VO for the other DW Spray Isolation Valve so that Drywell sprays can be initiated on the other division of RHR.
Directs placing other Loop of RHR in DW Spray in accordance with 23.205.
- Places other loop of RHR in Drywell Spray. Before primary containment pressure reaches 0 psig, secures torus and drywell sprays.
Termination:
Torus Sprays initiated Drywell Sprays initiated (if necessary)
RPV water level and pressure stable
NUREG 1021, Rev.8, Supplement 1 Appendix D Scenario Outline Form ES-D-1 Facility: FERMI 2 Scenario No. 2 Op-Test No: 2003-301 Examiners:
Operators:
Initial Conditions: IC-11, BOL 25%, Reactor Power Division 2 RPS supplied by Alternate Transformer and B CRD pump in service.
NOTE: The Pre-job Briefing for 23.107 Section 5.6 is to be conducted by the crew prior to entering the simulator. (suggested time 30 minutes prior to beginning the scenario)
Event No.
Malf. No.
Event Type*
Event Description 1
N/A N(BOP)
Transfer feedwater from the SULC valve to single element control 2
N/A R(RO)
N(SRO)
Raise power with Control Rod withdrawal 3
MF 2469 All Seismic Event alarm 4
MF 1442 I(BOP)
RCIC spurious initiation 5
RF 1433 C(All)
Spurious Trip of Breaker 65 E E6 Local Operation 6
MF 0068 MF 2469 M(All)
Recirc B Loop Rupture (5% break)
Seismic Event alarm 6
MF 1432 C(All)
HPCI Turbine Exhaust Check Valve Failure E41-F049 6
MF 3595 RF 2315 RF2316 RF 2317 RF 2318 I(RO)
Total Scram Failure Division 1 ARI Level 2 Isolation Defeat Division 2 ARI Level 2 Isolation Defeat Division 1 ARI Pressure Isolation Defeat Division 2 ARI Pressure Isolation Defeat 6
VO 211 C
SULC Valve fail as-is (0%)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
NUREG 1021, Rev.8, Supplement 1 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.: 2003-301 Scenario No.: 2 Event No.: 1 Page 1 of 1 Event
Description:
Transfer Feedwater Control from the SULC valve to single element control Time Position Applicant's Actions or Behavior 0 min SRO Direct the Transfer of Feedwater Control from the SULC valve to single element control in accordance with 23.107 Section 5.6.
RO Monitor Reactor Water level during the feedwater evolution.
BOP Provide a short crew briefing on the evolution.
Transfer feedwater as follows:
- 1. Place or verify, Level Control Mode switch in 1 ELEM.
- a. Place C32-R616A (B), N (S) Reactor Feed Pump Controller, in AUTO for the desired Reactor Feed Pump.
- b. Adjust or verify, C32-R616A (B), N (S) Reactor Feed Pump Controller, bias is 0%.
- c. Place C32-R618, Master Feedwater Level Controller, in AUTO.
- e. Adjust the RPV water level setpoint, if required.
- f. Adjust output of C32-R620, N21-F403 RPV Startup LCV Controller, until N21-F403, RPV Startup LCV, is 100% open.
Allow time for Reactor Feed Pump Turbine North (South) speed to lower after each adjustment.
- 3. Lower RPV water level setpoint approximately 2 inches and allow RPV water level to stabilize before proceeding to the following step.
- 6. WHEN RPV water level stabilizes, slowly return RPV water level setpoint to desired RPV water level (Level 4 to Level 7).
- 10. Verify selected drain valves remain open.
NUREG 1021, Rev.8, Supplement 1
Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.: 2003-301 Scenario No.: 2 Event No.: 2 Page 1 of 1 Event
Description:
Increase power with control rods.
Time Position Applicant's Actions or Behavior 15 min SRO Conduct a (Short) Briefing on pulling rods to increase reactor power in accordance with 23.623.
Booth operator: Provide FULL OUT/COUPLING VERIFICATION sheets (23.623. Att 2 P1/2 filled out to reflect this control rod configuration.)
15 min RO Begin to withdrawal control rods to increase reactor power in accordance with 23.623:
Place rod select power in ON Select control rod to be withdrawn Position rod IAW the rod pull sheets (perform rod coupling check on rods withdrawn to position 48)
When rod movement is complete for the selected control rod, select another rod for movement or turn rod select power to OFF.
Conducts coupling check for rods withdrawn to position 48 in accordance with 23.623 Attachment 2.
BOP Monitor the plant during the power increase. Maintain the Turbine Flow Limiter 5% above Reactor power during power increase.
Booth operator: Following the withdrawal of the second or third control rod or when directed by the lead examiner step the scenario to cause the seismic event and the spurious initiation of RCIC.
NUREG 1021, Rev.8, Supplement 1 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.: 2003-301 Scenario No.: 2 Event No.: 3 Page 1 of 1 Event
Description:
Respond to a seismic event Time Position Applicant's Actions or Behavior 20 min SRO Respond to annunciator 6D69 Seismic Event/Trouble Verify plant parameters are stable.
- 1. Direct an operator to D30-K800, Active Seismic Central Recorder, to perform 23.612,"Seismic Monitoring" (RR H11-P831).
- 2. IF D30-K800, Active Seismic Central Recorder, indicates an Actual Seismic Event, ENTER 20.000.01, "Acts of Nature."
RO Verify Reactor Power Pressure and Level are stable by monitoring plant parameters for abnormal values using multiple indications when available BOP Monitor plant parameters for abnormal values using multiple indications when available Sends operator to check D30-K800, Active Seismic Central Recorder and to perform 23.612, Seismic Monitoring.
22 min Booth Operator:. Step the scenario again to clear 6D69 and respond as operator sent to check the active seismic recorder and report a reading of +.02 vertical and
+.03 horizontal. Also report that the Seismic Event trigger light is ON and the Error/Warning light is OFF. Following these reports again step the scenario causing the RCIC spurious initiation.
NUREG 1021, Rev.8, Supplement 1 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.: 2003-301 Scenario No.: 2 Event No.: 4 Page 1 of 1 Event
Description:
Respond to spurious RCIC Initiation.
Time Position Applicant's Actions or Behavior 23 min SRO Upon receipt of and1D24 RCIC SYSTEM ACTUATED, directs BOP to:
Verify Turbine Started Verify spurious initiation by checking Rx Water Level. Since automatic initiation was not valid:
Shutdown RCIC System in accordance with Section 8.1, RCIC Shutdown.
Refers to Tech Spec. 3.5.3 and declares RCIC inoperable.
Contact maintenance to investigate spurious initiation.
23 RO Verify RPV Water Level is normal and stable.
23 min BOP Verify Turbine Started Verify spurious initiation by checking Rx Water Level. Since automatic initiation was not valid:
Shutdown RCIC System in accordance with 23.206, Section 8.1, RCIC Shutdown.
Booth operator: After RCIC has been tripped per 23.206 step the scenario again to cause the trip of 4160 V ESS Bus 65 E
NUREG 1021, Rev.8, Supplement 1 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.: 2003-301 Scenario No.: 2 Event No.: 5 Page 1 of 2 Event
Description:
Respond to trip of bus 65E.
Time Position Applicant's Actions or Behavior 28 min SRO Enter AOP 20.300.65E Read override to the crew:
IF Reactor Building Steam Tunnel Temperature at 195°F.
THEN Place Reactor Mode switch in SHUTDOWN.
Direct BOP to enter the AOP and perform actions for the conditions that apply.
Based on Condition G of 20.300.65E (West CRD Pump was in service), direct the RO to perform 20.106.01 CRD Hydraulic System Failure.
BOP Enter the AOP and take actions for applicable conditions:
A.
EDG 13 starts.
Verify EDG 13 output breaker closes.
Verify the following closed:
Bus 72E Pos 2A.
Bus 72E Pos 5B.
Bus 72EC Pos 2C.
D.
RR MG Set North Cooling Fan was in service.
Verify RR MG Set Center Cooling Fan starts and dampers re-align.
RO After entering 20.106.01:
Take Actions for Condition A.CRD Pump failure.
1 Place CRD Flow Controller in MANUAL.
2 Close CRD Flow Control Valve.
3 Close CRD Pressure Control Valve.
NOTE: The RO will need to have the BOP operator close breaker 72E-3A to allow operation of the CRD pressure control valve.
4 Start Standby CRD Pump.
5 Adjust CRD flow and pressure by adjusting:
CRD Flow Control Valve to establish normal system flow (37-63 gpm).
- 6. Pressure Control Valve to establish normal drive water differential pressure (255-265 psid) and Cooling Water
NUREG 1021, Rev.8, Supplement 1 Differential Pressure (6-30 psid).Null CRD Flow Controller and place in AUTO at desired flow (37-63 gpm).
NUREG 1021, Rev.8, Supplement 1 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.: 2003-301 Scenario No.: 3 Event No.: 5 Page 2 of 2 Event
Description:
Respond to trip of bus 65E.
Time Position Applicant's Actions or Behavior Booth Operator: If requested reset the CRD hydraulic high temperature alarm using RF 1713 SRO Exit 20.106.01 BOP Continuing in 20.300.65E, for the following conditions perform actions:
Condition J. If N RR MG Set Lube Oil Pump A2 was in service.
Verify N RR MG Set Lube Oil Pump A1 starts.
Condition K. If S RR MG Set Lube Oil Pump B1 was in service.
Verify S RR MG Set Lube Oil Pump B2 starts.
Condition L Place Div 2 130VDC Batt Charger 2B-1 in OFF/RESET, then in ON.
Condition M Place Div 2 24VDC Batt Charger 2IB-1 in OFF/RESET, then in ON.
Conditions N Components de-energized.Perform Attachment 1 of 20.300.65E.
Condition O EDG 13 has capacity available. Review Attachment 2 of 20.300.65E. and restore loads as applicable.
Booth Operator: After the battery chargers have been restored and while Attachments 1 or 2 are being performed step the scenario to initiate the final transient
NUREG 1021, Rev.8, Supplement 1 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.: 2003-301 Scenario No.: 2 Event No.: 6 Page 1 of 3 Event
Description:
Respond to a seismic event and a small break LOCA with a failure to automatically scram.
Time Position Applicant's Actions or Behavior 50 min SRO Upon receipt of Annunciator 6D69 Seismic System Event/Trouble, direct RO/BOP to verify plant parameters are stable.
The Seismic Event will come in slightly before or concurrent with the small break LOCA.
Responds to annunciator 3D81 Primary Containment Pressure High/Low and 3D85 Primary Containment High Pressure Channel Trip Direct RO/BOP to verify Primary Containment pressure.
Direct RO to place the Mode Switch to Shutdown.
Direct scram reports.
Enter EOP Sheet 1, RPV Control, due to High DW pressure Direct Reactor Scram - (RO will recognize that RPS did not actuate and report this to the SRO)
Enter EOP Sheet 1A, RPV Control-ATWS, Direct ADS defeat to the BOP.
Direct performance of FSQ 1-8 to the RO.
BOP CT Execute Scram Report ADS Defeated RO CT Execute Scram Report Places Reactor Mode Switch in Shutdown Recognizes the failure to scram Runs RR Pumps to minimum speed Trips RR pumps
- Manually Initiates ARI Recognizes control Rods inserted 15 seconds to 1 minutes after initiating ARI.
SRO Enter EOP Sheet 2, Primary Containment Control, due to high drywell pressure. Direct the following:
Confirm initiation of EECW and isolation from the drywell
NUREG 1021, Rev.8, Supplement 1 Restore cooling to CRD pumps Trip RR Pumps (already tripped from FSQ steps)
Op-Test No.: 2003-301 Scenario No.: 2 Event No.: 6 Page 2 of 3 Event
Description:
Respond to a seismic event and a small break LOCA with a failure to automatically scram.
Time Position Applicant's Actions or Behavior SRO CT CT Place RHR in Torus Spray mode in accordance with 23.205, RHR Operating procedure before torus pressure reaches 9 psig.
When torus pressure is > 9 psig:
Verify drywell temperature and pressure are within the Drywell Spray Initiation Limit (DWSIL)
S/D drywell fans Initiate Drywell Sprays Direct terminating drywell and/or torus sprays before drywell and/or torus pressure reaches 0 psig.
Exits Sheet 1A and returns to Sheet 1 when all rods are reported inserted. Directs the following:
Verifying ECCS Actuations and isolations using 29.ESP.01 Restore and keep RPV Level 173 to 214 using all available systems:
- Standby Feedwater
<1093 psig.
RO Recognize that Feedwater has not realigned through the SULC Valve because Post Scram feedwater logic was not activated on the RPS failure.
HFP and RFPs will trip following control rod insertion because of HFP low suction pressure and failure of the feedwater system to realign through the SULC valve.
BOP Recognize that HPCI has not started on high drywell pressure.
NUREG 1021, Rev.8, Supplement 1 Op-Test No.: 2003-301 Scenario No.: 2 Event No.: 6 Page 3 of 3 Event
Description:
Respond to a seismic event and a small break LOCA with a failure to automatically scram.
Time Position Applicant's Actions or Behavior BOP/RO CT The following actions will be taken IAW EOP sheet 1, RPV Control and EOP sheet 2, Primary Containment control. The actions may be taken by either RO, depending on the direction given by the CRS.
Confirms initiation of EECW and isolation from the drywell -
EECW/EESW Pumps running, Correct Valve alignments Restores cooling to CRD pumps - Places bypass switch for Div 2 EECW in OVERRIDE and opens P42-F604 EECW to CRD pumps isolation valve Places RHR in Torus Spray mode in accordance with 23.205, RHR Operating procedure when directed.
CTMT spray mode select switch to MANUAL When torus pressure is > 9 psig:
S/D drywell fans when directed Unlocks and opens E1150-F028A/B RHR torus iso vlv.
Verify one at least one RHR pump running Opens E1150-F027A/B RHR Torus spray valve May open E1150-F024A/B RHR Torus Clg iso if directed.
Initiate Drywell Sprays when directed Open E1150-F016A/B DW spray inbd iso valve Open E1150-F021A/B DW spray outbd iso valve CT Terminate drywell and/or torus sprays before drywell and/or torus pressure reaches 0 psig.
Termination:
Containment Parameters improving Reactor Level and Pressure are being controlled