ML100880242

2009-09-Draft Scenario

ML100880242
Person / Time
Site:	Cooper
Issue date:	09/21/2009
From:	Garchow S NRC Region 4
To:	Nebraska Public Power District (NPPD)
References
50-298/09-301 50-298/09-301
Download: ML100880242 (92)

Text

Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Lesson Rev. 00 Long, MSIV Closure, CR Drop, Fuel Failure/Scram/Failure of

Title:

No.:

SDIV, Gp 6 Failure Lesson#: SKL0124827 SAP BET # 36607 Prerequisites: None Duration (Hours): N/A Appendix D Scenario Outline Form ES-D-1 Facility: Cooper Nuclear Station Scenario No.: NRC 1 Op-Test No.:

Examiners: Operators:

Initial Conditions: The plant is operating at 8% power with a startup in progress.

Turnover: Raise power and put the main turbine on line. Rod 22-27 has been inserted from 48 to 46 to return temperatures back into the normal band.

Event No. Malf. No. Event Event Type* Description 1 N/A R Perform step 38 of the Rod Package 2 2 C Stuck Control Rod 3 3 I A Narrow Range Level Instrument fails downscale 4 N/A N Roll the Turbine 5 5 C TG Rotor Position (Long) 6 6 C Single MSIV Inadvertent Closure 7 7 C Rod Drop Accident Fuel Failure/Scram/Failure of Scram discharge volume drain valve 8 8 M to close.

9 9 C Group 6 isolation failure Page 1 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 Scenario Description The plant is operating at approximately 8% power with the mode switch in RUN.

After the crew takes the watch the RO withdrawals control rods to raise power. When the RO attempts to withdraws control rod 14-23 it does not move. The crew enters 2.4CRD IAC is contacted to correct the problem and the CRS addresses TS for the inop control rod.

After the TS call A Narrow Range Level Instrument fails downscale. The CRS addresses the TS for the INOP instrument.

Crew rolls the turbine. As the Turbine is accelerating Main Turbine Rotor Expansion Governor End alarm occurs. Indications are a rotor LONG condition exists. The crew enters 2.4TURB and eventually takes the Turbine offline to allow maintenance to investigate.

After the turbine is tripped a single MSIV inadvertently closes. The crew investigates per 2.4MSIV. When the actions of 2.4MSIV are complete, a control Rod which was uncoupled from its drive and its drive withdrawn drops to the level of its drive causing a power excursion. The excursion results in fuel failure that increases steadily until the radiation levels cause the crew to SCRAM the reactor.

When radiation levels increase the crew scrams the reactor. All rods insert on the scram but the North Scram Discharge volume drain valve fails to close. This results in a reactor to reactor building steam leak. The crew enters EOP-5A. A group 6 isolation fails to occur and must be manually actuated by the crew.

If the crew takes immediate action the scram may be reset and ED due to high area radiation or release rate approaching GE will not occur. If the crew does not reset the scram then the crew will eventually be required to ED due to Max Safe radiation in two areas or release rate approaching a GE.

The scenario may be terminated when the reactor is depressurized or the scram is reset and reactor pressure and level are being controlled.

Page 2 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 Simulator Setup Malfunction Description Delay Ramp Event Value Final TU01J Main Turbine Bearing High Temp. 6 min. 5 0 50 MSIV Disc Separates form Stem MS06B 6 False True MSL-B AO RD122227 Control Rod Stuck 22-27 Active True True RD132227 Control Rod Uncoupled 22-27 Active True True CR03 Gross Fuel Cladding Failure (NRV) 8 min. 7 0 30 SDV Drain/Vent Valve Failure CRD-RD01A Active 100 100 CV-33 RP07 Group 6 High Rad Isolation Failure Active True True RD121423 Control Rod Stuck 14-23 3 False True N186 CRD 22-27 Temperature Active 183 Remotes Description Delay Ramp Event Value Final RD17 South SDV Drain Valve Active Gag- Gag-open open Overrides Description Delay Ramp Event Value Final

-10 to +10 in Torus Level Indicator 01M01 5 min. 2 10 Narrow Range Scram Discharge VLM. Isol Valve 03DS046 Active ON ON 3-34 OP Scram Discharge VLM. Isol Valve 03DS045 Active OFF OFF 3-34 CL Event Event Action Command 7 Dmf RD122227 Cause Gross clad failure on rod drop Cause Rx Build Vent Rad Monitors to begin rising on the Rx 14 ZLORPSDS1A==0 SCRAM Panel Set-up

1. 30-39 Step 38 page 20 of 22 in Startup to IC18 100% BOL.

2. 22-27 Gets stuck at position 12 and its drive is pulled to 46 and substitute position 48 for it. Reinitialize the RWM and clear alarms.

3. Insert enough rods to lower power to approximately 8%.

4. Discharge Tags on non-running Condensate and Booster Pumps.

Page 3 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 Op-Test No.: Scenario No.: NRC 1 Event No.: 1 Page 1 of 2 Event

Description:

Perform step 38 of the Rod Package When to initiate: When the Crew has assumed the watch and at the direction of the lead examiner.

Time Position Applicants Action or Behavior Will brief the crew on the power change and will assign responsibilities. He will CRS take the position of the Reactivity Manager.

Asks the BOP to second check the pulling of the rods.

RO The Examiner will act as the second checker.

RO Observes the CRD Parameters and may make adjustments to drive water d/p.

RO Checks the position of the other rods and verifies where in the pull sheet he is.

RO Selects the next rod to pull and pulls it to the assigned position in the pull sheet.

Selects the rods to pull and pulls it to the assigned position in the pull sheet until RO Turbine Bypass Valves are approximately 50% open.

Monitors the balance of plant and indicates when the RO has opened the bypass BOP valves enough.

BOP Updates the crew when the bypass valves are 50% open.

RO Stops pulling rods.

END OF EVENT Notes Page 4 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 Page 5 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 Op-Test No.: Scenario No.: NRC 1 Event No.: 2 Page 1 of 2 Event

Description:

Stuck Control Rod When to initiate: As the RO pulls rods he will encounter this event when he attempts to pull Rod Time Position Applicants Action or Behavior RO Attempts to withdraw Control Rod 14-23 sees that it will not move off of 00.

RO Attempts to increase drive water d/p and tries to pull the rod again.

RO Updates the Crew that Rod 14-23 will not move and that is an entry into 2.4CRD.

CRS Enters 2.4CRD and assigns its actions to the RO.

Contacts the WCC and asks for assistance in investigating the problem with the CRS rod.

Role As the WCC, respond to the request and inform the CRS that some Play mechanics and I&C techs will go out to investigate the problem.

Contacts the Building Station Operator and request that he check the HCU for RO problems As the Building SO, respond to the request and tell them that you will be Role right there.

Play Wait 2 minutes and report that you see nothing wrong with 14-23 CRS Contacts the WCC with the information and request an IAC investigate 14-23.

As the WCC, respond to the request and tell them that you will get it started.

Role Play CRS Addresses Tech Specs and determines that the rod was is inoperable.

END OF EVENT Notes Page 6 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 Page 7 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 Op-Test No.: Scenario No.: NRC 1 Event No.: 3 Page 1 of 1 Event

Description:

A Narrow Range Level Instrument fails downscale When to initiate: At the direction of the lead examiner.

Time Position Applicants Action or Behavior Identify increasing RFPs speed and disparity in RPV narrow-range level RO instruments or receipt of Annun 9-5-2/ G-1 Reactor Low Water Level CRS/BOP/RO Identify entry to 24RXLVL and 4.4.1 CRS Assign 2.4RXLVL subsequent actions and 4.4.1 to BOP BOP Announces SCRAM actions from 2.RXLVL RO Accepts SCRAM actions from 2.4RXLVL Compare narrow ranges to NBI-LI-92, STEAM NOZZLE LEVEL, to determine BOP actual level. Determines that B Narrow range level instrument is correct.

Notify WCC to inform FRED and system engineer, and I& C to investigate A CRS Narrow Range Level Instrument RO Monitors power pressure and level Evaluates the failure against Tech Spec and determines that TS 3.3.2.2 CRS applies.

END OF EVENT Notes Page 8 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 Op-Test No.: Scenario No.: NRC 1 Event No.: 4 Page 1 of 1 Event

Description:

Roll the Turbine When the actions of the stuck rod are addressed and the CRS has addressed When to initiate:

Tech Specs. And at the direction of the lead examiner contact CRS that a new Rod Sequence package is being developed and to continue the Main Turbine Start-up.

Time Position Applicants Action or Behavior CRS Directs the BOP to roll the Main Turbine in accordance with procedure.

BOP Checks that bypass valve opening is 50% and that the prerequisites are met.

BOP Using Procedure 2.2.77 Attachment 1 Rolls the Main Turbine.

RO Monitors the Reactor as the Turbine is rolled.

END OF EVENT Notes Page 9 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 Op-Test No.: Scenario No.: NRC 1 Event No.: 5 Page 1 of 2 Event

Description:

Main Turbine Rotor Expansion Governor End alarm occurs.

Indications are a rotor LONG condition exists.

When to initiate: While the Turbine is being rolled up this event will start.

Time Position Applicants Action or Behavior As the Main Turbine is being rolled the rotor begins to heat up abnormally causing BOP Main Turbine Rotor Expansion Governor End alarm occurs. Indications are a rotor LONG condition exists.

Updates the Crew Main Turbine Rotor Expansion Governor End, indications are a BOP rotor LONG condition exists and that is an entry condition into 2.4TURB.

Enters 2.4TURB and assigns the BOP the rotor position as a critical parameter to CRS monitor.

Monitors the rotor position updates the crew that the Turbine should be removed BOP from service.

CRS Directs the BOP to trip the Main turbine.

BOP Depresses both Turbine Trip pushbuttons on Panel B.

Directs the BOP to monitor for vibrations as well as temperature as the turbine CRS speed slows down.

ROLE Once the turbine has been tripped then modify malfunction TU06B to 50% over 20 PLAY minutes.

Contacts the WCC to request maintenance to investigate the problem with the CRS rotor conditions.

END OF EVENT Notes Page 10 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 Page 11 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 Op-Test No.: Scenario No.: NRC Event No.: 6 Page 1 of 2 Event

Description:

Single MSIV Inadvertent Closure When to initiate: When the Main Turbine actions are completed and at the direction of the lead examiner.

Time Position Applicants Action or Behavior RO Notes a pressure and power spike on the RPV and updates the crew.

CRS Directs the BOP to investigate the problem.

Notes that the B Main Steam Line flow is 0 and the other three lines are above BOP normal.

Checks the MSIV positions and notes that all of them indicate open, however BOP recommends that 2.4MSIV be entered.

CRS Enters 2.4MSIV and assigns the abnormal to the BOP operator.

BOP Enters 2.4MSIV and performs the required actions.

Updates the crew that the most probable cause is a disc separation on one of the BOP MSIVs.

CRS Contacts WCC and request assistance with the problem.

Role As the WCC, respond to the request and tell the CRS that a team will be Play formed and that a work order will be initiated.

END OF EVENT Notes Page 12 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 Page 13 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 Op-Test No.: Scenario No.: NRC 1 Event No.: 7 Page 1 of 2 Event

Description:

Rod Drop Accident When to initiate: When the crew has addressed the closure of the Main Steam Line and at the direction of the lead examiner Time Position Applicants Action or Behavior RO Notes spike in power again but no corresponding spike in pressure this time.

BOP Checks MSIVs and steam flow.

BOP Notes that rad levels are coming up in the DW.

CRS Enters 5.2FUEL and assigns the BOP the actions.

Continues to monitor building radiation levels by bringing up the PMIS screen for BOP RAD.

Enters EOP 5A and has the crew monitor Reactor Building Rads, Temperatures, CRS and Levels Contacts the WCC and request assistance with failed fuel from system engineering CRS and Reactor Engineering.

Role Respond to the request for assistance and tell the CRS that they will be Play notified.

CRS Directs the RO to scram the unit and perform the mitigating scram actions.

Presses the two manual scram pushbuttons and performs the mitigating scram RO actions.

Role When is inserted then DELETE malfunction N186.

Play END OF EVENT Notes Page 14 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 Page 15 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 Op-Test No.: Scenario No.: NRC 1 Event No.: 8 Page 1 of 2 Event

Description:

Fuel Failure/Scram/Failure of Scram discharge volume drain valve to close.

When to initiate: This event happens as a result of the last event and will occur shortly following the dropped rod.

Time Position Applicants Action or Behavior RO Scrams the Unit and performs the required scram actions.

Enters 5.2FUEL and EOP5A and directs the board operators to monitor the CRS radiation levels and temperatures in the Reactor Building.

CRS Has the BOP verify ECCS and PCIS actuates as designed.

Reports that the South HCU area Radiation and temperatures are rising quicker BOP than the rest of the building.

RO Reports that the SDV drains 33 and 34 did not close on the scram.

Directs the RO to verify all scram signals are clear and to reset the scram to isolate CRS the SDV due to a possible direct path from the reactor to the building.

Checks all scram signals and makes sure that they are clear and then resets the RO scram to close the Scram Valves.

Notes that the radiation levels and temperatures around the South SDV are BOP returning to normal.

CRS Remains in EOP 1A and EOP 5A and performs the cleanup steps CRS Directs the RO to maintain level between +3and +54 inches RO Adjust the level control system to maintain the level band.

CRS Directs the BOP to maintain pressure less than 1050 psig.

CRS Directs the BOP to verify Groups BOP Checks on the computer first and notes that Group 6 has failed. Next Event END OF EVENT Notes Page 16 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 Page 17 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 Op-Test No.: Scenario No.: NRC 1 Event No.: 9 Page 1 of 2 Event

Description:

Group 6 isolation failure.

When to initiate: This event is active as soon as the radiation levels in the reactor building exceed the isolation setpoint.

Time Position Applicants Action or Behavior BOP When directed to verify groups notes that Group 6 failed to actuate.

CRS Directs the BOP to isolate the Group 6 valves.

BOP Using the hard card, closes all of the Group 6 valves.

Updates that all group 6 valves are closed and that all the other groups actuated BOP as designed.

END OF EVENT Notes Page 18 of 92

Lesson Narrow Range Level fails, Stuck CR, Roll the MT, TG Rotor Long, MSIV

Title:

Closure, CR Drop, Fuel Failure/Scram/Failure of SDIV, Gp 6 Failure Lesson#: SKL0124827 Rev. No.: 00 CREW CRITICAL TASKS TECHNICAL BASIS SAT UNSAT When a system fails to isolate, EOP-5A directs that this action be taken manually isolate the system. when a maximum normal operating value is exceeded. Failing to do so can NOTE: If the crew does not significantly change the mitigation RESET the SCRAM and strategy as an unnecessary release will Emergency Depressurizes then result and possibly endangering plant this Critical Task will not apply. personnel.

Should secondary containment parameters exceed their maximum safe operating values in more than one area, the RPV must be depressurized to preclude further degradation. RPV When a primary system is depressurization places the primary discharging into the secondary system in its lowest possible energy containment through an state, rejects heat to the suppression unisolable break, execute pool in preference to outside the Emergency Depressurization containment, and reduces the driving when maximum safe operating head and flow of primary systems that values are exceeded in two or are unisolated and discharging into the more areas for the same secondary containment.

parameter.

The criteria of "two or more areas" specified identifies the rise in secondary NOTE: If the crew does RESET containment parameters as a wide-the SCRAM then this Critical spread problem which may pose a Task will not apply.

direct and immediate threat to secondary containment integrity, equipment located in the secondary containment, and continued safe operation of the plant.

When RB refuel floor exhaust EOP-5A directs that a Group 6 be radiation level exceeds 10 mr/hr initiated when the High-High Alarm is or on a valid RB vent radiation received. This ensures any release is a Hi-Hi alarm, initiate a Group 6 filtered, elevated release.

Isolation (RBIS).

Page 19 of 92

Lesson

Title:

Lesson#: SKL0124827 Rev. No.: 00 IX. INITIAL CONDITIONS A. Plant Status:

1. 10% power Beginning of Cycle.

2. Rod Sequence Information: Step: 38 Rod: 38-23 Notch: 8 B. Tech. Spec. Limitations in effect:

C. Significant problems/abnormalities:

Rod 22-27 at position 46 due to high CRDM temperatures.

D. Evolutions/maintenance for the on-coming shift:

1. Complete step 38 of the rod sequence package

2. Roll the Main Turbine per 2.2.77 attachment 1 at 2.16

3. Continue plant Start-up:

a. Procedure 2.1.1 step 5.36 and step 6.3

b. Procedure 2.2.60 step 6.17

c. Procedure 2.2.28.1 step 5.14 Page 20 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Rev. 00

Title:

Cond Pump Trip, A RR Fails to run back, MT Vib, ATWS, Non No.:

Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 SAP BET # 36606 Prerequisites: None Duration (Hours): N/A Appendix D Scenario Outline Form ES-D-1 Facility: Cooper Nuclear Station Scenario No.: NRC 2 Op-Test No.:

Examiners: Operators:

Initial Conditions: Near the End of the Operating Cycle at 95% power and rising power to 100%. EDG 1 running unloaded for break-in run after maintenance that replaced 1 piston.

Turnover: Continue EDG 1 synch and load per procedure. Continue raising power to rated power. EDG 1 LCO due to maintenance.

Event No. Malf. No. Event Event Type* Description 1 N/A N Synchronize and Load EDG 1 per procedure 2 N/A R Raise Power with RR to rated power 3 1 C HPCI inadvertent Initiation 4 2 I APRM B fails at 100%

5 3 C Condensate Pump A Trip, A RR Pump Fails to run back 6 4 M Main turbine vibration increase resulting in Turbine Trip Required, Reactor Manual Scram (ATWS no rods move) 7 5 M Non Critical Busses fail to fast transfer on Turbine Trip 8 6 C SLC Pump A starts then trips immediately 9 7 C RCIC Turbine Trip Page 21 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 Scenario Summary The BOP will synchronize and load Diesel 1 to 4000 kW for post maintenance testing following a piston replacement per 2.2.20.1 Diesel Generator Operations, beginning at Step 5.23.

When DG 1 is being loaded the Doniphan Control Center will call to request a main generator load rise to 750 MWe. The crew will raise power IAW 2.1.10 Station Power Changes section 6.

HPCl will inadvertently start up after the plant is stable at the new higher power level.

The crew will recognize the initiation signal is not valid and will isolate HPCl. The crew will enter 2.4CSCS, for the inadvertent HPCI start. The SRO will determine HPCl is INOPERABLE and enter TS LCO 3.5.1 condition C (14 days).

APRM B will fail upscale over approximately 2 minutes. The crew will respond IAW alarm response procedures, determine the channel is failed and bypass the channel.

The SRO will reference TS 3.3.11 and 3.3.6.

Turbine vibration starts to increase. The crew takes actions per 2.4TURB. Vibrations continue to rise and when the crew attempts to scram the reactor an ATWS occurs due to the water added to the volume by the drifting rod. The turbine is tripped and pressure control is hindered by the limited capacity of the bypass valves. The crew starts RCIC for level control and stops and prevents the other feed systems. This action will aid in reducing reactor power.

When SLC pumps are started, SLC A will trip approximately 1 minute after starting. The crew is able to insert all control rods by resetting the scram and draining the volume and re-scramming the reactor.

Page 22 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 SIMULATOR SETUP IC 20 EOL Type Event Description State Delay Ramp Value Malf 1 hp05 HPCI INADVERTANT INITIATION Delayed FALSE Malf 3 rr17a RECIRC A JORDAN FAILURE Delayed 80.1976 Malf 2 nm09b APRM SIGNAL FAILURE Delayed 02:00 74.4905 CHANNEL B Malf 3 fw14a CONDENSATE PUMP TRIP Delayed FALSE CONDENSATE PUMP 1A Malf none rd02 ATWS Delayed 100 Malf 4 tu03c MAIN TURBINE BEARING HIGH Delayed 05:00 0 VIBRATION BEARING #3 (#1LP Malf 4 tu03d MAIN TURBINE BEARING HIGH Delayed 07:00 0 VIBRATION BEARING #4 (#1LP)

Malf 4 tu03e MAIN TURBINE BEARING HIGH Delayed 10:00 0 VIBRATION BEARING #5 (#2LP)

Malf None ed03a 4160V BUS AUTO TRANSFER Active TRUE FAILURE 4160V BUS 1A (52B/1AN)

Malf None ed03b 4160V BUS AUTO TRANSFER Active TRUE FAILURE 4160V BUS 1B (52B/1BN)

Malf 6 sl01a SLC PUMP TRIP SLC PUMP 1A Delayed 00:03 FALSE Malf 7 rc04 RCIC FLOW CONTROLLER Delayed 99.9999 FAILURE Malf 8 rc02 RCIC TURBINE TRIP Delayed FALSE Event 6 ZLOSLCSWS1A(1)==0 Page 23 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 Op-Test No.:1 Scenario No.:2 Event No.: 1 When the Crew has assumed the watch and at the direction of the When to initiate:

lead examiner.

Event

Description:

Synchronize and load Diesel 1 to 4000 kW for post maintenance testing following a piston replacement per 2.2.20.1 Diesel Generator Operations Time Position Applicants Action or Behavior Direct BOP to continue with diesel generator Synchronize and CRS loading per 2.2.20.1 Diesel Generator Operations BOP Obtains copy of 2.2.20.1 Diesel Generator Operations Adjust DG1 speed so SYNCHROSCOPE is rotating slowly in BOP clockwise (FAST) direction.

BOP Adjust DG1 voltage slightly higher than voltage of Bus 1F.

When SYNCHROSCOPE is at 11 o'clock, close DIESEL GEN 1 BOP BKR EG1.

BOP Raise DG1 load to ~ 1000 kW.

BOP Adjust DG1 kVARs to 400 to 600.

DG1 kVARs should be maintained at 400 to 600 when changing NOTE load.

When DG1 has run for 5 minutes at 1000 kW, slowly raise load BOP until desired load reached.

Record data on Attachments 1 and 2, 15 minutes after DG1 loaded BOP to desired load, then every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thereafter.

END OF EVENT Notes Examiner Note Proceed to the next event when diesel load is stable at the target load value of 4000 KW.

Page 24 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 Op-Test No.:1 Scenario No.:2 Event No.: 1 Page 25 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 Op-Test No.: Scenario No.: 2 Event No.: 2 Event

Description:

Doniphan Control Center will call to request a main generator load rise to 780 MWe.

Time Position Applicants Action or Behavior SRO Take position of Reactivity Manager Ensure reactivity brief has been completed with involved Control SRO Room personnel.

Monitor various independent/redundant parameters and power indications for proper plant response during all power changes; utilize the list below (as a minimum) as dictated by plant conditions:

• Reactor Water Level.

• Reactor Steam Pressure and Flow.

SRO/RO

• Reactor Power, APRMs, RBMs, IRMs, or SRMs, as required.

• Reactor Recirc Speed, Jet Pump, and Loop Flows.

• Total Core Flow and Core Support Plate DP.

• Reactor Feed Pump Flow and Speed.

• Main Generator Output (Gross and Net).

Ensure APRM indicated power versus actual power from other indications does not result in non-conservative protective trip SRO/BOP setpoints (indicated power + allowable gain adjustment tolerances less than actual power)

If called to monitor and adjust DEH and Reactor Recirc oil temperature, tell them that you are on your way and will call them Role Play when you are ready. In a few minutes call back and tell them that you are standing by.

RO Ensure RR Subsystem flows are balanced.

Page 26 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 Raise power by raising RR pump flow as follows:

RO Maintain rate of power change consistent with system capabilities as determined by Load Dispatcher and TG limits.

Monitor core thermal limits (MFLCPR, MFLPD, and MAPRAT), per RO Procedure 6.LOG.601, to ensure compliance with Technical Specifications Section 3.2.

RO Inform CRS of completion of power rise.

END OF EVENT Notes Proceed to the next event at the direction of the lead examiner Page 27 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 Op-Test No.: _____ Scenario No.: NRC 2 Event No.: _3____

Event

Description:

Component - HPCI inadvertently starts.

Time Position Applicants Actions or Behavior Identifies HPCI initiation by observing the initiation of the BOP/RO systems valve and parameter indications on Panel 9-3.

Observes drywell pressure and reactor water level to determine that it is an inadvertent start. A lack of a high BOP/RO drywell pressure and low level alarms are an appropriate way to quickly verify this is inadvertent.

Secures HPCI and places it in Pull To Lock (PTL).This is a BOP/RO from-memory task, however the hard card may be used.

Updates the crew that this is an entry into 2.4CSCS and CRS directs the BOP to ensure all necessary actions are performed.

Sends Building Station Operator to the area to investigate the BOP/RO initiation.

As the Station Operator, respond to the report and let the Role Play BOP know that you will look around to try to determine what caused the initiation.

Monitors for signs that HPCI injected into the vessel. This is RO done by checking for level swings, power spikes.

Technical Specifications 3.5.1 (C) HPCI is inoperable. LCO CRS time of 14 days. RCIC must be administratively verified operable within one hour.

Contacts Work Control to confirm that RCIC surveillance was CRS successful and within periodicity.

Page 28 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 As either Work Control or Management, respond to the Roll Play report about the Inadvertent Initiation of HPCI and the fact that both HPCI and RCIC are inoperable.

CRS Updates Crew with status of HPCI.

Event ends with system declared inoperable and RCIC verified operable END OF EVENT Notes Proceed to the next event at the direction of the lead examiner Page 29 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 Op-Test No.: Scenario No.: NRC 2 Event No.: 4 Event

==

Description:==

APRM B fails upscale Time Position Applicants Action or Behavior RO Reports 1/2 Scram and its cause to the Crew.

Diagnoses that APRM B has failed upscale causing the 1/2 scram.

RO Also that it was the only one.

Pulls Annunciator cards for the RPS Trip and APRM Upscale and RO reports the actions to the CRS.

Checks the APRM in the back panels and reports finding to the BOP crew.

CRS Directs the RO to bypass the APRM and reset the 1/2 Scram.

Selects B APRM joy stick and places it to the B position to bypass the failed APRM. Following the instructions in the APRM RO Upscale Alarm Procedure, Selects the appropriate Joy Stick and places it to the B position.

BOP Peer checks bypassing the APRM.

Selects the Scram Reset switch and places it momentarily in the 1-RO 4, then the 2-3 positions and lets it return to the neutral position.

Reports that the 1/2 has been reset and that the annunciators have RO cleared.

Evaluates TS and determines that potential LCOs exists for T.S.

CRS 3.3.1.1 (RPS Instrumentation) Table 3.3.1.1-1 Function 2, TLCO 3.3.1 for Rod Blocks, and TLCO 3.3.3 PAM CRS Notifies work control of the failures and request repair.

Page 30 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 As the work control center, respond to the report and let the CRS Role know that a work order will be initiated and a team put together to Play investigate the failure of the APRM.

END OF EVENT Notes Proceed to the next event Page 31 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 Op-Test No.: Scenario No.: NRC 2 Event No.: 5 Page 1 of 2 Event

==

Description:==

Condensate pump trip and A RR RUNBACK failure When to initiate: At the direction of the lead examiner.

Time Position Applicants Action or Behavior BOP Reports that the 1A Condensate Pump has tripped.

BOP Monitor reactor feed pump suction pressure.

RO or Sends the Station Operator to investigate the tripping of the 1A BOP Condensate Pump.

Respond as the Station Operator and tell the Control Room Role Operator that you will go check the 1A Condensate Pump out Play and report back that there is no obvious cause.

BOP Update the crew that this is an entry condition into 2.4MC-RF.

RO Reports Reactor Recirc Pump runback.

Reports A RR RUNBACK failed to completely runback currently at RO 80% and entry to 2.4RR.

RO Reports mismatched flows between A and B Recirc loops.

CRS Ensure requirements of SR 3 .4.1 .1 are met as soon as practical.

CRS Announce entry into 2.4RR and assign it to the RO.

If requested as a licensed operator to locally adjust A RRMG Role then use remote function RR05 RRMG A SCOOP TUBE us Play directed by the reactor operator.

CRS Announce entry into 2.4MC-RF and assign it to the BOP.

Page 32 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 Assign critical parameters, scram actions, and subsequent operator CRS actions.

RO Monitors reactor parmeters and core stabilities.

BOP Monitors condensate pressures and flows.

END OF EVENT Notes Page 33 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 Op-Test No.: Scenario No.: NRC 2 Event No.: 6 Event

==

Description:==

Turbine High Vibration/Turbine Trip/ATWS When to initiate:

Time Position Applicants Action or Behavior Notes that Turbine Bearing vibrations are rising. Either by BOP seeing the red LEDs on the Bentleys or by the vibration annunciator.

Updates the crew with the fact that turbine vibrations are rising BOP and that is an entry into 2.4TURB.

CRS Enters 2.4TURB and assigns it to the BOP Operator.

BOP Updates crew as vibrations rise.

Briefs crew on action points and responsibilities if the vibrations continue to rise.

• Report vibration in 1 mil increments on highest reading bearing.

• Alert LED - contact engineering.

• Danger LED - reduce power.

• 14 mils - Scram Action.

CRS

• Brief Procedure 2.1.5 and assign responsibilities (If TCV/TSV scram enabled).

• Assign operator to continue Procedure 2.4TURB action post-scram.

• Brief power reduction.

• Obtain TG/BOP Engineering recommendation on continued operation.

• Monitor hotwell conductivity for indications of thrown blade.

CRS Directs that Reactor Power be reduced.

Page 34 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 Performs a power reduction in accordance with Procedure RO 2.1.10.

BOP Updates Vibration 14 Mils which is the Scram Point.

CRS Directs the RO to Scram the Reactor.

Presses the Manual Scram Pushbuttons and announces RO ATWS conditions. Next Event Directs the BOP to trip the Turbine and continue actions of CRS 2.4TURB.

END OF EVENT Notes Page 35 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 Op-Test No.: Scenario No.: NRC 2 Event No.: 7 Page 1 of 1 Event

Description:

Non Critical Busses fail to fast transfer on Turbine Trip Time Position Applicants Action or Behavior Identifies 4160 A and B non-critical buses failed to transfer and BOP/RO critical buses are powered from the emergency transformer.

CRS/BOP/RO Entry in to 5.3EMPWR CRS Assigns 5.2EMPWR and sets priorities on restoring SW, Station Service air, and REC cooling BOP Restores SW, Station Service air, and REC cooling using 5.3empwr Notes Page 36 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 Op-Test No.: Scenario No.: NRC 2 Event No.: 8 Page 1 of 2 Event

==

Description:==

SLC Pump A starts then trips immediately.

When to initiate: This is an automatic event once the SLC system is started.

Time Position Applicants Action or Behavior Starts the 1A and 1B SLC Pumps using the control switches on RO Panel 9-5.

Observes that SLC Pumps Started and has developed sufficient discharge Pressure to inject into the vessel that the squib valve RO continuity light is extinguished and that RWCW isolated. And reports the observations and initial SLC tank level to the CRS.

Notes that the 1A SLC Pump tripped approximately one minute RO after starting and reports that to the CRS.

CRS Calls WCC and request repair of the SLC system.

Role As the WCC respond to the report about SLC pump 1A failure Play and tell the CRS that a team is getting right on it.

CRS Directs the RO to concentrate on driving rods and scramming.

END OF EVENT Notes Page 37 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 Page 38 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 Op-Test No.: Scenario No.: NRC 2 Event No.: 9 Page 1 of 1 Event

==

Description:==

RCIC Turbine Trip Time Position Applicants Action or Behavior BOP Identifies RCIC turbine tripped and informs CRS SRO Calls WCC to investigate trip of the RCIC system.

BOP Dispatch a station operator to investigate cause of the RCIC turbine trip.

ROLE When directed as a station operator to investigate the RCIC PLAY turbine trip wait a few minutes then report that the cause of the RCIC trip is not readily apparent.

Notes TERMINATE THE SCENARIO Page 39 of 92

Lesson Synchronize EDG 1, HPCI inadvertent Initiation, APRM B fails, Cond Pump

Title:

Trip, A RR Fails to run back, MT Vib, ATWS, Non Critical Busses fail to transfer, SLC A trips, RCIC Trip Lesson#: SKL0124826 Rev. No.: 00 CREW CRITICAL TASKS TECHNICAL BASIS SAT UNSAT With a Reactor Scram required, reactor not shutdown, and conditions for ADS blowdown are met, INHIBIT ADS to Inhibit ADS prior to auto initiation prevent an uncontrolled RPV during a failure to Scram.

depressurization and cold water injection from low pressure sources, to prevent causing a significant power excursion.

Failure to inject SLC and insert control Take action to reduce reactor rods could result in torus water power by injecting boron and/or temperature exceeding the HCTL.

inserting control rods, to prevent Exceeding the HCTL unnecessarily exceeding the primary would require that the RPV be containment design limits. depressurized which substantially changes the mitigation strategy.

During failure to scram conditions, insert control rods using one or more methods contained within Procedure Achieving reactor shutdown is one of the 5.8.3. (This does not require the primary goals of EOP-6A.

Operator to reach the point of Reactor Shutdown, but instead to demonstrate the skills necessary to perform this task.)

Page 40 of 92

Lesson

Title:

Lesson#: SKL0124826 Rev. No.: 00 IX. INITIAL CONDITIONS E. Plant Status:

1. 95% power End of Cycle.

2. Rod Sequence Information: Page:

Rod:

Notch:

F. Tech. Spec. Limitations in effect:

Day 5 of 7 LCO 3.8.1B for DG-1.

G. Significant problems/abnormalities:

DG1 in running unloaded, currently at step 5.23 of procedure 2.2.20.1 H. Evolutions/maintenance for the on-coming shift:

1. Synchronize DG-1 to 4160 1F and complete an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> full load run.

2. Restore Reactor power to 100% per 2.1.10 using Reactor Recirculation.

Page 41 of 92

Start CBP, Raise Power, Runaway RR pump, DC Lesson

Title:

failure, Loss of Vacuum, EOP1 Station Blackout Rev 00 Steam cooling, Emergency Depressurization No.:

Lesson No.: SKL0124824 BET No.: 36604 Prerequisites: None Duration (Hours) 1.5 Facility: Cooper Nuclear Station Scenario No.: _NRC 3_______ Op-Test No.:

Examiners: ________________________ Operators:___________________________

Initial Conditions: The plant is operating at 75% power near the end of the current fuel cycle. CBP B is being restored to service following corrective maintenance. It is a red light day and the dispatcher has requested that power be raised to maximum. SLC pump 1A is out of service to replace the discharge relief valve.

Turnover: Crew is to Start CBP B and continue power ascension. TS for SLC pump LCO is included.

Event Malf. Event Event No. No. Type* Description 1 N Start Condensate Booster Pump B 2 R Raise Power using RR 3 1 I RRMG A controller failure to maximum 4 2 C Loss RCIC 125 VDC 5 3 M Lowering Main Condenser Vacuum resulting in Scram and Turbine trip Required 6 R Emergency Power reduction to maintain Vacuum 7 4 C When Reactor is Scrammed both Reactor Feed pumps trip 8 5 M When turbine tripped Loss of Offsite power occurs. EDG

1. 2 fails to start and can not be started from the Control room and 4160F lock out occurs due to a fault on the bus. This results in a Station black Out.

9 6 C HPCI oil system fails (leak) resulting in HPCI unavailable to inject to RPV Page 42 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00

References:

1. Technical Specifications

a. 3.5.3 RCIC

b. 3.4.1 Recirculation Loops Operating

2. Procedures

a. COP 2.0.11, Entering and exiting TS/TRM/ODAM LCO Conditions

b. GOP 2.1.5, Reactor Scram

c. 2.4RR Reactor Recirculation Abnormal

d. 2.2.68.1 Reactor Recirculation

e. EPIP 5.7.1, Emergency Classification

f. EOP 1A, RPV Control

g. EOP 2A, Emergency RPV Depressurization/Steam Cooling

h. 5.3SBO Station Blackout.

3. Miscellaneous

a. None

4. PRA

a. Key Contributor - HPCI Failure, Loss of DG#2

b. Initiator of Core Damage - Loss of Offsite power COMMITMENT LIST Commitment Rev. Added None Method:

This evaluation scenario is intended to be used as an examination mechanism for evaluating Licensed Operator candidates in a dynamic plant situation.

Special Equipment/Materials/Special Instructions:

Validation Load 0912. Compare current simulator load to the validation load. If they are not the same, run the scenario and look for possible changes.

Page 43 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 I. SCENARIO

SUMMARY

The plant is operating at 75% power near the end of the current fuel cycle. CBP B is being restored to service following corrective maintenance. It is a red light day and the dispatcher has requested that power be raised to maximum. SLC pump 1A is out of service to replace the discharge relief valve.

The crew starts CBP B in preparation to raise power. After the CBP is running, power is raised with recirc flow to approximately 600 MWe net. A controller failure causes RRMG set 1A to increase. The crew locks the scoop tube on the RR pump. The crew addresses Technical specifications and may continue to raise power.

A loss of the RCIC 125VDC SR occurs making the RCIC system inoperable. The crew declares the RCIC system inoperable and addresses Technical Specifications.

After the loss of power to RCIC is addressed condenser vacuum begins to degrade due to air in-leakage. The Crew takes action to address the loss of vacuum including reducing reactor power. Eventually the crew determines that a scram is required and scrams the reactor and trips the turbine. When the scram actions are taken both feed pumps trip resulting in a loss of feedwater. When the turbine trips offsite power is lost due in part due to the loss of generation from Cooper.

After offsite power is lost 4160V 1F switchgear develops a fault and #2 DG fails to start resulting in a station blackout. The crew enters 5.3SBO and EOP-1A.

When HPCI initiates (manual or automatic) an oil system rupture occurs preventing HPCI operation. RCIC is not available to automatically initiate or inject due to the loss of the RCIC SR. The crew may initiate action to start RCIC locally at the pump, but these actions are not completed before the steam cooling contingency is entered. RPV level slowly decreases due to LLS cycling. When TAF is reached, steam cooling is required. After the crew enters steam cooling maintenance reports that DC power to RCIC can be restored. The crew restores DC power to RCIC and the crew initiates RCIC.

When RCIC is placed in service the RCIC injection valve fails partially open limiting RCIC flow to approximately 50 gpm. Since this is insufficient flow to restore water level to greater than -183 FZ, emergency depressurization is required. After emergency depressurization is commenced the #2 DG is restored to service and RHR and CS are used to restore reactor water level.

The scenario ends when Emergency Depressurization has been completed, RPV level restored and maintained +3 to 54 and containment is being cooled.

Page 44 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 II. SIMULATOR SET-UP A. Materials Required None B. Initialize the simulator in IC18, 100% (BOC) or from a saved IC C. Change the simulator conditions as follows:

1. Triggers Number File Name Description E1 None E2 None E3 None E4 None E5 None Trigger is true when the turbine trips E6 None Page 45 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00

2. Malfunctions Number Title Trigger TD Severity Ramp Initia l

ED12b Loss of RCIC Starter Rack E3 0 N/A N/A N/A RR17a RR Control Signal Failure E2 0 100% 1:00 N/A MC01 Main Condenser Air In-leakage E4 0 100% 20:00 N/A ED05 Loss of Power (Startup E5 1 sec N/A N/A N/A Transformer)

ED06 Loss of Power (Emergency E5 1 sec N/A N/A N/A Transformer)

ED08f Loss of 4160 F E5 16 Sec N/A N/A N/A DG01b DG2 Fail to Start A N/A N/A N/A N/A DG06b DG2 Fails to Auto Start N/A N/A N/A N/A HP12 HPCI LUBE OIL PUMP DISCHARGE A N/A N/A N/A N/A LINE RUPTURE

3. Remotes Number Title Trigger Value Ramp FW14 MC-MO-302 N/A 10% N/A RC09a RCIC Injection Valve Power E10 DE-ENERG N/A RC09b RCIC Injection Valve manual E10 .5 N/A position SL06 SLC Pump A TAGOUT N/A TAGOUT N/A

4. Overrides Instrument Tag Trigger TD Value Ramp none Page 46 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 D. Panel Set-up

1. Ensure PMIS IDTs are blank.

2. Take the simulator out of FREEZE and allow it to run for several minutes to verify stable plant conditions.

3. Reduce power to 75%.

4. Adjust generator MVARs to ~+50 MVARs.

5. Ensure CRD pump 1B is running and CRD pump 1A is OFF.

6. Stop CBP B and start its auxiliary oil pump.

7. Ensure CBP Auxiliary Oil Pump B is operating.

8. Place a red tag on SLC pump 1A control switch.

9. FREEZE the simulator.

Page 47 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 Op-Test No.: Scenario No.: NRC 3 Event No.: 1 Page 1 of 4 Event

==

Description:==

Start Condensate Booster Pump B When to initiate: When directed by the lead evaluator call as the WCC that you standing by for the start of Condensate Booster Pump B Time Position Applicants Action or Behavior CRS Directs BOP to Start Condensate Booster Pump B per procedure 2.2.6 Inform Radwaste Operator condensate booster pump is to be placed BOP in service and are sufficient F/Ds are precoated per Procedure 2.2.5.

Role Report as Radwaste operator that all condensate F/Ds are Play precoated per Procedure 2.2.5.

Direct Turbine Building operator to throttle open following valves until air free water flows and then close valves:

BOP

a. MC-272, CONDENSATE BOOSTER PUMP B VENT.

b. MC-273, CONDENSATE BOOSTER PUMP B VENT.

c. MC-274, CONDENSATE BOOSTER PUMP B VENT.

d. MC-912, CONDENSATE BOOSTER PUMP B SEAL FLUSH VENT.

Report that you have throttled open following valves until air free water flows and then close valves:

Role Play a. MC-272, CONDENSATE BOOSTER PUMP B VENT.

b. MC-273, CONDENSATE BOOSTER PUMP B VENT.

c. MC-274, CONDENSATE BOOSTER PUMP B VENT.

d. MC-912, CONDENSATE BOOSTER PUMP B SEAL FLUSH VENT.

BOP Ensures Auxiliary Oil Pump B has been operating for 5 minutes.

Page 48 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 Direct Turbine Building operator to:

• Ensure pump oil reservoir level is normal and flow exists through bearing sightglasses.

• Ensure TEC-42, CONDENSATE BOOSTER PUMP B OIL COOLER INLET, is open.

BOP

• Ensure TEC-43, CONDENSATE BOOSTER PUMP B OIL COOLER OUTLET, is throttled to maintain oil temperature as high as possible but < 110°F.

• Ensure MC-MO-302, CONDENSATE BOOSTER PUMP B DISCHARGE, is closed.

• Place MC-SW-FCV10, LOCAL MANUAL SWITCH FOR MC-AOV-FCV10, to OPEN.

Report that:

• Pump oil reservoir level is normal and flow exists through bearing sightglasses.

• TEC-42, CONDENSATE BOOSTER PUMP B OIL COOLER Role INLET, is open.

Play

• TEC-43, CONDENSATE BOOSTER PUMP B OIL COOLER OUTLET, is throttled to maintain oil temperature < 110°F.

• MC-MO-302, CONDENSATE BOOSTER PUMP B DISCHARGE, is closed.

• MC-SW-FCV10, LOCAL MANUAL SWITCH FOR MC-AOV-FCV10, is in OPEN.

BOP Checks MC-FCV-10, MIN FLOW VLV, open BOP Direct Turbine Building operator to Jog open for ~ 2 seconds MC-MO-302.

Role Report that MC-MO-302 has been opened ~ 2 seconds Play BOP Start Condensate Booster Pump B and Direct Turbine Building operator to slowly open MC-MO-302.

Role Report that MC-MO-302 has been slowly opened.

Play Modify Remote Function FW14 to 100%.

When pump is up to speed and oil pressure is normal, place AUXILIARY OIL PUMP B switch to OFF to stop pump.

BOP Check Condensate Booster Pump B AMPS are in green band.

Direct Turbine Building operator to place MC-SW-FCV10, LOCAL MANUAL SWITCH FOR MC-AOV-FCV10, to AUTO Page 49 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 Role Report that LOCAL SWITCH for MC-AOV-FCV10 is in AUTO Play Press COND SYS/BOOSTER PUMP MIN FLOW RESET button to close MC-FCV-10 BOP Direct Turbine Building operator to check Condensate Booster Pump B is operating properly and throttle TEC-43 to maintain oil temperature between 100°F and 110°F Report that Condensate Booster Pump B is operating properly and Role Play you throttle TEC-43 to maintain oil temperature between 100°F and 110°F.

Direct Turbine Building operator to:

.1 Open MC-906, ROOT HYDROGEN INJECTION INTO BOOSTER PUMP B (T-882-N CBP B Suction).

BOP

.2 Cycle OWC-SW-H2B, H2 ISOLATION TO CBP B, to CLOSE and then back to AUTO (OWC Control Room, P500 Panel).

.3 Verify OWC-SOV-H2B indicates OPEN (OWC Control Room, P500 Panel).

Report that:

Role .4 MC-906 is Open Play .5 Cycle OWC-SW-H2B, has been cycled CLOSE and then back to AUTO

.6 OWC-SOV-H2B indicates OPEN BOP Report to CRS that Condensate Booster Pump B is in service.

END OF EVENT Notes Page 50 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 Page 51 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 Op-Test Scenario Event o No.: No.: NRC 3 No.: 2 Page 1 f 2 Event

==

Description:==

Raise Reactor Power When to initiate: Following the start of the CBP or directed by the lead evaluator call as the load dispatcher and request that power be raised to 600 MWe net.

Positio Time Applicants Action or Behavior n

Role As the Load Dispatcher call the CRS and request that Cooper raise Play load to 600 Net following normal rate of rise.

Role If contacted as reactor engineering indicate that we are at the Play target rod line and to accomplish the entire power increase should be with recirc flow.

CRS Directs the RO to raise power using Reactor Recirc Pumps to 600 Net Megawatts.

RO Reviews Procedures 2.1.10, Plant Power Changes for raising power with recirc pump speed controllers.

RO Contacts the RB Station Operator to monitor reactor Recirc Pump Temperatures while raising load.

Role As the RB Station Operator respond to the request.

Play RO Request a Peer Check from the BOP.

BOP Provides requested Peer Checks.

CRS Provides oversight as the reactivity manager for the power change.

RO Checks current power and RR Pump Speeds.

RO Selects one of the RR Pump controllers and rotates the speed adjust potentiometer clockwise to raise the speed of the RR Pump.

RO Selects the other RR Pump controllers and rotates the speed adjust potentiometer clockwise to raise the speed of the RR Pump.

RO Alternates between the A and B RR Pump controllers and raises the speed of the pumps and therefore Reactor Power.

BOP Monitors the balance of plant as reactor power is raised.

RO Stops raising power when Net Megawatt output is 600 and notifies the CRS.

Page 52 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 END OF EVENT Notes Page 53 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 Scenario Event Op-Test No.: No.: NRC 3 No.: 3 Page 1 of 2 Event

==

Description:==

RRMG A controller failure to maximum When to initiate: When power has increased TO APPROXIMATELY 600 MWe net Time Position Applicants Action or Behavior RO Announces increasing RR loop A flow.

RO Lockout the RRMG A scoop tube RO Reports RRMG A speed is no longer raising and loop flows differ.

CRS Directs actions per 2.4RR and assigns 2.4RR to BOP Announce SCRAM actions from 2.4RR:

If both RR pumps are tripped and reactor power > 1 % rated thermal .

• SCRAM CRS/BOP

• Enter Procedure 2 .1 .5 If abnormal neutron flux oscillations are observed while operating in the Stability Exclusion Region :

• SCRAM

• Enter Procedure 2 .1 .5 RO Accepts SCRAM actions from 2.4RR Assesses Technical Specification 3.4.1 to determine RR loop CRS operability, if loop flows differ by 15% then loop B is declared inoperable.

Takes action per 2.4RR attachment 4 Reactor Recirculation Flow BOP Control Failure/RRMG Scoop Tube Lockout to Operate scoop tube locally per Procedure 2 .2.68.1 END OF EVENT Page 54 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 Notes Page 55 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 Scenario Event Op-Test No.: No.: NRC 3 No.: 4 Page 1 of 2 Event

==

Description:==

Loss RCIC 125 VDC When to initiate: After actions for RRMG A controller failure complete Time Position Applicants Action or Behavior Announces the 125VDC Blown Fuse Annunciator C-1/A-2 125V DC SWGR BUS 1A BLOWN FUSE BOP Blown fuse on SWGR for:125 VDC RCIC SR NORMAL FEEDER BLOWN FUSE BOP Announces entry to 5.3DC125 referenced in alarm card.

CRS Enters 5.3DC125 and assigns procedure to BOP BOP Direct Turbine building operator to investigate B 125 DC switchgear for RCIC starter rack.

Role Report that you can not determine cause of the blown fuse.

Play Declares RCIC inoperable and refers to TS 3.5.1.

CRS Enters LCO 3.5.3.A and determines that HPCI is required to be verified operable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> by administrative means and that RCIC is required to be restored to operable status with 14 days.

Contacts the WCC to initiate actions to investigate repair the RCIC starter rack.

CRS Role Respond as the WCC that a team will investigate the cause of the Play 125 VDC RCIC blown fuse END OF EVENT Page 56 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 Notes Page 57 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 Scenario Event Op-Test No.: No.: NRC 3 No.: 5 Page 1 of 2 Event

==

Description:==

Lowering Main Condenser Vacuum resulting in Scram and Turbine trip Required When to initiate: When the initial actions for the loss of RCIC starter Rack are complete Activate Trigger E4, MC01, Main Condenser Air In leakage.

Time Position Applicants Action or Behavior Reports lowering condenser vacuum.

BOP May diagnose the cause of the lowering vacuum as air in leakage.

Entry to 2.4VAC CRS Enters 2.4VAC and assigns to BOP Announce SCRAM actions from 2.4VAC:

If vacuum cannot be maintained >_ 23" Hg:

CRS/BOP

• If Annunciator 9-5-2/C-4 clear, SCRAM and enter Procedure 2.1.5.

• Trip Main Turbine.

• If reactor not scrammed, enter Procedure 2 .2 .77 RO Accepts SCRAM actions from 2.4VAC CRS Directs the RO to reduce reactor power to maintain vacuum RO Reduces reactor power to maintain vacuum END OF EVENT Notes Page 58 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 Scenario Event Op-Test No.: No.: NRC 3 No.: 6 Page 1 of 1 Event

==

Description:==

Emergency Power reduction to maintain Vacuum When to initiate: Automatic as vacuum lowers Time Position Applicants Action or Behavior Reduces Reactor Recirc Pump A and B speeds to maintain condenser RO vacuum. Both speeds are reduced one at a time in accordance with Procedure 2.1.10 while checking with the BOP on the status of vacuum.

RO Monitors RR Pump speeds and parameters on RR Speed controller along with reactor power as the speeds are reduced.

RO/BOP Sends the Station Operators to monitor Recirc Pump MG Set oil temperatures Role Respond to the order to monitor DEH and RR MG Set temperatures.

Play Directs that the RO and BOP coordinate actions to maintain CRS condenser vacuum.

CRS Contacts Load dispatcher that an emergency load reduction is in progress due to a lowering condenser vacuum CRS Orders Reactor SCRAM when vacuum can not be maintianed END OF EVENT Notes Page 59 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 Event Op-Test No.: Scenario No.: NRC 3 No.: 7 Page 1 of 3 Event

==

Description:==

When Reactor is Scrammed both Reactor Feed pumps trip When to initiate:

Time Position Applicants Action or Behavior Simulator When the reactor scrams Modify Malfunction MC01 ramp time to 0.0 operator secs.

RO Scrams the reactor per 2.1.5 and takes scram actions when vacuum can not be maintained.

Reports the trip of both reactor feed pumps RO And EOP entry on low RPV level CRS Enters EOP-1A.

BOP Trips the Main Turbine END OF EVENT Notes Page 60 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 Scenario Event Op-Test No.: No.: NRC 3 No.: 8 Page 1 of 4 Event When turbine tripped Loss of Offsite power occurs. EDG #2 fails

==

Description:==

to start and can not be started from the Control room and 4160F lock out occurs due to a fault on the bus. This results in a Station black Out.

When to initiate: Automatic on turbine trip Time Position Applicants Action or Behavior When the turbine is tripped VERIFY that trigger E5 goes active.

Simulator Operator

• Announces the loss of Offsite power/Station Blackout BOP

• Reports #1 DG running

• Reports 1FE is tripped and will not close.

• Announces that DG2 will not start.

BOP Dispatch Station Operators to investigate the DG failure to start and run.

RO Monitors LLS operation.

Role Play When directed to secure DG1 Remote Function DG17 to secure the DG When directed to investigate 4160V Bus 1F, wait 3 minutes, Role Play report all feeder breakers have numerous lockout devices tripped.

When directed to investigate #2 DG, wait 2 minutes, report that Role Play the DG cranked but did not start, you have contacted Maintenance for assistance.

When directed to go to Instrument Rack 25-5 monitor reactor Role Play level and report level to the control room on the requested periodicity.

Simulator Use RR19 Shutdown Cooling Loss of Mass to reduce RPV level as Operator directed by Floor instructor. (use monitored parameter rrmrvloss=0 to reset RR19 as required)

Page 61 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00

• CRS enters and ensures actions of EOP-1A: RPV Control/RPV Level.

• Low-Low Set operation verified.

• Directs HPCI Failure Investigated CRS

• Directs PCIS isolations verified.

• Directs ADS Inhibited.

• Enters 5.3SBO

• Enters and directs actions per all three attachments of 5.3SBO.

• May direct a cooldown to be started.

• Verifies the start of DC Oil pumps.

• Places CP, CBP and CW pump switches to trip.

BOP

• VBD-H, place MANUAL TRANSFER SW to ALT

• Secures DC oil pumps when equipment stops.

• Aligns Electric Plant per attachment 3.

When directed by the crew to open N2-74, Modify Remote Function PC-21 Nitrogen storage tank isolation solenoid bypass to 100%.

Role Play When remote function PC-21 is at 100% report to the control room that N2-74 is open.

RO/BOP

• Monitors Available Instrumentation.

• Directs Field Operations of 5.3SBO At the discretion of the lead examiner report indicated level Simulator at -40 FZ (this corresponds to TAF at 1000 psig and would push Operator the crew into steam cooling). Adjust the value as needed dependent upon reactor pressure.

When reactor water level reaches TAF the CRS determines that steam CRS cooling is required and Enters EOP-2A.

Directs that reactor pressure be stabilized.

RO/BOP Stabilizes reactor pressure.

When steam cooling has been entered, contact the control room Role Play as maintenance and inform them that the RCIC Starter Rack is repaired and you can re-energize it when directed.

CRS Direct that RCIC SR be place in service and RCIC started.

RO/BOP Directs RCIC SR reenergized and starts the RCIC system When the crew directs that the RCIC starter rack be reenergized, Insert Trigger E10, Role Play then DELETE Malfunction ED12b.

Page 62 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00

• Determines that RCIC is not developing full flow.

RO/BOP

• Informs the CRS that RCIC is injecting at 50 gpm

• May diagnose the cause as a failure of the RCIC injection valve.

Role Play If directed to manually open the RCIC injection valve report that you cannot move the valve it seems to be seized.

Determines that an emergency depressurization is required because an CRS injection system is available and level is less than -25FZ.

Directs the RO to open 6 ADS valves.

RO Opens 6 ADS valves.

Once ED has commenced then, delete Malfunction DG01b and inform Role Play the control Room that DG2 is repaired and may be started from the Control Room.

BOP Starts DG2 and verifies that 41601G is energized.

RO/BOP Control Reactor water level +3 to +54 using CS and/or RHR This scenario was developed to evaluate Hot license candidates.

As such it may not be practical for the SRO candidate to make the emergency classification until after the scenario is NOTE terminated.

CRS DECLARES a General Emergency EAL 4.4.1 loss of all AC power with the inability to keep the core covered.

END OF EVENT Notes Page 63 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 Page 64 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 Scenario Event Op-Test No.: No.: NRC 3 No.: 9 Page 1 of 1 Event HPCI oil system fails (leak) resulting in HPCI unavailable to

==

Description:==

inject to RPV When to initiate: This is a latent failure.

Time Position Applicants Action or Behavior RO/BOP Identifies that HPCI failed to start automatically and attempts to start HPCI manually and informs CRS.

RO/BOP Recognizes that HPCI AOP is running with no oil pressure RO/BOP Direct station operator to investigate failure of HPCI Role When directed to investigate the HPCI Failure report that an oil Play pipe is broken and the floor is covered with oil and maintenance has been contacted to investigate the failure.

RO/BOP Reports HPCI oil leak to CRS and recommends placing AOP in pull-to-lock.

CRS Directs HPCI AOP be place in pull-to-lock and contacts WCC to investigate failure of HPCI Role As WCC report that a team will investigate HPCI failure.

Play END OF EVENT Notes Page 65 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 VI. SCENARIO TERMINATION When the RPV has been depressurized and Reactor water level is restored within the Normal Level Band, FREEZE the simulator.

VII. POST-SCENARIO CRITIQUE If this scenario is not being used to evaluate HLC candidates for NRC Audit Exam or NRC Exam or for an annual exam, provide a critique in accordance with the general critique guidelines of OTP-806.

CREW CRITICAL TASKS TECHNICAL BASIS SAT UNSAT Failure to recognize the auto start Energize a 4160 VAC safety not occurring and energizing of the bus when off-site power is safety bus, and failure to take not available and EDGs fail manual action per to automatically start. Procedure 5.3EMPWR will result in loss of safety-related equipment.

An unnecessary ADS initiation would significantly change the mitigation strategy. Additionally, during Inhibit ADS prior to auto certain conditions an ADS blowdown initiation. could result in a loss of adequate core cooling and/or exceeding the Technical Specification allowable cooldown rate.

The MSCRWL is the lowest RPV water level at which the covered portion of the reactor core will generate sufficient When RPV level cannot be steam to preclude any clad temperature restored and maintained > - in the uncovered portion of the core 183", Emergency Depressurize per EOP 2A. from exceeding 1500°F. When water level decreases below MSCRWL with injection, clad temperatures may exceed 1500°F.

Submergence is the preferred method Ensure RPV water level restoration and maintenance for cooling the core. All fuel nodes are above -158" (TAF) when low then assumed to be covered with water pressure systems are and heat is removed by boiling heat available.

transfer.

Page 66 of 92

Start CBP, Raise Power, Runaway RR pump, DC failure, Loss of Lesson

Title:

Vacuum, EOP1 Station Blackout Steam cooling, Emergency Depressurization Lesson No.: SKL0124824 Rev No.: 00 CREW CRITICAL TASKS TECHNICAL BASIS SAT UNSAT At -202", the steam generated by the covered portion of the core is sufficient to remove the heat generated in the uncovered region with PCT at 1800°F.

The level at which this correspondence occurs is designated the Minimum Zero-Injection RPV Water Level (MZIRWL). When RPV water level drops below the MZIRWL, steam cooling may no longer be sufficient to preclude the peak clad temperature During steam cooling operations, Emergency from exceeding 1800°F. RPV Depressurize IAW EOP-2A the depressurization is then required per reactor when RPV level EOP-2A. Unless the RPV is already reaches -202".

depressurized, it is expected that the resulting swell will be sufficient to quench the uncovered portion of the fuel and reduce PCT almost to the value that would exist if the core were submerged. As the swell subsides and steam flow through the open SRVs decreases, however, PCT turns and again rises. If no injection source can be made available, PCT will eventually exceed 1800°F.

Page 67 of 92

Lesson

Title:

Lesson No.: SKL0124824 Rev No.: 00 IX. INITIAL CONDITIONS I. Plant Status:

1. 70% power Beginning of Cycle.

2. Rod Sequence Information: Page: 1 Rod: 26-19 Notch: 8 J. Tech. Spec. Limitations in effect:

7 day LCO is in effect due to inoperability of SLC pump 1A.

K. Significant problems/abnormalities:

Limiting Control Rod Pattern L. Evolutions/maintenance for the on-coming shift:

1. Start CBP B and raise power to maximum currently at step 8.6.9 of procedure 2.2.6 Page 68 of 92

Lesson Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument, Rev. 01

Title:

CBP trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail No.:

to Auto Open, RHR pumps fail to Auto Start, ED Lesson#: SKL0124822 SAP BET # 30052 Prerequisites: None Duration (Hours): N/A Facility: Cooper Nuclear Station Scenario No.: NRC 4 Op-Test No:

Examiners: Operators:

Initial Conditions: The plant is operating at 90% power with no equipment out of service.

Turnover: After the crew has assumed the watch, Start 1B CRD Pump and secure 1A CRD Pump to allow maintenance on the motor.

Event No. Malf. No. Event Event Description Type*

1 N/A N Swap CRD Pumps 2 1 C RCIC Steam Leak and Manual Isolation of RCIC 3 2 I Oscillating Feedwater Flow Instrument 4 3 C Condensate booster pump trip 5 5 C A Reactor Recirc Pump Trip 6 4 R Emergency Power Reduction 7 6 C Reactor Recirc Pump Seal Failure 8 7 M Large LOCA 9 8 C RHR Pumps fail to Auto Start 10 9 C Core Spray Valves Fail to Auto Start Page 69 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Scenario Description The plant is operating at 90% power.

After the Crew assumes the watch the crew will start 1A CRD pump and secure 1B out of service.

Shortly after the CRD Pumps have been swapped a steam leak occurs on the RCIC steam supply line. The crew manually isolates the RCIC steam supply line terminating the steam leak. The CRS evaluates Technical Specifications for RCIC INOP.

After conditions are stable following the RCIC steam line break a Main Feedwater Flow Signal Oscillation occurs causing reactor water level transient. The crew responds per 2.4RXLVL and 4.4.1.

After the crew stabilizes reactor water level, a Condensate Booster Pump trips resulting in a Reactor Recirc runback and lowered reactor power. While the power is lowering the A Reactor Recirc Pump trips requiring the crew to make an emergency power reduction. This will cause in the future the failure of the seals.

After the A Reactor Recirc Pump trips and the plant is stable the #1 seal on RR Pump 1A fails. After the initial actions are complete the #2 seal fails resulting in rising DW pressure and temperature. The crew attempts to isolate the reactor recirc loop but when the loop isolation valves are closed a preexisting flaw in the RR pump suction piping propagates resulting in a large unisolable LOCA.

The crew responds per EOP-1A and EOP-3A. Eventually level cannot be maintained and an Emergency Depressurization is required. When the LOCA signal occurs the RHR pumps fail to start and the Core Spray injection valves fail to automatically open as required as reactor pressure decreases. The operators manually start and align RHR and CS to refill the reactor vessel.

The scenario may be terminated when reactor water level is greater than 3 and containment spray/cooling is in service.

Page 70 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Simulator Setup Malfunction Description Delay Ramp Event Value Final RC06 RCIC Steam Line Break 2 0 30 MAIN FW FLOW SIGNAL OSCILLATION FW12B 5 min. 3 100 FT-50A FW15C Condensate Booster Pump Trip CBP 1C 4 False True RR03A Recirc Pump Shaft Binding RR Pump 1A 15 False True RR05A Recirc Pump Field Breaker Trip RRMG 1A 4 sec. 15 False True RR10A Recirc Pump #1 Seal Failure RR Pump 1A 3 min. 7 100 RR11A Recirc Pump #2 Seal Failure RR Pump 1A 5 min. 10 min. 7 100 RR32A Recirc Discharge Loop A Rupture 8 2 RH08A RHR Pump A Auto Start Failure Active True RH08B RHR Pump B Auto Start Failure Active True RH08C RHR Pump C Auto Start Failure Active True RH08D RHR Pump D Auto Start Failure Active True Core Spray Injection Valve Fails to Auto CS02A Active True Open. A Loop Core Spray Injection Valve Fails to Auto CS02B Active True Open. B Loop Remotes Description Delay Ramp Event Value Final Overrides Description Delay Ramp Event Value Final 02S48 Control Switch for RR-MO43A Active Open Open ZDIRRSWS6A[2]

02S49 Control Switch for RR-MO53A Active Open Open ZDIRRSWS7A[2]

Event Event Action Command When Recirc A Flow drops to 35,000 the shaft will bind 15 RRFT110[1] < 35000 followed by the tripping of the field breaker in 4 seconds.

Page 71 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Op-Test No.: Scenario No.: NRC 4 Event No.: 1 Page 1 of 2 Event

Description:

Swap CRD Pumps.

After the crew has assumed the watch and have settled into their roles and at the When to initiate:

direction of the lead examiner.

Time Position Applicants Action or Behavior CRS Directs the RO to start CRD Pump 1A and secure 1B CRD Pump.

Pulls Procedure 2.2.8 CRD Section 14 and calls the Station Operator in the CRD RO Pump area.

As the Station Operator report that the 1A CRD Pumps suction, min flow, Role and discharge valves are OPEN and that Pump and Motor oil levels are Play normal. Also report that the casing and suction filter have been vented.

RO Request Peer Check from BOP.

BOP Supplies Peer Checks RO At Panel 9-5 balances the CRD Flow Controller and places it to manual.

RO Select the 1A CRD Pump and Starts it by placing its control switch to START.

RO Contacts Station Operator and inquires if the pump is running normally.

Role Report as the Station Operator that the 1A CRD Pump is running Normally.

Play RO Selects and stops the 1B CRD Pump.

Slowly adjust the CRD Flow Controller to 50 gpm and places the controller to RO BALANCE.

RO Checks that the CRD parameters are normal.

END OF EVENT Page 72 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Notes Page 73 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Op-Test No.: Scenario No.: NRC 4 Event No.: 2 Page 1 of 2 Event

Description:

RCIC Steam Leak and Manual Isolation.

When the CRD Pumps have been swapped and the CRD Parameters are normal When to initiate:

and at the direction of the lead examiner.

Time Position Applicants Action or Behavior Updates the Crew that Annunciator 9-4-1 A-2 RCIC Steam Line D/P has been BOP received and pulls the Annunciator card.

Identifies steam leak on RCIC and recommends closing RCIC-MO-15, INBD STM BOP SUPP ISOL VLV and RCIC-MO-16, OUTBD STM SUPP ISOL VLV.

Directs closure of RCIC-MO-15, INBD STM SUPP ISOL VLV and RCIC-MO-16, CRS OUTBD STM SUPP ISOL VLV.

CRS Directs the BOP to monitor Reactor Building Temperatures and Radiation Levels.

Sends Rx Building Station Operator to investigate. He should provide him with BOP steam leak safety information.

As the Reactor Building Station Operator respond to the request and call him Role back in a few minutes, when he is not busy and report that in the area of the Play Steam Tunnel there is a sound of a decreasing steam leak.

Notes that RCIC Area temperatures have risen and are returning to normal after BOP the isolation. Updates the Crew that, that is an entry into EOP-5A.

Enters EOP 5A and notes that all of the actions have already been performed and CRS exits the EOP.

CRS Briefs the Crew concerning the RCIC Steam Leak.

Contacts the Work Control Center and reports the problem with RCIC Steam Line CRS leak.

Role As the WCC respond to the report and tell the CRS that a team will be formed Play to recover from the Steam Line leak.

Page 74 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Evaluates the condition against Tech Specs and determines that RCIC is CRS inoperable per T.S. 3.5.3, ensure HPCI is operable and restore to operable within 14 days.

END OF EVENT Notes Page 75 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Op-Test No.: Scenario No.: NRC 4 Event No.: 3 Page 1 of 2 Event

Description:

Oscillating Feedwater Flow Instrument When to initiate: When the RCIC Steam Leak has been isolated and at the direction of the lead examiner.

Time Position Applicants Action or Behavior Updates the crew that level and Reactor Feed pump is oscillating and this is an BOP entry into 2.4RXLVL. The Crew may catch that the feedwater flow instrument is oscillating causing the feed pump and level oscillations.

Enters 2.4RXLVL & 4.4.1 and assigns it to the BOP. The CRS will also enter the CRS procedure and ensure that the appropriate steps are performed. Establish action points including scram action setpoint.

Performs the steps of 2.4RXLVL and Updates the Scram Actions If RPV Level cannot be maintained above +12 inches on the Narrow Range Instruments or RPV CRS/BOP Level cannot be maintained below +50 inches on the Narrow Range instruments the reactor is to be scrammed.

BOP Identifies feedwater flow instrument is oscillating and updates the crew.

Determines that Attachment 2 should be performed for a failure of a Level/Steam/

BOP Feed/Flow Instrument.

After level has stabilized, perform one of following :

1. If affected instrument parameter displays a quality of red INV, then affected instrument has been automatically bypassed . No further action required.

BOP

2. If affected instrument parameter displays a quality of green, then perform following :Ensure LEVEL CONTROL SELECT switch is in 1 ELEMENT CONT.

3. Bypass selected instrument per Procedure 4 .4.1.

Page 76 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Contacts the Work Control Center and reports the problem with Oscillating CRS Feedwater Flow Instrument, requesting assistance for I&C, FRED, and system engineer.

END OF EVENT Notes Page 77 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Op-Test No.: Scenario No.: NRC 4 Event No.: 4 Page 1 of 2 Event

Description:

Condensate booster pump trip When to initiate: After the crew has recovered from the loss of the Steam Flow Instrument and at the direction of the lead examiner.

Time Position Applicants Action or Behavior BOP Reports that the 1C Condensate Booster Pump has tripped.

BOP Monitor reactor feed pump suction pressure.

RO or Sends the Station Operator to investigate the tripping of the 1C Condensate BOP Booster Pump.

Respond as the Station Operator and tell the Control Room Operator that Role you will go check the 1C Condensate Booster Pump out and report back that Play there is no obvious cause.

BOP Update the crew that this is an entry condition into 2.4MC-RF.

CRS Announce entry into 2.4MC-RF and assign it to the BOP.

RO Monitors Reactor plant parameters BOP Monitors condensate pressures and flows.

END OF EVENT Next Event Notes Page 78 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Page 79 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Op-Test No.: Scenario No.: NRC 4 Event No.: 5 Page 1 of 2 Event

Description:

A Reactor Recirc Pump Trip.

When to initiate: When directed by the lead evaluator.

Time Position Applicants Action or Behavior RO Updates the crew that the A Recirc Pump tripped.

Directs the RO to monitor for instabilities, Updates the crew that this is an entry CRS condition into 2.4RR and assigns it to the RO.

Updates the crew with Scram Actions of If both Recirc Pumps are tripped, and If RO abnormal neutron flux oscillations are observed while operating in the stability exclusion region. Scram and enter 2.1.5.

Displays the Power to Flow map on the CRT and evaluates the location of RO operation. It will take approximately 1 minute for the screen to update real time data.

Determines that the plant is operating in the Stability Exclusion Region of the RO Power to Flow Map.

RO Updates the Crew that the plant is operating in the Stability Exclusion Region.

RO Performs both Attachment 1 and Attachment 3 of 2.4RR.

RO Informs the CRS that LCO 3.4.1 Condition A entry is required.

States that he will have to insert the emergency Power Reduction Rods per RO Procedure 10.13.

Address Tech Specs and finds that with one RR Pump out of service, LCO 3.4.1 Condition A applies and that Required Action A.1 Initiate Action to Exit the Stability Exclusion Region immediately; Also Condition B Required Action B.1 Satisfy the CRS requirements of the LCO within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. That will required entry into LCOs 3.2.1 APLHGR Single Loop limits, 3.2.2 MCPR single loop operation limits, 3.3.1.1 RPS APRM reset for single loop settings and T 3.3.2 Single Loop Operation LHGR Limits. If missed, this should be asked as a follow-up question of the CRS.

Page 80 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 END OF EVENT Notes Page 81 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Op-Test No.: Scenario No.: NRC 4 Event No.: 6 Page 1 of 2 Event

Description:

Emergency Power Reduction When to initiate: The crew will perform an emergency power reduction to exit the stability exclusion region.

Time Position Applicants Action or Behavior Directs the RO to perform an emergency power reduction in accordance with CRS Procedure 2.4RR and monitor for abnormal neutron flux oscillations.

RO Inform CRS LCO 3 .4.1, Condition A, entry required.

Monitor for abnormal neutron flux oscillations by NOISE Program on PMIS RO computer to monitor peak-to-peak fluctuations of LPRMs and APRMs and SRM period, APRM, and LPRM indications.

Exit region by performing either or both of following: raise speed of operating RO recirculation pump(s) per Procedure 2 .1 .10 or insert Emergency Power Reduction Rods per Procedure 10.13.

RO Updates the crew when stability exclusion region has been exited.

Contacts the Work Control Center and FRED on entry to the stability exclusion CRS region.

END OF EVENT Next Event Notes Page 82 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Page 83 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Op-Test No.: Scenario No.: NRC 4 Event No.: 7 Page 1 of 2 Event

Description:

Reactor Recirc Pump Seal Failure When the plant is stable following the Recirc Pump trip and before the crew starts When to initiate: the actions to exit the Stability Exclusion Region of the power to flow map and at the direction of the lead examiner.

Time Position Applicants Action or Behavior Updates the crew on the failure of the #1 seal of the A Reactor Recirc Pump; BOP Annunciator 9-4-3 A-3 Recirc Pump A Seal Trouble. The BOP Operator may notice the pressure on the seal instrument above the RR controls before it alarms.

Updates the crew that this is an entry into 2.4RR again. Notes that the # 1 seal for BOP the A RR Pump has failed and that the #1 seal pressure has equalized with #2.

Enters Attachment 2 of 2.4RR, and Updates the crew with actions to take if both BOP seals fail. There are no real actions to take on the failure of one seal, but it does provide a good time to brief the crew on the possibility of the other seal failing.

Briefs Crew on the possibility for both seals to fail on the A Reactor Recirc Pump and what to expect. He will assign action points and parameters for the operators CRS to observe and take action, such as at 1.5 psig in the Drywell Scram the Reactor or isolate the RR Pump if there are indications that the other seal is failing Notes that the number 2 seal is also failing and attempts to isolate the pumps BOP suction and discharge valves. This failure is slow and will allow actions to be taken.

Updates the crew that the number 2 seal is failing and that Drywell Pressure is BOP rising slowly.

Updates the Crew that 2.4PC has been entered and directs the BOP to vent the containment per 2.4PC in an attempt to maintain pressure below 1.5 psig. This CRS activity may be directed before isolating the Recirc Loop or the other order can be expected.

Using 2.4PC operates the Primary Containment Vents to attempt to lower BOP containment pressure.

Page 84 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Attempts to isolate the A Reactor Recirc Pump by placing the RR-MO-43 and 53 BOP valve control switches to close. Notes that neither valve closed and reports same.

CRS When Containment is 1.5 psig the CRS directs the RO to scram the unit.

Pushes the manual scram pushbuttons and performs the scram actions. Places RO the Reactor Mode Switch to the Shutdown Position, trips a feed pump and makes a scram report - Reactor Shutdown, APRMs Downscale.

Enters EOP 1A and 2.4PC and assigns the BOP actions of 2.4PC. If DW CRS Pressure is above 1.84 psig will enter EOP-3A. At this point the RHR Pumps should have started, but they fail to.

Directs the RO to maintain RPV Level greater than +3 inches and Pressure less CRS than 1050 psig.

Monitors level and pressure and adjust the level control system to control level RO within the desired band of +3 to +54 inches.

Uses Turbine Bypass Valves to control pressure at 960 psig. The MSIV should RO remain open and the Bypass valves will work to control pressure around 960 psig.

Performs the steps of 2.4PC and ensures all DW FCUs are running and that REC-BOP MO-702 and REC-MO-709 are open. This is performed in the back panels.

May ask the RO if HPCI is needed for level control, gets permission from the CRS to trip and lock out HPCI. The operator will Place the Aux Oil Pump Control Switch BOP to START, then Manually trip HPCI by depressing the trip pushbutton until the turbine speed drops to 0 the places the Aux Oil pump control switch to PTL.

END OF EVENT Notes Page 85 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Page 86 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Op-Test No.: Scenario No.: NRC 4 Event No.: 8 Page 1 of 2 Event

Description:

Large LOCA When to initiate: When RR pump isolation is conducted by the crew.

Time Position Applicants Action or Behavior RO Notes Drywell Pressure rising rapidly and Level falling rapidly, updates the crew.

Controls HPCI to maintain reactor water level in the specified level band +3 to +54 BOP inches.

CRS At a Drywell Pressure of 1.84 psig will enter EOP-3A.

CRS Directs the use of HPCI to maintain Level +3 to +54 inches.

EOP 1A has a step right at the top of the level leg to ensure that Group isolations CRS ECCS and DGs initiate. CRS notes that the RHR Pumps are not running if not recognized by the board operators. Next Event 9 BOP Sends an operator to monitor the Diesel Generators.

Respond as the Station Operator and following a few minutes report that the Roll Play Diesels are running fine.

If the ADS timer starts, will direct the inhibiting of ADS, if the timer is not running, CRS then this actions will be performed later as level lowers.

If the ADS timer is running will place both ADS timer inhibit switches to Inhibit and BOP report back to the CRS when it is done.

Direct the BOP or RO to restore and maintain level above -150 inches using the CRS available injection systems.

RO and/or BOP will initiate and align all available injection sources and will ensure RO, BOP that the ones with a high enough discharge pressures are injecting into the RPV.

BOP,RO Updates the crew that level cannot be maintained above -150 inches.

CRS Directs the ADS Inhibit Switches to be placed in Inhibit Page 87 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 RO,BOP Places the ADS Inhibit switches to Inhibit and reports same.

BOP,RO Updates the crew at 0 inches Fuel Zone and dropping.

Directs the board operators to make available for injection any injection system CRS with pumps running.

RO,BOP Report back that all Injection Systems are available and with pumps running.

RO,BOP Updates crew that level is -183 inches Fuel Zone.

CRS Directs Emergency Depressurization.

RO,BOP Monitors and controls injection into the RPV as pressure drops.

RO,BOP Secure injection systems or throttles them back as RPV level starts rising.

END OF EVENT Notes Page 88 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Op-Test No.: Scenario No.: NRC 4 Event No.: 9 Page 1 of 1 Event

Description:

RHR pumps fail to Auto Start When DW Pressure is 1.84 psig the RHR Pumps should have started, so as soon When to initiate:

as they are noticed not running.

Time Position Applicants Action or Behavior Notes that The RHR Pumps failed to start when the 1.84 psig signal was received.

BOP,RO Confirms the auto start signal and manually started them. Letting them run on minimum flow.

BOP,RO Updates the crew that the RHR pumps failed to start on an initiation signal.

BOP, RO END OF EVENT Notes Page 89 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 Op-Test No.: Scenario No.: NRC 4 Event No.: 10 Page 1 of 1 Event

Description:

Core Spray Valves failed to open When to initiate: When RPV level is -183 inches Fuel Zone and injection systems are aligned and running.

Time Position Applicants Action or Behavior CRS Directs the BOP to open 6 SRVs.

Opens 6 SRVs one at a time and verifies that the amber light illuminates to indicate BOP that the valves are actually open.

BOP Updates that RPV Pressure is dropping rapidly.

BOP Notes that the Core Spray Valves failed to open and reports that to the CRS.

Monitors for RPV Pressure of 50 psig above Torus Pressure, and updates that BOP Emergency Depressurization is completed.

RO Monitors and controls injection into the vessel as pressure lowers.

END OF EVENT Notes Page 90 of 92

Swap CRD Pumps, RCIC STM Leak, Oscillating FW Instrument , CBP Lesson

Title:

trip, RR Pump Trip, RR Seal Failure, LOCA, CS Valves Fail to Auto Open, RHR pumps fail to Auto Start, ED Lesson No.: SKL0124822 Rev No.: 01 CREW CRITICAL TASKS TECHNICAL BASIS SAT UNSAT Inhibit ADS prior to auto initiation. An unnecessary ADS initiation would significantly change the mitigation strategy. Additionally, during certain conditions an ADS blowdown could result in a loss of adequate core cooling and/or exceeding the Technical Specification allowable cooldown rate.

When RPV level cannot be restored The MSCRWL is the lowest RPV water level at and maintained > -183", Emergency which the covered portion of the reactor core will Depressurize per EOP 2A. generate sufficient steam to preclude any clad temperature in the uncovered portion of the core from exceeding 1500°F. When water level decreases below MSCRWL with injection, clad temperatures may exceed 1500°F.

Ensure RPV water level restoration Submergence is the preferred method for cooling and maintenance above -158" (TAF) the core. All fuel nodes are then assumed to be when low pressure systems are covered with water and heat is removed by available. boiling heat transfer.

When systems required to maintain Submergence is the preferred method for cooling core submergence do not the core. All fuel nodes are then assumed to be automatically start, manually align the covered with water and heat is removed by systems. boiling heat transfer.

Page 91 of 92

Lesson

Title:

Lesson No.: SKL0124822 Rev No.: 01 IX. INITIAL CONDITIONS M. Plant Status:

1. 90% power End of Cycle.

2. Rod Sequence Information: Page:

Rod:

Notch:

N. Tech. Spec. Limitations in effect:

None.

O. Significant problems/abnormalities:

None P. Evolutions/maintenance for the on-coming shift:

1. Start 1B CRD Pump and secure 1A CRD Pump to allow Post maintenance Testing.

Page 92 of 92