ML081330659
| ML081330659 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/29/2008 |
| From: | Ludlam G AmerGen Energy Co |
| To: | Caruso J Operations Branch I |
| Hansell S | |
| Shared Package | |
| ML072851077 | List: |
| References | |
| U01688 05000219/2008-301 | |
| Download: ML081330659 (98) | |
Text
OC ILT 07-1 NRC Exam Scenario NRC SIM 1 NRC SIM 1 Simulator Scenario Summarv Event Event Summary 1 The BOP will backwash condenser C South section IAW procedure 323, Main Condenser Circulating Water System, section 8.3.12. This will require several switch manipulations (2 switches to place into backwash; same 2 switches to recover from backwash). (BOP:
NORMAL EVOLUTION) 2 After the backwash is complete, the ATC will withdraw 6 control rods from position 10 to position 12. Then, the ATC will recover reactor power by raising reactor recirculation flow. (ATC: REACTIVITY MANIPULATION) 3 The Unit Supervisor will be notified by Work Control that thermography images of the in-service Steam Packing Exhauster Blower motor breaker show several hot spots indicating the possibility of failure. Work Control will recornmend that the Blowers be swapped.
The US will direct the Blowers be swapped IAW Procedure 325, Air Extraction and Offgas System.
4 The ATC will respond to indications of inadequate CRD Pump A performance. The ATC will swap CRD Pumps IAW procedure 302.1, Control Rod Drive System, section 6.3. This will require several switch manipulations (takes manual control of CRD FCV, starts second CRD pump, places CRD flow in auto, stops first CRD pump).
The SRO will declare CRD Pump A inoperable and apply Technical Specifications (TS 3.4.D.2 and TS 3.0.8 which will require a plant shutdown with EDG 2 inoperable). (ATC: COMPONENT MALFUNCTION; SRO: TECHNICAL SPECIFICATION)
[PMP-CRD002C to 75 for reduced head on CRD Pump A.]
5 The BOP will respond to annunciator J8f for high FW/Condensate pump/motor bearing temperatures. The BOP will see that the FW Pump B outboard bearing temperature (ICH-CFW065A to 190 [alarm at 1851) is high. The RAP says, if the alarm persists, to remove the FW Pump from service and perform a rapid power reduction. The BOP will shutdown the FW Pump B IAW procedure 317. Power will be first reduced to about 70%, the B String of Feedwater heaters removed (IAW procedure 317), Hydrogen injection to the B FW Pump secured (IAW procedure 31 7.4) then the FW Pump's MFRV is taken to manual and reduced, and the pump tripped.
NRC SIM 1 Page 2 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 1 6 The ATC will respond to an outward drifting control rod IAW ABN-6, Control Rod Malfunctions. This rrialfunction will require several switch manipulations (places rod power switch on, selects the control rod, and manually inserts). Upon being inserted, the control rod will become stuck at a non-fully inserted position. The SRO will declare the control rod inoperable and apply Technical Specifications for an inoperable control rod and for shutdown margin (TS 3.2.B.4 and TS 3.2.A.2). (ATC: COMPONENT MALFUNCTION; SRO: TECHNICAL SPEC I FICAT10N)
[MAL-CRD005-3015 for outward drift of control rod 30-15. MAL-CRD007-3015 for the stuck rod control rod 30-15.1 7 The crew will respond to a large feedwater line break compounded with the failure of the feedwater isolation check valves. The crew will enter the RPV Control - No AWVS EOP. During the event, if the Feedwater Pumps are not secured, all Feedwater Pumps will trip. The crew will Emergency Depressurize (ED) when RPV water level reaches 0. (MAJOR)
[MAL-CFWO126 to 100°/o for feedwater line break. SRV-CW002B to 100% and SRV-CFWOO3B to 100% for backseat leakage.]
8 The crew will respond to the failure of all Core Spray System Parallel Isolation Valves to open. The valves will open by actions of the RB EO when requested to open the valves. The crew will be successful in recovering RPV water level after ED. (FAILURE AFTER EOP ENTRY)
Critical The SRO will direct Emergency Depressurization when RPV water Task #1 level reaches 0 provided at least one injection source is lined-up and running. ED will rapidly reduce RPV pressure to allow maximum injection of low pressure injection systems. (PRA) Or, With low pressure systems running that have the capacity to restore and maintain RPV water level, the SRO will direct to lower RPV pressure as necessary to allow low pressure systems to inject.
Critical The EO opens the Core Spray System Parallel Isolation Valves to Task #2 allow Core Spray injection to recover RPV water level above the top of active fuel (TAF). Recovering RPV water level will re-assure adequate core cooling to minimize fuel damage. (PRA)
NRC SIM 1 Page 3 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 1 Op-Test No.: OC 2008 Scenario No.: NRC SlMl Event No.: 1 Event
Description:
Backwash Condenser half. C South section IAW Procedure 323.
Initiation: Following shift turnover, or as directed by the Lead Examiner.
- _ ~- _ _ - ~~ __ _ _ _ _ ~
Cues: As directed by the SRO.
---I--
Time Position Applicant's Actions or Behavior I SRO Provides Pre-shift brief.
Directs BOP to backwash the Condenser half C South IAW Procedure 323, starting at step 8.3.13.1.
Notifies the Work Week ManagerIOS when backwash is complete to evaluate condenser performance IAW Procedure 323.1
__ __ _ ~ ~
t- BOP - ~~ -~ _ ~~ -
Performs backwash of the Condenser half C South IAW Procedure 323. [PANEL 5F/6F]
- . ~
Initiates the backwash Notifies EO of backwash status Places COND C SOUTH BACKWASH CONTROL switch to BACKWASH (spring return to normal)
After approximately 10 seconds, places COND C SOUTH ClRC WATER INLET & OUTLET switch to CLOSE (spring return to normal)
Verifies the following valve positions:
V-3-17, COND C SOUTH INLET VALVE closed
. V-3-32, COND C SOUTH OUTLET VALVE closed V-3-23, COND C SOUTH BACKWASH VALVE open
. V-3-26, COND C SOUTH CROSS-CONNECT VALVE open V-3-31, COND C SOUTH NORTH OUTLET VALVE closed
- V-3-16, COND C NORTH INLET VALVE open
. V-3-22, COND C NORTH BACKWASH VALVE closed Allows the backwash to continue for approximately 3-5 minutes, and monitors the following:
Condenser Hotwell Level Turbine Exhaust Hood Temperature
~- - - -~ ~ _ _
NRC SIM 1 Page 4 of 25
. Condenser vacuum Secures from backwash 0 places COND C SCPUTH ClRC WATER INLET & OUTLET switch to OPEN 0 After approximately 10 seconds, places COND C SOUTH BACKWASH CONPROL switch to CLOSE Verifies the following valve positions:
. V-3-17, COND C: SOUTH INLET VALVE open
.. V-3-32, COND C:; SOUTH OUTLET VALVE open V-3-23, COND C: SOUTH BACKWASH VALVE closed
.. V-3-16, COND C: NORTH INLET VALVE open V-3-31, COND C:: SOUTH NORTH OUTLET VALVE open
.. V-3-22, COND C NORTH BACKWASH VALVE closed V-3-26, COND C:SOUTH CROSS-CONNECT VALVE closed Notifies the SRO that the backwash of Condenser half C South IS complete and that to evaluate the condenser performance IAW Procedure 323.1. - -- - -
- ~ -- - ~ - -
Provides peer check for valve manipulations.
Terminus: 1 The backwash of Condenser half C South is complete.
NRC SIM 1 Page 5 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 1 3p-Test No.: OC 2008 Scenario No.: NRC SlMl Event No.: 2
!vent
Description:
Withdraws Control Rods.
nitiation: The backwash of Condenser half C South is complete, or as directed by the
-ead Examiner. (NOTE: The Reactor Engineer remains in the CR for this evolution.)
h e s : As directed by the SRO.
Time 1 Position Applicants Actions or Behavior
~ - _ -~ - ~ - -__ - - - - ~
SRO Conducts a pre-job reactivity maneuver brief.
Directs the ATC to withdraw control rods IAW the reactivity maneuver sheet .
Acts as the Reactivity Manager during the evolution.
~ .~ - ~ - - - ~- - - - - ~~ - -
- - ~ ~ - ~ -
r-BOP Provides a peer-check for withdrawing control rods and initials on the reactivity maneuver sheet after each control rod is withdrawn .
__ - _ - - ~ ~ - - - -~
Withdraws control rods IAW the reactivity maneuver sheet and Procedure 302.2, Control Rod Drive Manual Control System.
[PANEL 4F]
Verifies the PERMIT light is illuminated Places the ROD POWER switch to ON.
Selects the control rod by depressing the corresponding pushbutton on the CONTROL ROD SELECT matrix.
o Verifies the pushbutton light is lit and no others are lit.
Places the ROD CONTROL switch to ROD OUT NOTCH for about 1 second and verifies:
o Green INSERT light is illuminated for about 1 second.
Releases the switch and Verifies:
o The red WITHDRAW light is illuminated about 2 seconds after the switch movement and remains on for about 1.5 seconds.
o The control rod latches in the next even-numbered position before the SETTLE light is extinguished.
o Initials on the reactivity maneuver form.
- - The ATC
~ ~. ~may request suspension
- - - ~- of place keeping
__ during- the NRC SIM 1 Page 6 of 25
OC ILT 07-1 NRC Exam !kenario NRC SIM 1 evolution.
Repeats this process for all control rods to be withdrawn.
Reports the control rods have been withdrawn.
Terminus: Control rods have been withdrawn.
I No- - tes/Co mment s .. .~. . ~
NRC SIM 1 Page 7 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 1 Op-Test No.: OC 2008 Scenario No.: NRC SIM1 Event No.: 3 Event
Description:
Swaps Steam Packinq Exhauster Blowers.
Initiation: Control rods have been withdrawn, or as directed by the Lead Examiner.
- _-_ ~ _- ___ - - ~. _ - --_____ .-
Cues: As directed by the SRO.
Time I Position 1 Applicants Actions or Behavior BOOTH Call the SRO as Work Control and report the following: I have just been CUE: discussing thermographic images of the breaker for the Steam Packing Exhauster Blower 1 with the Offgas System Engineer and Electrical Maintenance. The images show several hot spots, which could be predictive of failure. We recommend that you swap blowers so that the breaker can be inspected. _ _ _ _
- _ - - _- ~ _ - _ _ - _
SRO Directs the BOP to swap Steam Packing Exhauster Blowers IAW procedure 325. _ - -_ ~_ __
_ - _.___ ~_ -- - _-- -
BOP Swaps Steam Packing Exhauster Blowers o Starts EXHAUSTER BLOWER 2 by placing its control switck to START o Verifies Blower ON light is on o Throttles open EXHAUSTER VALVE 2 V-7-39 with its control switch to OPEN and release o Throttles closed EXHAUSTER VALVE 1 V-7-38 with its control switch tcl CLOSE and release o When the EXHAUSTER VALVE 1 V-7-38 is closed, stops the EXHAUSTER BLOWER 1 by placing its control switch to STOP o Adjusts EXHAUSTER VALVE 2 V-7-39 as necessary to maintain GLAND STM HEADER VACUUM at 15 - 17.5 inches of water Reports Steam Packing Exhauster Blowers have been swapped.
NOTE: i Have the procedure 325 N/Ad appropriately up to section 5.4 to provide the 1 Crew to- allow them to move forward.
NRC SIM 1 Page 8 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 1 NRC SIM 1 Page 9 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 1 Op-Test No.: OC 2008 Scenario No.: NRC SIM1 Event No.: 4 mp A low pump head conditions lnitiationfiw-17~ as dirrected by the Lead Examiner.
Cues: Annunciator H7c, CHARG WTR PRESS LO; CRD Hydraulic System indications are lower; CRD Flow Control Valve indicates full open Time Position Applicants Actions or Behavior
. - ~ ~~~ ~~~-~ - -
ATC Responds to annunciator H7c, CHARG WTR PRESS LO Monitors CRD system indications Reports low readings on the CRD system and the CRD FCV IS full open [PANEL 4F]
Directs an EO to check the CRD Pump A locally and the pump breaker [ROLE PLAY 11 May refer to Procedure 235 Swaps CRD Pumps IAW Procedure 302.1, section 6.3.1 Directs the RB EO to the CRD Pump Room with a radio Places the CRD FLOW CONTROLLER in MAN Starts CRD Pump B by placing the CRD PUMP NC08B control switch to START [ROLE PLAY21 Confirms normal CRD System flow 55-65 gpm and confirms a good pump start with the local EO [ROLE PLAY31 Stops CRD Pump A placing the CRD PUMP NC08A control switch to STOP Places the CRD FLOW CONTROLLER in AUTO Verifies normal CRD System indications Reports CRD Pump B running and CRD Pump A IS secured.
~ ~ ~- ~~~
~ _ _ ~~- ~~ -~ - - - ~
SRO Directs the ATC to swap CRD Pumps IAW Procedure 302.1, section 6.3.1 Declares CRD PUMP A inoperable Applies TS 3.4.D.2 and TS 3.0.B o The Unit shall be placed in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />
~~
Notifies the WWWSM about CRD Pump A
~ ~~
NRC SIM 1 Page 10 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 1
~-
BOP 1I 0
-Makes plant announcement for the start of CRD Pump B
___.. _L--_ - ~- . - __ - - - - _- . ~- _- _ - _
ROLE General Instructions: Wait 1-2 minules after being requested to perform an PLAY action, then report.
- 1. As the RB EO sent to check CRD Pump A, report CRD Pump A is operating but it is making a lot more noise than usual. Oil levels are normal. No abnormal indications at the breaker
on CRD-Pump B.- - ~_ - - - - - - - - _
____ I -- -_ - __ _ _ - __ -_ - - - _ - - _
Terminus: CRD Pump B is running and CRD Pump A is secured; The SRO has briefed the Crew.
I I NRC SIM 1 Page 11 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 1 Op-Test No.: OC 2008 Scenario No.: NRC SIM1 Event No.: 5 Event
Description:
Respond to hiah temperature on Feedwater Pump B bearinq Initiation: CRD Pump B is running and CRD Pump A is secured; The SRO has briefed the Crew, or as directed by the Lead Examiner.
- ~ -- - -- -- - - -- -- - . - ~-
Cues: Annunciators J8f, COND/FD PMP BRC; TEMP HI Time Position I Applicants Actions or Behavior
--- 1 _- . - ____~~~ - . . - - - _ _ - - ~ ~ . _- -- - --
The intent of this event is to cause the Crew to shutdown Feedwater Pump B iAW procedure.
SM and ask I- f - -- -~ -
__ - - ~ - -- _ _ ~ -- -
BOP Responds to annunciator J8f, COND/FD PMP BRG TEMP HI Verifieshdentified high bearing temperature on FW Pump B outboard bearing Directs EO to verify TBCCW to FW Pump B and supply to the bearing [ROLE PLAY11 Removes FW Pump B from service IAW procedure 317 Removes the FW Pump 6 heater string from service IAW procedure 317.1 [PANEL 7F] (Steps may be performed concurrently) o Slowly throttles closed the HP EXTRACTION STEAM ISOLATION valve 183 V-1-96 (NOTE: Valves V-1-96 and V-1-95 may be performed concurrently) o Verifies MOISTURE REMOVAL VALVE OPEN annunciator N2e is received o Directs the EO to place the alternate drain valve control switch for heater 163 to AUTO, V-4-14 [ROLE PLAY21 o Remove the IP Heater by slowly throttling closed the IP EXTRACTION STEAM ISOLATION valve 162 V-1-95 o Verifies MOISTURE REMOVAL VALVE OPEN annunciator N5e is received o Directs the EO to place the alternate drain valve control switch for heater 162 to AUTO, V-4-15 [ROLE PLAYS]
~ ~ ---- - - - -
NRC SIM 1 Page 12 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 1 Directs the EO to secure hydrogen injection to FW Pump B IAW procedure 317.4 [ROLE PLAY41 Shuts down FW Pump B IAW procedure 317 o Places the FW Pump B MFRV FLOW CONTROLLER V-ID1 1 B in MAN o Monitors flows through the other FW Pumps o Directs the EO to start the auxiliary oil pump for FW Pump B by pressing the start pushbutton and latching [ROLE PLAY51 o Slowly closes FW Pump B MFRV by rotating the manual knob CCW and observes other controllers o Verifies MIN FLOW VALVE opens at about 0.25 x 1O6 Ib/hr o When MFRV controller indicates 0% (closed), closes the HEATER BANK OUTLET Valve V-2-11 o Stops the FW Punvp B by placing FEED PUMP 1B control switch to STOP [BOOTH]
o Directs EO to secure B Feed Water Pump supplemental cooling [ROLE PLAY61 Reports the FW Pump B is secured.
-~ - ~~ ~ ~-~ . _ - ._ __ __ ~_
ATC Reduces recirculation flow as directed by rotating the MASTER RECIRC SPEED CONTROLLER manual knob CCW, as directed For a rapid power reduction, rotate the MASTER RECIRC SPEED CONTROLLER manual knob CCW to no less than 8.5 x 1O4 gpm or as directed NRC SIM 1 Page 13 of 25
OC ILT 07-1 NRC Exam !Scenario NRC SIM 1 I ROLE PLAY ~
General: Wait 1-2 minutes after being requested to perform an action, then report.
- 1. As the EO requested to verify 1BCCW and supply to FW Pump outboard bearing, report TBCCW lineup I S correct and that the supply to the bearing has been verified.
1 2. As the EO requested to place the alternate drain valve control switch for I heater 183 to AUTO, V-4-14, report that it is in AUTO.
- 3. As the EO requested to place the alternate drain valve control switch for heater 182 to AUTO, V-4-5, report that it is in AUTO.
- 4. As the EO requested to secure hydrogen injection to Feedwater Pump B, then Insert VLV-HWC002 to CL.OSE; then report you have the closed indication for the valve.
- 5. As the EO requested to start and latch the FW Pump B auxiliary oil pump, insert LOA-CFW059 to START and then notify that the auxiliary oil pump is started
- 6. As the EO requested to secure B Feed Water Pump supplemental cooling, acknowledge the report. _ _
SRO I Provides brief prior to down power I
Directs ATC to reduce reactor power with recirculation flow to reduce load on FW Pump B to clear the FW Pump alarm With the alarm persisting, directs the ATC to perform a rapid power reduction 1 Directs the BOP to remove the FW Pump B from service IAW procedure Notifies Ops. ManagemenVSM for the power reduction and to I
make required not if icat ions I ! _~
Notifies WWM/SM for the FW Pump B repair
_ - _ ~
NRC SIM 1 Page 14 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 1 NRC SIM 1 Page 15 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 1 0
Op-Test No.: OC 2008 Scenario ho.: NRC SlMl Event No.: 6 Event
Description:
Responds to a driftinq-out. control rod Initiation: Reactor power has been reduced and FW Pump B has been removed from service.
- ._ - ___ - ____ ~~ - - ~ . --- -
~ ~~ ~- - -
Cues: Annunciator H6a, ROD DRIFT Time Posit ion Applicants Actions or Behavior
~ - -~ -~ - -
Responds to annunciator H6a, ROD DRIFT Reports control rod 30-15 is drifting out Enters ABN-6, Control Rod Malfunctions [PANEL 4F]
o Places ROD POWER switch to ON o Selects control rod 30-15 o Inserts control rod 30-15 to its original position by placing the ROD CONTROL switch to ROD IN and releases o Reports control rod 30-15 is drifting outward again o Inserts control rod :30-15 to the full in position by placing the ROD CONTROL switch to ROD IN o Reports control rod 30-15 is at position 00 while still holding the ROD CONTROL switch o After the single rod scram, releases the ROD CONTROL switch o Directs the EO to isolate HCU 30-15 [ROLE PLAY41 o Turns ROD POWER switch OFF.
- - ~~
~ ~. ---
Scrams control rod IAW procedure 302 2 o Asks for SM/QNE permission to scram control rod 30-15
[ROLE PLAY11 o Directs EO to verify open HCU 30-15 valves 101, 102, and 108 [ROLE PLAY;!]
o Obtains key from SM Office o Unlocks Panel 6XR o Points to switch 30-15 o Peer checker verifies correct switch o Places the correct toggle switch in the up position (scram)
~ - ~ -~ - - -
NRC SIM 1 Page 16 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 1 o Verifies scram display on Panel 4F [BOOTH]
o Places correct toggle switch in the down position o Verifies scram signal removed o Locks Panel 6XR i.ind returns the key
_ - - _ -~ __- __ - ___ __ _ _
SRO Directs entry into ABFJ-6, Control Rod Malfunctions Notifies Reactor Engineering about the control rod [ROLE PLAY31 Declares control rod 30-15 inoperable and applies TS 3.2.B.4 o 3.2.B.4: Verifies 5 6 inoperable control rods Briefs the Crew on the Tech Specs Notifies WWM/SM of the control rod problem - _
BOOTH When control rod 30-15 is indicated scrammed, DELETE the CRD maIf unct ion.
1---
~
I
~ _._ . - 1 -_ - _ -- _ - _ _ - . - .
ROLE 1. If asked for permission from the Shift Manager and QNE, to scram control PLAY rod 30-15, role play as both and provide permission.
- 2. When asked to as the EO to verify open HCU 30-1 5 valves 101, 102, and 108, report the valves are open
- 3. As System Manager and Reactor Engineering, when contacted about the drifting control rod, acknowledge the report.
- 4. When asked as the EO to isolate HCU 30-15, acknowledge the report. No action is required. Report when isolated.
.___ -7 -_ - ~ _ - -- - - - - - ~ - _ _ _ ~ _ _ _ _ _ _ _ _
- - -_ - __ -I_ ~ _- _- - - -- - _ - __ ___- _-__
Terminus Control rod 30-1 5 has been inserted/scrammed and the SRO has addressed TS 3.2.B.4.
1 NRC SIM 1 Page 17 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 1 Op-Test No.: OC 2008 Scenario Lo.: NRC SIM1 Event No.: 7/8 Event
Description:
Feedwater line break in the Turbine Buildincl followed by the failure of FW check valves leadina to a LOCA outside the Primarv Containment Initiation: Control rod 30-15 has been inserterYscrammed and the SRO has addressed TS 3.2.B.4.
- - ~~ - ~ - - - - - ~- ~ - - -~
Cues: Annunciator P2f, CONDENSATE BAY 1-2 LEVEL HI; RPV water level lowers; FW flow becomes > steam flow; Annunciator J8c FCS/RFCS TROUBLE; Feed Pumps flow becomes limited (MFRV LIMIT light ON)
Position Applicants Actions or Behavior
__ -- __ ~ ~- -_ - . ~~~~ - - -
BOP 0 Responds to Annunciator P2f, CONDENSATE BAY 1-2 LEVEL HI and directs to verily locally [ROLE PLAY11 0 Reports RPV water level Performs Support Procedure 2 o When RPV water level begins to rise, trips 1 FW Pump by placing its control switch to STOP o May re-start the FW Pump to control RPV water level 0 Performs SP-11 and cycles IC condensate return valves as required to maintain given RPV pressure band Bypasses ADS by placing key into ADS TIMER keylocks and rotates to BYPASS Performs Support Procedure 8 o Confirms MFRVs in MAN and opens Places ROPS switch in BYPASS when directed
-~- ~~~ - - - .._ - --- -- ~ - -- ~ -
ATC Reports FW Flow > steam flow 0 Reports the FW Pumps are at runout conditions 0 Lowers recirculation flow as directed by rotating the MASTER RECIRC SPEED CONTROLLER manual knob CCW to no less than 8.5 x 1O4 gpm if directed to reduce FW demands 0 Scrams reactor when directed o Depresses MANUAL SCRAM BUS 1 and BUS 2 o Places the REACTOR MODE SELECTOR switch in SHUTDOWN o Inserts
-~ - -
SRMs,
~- ~
- ~-~ --
NRC SIM 1 Page 18 of 25
OC ILT 07-1 NRC Exam !Scenario NRC SIM 1
~-
e Performs Support Procedure 3 o Starts the standby CRD Pump by placing its control switch to start o Directs the EO to close the CRD Charging Header Supply valve V-15-52, to open CRD Bypass Isolation Valve V 237, and to throttle with CRD Bypass Valve V-15-30 [ROLE PLAY21 e Reports all FW Pumps tripped and reports RPV water level e Performs Support Procedure 9 o When RPV pressure drops to .= 305 psig, confirms open Core Spray Parallel Isolation Valves (Failed to auto open) o Manually opens all PARALLEL ISOL valves when RPV 1 pressure drops < :305 psig e Places AUTO DEPRESS VALVE to MAN to open EMRVs to lower RPV pressure e Places all AUTO DEPRESS VALVE to MAN for ED e When RPV pressure lowers, opens Core Spray is injecting and RPV water level rising
__ ~_ _ ~_ _ - _- _~ _ - - . -
e May directs the ATC to reduce power with recirculation flow to reduce FW flow demands e Directs manual scran-i prior to the auto RPV water level setpoint e Directs entry into RPV Control - No ATWS EOP e Directs Support Procedure 1 e Directs ATC to maintain RPV water level 138-175 with Support Procedure 2 and 3 e Directs RPV pressure 800-1000 psig with TBV e When RPV water level lowers to near 86, directs RPV pressure control to the Isolation Condensers IAW Support Procedure 11 e With RPV water level < 61, directs ADS bypassed e Directs confirmation of Isolation Condensers e Directs Support Procedure 8 and 9 e Directs RPV pressure be reduced with ICs and RPV pressure to allovv low pressure e IF RPV water level lowers to 0, directs ED o Directs ROPS bypassed o Directs all EMRVS opened
_ - _ _ _ -~
NRC SIM 1 Page 19 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 1 ROLE 1 - - ~- - - - ~
General: Wait 1-2 minutes after being requested to perform an action, then PLAY report.
Also report that water is raining down from the ceiling in the FW Pump Room.
- 2. As the EO directed to close the CRD Charging Header Supply valve V 52 and to open CRD Bypass Isolation Valve V-15-237, insert LOA-CRD024 to 0 (close V-15-52) and LOA-CRD052 to 1 (open V-15-237) and open V-15-30 LOA-CRD51 to 1 (open) 1RPV pressure has been reduced and Core Spray is injecting into the RPV
- -- - - -- - - -- ~ - - .- - -- . ~
NRC SIM 1 Page 20 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 1 SIMULATOT SETUP
- 1. Setup to full power IC-65.
- 2. Reduce power with recirculation flow to 95% (about 43 hz.)
- 3. Insert control rods 14-31, 38-31, 38-23, 14-23, 30-15, and 22-15, from position 12 to position 10.
- 5. Place RWM in bypass and hang tag.
- 6. Place Dilution Pump 2 in PTL and hang tag.
- 7. Place EDG 2 in Local Stop: Insert LOA-DGNOOS to STOP. This will activate annunciator RAP-T5f (EDG2 NOT IN AUTO) and hang 2 tags.
- 8. Have a completed reactivity maneuver sheet (include control rods 22-15, 14-23, 22-39, 30-39, 38-31 and 30-15 from position 10 to position 12).
- 9. Have a copy of procedure 325, N/Ad section 5 up to section 5.4 to swap exhauster blowers.
- 10. Have Procedure 323 completed for backwash up to step 8.3.13.
Malfunctions:
Malfunction None 1
None
~~ --- - -
None
~ ~ ~-~ -- - - .- --
PMP-CRD002C to 75%
This causes a reduction in head of the running CRD Pump A i -
5 T2 f ICH-CFW065A from 185-190 over 10 minLJtes This will increase the Feedwater Pump B outboard bearing from 185 OF to 190 OF- over the period
. _WHEN- the ~-
FW Pump B is tripped, NRC SIM 1 Page 21 of 25
OC ILT 07-1 NRC Exam !Scenario NRC SIM 1
... - _ . ~~ ~ _ _ _ -
DELETE the malfunction.
Insert VLV-HWC002 to CLOSE INSERT This will close hydrogen injection valve when required V-567-34 to FW Pump B Insert LOA-CFW059 to START This will manually start FW Pump B auxiliary oil pump
. ~ ~
MAL-CRD005-3015 This will cause control rod 30-15 to drift outward DEfLETE this malfunction when the single rod is scrammed.
~
MALCFW012B to 20% over 20 minutes This will cause a FW leak in the W Heater Bay T4 --+
SRV-CFW002B to 100% with.a 8 minute delay SRVCFW003B to 100% with a 8 minute delay This causes a leak through the FW line check valves to reduce RPV water level T4 --> MAL.CFWOO6A with a 10 minute delay MAL-CFWOO6B with a 10 minute delay MAL-CFW006C with a 10 minute delay This will cause a trip of all Feedwater Pumps
_ _ ~
~. ~~ ~ - - - ~~
PRESET VLV-CSSOll (for V-20-40) to FAIL AUTO OPEN VLV-CSSOO4 (for V-20-15) to FAIL AUTO OPEN VLV-CSSOI 2 (for V-20-41) to FAIL AUTO OPEN
~ -~ ~~-
NRC SIM 1 Page 22 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 1 VLVCSSOO6 (for V-20-42l)to- FArCAUTO 0PE:N 0 This prevents auto opening of the Core S1:)ray System Parallel Isolation Valves NRC SIM 1 Page 23 of 25
4 OC ILT 07-1 NRC Exam Scenario NRC SIM 1 Procedures Event ~
Number
-Title
- --- -1 I
I
~
Main Ccndenser Circulating Water System
- _ -- -_ - -~ - - __ -- - - __
1 2
- 1 302.2
~
135 Handout provided
- - --I-I Control Rod Drive Manual Control System OP-AB-300-1003/3, Reactivity Maneuver I
I I
Approval Cover Page and Reactivity Maneuver Guidance Sheet 3 --
I Air Extraction and Offgas System I
I CHARG WTR PRESS LO 4 R A P - H ~ /c 1 i 11
~ -
Determiriation and Correction of Control Rod -1
- - - - - - - Drive System Problems
- - - -1 Control Rod Drive System
- - -__ -__ - 1 COND/FD PMP BRG TEMP HI - - - - JI Feed_wa_
ter _ - -
- 1 FW -Heaters
- - - - - - -- _ - 1 FW Hydrogen Injection i
Power-Operation . - 1 ROD DRIFT - - - - 4 Control Rod Malfunctions - - - - -
I 4
Control Rod Drive Manual Control System
- _ _ - - - - - 1 CONDENSATE BAY 1-2 LEVEL HI I FCS1RFC:S TROUBLE - - - - -
I NRC SIM 1 Page 24 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 1 Shift Turnover 1 . The plant is at 92% power with condenser backwash in-progress.
- 2. The following equipment is out of seirvice:
- a. EDG 2 is out of service to replace a fuel pump.
- b. RWCU Pump B is out of service for repair.
- c. Dilution Pump 2 is out of service for maintenance.
- d. The RWM is out of service due to a fault, and is bypassed.
- e. Plant risk is yellow
- 3. Following shift turnover:
- a. Complete the condenser backwash IAW Procedure 323
- i. Complete the backwash on condenser half C South, starting at step 8.3.13.1.
- b. Following the backwash, withdraw control rods IAW the Reactivity Maneuver Form.
NRC SIM 1 Page 25 of 25
OC ILT 07-1 NRC Exam Scenario NRC SIM 2 NRC SIM 2 Simulator Scenario Summary
~ - _ ~ - ~ - - _- - - - ~ -~~
Event Event Summary
~ - - _ _ - ~
~c - ~-
The BOP will complete procedure 61 0.4.002, Core Spray Pump Operability Test. This will require several switch manipulations (securing the running core spray booster pump and then the running core spray pump). After the Core Spray Test Valve (V-20-27) is closed, an electrical short will cause it to re-open and cannot be closed. The SRO will declare Core spray System 1 inoperable and apply Technical Specifications (TS 3.4). (BOP: NORMAL EVOLUTION; SRO: TECHNICAL SPECIFICATIONS)
- ~ -- ~- -~ - ~~ _-__ - ~
The BOP will respond to the loss of 480 VAC USS 1 B1 and enter ABN-47, Loss of USS 181. The standby TBCCW Pump fails to auto start and is manually started. l h e BOP performs several switch manipulations (start TBCGW Pump 2, start SJAE Drain Pump 1-1, place Aux. Flash Tank Pump 1-1 in auto, start air compressor 1, and place the condensate prefilter bypass switch to open). (BOP:
COMPONENT MALFUNCTION) I
_- ~-~ - _ . ~ _ -_- - ~
The in-service main generator isophase cooling fan will trip (RAP-R7d). The SRO will direct that reactor power be reduced with recirculation flow. (ATC: REACTIVITY MANIPULATION) 4 As reactor power is reduced, APRM 4 will slowly fail upscale. This will result in a '/2 scram and control rod block. The ATC will bypass the APRM and reset the !/z scram. (ATC: COMPONENT MALFUNCTION)
~ ~ ~
5 EMRV 6 will inadvertently operi and the Crew will respond IAW ABN-40, Stuck Open EMRV. The BOP will place Feedwater Control in manual, then attempt to close the valve with the front panel switch, then by placing the inside panel switch to disable, which will close the valve, and place FWLCS back in auto. The SRO will declare the EMRV inoperable and apply Technical Specifications (TS3.4.B.2). If torus temperature gets high enough, the Primary Containment Control EOP will be entered and torus cooling initiated.
(BOP: COMPONENT MALFUNCTION; SRO: TECHNICAL ~
I SPEC I FIC AT10N)
-~ - _ - I 6 The ATC will respond to a high temperature control rod 46-15 (at position 48). The ATC will perform stall flows IAW procedure 61 7.4.002, CRD Exercise and Flow TesVlST Cooling Water Header Check Valve. This requires placing the rod power switch on, selecting the high temperature control rod and instituting a withdraw
~ -
signal several-times.
~-- This _will clear
- _ the- alarm. (ATC:
- - COMPONENT NRC SIM 2 Page 2 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2 7 The crew will respond to rising fuel failures and an Isolation Condenser B tube leak, which cannot be isolated. The crew will enter the Radioactivity Release Control EOP. The Isolation Condenser tube leak will not be isolable. The crew will scram when fuel damage is evident. When the SM/ED declares a General Emergency, the Crew will Emergency Depressurize the RPV.
(MAJOR) 8 The crew will respond to the loss all condensate pumps when the first EMRV is opened for the ED. This will remove feedwater/condensate as an injection source and RPV water level will be maintained with Core Spray when RPV pressure reduces to 305 psig. Core Spray will fail to automatically start and wil be manually started and injected. (COMPONENT MALFUNCTION AFTER EOP)
Critical Manually scram the reactor when indications are present of core Task #1 damage with an Isolation Condenser tube leak. This action places the reactor in the lowest energy state and allows a cooldown and depressurization to minimize the severity of an offsite radiological release.
Critical Emergency Depressurize the RPV when a General Emergency (for Task #2 offsite release) is declared and a primary system is discharging outside primary and secondary containment. This reduces the driving head responsible for the offsite radiological release rate.
P A )
NRC SIM 2 Page 3 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2 Op-Test No.: OC 2008 Scenario No.: NRC SIM2 Event No.: 1 Event
Description:
Continue in Surveillance tpst 61 0.4.002, with failure of Core Spray Test Valve V-20-27 Initiat ion: FoIlow ing shift turnover
__ __ ~ - -- _-- -
Cues: As directed by the SRO
.~
Time Applicants Actions or Behavior Conducts pre-shift brief.
Directs BOP to continue in surveillance test 610.4.002, Core Spray Pump Operability Test, starting at step 6.9 Notifies WWM/SM about V-20-27 stuck open. May request from the SM what to do about the surveillance [ROLE PLAY]
Declares Core Spray System 1 inoperable Reviews/applies Tech Specs 3.4.A.1 o The plant may rerriain in operation for 7 days.
Briefs the Crew As the SM, when asked how to proceed with the surveillance after the valve
- - ~-
- -_ r ~
0 failure, tell him to leave it i nt e current configuration until the event has been investigated.
i
~ _- - ~ _ _ - _ ~- _ - -
BOP Continues in surveillance test 61 0.4.002, Core Spray Pump 1 Operability Test, starting at step 6.9 [PANEL 1F/2F]
Stops Core Spray Booster Pump by placing BOOSTER PUMP NZ03A control switch to STOP NOTE: TIME COMPRESSION IS USED HERE: REPORT THAT >10 MINUTES HAS ELAPSED.
Records pressure and flow data Directs the EO to close valve V-20-27 [ROLE PLAY 11 Verifies V-20-27 indicates closed Directs EO to verify Core Spray Keep Fill Pump NZ04A is running (MCC 1 E321B, Unit C03) [ROLE PLAY 21 Stops Core Spray Main Pump NZOlA by placing MAIN NRC SIM 2 Page 4 of 26
OC ILT 07-1 NRC Exam !Scenario NRC SIM 2
. -~ .. . _ . _- ___
PUMP NZOTA contrbl switch to STOP j clear
~ Directs the EO i o unlock and open Torus Test Return Line Vacuum Breaker on RB 51' NM, V-20-262 [ROLEPLAY 31 I When Core Spray PUMP DISCH PRESS - MAINS is no longer rising, directs the EO to close and lock V-20-262 1 [ROLE PLAY 411
' Directs EO to turn off and lock V-20-27 supply breaker
~- - -
1 -_
(MCC lA21B) -
[ROLE PLAY 51 .
- - - _ __ _- ~
~- - -- - - - - ~_ - _
ROLE 1 . As the EO, when requested to close valve V-20-27, wait 1 minute, then PLAY insert LOA-CSS031 to NORMAL and LOA-CS030 to CLOSE. When the valve indicates closed, report that V-20-27 indicates closed. (step 6.16)
- 2. As the EO, when requested to verify Core Spray Keep Fill Pump NZ04A running, wait 1 minute and then report that it is running. (step 6.17.1)
- 3. As the EO, when requested to unlock and open Torus Test Return Line Vacuum Breaker on RB 51' NM, V-20-262, wait 1 minute and then report the valve is open. (step 6.17.5)
- 4. As the EO, when requested to close and lock Torus Test Return Line Vacuum Breaker, V-20-262, want 1 minute and then report the valve is closed and locked. Also report that another Operator has verified the valve closed and locked.
- 5. As the EO, when requested to turn off and lock the breaker for V-20-27, acknowledge the report. Then ir'isert: LOA-CSS030 to NORMAL and LOA-CS031 to open to re-open V-20.27. THEN report that V-20-27 now indicates open. If requested to re-close, report that it will not close, and that the control switch is in the closed position.
~- _ _ _ - _
_ _ - ~- __ 1 - - -~ -~ - - __. _
Terminus Core Spray System 1 is declared inoperable and Tech Specs applied.
NRC SIM 2 Page 5 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2 Op-Test No.: OC 2008 Scenario No.: NRC SIM2 Event No.: 2 Event
Description:
Responds to a loss of US-S 1B1 and the failure of TBCCW Pump to auto start Initiation: Core Spray System 1 is declared inoperable and Tech Specs applied.
_ _ __ - - __ - .. _ _ ~~ ~ ~ _ ~
Cues: Annunciators U l c , 1B1 MN BRKR TRIP; T6d, FDR TO 460V 1B1 TRIP Time 1 Position Applicant's Actions or Behavior
_ _ ~~~ ~ ~_ _~~ ~~~ _~~~
BOP Responds to annunciators U1c, 1B1 MN BRKR TRIP; T6d, FDR TO 460V 1B1 TRIP Reports the loss of llSS 1B1 and responding IAW ABN-47, Loss of USS 1B1 o Starts TBCCW Pump 2 by placing TBCCW PUMP 2 switch to start [PANEL 13R]
o Monitors TBCCW temperatures o Confirms 1-1 Station Air Compressor is operating [PANEL 7F]
o Monitors Instrument Air pressure [PANEL 5F/6F]
o Directs EO to confirm Condensate Prefilter System Bypass Valve V-425-301 is open on LIR-425-1-8 [ROLE PLAY 11 o Opens V-425-301 by placing V-425-301\CS to OPEN [PANEL 5F/6F]
o Confirms Trunion Room Ran 1-6 is operating [Panel 10R]
o Monitors Trunion Room temperatures o Confirms SJAE Drain Pump 1-1 operating o Confirms AUX FLASH TANK DRAIN PUMP switch is in AUTO and is controlling [PANEL 7F]
o Monitors Feed Pump and Condensate Pump temperatures
[PANEL 12XRl o Confirms Exhauster Blower #1 IS operating [PANEL 7F]
o Confirms with EO that Stator Cooling Pump 1A is operating
[ROLE PLAY 21 o Directs EO to operate 1-2 and/or 1-3 sump pumps o Confirms with EO that Phase Bus Cooling Fan 1-1 is operating [ROLE PLAY 31 o Directs EO to conl'irm V-567-0005 is closed, HWC Isolation Valve [ROLE PLAY41
~~ o Verifies Main Tranlsformer M1A cooling power remains on its
_~
NRC SIM 2 Page 6 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2
- - - _ _ _ _ ~ _ _ _ - -~ ~ -.
normal power feed as indicatedby alarm R6e clear o Confirms with EO that Main Transformer M1A cooling fans and oil pumps are running [ROLE PLAY 51 o Verifies Main Transformer M1 B cooling power remains on its normal power feed as indicated by alarm R6f clear o Confirms with EO that Main Transformer M1B cooling fans and oil pumps arc? running [ROLE PLAY 61 o Verifies Aux Transformer cooling power remains on its normal power feed as indicated by alarm S6a clear o Confirms with EO that Aux Transformer cooling fans and oil pumps are running [ROLE PLAY 71 o Monitors TB area temperatures and AP o Notifies
-~
Rad Pro and Chemistry of the bus loss
___ -~ ~ - _ _ ~- - - ~~-
-__ -- -- - - - - - ~ ~_ _ - _ _ - ~- _
Directs the BOP to enter and perform ABN-47, Loss of USS 1 B1 Notifies WWM/SM about the loss of USS 151
~~ - _ - ~ _ . ~ _ - -
Makes plant announcement for loss of USS 1 B1 Directs EO to investigate tripped breaker 1B1 [ROLE PLAY81
_- ~ -_ - - - - _ . ___ _ ~_
NRC SIM 2 Page 7 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2
- - - - - - -- ~ -- _ -__ _ ~
ROLE 1. When asked as the EO to confiirm Condensate Prefilter System Bypass PLAY Valve V-425-301 is open on L15-425-1-8, wait 1 minute and then report:
Valve V-425-301 is open.
- 2. When asked as the EO to confirm Stator Cooling Pump 1A is running, wait 1 minute and report: Stator Cooling Water Pump 1A is running.
- 3. When asked as the EO to confirm Phase Bus Cooling Fan 1-1 is running, wait 1 minute and report: Phase Bus Cooling Fan 1-1 is running.
- 5. When asked as the EO to confirm that the Main Transformer M1A cooling fans and oil pumps are running, wait 1 minute and report: the Main Transformer M1A cooling fans and oil pumps are running. The emergency power breaker is tripped.
6 . When asked as the EO to confirm that the Main Transformer M1B cooling fans and oil pumps are running wait 1 minute and report: the Main Transformer M1B cooling fans and oil pumps are running. The emergency power breaker is tripped.
7 . When asked as the EO to confirm that the Aux Transformer cooling fans and oil pumps are running, wait 1 minute and report: the Aux Transformer cooling fans and oil pumps are running. The emergency power breaker is tripped.
- 8. When asked as the EO to investigate USS 161 main breaker, report that is
- - ~ ~ ._
is open and is hot to the touch. _ -
7-
_~ ~ _~ - I - - - - ~ - - _ _--_ - -- -
Terminus The Subsequent Operator Actions in ABN-47 have been completed.
NRC SIM 2 Page 8 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2 Op-Test No.: OC 2008 Scenario No.: NRC SIM2 Event No.: 3 Event
Description:
lsophase Fan 1 Tri Initiation: The Subsequent Operator Actions in ABN-47 have been completed.
Cues: Annunciator R7d, ISOL PH FAN 1 TRIP Time 1 Position Applicant's Actions or Behavior
~p 1 -- - -~ p . ~ - - .-p - - . _ - _ _ p -
NOTE, The intent of this event is to cause the SRO to direct a reactor power reduction. The RAP directs that the internal bus temperature shall not exceed 120 "C. Role Play temperatures may need to be adjusted to cause the reactor power reduction in a timely manner. Once power has been reduced, report lower temperatures than provided at rated reactor power.
7-
! BOP Responds to annunciator R7d, ISOL PH FAN 1 TRIP o Reports lsophase Fan 1 tripped o Direct EO to monrtlor 3 internal bus contact temperatures and to investigate the tripped isophase fan [ROLE PLAY 11 o Directs EO to monitor external temperatures with a contact
__ -p pyrometer at the top and middle of the duct-also - -
. _ _ p ~
~ 1 Notifies WWM/SM to replace the belts on the lsophase Cooling Fan1 1 -
Directs the ATC to reduce reactor power with recirculation flow ATC Reduces reactor power as directed by rotating the knob CCW on the MASTER RECIRC SPEED CONTROLLER until the desired power is reached
- -p - p -~ - p- -~ - ~ . _ p _ _
NRC SIM 2 Page 9 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2
- 1. When directed to monitor 3 internal bus contact temperatures and to investigate the tripped isophase fan, wait 2 minutes and then report: the 3 internal bus contact temperatures indicate 100 "C, 102 "C, and 101 "C, and rising slowly. Also report that the isophase fan 1 belts have disintegrated and little pieces are everywhere.
- 2. After about 5 minutes after the last report above OR before power is reduced: Call the Control Rooni and report: the 3 internal bus contact temperatures indicate 103 "C, '105 "C, and 104 "C, and still rising slowly (LIMIT is 120 "C). The maximum surface temperature IS177 "F and rising slowly (LIMIT is 200 "F).
- 3. After reactor power has been reduced to 5 90% power, call the Control Room and report: 3 internal bus contact temperatures indicate 104 "C, 105 "C, and 105 "C, and steady. Duct surface temperatures have also stabilized with the highest reading at 183 "F.
- . _ - _ ~ _ - - -
.~
Terminus: Reactor power has been reduced to 1. 90% with recirculation flow.
NRC SIM 2 Page 10 of 26
- - * - -I--
OC ILT 07-1 NRC Exam Scenario NRC SIM 2 Op-Test No.: OC 2008 Scenario No.: NRC SIM2 Event No.:
Event
Description:
Respond to the upscale failure of APRM 4 Initiation: Reactor power has been reduced to 5 90% with recirculation flow.
Cues: Annunciators G l c , SCRAM CONTACTOR OPEN; G l d , CHANNEL I; G l f , APRM HI-HI INOP I; G3f, APRM HI; H7a, ROD BLOCK I-Time 1 Position 1
1 Applicant's Actions or Behavior t-
- - - ~ _ . - - - - - -
Responds to annunciators G1c, SCRAM CONTACTOR OPEN; G l d , CHANNEL I; G l f , APRM HI-HI INOP 1; G3f, APRM HI; H7a, ROD BLOCK Reports Y2 scram on RPS 1 Reports APRM 4 indicates upscale; all other APRMS indicate normally Verifies APRM drawer readings Byasses APRM 4 IAVV Procedure 403 [PANEL 4F]
o Places the APRM BYPASS joystick to APRM 4 position o Updates Attachment 403-2 as directed by the SRO Resets the M scram by depressing the SCRAM SYSTEM RESET pushbutton Reports APRM 4 is bypassed and the '/2 scram reset
- -. - - ~ - ~ - -~ ~ -__ __
1 __
~
_- ~ - _ - -
Verifies able to bypass APRM 4 Directs ATC to bypass APRM 4 IAW Procedure 403, and then to 1 0 1 reset the Y2 scram Notifies WWM/SM about the failed APRM 4 May update Attachment 403-2
~- - - - - _ _ _-
1 BOP 1 Makes plant announcement to stop surveiNance testing 0 Verifies APRM 4 indicates bypassed on Panel 3R
- - - - ~- - -
APRM 4 is bypassed and the '/i scram is reset.
NRC SIM 2 Page 11 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2 NRC SIM 2 Page 12 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2 Op-Test No.: OC 2008 Scenario No.: NRC SIM2 Event No.: 3 Event
Description:
Electromatic Relief Valve-EMRV NRlO8B opens Initiation: APRM 4 is bypassed and the M scram is reset.
- ~ - - --_ - ~ -~ _ - - ~ - ~
Cues: Annunciators B39, EMRV OPEN; B4g, SV/EMRV NOT CLOSED; Audible alarm Time Position Applicant's Actions or Behavior
~ _~ _ . _ ~
BOP Responds to annunciators B3g, EMRV OPEN; B4g, SV/EMRV NOT CLOSED Reports EMRV NR108B is open from acoustics and tailpipe temperatures Enter and performs ABN-40, Stuck Open EMRV c Waits for RPV water level transient to clear o Updates the Crew about placing FW Control in manual c Places Feedwater control in manual by selecting MAN on the MASTER FEEDWATER LEVEL CONTROLLER [PANEL 4F]
c Places the AUTO DEPRESS VALVE NR108B switch in OFF
[PANEL 1F/2F]
o Recognizes/reports the valve still open c Cycles the AUTO DEPRESS VALVE NR108B switch from OFF to MAN to OFF o Recognizes/reports the valve still open c Cycles the AUTO DEPRESS VALVE NR108B switch from OFF to MAN to OFF 3-5 times c Recognizes/reports the valve still open c Places the EMRV NORMAL/DlSABLE NR108B keylock switch to DISABLE [INSIDE PANEL 1F/2F]
o Recognizes/reports the EMRV is closed o Places Feedwater Control back in AUTO:
m Selects the P display on the MASTER FEEDWATER LEVEL CON'TROLLER Selects the S display on the MASTER FEEDWATER LEVEL CONTROLLER
. Verifies S and P are matched (raises or lowers as required) on the MASTER FEEDWATER LEVEL CONTROLLER m Places Feedwater control in automatic by selecting AUTO NRC SIM 2 Page 13 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2
. ~
.. on the MAST[% FTEDWATERLEVELCONymLLER Verifies the green AUTO light is lit Monitors RPV water level and adjusts as required o Resets the MASTER ALARM units in Panel 15R to silence the acoustic monitor alarm by pressing the reset buttons o Plots the EMRV dlowncomer temperature IAW Procedure 602.4.003 o Refers the SRO to Tech Spec 4.5.F.5 and 4.5.L.
- -~ _ ~ -- ~ - ~ - ~~ -
~ ~ ~ - __ -- .
SRO Directs entry into ABN-40, Stuck Open EMRV Directs entry into Primary Containment Control EOP if/when Torus water temperature exceeds 95 OF o Directs ATC to initiate Torus Cooling IAW Support Procedure 25 (using a given loop)
Reviews/applies Tech Specs 3.4.6.2 o The reactor may remain in operation for a period not to exceed 3 days provided the motor operated isolation and condensate makeup valves in both isolation condensers are verified daily to bc operable, Reviews/applies Tech Spec 4.5.F.5 o Once every 3 moriths and following any release of energy which would tend to increase pressure in the suppression chamber, each operable suppression chamber-drywell vacuum breaker shall be exercised.
Reviews/applies Tech Spec 4.5.L.3 o Whenever heat from relief valve operation is being added to the suppression pool, the pool temperature shall be continually monitored and also observed until the heat addition is terminated.
Updates the Crew.
Notifies WWM/SM about the failed EMRV.
Makes notification to Management about the TS required shutdown. _ _ - - _ -_.
I -
ATC Reports EOP entry into Primary Containment Control EOP if/when Torus water temperature exceeds 95 OF Initiates Torus Cooling IAW Support Procedure 25 [PANEL 1 F/2F] (Assume Torus Cooling System A) o Confirms the SYSTEM 1 MODE SELECT and SYSTEM 2 MODE SELECT switches are in the TORUS CLG position
_. ~ ~ - _~ . _ - _ _ ~ - ~_ ~
NRC SIM 2 Page 14 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2
__- - -~ - - -
~ - _ ~ ~ - -
o Starts the associated ESW Pump by placing the ESW PUMP 52A switch to ST84RT o Starts Containment Spray Pump 51A
. Places and holds the SYSTEM 1 PUMPS START
. PERMISSIVE keylock switch to the A position Starts the Containment Spray Pump by placing the CONTAINMENT SPRAY 51A control switch to START 9 Releases the SYSTEM 1 PUMPS START PERMISSIVE keylock switch o Reports Torus Cooling in service _
~ - - _ - -~
Terminus.
EMRV NRl08B is closed and Torus Cooling is in service (if Torus water temperature exceeds 95 O F ) . The SRO has reviewed/applied Tech Specs.
NRC SIM 2 Page 15 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2 Op-Test No.: OC 2008 Scenario No.: NRC SIM2 Event No.: 6 Event
Description:
Responds to a hiah temperature control rod 46-15 [See NOTE 1 below]
Initiation: EMRV NR108B is closed and Torus Cooling is in service (if Torus water temperature exceeds 95 O F ) . The SRO has reviewed/applied Tech Specs.
-p ~ - - - - -- p - -~ __ ~~
Cues: Annunciator H5c, CRD TEMP HI Time Posit ion Applicants Actions or Behavior
. ~ __ ~~ -~ - ~ -- -~ -- - ~ -- ~-
ATC e Responds to annunciator H5c, CRD TEMP HI o Verifies CRD cooling water AP and flow are consistent with those listed in Prccedure 302 1, Control Rod Drive System o Directs EO to check for a leaky scram discharge valve on HCU 46-15 [ROLE PLAY]
o Applies stall flow IAW Procedure 617.4.002 [NOTE 21 Places the ROD POWER switch to ON Selects control rod 46-1 5 by depressing its P/B switch Holds the NOTCH OVERRIDE switch to NOTCH OVERRID E Holds the ROD CONTROL switch to ROD OUT NOTCH position
- When the control rod returns to position 48, releases the switches Repeat 2 more times for control rod 46-15 [BOOTH]
I [NOTE 3) o Reports the high temperature alarm has cleared o Places the ROD POWER switch to OFF
~ _ - ~ _ ~ . ~ - - - p ~_.-p
- _ _ ~ _ _ ~ _ p _ _ ___ ~ -
Identifies control rod 46-1 5 as the high temperature control rod I
on Panel 8R recorders [NOTE 31 Checks the control rod temperature panel on 8R and confirms 1
I the high temperature 110 longer exists NRC SIM 2 Page 16 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2
. - - ~ ~_ - _ _ _ _ _ _ --
NOTE 1. Because the CRD temperature recorders do not function, POST a stickey with 46-15 indicates 260 F and steady on the recorder BEFORE the annunciator is brought in.
- 2. Have SQRd copy of 61 7.4.002 ready. initial step 6.1, and N/A step 6.2. The candidates will perform step 6.3. N/A all steps after this.
- 3. PRIOR to clearing the alarm, remove the previous stickey, and place a new stickey: 46-15 indicates 235 F and steady
-_ _~ _
- ~ - _-_
_- i
- _. _I-. - - ~- _ _ ~ _ - _- - -_
ROLE 1 . When directed as the EO to check for a leaky scram valve on HCU 46-1 5, PLAY watt 1 minute and then report: the scram discharge piping on HCU 46-1 5 and ones on either side of 46-1 5 all feel the same, and not too hot.
- -~ - -
-_ _ I-
~~ .-- _ - ____ -~ - _ _ ~_ - ~_ - - - - ____ _ - _ _ _ ~- - -
While the candidate is applying the stall flow the third time, then place ANN-H5c to OFF.
_ - ~ - _ - - - _ -_ - ~ _ _ _
- _ ~ 1 _ _ _ - - ~ __ _~ - - ~- ~ -
The high temperature control rod has been cleared.
Notes/Co m men t s -
~ _ _~
N R C SIM 2 Page 17 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2 Op-Test No.: OC 2008 Scenario No.: NRC SIM2 Event No.: 7 Event
Description:
Responds to Isolation Condenser B tube leak with indications of fuel failures Initiation: The high temperature control rod has been cleared, or as directed by the Lead Examiner.
-- ~-~ ~ __~_ ~ ~ -
Cues: Annunciator 1OF1 k, AREA MON HI; SJAE area radiation monitor tripped high; Later, annunciators C6b, SHELL B LVL HVLO; C3b, COND B FLOW HI POSSIBLE RUPTURE
-~ -~~
Time Position Applicants Actions or Behavior
- -~ -~ - ~~ -~
BOP 0 Responds to Annunciator 1OF1k, AREA MON HI o Reports SJAR radiation monitor in high alarm o Announces evacuation of the affected area e Reports offgas radiation monitors rising e Performs ABN-26 o Directs Chemistry to sample offgas and reactor coolant o Informs the SRO of Tech Specs 3.6.E and 4.6.E o Informs Reactor Eogineering e Responds to annunciators C3b, COND B FLOW HI POSSIBLE RUPTURE and C6b, SHELL B LVL HVLO o Checks area temperatures o checks shell level (high) o checks shell temperature (high) o Reports indications of a tube leak in IC-B o Reports that Isolation Condenser B failed to isolate and attempts to isolate without success 0 Reports Isolation Condenser area radiation monitor above its alarm point (EOP entry) e Places ROPS switch in BYPASS when directed for ED 0 Performs ED by placing all AUTO DEPRESS switches to MAN A position e Performs Support Procedure 4 o Starts one Core Spray Main Pump in each System by placing their control switches to START
~ o Starts
- - one Core
- Spray Booster Pump in each System by- -
Page 18 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2 placing their control switches to START-o When RPV pressure drops to < 310 psig, opens Core Spray Parallel Isolation Valves with their control switches to OPEN o Reports Core Spray is injecting and RPV water level rising o Control RPV water level 100 - 175 by cycling the Core Spray Parallel Isolation Valves
__ _____ ~- -
- ~_ - __ - ~ _ ____
- __ _ ~ _
_ - - -~ -
Directs entry into ABIV-26 Directs entry into Radioactivity Release Control EOP o Directs BOP to isolate IC-B, if not already attempted o When fuel failures are recognized by high offgas/MSL radiation monitors high alarm, directs ATC to manually scram Directs entry into Secondary Containment Control EOP o Directs isolating Isolation Condenser B, if not already attempted Directs entry into RPV Control - No ATWS o Directs BOP to perform Support Procedure 1 c Directs ATC to perform Support Procedure 2 c Directs RPV water level 138 - 175 o Directs RPV pressure 800 - 1000 psig with TBV Directs entry into ED - No ATWS o Directs ROPS bypassed o Directs all EMRVS opened With RPV water level lowering after the Condensate Pumps tripped, directs Support Procedure 3 Directs Support Procedure 4 to maintain an RPV water level 100 - 175 If RPV water level < 61:
o Directs ADS bypassed o Directs Support Procedure 9
_ ~ _ -
a Scrams the reactor when directed o Depresses MANUAL SCRAM BUS 1 and BUS 2 o Places the REACTOR MODE SELECTOR switch in SHUTDOWN o Inserts SRMs, IRMs o Reports all control rods in Performs Support Procedure 2
_ ~
NRC SIM 2 Page 19 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2
~- - - __ __ ~
o With RPV water level rising after the scram, trips 2 Feedwater Pumps by placing their control switches to STOP o Manually controls Feedwater flow with the MFRVs to maintain desired water level 138 - 175 Reports Condensate Pumps tripped Reports RPV water level lowering and when below 138 Reports when HPV water level reaches LO-LO setpoint Performs Support procedure 3 o Confirms CRD Pumps running o Directs EO to close CRD Charging Header Supply Valve V-15-52 o Directs EO to open CRD Bypass Isolation Valve, V-15-237 and to monitor flow o Directs EO to throttle open CRD Bypass Valve V-15-30 not to exceed 150 gpm Bypasses ADS by placing key into ADS TIMER keylocks and rotates to BYPASS, if requested
~ ~- - _ -
ROLE After the scram and RPV water level and pressure are under control, call the PLAY control room as the ED and state that you are declaring a General Emergency due to Offsite Radiological Release.
_ - ~ -
1 - - - ~ - - - ._ - __
The RPV has been emergency depressurized and Core Spray is injecting to raise RPV water level.
NRC SIM 2 Page 20 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2 SIMULATOI- SETUP
- 1. Setup to full power IC-65.
- 3. Place RWM in bypass and hang tag.
- 4. Hang tag on Dilution Pump 2.
- 5. Start Core Spray IAW 610.4.002 (Core Spray Pumps NZOlA and NZ03A running with V-20-27 open). The Crew will start at step 6.9. Have 2 copies:
1 for the crew, and 1 for the booth.
- 6. Start SJAE Drain Pump 1-2. Verify TBCCW 1 and 3 running; and Aux.
Flash Tank Drain Pump 1-2 running.
- 7. Have a clean signed/dates Attachment 403-2 in the 403 book.
Malfunctions:
~- - _ ~ -_ ~ -- _- __-__
Triqqer PRESET Malfunction LOA-CSSO17 to FALSE
- ~~ ~
-1 This will close the breaker for Core Spray test valve V-20-27 LOA-CSS031 to OPEN This will open Core Spray test valve V- 1 20 -27 LOACSS031 to NORMAL I
LOA-CSS030 to CLOSE I I
I This will close V-20-27 2
standby TBCCW Pump on the loss of ~
USS 1B1 (it also fails annunciator Q l f ) 1 NRC S I M 2 Page 21 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2 I MAL-EDSOO3D 0 This will trip USS 1B1
- ~ ~ __ ~~ -
3 PMF" - G EA 005B 0 This provides a shaft seizure on lsophase Fan 1 and resultant trip
-. ~ - - -~ ~ ~
4 MAL -NIS020D This results in an upscale failure of APRM 4 and '/2 scram
~- ~ ~~ ~
SW I -ADS002C to ON This will cause EMRV MR108B to open with the control switch and will close when DISABLED
. ~- ~ _ _ ~ ~ ~~ -~ - -
T5 -+ ANN-H5c to ON This makes annunciator H5c, CRD TEiMP HI, turn on PRESET VLV. ICs008 to MECH SIEZE (V-14-33)
VLV.ICSOO7 to MECH SIEZE (V-14-32)
This keeps IC-B steam IVs open T6 ICH-RMS032A to 2.1 This raises SJAE area rad monitor to just above its alarm point ICH-RMS054A 200 to 300 over a 15 minute period ICH-RMS055A 200 to 300 over a 17 minute period This raises the offgas rad monitors to the values listed over the ramp time EVENT Insert Event Trigger 7: hwx07d014r.gt.250 TRIGGER 7 MAL-ICS002B at 50% on trigger 7 I
T7 This starts a tube leak in IC-B when
~ ~ ~
NRC SIM 2 Page 22 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2
- - ~ - - -
offgas rad monitor reaches 250 mr/hr INSERT WHEN the SRO has entered RAD REL.EASE CONTROL EOP: Insert ICH-RMS054A 700 to 825 over a 6 minute ramp ICH-RMS055A 700 to 800 over a 5 minute ramp This raises the offgas rad monitors to above the OFFGAS HI alarm setpoint (700 mr/hr)
EVENT TRIGGER 8 On TRIGGER 8: hwxOlo076r.gt.O This conditional trigger will activate Trigger 8 when EMRV NR108A red light comes on (during ED)
T8 --t MALCFW003A MALCFW003B MAL-CFW003C When triggered, all condensate pumps ,
will trip PRESETS MAL-CSSOO7A MAL-CSS007B MAL-CSS007C MAL-CSS007D This prevents Core Spray auto start and the parallel IVs will not auto open
~ - -
- - - i - - _ - _ -
NRC SIM 2 Page 23 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2 Procedures I Event I -
Number/revision I -
Title
-~
1 1 I
I 610.4.002 / 48 1 Core Spray Pump Operability Test 602.4.003 / 31
__- __-I ' Electromatic Relief Valve Operability Test ]
I97 - Control Rod Drive System I
1 6 1 617.4.002 I 4 8 CRD Exercise and Flow Test/lST Cooling I
I I Water Header Check Valve RAP-1OF1 k 1 AERA MON Hi i
7 1 ABN-26/2 High Main Steam/Offgas/Stack Effluent
-I--
I
_ _ ~
Activity
- I-_-
I RAP -
OF2c - - -
OFFGAS HI L
7 I RAP-C6b - -I SHELL-E LVL HI -- - - _ -- . --- -
1 -
7 1 RAP-C4b I I
COND B VLVS OFF NORM NRC SIM 2 Page 24 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2 NRC SIM 2 Page 25 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 2 Shift Turnover
- 1. The plant is at 100% power with Procedure 610.4.002, Core Spray Pump Operability Test in-progress.
- 2. Plant risk is yellow.
3 . The following equipment is out of service:
- a. RWCU Pump B is out of service for repair.
- b. Dilution Pump 2 is out of service for maintenance.
- c. The RWM is inoperable and is bypassed.
- 4. Following shift turnover:
- a. Continue in Procedure 610.4.002, Core Spray Pump Operability Test, starting at step 6.9.
- b. This is a normal surveillance for Core Spray Main Pump NZOlA and Core Spray Booster Pump NZ03A only.
NRC SIM 2 Page 26 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 NRC SIM 3 Simulator Scenario Summary Event Event Summaw 1 The BOP will startup Feedwater Pump B and place it on the Master FW Controller IAW Procedure 317, Feedwater System and 202, . The BOP will also initiate hydrogen injection to the pump and place the IP/HP feedwater heaters is service IAW Procedure 317.1. (BOP: NORMAL EVOLUTION) 2 The ATC will withdraw 4 coritrol rods from position 40 to position 48 as part of a planned control rods for flow swap. The last control rod will be uncoupled and entry into ABN-6, Control Rod Malfunctions, will be made. The control rod will be inserted, where it will re-couple, and be withdrawn to position 48 (place rod power switch to on, select the control rod, rod control switch to rod out notch, rod control switch to rod in, rod control switch to rod out notch). (ATC: COMPONENT MALFUNCTION) 3 The ATC will raise reactor power to 75% with recirculation flow and notify Reactor Engineering as a hold point. (ATC:
R EACT IVlTY MAN IPULATlO N) 4 The BOP will respond to EPR setpoint changes resulting in lower RPV pressure (and will diagnose a faulted EPR) and will enter ABN-9, Electronic Pressure Regulator Malfunction. The BOP will place the MPR in control, secure the EPR, and raise RPV pressure back to normal. (BOP: COMPONENT MALFUNCTION) 5 The SRO will respond to the CNTRL DC LO/LOST annunciator and will declare EDG 1 inoperable. The SRO will apply Technical Specifications. (TS 3.7) (SRO: TECHNICAL SPECIFICATIONS) 6 The BOP will respond to RWCU non-regenerative heat exchanger outlet temperature alarm (D8b) with a failure of the RWCU System to trip and isolate. The BOP will manually perform these functions.
This will require several switch manipulations (trips RWCU Pump, close isolation valves V-16-7 and V-16-14), (BOP: COMPONENT MALFUNCTION) 7 The ATC will respond to a trip of the in-service CRD Pump. IAW the RAP, the ATC will start the standby pump and then a control rod drift inward will occur. The ATC will insert the control rod IAW ABN-6, Control Rod Drive System. The SRO will apply Technical Specifications. (ATC: COMPONENT MALFUNCTION; SRO:
TECHNICAL SPECIFICATIONS)
NRC SIM 3 Page 2 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 EMRV E will begin to leak to the Torus. The BOP will enter ABN-40, Stuck Open EMRV. The BOP will not be successful in stopping the leak. The SRO will direct a manual scram. There will be an electric ATWS. The crew will enter RPV Control -With ATWS and lower RPV water level and inject SLC. (MAJOR) (PRA)
The first SLC Pump will not function and the alternate SLC Pump will be started. (COMPONENT MALFUNCTION AFTER EOP)
Critical Tas,, Inject SBLC when Torus water temperature cannot be maintained
- 1 below the boron injection initiation temperature (BIIT). This will ensure that the hot shutdown boron weight of boron will be injected before the torus temperature exceeds the heat capacity temperature limit (HCTL) of the primary containment. (PRA)
Critical Task Insert control rods IAW Support procedure 21. Complete insertion
- 2 of control rods is an absolute method in ensuring that power production has been ceased, and is preferable to boron injection alone.
Critical Task With reactor power > 2%, terminate and prevent injection into the
- 3 RPV by all systems except CrRD and Boron injection systems IAW Support procedure 17. These actions lower core subcooling to reduce the possibility of reduce/prevent power oscillations.
NRC SIM 3 Page 3 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 Op-Test No.: a 2 0 0 8 Scenario No.: NRC SIM3 Event No.: 1 Event
Description:
Starts Feedwater PumD ti3 Initiation: Following shift turnover, or as directed by the Lead Examiner
_ _ ~ ~ -~ -~~ -~
Cues: As directed by the SRO Time Position Applicants Actions or Behavior
- - ~- - ~ ~ - _ - .~ - ~ ~
Directs the BOP to start the Feedwater Pump B IAW procedure 317 ~~ ~ -
~ ~~ ~ ~ - ~
Starts Feedwater Pump B IAW procedure 317 [Panel 5F/6F]
e Places the FEED PUMP 1B control switch to START and holds e When FEED PUMP AMPS 1B indicates breaker closed, releases the switch e Verifies proper operation of Feedwater Pump B [ROLE PLAY11 o Requests EO report on FW Pump operation e Requests EO to stop the FW Pump B auxiliary oil pump [ROLE PLAY21 e Places HEATER BANK OUTLET V-2-11 to the OPEN position e Operates the FW Pump for 10 minutes [LEAD FLOOR NOTE]
e Initiates flow through the FW Pump B by slowly rotating the MFRV FLOW CONTROLLER V-ID11 B manual know CW e Monitors flow in the other 2 FW strings to ensure they reduce flow as flow from the FW Pump B rises e When FEED PUMP CIISCHARGE FLOW 1B reaches about 0.5 x 106 Ib/hr, verifies MIN FLOW VALVE V-2-19 closes e When the S display and the V display are about equal on MFRV FLOW CONTROLLER V-ID1 1E, presses the AUTO/MAN button Reports that FW Pump E is in automatic on the Master Controller Directs EO to start hydrogen injection to FW Pump B IAW procedure 317.4 [ROLE PLAY31 Places the FW Pump B feedwater heaters in service IAW procedure 317.1 at step 2.3.2.4 [PANEL 7F]
Slowly opens the EXTRACTION STEAM ISOLATION valve 182 V-1-95 by alternating the control switch between OPEN and spring return to NORMAL until fully open ~
NRC SIM 3 Page 4 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 Directs the EO to close IP HEATERVENT VALVE v-4-68
[ROLE PLAY41 Directs the EO to reset the Reverse Check Valve, check valve V-1-90 with trip V-6-100 [ROLE PLAYS]
Directs the EO to place the normal and alternate drain valve control switches V-4-17 in AUTO and V-4-14 in CLOSED [ROLE PLAY61 Slowly opens the EXTRACTION STEAM ISOLATION valve 163 V-1-96 by alternating the control switch between OPEN and spring return to NORMAL until fully open Directs the EO to close HP HEATER VENT VALVE V-4-72
[ROLE PLAY71 Directs EO to monitor shell water level at LIR 1-3 until level stabilizes Reports FW Pump B feed heaters in service ROLE General Instructions: Wait 1-2 minutes after being requested to perform an PLAY action, then report 1 When asked to report on the FW Pump B start, report that FW Pump B start IS good.
- 2. When asked as the EO to stop the FW Pump 6 auxiliary oil pump, insert LOA-CFW059 to STOP, and report oil pump stopped.
- 3. When asked as the EO to start hydrogen injection to FW Pump 6, insert VLV-HWC002 to OPEN, and then report hydrogen injection is in service.
- 4. When asked as the EO to closc IP HEATER VENT VALVE V-4-68, report it is closed 5 When asked as the EO to verify TRIP V-6-100 is reset in the up position, report that V-6-100 is reset in the up position 6 When asked as the EO to place the normal and alternate drain valve control switches V-4-17 in AUTO and V-4-14 in CLOSED, report the positions as NORMAL and CLOSED
~- - ---- - - - _. ~- - p - - ~ p p _ _
I---
- -_ -pi - - - - p - - ~ - -- .p_ -
LEAD Time compression may be used here. Report that 10 minutes has elapsed.
FLOOR NOTE
~-
- I_ -- - - -
Terminus FW Pump B is in service and on the MASTER FEEDWATER LEVEL CONTROLLER. Hydrogen injection and extraction steam have been established.
NRC SIM 3 Page 5 of 26
OC ILT 07-1 NRC Exam Scenario N R C SIM 3 NRC S I M 3 Page 6 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 Op-Test No.: m 2 0 0 8 Scenario No.: NRC SIM3 Event No.: 2 Event
Description:
Withdraws control rods 22-31, 22-23, 30-23, and 30-21 from position 36 to 48 and resDond to control rod 22-31 uricoupled NOTE: The Reactor Engineer is present in the Control Room during control rod manipulations.
Initiation: FW Pump 8 is in service and on the MASTER FEEDWATER LEVEL CONTROLLER. Hydrogen injection and extraction steam have been established, or as directed by the Lead Examiner.
~ - ~ - - - -~ - - __ ~~ -- -
Cues: As directed by the SRO.
Time Position Applicants Actions or Behavior
-~ _ __-_ ~ - ~~ -~
SRO Conducts a pre-job reactivity maneuver brief.
Directs the ATC to withdraw control rods IAW the reactivity maneuver sheet Acts as the Reactivity Manager during the evolution.
Notifies the Reactor Engineer about the uncoupled control rod
[ROLE PLAY] ~
~ ~ ~- ~- ~- ~ ~ __
Provides a peer-check for withdrawing control rods and initials on the reactivity maneuver sheet after each control rod is withdrawn.
~ ~ ~ - ~ ~ - .
~- - ~ ~ __ ~- ~ -- -~ ~ _~ -~ ~~
Withdraws control rods IAW the reactivity maneuver sheet and Procedure 302.2, Control Rod Drive Manual Control System.
[PANEL 4F]
e Verifies the PERMIT light is illuminated.
Places the ROD POWER switch to ON.
e Selects the control rod by depressing the corresponding pushbutton on the CONTROL ROD SELECT matrix.
o Verifies the pushbutton light is lit and no others are lit.
e Turns the ROD CONTROL switch to ROD OUT NOTCH position and simultaneously turns the NOTCH OVERRIDE switch to NOTCH OVERRIDE e Verifies:
o Amber OVERRIDE light is ON o Green insert light is ON following switch movement and remains on for about 1 second L- .- ~ - - ~
NRC SIM 3 Page 7 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 r- 0
- - --___ ~
o Rod position readout momentarily displays the next odd-numbered digit Verifies the WI'THDRAW light remains ON for the duration of the withdrawal and an increasing rod position is displayed and
~ ~-
releases at position 48 Performs a coupling check at position 48 o Turns the ROD CONTROL switch to ROD OUT NOTCH position and simultaneously turns the NOTCH OVERRIDE switch to NOTCH OVERRIDE o Verifies rod display indicates a continuous readout of 48 with red backlight [NOTE]
Reports control rod 22-31 IS uncoupled and enters ABN-6, Control Rod Drive System o Applies a continuous insert signal by placing the ROD CONTROL switch to ROD IN until a response is observed on the nuclear instruinentation (APRMs, LPRMs) or fully inserted. [BOOTH]
o Withdraws the control rod and verifies coupling at position 48 o Reports control rod 22-31 has re-coupled.
o Returns CRD Drive Pressure to normal pressure o Notifies Reactor Engineering Continues withdrawing control rods Reports all-~
control rods withdrawn IAW the reactivity
-~ _ _
maneuver form 1 - - - -
I - 1 - ~ -~ ~ ~ - - ~- -
NOTE Control rod 22-31 will be uncoupled.
I I- -
I I As the Reactor Engineer for the uncoupled rod, acknowledge the report. IF the control rod is inserted to between 24-48 during re-coupling, direct that continuous withdrawal is allowed.
~- _. -
Below this, single notch, until position 24 I
~~ -7 ~ -
I
~- _-_ . - - __-I ~ ~ ~~ ~- -- - _- ~ -~
BOOT When the RO is inserting the uncoupled control rod, DELETE the uncouple H ~ ~-
malfunction
- - ~ ~ - -
I Termi
~~
II Control rods have been withdrawn
- -~ - ~ _ _ - - - - - __ - -
nus: ,
i NRC SIM 3 Page 8 of 26
- * - ~ ---"-.." ' ~. ~ ~ ~
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 NRC SIM 3 Page 9 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 Op-Test No.: E 2 0 0 8 Scenario No.: NRC SIM3 Event No.: 3 Event
Description:
Raise reactor power with reactor recirculation flow to 75% power Initiation: Control rods have been withdrawn or as directed by the Lead Examiner.
Cues: As directed by the SRO 1
1 Time Applicants Actions or Behavior I
__ ~ - - ~
n;;P r - : jI Directs the ATC: to increase recirculation flow to raise I reactor power to 75% power Acts as the Reactivity Manager during the- evolution.
BOP 1 Provides a peer-check for recirculation flow changes.
I - -
I I -- -- - - -_ -- -_ _
ATC Raises recirculation flow in small increments by rotating the j
I 1
~ manual knob CW on the MASTER RECIRC SPEED i
CONTROLLER until 75% power is reached.
I I Notifies SRO when at 75% power.
t- - - - - .
Terminus: Recirculation flow has been raised to reach 75% reactor power.
NRC SIM 3 Page 10 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 Op-Test No.: E 2 0 0 8 Scenario No.: NRC SIM3 Event No.: 4 Event
Description:
Initiation: Recirculation flow has been raised to reach 75% reactor power, or as directed by the Lead Examiner.
Cues: RPV pressure drops in 3-4 psig incrernents; EPR RELAY SETPOINT drops in 3-4 psig increments Time Positic Applicants Actions or Behavior Reports PRV pressure lowering e Monitors__RPV _--
pressure
- -- _ ~ _-
Reports EPR RELAY SETPOINT is lowkhanged Performs ABN-9, Electronic Pressure Regulator Malfunction
[PANEL 7F]
o Slowly lowers the IVlPR setpoint by placing the MPR RELAY POSITION switch in the t % position using 1 second bumps until the MPR position indicator moves in the direction of and reaches the EPR setting and the MPR takes control o Verifies MPR CONTROLLING light is ON o Verifies the EPR CONTROLLING light is OFF o Places the EPR POWER switch to OFF o Verifies alarm Q6a, EPR PWR LOST alarm is received o Slowly raises RPV pressure to the previous pressure by placing MPR RELAY POSITION switch in the ?YOposition o Refers to Procedure 202.1 for limitations with one pressure regulator out of service (no actions required)
Reports MPR in control and RPV pressure back to its previous pressure e Directs entry into ABN-9, Electronic Pressure Regulator Malfunction e Notifies WWM/SM about the EPR failure
- __ _ - - - ~ - - -
_ - _ - __ _ ~-
- -~ -
NRC SIM 3 Page 11 of26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 Terminus The EPR IS off and the MPR is in control, and RPV pressure has been re-established.
NRC SIM 3 Page 12 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 Op-Test No.: E 2 0 0 8 Scenario No.: NRC SIM3 Event No.: 5 Event
Description:
DC power is lost to Emergencv Diesel #1 Initiation: The EPR IS off and the MPR is in control, and RPV pressure has been re-established, or as directed by the Lead Examiner.
- - _ ~ - - - - - _ - - _ -- - -_- -- - -
Cues: Annunciator T4b, EDGl DISABLED Time Position Applicants Actions or Behavior BOP Responds to Annunciator T2b, EDG1 CONTRL DC LO/LOST o Directs EO to check the EDGl local alarm panel [ROLE PLAY]
SRO 0 Notifies WWM/SM to inspect EDG1 Declares EDGl inoperable and applies Tech Specs (1 TS 3.7.C.3: the plant shall be placed in cold shutdown in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Briefs the Crew. - -
ROLE When asked as the EO to check EDGl indications, report that there is oil on PLAY -
the EDGl compartment floor and that the Engine Protection Light is ON.-
--T
~
~ - -
- - -____ _ 1 - -- _ _ - ~_
Terminus EDGl has been declared inoperable and TS have been applied.
NRC SIM 3 Page 13 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 Op-Test No.: a 2 0 0 8 Scenario No.: NRC SIM3 Event No.: 6 Event
Description:
Loss of coolinq to Reactqr Water Cleanup System heat exchanqer and failure to auto isolate Initiation: EDGl has been declared inoperatAe and TS have been applied, or as directed by the Lead Examiner.
Cues: Annunciator D8b, NRHX OUTLET TEMP HI (May also get C3f, DW PRESS H VLO)
Time Position Applicant's Actions or Behavior 1 Bop I e Responds to Annunciator D8b, NRHX OUTLET TEMP HI I o Directs EO to verify high system temperatures [ROLE PLAY11 0 Reports the RWCU failed to isolate and manually isolates i o Isolates RWCU and trips running RWCU Pump o Places SYSTEM INLET V-16-4 control switch to CLOSE o Places CLEANUP SYSTEM V-16-1 to CLOSE o Places RECIRC PUMP ND02A control switch to STOP Directs EO to check RBCCW flow/temperatures to the NRHX
[ROLE PLAY21 Reports RWCU is isolated and RWCU Pump is tripped
-- ~ - _- - - - - ~
SRO '
t Notifies WWM/SM for the event and the failure to auto isolate/trip
-~
ROLE 1 1. As the EO directed to checkhigh system temperatures, report that RWCU PLAY out of the NRHX is 160 O F and rising.
- 2. As the EO directed to check RBCCW flow/temperatures to the NRHX, report that everything appears normal.
- ~ - _
i --- - - ~- - -- ~ -- - -___-_ -~ ----
c - -
_I _ - - _ .- - - -
RWCU has been isolated and RWCU Pump tripped.
NRC SIM 3 Page 14 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 NRC SIM 3 Page 15 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 Op-Test No.: E 2 0 0 8 Scenario No.: NRC SIM3 Event No.: 7 Event
Description:
CRD Pump A trips and a sinqie control rod drifts inward when the standbv CRD Pump is started Initiation: Annunciator H l c , PUMP A TRIP; F?AP-H5c,CRD TEMP HI; H6a, ROD DRIFT
~~ ~~ _ _ ~ ~ ~
Cues: RWCU has been isolated and RWCU Pump tripped Time Position Applicants Actions or Behavior
~ -~ . ~ ~~ ~
ATC 0 Responds to Annunciator H l c , PUMP A TRIP; R A P - H ~ cCRD ,
TEMP HI 0 Reports CRD Pump R tripped o Directs EO to check CRD Pump A breaker locally at USS 1A2 and at the pump o Starts CRD PUMP NC08B by placing its control switch to START or restarts CRD PUMP NC08A by placing its control switch to START if no overload o Checks the following:
n CRD System flow
- Directs EO to check CRD Pump min. flow valve, motor/pump bearings for loss of lubrication and excessive temperatures. system leaks, pump suction valve [ROLE PLAY11 Responds to control rod drift o Reports control rod 22-31 is drifting in o Performs ABN-6 Places the ROD POWER switch to ON
. Selects control rod 22-31 by pressing the appropriate button on the control rod matrix inserts by placing the ROD CONTROL switch to ROD IN until fully inserted Directs the EO to isolate HCU 22-31 [ROLE PLAY21
__ - ~
. Notifies Chemistry
~-~ ~ _. ~ __ ~ ~ ~ _ _ ~ -
- - -_ _ ~ ~ ~ ~~ - ~~-
SRO Declares CRD Pump A inoperable Notifies WWM/SM about the pump Reviews/applies Tech Specs 3.2.6.4 o In no case shall the number of inoperable control rods valved
~~ ~~ ~
NRC SIM 3 Page 16 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3
-_. 1 - ~ _ ~_
ROLE 1. As the EO directed to check CRD Pump A, report that there is oil all over PLAY the floor around the pump, but none has gotten to any floor drains and that you are containing it.
- 2. As the 0directed to isolate HCU 22-31, DELETE the drift and report WCU isolated.
~_ r - ~ ~_ ._ _
_ L - _ ~- -
Terminus CRD Pump 6 is running and the SHO has applied Tech Specs.
NRC SIM 3 Page 17 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 Op-Test No.: E 2 0 0 8 Scenario No.: NRC SIM3 Event No.: 8/9 Event
Description:
EMRV E leaks-bv and ar! electric ATWS I
Initiation: Annunciator B4g, SV/EMRV NOT CLOSED; EMRV E indicating in the VALVE OPEN REGION; Acoustic monitor audible alarm
- ~~ -- - - - ~
Cues: CRD Pump B is running and the SRO has applied Tech Specs.
Time Position Applicant's Actions or Behavior
_ _ ~- ~ - - - ~ -
Responds to annunciator B4g, SV/EMRV NOT CLOSED Reports EMRV B indicates open Checks RPV pressure and ADS Performs ABN-40 o Waits for RPV water level transient to clear o Places Feedwater control in manual by selecting MAN on the MASTER FEEDWATER LEVEL CONTROLLER [PANEL 4F]
o Places the AUTO DEPRESS VALVE NR108E switch in OFF
[PANEL 1 F/2F]
o Recognizes/reports the valve still open o Cycles the AUTO DEPRESS VALVE NR108E switch from OFF to MAN to OFF o Recognizes/reports the valve still open o Cycles the AUTO DEPRESS VALVE NR108E switch from OFF to MAN to OFF 3-5 times o Recognizes/reports the valve still open o Places the EMRV NORMAL/DISABLE NR108E keylock switch to DISABLE [INSIDE PANEL 1F/2F]
o Reports EMRV NR108E is still open o Places Feedwater control in manual by selecting MAN on the MASTER FEEDWATER LEVEL CONTROLLER [PANEL 4F]
Bypasses ADS by placing both ADS TIMER keylock switches to BYPASS Performs Support Procedure 16 to bypass MSlV isolation o Obtains 4 bypass plugs o Inserts plug in position BP1 and BP2 in the EOP BYPASS PLUGS Panel in the rear of Panel 6R o Inserts plug in position BPI and BP2 in
~~
the EOP BYPASS NRC SIM 3 Page 18 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3
-_ - -~ _- - -
TI _- PLUGS Panel in the rear ofpanel 6R 1 o Places the ISOL SIGNAL BYPASS V-6-395 switch to BYPASS o Reports MSlV LO-LO isolation bypassed Performs Terminate and Prevent Support Procedure 17 o Presses OVERRIDE switches that are lit o Presses all ACTUATED switches o Confirm Core Spray Parallel Isolation valves closed o Confirms Core Spray Booster pumps tripped o Places Core Spray MAIN PUMP control switches in PULL-TO-LOCK position o Trips all FW Pumps by placing their control switches to STOP o Confirms 1 Condensate Pump running and trips the other 2 by placing their control switches to STOP o Places MFRVs in MAN by pressing the AUTO/MAN button on the MFRV FLOW CONTROLLERS o Closes all MFRVs by rotating the manual knob CCW o Closes all LFRVs by rotating the manual knob CCW o Reports injection terminated and prevented Maintains RPV water level -20 to 30 with Support Procedure 19 o Starts 1 FW Pump by placing its control switch to START o Manually controls flow with the MFRV manual knob Performs Support Procedure 25 o Confirms the SYSTEM MODE SELECT switch is in the TORUS COOLING position o Starts the selected ESW Pump by placing its control switch to START o Places and hold thle keylock SYSTEM PUMPS START PERMISSIVE to the selected pump o Starts the selected Containment Spray by placing its control switch to START o Reports Torus Cooling in service ATC Manually scrams the reactor o Places the REACTOR MODE SELECTOR switch in SHUTDOWN o Presses MANUAL SCRAM BUS 1 and BUS 2 o Reports failure to scram
- - ~ - -
NRC SIM 3 Page 19 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 0 Presses ALT ROD INJECTION INSERTION 0 Places ROPS in BYPASS 0 Reduces recirculatioi flow to minimum by rotating MASTER RECIRC SPEED CONTROLLER manual know CCW to minim um Trips all Recirculation Pumps by DRIVE MOTOR switches to STOP Performs Support Procedure 22 o Starts SLC Pump by placing STANDBY LIQUID CONTROL keylock to FIRE SYS 1 or FIRE SYS 2 o Reports SLP Pump IS not indicating proper discharge pressure o Starts the alternatle SLP Pump Performs Support Procedure 21 for an electrical ATWS o Directs EO to venl the Scram Air Header o Places REACTOR, SELECTOR MODE switch in REFUEL o Closes CRD DRIVE WATER PRESSURE CONTROL NC18 o Inserts Cram Array control rods Places ROD POWER to ON a Selects cram array control rod 9 Places ROD CONTROL switch to ROD IN Reports all control rods inserted (after air header de-pressurized)
Maintains RPV water level 138 - 175 with Feedwater/Condensate Support Procedure 2
- _ _ - ~ ~- ~ ~
Directs entry into ABN-40, Stuck Open EMRV 0 Directs ATC to manually scram 0 Directs entry into RPV Control - With A W S o Confirms reactor scram and Mode switch in SHUTDOWN o Confirms ARI initialed c Directs ROPS bypassed o Directs recirculation flow reduced to minimum o Directs all Recirculation Pumps tripped o When Torus water temperature cannot be maintained below BIIT, directs Liquid Poison initiated IAW Support Procedure 22 I c Directs bypassing ADS o Directs Support Procedure 21 to insert control rods NRC SIM 3 Page 20 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3
~-
o birects Support Procedure 16 to bypass MSIV LOILO isolation o Directs Terminate and Prevent Support Procedure 17 o Directs RPV water level lowered to 30 o Directs RPV water level -20 to 30with Support Procedure 19 Directs entry into Prirnary Containment Control EOP when Torus water temperature exceeds 95 OF o Directs Torus cooling IAW Support Procedure 25 Exits the ATWS EOP and enters RPV Control - No ATWS when control rods are inserted o Directs RPV water level 138 - 175 with
~~ -
Feedwa t e r/Co ndensat e SupPO rt Procedure 2
_ - ~ ~~ ~ ~
ROLE When:
PLAY RPV water level has been terminated and prevented RPV water level is being controlled -20 to 30 Control rods are being manually inserted Close the-scram air header isolation valve V-6-157: LOA-CAS 012 0 ,.I Open the scram air header drain valve V-6-409: LOA-CAS022 to 1 Report you have vented the scram air header after control rods start inserting
~- _ - -~ _ ~-
~ ~ -.I - ~ _ _ ~ ~~- ~~ -~ -
Terminus: All control rods have been inserted and RPV water level is being re-established to 138-175 in RPV Control - No A W S EOP.
Notes/Co mm ent s
~
_~ ~.
NRC SIM 3 Page 21 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 SIMULATOFj SETUP
- 1. Reset to full power IC-65
- 2. Open EMRV NR108E to raise Torus temperature to 89 OF, then close and let plant stabilize.
- 3. Insert the following control rods from position 48 to position 40:
- i. 22-31, 22-23, 30-23, 30-31
- 4. Reduce reactor power to about 70% with recirculation flow (to about 27 hz)
- 5. Place FW Pump B in manual and reduce flow to 0, and trip the pump
- 6. Close the FW Pump 6 heater bank outlet valve
- 7. Close the H2 injection valve to FWP B (V-567-34): Insert VLV-HWC002 to CLOSE
- 8. Close FWP 6 IP/HP heater valves ('7F): 1B2 V-1-95 and 163 V-1-96
- 9. Start the FW Pump B aux oil pump (LOA-CFW059 to START)
1 1. Place RWM in bypass and hang tag.
- 12. Hang tag on Dilution Pump 2.
- 13. Place EDG 2 in Local Stop: Insert LOA-DGNOO9 to STOP. This will activate annunciator RAP-T5f (EDG2 NOT IN AUTO).
- 15. Have a completed reactivity Maneuver Form for the rod withdrawal (ensure rod 22-31 is moved last).
I -
i
~~ ~ -
Event 1
~
Triqger T1 -P
~
Ma If unction Insert VLV-HWC002 to OPEN
--- - - ~-
1 I
i 1
I This will open FWP B hydrogen injection 1
valve V-567-32 to FWP B
' PRESET MAL-CRD008-.22-31 1 - 1 -
NRC SIM 3 Page 22 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3
- ~- - ~ -
This will uncouple control rod 22-31 Delete this malfunction when the Operator is inserting the control rod
- ~ ~ _ - __ ~~-~
3 ii None None T2 -+ MAL-TCSO10 to 3 psig BELOW the C U I7R EN7- set po int MAL-TCSO10 to 3 psig BELOW the PRt:fVIOUS setpoint after about 1 minute MAL-TCSOlO to 3 psrg BELOW the PREVIOUS setpoint after about 1 minute MAL--TCSOlOto 3 psrg BELOW the PREVIOUS setpoint after about 1 minute This lowers the EPR setpoint by 3 psig each time. This lowers RPV pressure about the same amount. Continue until the event is diagnosed
.. . ~- __
T3 -+ ANN-T4b to ON This activates annunciator T4b (EDG1 D ISABL ED)
_ ~ _
--I .- . -
~ ~ _ _ ~ - - __ -~
6 PRESETS MAI..-RCUO14 This inserts a failure of the RWCU System to auto isolate BKR-RCU001 to FAIL AUTO TRIP This prevent the auto trip of RWCU Pump A MAL-RBC005 T4 ----f Ttiis inserts a loss of RBCCW to the RWCU non-regenerative heat
~
ex h ang e r I I
7 T5 -+ BKR-CRD002 to TRIP This trips CRD Pump A breaker and prevents re-start NRC SIM 3 Page 23 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3
~
T6 -+ Inserton Conditional TRIGGER 6:
hwx030277r.gt.O on Event Triggers MAL-CRD006-223 1 ~
Control rod 22-31 will drift-in when the CRD Pump 6 red light comes on
~. - __ ~ ~-
8 T7 --+ MAL-NSS025E to 100% over a 3 minute ~
I ramp
~
This inserts leakage through EMRV ~
~ N R108E that cannot be stopped INSERT - f Insert CAE File ATWS at this time I This inserts an electric ATWS I PRESETS PMP-SLC001A (for SLC Pump A)
~
PMP-SLC002A (for SLC Pump B)
This places a broken shaft on each SLC ,
Pump 1
NOTE: IF SLC Pump A is started first, ,
then DELETE 002A BEFORE SLC Pump B is started NOTE: IF SLC Pump 6 IS started first, then DELETE 001A BEFORE SLC Pump A is started NRC SIM 3 Page 24 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 Procedures NRC SIM 3 Page 25 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 3 Shift Turnover Initial Conditions:
- 1. The plant is about 68% power.
2 . Feedwater Pump 8 tripped a short while ago. Investigation revealed that an electrician accidentally bumped ti relay at the breaker and there was no damage to the breaker or feedwater pump/motor. The pump is being prepared to be placed back in service.
- 3. EDG 2 is out of service to replace a fuel pump (Out of service time began this morning at 600). Technical Specifications have been reviewed and applied as required.
- 4. Dilution Pump 2 is out of service for maintenance.
- 5. The RWM is inoperable and bypassed.
- 6. RWCU Pump B is out of service.
Shift Activities:
- 1. Place Feedwater Pump B in service IAW Procedure 317, starting at step 9.3.7. After hydrogen injection to the Feedwater Pump has been established, place the associated Feedwater Heater string in service, IAW Procedure 317.1, starting at step 2 3 2 . 4 . The trip handle for the Reverse Flow Check Valve for the 162 Feedwater heater is reset. An EO has been briefed, has a copy of the procedures and is standing by.
- 2. Withdraw control rods IAW the Reactivity Maneuver Approval Form.
- 3. Raise reactor power to 75% with recirculation flow and notify Reactor Engineering when 75% has been reached.
NRC SIM 3 Page 26 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4
- _. ~ ~ - - - - - - ~-
-1
~ ~ ~ ~
Event Event Summarv
- ~- ~- -- - ~ ~- - -~ - ~ - - -
4 1 The ATC will insert control rod 22-15 from position 12 to position 00 The ATC will then withdraw control rod 22-1 1 from position 00 to I I
position 48. It will be initially stuck and ABN-6, Control Rod Malfunctions. After adjusting drive pressure, the control rod will move.
The ATC will then withdraw control to its original position (12). This ~
evolution requires several switch manipulations (rod power switch to on, select the control rod, CRD drive pressure control switch, rod I I
control switch to rod out notch). (ATC: COMPONENT MALFUNCTION)
~- _ _ - ~ - - - -~ ~-
2 The BOP will perform 609.4.001, Isolation Condenser Valve Operability and In Service Test. Manipulations include closing V 1' 36, opening V-14-34, closing V-14-34, opening V-14-5N-14-20,re-opening V-14-36. When valve V-14-36 is closed, it will not re-open.
The SRO will declare the Isolation Condenser A inoperable and will 1 apply Technical Specifications ('TS 3.8). (BOP: NORMAL I EVOLUTION; S R 0: TECH N ICAL S P EC IFIC AT10N)
I
- 3. The ATC will respond to an inoperable trip of APRM 5. The ATC will bypass the APRM and reset the YZ scram on RPS 2. (ATC:
COMPONENT MALFUNCTION)
~- ~ - - -~ . - . - --
- 4. The BOP will respond to a loss of USS 1A2 and will perform ABN-45, Loss of USS 1A2. Actions include starting RBCCW Pump 2, CRD Pump 6, securing normal RB ventilation and starting Standby Gas Treatment, restoring RPS 1, resetting YZ scram and isolations. The I SRO will apply Technical Specifications (TS 3.7). (BOP: - ,-
- I COMPONENT MALFUNCTION; SRO: TECHNICAL I S P ECIFICAT10N) 5 The BOP will diagnose reactor power oscillations due to reactor recirculation pump A, and will enter ABN-2, Recirculation System Failures. The power oscillations will be of such a magnitude that the pump will require manually tripping. This evolution will require several 1 switch manipulations (Placrng pump speed controller in manual, I manually controlling speed, trip the pump, close the pump discharge I valve). (BOP: COMPONENT MALFUNCTION)
-~ - - -- - -
1
- 6. The ATC will be directed to lower reactor power in response to high turbine vibrations by lowering recirculation flow. The vibrations will lower after reactor power is redulced (ATC: REACTIVITY MANIPULATION)
NRC SIM 4 Page 2 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4
~~
__ -~ - _ _ ~- - ~ - -_
- 7. The Crew will respond to a primary coolant leak in the Primary Containment. The reactor scram will be successful. (MAJOR EVOLUTION)
~ ~ - -~ ~ ~ - ~ ~
- 8. When the reactor is manually scrammed, the leak will worsen. Also, 30 seconds after the manual scram, there will be a loss of offsite power and a complete failure ot all Core Spray main Pumps to start (both auto and manual fail). The Crew will be successful in spraying the Drywell. RPV water level will fall to TAF, which will require an ED.
The Crew will be successful with injecting the Fire Protection System 1 via the Core Spray System, SLC Pump B and CRD Pump 6.
(COMPONENT FAILURE AFTER EOP ENTRY)
-~ ~ ~ ~ ~
Critical The SRO will direct Emergency Depressurization when RPV water 1 Task #l level reaches 0 provided at least one injection source IS lined-up and running. ED will rapidly reduce RPV pressure to allow maximum iniection of low wessure iniection svstems. [PRA) Or With low pressure systems running that have the capacity to restore and maintain RPV water level, the SRO will direct to lower RPV pressure as necessary to allow low pressure systems to inject. I
- ~ ~ ~~ -
Critical With the loss of Core Spray during a LOOP-LOCA, inject into the RPV Task #2 with Alternate Sub-systems.
~- - -~
~
~ ~~ ~
NRC SIM 4 Page 3 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4 Op-Test No.: E2008 Scenario No.: NRC SIM4 Event No.: 1 Event
Description:
Manipulates control rods and responds to a stuck control rod at position 00 Cues:
Time Position Applicants Actions or Behavior
~~ ~ ~-
SRO e Conducts a pre-job reactivity maneuver brief Directs the ATC to withdraw control rods IAW the reactivity maneuver sheet Acts as the Reactivity Manager during the evolution.
Directs entry into ABN-6, Control Rod Drive System
~
~- ~~ ~ ~~ ~ ~ - ~ - ~~ ~ __ ~
BOP Provides a peer-check for withdrawing control rods and initials on the reactivity maneuver sheet after each control rod is
~ ~
withdrawn. ~ ~ ~ - ~~ ~ - ~
~ ~ ~
ATC Withdraws control rods IAW the reactivity maneuver sheet and Procedure 302.2, Control Rod Drive Manual Control System
[PANEL 4F]
Verifies the PERMIT light is illuminated.
Places the ROD POWER switch to ON.
Inserts control rod 22-15 o Selects the control rod by depressing the corresponding pushbutton on the CONTROL ROD SELECT matrix.
o Verifies the pushbutton light is lit and no others are lit.
o Places and holds the ROD CONTROL switch to ROD IN o Releases the switch when the control rod indicates 00 Withdraws control rod 22-11 from 00 - 12 continuous c Selects the control rod by depressing the corresponding pushbutton on the CONTROL ROD SELECT matrix.
o Verifies the pushbutton light is lit and no others are lit.
o Places the ROD CONTROL switch to ROD OUT NOTCH and simultaneously places the NOTCH OVERRIDE switch in
~
NRC SIM 4 Page 4 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4
~ ~~~ ~~ ~~~.~ ~- ~ - ... ~ . . .- ~-~ ~~ ~~~~ . . ...
NOTCH OVERRIDE and verifird:
1 Amber OVERRIDE light ON Green INSERT light is ON following switch movement for about 1 second 1 Rod positior-i readout momemtarily displays the next odd-numbered digit o Verifies the WITHDRAW light ON for the duration of the withdrawal and increasing rod position o Releases the switches one notch before the desired position and verifies the control rod latches in an even-numbered position o Reports the control rod will not move 0 Enters ABN-6 OR Procedure 302.2 Precautions & Limitations ABN-6 o Verifies no rod blocks o Verifies CRD DR WTR PRESS at 250 psig o Applies an insert signal for about 2 minutes by placing the ROD CONTROL switch to ROD in then to ROD OUT NOTCH o Applies alternatel,y withdraw and insert signals o Raises CRD DR WTR PRESS to 390 psig by closing the CRD DRIVE WATER PRESS CONTROL switch to close [BOOTH]
o Attempts to withdraw the control rod o Reports the control rod moves o Lowers CRD DR WTR PRESS to 250 psig and withdraws the rod continuously to position 12 Procedure 302.2 Precautions & Limitations o Raises CRD drive by throttling closed CRD DRIVE WATER PRESS CONTROL switch to obtain 50 psi increase in drive pressure and attempts to drive the control rod. If no motion, can continue to increase pressure in 50 psi increments not to exceed 390 psid. [BOOTH]
o Reports the control has moved o Lowers CRD DR WTR PRESS to 250 psig and withdraws the rod continuously to position 12 Withdraws control rod 22-1 1 from 12-24 single notch o Places the ROD CONTROL switch to ROD OUT NOTCH and verifies:
Green INSERT light ON and remains for 1 second Immediately rleleases the switch and verifies the red WITHDRAW light is ON 2 seconds after switch movement for about 1.5 seconds
. .. ~~
and
~
~~ ~~~~~~~~~ ~
the. rod latches in the next
. ~ ~ . ~ .. . ~ ~~~~~ ~ ~ ~
NRC SIM 4 Page 5 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4
- - - - - ~ ~- -
even-n umbered position Continues withdrawing to position 36 0 Withdraws control rod 22-1 1 from 24-48 continuous
. Performed as before Performs coupling check at position 48 Withdraws control rod 22-15 from 00-12 continuous 0 Reports rod movements complete -
- - - ~ -~
Booth DELETE the stuck rod when drive pressure IS raised.
~
I - - -
~
I
- I_-- - ___ . - - ~~ __ ~ __-_ ~____ _- -
Terminus : Control rods are moved IAW the reactivity maneuver form.
NRC SIM 4 Page 6 of 26
1 Op-Test No.: s 2 0 0 8 Scenario No.: NRC SIM4 Event No.: 2 Event
Description:
Isolation Condenser surveillance results in inoperability of Isolation.
Condenser A Initiation: Control rods are moved IAW the reactivity maneuver form as directed by the SRO
~~ ~ ~- - ~ - ~
__ - -~ ~ ~- -~ ____ ~
Cues: As directed by the SRO Applicant's Actions or Behavior
~
0 Continue performance of surveillance 609 4.001, starting at step 6 1.9.7 Declares Isolation Condenser A inoperable when valve fails Reviews/applies Tech Specs 3.8 C o 7-day LCO with verifying motor operated isolation and condensate makeup valves in the operable IC are verified operable daily Notifies WWM/SM for investigation/repair Updates the Crew
~~ ~ ~
~ - ~
Continue performance of surveillance 609.4.001, starting at step 6.1.9.7 o Places CONDENSATE RETURN VALVE V-14-36 to CLOSE Verifies alarms C4a and C5a IS received
. Records closing time o Places CONDENSATE RETURN VALVE V-14-34 to OPEN
.. Records closing time
. Verifies alarm C1a is received Verifies ISOL COND VENTS V-14-5 and V-14-20 CLOSED o Places CONDENSATE RETURN VALVE V-14-34 to AUTO Verify alarm C1a clears o Places ISOL COND VENTS V-14-5 and V-14-20 switch to OPEN Verifies V-14-5 and V-14-20 open o Places CONDENSATE RETURN VALVE V-14-36 to AUTO
~~ ~
NRC SIM 4 Page 7 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4 I
1 .. Reports that V-14-36 will not open Directs the EO to check the breaker for the valve [ROLE PLAY] -
. - -- - - - __ - . _- ~
ATC Acts as_-_ peer checker during the surveillance
- - ~ - - ~ ~ ~ __-- -
to check the breaker for CONDENSATE RETURN PLAY i VALVE V-14-36, reports that everything looks normal.
- c - -1 - -
i Isolation condenser A is declared irioperable and TS have been applied.
NRC S I M 4 Page 8 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4 Op-Test No.: E 2 0 0 8 Scenario No.: NRC SIM4 Event No.: 3 Event
Description:
Responds to inop failure of APRM 5
_ I - - --
Initiation: Isolation condenser A is declared inoperable and TS have been applied, or as directed by the Lead Examiner Cues: Annunciator G l c , SCRAM CONTACTOR OPEN; G2d, CHANNEL II; G2f, APRM HI-HIANOP II; M scram Time ~osition 1I Applicants Actions or Behavior I I II ATc 1 --
e Responds to Annunciator G l c ,
~-
G2d, CHANNEL I I , G2f, APRM HI-HVINOP I1 SCRAM CONTACTOR OPEN;
~-
I 1 o ChecksAPRMs o Reports APRM 5 INOP o Checks APRM drawer
. mode switch position module removed a > 3 bypassed LPRMs (I Refers to procedure 403 1 Bypasses APRM 5 by placing APRM BYPASS joystich to CH 5 1 position Resets YZ scram by pressing SCRAM SYSTEM RESET 1 __ ~ ~ ~ -
~~ -
the APRM 5 can be bypassed Directs bypassing the APRM IAW 403 f .~-
Notifies WWM/SM for repaidinvestigation of APRM 5
_ ~ _ ~ -.- - - ~ - ~-
1 ~ APRM 5 has been bypassed.
- I NRC SIM 4 Page 9 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4 NRC SIM 4 Page 10 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4 Op-Test No.: E 2 0 0 8 Scenario No.: NRC SIM4 Event No.: 4 Event
Description:
Loss of USS 1A2 Initiation: APRM 5 has been bypassed, or as directed by the Lead Examiner.
- ~- - ~
Cues: Annunciators U3a, 1A2 MN BRKR TRIP; S7f, FDR TO 460V 1A2 TRIP; Y2 Scram Time Position Applicants Actions or Behavior
~ ~ ~- ~ ~~~ ~~ ~ -
0 Directs entry into ABN-45, Loss of USS 1A2 Reviews Tech Specs o 3.7.8 (AC Electrical Power)
The reactor shall be placed in cold shutdown in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> o
3.7.D.3 (Batteries)
Restore the inoperable battery to operable within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, The reactor shall be placed in cold shutdown in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> o 3.8.D (Isolation Condensers)
The reactor shall be placed in cold shutdown in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> o 3.5.A.3 (Containment)
For RBCCW valve V-5-167 Restore or isolate within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or shutdown in the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Notifies WWM/SM for repair/investigation of USS 1A2 Makes notifications folr TS required shutdown I
BOP Responds to Annunciators U3a, 1A2 MN BRKR TRIP; S7f, FDR TO 460V 1A2 TRIP Reports loss of USS 1A2 Performs ABN-45 o Starts RBCCW Purrrp 1-2 running by placing its control switch to START o Starts CRD Pump 6 running by placing its control switch to START o Confirms OW Cooling Recirculation Fans 1-4, and 1-5 running o Secures Reactor Building Ventilation I
I I
Confirms V-28-42 and V-28-42 CLOSED, RB Ventilation Isolation Inlet to Drywell 1- ~
NRC SIM 4 Page 11 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4
.. Confirms R B Ventilation Supply Fan SF-1 -14 tripped Confirm RB Exhaust Fan EF-1-6 tripped
. Position EXH VALVES TO MAIN EXHAUST switch to CLOSE
. Verify Reactor Building Exhaust Main Isolation Damper, V-28-21 closed
. Verify Reactor t3uilding Exhaust Main Isolation Damper, V-28-22 closed
. Verify RB Ventilation Supply isolation Valves o V-28-1 and V-28-2 o V-28-3 and V-28-4 o V-28-5 and V-28-6 o V-28-7 and V-28-8 o V-28-9 and V-28-10 o V-28-11 and V-28-12 o V-28-13 and V-28-14 o V-28-15 and V-28-16 o V-28-38 and V-28-39 o Starts Standby Gas Treatment System 2 Places STANDBY GAS SELECT switch in SYS 2 position Starts EF 1-9 by placing SGTS System Exhaust Fan control switch to HAND position
. Verifies o EFR 1-9 starts o V-28-27 opens o V-28-28 opens
. o V-28-30 opens After flow is established, verifies:
o V-28-28 closes
. o V-28-24 C ~ O S ~ S Places SGTS Cross-Tie Valve, V-28-48 switch to CLOSE o Re-energizes Protection System Panel 1 [ROLE PLAY]
Directs the EO to perform the following o Confirm disconnect switch SW-733-169 is off and Kirk Key removed o Confirm Kirk Key inserted and disconnect switch SW-733-170 is on o Confirm EPA breaker 5 and 6 closed Verifies TRANSFORMER OUTPUT green OFF light is lit
~
~- ~ . __ ~
NRC SIM 4 Page 12 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4 above RPS? POWER SELECT switch (Panel 6R)
Places RPSl POWER SELECT switch to TRANS position Verifies TRANSFORMER OUTPUT red ON light is lit above RPSl POWER SELECT switch Resets YZ scrani by pressing SCRAM SYSTEM RESET pushbutton Resets main steam isolation by pressing MAIN STEAM ISOLATION RESET pushbutton APRM lights APRM flow converters Main Steam Line Radiation Monitors Verifies FCTR card status IS green and curve selected to 0 Verifies annunciator 9XF3a is clear Verifies auto restart of DCC-Y computer (NOT modeled)
Confirms VLDP-1 transferred to VMCC 182 by verifying annunciator 9XF1 c is received Informs the SRO of Tech Specs 3.7 for inoperable valves V-14-33 and V-14-35 (Isolation Cooling B steam inlet and condensate return)
Informs SRO to declare C Battery inoperable Monitors
~- ~
DC Bus C voltage
~ ~ - _ _ - -~ ~
~ ~ ~- - -~ -
May start CRD Pump 8 running by placing its control switch to START Directs EO to investigate USS 1A2 and its feeder breaker Makes announcement of loss of bus, YZ scram
-~ ~ ~ -~ - - . - - ~~- ~~~
To re-energizes Protection System Panel 1 from USS 182:
to open disconnect switch SW-1'33-169, insert LOA-EDS133 to OPEN to close disconnect switch SW-733-170, insert LOA-EDS133 to 182 to close EPA 5 and 6 breakers, insert LOA-RPS007 When performed, notify the control room: Transformer PS-1 is lined-up to the Bus USS 182.
If the SRO orders a reactor shutdown started with the loss of USS 1A2,call him as the SM and tell him to leave the plant at its present power to give electrical maintenance a chance to correct the problem.
- - ~- ~ ~- ~ -~ - ~~
NRC SIM 4 Page 13 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4
' ABN-45 has been performed and the SRO has addresses Technical 1 -
Specifications.
NRC S I M 4 Page 14 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4 Op-Test No.: E 2 0 0 8 Scenario No.: NRC SIM4 Event No.: 5 Event
Description:
Responds to oscillatinq Reactor Recirculation Pump 3 Initiation: ABN-45 has been performed and the SRO has addresses Technical Specifications, or as directed by the Lead Examiner.
- ~
Cues: Oscillations in reactor power and reactor pressure; Possibly annunciator H7a, ROD BLOCK; Indications of oscillations at recirculation Pump A Time 1 Position Applicants Actions or Behavior
- -~ - - ~ - ~~ - ~ ~-
t - BOP Reports oscillations in reactor Recirculation Pump B Performs ABN-2 0 Places Recirculation Pump B in manual by pressing the AUTO/MAN button on the Recirculation Pump A MG-SET SPEED CONTROLLER 0 Attempts to manually control by rotating the manual knob on the MG-SET SPEED CONTROLLER 0 Reports that control has not been regained 0 Verifies power fluctuations > 5% peak to peak or > 30 MWe and trips the pump by placing the Recirculation Pump B DRIVE MOTOR switch to STOP 0 Verifies the Recirculation Pump B DISCH BYPASS valve open 0 Closes the discharge valve for Recirculation Pump B by placing DISCHAHGE V-37-21 switch to CLOSE 0 Verifies operating point on Power Operation Curve 0 Informs SRO of Tech Specs 3 3.F, and 3.10.A
- _ ~ - - ~ - ~~ ~
- ~ ~-~ _ ~~~ ~ -
Directs entry into ABN-2, Recirculation System Failures Reviews Tech Specs 3.3.F, and 3.10.A (no actions)
Notifies WWM/SM for repairiinvestigation of Recirculation Pump B event NRC SIM 4 Page 15 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4 I ~ Specs. I NRC S I M 4 Page 16 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4 BOP Responds to annunciator Q3b, VIBRATION HI o Reports bearings 9 and 10 are at 10.3 and 10.5 mils o Reports RAP direction to reduce reactor power to minimize vibrations o Reports 15 minute time limitation on vibrations o Monitors main turbine vibrations l SRO Directs ATC to reduce reactor power with recirculation flow LI -0 Notifies WWM/SM to investigate turbine vibrations 1
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Terminus Reactor power has been reduced with recirculation flow NRC SIM 4 Page 17 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4 Op-Test No.: a 2 0 0 8 Scenario No.: NRC SIM4 Event No.: 1 Event
Description:
Loss of Coolant in the Priinarv Containment with Loss of Offsite Power (after the scram)
Initiation: Reactor power has been reduced with recirculation flow, or as directed by the Lead Examiner.
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Cues: Rising Drywell pressure; annunciator C3f, DRYWELL PRESS HVLO; C3h, DW SUMP HI LEAWPWR FAIL Time Position I A pp Iicant s Act ions o r Behav io r
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ATC Reports Drywell pressure rising I Scrams reactor when directed
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o Depresses MANUAL SCRAM BUS 1 and BUS 2 o Places the REACTOR MODE SELECTOR switch in SHUTDOWN l
o Inserts SRMs, IRMs o Reports all control rods in l Reports loss of offsite power l Performs Suppclrt Procedure 3 l
o Starts the standby CRD Pump by placing its control switch to start l o Directs the EO to close the CRD Charging Header I Supply valve V-15-52, to open CRD Bypass Isolation Valve V-15-237, and to throttle with CRD Bypass Valve V-15-30 [ROLE PLAY]
Bypasses ADS by placing ADS TIMER switches in BYPASS Performs Support Procedure 9 I o Verifies Coro Spray suction valves open I
o Confirms Core Spray Test Flow Return Valves V-20-27, V-20-26 closed I
1 o Attempts to start Core Spray Pumps in each system and reports no Core Spray pumps will start Performs Support Procedure 5 1I o Overrides Core Spray logic by pressing OVERRIDE switches for those lit
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NRC SIM 4 Page 18 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4
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o Presses all ACTUATED switches o Confirms Core Spray System 1 (but could be System 2) l is not available 1 o Confirms Condensate Transfer is not being injected via Core Spray I o Confirms Core Spray System 1 Booster Pumps and Main Pumps o Places Core Spray System 1 Main Pumps in pull to lock o Directs EO to close Tell-Tale Drain, V-20-91 [ROLE
~ PLAY11 1 o Confirms all available Diesel Fire Pumps (if not running)
I I by placing their control switches to MAN position I o Directs EO cpen Fire Water Supply Valve V-20-83
[ROLE PLAYS]
o Confirms open Core Spray System 1 Discharge Valve V-20-12 l
o Confirms closed open Core Spray System 1 Test Flow I Return Valve V-20-27 o Closes Core Spray System 1 suction valves V-20-32 and V-20-3 with their common control switch to CLOSE (only
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1 valve has electrical power) 1 o May request EO to close V-20-3 [ROLE PLAY41 o When RPV pressure is less than 310 psig and directed I by the SRO,opens either Core Spray System 1 Parallel I Isolation Valves by taking the control switch to OPEN o Reports Fire Water injecting into the RPV
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Directs manual scram prior to automatic scram setpoint (2.9 PSQ)
Enters RPV Control EOP and Primary Containment Control EOP on high Drywell pressure and RPV water level RPV Control o Directs RPV water level band 138-175 with Support Procedure 2 and 3 0 Directs RPV pressure band 8000-1000 with TBV o Following LOOP and lowering RPV water level lowering
.. Directs Support Procedure 3 Directs AL)S bypassed ccln- f&)
Confirms initiation of Isolation Condensers Confirms Core Spray running IAW Support NRC SIM 4 Page 19 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4
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ROLE 1. As the EO,when asked to close Tell-Tale Drain, V-20-91, report it is PLAY closed (to Core Spray System 1)
- 2. As the EO,when asked open Fire Water Supply Valve V-20-83, insert LOA-CSS029 to 1. (to Core Spray System 1)
- 3. As the EO, when asked to close Core Spray System 1 suction valve V-20-3, insert LOA-CSS003 to 0.
- 4. As the EO, when asked to close Tell-Tale Drain, V-20-90, report it is closed. (to Core Spray System 2)
- 5. As the EO, when asked open Fire Water Supply Valve V-20-82, insert LOA-CSS028 to 1. (to Core Spray System 2)
- 6. To perform Support Procedure 2, as the EO directed to close the CRD Charging Header Supply valve V-15-52 and to open CRD Bypass Isolation Valve V-15-237, insert LOA-CRD024 to 0 (close V-15-52) and LOA-CRD052 to 1 (open V-15-237) and open V-15-30 LOA-CRD51 to 1 (open)
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Te rminus : The RPV has been Emergency Depressurized or RPV pressure has been lowered to allow low pressure systems to inject into the RV and Fire Water is injecting.
NRC SIM 4 Page 21 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4 SIMULATOR SETUP
- 1. Reset to full power IC-65
- 2. Insert control rod 22-1 1 from position 48 to position 00.
- 3. Reduce reactor power to about 95% with recirculation flow.
- 5. Place RWM in bypass and hang tag.
- 6. Hang tag on Dilution Pump 2 and place in PTL
- 7. Place EDG 1 in Local Stop: Insert LOA-DGN003 to STOP. This will activate annunciator RAP-T5b (EDGl NOT IN AUTO).
- 8. Ensure a newly dated 403 is in the Procedure 403 book.
- 9. Verify RBCCW Pump 1-1 in service.
- 10. Have a completed 609.4.001 complete up to step 6.1.9.8.
- 11. Verify SGTS Selected to System 1.
- 12. Have stopwatch available.
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1 ~ - - __ - - - -- - - - -- --- .
i :
1 Event Trigger Malfunction
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I I
1 j PRESET - MAL-CRD007-2211 I
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1 This will stick control rod 22-1 1 at I
I ~ position 00.
1 I
I DELETE this malfunction when CRD 1 drive pressure is raised to 390 psid I 2 ~ EVENT I1 On -Event Trigger: Trigger 1 I hwx0lol34R.eq.O
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VLV-ICSOO6 to MECH SIEZE on Trigger 1 When the red light for V-14-31 turns off, I this will stick V-14-31 in its current position (closed)
NRC SIM 4 Page 22 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4
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MAL-NIS021E
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3 T2 --+ 1 This inserts an INOP failure of APRM 5 1
~ _ ._ ~ ~- ~- ~~ _ ~ _ I 4 T3 --f MA L-EDS003B This results in the loss of USS 1A2 Bus
~ _ - ~ ~ -~ ~ -1 5 STL-RFC002 to OFF This keeps the Recirculation Pump B AIR FAIL light off T4 --t LOA-RFC002 to TRUE This places the Recirculation Pump B MG scoop tube in local manual control INSERT --f LOA-RFC007 to 0.50 LOA-RFC007 to 0.40 LOA-RFC007 to 0.50 LOA-RFC007 to 0.40 LOA-RFC007 to 0.50 Oscillate between 0.4 and 0.5 about every 3-5 seconds until the pump is manually tripped This will cause oscillations on Recirculation Pump B greater than 5%
peak-peak APRMs 6 T5 --+ ICH-TSIO17A to 10.3 ICH-TSIO18A to 10.5 This causes high vibrations on turbine bearings #9 and #10 INSERT --f WHEN power has been reduced by
> 5%, then ramp the two bearings to 5.5 and 5.9 mils over 2 minutes I
7 T6 f MAL-NSS005B to 0.1YOover 10 minutes 1 This inserts a small recirculation line I break to initiate the event
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NRC SIM 4 Page 23 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4 I
EVENT Insert EVENT TRIGGER 7:
TRIGGER - 4 I hwx03i254b.gt.O to trigger 7 MAL-NSS005A to 3% over 20 minutes MAL -OED003 with a 3 minute time delay '
This starts a larger recirculation line I break inside the PC and a loss of offsite power with a 3 minute delay from the ~
manual scram button (RPS2)
PRESETS -+
BKR-CSS003 to MECH SIEZE (NZO1A) I BKR1-CSS004to MECH SlEZE (NZO1B) I BKR-CSS005 to MECH SIEZE (NZOlC)
BKH-CSSOOG to MECH SIEZE (NZO1D)
This prevents all Core Spray Main Pump breakers from closing
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8 T8 -+ LOA-CSS029 to 1 This opens fire protection valve V-20-83 to Core Spray System 1 I
T9 ->
LOA-CSS028 to 1 I This opens fire protection valve V-20-82 ~
to Core Spray System 2 I INSERT ->
LOA-CSS003 to 0 This closes Core Spray System 1 suction valve V-20-3 (to Pump A)
L o P ~ - c s s o 2 1to 0 This closes Core Spray System 2 suction valve V-20-33 (to Pump D)
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NRC SIM 4 Page 24 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4 Procedures
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Event Nurnberhevision Title 1 ABN-6 -
Control Rod Malfunctions 1
1 p -
1 302.2 Control Rod Drive- -
Manual Control System 2 1-Handout 609.4.001 Isolation Condenser Valve Operability and Insewice test
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I--I RAP-GlC - P SCRAM CONTACTOR OPEN
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CHANNEL II p - _. - - --- - __
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APRM til-HVINOP 3 ~ - 1403
-- LPRM APRM System 4 ~ RAP-u3a --
12 MN BRKR -
TRIP - - - -
NRC SIM 4 Page 25 of 26
OC ILT 07-1 NRC Exam Scenario NRC SIM 4 Shift Turnover Initial Conditions:
- 1. The plant is at 92% power. Reactor power is limited to ~ 9 8 % due to turbine control fluctuations at 298%.
2 . The following equipment is out of service:
- a. EDG 1 is out of service to replace a fuel pump
- b. RWCU Pump B is out of service for repair
- c. Dilution Pump 2 is out of service for maintenance.
- d. The RWM is out of service due to a fault, and is bypassed.
- 3. Procedure 609.4.001 , Isolation Condenser Valve Operability and In Service Test, is in progress and is completed up to and including step 6.1.9.6. Remote position verification is not required for this test. The test was halted by RP to allow emergenl work on RB 75. This work will completed soon and will notify the US.
- 4. Control rod 22-11 had the scram valve diaphragm replaced and has been declared operable. It is currently at position 00 and needs to be withdrawn back to its normal position, 48. This activity may take place while RP has a hold on the surveillance test.
NRC SIM 4 Page 26 of 26