ML13308B015
| ML13308B015 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/08/2013 |
| From: | NRC/RGN-III |
| To: | NextEra Energy Duane Arnold |
| Randal Baker | |
| Shared Package | |
| ML11354A410 | List: |
| References | |
| Download: ML13308B015 (88) | |
Text
Scenario Event Description ES-D1 DAEC 2013 NRC Scenario 1 2013 NRC Scenario 1 ES D
-1, Rev 01-14-13 Facility:
DAEC Scenario No.:
1 Op Test No.:
2013 NRC Examiners:
Operators:
SRO - RO - BOP - Initial Conditions:
Reactor is at 100% power Well Water Pump "C" inoperative because of suspected cracks in the discharge piping. Maintenance is investigating.
Turnover:
CV-1579, A Feed Reg Valve is presently locked.
"B" Feedwater Regulating Valve is in AUTOMATIC controlling RPV level per the ARP.
Investigation revealed the cause to be a blown fuse internal to the Feed Reg Valve controller.
Technicians have completed all troubleshooting and repairs on CV
-1579, Feed Reg Valve controller.
The crew is directed to reset the locked Feed Reg Valve in accordance with ARP 1C05A (F
-1), "A" or "B" Feed Reg Valve Position Locked
, Section 4.
Critical Tasks:
- 1. Lockout ADS
- 2. Terminate & Prevent Injection
- 3. Insert all control rods Event No. Malf. No.
Event Type* Event Description 1 R - RO R -SRO Lower power to 95% to allow for any power excursions when CV-1579, A Feed Reg Valve lockout is reset.
2 FW16a (reset) N - BOP N - SRO Reset the locked CV-1579, A Feed Reg Valve IAW ARP 1C05A (F-1) 3 NM11B I - RO I - SRO TS - SRO "B" APRM Flow Unit fails downscale 1C05A, E-2, TS 3.3.1.1-1 4 DI-ED-051 (TRIP then return to NAC ED07E C-BOP C-SRO TS-SRO 1B303 Trip with failure to auto transfer to the alternate power supply (Power will still be lost to "A" S BLC, "A" SBGT, "A" Core Spray and RHR components
) ARP 1C08A C
-5 and D-5, TS 3.8.7.A
Scenario Event Description ES-D1 DAEC 2013 NRC Scenario 1 2013 NRC Scenario 1 ES D
-1, Rev 01-14-13 5 FW12A C-RO C-SRO "A" Feed Reg Valve failure AOP 644 6 AD01G C - BOP C - SRO SRV leak and Fast Power Reduction IAW IPOI
-4, valve does NOT close a scram is required AOP 683, IPOI-5, EOP-2, (There should may not be sufficient time to enter TS 3.4.3.A) 7 RP05A,B,C,D,E M-ALL Electrical ATWS
, EOP-ATWS 8 SL01B C-BOP C-SRO "B" SLC Pump trips after starting SEP 304 * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Scenario Event Description ES-D1 DAEC 2013 NRC Scenario 1 2013 NRC Scenario 1 ES D
-1, Rev 01-14-13 DAEC 2013 NRC Scenario #1 The scenario begins with the plant at 100% power.
The crew is directed to lower power to 95% to allow for any power changes that may occur when they reset the locked Feed Reg Valve in accordance with ARP 1C05A (F
-1). After the Feed Reg valve is reset and proper operation verified, the "B" APRM flow unit will fail downscale causing a half scram and rod block. The crew must diagnose the failure and bypass the APRM flow unit. The SRO will enter Technical Specifications 3.3.1.1 for the failed instrument.
After the Technical Specification is addressed breaker 1B303 will trip and the automatic transfer to the alternate power supply will fail, resulting in a loss of an Essential Bus 1B34. This results in a loss of the "A" S BLC, "A" SBGT, "A" side Core Spray and RHR components.
The crew will enter the ARPs to take actions and the SRO must address Technical Specification TS LCO 3.8.7
.A. The SRO may discuss the need to enter TS LCO 3.0.3 when the swing bus is de
-
energized. The crew may recover 1B34A/1B44A LPCI Swing Bus, by manually closing 1B4401.
After the actions are taken for the trip of 1B303
, a previous problem with the "A" Feedwater Regulating Valve will re-occur and the controller will fail
. The operators must take manual control of feedwater to control RPV level IAW the abnormal procedure AOP
-644, FW/Condensate Malfunction. After the crew has established manual control of RPV water level an SRV will fail open requiring a power reduction.
The SRO may address Technical Specifications but the SRV will not close requiring a reactor scram. An RPS failure will occur and an electrical ATWS will result. EOP-1 and EOP
-ATWS will be entered. The "B" SLC Pump will trip shortly after starting and the crew must implement SEP 304, Boron Injection Using RWCU. The crew will take actions to Lockout ADS (Critical Task), Terminate and Prevent Injection (Critical Task) and insert all control rods (Critical Task)
.
The scenario may be terminated when all rods are full in and RPV level has been restored to normal.
2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 1 of 23 EXAMINATION SCENARIO GUIDE (ESG)
SITE: DAEC LOWER REACTOR POWER, RESET THE LOCKED A FEED REG VALVE
, APRM FLOW UNIT "B" FAILS, 1B303 TRIP WITH FAILURE TO AUTO TRANSFER, "A" FEED REG VALVE FAILURE
, ELECTRICAL ATWS, STANDBY LIQUID CONTROL PUMP TRIP . ESG NRC #1 REV 0 PROGRAM: OPERATIONS
- COURSE: INITIAL LICENSED OPERATOR #: TOTAL TIME:
90 MINUTES Developed by:
Edwin Bowles 11/14/12 Instructor Date Validated by:
SME/Instructor Date Reviewed by:
Operations Manager Date Approved by:
Training Supervisor
-Operations Date 2013 NRC ILT Scenario #1 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 2 of 23 GUIDE REQUIREMENTS Goal of Training:
The goal of this scenario is to evaluate ILT students during the NRC Exam with 3 man crew.
Learning Objectives:
There are no formal learning objectives Prerequisites:
None Training Resources:
Simulator Simulator Booth Instructor Phone Talker Simulator Floor Instructor
References:
None Commitments:
None Evaluation Method: Dynamic Simulator Operating Experience:
None Related PRA Information:
Initiating Event with Core Damage Frequency:
N/A due to exam security Important Component s: N/A due to exam security Important Operator Actions with Task Number:
N/A due to exam security
2013 NRC ILT Scenario #1 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 3 of 23 SCENARIO SUMMARY The scenario begins with the plant at 100% power.
The crew is directed to lower power to 95% to allow for any power changes that may occur when they reset the locked Feed Reg Valve in accordance with ARP 1C05A (F
-1). After the Feed Reg valve is reset and proper operation verified, the "B" APRM flow unit will fail downscale causing a half scram and rod block. The crew must diagnose the failure and bypass the APRM flow unit. The SRO will enter Technical Specifications 3.3.1.1 for the failed instrument.
After the Technical Specification is addressed breaker 1B303 will trip and the automatic transfer to the alternate power supply will fail, resulting in a loss of an Essential Bus 1B34. This results in a loss of the "A" S BLC, "A" SBGT, "A" side Core Spray and RHR components.
The crew will enter the ARPs to take actions and the SRO must address Technical Specification TS LCO 3.8.7
.A. The SRO may discuss the need to enter TS LCO 3.0.3 when the swing bus is de
-energized. The crew may recover 1B34A/1B44A LPCI Swing Bus, by manually closing 1B4401.
After the actions are taken for the trip of 1B303
, a previous problem with the "A" Feedwater Regulating Valve will re-occur and the controller will fail
. The operators must take manual control of feedwater to control RPV level IAW the abnormal procedure AOP
-644, FW/Condensate Malfunction. After the crew has established manual control of RPV water level an SRV will fail open requiring a power reduction.
The SRO may address Technical Specifications but the SRV will not close requiring a reactor scram. An RPS failure will occur and an electrical ATWS will result. EOP
-1 and EOP-ATWS will be entered.
The "B" SLC Pump will trip shortly after starting and the crew must implement SEP 304, Boron Injection Using RWCU
. The crew will take actions to Lockout ADS (Critical Task), Terminate and Prevent Injection (Critical Task) and insert all control rods (Critical Task)
.
The scenario may be terminated when all rods are full in and RPV level has been restored to normal.
2013 NRC ILT Scenario #1 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 4 of 23 SCENARIO OUTLINE:
BOOTH INSTRUCTOR ACTIONS 1 SIMULATOR SET UP: (perform set up per the "Simulator Setup Checklist", including entering actions items per the "Simulator Input Summary.")
Start Sim View / Data Capture Program for EXAM ONLY 1.1 General Instructions
- a. Identify any extra copies of student materials (STPs, OIs) that are needed for this training activity.
- b. Reset to IC (number or plant condition).
- c. Verify event trigger definitions.
- d. Which malfunction files to restore for setup, if any
. e. Which override files to restore for setup, if any
. f. Which remote functions files to restore for setup, if any
. g. Pull sheet setup should be labeled MOL and instructions as necessary.
- h. Leakage calculations, if required
. i. Control panel setups, including valves/equipment to tag out
. j. Which STPs are being worked, and what steps are completed
. k. Verify the availability of sufficient copies of STPs in the back panel hanging files
. l. LCO and Safety Function Determination paperwork, for any outstanding LCOs
. m. Miscellaneous Systems Status Board updated for plant conditions
. n. If the ESG is going to be utilized as a DEP PI opportunity, contact security to determine if they will be able to participate and make EAL notifications.
- o. Mark up a copy of ARP 1C05A, F
-1 up to but not including step 4.1
- p. Place a MIP tag on "C" Well Water Pump control switch
- q. Reset GAF/Recorders by running schedule file
- r. On the VAX Computer run the fix 4 application.
2013 NRC ILT Scenario #1 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 5 of 23 1.2 EVENT TRIGGER DEFINITIONS:
Trigger No. Trigger Logic Statement Trigger Word Description 5 ZDISLHS2613 == 1 SBLC Pump "B" Trips 5 secs after the Pump & Squib Valve key lock switch is placed in Pumps A & B Run 10 ZDIRPC71AS5(1)
Scram Reset Switch to Gp 1 & 4
1.3 MALFUNCTIONS
Time Malf. No.
Malfunction Title Delay Ramp ET Initial Value Final Value Delete in Setup FW16A FW Reg Valve Lockup
-FWRV A Active Reset 10 sec Setup RP05A RPS Scram Circuit Failure (ATWS)-Auto Scram Failure 15 sec 10 Active Active Setup RP05B RPS Scram Circuit Failure (ATWS)-Manual Scram Failure 15 sec 10 Active Active Setup RP05C RPS Scram Circuit Failure (ATWS)-ARI Failure 15 sec 10 Active Active Setup RP05D RPS Scram Circuit Failure (ATWS)-RPS Fuse removal Failure 15 sec 10 Active Active Setup RP05E All Individual Rod Scram Switches Fail 15 sec 10 Active Active Setup ED07E Any Bus Auto Transfer Failure
- Bus 1B34A/44A Active Active As Dir NM11B RECIRC FLOW UNIT FAILS
- UNIT B 1 As Is 0 As Dir FW12A FW Reg Valve Controller Failure (Auto) - FWRV A 1 min 3 As-Is 100% As Dir AD01G Reac Press RLF or Safety Valve Leak - PSV4406 4 Inactive 50% As Dir SL01B STANDBY LIQUID PUMP TRIP
- PUMP B 5 Inactive Active 2013 NRC ILT Scenario #1 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 6 of 23 OVERRIDES:
Time Override No. Override Title Delay Ramp ET Initial Value Final Value Delete In Setup DO-SW-055 HS-4483A(1) WELL PUMP 1P
-58C (GREEN)
On Off Setup DO-SW-056 HS-4483A(2) WELL PUMP 1P
-58C (RED)
On Off As Dir DI-ED-051 1B303 FEEDER BREAKER 1B303 TO MCC 1B34 2 NAC TRIP 10sec 1.5 REMOTE FUNCTIONS:
Time Remote No. Remote Title Delay Ramp ET Initial Value Final Value Delete In
FLOOR INSTRUCTOR ACTIONS
Simulator Pre
-brief:
2.1 Individual position assignments
2.2 Simulator training changes since last module (N/A)
2.3 Simulator hardware and software modifications/problems that may impact training
2013 NRC ILT Scenario #1 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 7 of 23 TURNOVER INFORMATION Day of week and shift Today Day Shift Weather conditions Warm, spring day No watches / warnings (Plant power levels)
MWT 1906 MWE 630 CORE FLOW m/hr Thermal Limit Problems/Power Evolutions None Plant Risk Status CDF Baseline Color Green Existing LCOs, date of next surveillance None STPs in progress or major maintenance CV-1579, "A" Feed Reg Valve is presently locked.
Last shift there was a blown fuse that caused a loss of signal and valve lockup. I & C has replaced the fuse and directed that the valve be returned to service. They are standing by waiting for the valve to be returned to service so they may observe its operation.
Well Water Pump "C" inoperative because of suspected cracks in the discharge piping. Maintenance is investigating.
Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment CV-1579, "A" Feed Reg Valve lock
-out is to be reset and the Feed Reg Valve returned to service. Operations management has directed that the BOP operator should reset the valve while the ATC operator monitors the reactor for any level/power transients.
Prior to resetting the Feed Reg Valve lock
-out the crew is directed to lower reactor power to 95% to prevent any power changes that may be caused by a level transient from exceeding limit. The previous crew started the recovery in ARP 1C05A, F
-1 and has completed the procedure up to step 4.1.
Comments, evolutions, problems, core damage frequency, etc.
-1), CV-1579, "A" Feed Reg Valve lock
-out is to be reset and the Feed Reg Valve returned to service.
2013 NRC Scenario #1 SCENARIO TIMELINE 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 8 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Shift Turnover
COMPLETE TURNOVER:
Provide Shift Turnovers to the SRO and ROs. a. Review applicable current Plant Status b. Review relevant At
-Power Risk status c. Review current equipment status and evolutions to be preformed this shift d. Verify crew performs walk down of control boards and reviews turnover checklists Get familiar with plant conditions.
SRO will provide beginning of shift brief to coordinate the tasks that were identified on the shift turnover.
EXAMINER NOTE: Continue to next event at examiners direction
2013 NRC Scenario #1 SCENARIO TIMELINE 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 9 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #1 Lower Power with Reactor Recirc to 95%
Booth Instructor respond as plant personnel and respond as necessary:
Role Play:
If necessary, call in as Operations Manager to prompt crew to lower power SRO Provides a reactivity brief (may be performed before scenario begins).
Communicates with Real Time Desk.
Provide direct oversight of reactor power reduction
. Directs reducing power with control rods to get below load line.
When below load line directs lowering reactor power with recirc flow.
RO Monitors process computer point C136 to determine % of load line Inserts control rods in reverse of sequence to get below load line Lowers power with Recirc Pump Flow Controllers IAW IPOI
-3, Section
- 5. To lower recirc flow, verify the digital display to the S PERCENT SPEED DEMAND variable by pressing the display switch, then rotate the A[B] MG SET SPEED CONTROL SIC 9245A[B] knobs on 1C04 counter clockwise in small equal increments.
Keep loop flows balanced by comparing the Recirc Pump discharge flow on FI 4634A vs. FI 4634B or A pump (red channel) vs B pump (black channel) on FR
-4635 Monitors critical plant parameters
- power, pressure, level BOP Monitors balance of plant equipment.
Provides peer check for RO during power reduction
. EXAMINER NOTE: Continue to next event at examiners direction
2013 NRC Scenario #1 SCENARIO TIMELINE 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 10 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #2 Reset the locked A Feed Reg Valve IAW ARP 1C05A (F
-1)
Booth Instructor respond as plant personnel and respond as necessary:
Attachment 1, CV
-1622 Position vs. Demand has the CV
-1622 Demand "V" on the horizontal (X) axis and the ZI-1622 Valve Position (%) on the vertical (Y) axis. (Attached at the last page of the scenario)
Crew Reviews ARP 1C05A (F-1) SRO Directs reset the locked Feed Reg Valve in accordance with ARP 1C05A (F-1), "A" or "B" Feed Reg Valve Position Locked, Section 4.
RO Monitors Reactor Power, Pressure and Level Performs peer checks for BOP actions BOP Reviews ARP 1C05A (F
-1) Verifies that the controller LED displays for the locked Feed Reg Valve are lit. Verify the Feedwater Lockout Relay amber light above the associated Lockout Relay is dim.
At HC-1579 A FEED REG VALVE MANUAL/AUTO TRANSFER for the locked Feed Reg Valve
- o Places in MANUAL ('M' is selected on the A/M pushbutton).
o Selects 'Y' on the display.
o Adjusts the 'Y' bias setting to zero.
Obtains the current Feed Reg Valve position using ZI
-1579. Using Attachment 1 of the ARP, determines the appropriate M/A station controller output signal 'V' (Attached)
At HC-1579, performs the following:
o Selects 'V' on the display to indicate controller output.
o Adjusts 'V' to the value obtained from Attachment 1.
Reset the lockout using HSS
-1579 2013 NRC Scenario #1 SCENARIO TIMELINE 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 11 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #2 cont.
The controller will automatically select "V" when the controller is placed in "M" (manual).
BOP cont. Verifies the Feedwater Lockout Relay amber light is no longer lit
. Notifies the crew that FW Reg Valve Lockout is reset May manually adjust feed reg valve to limit level transient Transfers CV
-1579 to AUTO Verifies the A FEED REG VALVE CONTROLLER HC
-1579 is in MANUAL. Selects 'V' on the display for A FEED REG VALVE CONTROLLER, HC-1579. Selects 'V' on the display for MASTER FEED REG VALVE CONTROLLER, LC
-4577. Matches the Feedwater Reg Valve controller top meter display with the MASTER FEED REG VALVE CONTROLLER top meter display by adjusting the potentiometer on HC
-1579. Verifies proper response of the Feedwater Regulating valve by monitoring ZI
-1579. Selects AUTO on HC
-1579[1621].
Selects 'S' on the display for A[B] FEED REG VALVE CONTROLLER, HC1579. Selects 'S' on the display for MASTER FEEDREG VALVE CONTROLLER, LC
-4577. When both Feed Reg Valves are in AUTO on the Master Feed Reg Valve Controller, adjust biases as necessary, per OI 644, Section 4.2.
Notifies Crew that the "A" FW Reg Valve is in service in auto EXAMINER NOTE: Continue to next event when the A FW Reg Valve is in service in auto and candidate reports are completed
2013 NRC Scenario #1 SCENARIO TIMELINE 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 12 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #3 B APRM Flow comparator fails downscale
Booth Instructor: Insert Trigger:
1 This will cause the B APRM flow comparator failure and resulting rod block and half scram CREW Respond to Annunciator s 1C05A, E-2 APRM FLOW UNIT UPSCALE
, INOP OR COMPARE ERROR 1C05B, A-6, ROD OUT BLOCK 1C05B, E-4 "B" RPS BACK UP SCRAM HALF SCRAM 1C05B, A-2 "B" RPS AUTO SCRAM 1C05B, B-2, APRM B, D, or F UPSCALE TRIP OR INOP 1C05A, C-2 APRM UPSCALE 1C05A, A-5 NEUTRON MONITORING SYSTEM TRIP Indications
- 1C05 AMBER "COMPAR" lights for B/D Flow Units Diagnoses B flow unit as the probl em SRO Direct actions IAW ARP to Bypass the B flow unit Verify Reactor Power and Reactor Total Core Flow are within operating limits at 1C05 Verify Recirculation Loop and Recirc Pump discharge flows are within operating limits at 1C04.
At 1C37, confirm the flow unit UPSCALE/INOP condition.
If a flow unit instrument fault is indicated, place the FLOW UNIT ROD BLOCK BYPASS switch in the position for the malfunctioning flow unit Directs reset of half scram Verify that the alarm and rod withdrawal block conditions clear.
Enters T.S. 3.3.1.1 Condition A
, Table 3.3.1.1-1. Function 2B May also enter TRM 3.3.2.
Condition A, Function 1A
2013 NRC Scenario #1 SCENARIO TIMELINE 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 13 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #3 cont. RO Verifies reactor power and core flow are within operating limits When directed bypasses the B flow unit o At 1C05, places Flow Unit Rod Block Bypass (C51B-S8) in the B position o Confirm BYPASS light for selected Flow Unit is on When directed resets the half scram IAW OI 358 as follows:
Turns the REACTOR SCRAM RESET switch C71A
-S5 first to Group 1 and 4 [Group 2 and 3] then to Group 2 and 3 [Group 1 and 4] to reset the scram signal.
Verifies the eight white SCRAM GROUP indicating lights are ON Verifies Annunciator s 1C05A, A-2 and E-4 reset
BOP Checks backpanel 1C37 (APRM F Cabinet) indications and verifies B comparator is the probl em When directed o At 1C37, perform the following at "B" Flow Unit.
o Place mode switch (S1) to ZERO o Confirm Flow Unit INOP light is on EXAMINER NOTE: Continue to next event at examiners direction
2013 NRC Scenario #1 SCENARIO TIMELINE 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 14 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #4 1B303 trip Booth Instructor:
respond as plant personnel and respond as necessary:
When directed by Lead Evaluator:
Insert Trigger: 2 This will result in a loss of power to MCC 1B34 Examiner Note:
Power will still be lost to "A" SLC. "A" SBGT, and "A" side Core Spray and RHR components
Role Play:
When sent to investigate 1B303 Breaker report that there is no apparent reason the breaker tripped. It looks like a probable mechanical trip CREW Responds to Annunciator s: 1C-08A, D-5, MCC 1B34A Tie BKR 1B3401 Trip 1C08A, C-5, LC 1B3 Breaker 1B301, 1B302 1B303 OR 1B304 Trip Diagnose trip of Breaker 1B34 SRO Directs actions IAW ARP Investigate locally Determines 1B34A is de
-energized and directs an attempt to close 1B4401 one time. Enters TS LCO 3.8.7. Condition A.
- AC Power
-8 hours May enter TS LCO 3.0.3 (ECCS) until bus power is restored because of the loss of power to the A side ECCS valves and the B RHR injection valves RO Monitors reactor power pressure and level Helps to diagnose the failure of 1B4401 to CLOSE when 1B303 TRIPS.
-5 Table 1 cause 7 (Tie Bkr Fails to close)
Dispatches field operator to investigate Diagnoses failure of Tie Bkr 1B4401 to auto close When directed, closes Tie Bkr 1B4401 Reports to CRS that Tie breaker 1B4401 is closed EXAMINER NOTE: Continue to next event at examiners direction and after the SRO has addressed the Technical Specifications
2013 NRC Scenario #1 SCENARIO TIMELINE 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 15 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #5 Feed Reg Valve "A" controller fails requiring manual control
If sent to investigate the "A" FRV Booth Instructor:
respond as plant personnel as necessary:
BOOTH INSTRUCTOR:
When directed by examiner:
Insert Trigger:
3 This results in FRV "
A" failing high on a slow ramp Wait 3 minutes then report that there is no abnormal condition noted at the "A" FRV.
CREW Responds to indications of FRV "A" failure:
Reactor Feed Pump "A" high amps FRV "A" Position Indication Open is higher than the "B" FRV Annunciator 1C05A-D1 - Reactor Vessel Hi/Lo Level Rising RPV level SRO Directs entry to AOP
-644 - FW/Condensate Malfunction Directs taking manual control of FW RO As directed or as immediate operator actions, takes manual control of Feedwater by placing controlle r(s)r in Manual Maintains RPV level 186 to 195 inches Determines that the "A" FRV has failed in Automatic.
BOP Monitors balance of plant equipment Assists RO in completing the actions associated with AOP 644.
Dispatches operator to investigate failure of the "A" FRV. EXAMINER NOTE: Continue to next event at examiners direction
2013 NRC Scenario #1 SCENARIO TIMELINE 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 16 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #6 SRV leak and Fast Power Reduction IAW IPOI-4, valve does NOT close a scram is required BOOTH INSTRUCTOR:
When directed by examiner:
Insert Trigger:
4 This results in SRV "PSV 4406" leaking with a large leak (50%)
EXAMINER NOTE: RPV High Level Alarm is expected due to this malfunction CREW Responds to
- Annunciator 1C03A, C-5, SRV/SV TAILPIPE HI PRESS OR HI TEMP SRV PSV 4406 Amber light will momentarily light Lower steam flow on "D" steam line
SRO Directs action IAW AOP 683 - Abnormal SRV operation Directs BOP to check Panel 1C21 temperature indications May enter AOP 255.2 - Power/Reactivity Abnormal Change May direct that core flow be lowered to 39mlbm/hr IAW IPO
-4, Fast Power red uction May direct inserting control rods to stay below MELLLA Determines SRV remains partially open by rising tailpipe temperature Directs placing the "B" Loop of RHR in torus cooling Enter EOP 2 on torus temperature May enter T.S. 3.4.3.A Before Torus temperature reaches 110°F directs Reactor scram and entry to IPOI
-5 Directs RO to take IPOI
-5 actions Directs RPV level band of 170"
-211" with Condensate and Feedwater
2013 NRC Scenario #1 SCENARIO TIMELINE 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 17 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #6 cont. RO May perform a fast Power Reduction IAW IPOI
-4 and lowers recirc flow to 39mlbm/hr Maintains RPV level in normal band Scrams the reactor as directed using both RPS Pushbuttons Places Mode Switch to Shutdown Diagnose that all rods did not fully insert and inform the CRS.
And report that an "Electrical ATWS" has occurred.
BOP Identifies SRV "PSV 4406" indicates partially open Check Panel 1C21 temperature indications and reports rising tailpipe temperatures on SRV "PSV 4406" Monitors and reports torus temperatures Places Torus Cooling in service as follows:
o Starts RHR pump B or D o Place keylock HS
-1932 Outboard Torus Cooling/Spray Valve handswitch in OPEN and verify valve opening o Open MO-1934, Torus Cooling/Test Valve Verifies Turbine Trip Monitors BOP equipment and containment parameters
2013 NRC Scenario #1 SCENARIO TIMELINE 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 18 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Events #7 and #8 Electrical ATWS, SBLC Pump trip
Booth Instructor:
Examiner Note:
At some point after the scram the lowering Main Condenser vacuum will cause a Group 1 and Bypass Valve isolations.
NOTE: there is no specified order to implement the RIPs. The Crew may assess the effectiveness of the RIPs based on plant conditions. But the crew should recognize that only manually inserting control rods with RMCS, drifting the control rods, and Manually venting the scram air header will insert all of the control rod
- s.
CREW Respond to ATWS and loss of SBLC SRO ENTER EOP 1 and transition to ATWS
- RPV Control Lock out ADS (Critical Task)
. May direct installation defeat 15, Group 1 Override which includes bypassing the condenser high back pressure trip Directs defeat 11 to maintain Nitrogen to the drywell IF a scram is required and Reactor power is above 5%, THEN reduce power below 5% using one or more of the following methods:
Manual scram signal Inserting control rods using RIPs Manual ARI signal Injection of Boron o Per the /Q leg:
o Mode switch to shutdown.
o Recirc to minimum.
o Initiate ARI.
o Initiate SBLC. After determination that SBLC pumps have failed, direct alternate Boron Injection via RWCU SEP 304.
o Initiate the Rod Insertion Procedures, RIPs.
Per the /L leg:
Assess power greater than 5% and enter Power Level Control.
Direct terminate and prevent injection until conditions allow re
-injection (Critical Task).
Direct controlling RPV level between
-25 in. and +15 in.
2013 NRC Scenario #1 SCENARIO TIMELINE 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 19 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Events #7 and #8 cont.
SRO cont. When all of the control rods are inserted, Exit ATWS and re
-enter EOP 1 Enter EOP 1 and perform the following:
o Maintain level 170 to 211.
RO Terminate and prevent injection until conditions allow re
-injection (Critical Task).
Secure and prevent injection from:
Condensate and feed Manually initiates ARI, diagnoses ARI failure and manually trips the recirc pumps. Start the SBLC pump and monitor Boron injection o Diagnose trip of the "B" SBLC Pump o Report the loss of SBLC to the crew o Installs DEFEAT 14 by placing the keylock switch at Panel 1C52, in the BYPASS position o Restores the RWCU system to operation o Dispatch an operator to the IC82 Panel to backwash the RWCU system Start the "B" CRD Pump Place CRD Flow Controller FC
-1814 in MANUAL and run the output to maximum Observe increased cooling water flow on FI-1838 and cooling water dp increase on PDI
-1832A Throttle open MO
-1830, DRIVE WATER P CONTROL, as necessary to maximize cooling water flow and pressure Monitor for inward rod motion and report rod motions when it occurs
2013 NRC Scenario #1 SCENARIO TIMELINE 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 20 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Events #7 and #8 cont.
Role Play:
If called as the operator to vent the scram air header, acknowledge the call, and state that you are getting the adjustable wrench and will proceed to the scram air header, then delay.
RO cont. Insert control rods by manually inserting control rods with RMCS and/or drifting the control rods (Critical Task).
RO/BOP must direct NLO to Manually Vent the Scram Air Header.
May initiate RPV injection with RCIC or condensate and feedwater
. Controls RPV level between
-25 in. and +211 in. BOP RO/BOP must direct NLO to Manually Vent the Scram Air Header.
Lock out ADS (Critical Task)
. Installs Defeat 1 5 as follows:
At Panels 1C15 and 1C17 places the keylock switch es in OVERRIDE At Panels 1C15 and 1C17 places the keylock switches in OVERRIDE to bypass the High Condenser Vacuum isolation Terminate and prevent injection until conditions allow re
-injection (Critical Task).
Secure and prevent injection from:
HPCI Core Spray and RHR.
Per the /P leg Installs Defeat 11 as follows:
At Panel 1C35, place GROUP 3 OVERRIDE keylock switch es in OVERRIDE OPEN position.
Confirm CV
-4371A opens by observing valve position.
Maintain pressure stable.
Enter SEP 304 if directed.
2013 NRC Scenario #1 SCENARIO TIMELINE 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 21 of 23 Scenario Termination Criteria All control rods inserted and RPV water level restored to Maintain level 170 to 211. Event Classification Site Area Emergency per SS2
.1, Failure of Reactor Protection System Instrumentation to Complete or Initiate an Automatic Reactor Scram Once a Reactor Protection System Setpoint Has Been Exceeded and Manual Scram Was NOT Successful
- END OF SCENARIO ***
SEG Validation Checklist 2013 NRC Exam Scenario #1 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 22 of 23 Correct IC or plant status identified.
Shift turnover forms filled out (both CRS/OSM and NSOE) if required.
Additional documents are prepared (STPs, Work Orders, LCO Paperwork).
Tasks and Objectives have been verified to be correct.
Plant PRA initiating events, important equipment and important tasks are identified.
SOMS tags identified and included in setup instructions.
Special setup instructions identified; handswitch manipulations, procedure markups, alarm borders, 3D case available, computer points substituted, etc.
Setup files correctly called out.
Malfunction list is accurate.
Override list is accurate.
Remote function list is accurate.
Event triggers are accurate.
Time/Notes section is accurate and includes all reasonable cues that may be given to initiate an action. Cues are unambiguous and provide a definitive moment to take action. Instructor Activity section is accurate and complete: Actions are clearly defined for Booth or Floor instructor.
Role-playing is clearly noted.
The sequence of events is completely and concisely narrated even if it takes no instructor action.
Automatic actions that require verification are noted.
Reasonable alternate paths are considered and included.
Event trigger activation is distinguished from narrative text (Bold font
) Noun descriptions of actions that occur on event trigger initiation are complete, for example "-set ET 3 to TRUE which activates Override 1B303 Feeder Breaker 1B303 to MCC 1B34 TRIP then return to NAC) which removes power from Essential Bus 1B34."
Other simulator control actions are clearly distinguished from narrative text, for example "-Event Trigger 6 when loads are shifted from the Auxiliary Transformer. This inserts the Circ Water Pump trips.
Student and Instructor copies of worksheets or other training activities are verified correct and electronically attached to the file if appropriate.
SEG Validation Checklist 2013 NRC Exam Scenario #1 2013 DAEC NRC Scenario 1 Script, Rev 01-14-13 Page 23 of 23 Expected Student Response Section is accurate and complete:
Critical tasks are accurate and clearly identified. Probable critical tasks are also listed with logical connection to the scenario; for example "If the crew fails to get all the rods inserted before ED the critical task becomes-" (N/A as appropriate)
Tasks are clearly noted and properly numbered as appropriate.
Knowledge objectives are clearly noted and properly numbered as appropriate.
Expected as well as probable student responses are listed with logical connection to the scenario. (N/A as appropriat e) Actions are appropriately delineated by position(s); OSM, CRS, STA, RO, NSOE, Fire Brigade Leader, At the Controls Operator, etcetera. (N/A as appropriate)
Success paths are procedurally driven unless specific training not requiring procedures is desired and delineated. Procedural discrepancies are identified and corrected before training is given.
Responses for all communications to simulated personnel outside the Control Room are included, based on procedural guidance and standard operating practices.
Actions are listed using a logical order; by position and chronology. (N/A as appropriate)
Operating Experience, Human Performance Tools and Operator Fundamentals topics are included when appropriate.
Crew Performance Criteria follow the same chronology as the student responses, are complete and accurate. (For ESGs only)
For Walkthrough and Training Mode Scenarios with pre
-planned pauses, sufficient information is presented to allow the instructor to meet the goal of the training.
Turnover information (as required) is correct:
Day and shift are appropriate.
Weather conditions do not conflict with malfunctions.
Power levels are correct.
Thermal limit problems and power evolutions are realistic and include a reason for any downpower.
Existing LCOs include start date, remaining time and actions.
Plant Risk Assessment (CDF and Color).
STPs are appropriate for day and shift.
Core Damage Frequency has been properly calculated and listed to 3 decimal places. Maintenance is realistic for plant conditions.
Comments, evolutions, problems, etc, includes extra personnel (licensed/non
-licensed if necessary), any condition that affects the flow of the scenario and any condition that does not fit in another category.
SME/Instructor Date SME/Instructor Date SEG Validation Checklist 2013 NRC Exam Scenario #1 Crew: Instructors:
OSM ____________________________
Booth ________________________________
CRS ____________________________
Floor __________________________
STA _________________________________
_ Extra ________________________________
1C05 ____________________________
1C03 ____________________________
BOP ____________________________
Crew Comment:
Resolution:
Crew Comment:
Resolution:
NOTE: Following approval of SEGs, this page may be discarded.
SEG Validation Checklist 2013 NRC Exam Scenario #1 Crew Comment:
Resolution:
Crew Comment:
Resolution:
Crew Comment:
Resolution:
NOTE: Following approval of SEGs, this page may be discarded.
ATTACHMENT 1
Scenario Event Description ES
-D1 DAEC 2013 NRC Scenario 2 2013 NRC Scenario 2 ES D
-1, Rev 01-02-13 Facility:
DAEC Scenario No.:
2 Op Test No.:
2013 NRC Examiners:
Operators:
SRO - RO - BOP - Initial Conditions:
Startup in progress IAW IPOI
-02 - At step 20 of pull sheet Reactor Pressure is about 390 psig Turnover:
Continue with startup IAW IPOI
-02, Step 4.2. Step 10 I & C is performing a visual check on NI cabinets RPV level is being maintained low in the green band in preparation for startup of first feedwater pump Two Condensate Demineralizers are in service and two are in Standby Place the "B" Feedwater pump in service IAW OI 644 Critical Tasks:
- 1. Initiate a manual scram prior to torus level reaching 7.1 feet
- 2. Emergency depressurize prior to torus level reaching 7.1 feet Event No. Malf. No.
Event Type* Event Description 1 N/A N - BOP N - SRO Startup the "B" feedwater pump IAW OI 644.
2 N/A R - RO R - SRO Continue startup by withdrawing control rods IAW IPOI
-02 3 RD02-1819 C - RO C- SRO Stuck Control Rod
AOP 255.1 4 CS HS-2103 C-BOP C-SRO TS-SRO "A" Core Spray Pump Spurious Start
TS 3.5.1.B and TS 3.3.5.1 5A ED08A C - RO C - SRO TS-SRO Loss of 4 KV bus 1A 1 (Loss of Recirc due to loss of bus)
AOP 255.2 and AOP 264, TS 3.4.1 (LCO entry is Not required at this power level
)
Scenario Event Description ES
-D1 DAEC 2013 NRC Scenario 2 2013 NRC Scenario 2 ES D
-1, Rev 01-02-13 5B C-BOP C - SRO Loss of 4 KV bus 1A1 (Loss of 4 KV bus 1A1 and associated equipment)
AOP 304.1 6 ZZ02 NM04A C - RO C - SRO TS-SRO Small Seismic event causes IRM "A" to become Inoperative causing a half scram and causes the HPCI suction to swap to the Torus
. AOP-901, T.S. 3.6.1.F and T.S. 3.5.1.H 7 ZZ02 PC14 M - ALL Larger Seismic event Torus Rupture requires scram and eventual ED AOP-901, IPOI 5 8 CS01 CS02 DO-HP-036 C - BOP C - SRO Failure of CS and/or HPCI makeup to the Torus.
EOP 1, EOP 2, EOP 3, ED * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Scenario Event Description ES
-D1 DAEC 2013 NRC Scenario 2 2013 NRC Scenario 2 ES D
-1, Rev 01-02-13 DAEC 2013 NRC Scenario #2 The scenario begins with reactor power at about 3% and a startup in progress.
The crew will place the "B" feedwater pump in service IAW OI 644 and then continue the startup.
While pulling control rods, control rod 18-19 will become stuck and require actions IAW AOP 255.1 to continue rod movement. The SRO may enter TS 3.1.3. Once the stuck rod is addressed, a spurious start of the "A" Core Spray pump will occur and the pump must be manually secured. The SRO will reference TS 3.5.1 .B and TS LCO 3.3.5.1 Condition A for functions 1a and 1b.
Once the Technical Specifications have been addressed a loss of Non Essential 4160v Bus 1A1 will occur. The crew will take actions IAW AOP 304.1, AOP 255.2 and AOP 264 and address the resultant Recirc Pump trip and also swap bus power supplies. The SRO will address TS for single loop operation, however on checking the T.S
. the crew will determine that the actions are not required at this power level.
Once the power supplies have been swapped and the Technical Specifications identified, a seismic event will occur. The operators will take action IAW AOP 901 to monitor the plant. The seismic shock will cause IRM "A" to become inoperable requiring the RO to bypass the IRM.
The torus will have received a shock and a small break will have developed. Additionally the earthquake will have caused a momentary torus level spike that causes the HPCI suction to shift to the Torus. IAW OI 152, Section 8 HPCI must be declared inoperable because the low pressure keep fill system is NOT in service. This requires entry into T.S. 3.5.1.F and 3.5.1.H. At that time unknown to the crew the HPCI CST suction will fail in the closed position.
A second seismic event will occur and the Torus will then develop a large unisolable leak. As torus level lowers the crew will attempt to make up to the torus, but efforts will be unsuccessful because the Core Spray manual CST suction valves cannot be opened and the HPCI CST suction valve has closed and will not open. A manual scram will be required (CRITICAL TASK
) before Torus level lowers below 7.1 feet
. Further lowering of Torus level will require a n Emergency Depressurization (CRITICAL TASK
).
The scenario may be terminated after the ED is performed and RPV level is returned to the normal operating band.
2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 1 of 23 SIMULATOR EXERCISE GUIDE (SEG)
SITE: DAEC STARTUP FIRST FEEDWATER PUMP, CONTINUE STARTUP, STUCK CONTROL ROD, CORE SPRAY PUMP SPURIOUS START
, LOSS OF BUS 1A1, SEISMIC EVENT, IRM INOP, SECOND SEISMIC EVENT, BREAK IN TORUS, LOSS OF TORUS MAKEUP ESG NRC #2 REV. 0 PROGRAM: OPERATIONS
- COURSE: INITIAL LICENSED OPERATOR #: TOTAL TIME:
90 MINUTES Developed by:
Edwin Bowles 11/14/12 Instructor Date Validated by:
SME/Instructor Date Reviewed by:
Operations Manager Date Approved by:
Training Supervisor
-Operations Date 2013 NRC Scenario #2 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 2 of 23 GUIDE REQUIREMENTS Goal of Training:
The goal of this scenario is to evaluate ILT students during the NRC Exam with 3 man crew.
Learning Objectives:
There are no formal learning objectives Prerequisites:
None Training Resources:
Simulator Simulator Booth Instructor Phone Talker Simulator Floor Instructor
References:
Commitments:
None Evaluation Method: Dynamic Simulator Operating Experience:
None Related PRA Information:
Initiating Event with Core Damage Frequency:
N/A due to exam security Important Components
- N/A due to exam security Important Operator Actions with Task Number:
N/A due to exam security
2013 NRC Scenario #2 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 3 of 23 SCENARIO SUMMARY:
The scenario begins with reactor power at about 3% and a startup in progress. The crew will place the "B" feedwater pump in service IAW OI 644 and then continue the startup. While pulling control rods, control rod 18-19 will become stuck and require actions IAW AOP 255.1 to continue rod movement. The SRO may enter TS 3.1.3. Once the stuck rod is addressed, a spurious start of the "A" Core Spray pump will occur and the pump must be manually secured. The SRO will reference TS 3.5.1 .B and TS LCO 3.3.5.1 Condition A for functions 1a and 1b.
Once the Technical Specifications have been addressed a loss of Non Essential 4160v Bus 1A1 will occur. The crew will take actions IAW AOP 304.1, AOP 255.2 and AOP 264 and address the resultant Recirc Pump trip and also swap bus power supplies. The SRO will address TS for single loop operation, however on checking the T.S
. the crew will determine that the actions are not required at this power level.
Once the power supplies have been swapped and the Technical Specifications identified, a seismic event will occur. The operators will take action IAW AOP 901 to monitor the plant. The seismic shock will cause IRM "A" to become inoperable requiring the RO to bypass the IRM.
The torus will have received a shock and a small break will have developed. Additionally the earthquake will have caused a momentary torus level spike that causes the HPCI suction to shift to the Torus. IAW OI 152, Section 8 HPCI must be declared inoperable because the low pressure keep fill system is NOT in service. This requires entry into T.S. 3.5.1.F and 3.5.1.H. At that time unknown to the crew the HPCI CST suction will fail in the closed position.
A second seismic event will occur and the Torus will then develop a large unisolable leak. As torus level lowers the crew will attempt to make up to the torus but will be unsuccessful because the Core Spray manual CST suction valves cannot be opened and the HPCI CST suction valve has closed and will not open. A manual scram will be required (CRITICAL TASK
) before Torus level lowers below 7.1 feet
. Further lowering of Torus level will require an Emergency Depressurization (CRITICAL TASK).
The scenario may be terminated after the ED is performed and RPV level is return ed to the normal operating band.
2013 NRC Scenario #2 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 4 of 23 SCENARIO OUTLINE:
BOOTH INSTRUCTOR ACTIONS 1 SIMULATOR SET UP:
(perform set up per the "Simulator Setup Checklist", including entering actions items per the "Simulator Input Summary.")
Start Sim View / Data Capture Program for EXAM ONLY 1.1 General Instructions
- a. IC 8 b. Mark up IPOI 2 to Section 4.2 Sep 10 c. A2 Sequence, Step 20 of the MOL pullsheet
- d. Place Well Water B in service. D out of service
- f. Insert the remote functions per the table below.
- g. Provide RE paperwork for continuing the startup
- h. On the VAX Computer run the fix 4 application.
1.2 EVENT TRIGGER DEFINITIONS:
Trigger No.
Trigger Logic Statement Trigger Word Description 1 ZAORDPDI1825 .GE. 0.6 Setup a schedule file to delete malfunction RD021803 on TRG 1 When drive water pressure greater than 295 psig, delete the stuck rod malfunction
? AUTO Delete 2 seconds after insertion CS03 Man Operation of "A" CS Pump (1P
-211A Breaker)
AUTO Delete 2 seconds after insertion CS03 Man Operation of "A" CS Pump (1P
-211A Breaker) 2013 NRC Scenario #2 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 5 of 23 1.3 MALFUNCTIONS:
Time Malf. No.
Malfunction Title Delay Ramp ET Initial Value Final Value Setup RD021819 Control Rod Blade Stuck
- Rod 18-19 ACTIVE ACTIVE As Dir ED08A 4.16kv/480V Bus Fault
-Bus-1A1 3 Inactive Active As Dir ZZ02 Operating Basis Earthquake Event Note: delete in 2 minutes 4 Inactive Active As Dir NM05A IRM Channel Fails INOP - CHNL A 4 Inactive Active As Dir HP11 HPCI SPURIOUS SUCTION SWAP 4 Inactive Active As Dir PC14 Primary Containment Torus Leakage 100 4 0 1 As Dir ZZ02 Operating Basis Earthquake Event Note: delete in 2 minutes 5 Inactive Active As Dir PC14 Primary Containment Torus Leakage 800 5 1 100 1.4 OVERRIDES:
Time Override No.
Override Title Delay Ramp ET Initial Value Final Value Setup DI-CS-008 Pump 1P-211A NASP NASP DI-HP-025 HS-2300 PMP SUCTION MOV-2300 (CST) 00:01:10 4 AUTO CLOSE 1.5 REMOTE FUNCTIONS:
Time Remote No. Remote Title Delay Ramp ET Initial Value Final Value As Dir CS03 Man Operation of "A" CS Pump (1P-211A Breaker)
AUTO Delete 2 seconds after insertion 2 Norm Close 2013 NRC Scenario #2 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 6 of 23 FLOOR INSTRUCTOR ACTIONS 2 Simulator Pre-brief:
2.1 Individual position assignments
2.2 Simulator training changes since last module 2.3 Simulator hardware and software modifications/problems that may impact training 2.4 Mark IPOI 2 Section 4.2 to step 10 2.5 Mark up the A2 Sequence, to Step 20
2013 NRC Scenario #2 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 7 of 23 3 TURNOVER INFORMATION Day of week and shift Today Day Shift Weather conditions Warm, spring day No watches / warnings (Plant power levels)
~3% Pwr MWT 0 MWE 0 CORE FLOW 14.1 Thermal Limit Problems/Power Evolutions None Plant Risk Status CDF GREEN Existing LCOs, date of next surveillance None STPs in progress or major maintenance None Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment None Comments, evolutions, problems, core damage frequency, etc
. Continue with startup IAW IPOI
-02, Step 4.2. Step 1 0 I & C is performing a visual check on NI cabinets Both Recirculation Pumps have been in operation >24 hours, surveillance to match pump speeds has been successfully completed.
RPV level is being maintained low in the green band in preparation for startup of first feedwater pump Two Condensate Demineralizers are in service, two are in hold ready to be placed in service. Place the "B" Feedwater pump in service IAW OI 644 Continue the startup by withdrawing control rods until BPV #1 is 60% open The control rods have been withdrawn in the A2 sequence halfway through Step 20
2013 NRC ILT Scenario #2 SCENARIO TIME
-LINE 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 8 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Shift Turnover
COMPLETE TURNOVER:
Provide Shift Turnovers to the SRO and ROs. a. Review applicable current Plant Status b. Review relevant At
-Power Risk status c. Review current LCOs not met and Action Requirements
- d. Verify crew performs walk down of control boards and reviews turnover checklists Get familiar with plant conditions.
SRO will provide beginning of shift brief to coordinate the tasks that were identified on the shift turnover
2013 NRC ILT Scenario #2 SCENARIO TIME
-LINE 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 9 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1 Start First RFP IAW OI 644
Booth Instructor:
Role Play as noted below Role Play:
As an operator sent to the 1C-80 panel report that a low demin flow alarm has occurred and cleared.
NOTE: First Step is N/A
Role Play: As field operator respond that V-07-134, V-07-139 & RFP 1P
-1B are OPEN CREW May have to respond to Annunciator 1C06B, A
-1, CONDENSATE DEMIN PANEL 1C-80 TROUBLE Send an operator to Panel 1C
-80 to determine the cause of the trouble alarm SRO Gives crew brief and directs placing the "B" feedwater pump in service IAW OI 644 RO Monitors plant parameters during evolution focusing on RPV level and reactor power.
BOP Places first feedwater pump is service IAW OI 644 as follows
- Verify Well Water Pump 1P
-58D secured or verify the respective ESW pump is operating for the Control Building Chiller in service Verify B RFP AUX LUBE OIL PUMP 1P
-2B running either locally or at 1C06 Contacts field operator to verify open the following valves: V-07-134 RFP SEAL WATER FILTERS INLET ISOLATION AND V-07-139 RFP 1P
-1B SEAL WATER SUPPLY HEADER ISOLATION Verify CV
-1622 STARTUP FEED REG VALVE is in the necessary lineup to support the Reactor Feed Pump that is being started
2013 NRC ILT Scenario #2 SCENARIO TIME
-LINE 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 10 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1(cont)
Role Play: As field operator report that cooler outlet temperature is 80 degrees Role Play:
If asked, report that sufficient demins are in service and flows are balanced Role Play: As field operator
, if called and asked about the status of the started feed pump report that the motor and pump appear to be running correctly and all flows and temperatures appear normal
BOP (cont) Contact field operator to verify that RFP Lube Oil Cooler 1E
-41B outlet temperature is above 70°F on local temperature gauge TI
-1227 Place as many F/D vessels as possible in operation per OI 639. Filter Demin flows should be balanced with at leas t one bed effluent valve full open Verify CV
-1611 B REACTOR FEED PUMP 1P
-1B RECIRC valve closed at 1C06 Monitor reactor water level closely to verify automatic operation of STARTUP FEED REG VALVE CV
-1622. If necessary, adjust the potentiometer on MASTER REG VALVE AUTO/MAN CONTROL Reactor Water Level Controller LC
-4577 to maintain reactor water level between 186 and 195 inches Start B REACTOR FEED PUMP 1P
-1B using handswitch HS
-1616 on 1C06 Verify the FIC
-1611 A[B] RX FEED PUMP 1P
-1B RECIRC FLOW CONTROL indicators establishes and maintains a recirc flow of at least 2800 gpm flow If 1P-58D trips due to the voltage transient caused by the B Reactor Feed Pump start, monitor Drywell Air Temperatures and the Well Water system parameters (otherwise N/A this step)
Verify B RFP SHAFT Driven oil pump is operating properly by verifying adequate oil flows and pressure.
Stop B RFP AUX LUBE OIL PUMP 1P
-2B by performing the following:
Place handswitch HS
-1648 on 1C06 in the STOP position 2013 NRC ILT Scenario #2 SCENARIO TIME
-LINE 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 11 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1(cont)
Role Play: As RW operator if called reply that you will balance F/D Effluent Flows per OI-639 Note: 1P-1A RECIRC valves will not close until feedwater flow rises.
Role Play:
Zinc injection will be started up later today.
BOP (cont)
After B RFP AUX LUBE OIL PUMP 1P
-2B has stopped, place handswitch HS
-1648 in the AUTO position Ensure RW Operator adjusts F/D Effluent Flows per OI-639 Check CV-1569 B[A] REACTOR FEED PUMP 1P-1A RECIRC valves position Startup the Zinc Injection System per Section 9.1 EXAMINER NOTE: When Feed Pump has been started, go to next event
2013 NRC ILT Scenario #2 SCENARIO TIME
-LINE 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 12 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2 Continue Startup with Control Rods
Booth Instructor:
respond as plant personnel as necessary SRO Directs Operators to increase power IAW IPOI and RE guidance
RO Continues control rod withdrawal IAW OI 856.1 following the sequence.
Monitors neutron monitoring instrumentation during control rod movements Verifies the following indications:
o White backlight on the Rod Select pushbutton turns ON o On the Full Core Display, the white "XX
-XX" select light corresponding to the rod selected turns ON o On the Four Rod Group Display, the white SELECT light turns ON denoting the position display for the selected rod Momentarily places the ROD MOVEMENT CONTROL in the OUT
-NOTCH position and verifies o The green ROD IN light turns ON momentarily and then turns OFF o The red ROD OUT light turns ON after the green ROD IN light turns OFF. o The red ROD OUT light turns OFF o The amber ROD SETTLE light turns ON and then turns OFF o The rod has been withdrawn as indicated on the Four Rod Group Display Ranges IRM recorders as necessary to maintain them between 25/40 and 75/125 on the appropriate range BOP Monitors balance of plant equipment/plant status EXAMINER NOTE: Continue to next event at examiners direction
2013 NRC ILT Scenario #2 SCENARIO TIME
-LINE 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 13 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3 Stuck Control Rod Booth Instructor: respond as noted below for field actions Booth Instructor:
When drive water pressure greater than 295 psig, delete the stuck rod malfunction TRG 1 NOTE: Rod will move once drive water pressure is higher than 295 psig CREW
SRO Directs entry to AOP 255.1 when informed of stuck control rod Determines that the TS 3.3.2.1 requirements are met Contacts RE and/or Duty Manager RO While pulling control rods, recognizes rod 18-19 is stuck and informs the SRO As directed and IAW AOP 255.1, takes actions to address the stuck rod as follows:
o Raise drive water pressure to 310
-350 psid AND attempt to move the rod o Recognize rod movement and reports success to SRO o Returns drive water pressure to its normal band BOP Monitors balance of plant equipment/plant status EXAMINER NOTE: Continue to next event at examiners direction
2013 NRC ILT Scenario #2 SCENARIO TIME
-LINE 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 14 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4 "A" Core Spray pump spurious start Booth Instructor:
When the stuck rod event has been addressed, initiate the Core Spray "A" start event by:
-2103 NASP Start Need delete override as soon as pump starts Role Play: When contacted to check out the pump, report that the pump is running properly Crew Recognizes spurious start of Core Spray Pump "A" Responds to Annunciator 1C03A (C-9) - "A" CORE SPRAY DISCHARGE LINE HI PRESSURE SRO Directs sending field operators to check out pump Determines that no initiation signal existed for a pump start Directs securing the "A" Core Spray Pump Enters TS 3.5.1.B
- 7 day LCO for the "A" CS pump RO Monitors reactor power, pressure and level BOP Recognizes start of "A" Core Spray pump Dispatches field operators Confirms by two methods that adequate core cooling exists and that no valid initiation signals have occurred Places the control switch for the "A" Core Spray pump to STOP Confirms that the "A" Core Spray pump is secured EXAMINER NOTE: Continue to next event at examiners direction
2013 NRC ILT Scenario #2 SCENARIO TIME
-LINE 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 15 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #5 LOSS OF 4160V BUS 1A1
Booth Instructor: respond as plant personnel and respond as necessary:
When directed by the lead evaluator:
INSERT EVENT TRIGGER: 3 This inserts the Bus 1A1 Lockout.
CREW Responds to Annunciator 1C08A A2
- BUS 1A1 LOCKOUT TRIP OR LOSS OF VOLTAGE Diagnose the loss of Bus 1A1 SRO Directs actions IAW ARP Enters AOP 304.1
, Loss of Non essential Bus Enters AOP 255.2
, Power/reactivity Abnormal Power Change Reviews Power/Flow Map and determines NOT in the Buffer or Exclusion Region May Enter AOP 264
- Loss of Recirc Pump Contacts Duty Manager Refers to TS 3.4.1 Condition D
- single loop surveillance within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> o Determines T.S. 3.4.1 applies in Modes 1 and 2 however the requirements for thermal limits are not applicable below 21.7% power o Determines that flow biased scram setpoint is only applicable in Mode 1 RO Monitors critical plant parameters Responds to the Recirc Pump trip IAW AOP 264 For the Recirc Pump that tripped, performs the following:
Verify open A[B] RECIRC PUMP DISCH BYP valve MO
-4629[4630]
Close A[B] RECIRC PUMP DISCHARGE valve MO
-4627[4628]
After 5 minutes, reopen A[B] RECIRC PUMP DISCHARGE valve MO-4627[4628] (unless the A[B] Pump has to be isolated)
2013 NRC ILT Scenario #2 SCENARIO TIME
-LINE 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 16 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #5 cont. Role Play:
When contacted to investigate 1A1 loss, Report back in 5 minutes that the bus has a lockout and BKR 1A102 has an overcurrent flag BOP Determines Bus 1A1 lockout on process computer point D592 For LOSS of 1A1 ONLY, perform the following:
Crosstie 1B1 and 1B2 by performing the following:
o Momentarily place control switch FEEDER BREAKER 1B101 XFMR 1X11 to LC 1B1 to the TRIP position o Momentarily place control switch TIE BREAKER 1B107 LC 1B1/1B2 in the CLOSE position Crosstie 1B5 and 1B6 by performing the following:
o Momentarily place control switch FEEDER BREAKER 1B501 XFMR 1X51 to LC 1B5 to the TRIP position o Momentarily place control switch TIE BREAKER 1B505 LC 1B5/1B6 in the CLOSE position o Place BUS 1A1 TRANSFER switch in MANUAL Verify Offgas Closed Cooling Water Pump 1P
-105B in service Start Offgas Glycol Pump 1P
-243A EXAMINER NOTE: Continue to next event at examiners direction
2013 NRC ILT Scenario #2 SCENARIO TIME
-LINE 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 17 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 6 Seismic event and IRM "A" fails inoperable
Booth Instructor: When directed initiate the seismic event and IRM "A" Inoperable event by:
Insert Event Trigger:4 This will cause the initial seismic event.
Booth Instructor:
Verify ZZ02 is deleted 2 minutes after insertion Role Play:
If contacted, as I&C, report that you will investigate the IRM issue.
Report back in 3 minutes that it appears the IRM has lost its' high voltage power supply with no apparent cause
. CREW Responds to indications of an Earthquake Responds to annunciator s 1C05A B-3, IRM A, C, or E Upscale Trip or Inop 1C05A, A-2, "A" RPS AUTO SCRAM 1C03C, D-4, TORUS HI LEVEL HPCI SUCTION TRANSFER INITIATE SRO Enters AOP 901
- Earthquake Directs operators to perform building walk
-downs Directs actions IAW the ARP.
Directs RO to bypass the IRM Directs RO to reset the half scram Enters T.S. 3.5.1.F and 3.5.1.H and declares HPCI inoperable May address TS 3.3.1.1 ( no LCO required)
May direct the BOP to transfer the HPCI suction back to the CST May address TS Table 3.3.5.1
-1, Function 3e which requires entry into TS 3.3.5.1.D
RO Stops control rod withdrawal and takes actions as directed IAW the annunciator response Monitors critical plant parameters: reactor power pressure and level Diagnoses IRM "A" is inoperable Bypass the IRM "A" per CRS direction Resets the half scram
2013 NRC ILT Scenario #2 SCENARIO TIME
-LINE 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 18 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 6 cont BOP Acknowledge seismic alarm and attempt to reset.
Respond to earthquake condition.
Reports Torus level oscillating due to quake Recognizes HPCI suction transfer to the Torus Attempts to close MO
-2321 and MO
-2322 and open MO
-2300 Diagnoses MO
-2300 will NOT open and notifies SRO
EXAMINER NOTE: When IRM and HPCI suction swap have been addressed and initial earthquake actions taken OR when directed continue to next event
2013 NRC ILT Scenario #2 SCENARIO TIME
-LINE 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 19 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Events 7 & 8 Second seismic event torus rupture with failure of CS and/or HPCI makeup to the torus.
Booth Instructor:
When directed initiate the seismic event and large torus break event by:
Insert Event Trigger:5 Verify ZZ02 is deleted 2 minutes after insertion Role Play:
When called by MCR to find out where the leak is, respond in 5 minutes that from the catwalk you've seen water on the floor of the west side of the Torus room but cannot determine where its coming from. You'll continue to check NW corner room is B
-CS (V-21-2) SE corner room is A
- CS (V-21-1)
CREW Responds to indications of an Earthquake Respond to annunciator 1C03B, D9, Torus Hi/Lo water level Diagnoses Torus Low level SRO Re-enters AOP 901
- Earthquake Directs operators to perform a second building walk
-down Directs actions IAW the ARP for torus level (ARP refers to EOP)
Enters EOP 2
- Primary Containment Control due to LOW Torus Level <10.1 feet May direct raising Torus level with Core Spray IAW OI 151 and/or HPCI IAW OI 152 Directs contacting field operator to check areas for leaks When it is determined that Torus level cannot be maintained >7.1 feet, directs a manual scram and an EOP 1 entry (CRITICAL TASK)
Directs maintaining RPV level between 170" and 211" Directs a RPV pressure band to maintain Enters EOP 3
- due to Torus Area level > Max Normal Determines that Torus level is continuing to lower and BEFORE Torus level drops to 7.1 feet, Directs Emergency Depressurization. Open 4 SRVs Note may also anticipate depressurization and Rapidly depressurize the RPV with the main turbine bypass valves (SEP 307). (CRITICAL TASK)
2013 NRC ILT Scenario #2 SCENARIO TIME
-LINE 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 20 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Events 7 & 8 cont. Responds to indications of an Earthquake
Role Play:
When contacted by CR to perform OI 151
- Fill Torus with Core Spray, acknowledge request and report back in 5 minutes that you cannot align Core Spray to fill the Torus.
RO Monitors critical plant parameters As directed, Inserts manual scram (CRITICAL TASK)
Takes IPOI 5 "Reactor Scram" Actions Initiates a backup manual reactor scram.
Place THE MODE SWITCH in the SHUTDOWN position.
Verify all control rods fully inserted by one or both of the following means: Verifies the Refuel One Rod Select Permissive:
o Position THE MODE SWITCH to REFUEL.
o Turn Rod Select Power off and then on.
o Verify the white Refuel Select Permissive light is lit.
o Return THE MODE SWITCH to SHUTDOWN.
On the FULL CORE DISPLAY, verify the green FULL IN light for each rod is on.
Maintains RPV level as directed BOP Contacts field operators to check for leaks Monitors reactor pressure and maintains in the band directed by the SRO If directed, attempts to makeup Torus level with HPCI IAW OI 152 Section 12.1 as follows:
Verify the CST has at least 75,000 gallons of water available for use by the HPCI and RCIC Systems on demand. This corresponds to approximately 9.5 ft. with one CST or 5.2 ft. with two CSTs.
2013 NRC ILT Scenario #2 SCENARIO TIME
-LINE 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 21 of 23 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Events #7 & 8 (cont.) BOP (Cont)
With HS-2318A in the OVERRIDE position, HPCI shall be considered inoperable and the requirements of Technical Specifications complied with. Position HS
-2318A, EMERGENCY TORUS FILL PERMISSIVE on 1C03 to OVERRIDE Open MO-2318 MIN FLOW BYPASS valve with HS
-2318 on 1C03 Observe Torus level, UR
-4325 at 1C03.
-5216A and LI
-5217A on 1C06 while draining CSTs. When Directed opens 4 ADS SRVs to emergency depressurize (CRITICAL TASK)
Informs CRS when 4 SRVs are open RO Restore and maintain RPV level between 170" and 211" Scenario Termination Criteria The scenario may be terminated after the ED is performed and RPV level is returning to the normal band Event Classification Alert per HA1.1, Receipt of the Amber Operating Basis Earthquake Light and the wailing seismic alarm on 1C35 (+/
- 0.06 gravity)
SEG/ESG Validation Checklist 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 22 of 23 Correct IC or plant status identified.
Shift turnover forms filled out (both CRS/OSM and NSOE) if required.
Additional documents are prepared (STPs, Work Orders, LCO Paperwork).
Tasks and Objectives have been verified to be correct.
Plant PRA initiating events, important equipment and important tasks are identified.
SOMS tags identified and included in setup instructions.
Special setup instructions identified; handswitch manipulations, procedure markups, alarm borders, 3D case available, computer points substituted, etc.
Setup files correctly called out.
Malfunction list is accurate.
Override list is accurate.
Remote function list is accurate.
Event triggers are accurate.
Time/Notes section is accurate and includes all reasonable cues that may be given to initiate an action. Cues are unambiguous and provide a definitive moment to take action. Instructor Activity section is accurate and complete:
Actions are clearly defined for Booth or Floor instructor.
Role-playing is clearly noted.
The sequence of events is completely and concisely narrated even if it takes no instructor action.
Automatic actions that require verification are noted.
Reasonable alternate paths are considered and included
. Event trigger activation is distinguished from narrative text (Bold font
) Noun descriptions of actions that occur on event trigger initiation are complete, for example "-set ET 3 to TRUE which activates malfunction SW21C resulting in a loss of the C Well Water Pump."
Other simulator control actions are clearly distinguished from narrative text, for example "-after drywell temperature reaches 280 deg. F SNAP the simulator to IC 0." Student and Instructor copies of worksheets or other training activities are verified correct and electronically attached to the file if appropriate.
SEG/ESG Validation Checklist 2013 DAEC NRC Scenario 2 Script, Rev 01-04-13 Page 23 of 23 Expected Student Response Section is accurate and complete:
Critical tasks are accurate and clearly identified. Probable critical tasks are also listed with logical connection to the scenario; for example "If the crew fails to get all the rods inserted before ED the critical task becomes-" (N/A as appropriate)
Tasks are clearly noted and properly numbered as appropriate.
Knowledge objectives are clearly noted and properly numbered as appropriate.
Expected as well as probable student responses are listed with logical connection to the scenario. (N/A as appropriate)
Actions are appropriately delineated by position(s); OSM, CRS, STA, RO, NSOE, Fire Brigade Leader, At the Controls Operator, etcetera. (N/A as appropriate)
Success paths are procedurally driven unless specific training not requiring procedures is desired and delineated. Procedural discrepancies are identified and corrected before training is given.
Responses for all communications to simulated personnel outside the Control Room are included, based on procedural guidance and standard operating practices.
Actions are listed using a logical order; by position and chronology. (N/A as appropriate)
Operating Experience, Human Performance Tools and Operator Fundamentals topics are included when appropriate.
Crew Performance Criteria follow the same chronology as the student responses, are complete and accurate. (For ESGs only)
For Walkthrough and Training Mode Scenarios with pre
-planned pauses, sufficient information is presented to allow the instructor to meet the goal of the training.
Turnover information (as required) is correct:
Day and shift are appropriate.
Weather conditions do not conflict with malfunctions.
Power levels are correct.
Thermal limit problems and power evolutions are realistic and include a reason for any downpower.
Existing LCOs include start date, remaining time and actions.
Plant Risk Assessment (CDF and Color).
STPs are appropriate for day and shift.
Core Damage Frequency has been properly calculated and listed to 3 decimal places. Maintenance is realistic for plant conditions.
Comments, evolutions, problems, etc, includes extra personnel (licensed/non
-licensed if necessary), any condition that affects the flow of the scenario and any condition that does not fit in another category.
SME/Instructor Date SME/Instructor Date SEG/ESG Validation Checklist Crew: Instructors:
SM ____________________________
Booth ________________________________
CRS ____________________________
Floor ___________________
_______ STA __________________________________
Extra ________________________________
1C05 ____________________________
1C03 ____________________________
BOP ____________________________
Crew Comment:
Resolution:
Crew Comment:
Resolution:
NOTE: Following approval of SEGs, this page may be discarded.
SEG/ESG Validation Checklist Crew Comment:
Resolution:
Crew Comment:
Resolution:
Crew Comment:
Resolution:
NOTE: Following approval of SEGs, this page may be discarded.
Scenario Event Description ES
-D1 DAEC 2013 NRC Scenario 3 2013 NRC Scenario 3 ES D
-1, Rev 01-04-13 Facility:
DAEC Scenario No.:
3 Op Test No.:
2013 NRC Examiners:
Operators:
SRO - RO - BOP - Initial Conditions:
Reactor Power @100%
- Day 1 of 30 day LCO, due to "B" RHR Pump inoperative because a fault in the motor winding. Maintenance expects repairs to be completed in 3 days.
(Also T.S. 3.6.2.3)
Turnover:
Maintenance has requested the immediate securing of the "B" CRD Pump for a GE Service Bulletin that directs replacing the oil in the gear box. Remove the "B" CRD Pump from service IAW OI 255 - CRD Hydraulic System, Section 6.1 Critical Tasks:
- 1. Terminate and prevent injection prior to emergency depressurization with control rods stuck out of the core.
- 2. Emergency Depressurize when it is determined that drywell temp cannot be restored and maintained <280
°F 3. Following emergency depressurization maintain reactor pressure below the Minimum Steam Cooling Pressure.
Event No. Malf. No.
Event Type* Event Description 1 N/A N-RO N-SRO Remove the "
B" CRD Pump from service IAW OI 255, Section 6.1 2 FW07J R-RO R-SRO Loss of Feedwater Heating
- 5B dump valve fails open
-power reduction
AOP 646, AOP 255.2 3 RR17B C - RO C- SRO TS-SRO "B" Reactor Recirc Pump speed controller fails downscale AOP 255.2 TS 3.4.1 Scenario Event Description ES
-D1 DAEC 2013 NRC Scenario 3 2013 NRC Scenario 3 ES D
-1, Rev 01-04-13 4 RD11A RD070615 RD073435 RD073819 C-RO C-SRO TS-SRO "A" CRD Pump trips, Three CRD Accumulators alarm on low pressure. Permission is given to start standby pump IAW OI 255 TS 3.1.5 5A ED08C C-RO C-SRO TS-SRO Lockout on Essential Bus 1A3 (results in a loss of A & C RHR and A Core Spray)
Responds to loss of 1A3 Responds to half scram, PCIS Div 1 Groups 1
-5 isolations (except MSIVs)
ARP actions T.S. 3.0.3, 3.8.7 5B ED08C C-BOP C-SRO Lockout on Essential Bus 1A3 (results in a loss of A & C RHR and A Core Spray)
Responds to Auto Diesel START and secures Diesel due to running without cooling water Performs actions to restore Drywell cooling AOP 301 6 MS03C M- All Steam leak on main steam line C, in primary containment requires a manual scram IPOI - 5, EOP 1, EOP 2 7 RD020615 RD023435 C - All Two control rods are stuck out of the core
ATWS 8 RH01D C-BOP C-SRO "D" RHR Pump trips on overcurrent ED * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Scenario Event Description ES
-D1 DAEC 2013 NRC Scenario 3 2013 NRC Scenario 3 ES D
-1, Rev 01-04-13 DAEC 2013 NRC Scenario #3 The scenario begins at 100% power with the "B" CRD Pump in service. The crew will start the "A" CRD Pump and remove the "B" CRD Pump from service IAW OI 255 - CRD Hydraulic System, Section 6.1
Once the CRD pump swap is completed, a feedwater heater dump valve will fail open resulting in a loss of feedwater heating. The crew will enter the abnormal procedures AOP 646, and AOP 255.2 and take action to lower reactor power. Immediately after the power reduction the "B" Recirc Pump flow controller wi ll slowly fail downscale and the operators will lock up the scoop tube IAW the AOP.
The SRO will address Technical Specifications for the speed mismatch.
Then the "A" CRD pump will trip on overcurrent and three CRD accumulators alarm on low pressure. Permission is given to start standby pump IAW OI 255. After the "B" CRD Pump is returned to service the CRD Accumulators remain in alarm on low pressure. The SRO will address Technical Specifications 3.1.5.
After addressing the Technical Specifications for the three inoperable accumulators, Essential Bus 1A3 will trip and lockout requiring entry into AOP AOP-301. The operators will verify the diesel starts but does not tie to the 1A3 bus and that an ESW pump is not running requiring the crew to secure the SBDG to preclude its failure. Before RPS can be recovered the small break LOCA in the drywell will begin and there will be no time for the SRO to address Technical Specifications.
A small leak in the drywell and rising drywell pressure and temperature results in the operators inserting a manual reactor scram. Two of the control rods, which earlier had low accumulator pressures, will remain stuck out of the core following the scram. This will require the crew to terminate and prevent injection prior to the emergency depressurization (CRITICAL TASK)
. As Primary Containment pressures and temperatures rise the "D" RHR Pump will trip on overcurrent shortly after it's started. Without RHR the drywell temperature will rise above 280°F and the crew must emergency depressurize (CRITICAL TASK)
. Additionally when reactor water level is restored following the emergency depressurization the crew must maintain reactor pressure below the Minimum Steam Cooling Pressure (MSCP) (CRITICAL TASK)
.
The scenario may be terminated after the emergency depressurization is performed
, RPV level is restored and reactor pressure is below the MSCP
.
2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 1 of 26 EXAMINATION SCENARIO GUIDE (ESG)
SITE: DAEC REMOVE CRD PUMP FROM SERVICE, LOSS OF FEEDWATER HEATING, B RECIRC PUMP CONTROLLER FAILURE, CRD PUMP TRIP WITH ACCUMULATOR ALARMS, LOSS OF BUS 1A3, STEAM LEAK IN PRIMARY CONTAINMENT, RHR PUMP TRIP
, TWO CONTROL RODS STUCK OUT OF THE CORE ESG NRC #3 REV 0 PROGRAM: OPERATIONS
- COURSE: INITIAL LICENSED OPERATOR #: TOTAL TIME:
90 MINUTES Developed by:
Edwin Bowles 11/15/12 Instructor Date Validated by:
SME/Instructor Date Reviewed by:
Operations Manager Date Approved by:
Training Supervisor
-Operations Date 2013 NRC ILT Scenario #3 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 2 of 26 GUIDE REQUIREMENTS Goal of Training:
The goal of this scenario is to evaluate ILT students during the NRC Exam with 3 man crew.
Learning Objectives:
There are no formal learning objectives Prerequisites:
None Training Resources:
Simulator Simulator Booth Instructor Phone Talker Simulator Floor Instructor
References:
None Commitments:
None Evaluation Method: Dynamic Simulator Operating Experience:
None Related PRA Information:
Initiating Event with Core Damage Frequency:
N/A due to exam security Important Component s: N/A due to exam security Important Operator Actions with Task Number:
N/A due to exam security
2013 NRC ILT Scenario #3 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 3 of 26 SCENARIO SUMMARY The scenario begins at 100% power with the "B" CRD Pump in service. The crew will start the "A" CRD Pump and remove the "B" CRD Pump from service IAW OI 255 - CRD Hydraulic System, Section 6.1
Once the CRD pump swap is completed, a feedwater heater dump valve will fail open resulting in a loss of feedwater heating. The crew will enter the abnormal procedures AOP 646, and AOP 255.2 and take action to lower reactor power. Immediately after the power reduction the "B" Recirc Pump flow controller will slowly fail downscale and the operators will lock up the scoop tube IAW the AOP. The SRO will address Technical Specifications for the speed mismatch.
Then the "A" CRD pump will trip on overcurrent and three CRD accumulators alarm on low pressure. Permission is given to start standby pump IAW OI 255. After the "B" CRD Pump is returned to service the CRD Accumulators remain in alarm on low pressure. The SRO will address Technical Specifications 3.1.5.
After addressing the Technical Specifications for the three inoperable accumulators, Essential Bus 1A3 will trip and lockout requiring entry into AOP AOP-301. The operators will verify the diesel starts but does not tie to the 1A3 bus and that an ESW pump is not running requiring the crew to secure the SBDG to preclude its failure.
Before RPS can be recovered the small break LOCA in the drywell will begin and there will be no time for the SRO to address Technical Specifications.
A small leak in the drywell and rising drywell pressure and temperature results in the operators inserting a manual reactor scram.
Two of the control rods, which earlier had low accumulator pressures, will remain stuck out of the core following the scram. This will require the crew to terminate and prevent injection prior to the emergency depressurization (CRITICAL TASK)
. As Primary Containment pressures and temperatures rise the "D" RHR Pump will trip on overcurrent shortly after it's started.
Without RHR the drywell temperature will rise above 280°F and the crew must emergency depressurize (CRITICAL TASK)
. Additionally when reactor water level is restored following the emergency depressurization the crew must maintain reactor pressure below the Minimum Steam Cooling Pressure (MSCP) (CRITICAL TASK)
.
The scenario may be terminated after the emergency depressurization is performed
, RPV level is restored and reactor pressure is below the MSCP
.
2013 NRC ILT Scenario #3 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 4 of 26 SCENARIO OUTLINE:
BOOTH INSTRUCTOR ACTIONS 1 SIMULATOR SET UP: (perform set up per the "Simulator Setup Checklist", including entering actions items per the "Simulator Input Summary.")
1.1 General Instructions
- a. Identify any extra copies of student materials (STPs, OIs) that are needed for this training activity.
- b. Reset to IC (number or plant condition).
- c. Verify event trigger definitions.
- d. Which malfunction files to restore for setup, if any
. e. Which override files to restore for setup, if any
. f. Which remote functions files to restore for setup, if any
. g. Run Schedule File NRC
-3 and leave running on desktop.
- h. Pull sheet setup instructions as necessary.
- i. Leakage calculations, if required
. j. Control panel setups, including valves/equipment to tag out
. k. Which STPs are being worked, and what steps are completed
. l. Verify the availability of sufficient copies of STPs in the back panel hanging files
. m. LCO and Safety Function Determination paperwork, for any outstanding LCOs
. n. Miscellaneous Systems Status Board updated for plant conditions
. o. If the ESG is going to be utilized as a DEP PI opportunity, contact security to determine if they will be able to participate and make EAL notifications.
- p. Toggle the "B" RHR pump unavailable in ORAM Centinel.
- q. STP 3.4.2
-01, Jet Pump Operability Test should be available to the students if requested.
- r. On the VAX Computer run the fix 4 application.
2013 NRC ILT Scenario #3 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 5 of 26 1.2 EVENT TRIGGER DEFINITIONS:
Trigger No. Trigger Logic Statement Trigger Word Description 7 RH01D, RHR Pump Trip
- Pump D Active 10 sec.
after the "D" RHR Pump starts. 8 ZDIRDHS1807B(4) == 1 Runs schedule file and Deletes malfunction RD073819 10 sec. after CRD Pump B is started 1.3 MALFUNCTIONS:
Time Malf. No.
Malfunction Title Delay Ramp ET Initial Value Final Value Setup AN1C03B(8
) 1C03B (A-08) 'B' RHR Pump 1P-229B Trip Or Motor Overload ON ON Setup RD023435 Control Rod Blade Stuck Rod 34-35 Inactive Active Setup RD020615 Control Rod Blade Stuck Rod 06-15 Inactive Active Setup RD023819 Control Rod Blade Stuck Rod 38-19 Inactive Active As Dir FW07J FW Heater Dump Valve Fails
-CV1340 3 min. 1 AS IS 100%
2013 NRC ILT Scenario #3 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 6 of 26 As Dir RR17B Recirc MG Flow CTRLR Fails, Auto/Manual Modes MG B 6 min. 2 AS IS 0% As Dir RD070615 Control Rod Accumulator Trouble
- Rod 06-15 1 min 3 Inactive Active As Dir RD073435 Control Rod Accumulator Trouble
- Rod 34-35 1 min 10 sec 3 Inactive Active As Dir RD11A CRD Hydraulic Pump Trip
- Pump A 3 Inactive Active As Dir RD073819 Control Rod Accumulator Trouble
- Rod 38-19 1 min 30 sec 3 Inactive Active As Dir ED08C 4kv/480v Bus Fault Bus 1A3 5 Inactive Active As Dir MS03C MSL Rupture Inside Primary Containment/Steam Line C(NRVI) 5 min. 6 0 5.5 As Dir. RH01D RHR Pump Trip
- Pump D 15 sec 7 Inactive Active OVERRIDES:
1.5 REMOTE FUNCTIONS:
Time Remote No. Remote Title Delay Ramp ET Initial Value Final Value Setup RH10 MAN OPER OF 'B' RHR PUMP (1P229B BREAKER)
Norm Open Time Override No.
Override Title Delay Ramp ET Initial Value Final Value Setup DI-PC-038 HS-4321B GRP 7 CHAN B DW CLG AND FAN OVR Normal Override Setup DO-RH-063 HS-1915(2) RHR PUMP 1P
-229B LITES
- (WHITE) On Off Setup DO-RH-064 HS-1915(3) RHR PUMP 1P
-229B LITES
- (RED) On Off Setup DO-RH-065 HS-1915(4) RHR PUMP 1P
-229B LITES
- (AMBER) On Off Setup DO-RH-062 HS-1915(1) RHR PUMP 1P
-229B LITES
- (GREEN) On Off Setup DI-PC-037 HS-4321A GRP 7 CHAN A DW CLG AND FAN OVR Normal Override Delete in 16s AO-RH-005 1P-229D RHR PUMP D AMP METER (0-100 AMPS) 5s 10s 7 As is 100 2013 NRC ILT Scenario #3 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 7 of 26 FLOOR INSTRUCTOR ACTIONS Simulator Pre
-brief:
2.1 Individual position assignments
2.2 Simulator training changes since last module (N/A)
2.3 Simulator hardware and software modifications/problems that may impact training
2013 NRC ILT Scenario #3 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 8 of 26 TURNOVER INFORMATION Day of week and shift Today Day Shift Weather conditions Warm, spring day No watches / warnings (Plant power levels)
MWT 1906 MWE 630 CORE FLOW Thermal Limit Problems/Power Evolutions Plant Risk Status CDF 8.046E-6 Color Green Existing LCOs, date of next surveillance TS 3.5.1.B.1
- Day 1 of 30 day LCO, due to "B" RHR Pump inoperative TS 3.6.2.3, Condition A, Residual Heat Removal (RHR) Suppression Pool Cooling, Day 1 of 30 day LCO, due to "B" RHR Pump inoperative STPs in progress or major maintenance None Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment CRD Pump "B" Comments, evolutions, problems, core damage frequency, etc.
"B" RHR Pump is inoperable because of a fault in the motor winding. Maintenance expects repairs to be completed in 3 days.
Maintenance has requested immediately securing the "B" CRD Pump for a GE Service Bulletin that directs replacing the oil in the gear box. Remove the "
B" CRD Pump from service IAW OI 255 - CRD Hydraulic System, Section 6.1. An NSPEO is standing by the "A" CRD Pump.
2013 NRC Scenario #3 SCENARIO TIMELINE 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 9 of 26 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Shift Turnover
COMPLETE TURNOVER:
Provide Shift Turnovers to the SRO and ROs. a. Review applicable current Plant Status b. Review relevant At
-Power Risk status c. Review current LCOs not met an d Action Requirements
- d. Verify crew performs walk down of control boards and reviews turnover checklists Get familiar with plant conditions.
SRO will provide beginning of shift brief to coordinate the tasks that were identified on the shift turnover.
EXAMINER NOTE: Continue to next event at examiners direction
2013 NRC Scenario #3 SCENARIO TIMELINE 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 10 of 26 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #1 Remove the "
B" CRD Pump from service
Booth Instructor:
respond as plant personnel and respond as necessary:
Role Play:
As field operator directed to go to the CRD pump, report that the "A" CRD Pump oil level is good and that the "A" CRD Pump 1P
-209A Discharge Isolation V 8 is full open.
Role Play: As field operator, if requested, report that the standby pump has started and is operating normally.
NOTE: Crew may notify personnel to insure the switchgear room is clear before cycling the CRD Pump Breaker.
CREW Remove the "
B" CRD Pump from service SRO Directs RO/BOP to carry out OI 255 - CRD Hydraulic System, Section 6.1, Switching CRD Pumps Notifies Duty Station Manager RO Refers to OI 255 - CRD Hydraulic System, Section 6.1 and starts the standby pump as follows:
Notifies field operator to verify adequate oil level in standby CRD Pump 1P-209A. Verify standby CRD Pump 1P
-209A Discharge Isolation V 8 full open. At 1C05, starts "A" CRD PUMP 1P
-209A by momentarily placing hand switch HS
-1807A on 1C05 in the START position.
Stops the B pump as follows Stops "B" CRD PUMP 1P
-209B by momentarily placing hand switch HS-1807B on 1C05 in the STOP position.
Notifies CRS/Crew that the CRD Pumps have been swapped.
BOP Monitors BOP equipment May make PA announcement prior to start of the pump Provides peer check EXAMINER NOTE: Continue to next event at examiners direction
2013 NRC Scenario #3 SCENARIO TIMELINE 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 11 of 26 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #2 Loss of FW heating
Booth Instructor: respond as plant personnel and respond as necessary:
INSERT EVENT TRIGGER 1: This results in FW heater Dump valve 5B failing full open Evaluator Note: Thermal power will go above 1912 mwth and the crew must lower power below the license limit.
CREW Responds to indications of FWH 5B dump valve failing open on Panel 1C-06 Lowering FW temperature Power rising as indicated on the APRMs Annunciators 1C05B, A
-6 and 1C05A, B-2 SRO Enters AOP 646
, Loss of FW Heating Enters AOP 255.2, Power/Reactivity Abnormal Change o May direct fast Power Reduction IAW IPOI
-4 to lower Recirc Flow to reduce core flow to 39 mlbm/hr OR IPOI-3, Sect. 5, to lower power by lowering recirculation flow then inserting control rods to stay below MELLLA. o Insert Control Rods using Fast Power Reduction sheet or the normal control rod sequence.
Notifies Duty Manager and RE RO As directed, Performs a Power Reduction IAW IPOI-4 Step 5.0 OR IPOI-3, Sect. 5, as follows:
Fast Power Reduction Lowers Recirc Flow to reduce core flow to 39 mlbm/hr while maintaining level between +186" and +211" Inserts control rods to reduce below the maximum rod line or as directed by the SRO using Fast Power Reduction sheet with the Emergency In switch 2013 NRC Scenario #3 SCENARIO TIMELINE 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 12 of 26 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #2 cont. RO cont. Normal Power Reduction Confirm operation is within the limits of the Power/Flow Map Reduce RECIRC MG SET A and B SPEED CONTROL in small equal increments If loadline is greater than or equal to 99.9, then insert control rods per the current Control Rod Withdrawal Sequence Sheets Monitors computer points for reactor load line and inserts control rods as necessary
BOP Monitors balance of plant equipment.
Checks FW Dump controllers on back panel
-9, or OI 646, Section 6.2, attempts to take manual control and CLOSE FW Dump valve by placing the controller in MANUAL and lowering the setpoint Notifies crew that FWH 5B dump valve will NOT close EXAMINER NOTE: Continue to next event at examiners direction 2013 NRC Scenario #3 SCENARIO TIMELINE 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 13 of 26 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #3 "B" Reactor Recirc Pump speed controller fails slowly downscale
Booth Instructor, at the direction of the Lead Evaluator:
INSERT EVENT TRIGGER: 2 RR17A to 0 over 6 minutes This will cause the "B" Recirc M
-G speed controller to ramp down slowly Booth Instructor respond as plant personnel as necessary:
Respond that you will look at the MOORE controller logic for speed control and get back to them soon.
Report that you will call in a licensed operator to take manual control of the locked up recirc scoop tube but it will be about an hour.
Go along with what the crew wants to do, and tell them that ERT will take over the repairs of the "B" speed control problem.
Examiner Note:
Depending on when the scoop tube is locked up will determine whether or not the TS loop speed mismatch requirements for the Recirc Pumps will be exceeded Instructor Note: STP 3.4.2
-01, Jet Pump Operability Test may be requested. Crew Diagnoses event: Lowering APRM power and "B" Recirc Pump speed SRO Directs entry to AOP 255.2:
Take any necessary steps to bring the reactor power/reactivity transient under control, including, but not limited to:
o Lockup of the Scoop Tube Lockup o Direct determining reactor status on the power to flow map. If a fast power reduction was NOT performed during the previous event then the crew may be required to insert control rods Determines IF the recirc pump speed mismatch will put them out o f compliance with the LPCI Loop Select limits using STP 3.4.2
-01, Daily Jet Pump Operability Test, Sect. 7.1, Recirc Pump Speed Mismatch Check. TS SR 3.4.1.1 or OI 264, Appendix 1, states that the speed of the faster pump shall be 122% of the speed of the slower pump when operating at 69.4% RTP.
Based on the calculation or graph plot, the SRO will determine if they are in compliance with TS 3.4.1 Condition C. If not, then has 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to restore the mismatch within limits, or Trip one of the recirc pumps.
Plot the current position on the power to flow map.
IF Recirc Flow is outside of the Mismatch limits, the crew may discuss how they will restore the mismatch to within limits.
Either lower the speed of the unlocked Recirc Pump to match the locked Recirc Pump.
OR Send a licensed operator to the Recirc M
-G Set room and take manual control of the locked Recirc Pump and raise it to within the limits.
2013 NRC Scenario #3 SCENARIO TIMELINE 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 14 of 26 Event #3 cont. RO Determines that power is going down without operator action and that the "B" Recirc M-G speed controller speed demand is lowering. Takes the following actions to stop the run away:
Notifies the crew Lock the scoop tube of the "
B" recirc M
-G speed controller Acknowledge/Respond to 1C04A, C
-5, Enter AOP 255.2, "Power/Reactivity Abnormal Change."
Checks the power to flow map Inserts control rods as necessary BOP Monitors balance of plant equipment and parameters May check the X values on the recirculation pump controllers to determine the individual pump speeds EXAMINER NOTE: Continue to next event at examiners direction
2013 NRC Scenario #3 SCENARIO TIMELINE 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 15 of 26 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #4 "A" CRD Pump trips, three CRD Accumulators alarm on low pressure.
Booth Instructor:
respond as plant personnel and respond as necessary:
When directed by Lead Evaluator:
INSERT EVENT TRIGGER 3 This trips the B CRD pump and results in 3 CRD Accumulators alarming on low pressure. Booth Instructor respond as plant personnel and respond as necessary:
Booth Instructor When directed to investigate the cause of the "A" CRD pump trip Wait t wo minutes and respond from the switchgear room that the "A" CRD pump tripped on inverse time delay overcurrent.
Role Play: As field operator directed to check accumulators; 06
-15, 34-35, 38-19. Report the following accumulator pressures:
06 915 psig 34 890 psig 38 950 psig Role Play: As maintenance, if the crew does NOT requested starting the "B" CRD Pump contact the Control Room as maintenance and tell them that you are at the pump and no work has been done the pump is ready to start. If contacted report that the "B" pump is ready to run.
CREW Respond to annunciators:
ARP 1C05A, A
-6, "A" CRD PUMP TRIP OR MOTOR OVERLOAD".
Determine the cause of the trip.
May request permission to start the alternate pump.
1C05A, F-7, CRD ACCUMULATOR LO PRESSURE OR HI LEVEL Identifies CRD Accumulator lights for Accumulators; 06
-15, 34-35, 38-19 Directs in plant operator to determine the cause of the accumulator alarm on accumulators; 06
-15, 34-35, 38-19 SRO Directs RO/BOP to carry out the ARP actions May direct increased monitoring of RPV water level instruments due to loss of reference leg backfill system. May direct isolation of reference leg backfill Directs contacting Maintenance to determine the status of the "B" CRD Pump. Directs starting the "B" CRD Pump.
Ensure compliance with Technical Specifications for control rod scram accumulators.
o 3.1.5.A when the first accumulator is verified to be <940 psig and every one thereafter o 3.1.5.B when the second accumulator alarm activates o May contact RE to determine if control rod scram time was within the limits of Table 3.1.4
-1 May initiate a Work Request Card to have the "A" CRD Pump checked, meggered, and repaired as necessary.
Notifies Duty Manager
2013 NRC Scenario #3 SCENARIO TIMELINE 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 16 of 26 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #4 cont
.
Role Play:
As field operator directed to go to the CRD pump, report that the "B" CRD Pump oil level is good and that the "B" CRD Pump 1P
-209A Discharge Isolation V 10 is full open.
Booth Instructor If requested to close V 10 to 1/2 turn open: Insert RF RD04 at 0.5. If/when sent to open V 10, Insert RF RD04 at 100. NOTE: Crew may notify personnel to insure the switchgear room is clear before cycling the CRD Pump Breaker.
RO May direct isolation of reference leg backfill Refers to OI 255 - CRD Hydraulic System, Section 3 and starts the "B" CRD Pump as follows:
o Notifies field operator to verify adequate oil level in standby CRD Pump 1P-209A. o Verify standby CRD Pump 1P
-209A Discharge Isolation V 8 full open. o Directs the field operator to close V 10, "A" CRD pump discharge valve open to 1/2 turn open.
o Adjust CRD SYSTEM FLOW CONTROL FC-1814 to 0 gpm in MANUAL. o At 1C05, verify MO
-1833, INLET TO CRD RETURN LINE, is fully open. o At 1C05, starts "A" CRD PUMP 1P
-209A by momentarily placing hand switch HS
-1807A on 1C05 in the START position.
o Directs field operator to Slowly open Discharge Isolation V 10 o Slowly adjust CRD SYSTEM FLOW CONTROL FC
-1814 to obtain approximately 40 gpm on FI
-1814 CRD SYSTEM FLOW.
o Place FC-1814 in AUTO o -1830 to obtain approximately 260 psid on PDI
- o Start up the GEMAC Reactor Vessel Level Instruments Reference Legs Backfill System Diagnoses that Accumulators; 06
-15, 34-35 do NOT clear when CR D Pump "A" is started and placed in service Notifies crew of low pressure in Accumulators; 06
-15, 34-35 2013 NRC Scenario #3 SCENARIO TIMELINE 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 17 of 26 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #4 cont
. Role Play:
As field operator directed to charge the accumulators 06-15, 34-35, 38-19, acknowledge the reply and state you will charge the accumulators
. Role Play:
When called after the CRD Pump is started and the accumulator alarm for 38
-19 is cleared, report back that 06-15 is at 915 psig and 34
-35 is at 890 psig. BOP Contacts Maintenance to determine the status of the "B" CRD Pump Reports "B" CRD Pump is available Monitors BOP equipment May make PA announcement for start of pump Directs plant operator to charge the accumulators 06-15, 34-35, 38-19. Provides peer check when required EXAMINER NOTE: Continue to next event at examiners direction
2013 NRC Scenario #3 SCENARIO TIMELINE 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 18 of 26 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #5 Lockout o n Essential Bus 1A3 Booth Instructor:
Insert Trigger: 5 This will cause a lockout on Essential Bus 1A3 Booth Instructor:
Role Play
- as the NSPEOs; when asked to investigate 1A3, report back that the lockout relay has tripped and 1A302 has a time delay overcurrent flag
. Role Play
- as Event Response Team, plant management and maintenance when contacted to come out to the plant to help.
Role Play
- as electrician and report that the LOR 186
-3 has tripped You will initiate a work request and start developing a troubleshooting plan.
Role Play: as the NSPEOs if sent to check the 1C93 alarms and report back that all alarms are normal for a SBDG start. Booth Instructor:
As soon as you are directed to swap the RPS buses go to Events 6 and 7.
CREW Respond to Annunciator 1C05A, A5,
- BUS 1A3 LOCKOUT TRIP Verifies reactor half scram, PCIS DIV I Group 1
-5 Isolations (except MSIVs).
Verifies "A" SBDG 1G
-31 auto starts and Breaker 1A311 does NOT auto close Send an Operator/Maintenance to 1C31 as well as Bus 1A3 to check all breaker flags and lockout relays to determine the cause of the lockout trip.
SRO Enter AOP 301 and direct the Immediate Actions for the loss of 1A3.
Evaluate plant status to determine necessary mitigation strategies.
Review the automatic actions and determine the effect of the automatic actions.
Direct the Follow
-Up actions for the loss of 1A3 Direct performance of AOP 358 Determines that the "A" SBDG is running without cooling water and directs securing the "A: SBDG by placing the control switch to P
-T-L Enters T.S. 3.8.7 an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> LCO because of the loss of the bus May directly enter T.S. 3.0.3, because of two or more low pressure ECCS subsystems inoperable RO Respond to a loss of 1A3 Respond to reactor half scram, PCIS Div 1 Groups 1
-5 isolations (except MSIVs 2013 NRC Scenario #3 SCENARIO TIMELINE 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 19 of 26 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #5 cont.
BOP Determine that the "A" SBDG 1G
-31 is running without ESW cooling and requests to place control switch in P
-T-L. Verify CRD system status Verify Well water status, starts the "B" Well Water Pump Verify GSW system status Verify RWS system status, starts the "D" River Water Supply Pump Verify RBCCW and CB Chiller system status Verify DC system status EXAMINER NOTE: If the Technical Specifications call is not necessary go on to the next event when the initial actions have been taken.
2013 NRC Scenario #3 SCENARIO TIMELINE 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 20 of 26 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Events # 6 & 7 Steam line break RHR Pump "D" Trip Booth Instructor:
INSERT TRIGGER: 6 This inserts MS03C 5.5% over 5 minutes
- Steam Line Rupture inside Primary Containment.
Booth Operator:
Ensure EVENT TRIGGER 7 goes active 10 seconds after the "D" RHR Pump starts. CREW Recognizes Drywell pressure is increasing.
Responds to indications of rising Drywell pressure:
1C05B-B1, Primary Containment Hi/Lo Pressure 1C35A-C4, Drywell/Torus Air/Part/Iodine H i Rad or Downscale
- Primary Containment Control to attempt to maintain drywell pressure between 1.0 and 1.5 psig May direct a fast power reduction (if not performed previously)
Directs lowering power with the A Recirc Pump Directs reactor scram due to rising drywell pressure Directs implementing IPOI
-5, Reactor Scram, actions Enters EOP 1 on reactor level and/or drywell pressure Enters EOP
-2 on High Drywell Pressure Exits EOP
-1 and enters ATWS when informed that t wo control rods are stuck in the core.
Directs lockout of ADS Directs preventing injection by Condensate and Feedwater, HPCI, RHR or Core Spray Directs installing Defeat 15, Override MSIV Lo Lo Lo Level trip Directs installing Defeat 11, Containment N 2 Supply Isolation Defeat Directs RPV level band of 170" to 211" with Condensate and feedwater Directs inserting IRMs to determine reactor power if the RO has not inserted them
2013 NRC Scenario #3 SCENARIO TIMELINE 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 21 of 26 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Events #6 & 7 cont.
Role Play:
As Duty Station Manager or Work Control Center respond to the request to investigate and/or recover Bus 1A3 and/or an RHR Pump that you will send technicians to diagnose the problem.
Determines there are NO operable RHR Pumps SRO Cont Contacts Duty Station Manager or Work Control Center to recover an RHR Pump Directs installing Defeat 4, Drywell Cooler Isolation Defeat May direct lowering RPV pressure using pressure set to 880 psig May establish a cooldown at <100°F/hr May direct AIP 401 and attempt to spray the drywell with RHRSW Establishes a band of 600 to 800 psig Determines that drywell temperature cannot be restored and maintained below 280°F or they have been above 280°F for 15 minutes
, enters ATWS ED Directs terminating and preventing injection (CRITICAL TASK)
Directs Emergency Depressurization due to RHR failure and rising DW temperature (CRITICAL TASK)
When notified that 4 ADS valves are open directs that RPV pressure be maintained below the Minimum Steam Cooling Pressure. (CRITICAL TASK) When RPV pressure is <1 60 psig directs re
-establishing injection with Condensate and Feedwater to restore an RPV water level band of 170" to 211" 2013 NRC Scenario #3 SCENARIO TIMELINE 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 22 of 26 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Events #6 & 7 cont.
Role Play:
As the operator directed to investigate the trip of the "D" RHR pump report that there is the smell of burning wiring near the pump and that the motor is hot to the touch.
RO May perform fast power reduction, if not performed previously, lowering recirculation flow to 39 mlbm/hr Scrams the reactor as directed using both RPS Pushbuttons (IPOI 5 actions) Places Mode Switch to Shutdown Reports to CRS that all rods are NOT FULL IN, that two rods remain fully withdrawn Inserts the IRMs to determine reactor power Controls RPV level in a band of 170"
-211" with Condensate and Feedwater If directed to establish a cooldown lowers reactor pressure using pressure set to desired pressure and/or opens main steam line drains Attempts to insert the withdrawn control rods Reports that the t wo control rods are stuck out of the core As directed, lowers RPV pressure using pressure set Terminates and prevents injection (CRITICAL TASK)
Secure and prevent injection from:
Condensate and feed HPCI Core Spray and RHR.
When directed re
-establishes injection with Condensate and Feedwater to restore an RPV water level band of 170" to 211" Maintains RPV pressure below the Minimum Steam Cooling Pressure (160 psig) (CRITICAL TASK)
2013 NRC Scenario #3 SCENARIO TIMELINE 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 23 of 26 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Events #6 & 7 cont.
Role Play:
If an operator is directed to manually open MO 1942, report that when you attempted to manually de
-clutch the MO you heard a loud snap and the hand
-wheel just spins freely.
BOP Verifies Turbine
-Generator trip and transfer of busses Monitors BOP equipment and containment parameters Diagnoses the "D" RHR pump starts on high drywell pressure and then trips on overcurrent Directs an operator to locally inspect the "D" RHR pump Notifies the crew that there are NO operable RHR pumps Diagnoses that HPCI starts on high drywell pressure and trips on high water level. OR prevents HPCI from starting by placing the Auxiliary Oil Pump in P
-T-L. Installs Defeat 1 5 as follows:
At Panels 1C15 and 1C17 places the keylock switch es in OVERRIDE At Panels 1C15 and 1C17 places the keylock switches in OVERRIDE to bypass the High Condenser Vacuum isolation Installs Defeat 11 as follows:
At Panel 1C35, place GROUP 3 OVERRIDE keylock switch es in OVERRIDE OPEN position.
Confirm CV
-4371A opens by observing valve position.
As directed, Installs defeat 4 as follows:
At Panel 1C25 place GROUP 7 CHANNEL A DW COOLING AND FAN SPEED OVERRIDE keylock switches to OVERRIDE Diagnoses that Defeat 4 did NOT work and that drywell cooling is lost Reports that drywell cooling cannot be restored If directed to establish a cooldown lowers reactor pressure using pressure set to desired pressure and/or opens main steam line drains
2013 NRC Scenario #3 SCENARIO TIMELINE 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 24 of 26 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Events #6 & 7 cont. BOP Cont Terminates and prevents injection (CRITICAL TASK)
Secure and prevent injection from:
Condensate and feed HPCI Core Spray and RHR.
When directed, opens 4 ADS SRVs to Emergency Depressurize (CRITICAL TASK)
Reports to CRS that 4 ADS valves are open and RPV pressure is lowering Reports to CRS that containment parameters are improving Maintains RPV pressure below the Minimum Steam Cooling Pressure (160 psig) (CRITICAL TASK)
Scenario Termination Criteria The scenario may be terminated after an ED is performed; the DW parameters are under control and RPV level is being restored to the normal band. Event Classification Site Area Emergency per SS2
.1, Failure of Reactor Protection System Instrumentation to Complete or Initiate an Automatic Reactor Scram Once a Reactor Protection System Setpoint Has Been Exceeded and Manual Scram Was NOT Successful
- END OF SCENARIO ***
SEG Validation Checklist 2013 NRC Scenario #3 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 25 of 26 Correct IC or plant status identified.
Shift turnover forms filled out (both CRS/OSM and NSOE) if required.
Additional documents are prepared (STPs, Work Orders, LCO Paperwork).
Tasks and Objectives have been verified to be correct.
Plant PRA initiating events, important equipment and important tasks are identified.
SOMS tags identified and included in setup instructions.
Special setup instructions identified; handswitch manipulations, procedure markups, alarm borders, 3D case available, computer points substituted, etc.
Setup files correctly called out.
Malfunction list is accurate.
Override list is accurate.
Remote function list is accurate.
Event triggers are accurate.
Time/Notes section is accurate and includes all reasonable cues that may be given to initiate an action. Cues are unambiguous and provide a definitive moment to take action. Instructor Activity section is accurate and complete:
Actions are clearly defined for Booth or Floor instructor.
Role-playing is clearly noted.
The sequence of events is completely and concisely narrated even if it takes no instructor action.
Automatic actions that require verification are noted.
Reasonable alternate paths are considered and included.
Event trigger activation is distinguished from narrative text (Bold font
) Noun descriptions of actions that occur on event trigger initiation are complete, for example "-set ET 3 to TRUE which activates malfunction SW21C resulting in a loss of the C Well Water Pump
." Other simulator control actions are clearly distinguished from narrative text, for example "-after drywell temperature reaches 280 deg. F SNAP the simulator to IC 0." Student and Instructor copies of worksheets or other training activities are verified correct and electronically attached to the file if appropriate.
SEG Validation Checklist 2013 NRC Scenario #3 2013 DAEC NRC Scenario 3 Script, Rev 01-14-13 Page 26 of 26 Expected Student Response Section is accurate and complete:
Critical tasks are accurate and clearly identified. Probable critical tasks are also listed with logical connection to the scenario; for example "If the crew fails to get all the rods inserted before ED the critical task becomes-" (N/A as appropriate)
Tasks are clearly noted and properly numbered as appropriate. Knowledge objectives are clearly noted and properly numbered as appropriate.
Expected as well as probable student responses are listed with logical connection to the scenario. (N/A as appropriate)
Actions are appropriately delineated by position(s); OSM, CRS, STA, RO, NSOE, Fire Brigade Leader, At the Controls Operator, etcetera. (N/A as appropriate)
Success paths are procedurally driven unless specific training not requiring procedures is desired and delineated. Procedural discrepancies are identified and corrected before training is given.
Responses for all communications to simulated personnel outside the Control Room are included, based on procedural guidance and standard operating practices.
Actions are listed using a logical order; by position and chronology. (N/A as appropriate)
Operating Experience, Human Performance Tools and Operator Fundamentals topics are included when appropriate.
Crew Performance Criteria follow the same chronology as the student responses, are complete and accurate. (For ESGs only)
For Walkthrough and Training Mode Scenarios with pre
-planned pauses, sufficient information is presented to allow the instructor to meet the goal of the training.
Turnover information (as required) is correct:
Day and shift are appropriate.
Weather conditions do not conflict with malfunctions. Power levels are correct.
Thermal limit problems and power evolutions are realistic and include a reason for any downpower.
Existing LCOs include start date, remaining time and actions.
Plant Risk Assessment (CDF and Color).
STPs are appropriate for day and shift.
Core Damage Frequency has been properly calculated and listed to 3 decimal places. Maintenance is realistic for plant conditions.
Comments, evolutions, problems, etc, includes extra personnel (licensed/non
-licensed if necessary), any condition that affects the flow of the scenario and any condition that does not fit in another category.
SME/Instructor Date SME/Instructor Date SEG Validation Checklist 2013 NRC Scenario #3 Crew: Instructors:
OSM ____________________________
Booth ________________________________
CRS ____________________________
Floor __________________________
STA __________________________________
Extra ________________________________
1C05 ____________________________
1C03 ____________________________
BOP ____________________________
Crew Comment:
Resolution:
Crew Comment:
Resolution:
NOTE: Following approval of SEGs, this page may be discarded.
SEG Validation Checklist 2013 NRC Scenario #3 Crew Comment:
Resolution:
Crew Comment:
Resolution:
Crew Comment:
Resolution:
NOTE: Following approval of SEGs, this page may be discarded.