ML102230008
| ML102230008 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 07/07/2010 |
| From: | Kelly Clayton Operations Branch IV |
| To: | Luminant Generation Co |
| References | |
| 50-445/10-302, 50-446/10-302, CP-2010-07, ES-D-1 50-445/10-302, 50-446/10-302 | |
| Download: ML102230008 (6) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility: CPNPP 1 & 2 Scenario No.: 1 Op Test No.: July 2010 NRC Examiners: Operators:
Initial Conditions:
- Train A Emergency Diesel Generator is OOS for governor repair.
Turnover: Maintain steady-state 100% power conditions.
Critical Tasks:
- Trip Reactor Coolant Pumps Upon Loss of Subcooling.
- Manually Initiate Containment Isolation Phase A Upon Failure to Automatically Actuate.
- Maintain Core Cooling During a Loss of Cold Leg Recirculation.
Event No. Malf. No. Event Type* Event Description 1 RP06A I (RO, SRO) Loop 1 N-16 Channel I (1-JI-411A/B) Fails High.
+5 min TS (SRO) 2 RX18 I (BOP, SRO) Feed Header Pressure Transmitter (PT-508) Fails High.
+10 min 3 CH03 C (BOP, SRO) Neutron Detector Well Fan (FN-09) Motor Overcurrent.
+15 min 4 RX05B I (RO, SRO) Pressurizer Level Channel (LT-460) Fails Low.
+25 min TS (SRO) 5 RC17A M (RO, BOP, SRO) Large Break Loss of Coolant Accident (60 second ramp).
+30 min 6 RP09A C (BOP) Phase A Containment Isolation Trains A and B Fail to Automatically
+35 min RP09B Actuate.
7 RH01B C (BOP) Residual Heat Removal Pump (1-02) Trip Upon SI Sequencer
+35 min Start.
8 RHR15 C (RO) Containment Sump to Residual Heat Removal Pump (1-01) Suction
+50 min Isolation Valve (1-8811A) Will Not Open.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications CPNPP July 2010 NRC Sim Scenario #1 Rev c.doc
Scenario Event Description NRC Scenario #1 SCENARIO
SUMMARY
NRC #1 The crew will assume the watch and maintain steady-state conditions per IPO-003A, Power Operations. Train A Emergency Diesel Generator is out of service for governor repair.
The first event is a high failure of Loop 1 N-16 Channel I. Operator actions are per ABN-704, Tc/N-16 Instrumentation Malfunction, and include placing Rod Control in Manual and identifying the failed channel. The SRO will refer to Technical Specifications.
Once Technical Specifications are addressed, a Feedwater Header Pressure Transmitter fails high causing Main Feed Pump speed to decrease resulting in a drop in Feedwater flow. Operator actions are per ABN-709, Steam Line Pressure, Steam Header Pressure, Turbine 1st Stage Pressure, and Feed Header Pressure Instrument Malfunction, Section 5.0, and require manual Feedwater Header pressure control until repairs are made.
When Feedwater Header pressure is stable, the running Neutron Detector Well Fan will trip. Actions are per ALM-0031A, 1-ALB-3A, Window 2.1 - CNTMT FN MASTER TRIP. The BOP will start the standby Neutron Detector Well Fan per SOP-801A, Containment Ventilation System, and monitor for proper operation.
The next event is a Pressurizer Level instrument failure. Actions are per ABN-706, Pressurizer Level Instrumentation Malfunction. The RO will take manual control of Pressurizer level or Charging flow to maintain Pressurizer Level on program. When the failed instrument is identified, an alternate controlling channel is selected and Charging flow and Pressurizer Level control will be returned to Automatic.
Letdown flow will be restored per the Job Aid. The SRO will refer to Technical Specifications.
When Letdown flow is restored, a Large Break Loss of Coolant Accident develops inside Containment resulting in generation of signals for Safety Injection, Containment Isolation Phase A and Phase B.
Train B Residual Heat Removal Pump will trip upon pump start and the Train A Containment Sump to RHR Pump Suction Isolation Valve will NOT open. Reactor Coolant Pumps must be manually tripped due to a loss of subcooling and Containment Isolation Phase A must be manually initiated.
The crew enters EOP-0.0A, Reactor Trip or Safety Injection and at Step 14, transitions to EOP-1.0A, Loss of Reactor or Secondary Coolant. While in EOP-1.0A, the crew should recognize and transition to ECA-1.1A, Loss of Emergency Coolant Recirculation, at Step 11. When in ECA-1.1A, the crew will secure Containment Spray Pumps as required per Containment pressure conditions.
The scenario is terminated when Containment Spray flow is reduced in ECA-1.1A or when the conditions of FRZ-0.1A, Response to High Containment Pressure, have been met.
Risk Significance:
- Risk important components out of service: Train A Emergency Diesel Generator
- Risk significant core damage sequence: LBLOCA with Loss of Coolant Recirculation
- Risk significant operator actions: Manually Trip Reactor Coolant Pumps Manually Initiate Containment Isolation Manually Secure Containment Spray Pumps CPNPP July 2010 NRC Sim Scenario #1 Rev c.doc
Appendix D Scenario Outline Form ES-D-1 Facility: CPNPP 1 & 2 Scenario No.: 2 Op Test No.: July 2010 NRC Examiners: Operators:
Initial Conditions:
- Train A Emergency Diesel Generator is OOS for governor repair.
Turnover: Maintaining 72% power per Load Controller direction. Rod Control in AUTO.
Critical Tasks:
- Emergency Borate Required for Two Stuck Control Rods.
- Perform Actions to Identify and Isolate Faulted Steam Generator.
- Perform Actions to Initiate Feed Isolation to Faulted Steam Generator.
Event No. Malf. No. Event Type* Event Description 1 RX09A I (RO, BOP, SRO) Main Turbine 1st Stage Pressure Transmitter (PT-505) Fails Low.
+10 min TS (SRO) 2 CC02A C (BOP, SRO) Train A Component Cooling Water Pump (1-01) Trip.
+20 min CC03A TS (SRO) Train B Component Cooling Water Pump (1-02) Auto Start Failure.
3 RX08A I (RO, SRO) Pressurizer Pressure Channel (PT-455) Fails Low.
+30 min TS (SRO) 4 RX04A I (BOP, SRO) Steam Generator (1-01) Level Channel (LT-551) Fails High.
+40 min TS (SRO) 5 MS03A M (RO, BOP, SRO) Steam Generator (1-01) Steam Line Break Outside Containment
+45 min Before Main Steam Isolation Valve (300 second ramp).
6 RD04K6 C (RO) Two Control Rods Fail to Insert Upon Reactor Trip.
+45 min RD04K8 Emergency Boration Required.
7 SI04D C (BOP) Safety Injection Pump (1-02) Fails to Start.
+55 min 8 FW38 C (BOP) Feed Line Isolation Valves (HV-2134 to HV-2137) Fail to Close.
+55 min A/B/C/D
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications CPNPP July 2010 NRC Sim Scenario #2 Rev d.doc
Scenario Event Description NRC Scenario #2 SCENARIO
SUMMARY
NRC #2 The crew will assume the watch at 72% power with no scheduled activities per IPO-003A, Power Operations. The Grid Controller has requested that power remain at this level due to transmission line overload until further notice. Train A Emergency Diesel Generator is out of service for governor repair.
The first event is a Main Turbine 1st Stage Pressure Transmitter failure. The crew responds per ABN-709, Steam Line Pressure, Steam Header Pressure, Turbine 1st-Stage Pressure and Feed Header Pressure Instrument Malfunction, Section 4.0. Several actions are required on the part of the RO and BOP to stabilize plant conditions. The SRO will refer to Technical Specifications.
When plant conditions are stable, the Train A Component Cooling Water (CCW) Pump will trip and the Train B CCW Pump will fail to automatically start. The crew will respond per ABN-502, Component Cooling Water System Malfunctions, Section 2.0, and manually start Train B CCW Pump and perform equipment adjustments as required by procedure. The SRO will refer to Technical Specifications.
When ABN-502 actions are complete, a Pressurizer Pressure Channel will fail low. Response is per ABN-705, Pressurizer Pressure Malfunction, Section 2.0, to ensure Pressurizer Heaters are controlled and Power Operated Relief Valves remain closed. The SRO will refer to Technical Specifications.
Once systems are stable, a Steam Generator Level Transmitter fails high. ABN-710, Steam Generator Level Instrumentation Malfunction is referenced and the BOP takes Manual control of the Feedwater Control Valve to prevent a Unit trip on low Steam Generator level. Once identified, an Alternate Channel is selected and Automatic control restored. The SRO will refer to Technical Specifications.
When Technical Specifications have been addressed, a Main Steam Line Break Outside Containment before the Main Steam Isolation Valve will ramp in over five minutes on Steam Generator 1-01. With lowering Pressurizer pressure and Reactor Coolant System temperature, the Unit Supervisor will direct a Reactor and Turbine Trip.
The crew will enter EOP-0.0A, Reactor Trip or Safety Injection, and then transition to EOP-2.0A, Faulted Steam Generator Isolation, at Step 12. While performing the actions of EOP-0.0A, the RO will be required to manually initiate an Emergency Boration due to two stuck Control Rods and the BOP will start a Safety Injection Pump and manually close the Feed Line Isolation Valves while in Attachment 2.
Once the faulted Steam Generator is isolated, the Unit Supervisor will transition to EOS-1.1A, Safety Injection Termination. The scenario is terminated after EOS-1.1A, Safety Injection Termination, is entered and the actions to secure Safety Injection flow are performed.
Risk Significance:
- Risk important components out of service: Train A Emergency Diesel Generator
- Failure of risk important system prior to trip: Train A Component Cooling Water System
- Risk significant core damage sequence: Main Steam Line Break Outside Containment
- Risk significant operator actions: Emergency Borate Due to Two Stuck Rods Isolate Faulted Steam Generator Isolate Feedwater to Faulted SG CPNPP July 2010 NRC Sim Scenario #2 Rev d.doc
Appendix D Scenario Outline Form ES-D-1 Facility: CPNPP 1 & 2 Scenario No.: 3 Op Test No.: July 2010 NRC (Spare)
Examiners: Operators:
Initial Conditions: * ~1X10-8 amps BOL - RCS Boron is 1545 ppm by Chemistry sample.
- Steam Dump System in service for RCS Temperature Control.
Turnover: Raise Power to 2% in preparation for plant startup to 100% power.
Critical Tasks:
- Restore Feedwater Flow to any Affected Steam Generator.
- Determine Inadvertent Safety Injection & Secure Charging Prior to Pressurizer Overfill.
- Determine Loss of Coolant Accident in Progress and Reinitiate Safety Injection.
Event No. Malf. No. Event Type* Event Description 1 R (RO) Raise Reactor power to 2%.
+20 min N (BOP, SRO) 2 FW24A C (BOP) Motor Driven Auxiliary Feedwater Pump (1-01) Trip.
+30 min TS (SRO) 3 RP17D TS (SRO) Containment Pressure Transmitter (PT-937) Fails High.
+35 min 4 MS13B I (BOP, SRO) Atmospheric Relief Valve (1-02) Fails Open due to Steam Pressure
+40 min Transmitter (PT-2326) Failure.
5 RP14A M (RO, BOP, SRO) Spurious Train A Safety Injection Actuation Signal.
+45 min 6 CV01B C (RO) Centrifugal Charging Pump (1-01) Trip.
+45 min CV01E Centrifugal Charging Pump (1-02) SI Sequencer Start Failure.
7 RC17C C (RO) Loss of Coolant Accident at 1700 gpm Following Isolation of High
+60 min Head Injection.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications CPNPP July 2010 NRC Sim Scenario #3 Rev b.doc
Scenario Event Description NRC Scenario #3 SCENARIO
SUMMARY
NRC #3 The crew will assume the watch with a Plant Startup in progress and will continue raising power to approximately 2% per IPO-002A, Plant Startup from Hot Standby.
When conditions are stable, Motor Driven Auxiliary Feedwater Pump 1-01 will trip. The crew will refer to ABN-305, Auxiliary Feedwater System Malfunction, Section 3.0, and determine that Steam Generator levels are slowly decreasing and start the Turbine Driven Auxiliary Feedwater Pump. The SRO will refer to Technical Specifications.
When the Steam Generator levels are stable, a Containment Pressure Transmitter will fail high. Crew response will be per ALM-0022A, 1-ALB-2B, Window 3.10, CNTMT 1 OF 4 PRESS HI-3, and include verifying that only one channel is affected. The SRO will refer to Technical Specifications.
When Technical Specifications have been referenced, a Steam Generator Atmospheric Relief Valve (ARV) fails open due to a Main Steam Pressure Transmitter failure. This event is recognized by a Reactor power increase and the ARV Controller indicating 100% demand. The BOP will place the affected Controller in Manual and close the ARV. ABN-709, Steam Line Pressure, Steam Header Pressure, Turbine 1st-Stage Pressure, and Feed Header Pressure Instrument Malfunction, Section 2.0, will be referenced.
The major event begins with a spurious Train A Safety Injection Actuation Signal. The crew will enter EOP-0.0A, Reactor Trip or Safety Injection, and perform immediate actions including actuation of both Trains of Safety Injection.
When it is determined that a spurious Safety Injection actuation has occurred, the crew will transition to EOS-1.1A, Safety Injection Termination. During the event the Train A Centrifugal Charging Pump will trip and the Train B Centrifugal Charging Pump will fail to auto start on the Safety Injection Sequencer.
When the high head injection alignment is secured in EOS-1.1A, a Small Break Loss of Coolant Accident will occur. This will require re-initiation of Safety Injection flow per the Foldout Page Criteria of EOS-1.1A.
Event termination will occur when the crew has reinitiated Safety Injection and transitioned to EOP-1.0A, Loss of Reactor or Secondary Coolant.
Risk Significance:
- Failure of risk important system prior to trip: Loss of MDAFW Pump SG Atmospheric Relief Valve Failure
- Risk significant operator actions: Initiate Charging Flow upon Safety Injection Secure Charging Prior To Pressurizer Overfill Reinitiate Safety Injection Flow CPNPP July 2010 NRC Sim Scenario #3 Rev b.doc