ML043030574
| ML043030574 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 09/20/2004 |
| From: | Pederson C Division of Reactor Safety III |
| To: | O'Connor W Detroit Edison |
| References | |
| 50-341/04-301 | |
| Download: ML043030574 (13) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility: Fermi 2 Scenario No. 1 Op-Test No: 2004-401 Examiners: Operators:
Initial Conditions: IC-18, EOL, 100% Rx. Power.
Turnover: The plant has been operating for 364 days. Reactor Power is currently 100% of rated thermal power. All rods are full out. CRD Pump B is out of service due to high vibration on the motor bearings. It will be returned to service in two days. This shift will place D2 RHR in Torus Cooling in preparation of the next shift conducting a surveillance for RCIC Testing.
NOTE: The Pre-job Briefing for placing RHR in Torus Cooling is to be conducted by the crew prior to entering the simulator. (suggested time 30 minutes prior to beginning the scenario).
Event Malf. No. Event Event No. Type* Description 1 N/A N (BOP) Place RHR in Torus Cooling N (SRO) 2 MF 1423 C (BOP) RHRSW Pump B Trip C (SRO) 3 VO1402 I (BOP) Hotwell Level Controller Primary Instrument Fails high I (SRO) 4 MF 3652 C (All) Trip of South Reactor Feedpump 5 RF 2331 I (RO) Recirc Flow Limiter A Logic Failure RF 2333 I (SRO) 6 N/A R (RO) Insert CRAM Array N (SRO) 7 MR 3571 M (All) Leak in Torus (Value = 100%, ramped over 600 sec.)
8 MF 3595 C (RO) RPS Fails to Cause a Scram 9 N/A M (All) Emergency Depressurization is required 10 MF 3385 C (BOP) E Bypass Valve Fails Closed MF 3387 W Bypass Valve Fails Closed 11 MF 0020 C (BOP) SRV E Fails to open MF 0023 SRV H Fails to open
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG 1021, Draft Revision 9 40 of 41
Appendix D Scenario Outline Form ES-D-1 Facility: Fermi 2 Scenario No. 2 Op-Test No: 2004-401 Examiners: Operators:
Initial Conditions: IC-07, BOL, Rx. Press. 350 Psig Turnover: The plant is in the process of a startup in accordance with 22.000.02. IRM Range on range 6, Rod sequence A002, RWM Step 17, Rod 18-27 at position 00-04, page 21 of 53 of the Rod Pull Sheets. The crew is to continue the startup and synchronize the generator to the grid. EDG 13 is Out of Service for a relay repair that was discovered after startup commenced. Repairs and testing will be complete prior to entering Mode 1.
NOTE: The Pre-job Briefing for placing Power Increase and Generator Synchronization is to be conducted by the crew prior to entering the simulator. (suggested time 30 minutes prior to beginning the scenario).
Event Malf. No. Event Event No. Type*
Description 1 N/A R (RO) Increase reactor power using control rods R (SRO)
N (BOP) 2 MF 1200 I (RO) IRM D Failure Upscale (value = 130)
I (SRO) 3 MF 0069 C (BOP) CRD FCV F002A fails closed C (SRO) 4 VO 0097 I (All) Fuel Pool Radiation Monitor Fails Upscale (Value = 110 mr/hr) 5 RF 1424 M (All) Loss of Offsite Power RF 1425 RF1376 6 MF 3550 C (BOP) EDG 12 Trips after starting 7 MF 0005 M (All) Steam Leak in Drywell (HPCI Stm line)
(Value: 5%, ramped over 120 sec., 5 Min. T.D. after LOOP) 8 MF 1418 C (RO) RHR Pump A Fails to start (Trips)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG 1021, Draft Revision 9 40 of 41
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2004-401 Scenario No.: 1 Event No.: 1/2 Page 1 of 1 Event
Description:
Place RHR in Torus Cooling / RHR SW Pump B Trip (Do not insert RHRSW pump trip until RHR is running in Torus Cooling)
Time Position Applicant's Actions or Behavior 0 min SRO (Short)Brief shift on placing RHR Loop in torus cooling per SOP 23.205, Sec 5.4.
Direct BOP to place a loop of RHR in torus cooling using SOP 23.205, Sec 5.4.
+7 min Respond to Annunciator 2D47 Div.II RHR Serv/H2O Pump B/D Mtr. Tripped Refer to TS 3.7.1 RHR SW System. Declares RHRSW Pump B inoperable NOTE: SRO may elect to shutdown RHR BOOTH OPERATOR ACTION: Insert V01402, Hotwell Level Controller Primary Instrument Fails high. This malfunction takes approximately 10 minutes to build in.
RO NONE BOP Place Div. II of RHR in torus cooling using SOP 23.205.
Respond to Annunciator 2D47 Div.II RHR Serv/H2O Pump B/D Mtr. Tripped
- Place CMC Switch to OFF
Verify Flow (RHRSW) between 5250 to 6500 gpm with one pump running in a loop in accordance with 23.208.
BOOTH OPERATOR ACTION: When requested to check RHRSW Bkr., wait a 3 minutes and report that the Breaker for RHRSW Pump B is tripped. (51 relay - Overcurrent) 41 of 41 NUREG-1021, Draft Revision 9
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2004-401 Scenario No.: 1 Event No.: 3 Page 1 of 1 Event
Description:
Event
Description:
Hotwell Level Controller Failure Time Position Applicant's Actions or Behavior
+17 SRO Upon receipt of annunciator 5D131 South Hotwell Level High/Low, min direct the BOP to investigate and transfer Hotwell level control system in accordance with SOP 23.107..
RO Upon receipt of annunciator 5D131 South Hotwell Level High/Low, monitor plant parameters.
BOP Respond to annunciator 5D131 South Hotwell Level High/Low
- Determine the Primary Hotwell level control instrument has failed high by comparing with other hotwell level indications.
- Observe Normal and Emergency Hotwell reliefs are open even though hotwell level is actually low.
Selects course of action to transfer Hotwell level control system in accordance with 23.107, sec. 6.11 when directed by SRO.
Booth Operator:
Reports: Setpoint at ~60 and normal air pressure to controller.
(N61) RF1705 switches to B/U hotwell level instrument. (ON /
ACCEPT / START) 41 of 41 NUREG-1021, Draft Revision 9
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2004-401 Scenario No.: 1 Event No.: 4/5/6 Page 1 of 1 Event
Description:
Event
Description:
Hotwell Level Controller Failure Time Position Applicant's Actions or Behavior
+30 SRO Enters AOP 20.107.01 LOSS OF FEEDWATER, min
- directs RO to insert CRAM Array
When reported that A RR MG failed to runback, direct manually running MG back to 40% IAW 20.107.01.
When a loss of feedwater heating is detected, Direct BOP and RO to Reduce Recirculation Flow and Insert Control Rods using the CRAM Array, in accordance with AOP 20.107.02 LOSS OF FEEDWATER HEATING.
Determines that FW Temperature is decreasing.
Notify Chemistry that power changed greater than 15% in a one-hour period.
After inserting the CRAM array, verify power <65%
Direct shutdown of standby feedwater RO Ensure RR Runback and Insert CRAM Array to < 65%RTP when RFP Trips at SRO direction in accordance with AOP 20.107.01.
(When noticed that A RR MG did not runback, manually run back to 40%)
After inserting the CRAM array, verify power <65%.
BOP Start Standby Feedwater and inject at 1200 gpm.
When directed shutdown standby feedwater.
41 of 41 NUREG-1021, Draft Revision 9
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2004-401 Scenario No.: 1 Event No.: 7/8/9/10/11 Page 1 of 2 Event
Description:
Event
Description:
Hotwell Level Controller Failure Time Position Applicant's Actions or Behavior
+40 SRO Upon receipt of Annunciator 2D82 RB Torus Sump Level Hi-Hi/
min Low-Low, Enters EOP Sheet 5 on High Sump Level, Upon receipt of Annunciator 7D71 Torus Water Level Trouble, enters EOP Sheet 2 for Low Torus Level.
Enters EOP Sheet 1, RPV Control and order the Mode Switch placed in SHUTDOWN Upon communication of ATWS, enter EOP Sheet 1A, RPV Control
- ATWS Directs ATWS actions until rods are inserted using ARI.
Inhibit ADS Defeat MSIV isolations and bypass drywell pneumatics.
Trip recirc pumps Confirm ARI Verifies Reactor shutdown and Enters EOP Sheet 1, RPV Control
- Directs BOP to open 5 ADS SRVs and Emergency Depressurize the Reactor in accordance with EOP sheet 3, Emergency Depressurization, at or before Torus Level of -38 inches.
Upon receiving report from BOP of E & H SRVs not opening, directs BOP to open two additional SRVs.
Directs maintaining water level 173-214.
May direct placing torus cooling in service based on high torus temperature.
41 of 41 NUREG-1021, Draft Revision 9
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2004-401 Scenario No.: 1 Event No.: 7/8/9/10/11 Page 2 of 2 Event
Description:
Event
Description:
Hotwell Level Controller Failure Time Position Applicant's Actions or Behavior RO *At or before a Torus Water Level of -38, Scrams the reactor as directed
- Informs SRO that Mode Switch did not cause a Scram. Performs actions of EOP SH. 1A, RPV Control - ATWS, and:
Confirms RR Pumps runback Trips the Recirc Pumps Initiates ARI Reports all rods full in when ARI scrams the rods.
BOP Upon receipt of Annunciator 2D82 RB Torus Sump Level Hi-Hi/
Low-Low, investigates cause of alarm.
Upon receipt of Annunciator 7D71 Torus Water Level Trouble, investigates the cause for the alarm Upon direction performs the actions of EOP SH.1, RPV Control:
Inhibits ADS Confirms isolations occur (29.ESP.01)
Bypasses pneumatic interlocks and restores PC Pneumatics Orders bypassing MSIV L1 logic and high rad interlocks.
Upon receipt of Annunciator 7D71 Torus Water Level Trouble, investigates the cause for the alarm
- Opens 5 ADS SRVs and Emergency Depressurize the Reactor When directed. Reports that 2 SRVs will not open E & H Opens 2 additional SRVs to complete Emergency Depressurization.
Maintains RPV level as directed.
Places torus cooling in service in accordance with SOP 23.205 as directed 41 of 41 NUREG-1021, Draft Revision 9
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2004-401 Scenario No.: 2 Event No.: 1 Page 1 of 1 Event
Description:
Increase Reactor Power using Control Rods.
Time Position Applicants Actions or Behavior 0 min SRO (Short)Brief shift on (Review SOP 23.623 Sec 7.0), in preparation for Control Rod Withdrawal.
NOTE: SURROGATE STA will fill out heatup data sheets.
RO Review SOP 23.623 Sec 7.0,, in preparation for Control Rod Withdrawal.
Begin to withdraw control rods to increase power in accordance with SOP 23.623.
BOP Monitor plant parameters during power increase.
41 of 41 NUREG-1021, Draft Revision 9
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2004-401 Scenario No.: 2 Event No.: 2 Page 1 of 1 Event
Description:
IRM D Failure Upscale Time Position Applicants Actions or Behavior
+10 SRO Upon receipt of Annunciator 3D60 IRM CH B/F/D/H Upscale min Trip/Inop & 3D63 IRM UPSCALE, direct the RO to Stop Rod Movement.
When IRM cannot be reset, instruct the RO to bypass the IRM in accordance with 23.603 Intermediate Range Monitoring System.
Refer to Tech Spec 3.3.1.1, Reactor Protection System Instrumentation and TRM 3.3.2.1, Control Rod Block Instrumentation.
Upon receipt of Annunciator 3D74 Trip Actuators B1/B2 Tripped, direct the RO to reset the half scram in accordance with 23.610 Reactor Protection System (RPS), after bypassing IRM D.
Continue Startup upon reset of half scram.
RO Upon receipt of Annunciator 3D63 IRM UPSCALE, Stop Rod Movement and investigate the cause.
When IRM cannot be reset, request to bypass the IRM in accordance with 23.603 Intermediate Range Monitoring System.
Upon receipt of Annunciator 3D74 Trip Actuators B1/B2 Tripped, reset the half scram in accordance with 23.610 Reactor Protection System (RPS), after bypassing IRM D.
Continue startup upon direction from SRO.
BOP Assist in determining cause of IRM D upscale.
BOOTH OPERATOR ACTION When requested, wait approximately 3 minutes and report IRM D is upscale in relay room and no other IRMs indicate a problem 41 of 41 NUREG-1021, Draft Revision 9
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2004-401 Scenario No.: 2 Event No.: 3 Page 1 of 1 Event
Description:
CRD Flow Control Valve Failure (Closed)
Time Position Applicants Actions or Behavior
+20 SRO Upon notification of CRD FCV A Failure, enters AOP 20.106.03 min CRD FCV Failure, directs RO to perform actions associated with the procedure.
RO RO Notices no rod movement when withdrawing control rods and verifies CRD System Indicators on H11-P603 are below their normal ranges.
Notifies SRO of conditions Performs the actions of AOP 20.106.03
- 1. Places FCV to manual and tries to restore system flow.
BOOTH OPERATOR ACTION: When requested to place the standby CRD FCV in service, insert the following:
- RF0051 CRD FCVA Mode - Manual
- RF0053 CRD FCVB Mode - Auto
- RF0058 CRD FCVA Isol. Vlv. - 0%
- RF0059 CRD FDVB Isol. Vlv. - 100% (900 sec Ramp)
BOP Monitors plant parameters.
41 of 41 NUREG-1021, Draft Revision 9
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2004-401 Scenario No.: 2 Event No.: 4 Page 1 of 1 Event
Description:
Description:
Fuel Pool Rad Monitor Failure (Upscale)
Time Position Applicants Actions or Behavior
+30 SRO Upon receipt of annunciators 3D31 DIV I/II FP Vent Exh. Radn min Monitor Upscale & 3D35 DIV I/II FP Vent Exh. Radn Monitor Upscale Trip, direct RO and BOP to perform associated actions Refer to TS 3.3.6.2 Isolation Instrumentation 3.3.7.1 Control Room Emergency Filtration System TRM 3.3.6.2 Isolation Instrumentation 3.3.7.1 Control Room Emergency Filtration System NOTE: SRO may enter AOP 20.000.11 Loss of Secondary Containment Integrity and EOP sheet 5 Secondary Containment prior to discovering the failed instrument caused the transient.
RO Responds to 3D31 DIV I/II FP Vent Exh. Radn Monitor Upscale &
3D35 DIV I/II FP Vent Exh. Radn Monitor Upscale Trip.
BOP Checks (D11-K609 A) Fuel Pool East Radiation monitor and discovers it is pegged high.
Monitors Plant Parameters
- 1. Verifies CCHVAC shifts to RECIRC. Mode
- 3. SGTS initiates 41 of 41 NUREG-1021, Draft Revision 9
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2004-401 Scenario No.: 2 Event No.: 5/6/7/8 Page 1 of 2 Event
Description:
Loss of Offsite Power; Steamleak in Drywell; Trip of EDG 12 during startup; RHR Pump A Failure to Start.
Time Position Applicants Actions or Behavior
+40 SRO Enters AOP 20.300.03 Loss of Off-Site Power, and directs min implementation/actions.
Enters EOP sheet 1 directs actions for level and pressure of RPV.
- 2. Directs maintaining Reactor Pressure less than 1093 using bypass valves and SRVs.
- 4. Direct RO to place RHR in Torus Spray prior to Drywell pressure reaching 9 psig in accordance with 23.205.
BOP Performs actions of AOP 20.300.03 Loss of Off-Site Power
- Assess status of EDGs (12 not running)
- Starts CTG 11-1
Reports EDG 12 has tripped, (Annunciator 9D60) Dispatches an operator to investigate EDG fail to start at RHR complex.
Identify High Drywell Pressure.
May assist in stabilizing level and pressure or addressing containment parameters.
41 of 41 NUREG-1021, Draft Revision 9
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2004-401 Scenario No.: 2 Event No.: 5/6/7/8 Page 1 of 2 Event
Description:
Loss of Offsite Power; Steamleak in Drywell; Trip of EDG 12 during startup; RHR Pump A Failure to Start.
RO Enters EOP 20.000.21 Reactor SCRAM/EOP Sh.1 RPV Control
- 1. Places the mode switch to shutdown, and reports all rods full in.
- 2. Verifies reactor power decreasing
- 3. Verifies RR Pumps Runback to minimum.
- 6. Stabilize reactor pressure, if possible.
- 7. Insert SRM/IRM Detectors (If power available)
- 8. Verify Isolations have occurred.
Performs actions of EOP Sh.2 Primary Containment Control as directed.
- 1. Perform verification of initiation of EECW.
- 2. Perform verification of isolation of EECW to Drywell.
- 3. Restore Cooling to CRD in accordance with 23.127.
- 4. Shutdown RR Pumps in accordance with 23.138.01.
- 5. Verify ECCS Actuations and Isolations using 29ESP.01
- 6. Start RHR Loop in Torus Cooling in accordance with 23.205.
Identify that RHR Pump A did not and will not start.
(Annunciator 1D23)
- Spray Drywell with D RHR Pump and terminate before pressure drops to 0 psig.
41 of 41 NUREG-1021, Draft Revision 9