ML022760002
| ML022760002 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/03/2002 |
| From: | Grobe J Division of Reactor Safety III |
| To: | Skolds J Exelon Nuclear |
| References | |
| 50-237/02-301, 50-249/02-301 50-237/02-301, 50-249/02-301 | |
| Download: ML022760002 (52) | |
Text
FINAL AS-ADMINISTERED SCENARIOS FOR THE DRESDEN INITIAL EXAMINATION - JUNE 2002 MLD224*5 7
Dresden GeneratingStation SIMULATOR EXERCISE GUIDE ILT 01-1 NRC EXAM SCENARIO ILT-N-1 Rev. 01 05/02 DEVELOPED BY:
Exam Author Date APPROVED BY:
Facility Representative Date Master Copy SimScenario-ILT-N-l.doc
Appendix D Scenario Outline Form ES-D-1 Facility: Dresden Scenario No: ILT-N-1 Op-Test No: ILT 01-1 Examiners: Operators:
Initial Conditions: -33% reactor power; IRM channel 16 out of service; 2B EHC Pump OOS; Unit 3 is in Mode 4.
Turnover: Unit startup in progress; raise recirc flow, then transfer FWLC to 3-element control.
Event Malf. Event Event No. No. Type* Description 1 N/A R NSO raise reactor power recirculation flow SRO NSO 2 N/A N SO SRO transfer FWLC to 3-element control ANSO 3 EHD626 I SRO spurious opening of main turbine bypass valve 4 NIA5POT I NSO ARPM channel 5 fails downscale 5 NII15POT C NSO ARPM channel 5 companion IRM 15 spike upscale B15 SRO causing partial half-scram 6 K49 C ANSO main feed breaker to Bus 23-1 trips with failure of T12 SRO emergency diesel generator to start automatically B1 2 W
B1ALL AW4 failure of RPS to deenergize and ARI to initiate M
8 H31, H32, ANSO H33, H44 SRO trip of all reactor feed pumps tN)orrnal, 1.)eactivity, tl)nstrument, tu,)omponent, kivi)alor Page 2 of 12 NUREG-1021, Revision 8, Supplement 1
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-1 Event No.: 1 Page 1 of 1 Event
Description:
The team raises power using recirculation flow.
( Time Position Applicant's Actions or Behavior NSO Performs the following actions per DGP 01-01, Unit Startup, and DOP 0202 03, Reactor Recirculation Flow Control System Operation:
Raises recirculation pump speed using the master controller potentiometer.
Verifies expected power increase.
SRO Directs raising reactor power per DGP 01-01, Unit Startup, and DOP 0202 03, Reactor Recirculation Flow Control System Operation, by raising recirculation pump speed.
ANSO Monitors panels and assists as directed.
ILT 01-1 NRC EXAM, Scenario ILT-N-1 Page 3 of 12 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-1 Event No.: 2 Page 1 of 1 Event
Description:
The crew transfers Feedwater Level Control System to 3-Element control.
Time Position Applicant's Actions or Behavior NSO Performs the following actions per DOP 0600-06, Feedwater Regulating Valve (FRV) Operation:
Verifies the AUTO Control mode pushbutton is not amber.
Verifies that annunciator 902-5 G-8, 1-Element FW Control Active at Hi Flow, is in alarm.
Verifies that FWLCS is in Master Auto.
Depresses AUTO pushbutton and verifies that the AUTO and 3-ELEM white indicating lights are lit and the 1-ELEM light goes out.
SRO Directs transferring FWLC to 3-Element Control per DOP 0600-06,:
Feedwater Regulating Valve (FRV) Operation.
Note: RPV level may take a couple of inch swing during the transfer to 3-Element Control, so the NSO may take Manual Control of the FRV. If the crew requests Instrument Maintenance (IMD) assistance to check out FWLC, tell the crew that you are time compressing and that IMD reports the FWLC system is functioning niormally. The crew should then transfer FWLC back to AUTO Mode.
ANSO Monitors panels and assists as directed.
ILT 01-1 NRC EXAM, Scenario ILT-N-1 Page 4 of 12 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-1 Event No.: 3 Page 1 of 1 Event
Description:
The main turbine bypass valve #1 opens spuriously. The valve is closed when the ANSO takes manual action at the EHC control panel Time I Position ANSO Performs the following actions per DAN 902-7 G-3, Turb Byp Vlv Open, and/or DOA 5650-03, Turbine Control Valve or Bypass Valve Failed Open, as directed:
0l Verifies reactor pressure stable El Verifies bypass valve should be closed El Closes the bypass valve with the bypass valve jack.
NSO Acknowledges and announces alarm 902-5 C-8, Main Stm-Turbine Stm 10%
Mismatch. He should recognize it alarmed due to the bypass valve opening.
SRO Enters and directs performance of DOA 5650-03, Turbine Control Valve or Bypass Valve Failed Open.
El Places startup on hold.
El Notifies Shift Manager.
May refer to the site technical requirements and determine:
ITS 3.3.1.1 is not applicable.
ITS 3.3.6.1 is not applicable.
ITS 3.7.7 is not applicable.
ILT 01-1 NRC EXAM, Scenario ILT-N-1 P Page 5 of 12 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-1 Event No.: 4&5 Page 1 of 1 Event
Description:
APRM channel 5 fails downscale. IRM 15 spikes upscale and a partial half-scram occurs. The NSO inserts a complete half-scram. The SRO addresses the technical specification requirements for the ARPM channel. The APRM channel is bypassed but the half-scram should not be reset by the NSO.
Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR: .......
At the discretioni of the NRC chief examiner, activate trigger 3, which fails APRM 5 downscaand5seconds later spikes IRM 15 upscale.
NOTE: trigger 4 activates on the half scram signal to remove IRM 15 upscale so it appears to be a spike.
NOTE: If the teamn attempts to reset the half scram, trigger 5 will activate to~
fail the fuses for scrarn groups B2 and B3.
NSO Performs the following actions per DOA 0500-02, Partial 1/2 or Full Scram Actuation:
Recognizes and announces partial half scram.
Manually scrams RPS channel B. (immediate action)
Determines all channel B scram solenoid lights are off.
SRO Enters and directs performance of DOA 0500-02, Partial 1/2 or Full Scram Actuation.
NSO Performs the following actions per DAN 902-5 C-6, APRM Downscale, as directed:
Compares to other APRMs.
Notifies SRO Bypasses APRM channel 5.
ANSO Performs the following actions per DAN 902-5 C-6, APRM Downscale, as directed:
Checks APRM parameters on 902-37 panel.
SRO References plant Technical documents:
Li ITS Table 3.3.1.1.A-1, verifies sufficient RPS APRM trip channels (2 available / 2 required for B channel)
Li TRM Table T3.3.a-1, verifies sufficient APRM rod block channels available (5 available / 4 required)
Directs bypassing APRM 5.
Notifies the Shift Manager and IMD.
Events 4 & 5 Completion Criteria:
- RPS cha*nel B manually scrammed.
- APRM 5 bypassed.
- AND, at the direction of the NRC chief examiner.
ILT 01-1 NRC EXAM, Scenario ILT-N-1 Page 6 of 12 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-1 Event No.: 6 Page 1 of 2 Event
Description:
The main feed breaker to Bus 23-1 then trips and the 2/3 EDG fails to automatically start. The 2/3 EDG does run when manually started by the ANSO and power is restored to Bus 23-1.
Time Position Applicant's Actions or Behavior SIMULATOR .OPERATOR:
At the discretion of the NRC chief examiner, activate trigger 6, which inserts failure of RPS to deenergize, pulls ARI fuses, andf main feed breaker to MOO 23-1 trip with failure of 2/3 EDG to start auto~matically ANSO Diagnoses that Bus 23-1 has lost power and that the 2/3 EDG failed to auto start to pick up the bus Should perform the following actions of DGA 12, Partial or Complete Loss of AC Power, and DOA 6600-01, Diesel Generator Failure:
Places the 2/3 EDG control switch to start.
Dispatches an operator to the 2/3 EDG with Attachment A.
Verifies power restored to Bus 23-1 and Bus 28.
Resets annunciators and verifies the ones remaining are expected.
Dispatches an operator to check the U2 EDG trouble alarm May perform the following actions of DOA 6500-10, 4KV Circuit Breaker Trip if time permits:
Dispatches NLO to check for signs of fault or overload.
Verifies no other reason for trip.
NSO Monitors panels and assists as directed.
ILT 01-1 NRC EXAM, Scenario ILT-N-1 Page 7 of 12 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-1 Event No.: 6 Page 2 of 2 Event
Description:
The main feed breaker to Bus 23-1 then trips and the 2/3 EDG fails to automatically start. The 2/3 EDG does run when manually started by the ANSO and power is restored to Bus 23-1.
Time Position I Applicant's Actions or Behavior I
SRO Enters and directs actions for the following as time permits:
DGA 12, Partial or Complete Loss of AC Power.
DOA 6600-01, Diesel Generator Failure.
DOA 0500-05, Loss of Reactor Protection System Bus.
DOA 6500-01, 4KV Bus Failure.
DOA 6500-10, 4KV Circuit Breaker Trip.
The major actions to direct are:
Starting the 2/3 EDG Verifying major loads reenergize.
SRO Notifies Shift Manager and EMD.
ILT 01-1 NRC EXAM, Scenario ILT-N-1 Page 8 of 12 Rev. 01 (05/02)
Op-Test No: ILT 01 -1 Scenario No.: ILT-N-1 Event No.: 7 &8 Page 1_ of 4 Event
Description:
A spurious RPS Channel A scram begins an ATWS condition. The team should perform the ATWS DEOP and insert the control rods. The RFPs trip and the crew should use HPCI for RPV level control.
Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR:
At the discretion of the NRC chief examiner, activate trigger 7, which causes a spurious RPS channel A half scam and trips the RFPs.
NSO Performs the following actions per DGP 02-03, Reactor Scram:
Presses scram pushbuttons Places mode switch in shutdown Check rods inserted; discovers rods not inserted.
Initiates ARI, checks rods, announces ATWS condition.
Performs the following actions per DGP 02-03, Reactor Scram:
Verifies turbine and generator tripped (only if Group 1 has occurred or reactor power has dropped low enough that this should occur)
Inserts SRM/IRMs NSO Performs DEOP 400-5, Failure to Scram, actions as directed:
ANSO Places ADS to inhibit Places both CS pumps in PTL Power Leg Inserts IRMs & SRMs
- /Performs Alternate Rod Insertion. (see specific actions below)
"I May Inject SBLC.
Level Leq Rx Power >6% Rx Power *6%
J Terminates and Prevents Maintains level between -164 injection except boron and and 48 in.
CRD until RPV/L is < -35 in.
J Maintains RPV/L between -164 in. and the level lowered to.
Pressure Leg Verifies turbine/bypass valves maintaining RPV/P <1060 psig.
If MSIVs isolate, maintains <1060 psig using IC, ADSVs and /or HPCI.
SIMULATOR OPERATOR / ROLE PLAY:
Operator to jumper the MSIV Groupl -59 in. and offgas hi hi radiation isolations (wait 5 min):
Activate trigger 8 Ojumpers the MSIV Groupi -59 in. and offgas hi hi radiation isolations) and report "the MSIV Group-i -59 in. and offqas hi hi radiation ILT 01-1 NRC EXAM, Scenario ILT-N-1 Page 9 of 12 Rev. 01 (05/02)
Op-Test No: ILT 01-1 Scenario No.: ILT-N-1 Event No.: 7 &8 Page 2 of 4 Event
Description:
A spurious RPS Channel A scram begins an ATWS condition. The team should perform the ATWS DEOP and insert the control rods. The RFPs trip and the crew should use HPCI for RPV level control.
Time ] Position Applicant's Actions or Behavior SRO Enters and directs performance of DGP 02-03, Reactor Scram, and DEOP 100, RPV Control.
Due to report of ATWS condition, exits DEOP 100 and enters and directs performance of DEOP 400-05, Failure to Scram.
Placing ADS to inhibit Placing both CS pumps in PTL Power Leg I Directs any of the following control rod insertion methods (first two most preferred) per DEOP 500-05, Alternate Insertion of Control Rods:
"* step G.2: pulling scram channel A solenoid power supply fuses.
"* step G.4: venting the scram air header.
"* step G.5: using the scram test switches.
"* step G.6: manually driving of withdrawn control rods.
4 May direct Injecting SBLC Level Leq Verification water level instruments are accurate Verification any required automatic actions have occurred Directing jumpers installed for MSIV low level and Off Gas high Rad isolations Rx Power >6% Rx Power *6%
'1Terminating and Maintaining level between Preventing injection -164 and 48 in.
except boron and CRD until RPV/L is _<-35 in.
4 Maintaining RPV/L between -164 in. and the level lowered to.
Pressure Leg Maintaining <1060 psig using turbine/bypass valves.
If MSIVs isolate, maintaining <1060 psig using IC, ADSVs or HPCI.
ILT 01-1 NRC EXAM, Scenario ILT-N-1 Pagel10of 12 Rev. 01 (05/02)
Op-Test No: ILT 0 1- 1 Scenario No.: ILT-N-1 Event No.: 7 &8 Page _3 of 4 Event
Description:
A spurious RPS Channel A scram begins an ATWS condition. The team should perform the ATWS DEOP and insert the control rods. The RFPs trip and the crew should use HPCI for RPV level control.
Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR I ROLE PLAY:
Note: For the first two requested actions below, wait about 10 minutes and /
or at the discretion of the NRC chief examiner
- 1. Operator to pull scram channel A solenoid power supply fuses:
"Activatetrigger 10 (pulls Channel A RPS fuses and trips reactor feed pumps) and then after the fuses are all pulled report "the scram channel A solenoid power supply fuses are pulled".
- 2. Operator to vent the scram air header:
Activate trigger 11 (vents the scram air header) and report "I have vented the scram air header".
- 3. Operator to use the individual scram test switches (wait 2 min):
Go to Instructor Station screen RODS and begin simulating flipping the scram test switches. Follow the guidance in DEOP 500-05 for selecting rods.
NSO If directed, attempts to drive withdrawn control rods in per step G.6 of DEOP 500-05, Alternate Insertion of Control Rods:
May close CRD 25 charging water valve.
May start a second CRD pump.
May maximize drive water pressure using the CRD 8 valve Bypasses the RWM.
Applies an insert signal to insert rods in the following order:
"* intermediate 16-32
"* deep 4-14
"* shallow 34-48 SIMULATOR OPERATOR / ROLE PLAY:
NLO to close CRD 25 valve (wait 3 min):
Activate trigger 9 (closes the CRD 25 valve) and report "the ORD 25 valve is closed".
NSO Reports that all rods are inserted.
ANSO Restores RPV level to +8 to +48 inches as directed.
Begins cooldown as directed.
SRO When receives report that all rods are inserted, exits DEOP 400-05, Failure to Scram and enters DEOP 100 and directs:
Controlling RPV water level between +8 to +48 inches.
May direct depressurizing the RPV at <100 'F/hr.
ILT 01-1 NRC EXAM, Scenario ILT-N-1 Page 11 of 12 Rev. 01 (05/02)
Op-Test No: ILT 01 -1 Scenario No.: ILT-N-1 Event No.: 7 &8 Page 4 of 4 Event
Description:
A spurious RPS Channel A scram begins an ATWS condition. The team should perform the ATWS DEOP and insert the control rods. The RFPs trip and the crew I _______ --..
should u.se HPC.I for RPV level r-nntrnl
-.-..... .... . . ,, . ,. v l*vJl e Time Position Applicant's Actions or Behavior Critical Tasks: (identified by 4 in guide)
With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron and/or inserting control rods, to prevent exceeding the primary containment design limits.
During an ATWS with conditions met to perform power/level control TERMINATE AND PREVENT INJECTION, with exception of boron and CRD, into the RPV until conditions are met to re-establish injection. (May not apply if power becomes <6% before the step requiring this action is reached)
When conditions are met to establish injection use available injection systems to MAINTAIN RPV water level above -164".
Scenario Completion Criteria:
- Control rods inserted.
- Plant stabilized.
- AND, at the direction of the NRC chief examiner.
ILT 01-1 NRC EXAM, Scenario ILT-N-1 Page 12 of 12 Rev. 01 (05/02)
Dresden GeneratingStation SIMULATOR EXERCISE GUIDE ILT 01-1 NRC EXAM SCENARIO ILT-N-2 Rev. 01 05/02 DEVELOPED BY:
Exam Author Date APPROVED BY:
Facility Representative Date Master Copy SimScenario-ILT-N-2.doc
Appendix D Scenario Outline Form ES-D-1 Facility: Dresden Scenario No: ILT-N-2 Op-Test No: ILT 01-1 Examiners: Operators:
Initial Conditions: Unit in Mode 2 at approximately 2% reactor power; IRM channel 16 out of service; 2B EHC Pump OOS; Unit 3 is in Mode 4.
Turnover: Unit startup in progress; return TBCCW pump 2B to service following maintenance, then continue power ascension Event Malf. Event Event No. No. Type* Description ANSO 1 N/A N SRO swap TBCCW pumps NSO 2 N/A R SRO raise reactor power by withdrawing control rods NSO 3 RODC13DO C SRO control rod double notches during withdrawal NSO 4 NII12POT SRO IRM channel fails upscale 5
PCPDWTOR ANSO SRO drywell to torus differential pressure controller failure ANSO 5a AT23 I SRO fails 2A Rx Bldg to Torus vacuum breaker open ANSO 6 HP8 C SRO circulating water pump trip ANSO 7 CSBRKSEV M SRO lowering torus level from ECCS suction line break ANSO 8J33 C SRO loss of EHC system
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 12 NUREG-1021, Revision 8, Supplement 1
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-2 Event No.: 1 Page 1 of 1 Event
Description:
Maintenance has been completed on TBCCW pump 2B and the SRO directs the ANSO to switch running pumps and place the TBCCW pump 2B in service.
Time Position Applicant's Actions or Behavior ANSO Performs the following actions per DOP 3800-01, Turbine Building Closed Cooling Water System(TBCCW):
Directs NLO to verify 2B TBCCW pump suction and discharge valves open.
Directs NLO to verify 2B TBCCW pump oil levels.
Starts 2B TBCCW pump and verifies proper operation.
Stops 2A TBCCW pump.
Verifies system parameters normal.
SRO Directs swapping from 2A TBCCW pump to 2B TBCCW pump per DOP 3800-01, Turbine Building Closed Cooling Water System (TBCCW).
NSO Monitors panels and assists as directed.
ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page 3 of 12 Rev. 01' (05' /02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-2 Event No.: 2 Page 1 of 1 Event
Description:
The NSO, as directed by the SRO, then continues the power ascension for unit startup by control rod withdrawal.
[Time Position I Applicant's Actions or Behavior NSO Performs the following actions per DOP 0400-01, Reactor Manual Control System Operation, and DGP 03-04, Control Rod Movements, as directed Verifies the following prior to moving any control rod:
Control rod selected on the select matrix is correct rod.
Second Verification requirements satisfied.
Rod Out Permit light is illuminated.
Drive water pressure at nominal 260 psid.
Withdraws rods as follows:
Moves Rod Out Notch Override (RONOR) Switch to NOTCH OVERRIDE position (use of RONOR switch is optional) and the Rod Movement Control switch to ROD OUT.
Verifies ON light illuminated and proper Control Rod Timer operation.
Releases switches before target position is reached.
Verifies rod settles to target position and proper response of nuclear instrumentation.
ANSO / or Performs second verification checks.
Surrogate For first rod in a step:
Verifies correct control rod pattern Verifies correct step and array.
Verifies RWM rod blocks enabled For all rods moved:
Verifies correct control rod selected.
Verifies planned control rod motion is correct.
Immediately notify the NSO of errors during rod motion.
Verifies control rod at target position.
SRO Directs pulling control rods.
Reviews REMA.
Designates second verifier.
Directs NSO to pulls rods.
ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page 4 of 12 Rev. 01" (05' /02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-2 Event No.: 3 Page 1 of 1 Event
Description:
During the control rod withdrawal, a control rod double notches beyond the withdraw limit and must be repositioned.
[Time) Position] Applicant's Actions or Behavior NSO Two possible paths can occur:
Either: Observes and announces that control rod N-1 3 has moved to position 14 (1 notch beyond its target position) and responds to alarms:
902-5 B-3, Rod Worth Min Block 902-5 C-3, Rod Out Block Should perform the following actions per DOA 0300-12, Mispositioned Control Rod:
Discontinues rod movement and notifies SRO.
Moves the mispositioned rod to its target position.
Records in DOS-0300-06, Control Rod Abnormality Record.
Or: When observes rod N-13 moving past its target position of 12, then:
Uses the Emerg Rod In position of the Rod Out Notch Override switch to move the rod back to its target position prior to it latching in to position 14.
Notifies the SRO.
Records in DOS-0300-06, Control Rod Abnormality Record.
SRO May enter and direct performance of DOA 0300-12, Mispositioned Control Rod.
Notifies the Shift Manager.
May refer to ITS 3.1.3 and determine that no actions are required.
May enter DOA 0300-05, Inoperable or Failed Control Rod Drives.
ROLE PLAY:
Respond as the Shift Manager.
QNE: If crew requests guidance from the QNE respond "I recomtend inserting rod N-13 to position 12.
ANSO Monitors panels and assists as directed.
ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page 5 of 12 Rev. 01' (05' /02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-2 Event No.: 4 Page 1 of 1 Event
Description:
IRM channel 12 then fails upscale and a half-scram occurs on the RPS "A" channel.
The NSO bypasses the failed IRM channel and the SRO addresses the technical specification requirements for the failure.
Time J Position Applicant's Actions or Behavior SIMULATR.* OPE RTOR:
At e iscretion f the NRC chief examiner, activate trigger1, fails iRM 12.
NSO Should perform the following actions per DAN 902-5 C-15:
If not in the RUN Mode, verifies the following occurred:
- Channel A half scram
- Rod Block.
Verifies IRM 12 readings against other IRMs on 902-5 panel.
Verifies IRM range switch in correct position Bypasses IRM 12 after T. S. compliance verified by SRO.
Resets RPS channel A per DOP 0500-07, Insertion/Reset of Manual Half Scram, as follows:
- Verifies half scram no longer required
- Turns the Scram Reset switch in each direction and verifies all eight white group solenoid lights are lit.
- Verifies alarm 902-5 A-1 0, Channel A Manual Trip, resets.
ANSO Should perform the following actions per DAN 902-5 C-10:
Verifies IRM 12 readings against other IRMs on 902-36 panel.
Verifies IRM 12 function switch in operate.
Verifies power supplies operating properly.
SRO Should references plant technical documents:
"* ITS Table 3.3.1.1 .A-1, verifies sufficient RPS IRM trip channels (3 available / 3 required for A channel) for Mode 2.
"* TRM Table T3.3.a-1, verifies sufficient APRM rod block channels available (7 available / 6 required) for Mode 2.
Should direct IRM 12 bypassed and the half scram reset per DOP 0500-07, Insertion/Reset of Manual Half Scram.
Notifies the Shift Manager and IMD.
ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page 6 of 12 Rev. 01' (05' /02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-2 Event No.: 5 Page 1 of 1 Event
Description:
Drywell to Torus differential pressure then begins to decrease and pressure control is regained when the ANSO takes manual control of the Drywell to Torus differential pressure controller.
Time 1 Position I Applicant's Actions or Behavior AIt thediascretion fthe NRC chie examiner, activate trigger 2, which causes drywell to torusdifferenitial pressure controle inutt faWi igh causing the demand tofailto 00,%.
ANSO Acknowledges and announces alarm 902-4 B-15, DW to Torus DP Hi/Lo, and performs the following:
Should diagnose failure of the drywell to torus differential pressure controller AUTO mode of operation.
Performs any of the following as directed:
Places the drywell to torus differential pressure controller to MAN and controls the drywell to torus differential pressure manually; AND / OR, vents the torus to Reactor Building Ventilation per DOP 1600-01, Normal Pressure Control of the Drywell or Torus:
- Verifies atmospheric sample results allow venting.
- Verifies U2 Reactor Building Ventilation operating.
- Verifies AO 2-1601-91 open.
- Opens AO 2-1601-24. (closes when desired to stop venting)
- Opens AO 2-1601-61. (closes when desired to stop venting)
May close AO 2-1601-58 per DOP 1600-05, Primary Containment Inerting and Atmosphere Control.
SRO To maintain Primary Containment pressures to those specified in DOP 1600 05, Primary Containment Inerting and Atmosphere Control, should direct performance of any of the following:
Placing the drywell torus differential pressure controller to MAN and controlling Drywell to Torus differential pressure manually; AND / OR, venting the torus to Reactor Building Ventilation per DOP 1600-01, Normal Pressure Control of the Drywell or Torus, to maintain the required differential pressure.
May direct closing AO 2-1601-58 per DOP 1600-05, Primary Containment Inerting and Atmosphere Control.
May notify IMD.
NSO Monitors panels and assists as directed.
ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page 7 of 12 Rev. 01' (05' /02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-2 Event No.: 5.a Page 1 of 1 Event
Description:
A drifting Rx Bldg to Torus differential pressure instrument will cause the 2A Rx Bldg to Torus Vacuum Breaker to fail open. The Unit Supervisor should reference the Technical Specifications.
Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR: f* -,
At the~discretion of the NRC chief examinr,&activate trigger 6, which caus~es~
2A Rx Bldg to To~rus Vacuum Breaker 6o fail open ANSO Acknowledges and announces alarms 902-3 B-14, and 902-3 C14, and performs the following:
El Evaluates Rx Bldg to Torus DP to determine if valve should have opened.
I Directs a NLO to check the AO 2-1601-20A valve.
I Notifies IMD to perform DIS 1600-3, Torus to Reactor Building Vacuum Breakers Trip Unit Calibration.
SRO References Technical Specifications and determines:
Il ITS 3.6.1.7.A, close the open vacuum breaker within 7 days.
F ITS 3.0.4, cannot change mode.
Notifies Shift Manager and IMD.
NSO Monitors panels and assists as directed.
ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page 8 of 12 Rev. 01" (05' /02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-2 Event No.: 6 Page 1 of 1 Event
Description:
Circulating water pump 2C then trips on overload and the ANSO manually starts circulating water pump 2A to maintain condenser vacuum.
Time Position Applicant's Actions or Behavior SIMUATOR OPERATOR:.
At the discretion of the RO chief exam*ner, activate trigger , which trips C Circulating Water ptip. ~7~
ANSO Performs the following actions per DAN 902-7 A-15, Circ Wtr PP Trip, DOA 4400-01, Circulating Water System Failure, and DOA 6500-10, 4KV Circuit Breaker Trip, as directed:
Starts 2B Circulating Water pump. (immediate action)
Verifies condenser vacuum returning to normal.
Verifies 2C Circulating Water pump discharge valve closes.
Sends NLO to check 2C Circulating Water pump breaker and operation of 2B Circulating Water pump.
Places 2C Circulating Water pump control switch in PTL.
Verifies Circulating Water Flow reversal valves lined up normally.
May send NLO to check cribhouse bar racks and traveling screens.
SRO Enters and directs performance of DOA 4400-01, Circulating Water System Failure, and DOA 6500-10, 4KV Circuit Breaker Trip.
Notifies the Shift Manager and EMD.
NSO Monitors panels and assists as directed.
ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page 9 of 12 Rev. 01' (05' /02)
Op-Test No: ILT 01-1 Scenario No.: ILT-N-2 Event No.: 7 & 8 Page 1 of 3 Event
Description:
An ECCS suction line break occurs resulting in a lowering torus water level. HPCI spuriously initiates. HPCI should be secured, the reactor should be scrammed and an emergency depressurization should be performed as directed by the DEOP for primary containment control.
Time Position Applicant's Actions or Behavior SIMULATOR OPERATO0 At hedisretion o the NRC clief examiner, activate trigger 4, which starts an E S suc'tion line break in the otrus basement and spuriously initiates IPC I after 5 minutes._
When th euritis rnarnually scrammedvrf trigger5 auoaial aciaes to trip 2A EPC Pump.
Note: Ittakes about 30 minutes for torus level to reach 12 feet. At the discretion of the lead NRC examiner, use the cues later in this even to jump ahead in time to expedite the level drop if desired.
ANSO Reports the following alarms:
0 902-4 C-23 Torus Narrow Range Wtr Lvl Lo
- 923-4 B-2 U2 W RBFD Sump Lvl Hi Hi Checks the torus narrow range level indicator. Reports level dropping.
Directs NLO to perform DOS 1600-02,Torus Level Verification Using Local Sight Glass.
Directs NLO to investigate leakage to torus basement.
Verifies proper operation of the RBFD Sump pumps. (will require resetting the Group 2 isolation at both the 902-5 panel and the 923-4 panel for the sump pumps to operate if a Group 2 Isolation occurs)
ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page 10 of 12 Rev. 01" (05' /02)
Op-Test No: ILT 01-1 Scenario No.: ILT-N-2 Event No.: 7 & 8 Page 2 of 3 Event
Description:
An ECCS suction line break occurs resulting in a lowering torus water level. HPCI spuriously initiates. HPCI should be secured, the reactor should be scrammed and an emergency depressurization should be performed as directed by the DEOP for primary containment control.
Time Position Applicant's Actions or Behavior ANSO Performs the following actions per DEOP 200-01, Primary Containment Control, as directed:
May attempt to add water to the torus by opening the HPCI 14 valve.
Monitors/Reports DEOP 200-01 entry parameters.
4 Prevents HPCI operation by placing the HPCI 4 valve in PTL.
ANSO Performs the following actions per DOA 0040-02, Localized Flooding in Plant, as directed:
Makes PA announcement.
Directs NLO to investigate leakage to torus basement.
Notifies Radiation Protection and Security as time permits.
Cue: (if desired for timecompression (to be handed by Lead Examiner)
When torus level is < I4.feet and/or at te discretion ofhe lead NRC examiner, cue the crei that weare taking a time jump and that both torus wide range level mete indicate 12.5 feet and are dropping at about 0.1 ft per minute.
SRO Enters and directs performance of DEOP 0200-01, Primary Containment Control:
May attempt to add water to the torus by opening the HPCI 14 valve.
May decide to anticipate RPV Blowdown:
"* directs a manual scram per DGP 02-03, Reactor Scram.
"* enters DEOP 100, RPV Control.
"* directs opening turbine bypass valves.
q Directs ANSO to secure HPCI by placing the HPCI 4 valve in PTL before torus level reaches 12 feet.
Enters DEOP 0300-01, Secondary Containment Control, and directs:
If Reactor Building Ventilation Isolates when unit is scrammed, directs restarting Reactor Building Ventilation.
ANSO Performs DEOP 300-01, Secondary Control, as directed:
Time permitting, restarts Reactor Building Ventilation (if it isolates when the reactor is scrammed).
NSO 4 Performs DGP 02-03, Reactor Scram, as directed:
Presses scram pushbuttons Places mode switch in shutdown Checks rods inserted Maintain RPV/L between +25 and +35 inches or as directed by DEOPs ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page 11 of 12 Rev. 01' (05' /02)
Op-Test No: ILT 01 -1 Scenario No.: ILT-N-2 Event No.: 7 & 8 Page 3 of 3 Event
Description:
An ECCS suction line break occurs resulting in a lowering torus water level. HPCI spuriously initiates. HPCI should be secured, the reactor should be scrammed and an emergency depressurization should be performed as directed by the DEOP for primary containment control.
Time Position Applicant's Actions or Behavior ANSO When attempts to open bypass valves (if directed), reports that the 2B EHC pump tripped.
SRO When informed that torus level is approaching 11 feet:
'I Directs a manual scram (if not already directed above) per DGP 02-03, Reactor Scram.
Enters DEOP 0400-02, Emergency Depressurization, and directs:
Initiation of Iso Condenser to maximum flow Verification that SP/L >6 feet.
ý Opening all ADS valves Verification all relief valves are open.
ANSO Performs DEOP 0400-02, Emergency Depressurization, actions as directed:
Initiates Iso Condenser to maximum flow Verifies that SP/L >6 feet.
4 Opens all ADS valves Verifies all relief valves are open.
ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page 12 of 12 Rev. 01' (05" /02)
Dresden GeneratingStation SIMULATOR EXERCISE GUIDE ILT 01-1 NRC EXAM SCENARIO ILT-N-3 Rev. 01 05/02 DEVELOPED BY:
Exam Author Date APPROVED BY:
Facility Representative Date Master Copy SimScenario-ILT-N-3.doc
Appendix D Scenario Outline Form ES-D-1 Facility: Dresden Scenario No: ILT-N-3 Op-Test No: ILT 01-1 Examiners: Operators:
Initial Conditions: Approximately 78% reactor power; IRM channel 16 out of service; 2B EHC Pump out of service; Unit 3 is in Mode 4.
Turnover: Unit shutdown in progress for forced outage; shutdown reactor condensate pump 2B, then continue power reduction for unit shutdown Event Malf. Event Event No. No. Type* Description ANSO 1 N/A N SRO shutdown condensate pump for unit shutdown NSO 2 N/A R SRO lower reactor power by reducing recirculation flow SER1375 NSO 3 FWDOP2 C SRO reactor feed pump 2B failure FWDOP5 ANSO 4 ADS3ESD I SRO spurious ADS valve opening K11 ANSO stator cooling water pump trips on overload and MGDSCBTR SRO standby pump fails to start automatically NSO 6 RLLMLS I SRO feedwater level control system setpoint drifts high 7 F44 ALL small recirculation loop break M
8 ACDTP21 ANSO TR 22 feed to Bus 21 fails to close ACDCL21 SRO HP8VBKR ANSO 9 HPLCL8 HPLCL8 NSO SRO HPCI injection valve failure
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 13 NUREG-1021, Revision 8, Supplement 1
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-3 Event No.: 1 Page 1 of 1 Event
Description:
The team continues the shut down by securing 2B Condensate Pump.
[Time I Position Applicant's Actions or Behavior SRO Directs ANSO to secure 2B Condensate Pump per DOP 3300-03, Condensate System Shutdown.
ANSO Performs the following actions per DOP 3300-03, Condensate System Shutdown, to shutdown 2B Condensate Pump as directed:
I Verifies Reactor Feed Pump Suction Pressure >230 psig.
- Verifies closed the hydrogen isolation valves. (on turnover)
[ Stops 2B Condensate Pump
[ Selects 2B Condensate Pump for standby.
Fl Directs NLO to verify Condensate Pre-filter operating parameters.
NSO Monitors panels and assists as directed.
ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 3 of 13 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-3 Event No.: 2 Page 1 of 1 Event
Description:
The team reduces power using recirculation flow.
Time Position Applicant's Actions or Behavior NSO Performs the following actions per DGP 02-01, Unit Shutdown, and DOP 0202-03, Reactor Recirculation Flow Control System Operation:
0 Lowers recirculation pump speed using the master controller potentiometer.
[I Verifies expected power reduction.
SRO Directs reducing reactor power per DGP 02-01, Unit Shutdown, and DOP 0202-03, Reactor Recirculation Flow Control System Operation, by lowering recirculation pump speed.
ANSO Monitors panels and assists as directed.
ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 4 of 13 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-3 Event No.: 3 Page 1 of 3 Event
Description:
A 2B RFP low lube oil condition will require the team to start 2C RFP and secure 2B RFP.
Time Position Applicant's Actions or Behavior SIMULATOR~ OPERATOR:
At the discretion of th eTRaqchief examineractivate trigger 1, which insets~
28 RFP low oil pressure and causes faiiiure of its auxili~ary oil pumnp to start.
NSO Performs the following actions per DAN 902-6 H-8, 2B RFP Brg Oil Press Lo:
El Attempts to start 2B RFP Auxiliary Oil Pump.
l Directs NLO to report 2B RFP oil pressure, oil reservoir level and check for oil leaks.
il Informs SRO 2B RFP is running with low oil pressure and the auxiliary oil pump will not start.
ROLE PLAY:
NLO to check 2B RFP ~(wait 2 mirm Report"2BD REP oil pressU e is 16 psig. Oil reservoir level is ow.Tee is a large amount of oil on the pump base-plFate The oil had not reached the base plate drain yet. I plugged the base plate drain "
NLO to check 2B Aux Oil pump breaker_(wait 2 min)
Report "1see no problem with 21 ~RFPAux Oil pump lbrekeC~'.
SRO Directs starting 2C RFP and securing 2B RFP.
Contacts the Shift Manager, and appropriate maintenance departments.
ANSO Monitors panels and assists as directed.
NSO Starts 2C RFP per DOP 3200-03, Startup of second Reactor Feed Pump or Shifting to Alternate Reactor Feed Pump, as directed:
1l May direct NLO to perform pre-startup checks.
1l Places RFPs Standby selector switch in OFF.
El Closes the discharge valve.
13 Opens the recirculation valve.
El Verifies RPV level stable.
r- Starts discharge valve opening.
[l Starts the RFP. (should start it on Bus 22 per procedure)
El Verifies RPV level stable.
10 Closes the recirculation valve.
El Directs NLO to perform post-startup checks.
El Verifies auxiliary oil pump stops.
ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 5 of 13 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-3 Event No.: 3 Page 2 of 3 Event
Description:
A 2B RFP low lube oil condition will require the team to start another RFP and secure 2B RFP.
Time Position Applicant's Actions or Behavior ROLE PLAY:
NLO to perform RFP pre-starup check (wait 5 m m):
Respo "Ihave completed the requested RFP startup pre-checks per step GA1 through G.1 1of DOP 20,-03".
NLOto pefrm post-startup checks: (wat 5mrin)
Respond"The 1P post-startii checks are completed per G.31 o O NSO Performs the following actions per DOP 3200-05, Reactor Feed Pump Shutdown, to shutdown 2B RFP as directed:
[ Verifies zinc injection is not lined up to 2B RFP (may not wait on this).
El Places RFPs standby selector switch to OFF.
El Opens the recirculation valve.
EI Verifies RPV level stable.
U Closes the discharge valve.
U Verifies RPV level stable.
U Stops the RFP.
I Verifies the running RFP amps below 1115 amps.
U Closes the recirculation valve.
U Has NLO verify the RFP has come to rest.
El Has NLO adjust zinc injection to -20 gpm.
El Has NLO verify 2-5772-48B closed.
ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 6 of 13 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-3 Event No.: 3 Page 3 of 3 Event
Description:
A 2B RFP low lube oil condition will require the team to start another RFP and secure 2B RFP.
Time Position Applicant's Actions or Behavior Event 3 Completion Criteria:
- 2C RFP started<
- 2B RFP shutdowni
- AND, at the direction of the NRC chief examiner.
ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 7 of 13 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-3 Event No.: 4 Page 1 of 1 Event
Description:
The E ADSV setpoint will drift low causing it to open. The team should close it by placing its control switch in OFF.
Time Position Applicant's Actions or Behavior SIMULATOR O ROR:
At the discretion of t N ce examiner, activate trige 2 which sets the E ADS valve' stpoint to 890 pig c~ausing it to open~.
ANSO Performs the following actions per DAN 902-3 E-12, 2E Electromatic Relief Vlv Open:
0I Verifies valve actually open by checking any of the following:
- Valve position indication
- Generator output decrease.
- Acoustic monitor tripped.
- Increasing tailpipe temperature.
- Torus temperature increasing 1i Notifies SRO the valve is open.
SRO Enters and directs performance of DOA 0250-01, Relief Valve Failure.
ANSO Performs DOA 0250-01, Relief Valve Failure, as directed:
Li Places the 2E Electromatic Relief valve control switch to OFF.
(immediate action)
Li Verifies RPV level stable. (immediate action)
Li Verifies and reports the valve closed.
10 Resets the acoustic monitor.
SRO References Technical Specifications and determines:
10 ITS 3.6.2.1, Suppression Pool Average Temperature, is not applicable.
Li ITS 3.5.1.G, ECCS, if decides the failure does affect its ADS function, then restore the ADS valve to OPERABLE status within 14 days, otherwise, this is not applicable.
Li ITS 3.4.3.A, Safety and Relief Valves, restore the relief valve to OPERABLE status within 14 days.
Li ITS SR 3.6.1.8.2, Suppression Chamber to Drywell Vacuum Breakers, perform a functional test of each required vacuum breaker within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 8 of 13 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-3 Event No.: 5 Page 1 of 1 Event
Description:
The 2A stator cooling water pump trips on overload and the standby pump fails to start automatically. The team should manually start the 2B stator cooling water pump.
Time Position ANSO Announces the following alarms:
- DAN 902-7 B-10, Stator CIg PP Trip
- DAN 902-7 C-3, Turb Stator Coolant Runback Performs appropriate actions per DOA 7400-01, Failure of the Stator Coolant System:
0l Starts 2B Stator Cooling Water Pump (Immediate Action)
LI Verifies Runback condition clears.
1I Sends NLO to verify 2B Stator Cooling Water Pump operating normally.
Performs appropriate actions per DOA 6700-06, 480V Circuit Breaker Trip:
1I Sends NLO to check breaker and 2A Stator Cooling Water Pump for cause of trip.
LI Places 2A Stator Cooling Water Pump control switch in PTL.
Enters and directs performance of DOA 7400-01, Failure of the Stator SRO Coolant System.
Enters and directs performance of DOA 6700-06, 480V Circuit Breaker Trip.
Notifies Work Week Manager, IMD and/or EMD NSO Monitors panels and assists as directed.
ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 9 of 13 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-3 Event No.: 6 Page 1 of 1 Event
Description:
The FWLC system setpoint will begin drifting up. The team should take manual control of the FWLC system.
[Timee Position Applicant's Actions or Behavior SIMULATOR OPERATOR At the discretion ofthe C chie examiner activate trigger 7, which causes feedwaterlevel control systemr setpontto drift high (to 60 ) over 10 mm.
If the ce sca steuibgntenxtvn.
NSO Observes and announces RPV level rising or responds to alarm 902-5 E-8, RPV Lvl Hi.
Performs the following actions per DOA 0600-01 Transient Level Control:
0I Takes manual control of the Feedwater Regulating Valves.
l0 Restores level to within band specified by the SRO SRO Enters and directs performance of DOA 0600-01 Transient Level Control.
Notifies Shift Manager and IMD.
ROLE PLAY:
Respond to calls for assistance.
If ANSO goes to heck 1 screen, prompt him that the dIS Monitor is ANSO Monitors panels and assists as directed.
Evn ompletion Criteria:
- Fed&water level control system under manual control.
- AND, at the direction' of the NRC chief examiner.
ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 10 of 13 Rev. 01 (05/02)
Op-Test No: ILT 01 -1. Scenario No.: ILT-N-3 Event No.: 7, 8 & 9 Page 1_! of 4 Event
Description:
A small recirculation loop break occurs with a loss of high pressure injection. The team should perform the RPV Control and Primary Containment Control DEOPs. Due to the loss of high pressure injection and RPV level dropping to TAF, the team should Emergency Depressurize and restore RPV level with low pressure injection systems.
Time Position i
NSO Announces Reactor Scram on high Drywell pressure.
Performs the following actions per DGP 02-03, Reactor Scram, and DEOP 100, RPV Control, as directed:
LI Places Mode Switch to Shutdown and depresses the Scram pushbuttons.
0 Checks rods inserted.
LI Maintains RPV level as directed by SRO.
0 Checks turbine and generator tripped.
0I Checks recirc pumps run back to minimum speed.
0I Inserts SRMs and IRMs ANSO Should inform the SRO that High Pressure Feedwater and HPCI are not available.
SRO Enters DEOP 100, RPV Control, due to high PC/P and/or low RPV/L and performs/directs:
1I Entering DGP 2-3 10 Verification of water level instrument accuracy
[l Verification of all isolations, ECCS and EDGs starts 0 Holding RPV/L +8 to +48 inches El Maintaining RPV/P <1060 psig When informed no high pressure feed is available other than CRD, then directs:
El Inhibiting ADS before -59 inches.
L1 Initiating the isolation condenser 0I Directing use of hiah pressure Alternate Iniection systems. (SBLC and CRD Crosstie)
[I Verifies at least two low pressure injection systems available.
Waits until RPV level drops to TAF.
LI Verifies any low pressure system lined up with a pump running ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 11 of 13 Rev. 01 (05/02)
Op-Test No: ILT 01 -1 Scenario No.: ILT-N-3 Event No.: 7,8&9 Page 2 of 4 Event
Description:
A small recirculation loop break occurs with a loss of high pressure injection. The team should perform the RPV Control and Primary Containment Control DEOPs. Due to the loss of high pressure injection and RPV level dropping to TAF, the team should Emergency Depressurize and restore RPV level with low pressure injection systems.
Time Position Applicant's Actions or Behavior SIMULT~ZOR OPEATOR / OLE PLAY:
NLOtolinupmakupto--L Boron tank (wait 5 mmn):
Verify trigger 11 is activated then report makeup is lined up to SB C Boron tank".~
SRO Before RPV level reaches -164 inches, enters DEOP 400-02, Emergency Depressurization, and directs:
0I Initiation of Iso Condenser to maximum flow 0 Verification that SP/L >6 feet.
0 q Opening all ADS valves
[D Verification all relief valves are open ANSO Performs DEOP 400-02, Emergency Depressurization, as directed:
r Prevents injection from LPCI/CS pumps not needed for core cooling per Hard Card, LPCI INJ/CC CONTROL/SHUTDOWN U Initiates iso Condenser to maximum flow per Hard Card, ISOLATION CONDENSER 0 Verifies SP/L >6 feet El 4 Opens all ADS valves LI Verifies all relief valves are open SRO I Directs NSO/ANSO to control RPV level above TAF using any of the preferred injection systems listed below:
- Condensate
- LPCI NSO / *] Restores RPV level to that directed by the SRO (above TAF) using the ANSO systems specified by the SRO.
ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 12 of 13 Rev. 01 (05/02)
Op-Test No: ILT 01-1 Scenario No.: ILT-N-3 Event No.: 7, 8 & 9 Page 3 of 4 Event
Description:
A small recirculation loop break occurs with a loss of high pressure injection. The team should perform the RPV Control and Primary Containment Control DEOPs. Due to the loss of high pressure injection and RPV level dropping to TAF, the team should Emergency Depressurize and restore RPV level with low pressure injection systems.
Time Position Applicant's Actions or Behavior SRO Enters DEOP 200-1, Primary Containment Control, when PC/P reaches 2 psig and performs/directs:
I Monitoring of PC/P 0 Initiation of torus sprays before PC/P of 9 psig U When PC/P is above 9 psig or before DW/T reaches 281'F:
"* Verification of DSIL
"* Tripping of recirc pumps
"* Tripping of DW coolers
"* Initiation of DW sprays
[ Monitoring of DW/T (drywell sprays may be initiated for temperature control) 0 Monitoring of SP/T and initiation of torus cooling I Monitors SP/L El Verifies initiation of drywell and torus H2 /O 2 monitors ANSO Performs DEOP 200-1, Primary Containment Control, actions as directed:
U Monitors PC/P and initiates torus sprays and drywell sprays per Hard Card LPCI/CCSW OPERATION, as directed U Monitors DW/T U Monitors SP/T and initiates torus cooling per Hard Card LPCI/CCSW OPERATION as directed U Monitors SP/L U Verifies initiation of drywell and torus H2 /0 2 monitors ROLE PLAY:
NLO to checkEDG operation (it 3mi)
Report "Both EDGs~ ar pertng norrhil~y' Critical Tasks: (identified by 4 in guide)
With Reactor pressure greater than shutoff head of the low pressure systems and when RPV water level reaches TAF, INITIATE emergency depressurization, before level reaches Minimum Zero Injection RPV Water Level.
Action is taken to restore RPV water level above TAF by OPERATING available low pressure systems, when RPV pressure decreases below the shutoff head of low pressure systems.
ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 13 of 13 Rev. 01 (05/02)
Dresden GeneratingStation SIMULATOR EXERCISE GUIDE ILT 01-1 NRC EXAM SCENARIO ILT-N-5 Rev. 01 05/02 DEVELOPED BY:
Exam Author Date APPROVED BY:
Facility Representative Date Master Copy SimScenario-ILT-N-5.doc
Appendix D Scenario Outline Form ES-D-1 Facility: Dresden Scenario No: ILT-N-5 Op-Test No: ILT 01-1 Examiners: Operators:
Initial Conditions: Approximately 78% reactor power; IRM channel 16 out of service; 2B EHC Pump OOS; Unit 3 is in Mode 4.
Turnover: Power reduction in progress for drywell entry.
Event Malf. Event Event No. No. Type* Description 1 N/A N ANSO SRO rotating idle SDC pumps NSO 2 N/A R SRO lower reactor power by reducing recirculation flow MGGH2CON I ANSO main generator hydrogen temperature controller output SRO fails low 4 ICTUBLK C ANSO isolation condenser tube leak ICTULK C SRO N/A c NSO C
A SRO CRD pump failure RRMAFDBK NSO 6I SRO recirculation pump controller speed signal failure 7 CIGP1 I ALL spurious group 1 actuation and reactor scram 8 RDHLVFPA M RDHLVFPB RDHLDEGA ALL SDV partial hydraulic lock (ATWS)
RDHLDEGB SCRLFVAD NSO SCRLFVBD SRO SBLC pump relief valves fail open k (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 2 of 14 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-5 Event No.: 1 Page 1 of 1 Event
Description:
The ANSO, as directed by the SRO, performs DOP 1000-06, Rotating Idle SDC Pumps.
Time I Position I Applicant's Actions or Behavior SRO Directs ANSO to perform DOP 1000-06, Rotating Idle SDC Pumps.
ANSO Performs the following actions per DOP 1000-06, Rotating Idle SDC Pumps:
[0 Verifies the following valves closed:
- MO 2-1001-2A, B & C.
- MO 2-1001-4A, B & C.
1 Places each SDC pump control switch to start and then within 3 sec places each pump control switch to stop.
1 Requests operator to confirm rotation for each pump.
NSO Monitors panels and assists as directed.
11 ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 3 of 14 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-5 Event No.: 2 Page 1 of 1 Event
Description:
The NSO lowers reactor power by reducing recirculation flow following direction by the SRO.
Time I Position I Applicant's Actions or Behavior NSO Performs the following actions per DGP 03-01, Routine Power Changes, and DOP 0202-03, Reactor Recirculation Flow Control System Operation:
U Lowers recirculation pump speed using the master controller potentiometer.
I Verifies expected power reduction.
SRO Directs reducing reactor power per DGP 03-01, Routine Power Changes, and DOP 0202-03, Reactor Recirculation Flow Control System Operation, by lowering recirculation pump speed.
ANSO Monitors panels and assists as directed.
ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 4 of 14 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-5 Event No.: 3 Page 1 of 1 Event
Description:
Alarms are then received due to high main generator hydrogen temperature resulting from a failed controller. Hydrogen temperature is restored after the controller is placed in manual and adjusted by the ANSO.
[Time [Position Applicant's Actions or Behavior SIMULATOR OPERATOR:
Atthe discretion of ther'NRC chief exam~iner ,activate trigger 2~,
which fails the main geneator hydrogen temperature controller output.
Verify trigger 3 au~tomatically activates when the main generator hydrogen temperatur conitroller is placed to1 MAN.
ANSO Performs the following actions per DAN 902-7 E-1 1, H2 Seal Oil & Alterrex Pnl Trouble and DAN 2252-7 A-8,.
I Directs NLO to local panel 2252-7 to determine alarm received.
i Diagnosis that the main generator hydrogen cooler temperature controller auto mode has failed and places in MAN mode and restores temperature to normal band.
SIMULATOR OPERATOR IRLE PLAY NLO topaniel2252-7 (wait 2mifn):
Activate trigger 4 then Report'"the alarm is A-8, Machine Gas Temperature High, anda I have acknowldged it" NOto ch eck hydrogen cooler TOY operation: (wait 1 min)
Report "the hydrogen coole +CV appear tobe oprtignomll" SRO Directs ANSO to take manual control of the main generator hydrogen temperature controller.
Notifies Shift Manager and IMD of controller problem.
NSO Monitors panels and assists as directed.
ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 5 of 14 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-5 Event No.: 4 Page 1 of 2 Event
Description:
Alarms are received due to an isolation condenser tube leak. The isolation condenser is manually isolated by the ANSO. The SRO addresses the technical specification requirements for the inoperable isolation condenser.
Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR:
At the discretion of the NRC chief examiner, ctivate*riger 5 which inserts an Isolation Con~denser tube leak (0.5%)."7' ANSO Performs the following actions per DAN 902-3 C-4, Isol Condr Temp Hi, and /
or DOA 1300-01, Isolation Condenser Tube Leak:
LI May try to reseat the MO 2-1301-3 valve:
- Closes MO 2-1301-4
- Opens MO 2-1301-3
- Closes MO 2-1301-3
- Opens MO 2-1301-4
- Opens AO 2-1301-17 & 20
- Checks indication that leak has stopped 1I Isolates the Isolation Condenser by closing:
- MO 2-1301 -1
- MO 2-1301-2
- MO 2-1301-3
- MO 2-1301-4
- AO2-1301-17&20
- MO 2-1301-10
- MO 2-4399-74 SRO Enters DOA 1300-01, Isolation Condenser Tube Leak, and directs:
LI May try reseating the MO 2-1301-3 LI Isolating the Isolation Condenser.
LI Radiation Protection to survey below the IC vent.
I0 Security to limit access below IC vent.
LI Chemistry Department to sample IC shell side for activity.
LI Declares IC inoperable.
References Technical Specifications and determines:
LI ITS 3.5.3.A.1; verifies HPCI system operable immediately.
LI ITS 3.5.3.A.2; restore IC system to OPERABLE within 14 days Notifies Shift Manager and MMD of IC tube leak.
NSO Monitors panels and assists as directed.
ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 6 of 14 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-5 Event No.: 4 Page 2 of 2 Event
Description:
Alarms are received due to an isolation condenser tube leak. The isolation condenser is manually isolated by the ANSO. The SRO addresses the technical specification requirements for the inoperable isolation condenser.
Time Position I ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 7 of 14 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-5 Event No.: 5 Page 1 of 1 Event
Description:
A field report is received that the 2B CRD pump is failing due to rapid oil loss from a leak. The NSO shutdowns the 2B CRD pump and starts the 2A CRD pump.
Time Position I
NSO Performs the following actions per DOP 0300-01, Control Rod Drive System Startup and Operation:
1 May direct the NLO to perform pre-startup checks per the procedure.
0 Verifies 2A CRD pump discharge valve MO 2-0301-2A open.
0 Starts 2A CRD pump.
0 Stops 2B CRD pump 0 Verifies charging water pressure between 1450 to 1500 psig.
0 Directs NLO to perform post-startup checks per the procedure.
SRO Directs NSO to swap CRD pumps per DOP 0300-01, Control Rod Drive System Startup and Operation; OR, directs NSO to immediately swap CRD pumps per DOA 0300-01, Control Rod Drive System Failure.
Notifies Shift Manager and MMD of CRD pump problem.
ANSO Monitors panels and assists as directed.
ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 8 of 14 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-5 Event No.: 6 Page 1 of 2 Event
Description:
The speed control signal fails low for recirculation pump 2A and the pump flow increase is stopped when the NSO locks out the scoop tube.
[Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR:
At the discretionof the NRO chief examiner, activate trigger 6, which fails the 2A Recirculation Pump speed feedback signal.
NSO Performs the following actions per DAN 902-4 E-6, 2A/B Recirc PPs Speed Mismatch, and DOA 0202-03, Reactor Recirculation System Flow Control Failure:
0- Places the 2A M-G Set Scoop Tube Power Lockout Reset Switch in the Lockout position.
0- Verifies Core thermal power <2927 MWth.
0l Completes actions of 2A Recirc M-G Lockout in DOP 0202-12, Recirculation Pump Motor Generator Set Scoop Tube Operation.
"* Places both recirc pump speed control transfer stations to manual.
"* Runs 2A Recirc M-G Set speed demand to minimum.
- Places caution card on its Lockout Reset switch.
El Coordinates with licensed operator at the 2A Recirc M-G Set Scoop Tube to lower its speed to match 2B Recirc M-G Set per DOP 0202 12, Recirculation Pump Motor Generator Set Scoop Tube Operation.
SIMULATOR OPERATOR /ROLE PLAY:~
Licensed Operatorto lower 2AlRcir64G et speed locally (wait 3 min)
Report I amrdy to begin low.ering 2Aecirc M-GSt speed". When directed to lower the speed, toggle trigger 7 active and then inactive about every 10 seconds to "bump" the speed down until the NSO directs stopping the speed drop.
SRO Enters and directs performance of DOA 0202-03, Reactor Recirculation System Flow Control Failure.
El Enters and directs performance of DGA 7, Unpredicted Reactivity Addition.
E Contacts QNE.
El May request NLO to take local speed readings El Directs NSO to coordinate with a licensed operator at the 2A Recirc M-G Set Scoop Tube to lower its speed to match 2B Recirc M-G Set.
El Notifies Shift Manager and IMD of controller problem.
ANSO El Begins working through the steps of DGA 7, Unpredicted Reactivity Addition, but will not have time to complete the required actions.
ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 9 of 14 Rev. 01 (05/02)
Appendix D Operator Actions Form ES-D-2 Op-Test No: ILT 01-1 Scenario No.: ILT-N-5 Event No.: 6 Page 2 of 2 Event
Description:
The speed control signal fails low for recirculation pump 2A and the pump flow increase is stopped when the NSO locks out the scoop tube.
rTime Position Applicant's Actions or Behavior IROLE PLAY: <
ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 10 of 14 Rev. 01 (05/02)
Op-Test No: ILT 01 -1 Scenario No.: ILT-N-5 Event No.: 7,8&9 Page 1 of 4 Event
Description:
A spurious group 1 isolation and a reactor scram occurs. A partial hydraulic lock of the scram discharge volume results in an ATWS. The SBLC system fails due pump relief valves failincl open. The crew initiates alternate SBLC iniection.
Time Position NSO Performs the following actions per DGP 02-03, Reactor Scram:
0 Presses scram pushbuttons 0 Places mode switch in shutdown I Checks rods inserted; discovers ATWS condition 0 Initiates ARI 0 Verifies recirc pump speed at minimum.
SRO Enters DEOP 0100, RPV Control. When receives report that ATWS condition exists, exits DEOP 100 and enters DEOP 400-5, Failure to Scram, and directs the following:
LI 4 Placing ADS to inhibit 0 Placing both CS pumps in PTL Power Leq 0 Running back recirc to minimum.
0 Tripping the recirc pumps 0
- Directing Alternate Rod Insertion per DEOP 500-05:
- manually driving rods.
- repeated scram/resets.
0 Initiating SBLC before SP/T of 110°F.
Level Lea 0 Verification water level instruments are accurate U Verification any required automatic actions have occurred U Directing jumpers installed for MSIV low level and Off Gas high Rad isolations 0 q Terminating and Preventing injection except boron and CRD until RPV/L is _ -35 inches.
0 If SP/T is above 11 0°F, lets level drop until:
- Power is below 6%, OR
- All ADSVs stay closed and PC/P stays below 2 psig U */ Re-establishing injection to MAINTAIN RPV water level above
-164 inches.
Pressure Lea U Dropping RPV/P to 945 psig using ADSVs U Maintaining <1060 psig using HPCI/ADSVs ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 11 of 14 Rev. 01 (05/02)
Op-Test No: ILT 01 -1 Scenario No.: ILT-N-5 Event No.: 7.8&9 Page 2 of 4 Event
Description:
A spurious group 1 isolation and a reactor scram occurs. A partial hydraulic lock of the scram discharge volume results in an ATWS. The SBLC system fails due pump relief valves failing open. The crew initiates alternate SBLC injection.
Time Position Applicant's Actions or Behavior NSO I Performs DEOP 400-5, Failure to Scram, actions as directed:
ANSO 1I '4 Places ADS to inhibit LI Places both CS pumps in PTL Power Leq 0 Trips recirculation pumps
'4Performs Alternate Rod Insertion. (see below for specific 4
actions) 0 Initiates boron injection. Reports SBLC has failed to inject.
Level Leq
-I '4Terminates and Prevents injection except boron and CRD until RPV/L is _*-35 inches.
0 If SP/T is above 11 0°F, lets level drop until:
- Power is below 6%, OR
- All ADSVs stay closed and PC/P stays below 2 psig El '/Re-establishes injection to MAINTAIN RPV water level above
-164 inches.
Pressure Lea 0 Drops RPV/P to 945 psig ADSVs 0 Maintains <1060 psig using HPCI/ADSVs NSO '4Performs manual control rod insertion per DEOP 500-05, Alternate Insertion of Control Rods, as directed:
0 Bypasses the RWM 0l Starts the second CRD pump 0 Maximizes drive water pressure using one or more of the methods in DEOP 500-05.
I- Inserts rods using RONOR in EMERG IN or the normal rod movement control switch NSO '4Performs repeated scram/resets per DEOP 500-05, Alternate Insertion of Control Rods, as directed:
0 Depresses close pushbuttons for SDV vent and drain valves LI If RPV/L <-59 inches, directs pulling ARI fuses.
LI Attempts to reset scram 0 Directs scram jumpers installed.
0 Resets the scram LI Verifies all scram valves closed 0 Opens the SDV vent and drains 0 When 902-5 C-1 clears, scrams reactor LI Repeats as necessary ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 12 of 14 Rev. 01 (05/02)
Op-Test No: ILT 01 -1 Scenario No.: ILT-N-5 Event No.: 7,8&9 Page 3 of 4 Event
Description:
A spurious group 1 isolation and a reactor scram occurs. A partial hydraulic lock of the scram discharge volume results in an ATWS. The SBLC system fails due pump relief valves failing open. The crew initiates alternate SBLC injection.
Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR / ROLE PLAY:
Operator to jumper th9MSIVGroupl-59 in. and offgas hi hi radiation isolations (wait 5 min):
Activate trigger 9 and report "the MSiV Group1 -59 in. and offcgas hi hi radiation isolations are jumpered".
SIMULATOR OPERATO.R/ ROLE PLAY:-
OperatDr toP 2p0u. A.RImfuses (wait 5 mi):
Verify trigger 1o activated ad rep he ARfusesae Operator to istall sctram jumpers (wat 5 min):
Verify trigger 11factivated and report "hscram jmpers are instald",
SRO ElBased on failure of SBLC to inject, directs performance of DEOP 0500-01, Alternate Standby Liquid Control Injection.
SRO Enters DEOP 200-1, Primary Containment Control, when PC/P reaches 2 psig and performs/directs:
El May direct starting Drywell Coolers per DEOP 0500-02.
10 Initiation of torus sprays before PC/P of 9 psig l0 When PC/P is above 9 psig or before DW/T reaches 281°F: (may not reach these levels)
- Verification of DSIL
- Tripping of recirc pumps
- Tripping of DW coolers
- Initiation of DW sprays El Initiation of torus cooling E7 Verifies initiation of drywell and torus HP/O 2 monitors ANSO Performs DEOP 200-1, Primary Containment Control, actions as directed:
0l May start Drywell Coolers after jumpers installed per DEOP 0500-02.
i7 May initiate torus sprays and drywell sprays per Hard Card LPCI/CCSW OPERATION, as directed E7 Initiates torus cooling per Hard Card LPCI/CCSW OPERATION as directed 0l Verifies initiation of drywell and torus H 2/0 2 monitors ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 13 of 14 Rev. 01 (05/02)
Op-Test No: ILT 01-1 Scenario No.: ILT-N-5 Event No.: 7,8&9 Page 4 of 4 Event
Description:
A spurious group 1 isolation and a reactor scram' occurs. A partial hydraulic lock of the scram discharge volume results in an ATWS. The SBLC system fails due pump relief valves failing open. The crew initiates alternate SBLC injection.
Time Position Applicant's Actions or Behavior SIMULATOR....OPE OR:........"..... "
After the crew has res~et the scram anid attedsrtofteNRC chief.
examinerr, RUN CAEP File ClrHydLk.cae which will remove the SDV~
hydraulic lock.
SRO Based on report that all rods are inserted, exits DEOP 400-05, Failure to Scram, and enters DEOP100, RPV Control and directs:
0 Securing Boron injection if any was started.
0 Restoring RPV level to +8 to +48 inches.
1 Develop a cooldown strategy (i.e.; reopen MSIVs and/or restart RWCU)
NSO Reports that all rods inserted and performs the following as directed:
0l Restores level to +8 to +48 inches.
Critical Tasks: (identified by 4I in guide)
With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron and/or inserting control rods, to prevent exceeding the primary containment design limits.
With a reactor scram required, reactor not shutdown, and conditions for ADS blowdown are met, INHIBITADS to prevent an uncontrolled RPV depressurization, to prevent causing a significant power excursion.
During an ATWS with conditions met to perform power/level control TERMINATE AND PREVENT INJECTION, with exception of boron and CRD, into the RPV until conditions are met to re-establish injection.
When conditions are met to re-establish injection use available injection systems to MAINTAIN RPV water level above -164".
ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 14 of 14 Rev. 01 (05/02)