ML120180368: Difference between revisions

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| number = ML120180368
| number = ML120180368
| issue date = 05/01/2010
| issue date = 05/01/2010
| title = 2011-12 Draft Operating Test
| title = 12 Draft Operating Test
| author name =  
| author name =  
| author affiliation = NRC/RGN-IV
| author affiliation = NRC/RGN-IV
Line 77: Line 77:


1H13-P680-3A - 3C. 3. If asked about monitoring for THI, inform the trainee that another operator will monitor for THI. 4. This task begins at 04 01-B33-1/ Step 4.2.2 Task Overview:
1H13-P680-3A - 3C. 3. If asked about monitoring for THI, inform the trainee that another operator will monitor for THI. 4. This task begins at 04 01-B33-1/ Step 4.2.2 Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task shifts the second Reactor Recirculation Pump to fast speed in preparation for power ascension.
This task shifts the second Reactor Recirculation Pump to fast speed in preparation for power ascension.
The first recirc pump is already in fast speed.
The first recirc pump is already in fast speed.
Line 251: Line 251:
: 1. Unless otherwise stated, all control manipulations will be at panel P601 in the Main Control Room.
: 1. Unless otherwise stated, all control manipulations will be at panel P601 in the Main Control Room.
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task starts the RCIC system by manual operation of the system's individual components and controls.  
This task starts the RCIC system by manual operation of the system's individual components and controls.  
  - The normal means of starting RCIC for Rx level control would be automatic as a function of Rx level or depressing the system's automatic initiation pushbutton.
  - The normal means of starting RCIC for Rx level control would be automatic as a function of Rx level or depressing the system's automatic initiation pushbutton.
Line 321: Line 321:
Cue:  If asked for guidance, as the CRS direct the operator to ensure automatic actions occur.
Cue:  If asked for guidance, as the CRS direct the operator to ensure automatic actions occur.
Notes: Once E51-F022 is open, the steam leak will be triggered. The operator will have indications of a steam leak in the RCIC room as indicated by: (1) RCIC area temp high alarms (P601-21A-H2, H3, G3), (2)
Notes: Once E51-F022 is open, the steam leak will be triggered. The operator will have indications of a steam leak in the RCIC room as indicated by: (1) RCIC area temp high alarms (P601-21A-H2, H3, G3), (2)
(P601-21A-C1,D1), (3) PDS EP
(P601-21A-C1,D1), (3) PDS EP
-4 Operator Guide, (4) E31N602B on 1H13P642.
-4 Operator Guide, (4) E31N602B on 1H13P642.


Line 411: Line 411:
: 1. All controls and indications for this task are on panel 1H13
: 1. All controls and indications for this task are on panel 1H13
-P680. Task Overview:
-P680. Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task is to rotate from EHC pump A in operation to EHC pump C in operation, placing EHC pump A into standby.
This task is to rotate from EHC pump A in operation to EHC pump C in operation, placing EHC pump A into standby.
The fault in this task is the failure EHC pump C to maintain normal control fluid pressures.
The fault in this task is the failure EHC pump C to maintain normal control fluid pressures.
Line 566: Line 566:
: 2. Unless otherwise indicated, all valves are in the "E12" system.
: 2. Unless otherwise indicated, all valves are in the "E12" system.
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)


This task places the RHR system in service for Shutdown Cooling using the normal (E12-F053B) flow path. This is a Tech Spec Decay Heat Removal method. Throttling of RHR Shutdown Cooling flow caused damage to RHR Instrumentation piping during RF12. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
This task places the RHR system in service for Shutdown Cooling using the normal (E12-F053B) flow path. This is a Tech Spec Decay Heat Removal method. Throttling of RHR Shutdown Cooling flow caused damage to RHR Instrumentation piping during RF12. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Line 680: Line 680:
: 1. All Control Room operations will be on panel P870.
: 1. All Control Room operations will be on panel P870.
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)


This task is to manually initiate Suppression Pool Make Up per directions from EOP
This task is to manually initiate Suppression Pool Make Up per directions from EOP
Line 781: Line 781:
The task is complete when: Reactor core flow is lowered to 67 mlbm/hr and the operator determines the reactor is operating in the Monitored Region of the Power to Flow Map.
The task is complete when: Reactor core flow is lowered to 67 mlbm/hr and the operator determines the reactor is operating in the Monitored Region of the Power to Flow Map.
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The operator will perform 06
The operator will perform 06
-OP-1C71-W-0001 (Reactor Manual Scram Switch Test). When the operator depresses the first manual scram switch, two control rods (08-41 and 24-49) will scram due to a blown pilot solenoid fuse on the individual HCU units.
-OP-1C71-W-0001 (Reactor Manual Scram Switch Test). When the operator depresses the first manual scram switch, two control rods (08-41 and 24-49) will scram due to a blown pilot solenoid fuse on the individual HCU units.
Line 907: Line 907:
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE  Number: GJPM-OPS-P4271 Revision: 2 Page: 4 of  10    Task:  Rotate CCW Pumps Notes: (Notes to Evaluator)
ENTERGY NUCLEAR JOB PERFORMANCE MEASURE  Number: GJPM-OPS-P4271 Revision: 2 Page: 4 of  10    Task:  Rotate CCW Pumps Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task is to rotate CCW Pumps per SOI. During the evolution, a trip will occur on one of the operating CCW pumps requiring the restart of the non-operating CCW pump per the Loss of CCW ONEP. This is an Alternate Path JPM. This is a task that is coordinated from the control room.
This task is to rotate CCW Pumps per SOI. During the evolution, a trip will occur on one of the operating CCW pumps requiring the restart of the non-operating CCW pump per the Loss of CCW ONEP. This is an Alternate Path JPM. This is a task that is coordinated from the control room.
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Line 1,029: Line 1,029:
: 1. All controls will be from panel P870.
: 1. All controls will be from panel P870.
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task secures SGTS B following automatic initiation and reopens ventilation system isolation valves. SGTS A has already been secured to Standby Mode as an initial condition.
This task secures SGTS B following automatic initiation and reopens ventilation system isolation valves. SGTS A has already been secured to Standby Mode as an initial condition.
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Line 1,184: Line 1,184:
: 2. The valves and pipe plugs are located just south and west of the Hydraulic Control Station, near the Backup Scram Valves.
: 2. The valves and pipe plugs are located just south and west of the Hydraulic Control Station, near the Backup Scram Valves.
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task provides an alternate method of venting the scram air header to allow control rod insertion. The task consists of physically removing of pipe plugs located on the scram air header using a hack saw, allowing the scram air header to depressurize.
This task provides an alternate method of venting the scram air header to allow control rod insertion. The task consists of physically removing of pipe plugs located on the scram air header using a hack saw, allowing the scram air header to depressurize.
The scram pilot valves would fail open due to a loss of air pressure, allowing the control rods to insert into the reactor.
The scram pilot valves would fail open due to a loss of air pressure, allowing the control rods to insert into the reactor.
Line 1,297: Line 1,297:


ENTERGY NUCLEAR JOB PERFORMANCE MEASU RE  Number: GJPM-OPS-C6101 Revision: 2 Page: 4 of  10    Task: Startup RHR in Suppression Pool Cooling from the Remote Shutdown Panels Notes: (Notes to Evaluator)
ENTERGY NUCLEAR JOB PERFORMANCE MEASU RE  Number: GJPM-OPS-C6101 Revision: 2 Page: 4 of  10    Task: Startup RHR in Suppression Pool Cooling from the Remote Shutdown Panels Notes: (Notes to Evaluator)
: 1. Remote Shutdown Panels are located on the 111' elevation of the Control Building.
: 1. Remote Shutdown Panels are located on the 111' elevation of the Control Building.
: 2. Division 1 Remote Shutdown Panel is H22
: 2. Division 1 Remote Shutdown Panel is H22
-P150. 3. Division 2 Remote Shutdown Panel is H22
-P150. 3. Division 2 Remote Shutdown Panel is H22
Line 1,304: Line 1,304:
-protected train ESF inverter is selected and recorded on the initiating cues page.
-protected train ESF inverter is selected and recorded on the initiating cues page.
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)


This task is to startup RHR A or B in Suppression Pool Cooling from the Remote Shutdown Panels per the ONEP. This includes starting up SSW A or B. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
This task is to startup RHR A or B in Suppression Pool Cooling from the Remote Shutdown Panels per the ONEP. This includes starting up SSW A or B. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Line 1,453: Line 1,453:
-protected train ESF inverter is selected and recorded on the initiating cues page.
-protected train ESF inverter is selected and recorded on the initiating cues page.
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)


This task is to startup an ESF Static Inverter and transfer loads to the inverter per the SOI. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
This task is to startup an ESF Static Inverter and transfer loads to the inverter per the SOI. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Line 1,586: Line 1,586:
:  Fire Doors Surveillance Notes: (Notes to Evaluator)
:  Fire Doors Surveillance Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The operator will perform a Fire Door Alarm Check using the information provided in the initiating ques. The operator will discover tech spec door OC208 is INOP, tech spec door 1A212 is OPERABLE but requires a WR to fix the closing mechanism, and non
The operator will perform a Fire Door Alarm Check using the information provided in the initiating ques. The operator will discover tech spec door OC208 is INOP, tech spec door 1A212 is OPERABLE but requires a WR to fix the closing mechanism, and non
-
-
Line 1,690: Line 1,690:
:  Operator Qualification Verification Notes: (Notes to Evaluator)
:  Operator Qualification Verification Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
Using computer program Plateau LMS in accordance with Operations Section Guideline OPG-35, the operator will demonstrate the ability to verify his qualificati on s are current to stand shift as Reactor Operator.
Using computer program Plateau LMS in accordance with Operations Section Guideline OPG-35, the operator will demonstrate the ability to verify his qualificati on s are current to stand shift as Reactor Operator.
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Line 1,702: Line 1,702:
Standard:  Logs in to the Plateau LMS program
Standard:  Logs in to the Plateau LMS program
. Cue:  If asked, direct the operator to use his own user name and password. Notes: Three ways to access:
. Cue:  If asked, direct the operator to use his own user name and password. Notes: Three ways to access:
(1) Select START  
(1) Select START  
- All Programs  
- All Programs  
- Nuclear Corporate Applications  
- Nuclear Corporate Applications  
- Plateau LMS.
- Plateau LMS.
  (2) Operation Dept website homepage by selecting GGNS Homepage - Departments  
(2) Operation Dept website homepage by selecting GGNS Homepage - Departments  
- Operations  
- Operations  
- On the left menu under Plateau LMS select User Access.
- On the left menu under Plateau LMS select User Access.
Line 1,787: Line 1,787:
:  Determine Tagging Requirements  Notes: (Notes to Evaluator)
:  Determine Tagging Requirements  Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The operator will determine the proper isolations for the Motor Driven Fire Pump.
The operator will determine the proper isolations for the Motor Driven Fire Pump.
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Line 1,900: Line 1,900:
:  Primary Containment Water Level Determination Notes: (Notes to Evaluator)
:  Primary Containment Water Level Determination Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
Using EP Attachment 29 and the attached images to obtain RCIC Suction Pressure and Containment Pressure, determine Primary Containment Water Level from the Delta Pressure to Ctmt Level Conversion Table, EP Attachment 29 Table 1.
Using EP Attachment 29 and the attached images to obtain RCIC Suction Pressure and Containment Pressure, determine Primary Containment Water Level from the Delta Pressure to Ctmt Level Conversion Table, EP Attachment 29 Table 1.
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Line 2,002: Line 2,002:
:  Determine Fire Watch Requirements Notes: (Notes to Evaluator)
:  Determine Fire Watch Requirements Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The operator will determine that tech spec fire door OC208 is INOP and set a fire watch in accordance with TR 6.2.8 for the Division 1 ESF Switchgear Room (Control Building Elevation 111').
The operator will determine that tech spec fire door OC208 is INOP and set a fire watch in accordance with TR 6.2.8 for the Division 1 ESF Switchgear Room (Control Building Elevation 111').
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Line 2,100: Line 2,100:
:  Determine the plant EOOS Factor Notes: (Notes to Evaluator)
:  Determine the plant EOOS Factor Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task is to use the EOOS Computer to assess the Plant Safety Index and Risk Factor for out of service equipment and plant work.
This task is to use the EOOS Computer to assess the Plant Safety Index and Risk Factor for out of service equipment and plant work.
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Line 2,176: Line 2,176:
:  Review Adequacy of a Tagout Notes: (Notes to Evaluator)
:  Review Adequacy of a Tagout Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The operator will determine the proper isolations work on the MDFP.
The operator will determine the proper isolations work on the MDFP.
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Line 2,267: Line 2,267:
:  Review Radwaste Discharge Permit Notes: (Notes to Evaluator)
:  Review Radwaste Discharge Permit Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task is to perform the SRO review of the Batch Liquid Radwaste Discharge Permit performed by the Shift Manager to authorize a controlled release of liquid radwaste
This task is to perform the SRO review of the Batch Liquid Radwaste Discharge Permit performed by the Shift Manager to authorize a controlled release of liquid radwaste
. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Line 2,325: Line 2,325:
Batch Number Sample Date Today    Time  0345      One Total Suspended Solids (TSS) sample has been collected and analyzed for the month:
Batch Number Sample Date Today    Time  0345      One Total Suspended Solids (TSS) sample has been collected and analyzed for the month:
Yes  X  Initials  MR No        TSS mg/l (< 30mg/l)
Yes  X  Initials  MR No        TSS mg/l (< 30mg/l)
Minimum dilution factor  
Minimum dilution factor 3.2               


===3.2 Minimum===
Minimum dilution flow rate setpoint 6,800  gpm Maximum tank discharge flow rate setpoint 100  gpm Effluent Monitor Alarm Setpoint 4.52 E +3    cpm (Hi)   
dilution flow rate setpoint 6,800  gpm Maximum tank discharge flow rate setpoint 100  gpm Effluent Monitor Alarm Setpoint 4.52 E +3    cpm (Hi)   


Effluent Monitor Trip Setpoint 1.16 E +4    cpm (Hi-Hi)
Effluent Monitor Trip Setpoint 1.16 E +4    cpm (Hi-Hi)
Line 2,398: Line 2,397:
a)  Maximum Radwaste Tank Effluent Flow gpm  b)  Average Dilution Flow   
a)  Maximum Radwaste Tank Effluent Flow gpm  b)  Average Dilution Flow   


gpm
gpm
: 1)  Circulation Water Blowdown Flow  
: 1)  Circulation Water Blowdown Flow  
         ,            ,
         ,            ,
Line 2,494: Line 2,493:
- EAL Determination Notes: (Notes to Evaluator)
- EAL Determination Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
Event classification JPM in accordance with Emergency Preparedness Plan.
Event classification JPM in accordance with Emergency Preparedness Plan.
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Line 2,568: Line 2,567:
A. Initialization
A. Initialization
: 1. Startup the simulator using Simulator Instructor's Job Aid section 6.3
: 1. Startup the simulator using Simulator Instructor's Job Aid section 6.3
.
.
: 2. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 2. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 3. Set the Simulator to IC-31 and perform switch check (Using Quick Reset in Director)
: 3. Set the Simulator to IC-31 and perform switch check (Using Quick Reset in Director)
Line 2,675: Line 2,674:
-F217B. Notifies the local operator to cycle OPEN and SHUT C11
-F217B. Notifies the local operator to cycle OPEN and SHUT C11
-F109B to vent CRD pump B. Starts CRD pump B.
-F109B to vent CRD pump B. Starts CRD pump B.
(The BOP should alert the ACRO that he is starting the CRD B pump)
(The BOP should alert the ACRO that he is starting the CRD B pump)
Notifies the local operator to SLOWLY OPEN C11
Notifies the local operator to SLOWLY OPEN C11
-F217B. Check CRD system flow has stabilized between 54 to 66 gpm.
-F217B. Check CRD system flow has stabilized between 54 to 66 gpm.
Line 2,770: Line 2,769:
Failure of RPS to Scram TIME Position Applicant's Actions or Behavior ACRO
Failure of RPS to Scram TIME Position Applicant's Actions or Behavior ACRO
* Second Recirculation pump trips. Crew inserts manual reactor scram as observed by control rods inserted and scram annunciators received. Criterion is to give the highest priority to insert a manual scram.
* Second Recirculation pump trips. Crew inserts manual reactor scram as observed by control rods inserted and scram annunciators received. Criterion is to give the highest priority to insert a manual scram.
(The RPS automatic scram has been disabled)
(The RPS automatic scram has been disabled)
Report to CRS that he is placing the Mode SW in SHUTDOWN.
Report to CRS that he is placing the Mode SW in SHUTDOWN.
Place the Mode SW to SHUTDOWN.
Place the Mode SW to SHUTDOWN.
Line 2,931: Line 2,930:
A. Initialization
A. Initialization
: 1. Startup the simulator using Simulator Instructor's Job Aid section 6.3
: 1. Startup the simulator using Simulator Instructor's Job Aid section 6.3
.
.
: 2. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 2. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 3. Set the Simulator to IC-3 3 and perform switch check (Using Quick Reset in Director)
: 3. Set the Simulator to IC-3 3 and perform switch check (Using Quick Reset in Director)
Line 3,277: Line 3,276:
A. Initialization
A. Initialization
: 1. Startup the simulator using Simulator Instructor's Job Aid section 6.3
: 1. Startup the simulator using Simulator Instructor's Job Aid section 6.3
.
.
: 2. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 2. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 3. Set the Simulator to IC-9 and perform switch check (Using Quick Reset in Director)
: 3. Set the Simulator to IC-9 and perform switch check (Using Quick Reset in Director)
Line 3,302: Line 3,301:
Power  5%    Pressure  950 psig    B OC  EOOS  GREEN  A plant startup is in progress with all steps complete up to step 6.2.16.b in 03-1-01-1 (Cold Shutdown to Generator Carrying Minimum Load) and step 1.3.17 of Attachment 1 in 03 01-1 and step 163A of the cycle 18 BOC rod sequence movement sheet. Planned Evolutions this shift
Power  5%    Pressure  950 psig    B OC  EOOS  GREEN  A plant startup is in progress with all steps complete up to step 6.2.16.b in 03-1-01-1 (Cold Shutdown to Generator Carrying Minimum Load) and step 1.3.17 of Attachment 1 in 03 01-1 and step 163A of the cycle 18 BOC rod sequence movement sheet. Planned Evolutions this shift
:  The Crew will pull control rods to complete step 163B of the rod sequence movement sheet and then place the Mode Switch in RUN.
:  The Crew will pull control rods to complete step 163B of the rod sequence movement sheet and then place the Mode Switch in RUN.
(Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1.b will not be provided for this scenario)
(Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1.b will not be provided for this scenario)
When the Mode Switch is in RUN, the CRO will start a second Condensate Booster Pump prior to continuing with the Turbine Startup Procedure.
When the Mode Switch is in RUN, the CRO will start a second Condensate Booster Pump prior to continuing with the Turbine Startup Procedure.
C. Allow the crew to perform pre
C. Allow the crew to perform pre
Line 3,391: Line 3,390:
-LO  The Wide Range SP level indicator 1E30-LR-R600B will be downscale. All other SP level indications will read normally.
-LO  The Wide Range SP level indicator 1E30-LR-R600B will be downscale. All other SP level indications will read normally.
CRS Recognizes entry conditions and enters TS 3.
CRS Recognizes entry conditions and enters TS 3.
 
3.3.1 Condition A and TS 3.3.6.4 Condition C
====3.3.1 Condition====
A and TS 3.3.6.4 Condition C
.
.
Appendix D Required Operator Actions Form ES-D-2  Scenario 3 Page 12 of 18  Revision 1  Op-Test No:  12/11      Scenario No:
Appendix D Required Operator Actions Form ES-D-2  Scenario 3 Page 12 of 18  Revision 1  Op-Test No:  12/11      Scenario No:
Line 3,404: Line 3,401:
As indicated by LPCS/RHR A initiation when no reason for the initiation present (Reactor level above  
As indicated by LPCS/RHR A initiation when no reason for the initiation present (Reactor level above  
-151.3" and Drywell pressure < 1.39 psig)
-151.3" and Drywell pressure < 1.39 psig)
(The BOP will use various Control Room indications to determine reactor water level is above -150.3" and drywell pressure is below 1.39 psig)
(The BOP will use various Control Room indications to determine reactor water level is above -150.3" and drywell pressure is below 1.39 psig)
CRS Direct the BOP to recover from Division 1 ECCS initiation using SOI 04 01-E12-1 Attachment IX
CRS Direct the BOP to recover from Division 1 ECCS initiation using SOI 04 01-E12-1 Attachment IX
. OR Direct the BOP to secure the A DW purge compressor using SOI 04 01-E61-1 section 5.2.2 step a.
. OR Direct the BOP to secure the A DW purge compressor using SOI 04 01-E61-1 section 5.2.2 step a.
(Note that if this path is taken, the CRS should enter TS 3.6.3.3)
(Note that if this path is taken, the CRS should enter TS 3.6.3.3)
  *When Division 1 ECCS spuriously initiates, the crew secures the Division 1 Drywell Purge Compressor prior to the Drywell reaching 1.23 psig causing a reactor scram.
  *When Division 1 ECCS spuriously initiates, the crew secures the Division 1 Drywell Purge Compressor prior to the Drywell reaching 1.23 psig causing a reactor scram.
Enter the Control Rod/Drive Malfunctions ONEP.
Enter the Control Rod/Drive Malfunctions ONEP.
Line 3,570: Line 3,567:
A. Initialization
A. Initialization
: 1. Startup the simulator using Simulator Instructor's Job Aid section 6.3
: 1. Startup the simulator using Simulator Instructor's Job Aid section 6.3
.
.
: 2. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 2. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 3. Set the Simulator to IC-31 and perform switch check (Using Quick Reset in Director)
: 3. Set the Simulator to IC-31 and perform switch check (Using Quick Reset in Director)
Line 3,646: Line 3,643:
-1609, wait 3 minutes and report the beaker is tripped on thermal device.
-1609, wait 3 minutes and report the beaker is tripped on thermal device.
: b. If sent to the pump, report that it is very hot and that the motor casing is discolored.
: b. If sent to the pump, report that it is very hot and that the motor casing is discolored.
: 5. P41-F018B (SSW to Div 2 DG) will lose power on stroke.  
: 5. P41-F018B (SSW to Div 2 DG) will lose power on stroke.
: a. When directed by the control room to place division 2 diesel in MAINT, coordinate with the control room and trigger Event 6 to place the diesel in MAINT.
: a. When directed by the control room to place division 2 diesel in MAINT, coordinate with the control room and trigger Event 6 to place the diesel in MAINT.
: 6. E22-F004 (HPCS injection valve) will lose power on stroke. This valve CAN be manually opened if an operator is sent to open it. a. When the control room sends an operator to open this valve, wait until RPV water level is -100" wide range, then trigger Event 5 to manually open E22
: 6. E22-F004 (HPCS injection valve) will lose power on stroke. This valve CAN be manually opened if an operator is sent to open it. a. When the control room sends an operator to open this valve, wait until RPV water level is -100" wide range, then trigger Event 5 to manually open E22
Line 3,729: Line 3,726:
-4A2-E-4, CONT ROD DRIFT.
-4A2-E-4, CONT ROD DRIFT.
The operator will depress the ROD DRIFT RC&IS push button to determine which rod is drifting. The operator will then select that control rod for display on the full core display and determine the direction of the rod drift.
The operator will depress the ROD DRIFT RC&IS push button to determine which rod is drifting. The operator will then select that control rod for display on the full core display and determine the direction of the rod drift.
(This action is described in the ARI for the above annunciator)
(This action is described in the ARI for the above annunciator)
Applies a continuous insert signal for control rod 24
Applies a continuous insert signal for control rod 24
-33 FH per the Control Rod/Drive Malfunctions ONEP immediate operator actions.
-33 FH per the Control Rod/Drive Malfunctions ONEP immediate operator actions.

Revision as of 06:49, 30 April 2019

12 Draft Operating Test
ML120180368
Person / Time
Site: Grand Gulf  Entergy icon.png
Issue date: 05/01/2010
From:
NRC Region 4
To:
Entergy Operations
References
50-416/11-301, 50-417/11-301, GJPM-OPS-B3306
Download: ML120180368 (272)
v • d • e


Text

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3306 Revision: 05 Page: 1 of 13 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-CR 1 Time Critical Alternate Path Validation Time:

25 min TITLE: Shift Recirc Pumps to Fast Speed New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

Revised JPM to include new procedure steps added by procedure revision. Changed JPM completion point to reduce the time required to complete this JPM.

THIS DOCUMENT REPLACES

GJPM-OPS-B3306 Rev 4 REVIEW / APPROVAL (Print Name):

TEAR Approval ( )

Prepared By:

Jonathan Sparks 5/1/10 **Preparer Date Ops Review

++: Keith Huff 10/4/11 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Chris Laird 10/4/11 Training Representative Date Approved By:

Kane Ryder 10/4/11 +Discipline Training Supervisor Date Approval Date:*

10/4/11

  • Indexing Information
    • The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.

++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL) FINAL ACCEPTANCE BY RM (DATE/INITIALS) 04-1-01-B33-1 Rev 139 05-1-02-III-3 Rev 106 ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3306 Revision: 5 Page: 2 of 13 Task: Shifting Reactor Recirc Pumps to Fast Speed Setting: Simulator Type: RO Task: CRO-B33(1)-005 K&A: 202001: A4.01 (3.7/3.7)

Safety Function

Recirculation System Time Required
25 minutes Time Critical
No Alternate Path
Yes Performance
Actual Reference(s)
04-1-01-B33-1/4.2/6.2/6.3 Handout(s)
None # Manipulations
6 # Critical Steps
4 Group: 2 Simulator Setup/Required Plant Conditions
1. In the Simulator Instructor Booth, ensure Director is running and reset the simulator to IC-43 (IC with plant ready to upshift Recirc Pumps)
2. Perform or verify the following:

Verify plant power between 30% and 32% power Verify load line < 75%

Verify feedwater flow > 4.0 mlbm/hr.

Verify Recirc Pump "B" operating in SLOW speed with FCV 95% open Verify Recirc Pump "A" operating in FAST speed with:

o FCV at min position o Reset cavitation interlock o Depress the Recirc Pump "A" start PB Verify FCTR in SETUP (remote function c51 310) Verify that all prerequisites contained in section 4.2.1 of 04 01-B33-1 are satisfied.

3. Insert Malfunction rr196b (Incomplete Sequence B)

Safety Concerns

None ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3306 Revision: 5 Page: 3 of 13 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant is in power ascension, approximately 3 4% power. Recirc Pump A is in FAST speed APRM FCTR cards are in SETUP Breakers CB

-3B and CB-4B are racked in and closed.

Requirements for entry into Restricted Region have been met.

Initiating Cue(s):

The Shift Manager has directed you to shift Reactor Recirc Pump B to FAST speed.

All prerequisites are met.

This task is not time critical.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3306 Revision: 5 Page: 4 of 13 Task: Shifting Reactor Recirc Pumps to Fast Speed Notes: (Notes to Evaluator)

1. Several parameter verifications must be made prior to transferring a Recirc pump to fast speed. The standard for doing so offers only one source for this instrumentation. There may be more than one source, so the standard usually states "or equivalent" to let the evaluator know that there may another legitimate way to verify the parameter.
2. Unless otherwise indicated, all controls and indications for this task are on panel

1H13-P680-3A - 3C. 3. If asked about monitoring for THI, inform the trainee that another operator will monitor for THI. 4. This task begins at 04 01-B33-1/ Step 4.2.2 Task Overview:

(Detailed description of task)

This task shifts the second Reactor Recirculation Pump to fast speed in preparation for power ascension.

The first recirc pump is already in fast speed.

The fault in this task is that RRP fast speed breaker CB

-5B fails to close, resulting in an Incomplete Start Sequence and a system shutdown.

The operator will enter the Reduction in Recirc System Flow ONEP and close the discharge valve for the B Recirc Pump completing the JPM.

The core must be closely monitored for Thermal Hydraulic Instability (THI). For this task, it will be assumed that another operator will monitor for THI.

Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3306 Revision: 5 Page: 5 of 13 Step 1: 04-1-01-B33-1 step 4.2.2a(1)

  • ADJUST Recirc Loop B FCV to MIN ED position as follows:
  • USING Recirc Loop B FLO CONT on 1H13

-P680, THEN CLOSE Recirc is just indicated on B33 Process Diagram OR Computer point B33N027B

. ALLOW computer point B33K658B.C88 at least 5 seconds for computer point updates.

IF sufficient PDS computer points are NOT available, a FCV position of USING FEEDS indication May be used to set FCV

. Standard: Adjust B flow control valve to 20% open (Min Ed).

Cue: Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3306 Revision: 5 Page: 6 of 13 Step 2: 04-1-01-B33-1 step 4.2.2a(2) CHECK seal purge flow AND seal cavity pressure normal.

Seal purge flow 1.5 to 2.5 gpm. (Local C11

-FI-R020B). CHECK #1 seal cavity pressure slightly higher than Reactor pressure.

CHECK #2 seal cavity pressure indicates approximately half the value of #1 seal cavity pressure.

Standard: Check purge flow and cavity pressures are normal.

Cue: Report Seal Purge Flow as 2.0 gpm when asked as the local operator to check seal purge flow.

Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3306 Revision: 5 Page: 7 of 13 Step 3: 04-1-01-B33-1 step 4.2.2a(3) CHECK pump AND motor temperature normal on Recirc Pump Recorder 1B33-TR-R601 on 1H13

-P614. Standard: Cue: When the operator is on this step, inform the operator that all temperatures are normal.

Notes: This recorder is broken in the simulator.

SAT / UNSAT Step 4: 04-1-01-B33-1 step 4.2.2a(4) OBSERVE annunciators associated with Loop B HPU, seal flow, AND pump temperatures extinguished on 1H13

-P680-3A. Standa rd: Observes indications listed.

Cue: Notes:

SAT / UNSAT Step 5: 04-1-01-B33-1 step 4.2.2a(5) DEPRESS RECIRC PMP B CAV INTLK RESET pushbutton on 1H13

-P680 AND OBSERVE respective status light deenergizes.

Standard: Depress pushbutton. Cue: Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3306 Revision: 5 Page: 8 of 13 Step 6: 04-1-01-B33-1 step 4.2.2a(6) DEPRESS RX WTR LVL LO INTLK B RESET pushbutton on 1H13

-P680 AND OBSERVE respective status light deenergizes.

Standard: Depress pushbutton

. Cue: Not es:

SAT / UNSAT Step 7: 04-1-01-B33-1 step 4.2.2a(7)

  • RAISE respective BOP transformer tap setting to about 7.2 kV on Bus 11HD(12HE) for pump to be shifted

. Standard: On panel P807, raise the tap setting on transformer 11B by turning the BOP XFMR 11B X

-WDG TO BUS 12HE LTC clockwise to the "RAISE" position until approximately 7.2 KV is indicated on meter R22

-R603. Cue: Notes:

SAT / UNSAT Step 8: 04-1-01-B33-1 step 4.2.2a(8) NOTIFY Chemistry AND Radiation Protection of the possibility of a crud burst as a result of the Recirculation pump speed transfer.

Standard: Notifies Chemistry and RP.

Cue: Chemistry and RP is notified.

Notes:

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3306 Revision: 5 Page: 9 of 13 SAT / UNSAT Step 9: 04-1-01-B33-1 step 4.2.2a(9)

  • DEPRESS START pushbutton on TRANS TO LFMG/START handswitch on 1H13-P680 for Recirc Pump B.

CHECK the following:

CB-2B LFMG B GEN BRKR FDR 252

-1205A, OPENS.

CB-1B, LFMG B MTR FDR 152

-1411 OPENS. Recirc Pump B COASTS down to less than 360 rpm.

Standard: Depress pushbutton.

Cue: Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3306 Revision: 5 Page: 10 of 13

Step 10: 04-1-01-B33-1 step 4.2.2a(10)

WHEN pump speed lowers below 360 rpm, CHE CK that CB-5B, RECIRC PUMP B FDR, 252

-1205) CLOSED.

Standard: Observes that breaker CB

-5B DOES NOT close and Annunciator "PMP B AUTO XFER INC" P680

-3A-D9 actuates.

Cue: When the operator reports that Recirc Pump B did not start, as the CRS direct the operator to enter the Reduction in Recirc System Flow ONEP (05 02-III-3) and implement the immediate and subsequent actions.

Notes: This begins the alternate path for this JPM.

SAT / UNSAT Step 11: 05-1-02-III-3 step 3.1 MONITOR APRMs, LPRMs, SRM period meters, and PBDS Computer Trends. IF operating in the Restricted or Monitored Region and thermal hydraulic instability is observed, THEN IMMEDIATELY SCRAM the Reactor. Standard: Cue: As the CRS inform the operator that another operator will have the responsibilities as THI watch and to continue with the ONEP subsequent actions.

Notes: No conditions meet the requirements of step 2.1 Immediate Operator Actions.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3306 Revision: 5 Page: 11 of 13

Step 12: 05-1-02-III-3 step 3.2

  • IF one Recirc pump has stopped, THEN CLOSE RECIRC PMP B DISCH VLV B33

-F067B. Standard: Closes B33

-F067B Cue: This completes the JPM.

Notes:

SAT / UNSAT Task Standard(s)

The B Recirc Pump is tripped with the B33

-F067B closed per 04-1-01-B33-1 SOI. SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-B3306 Revision: 5 Page: 12 of 13 Task: Shifting Reactor Recirc Pumps to Fast Speed Follow-Up Questions & Answers

Comments:

Give this page to the student Initial Condition(s):

The plant is in power ascension, approximately 32% power.

Recirc Pump A is in FAST speed APRM FCTR cards are in SETUP Breakers CB

-3B and CB-4B are racked in and closed.

Requirements for entry into Restricted Region have been met.

Initiating Cue(s):

The Shift Manager has directed you to shift Reactor Recirc Pump B to FAST speed.

All prerequisites are met.

This task is not time critical.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5102 Revision: 05 Page: 1 of 12 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-CR 2 Time Critical Alternate Path Validation Time:

1 5 min TITLE: RCIC Manual Startup New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

Correct typographical errors discovered during operator validation and add instructions for the simulator operator.

THIS DOCUMENT REPLACES

GJPM-OPS-E5102 Rev 4 REVIEW / APPROVAL (Print Name)
TEAR Approval ( )

Prepared By:

Jonathan Sparks 8/5/20 10 **Preparer Date Ops Review

++: Keith Huff 9/26/2011 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Chris Laird 9/26/2011 Training Representative Da te Approved By:

Kane Ryder 9/28/2011 +Discipline Training Supervisor Date Approval Date:*

9/28/2011

  • Indexing Information
    • The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.

++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS)

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5102 Revision: 5 Page: 2 of 12 Task: RCIC Manual Startup Setting: Simulator Type: RO Task: CRO-E51-003 K&A: 217000: A4.04

- 3.6/3.6 Safety Function

Reactor Core Isolation Cooling System (RCIC)

Time Required

15 minutes Time Critical
No Alternate Path
Yes Performance
Actual Reference(s)
04-1-01-E51-1 section 5.2.2 ARI 1H13-P601-21A-G3 Handout(s)
None # Manipulations
12 # Critical Steps
8 Group: 1 Simulator Setup/Required Plant Conditions
IC-31 (or any full power IC).

Start SSW A per the SOI.

Ensure P11

-F064 and P11

-F065 auxiliary building isolation valves are open on P870.

Insert Malf. E51050 at severity 100 on trigger 1, "steam leak in RCIC room upstream of E51F045" Insert EP Attachment 3 as DONE, "RCIC Div 1 and 2 Isolations bypassed".

Safety Concerns

None ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5102 Revision: 5 Page: 3 of 12 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

RCIC is in STANDBY mode.

SSW A is in service.

RP has set up an air sampler in the RCIC room and is ready to take an air sample when RCIC starts.

Another operator is monitoring Suppression Pool temperature per

06-OP-1M24-V-0001. RCIC turbine oil level is between upper scribe marks in sight glass.

RCIC pump inboard and outboard bearing oil levels were checked and were "visible in bulb".

Initiating Cue(s):

You have been directed to do a controlled manual startup of RCIC in the CST-to-CST mode, with the following parameters:

o 800 gpm flow o 300 psig discharge pressure This task is not time critical.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5102 Revision: 5 Page: 4 of 12 Task: RCIC Manual Startup Notes: (Notes to Evaluator)

1. Unless otherwise stated, all control manipulations will be at panel P601 in the Main Control Room.

Task Overview:

(Detailed description of task)

This task starts the RCIC system by manual operation of the system's individual components and controls.

- The normal means of starting RCIC for Rx level control would be automatic as a function of Rx level or depressing the system's automatic initiation pushbutton.

The critical skills examined here are the operator's ability to locate and operate RCIC system controls in a manner that would provide for safe, uninterrupted operation of the system without reliance on the logic that would automatically operate this system in the same manner. Also, diagnostics involved for recognition of a steam line break and failure of the automatic isolation to occur, along with effecting the required isolation will be examined.

The fault in this task is a RCIC Steam Line break in the RCIC room with failure of the automatic isolation. - Continued operation of RCIC in this condition without isolating the steam supply line would lead to damage of equipment in the RCIC room and restricted personnel habitability, possibly spreading to other areas within the auxiliary building

. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5102 Revision: 5 Page: 5 of 12 Step 1: 04-1-01-E51-1 step 5.2.1 Prerequisites Check CST test return isolation valves P11

-F064 and F065.

Standard: Check that listed valves are open.

Cu e: Notes: SAT / UNSAT Step 2: 02-S-01-27 Ops Philosophy 6.6.13 Place the RCIC DIV 1 and 2 MOV TEST switches in TEST.

Standard: Place switches in TEST

. Cue: Notes:

SAT / UNSAT Step 3: 04-1-01-E51-1 step 5.2.2b START RCIC RM FAN COIL UNIT USING RCIC RM FAN COIL UNIT handswitch on 1H13

-P870-1C. Standard: Start fan, observing red light on and green light off.

Cue: Notes: step 5.2.2c is NA since the initial conditions indicate this step is complete. The operator may verify the SSW lineup.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5102 Revision: 5 Page: 6 of 12 Step 4: 04-1-01-E51-1 step 5.2.2d IF desired to run RCIC in recirculation mode only, CLOSE F268, PRESS LOCK ISO FOR F013; to PREVENT flow to the reactor due to disc flexing of E 51-F013. (Concurrent Verification Required)

Standard: Directs local operator to close E51

-F268. Cue: E51-F268 is closed.

Notes: step 5.2.2e is NA

SAT / UNSAT Step 5: 04-1-01-E51-1 step 5.2.2 f

  • Shift RCIC FLO CONT to MANUAL.

Standard: Place Controller E51

-R600 in manual.

Cue: Notes:

SAT / UNSAT Step 6: 04-1-01-E51-1 step 5.2.2g

  • Reduce RCIC FLO CONT output to minimum.

Standard: Lower E51-R600 controller to 0%

Cue: Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5102 Revision: 5 Page: 7 of 12 Step 7: 04-1-01-E51-1 step 5.2.2h

. Standard: Opens E51-F046, observing red light on and green light off.

Cue: Notes:

SAT / UNSAT Step 8: 04-1-01-E51-1 step 5.2.2i

  • START Turbine Gland Seal compressor USING RCIC GL SEAL COMPR handswitch.

Standard: Start compressor, observing red light on and green light off.

Cue: Notes:

SAT / UNSAT Step 9: 04-1-01-E51-1 step 5.2.2j

Standard: Open valve, observing red light on and green light off.

Cue: Notes: SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5102 Revision: 5 Page: 8 of 12 Step 10: 04-1-01-E51-1 step 5.2.2k

  • AFTER 6 seconds, OPEN F045 USING RCIC STM SPLY TO RCIC TURB handswitch.

Standard: Opens E51-F045, observing red light on and green light off.

Cue: Notes:

SAT / UNSAT Step 11: 04-1-01-E51-1 step 5.2.2l RAISE turbine speed to develop greater than 2000 rpm USING RCIC FLO CONT in MANUAL.

Standard: Raises turbine speed >2000 rpm as indicated on E51

-R605. Cue: Notes: An over-speed trip during this step will constitute a failure of the JPM.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5102 Revision: 5 Page: 9 of 12 Step 12: 04-1-01-E51-1 step 5.2.2m(1)

  • WHEN discharge pressure is above 125 psig, ESTABLISH RCIC discharge flow path.
  • OPEN F 059 USING RCIC OTBD TEST RTN TO CST handswitch.

THROTTLE OPEN FV-F551 USING RCIC TEST RTN FCV TO CST handswitch.

RAISE turbine speed as desired to establish desired flow.

Standard: Open E51-F059 and E51

-F022, observing red lights on and green lights off.

Cue: If asked for guidance, as the CRS direct the operator to ensure automatic actions occur.

Notes: Once E51-F022 is open, the steam leak will be triggered. The operator will have indications of a steam leak in the RCIC room as indicated by: (1) RCIC area temp high alarms (P601-21A-H2, H3, G3), (2)

(P601-21A-C1,D1), (3) PDS EP

-4 Operator Guide, (4) E31N602B on 1H13P642.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5102 Revision: 5 Page: 10 of 12 Step 13: 02-S-01-27 Ops Philosophy 6.1.1b

  • Close E51-F063 or E51

-F064, RCIC Steam Supply Isolation Valves to isolate the steam leak in the RCIC room.

Standard: Closes E51

-F063 and E51

-F064, observing red lights off and green lights on.

Cue: Notes: This completes the JPM. Depressing RCIC MAN ISOL pushbutton will not isolate RCIC steam supply and is not functional unless RCIC has been manually or automatically initiated.

SAT / UNSAT Task Standard(s)

RCIC was started IAW SOI 04 01-E51-1. RCIC steam supply line was isolated by closing E51F063 or E51F064 to isolate the steam leak in the RCIC room. SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E5102 Revision: 5 Page: 11 of 12 Task: RCIC Manual Startup Follow-Up Questions & Answers

Comments:

Give this page to the student Initial Condition(s):

RCIC is in STANDBY mode.

SSW A is in service.

RP has set up an air sampler in the RCIC room and is ready to take an air sample when RCIC starts.

Another operator is monitoring Suppression Pool temperature per

06-OP-1M24-V-0001. RCIC turbine oil level is between upper scribe marks in sight glass.

RCIC pump inboard and outboard bearing oil levels were checked and were "visible in bulb".

Initiating Cue(s):

You have been directed to do a controlled manual startup of RCIC in the CST-to-CST mode, with the following parameters:

o 800 gpm flow o 300 psig discharge pressure This task is not time critical.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-N3201 Revision: 0 Page: 1 of 11 Rtype:

QA Recor d Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-CR 3 Time Critical Alternate Path Validation Time:

1 0 min TITLE: Rotate EHC Pumps

- Pump A to Pump C New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

New Material THIS DOCUMENT REPLACES
NA REVIEW / APPROVAL (Print Name):

TEAR Approval ( )

Prepared By:

Kyle Grillis 11/30/09 **Preparer Date Ops Review++: Keith Huff 10/3/11 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Chris Laird 10/3/11 Training Representative Date Approved By:

Kane Ryder 10/3/11 +Discipline Training Supervisor Date Approval Date:*

10/3/11

  • Indexing Information
    • The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.

++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS)

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-N3201 Revision: 0 Page: 2 of 11 Task: Rotate EHC Pumps

- Pump A to Pump C Setting: Simulator Type: RO Task: CRO-N32-006 K&A: 241000: A2.06

- 3.1/3.2 Generic 2.1.30: 4.4/4.0 Safety Function

3 - Reactor Pressure Control Time Required
10 minutes Time Critical
No Alternate Path
Yes Performance
Actual Reference(s)
04-1-01-N32-1 section 5.1 Handout(s)
None # Manipulations
6 # Critical Steps
5 Group: 2 Simulator Setup/Required Plant Conditions
IC-31 o Reduce power to 95% using FCV's.

o Ensure the lead TCV is <65% open.

Verify EHC pumps A and B are operating and EHC pump C is in standby.

Open and play schedule file GJPM

-OPS-2011CR3 - OR - On TRIGGER 10 insert the following instrument overrides:

o ior ao_1n32r612 time delay 0, ramp 30 seconds, final value 410 o ior ao_1n32r627 time delay 0, ramp 30 seconds, final value 150 Safety Concerns

Non e ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-N3201 Revision: 0 Page: 3 of 11 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant is at rated power.

EHC pumps A and B are in operation.

Initiating Cue(s):

The CRS has directed you to rotate from EHC pump A to EHC pump C, such that EHC pumps B and C are left in operation, in accordance with 04 01-N32-1 section 5.1.

An operator is at the EHC pumps standing by for instructions.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-N3201 Revision: 0 Page: 4 of 11 Task: Rotate EHC Pumps

- Pump A to Pump C Notes: (Notes to Evaluator)

1. All controls and indications for this task are on panel 1H13

-P680. Task Overview:

(Detailed description of task)

This task is to rotate from EHC pump A in operation to EHC pump C in operation, placing EHC pump A into standby.

The fault in this task is the failure EHC pump C to maintain normal control fluid pressures.

The operator will then be redirected return EHC pump A to operation and place EHC pump C into standby.

Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 04-1-01-N32-1 step 5.1.1 Prerequisites Verifies prerequisites for rotating EHC pumps are met

. EHC FLUID PUMP C handswitch is in AUTO on 1H13

-P680-10C Annunciator "CF PMP SWITCH TO AUTO", 1H13

-P680-10A (C-5), i s not in Alarm. Lead turbine control valve N11

-F026D to be <65% open.

Standard: Verifies prerequisites are met.

Cue: Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-N3201 Revision: 0 Page: 5 of 11 Step 2: 04-1-01-N32-1 step 5.1.2a

  • PLACE STANDBY EHC Fluid pump into operation by first DEPRESSING CF PMP A/B/C START pushbutton

, (1) THEN DEPRESS respective Auto pushbutton.

Standard: Starts EHC pump C

. Cue: Notes: SAT / UNSAT Step 3: 04-1-01-N32-1 step 5.1.2b OBSERVE that discharge pressure on EHC Fluid pump just started is approximately the same as the other running pumps by MONITORING applicable local pressure indicators:

CF PMP A, 1N32

-PI-R006A (low pressure) 1N32-PI-R018A (high pressure)

CF PMP B, 1N32

-PI-R006B (low pressure) 1N32-PI-R018B (high pressure)

CF PMP C, 1N32

-PI-R006C (low pressure) 1N32-PI-R018C (high pressure)

Standard: Directs the local operator to observe EHC pump discharge pressures.

Cue: As the local operator, report the low and high discharge pressures are normal for EHC pump C and are approximately the same as discharge pressures of EHC pumps A and B.

Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-N3201 Revision: 0 Page: 6 of 11 Step 4: 04-1-01-N32-1 step 5.1.2c

  • SHUT DOWN one of the running EHC Fluid pumps by DEPRESSING CF PMP A/B/C STOP pushbutton on 1H13-P680-10C. WAIT approximately 30 seconds, THEN DEPRESS applicable CF PMP A/B/C AUTO pushbutton.
  • OBSERVE that CF PRESS HP SIDE AND CF PRESS LP SIDE remain at greater than 445 psig AND 175 psig respectively on 1H13

-P680-10B. Clear annunciator "CF PMP SWITCH TO AUTO," 1H13

-P680-10A (C-5). Standard: Stops EHC pump A.

Cue: When the operator reports abnormal control fluid pressures as a result of the pump shift, direct the operator

as the CRS to shift EHC pumps to EHC pumps A and B running with EHC pump C in standby.

Notes: A malfunction will be inserted when EHC Pump A is stopped. This will cause pump discharge pressure to drop to 410 psig and 150 psig.

Simulator Operator Trigger Event 10 when the operator stops EHC pump A.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-N3201 Revision: 0 Page: 7 of 11 Step 5: 04-1-01-N32-1 step 5.1.2a

  • PLACE STANDBY EHC Fluid pump into operation by first DEPRESSING CF PMP A/B/C START pushbutton

, (1) THEN DEPRESS respective Auto pushbutton. Standard: Starts EHC pump A.

Cue: Notes: EHC pressures will return to normal.

Simulator Operator Trigger Event 1 1 when the operator starts EHC pump A.

- OR - manually adjust AO_1N32R612 to 577 in 30 seconds manually adjust AO_1N32R627 to 198 in 30 seconds

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-N3201 Revision: 0 Page: 8 of 11 Step 6: 04-1-01-N32-1 step 5.1.2b OBSERVE that discharge pressure on EHC Fluid pump just started is approximately the same as the other running pumps by MONITORING applicable local pressure indicators:

CF PMP A, 1N32

-PI-R006A (low pressure) 1N32-PI-R018A (high pressure)

CF PMP B, 1N32

-PI-R006B (low pressure) 1N32-PI-R018B (high pressure)

CF PMP C, 1N32

-PI-R006C (low pressure) 1N32-PI-R018C (high pressure)

Standard: Directs the local operator to observe EHC pump discharge pressures.

Cue: As the local operator, report the low and high discharge pressures are normal for EHC pump A and are approximately the same as discharge pressures of EHC pumps A and C.

Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-N3201 Revision: 0 Page: 9 of 11 Step 7: 04-1-01-N32-1 step 5.1.2c

  • SHUT DOWN one of the running EHC Fluid pumps by DEPRESSING CF PMP A/B/C STOP pushbutton on 1H13

-P680-10C. WAIT approximately 30 seconds, THEN DEPRESS applicable CF PMP A/B/C AUTO pushbutton.

OBSERVE that CF PRESS HP SIDE AND CF PRESS LP SIDE remain at greater than 445 psig AND 175 psig respectively on 1H13

-P680-10B. Clear annunciator "CF PMP SWITCH TO AUTO," 1H13

-P680-10A (C-5). Standard: Stops EHC pump C.

Cue: As the CRS, prompt the operator to secure EHC pump C.

Notes: This ends the JPM.

SAT / UNSAT Task Standard(s)

EHC Pump A has been placed back into operation and EHC Pump C has been returned to standby in accordance with 04 01-N32-1 section 5.1 after it was determined EHC Pump C would not maintain normal control fluid pressures.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-N3201 Revision: 0 Page: 10 of 11 Task: Rotate EHC Pumps

- Pump A to Pump C Follow-Up Questions & Answers

Comments:

Give this page to the student Initial Condition(s):

The plant is at rated power.

EHC pumps A and B are in operation.

Initiating Cue(s):

The CRS has directed you to rotate from EHC pump A to EHC pump C, such that EHC pumps B and C are left in operation, in accordance with 04 01-N32-1 section 5.1.

An operator is at the EHC pumps standing by for instructions.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E1201 Revision: 3 Page: 1 of 9 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-CR 4 Time Critical Alternate Path Validation Time:

1 5 min TITLE: Startup Shutdown Cooling B New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

Revised JPM to include new procedure steps added by procedure revision.

THIS DOCUMENT REPLACES

GJPM-OPS-E1201 Rev 2 REVIEW / APPROVAL (Print Name):

TEAR Approval (

) Prepared By:

Jonathan W. Sparks 3/17/10 **Preparer Date Ops Review

++: Keith Huff 9/28/2011 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Chris Laird 9/28/2011 Training Representative Date Approved By:

Kane Ryder 9/28/2011 +Discipline Training Supervisor Date Approval Date:*

9/28/2011

  • Indexing Information
    • The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.

++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS) 04-1-01-E12-2 Rev 112 ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E1201 Revision: 3 Page: 2 of 9 Task: Startup Shutdown Cooling B Setting: Simulator Type: RO Task: CRO-E12-008 K&A: 205000 A4.01

- 3.7/3.7; A4.02

- 3.6/3.5; A4.03

- 3.6/3.5 Safety Function

4 Time Required
15 minutes Time Critical
No Faulted: No Performance
Actual Reference(s): 04-1-01-E12-2 sect 4.2.2c Handout(s)
None # Manipulations
6 # Critical Steps
6 Group: 1 Simulator Setup/Required Plant Conditions
Initialize the simulator to IC 3 Reactor in Mode 4 < 200 degrees F Verify/start SSW B in operation to the RHR B heat exchangers.

Secure the RHR Shutdown Cooling lineup.

o Stop the B RHR pump.

o Close/Verify Closed:

B21-F065A and F065B; E12- F004B; F008; F064B; F009; F053B and F006B o Shutdown the B RHR Jockey Pump.

Verify/start RHR Room B Fan Coil Unit.

Place the RHR B MOV TEST switch in TEST.

Safety Concerns

None ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E1201 Revision: 3 Page: 3 of 9 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

RHR B was previously in service for Shutdown Cooling but was secured.

Radiation Protection and Chemistry personnel have been notified of the startup of RHR 'B' Shutdown Cooling.

RHR B has been flushed, warmed up and is ready to be placed in Shutdown Cooling. SSW B is in operation.

ADHR is not in operation.

RHR Room B Fan Coil Unit is running. The B RHR Jockey Pump has been secured.

The RHR B MOV TEST switch in TEST.

Initiating Cue(s):

You have been directed to place RHR B in Shutdown Cooling through E12

-F053B, starting at Step 4.2.2c(12) of SOI 04 01-E12-2. Establish RHR flow with E12

-F003B closed and E12-F048B open.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E1201 Revision: 3 Page: 4 of 9 Task: Startup Shutdown Cooling B Notes: (Notes to Evaluator)

1. All controls will be from panels P601 and P680 in the Main Control Room.
2. Unless otherwise indicated, all valves are in the "E12" system.

Task Overview:

(Detailed description of task)

This task places the RHR system in service for Shutdown Cooling using the normal (E12-F053B) flow path. This is a Tech Spec Decay Heat Removal method. Throttling of RHR Shutdown Cooling flow caused damage to RHR Instrumentation piping during RF12. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E1201 Revision: 3 Page: 5 of 9 Step 1: 04-1-01-E12-2 step 4.2.2c(12)

  • OPEN OR CHECK OPEN the following valves:

F010 (Concurrent Verification Required)

  • F008
  • F009
  • F006B F047B F048B Standard: Open or Check open valves, observing red lights on and green lights off. For E12

-F048B observe valve position indication is at 100%. Cue: If asked, concurrent verification of E12

-F010 was performed.

Notes: E12-F008, E12-F009 and E12

-F006B need to be operated. The remaining valves are already open and need only observe indication as such.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E1201 Revision: 3 Page: 6 of 9 Step 2: 04-1-01-E12-2 step 4.2.2c(13)

. Standard: Close valve, observing valve position indication moves to 0%.

Cue: Notes:

SAT / UNSAT Step 3: 04-1-01-E12-2 step 4.2.2c(14)

CLOSE OR CHECK CLOSED B21-F065B, FW INL SHUTOFF VLV.

Standard: See Cue and Notes below. Check valve closed, observing red light off and green light on.

Cue: Inform the operator as the ACRO that B21

-F065B is closed.

Notes: Be mindful of other JPMs occurring in the simulator not to compromise exam security.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E1201 Revision: 3 Page: 7 of 9 Step 4: 04-1-01-E12-2 step 4.2.2c(1 7)

  • START RHR PMP B AND IMMEDIATELY FULLY OP EN one of the following valves:
  • E12-F053B, RHR B SHUTDN CLNG RTN TO FW.

Standard: Starts RHR pump and opens E12

-F053B, observing red lights on and green lights off.

Cue: This completes the JPM.

Notes: This step offers three valves to open. E12

-F037B and E12-F042B are the wrong valves and should not be operated. Steps 4.2.2c(15

-16) are NA since the operator will be using option 1 from the note prior to 4.2.2c(15).

SAT / UNSAT

Task Standard(s)

Shutdown Cooling B is started IAW SOI 04 01-E12-2. SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E1201 Revision: 3 Page: 8 of 9 Task: Startup Shutdown Cooling B Follow-Up Questions & Answers

Comments:

Give this page to the student Initial Condition(s):

RHR B was previously in service for Shutdown Cooling but was secured.

Radiation Protection and Chemistry personnel have been notified of the startup of RHR 'B' Shutdown Cooling. RHR B has been flushed, warmed up and is ready to be placed in Shutdown Cooling. SSW B is in operation.

ADHR is not in operation.

RHR Room B Fan Coil Unit is running.

The B RHR Jockey Pump has been secured.

The RHR B MOV TEST switch in TEST.

Initiating Cue(s):

You have been directed to place RHR B in Shutdown Cooling through E12

-F053B, starting at Step 4.2.2c(12) of SOI 04 01-E12-2. Establish RHR flow with E12

-F003B closed and E12-F048B open.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E 3013 Revision: 1 Page: 1 of 9 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-CR 5 Time Critical Alternate Path Validation Time:

5 min TITLE: Manually Initiate Suppression Pool Make Up New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

Remove Generic Instructions Sheet. This was removed from 14-S-2-18 THIS DOCUMENT REPLACES
GJPM-OPS-E3013 Rev 0 REVIEW / APPROVAL (Print Name):

TEAR Approval ( )

Prepared By:

Jonathan W. Sparks 11/24/09 **Preparer Date Ops Review

++: Keith Huff 9/28/2011 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Chris Laird 9/28/2011 Training Representative Date Approved By:

Kane Ryder 9/28/2011 +Discipline Training Supervisor Date Approval Date:*

9/28/2011

  • Indexing Information
    • The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.

++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS) 04-1-01-E12-2 Rev 112 ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E 3013 Revision:

1 Page: 2 o f 9 Task: Manually Initiate Suppression Pool Make Up Setting: Simulator Type: RO Task: CRO-E30-003 K&A: 223001 A2.11: 3.6/3.8 295030 EA1.04: 4.0/4.0 Safety Function

5 Time Required
5 minutes Time Critical
No Faulted: N o Performance: Actual Reference(s)
04-1-01-E30-1 Attachment V Handout(s)
None # Manipulations
4 # Critical Steps
4 Group #: 1 Simulator Setup/Required Plant Conditions
Reset to any IC other than Refuel (IC 3) Lower Suppression Pool Level to 18.1 feet. Set the following annunciators to card pulled:

o P680-4A2-A-6 o P680-4A2-C-7 o P680-4A2-D-6 o P601-16A-C-5 o P601-21A-C-5 Safety Concerns

None ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E 3013 Revision:

1 Page: 3 o f 9 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

Suppression Pool Level has dropped to 18.13 feet and is continuing to lower due to a leak in the RHR A Pump Room.

Repairs to the leaking pipe are in progress.

Emergency Procedure EP

-3 has been entered.

Initiating Cue(s):

You have been directed to manually initiate both divisions of Suppression Pool Make Up to raise Suppression Pool Water Level.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E 3013 Revision:

1 Page: 4 o f 9 Task: Manually Initiate Suppression Pool Make Up Notes: (Notes to Evaluator)

1. All Control Room operations will be on panel P870.

Task Overview:

(Detailed description of task)

This task is to manually initiate Suppression Pool Make Up per directions from EOP

-2 Containment Control. This is done per 04 01-E30-1 Attachment V from the Control Room to raise Suppression Pool Water Level.

Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E 3013 Revision:

1 Page: 5 o f 9 Step 1: 04-1-01-E30-1 Att. V Division 1 Place the SPMU MODE SEL handswitch to AUTO Standard: Verifies that the mode switch is in AUTO.

Cue: Notes: SAT / UNSAT Step 2: 04-1-01-E30-1 Att. V Division 1

  • Place the SPMU DUMP TEST handswitch to TEST

. Standard: Place switch in test, observing amber light above switch on.

Cue: Notes:

SAT / UNSAT Step 3: 04-1-01-E30-1 Att. V Division 1

  • Simultaneously depress both SPMU MAN INIT pushbuttons

. Standard: Place switch in test, observing amber light above switch on.

Cue: Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E 3013 Revision:

1 Page: 6 o f 9 Step 1: 04-1-01-E30-1 Att. V Division 2 Place the SPMU MODE SEL handswitch to AUTO Standard: Verifies that the mode switch is in AUTO.

Cue: Notes: SAT / UNSAT Step 2: 04-1-01-E30-1 Att. V Division 2

  • Place the SPMU DUMP TEST handswitch to TEST

. Standard: Place switch in test, observing amber light above switch on.

Cue: Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E 3013 Revision:

1 Page: 7 o f 9 Step 3: 04-1-01-E30-1 Att. V Division 2

  • Simultaneously depress both SPMU MAN INIT pushbuttons

. Standard: Place switch in test, observing amber light above switch on.

Cue: This ends the task.

Notes: SAT / UNSAT Task Standard(s)

Suppression Pool Make Up Valves E30

-F001A & B and E30

-F002A & B are open in accordance with 04 01-E12-2 attachment V

. SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-E 3013 Revision:

1 Page: 8 o f 9 Task: Manually Initiate Suppression Pool Make Up Follow-Up Questions & Answers

Comments:

Give this page to the student Initial Condition(s):

Suppression Pool Level has dropped to 18.13 feet and is continuing to lower due to a leak in the RHR A Pump Room.

Repairs to the leaking pipe are in progress.

Emergency Procedure EP

-3 has been entered.

Initiating Cue(s):

You have been directed to manually initiate both divisions of Suppression Pool Make Up to raise Suppression Pool Water Level.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C7105 Revision: 0 Page: 1 of 10 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-CR6 Time Critical Alternate Path Validation Time:

15 min TITLE: Reactor Manual Scram Switch Test New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

THIS DOCUMENT REPLACES
REVIEW / APPROVAL (Print Name):

TEAR Approval ( )

Prepared By:

Mark Pait 5/2 4/2011 **Preparer Date Ops Review

++: Chris Laird 9/26/2011 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Keith Huff 9/27/2011 Training Representative Date Approved By:

Kane Ryder 9/28/2011 +Discipline Training Supervisor Date Approval Date:*

9/28/2011

  • Indexing Information ** The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklis

t. ++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS) 04-1-01-T42-1 Rev 28 ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C7105 Revision: 0 Page: 2 of 10 Task: Reactor Manual Scram Switch Test Setting: Simulator Type: RO Task: CRO-C71-OFFNORM-005 K&A: 212000: A2.03 - 3.3/3.5 Safety Function

7, Instrumentation Time Required
15 minutes Time Critical
No Faulted: Yes Performance
Actual Reference(s)
06-OP-1C71-W-0001 Handout(s)
Copy of 06

-OP-1C71-W-0001 # Manipulations

5 # Critical Steps
4 Group: 1 Simulator Setup/Required Plant Conditions
Load any 100% IC (prefer IC 31)

Open and Run schedule file GJPM

-OPS-2011CR7 Safety Concerns

None ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C7105 Revision: 0 Page: 3 of 10 Name: ___________________________

Time Start: _______

Time Stop: __

_____ Initial Condition(s):

The plant is operating at rated power.

Initiating Cue(s):

The CRS has directed you to perform 06

-OP-1C71-W-0001. All prerequisites are verified met.

Start with Data Sheet 1 and go in order through Data Sheet 4.

This task is not time critical.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C7105 Revision: 0 Page: 4 of 10 Task: Reactor Manual Scram Switch Test Notes: (Notes to Evaluator)

The task is complete when: Reactor core flow is lowered to 67 mlbm/hr and the operator determines the reactor is operating in the Monitored Region of the Power to Flow Map.

Task Overview:

(Detailed description of task)

The operator will perform 06

-OP-1C71-W-0001 (Reactor Manual Scram Switch Test). When the operator depresses the first manual scram switch, two control rods (08-41 and 24-49) will scram due to a blown pilot solenoid fuse on the individual HCU units.

The operator should recognize two scramed rods and lower core flow to 67 mlbm/hr and plot reactor power and core flow on the Power to Flow Map.

Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 06-OP-1C71-W-0001 step 5.1 OBTAIN Shift Supervision's permission to start. Performer to RECORD Test Start Time on Data Package Cover Sheet.

Standard: Records the start time on the Surveillance Cover Shee

t. Cue: If the operator asks permission to begin the surveillance, inform the operator that the CRS has given permission to begin. Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C7105 Revision: 0 Page: 5 of 10 Step 2: 06-OP-1C71-W-0001 Data Sheet 1 step 5.2 VERIFY the following lights are ON to ensure that NO RPS trip signals are present: RPS DIV 1 SCRAM SOL VLV 1A AND 1B lights ON (5C1)

RPS DIV 2 SCRAM SOL VLV 2A AND 2B lights ON (7C1)

RPS DIV 3 SCRAM SOL VLV 3A AND 3B lights ON (5C1)

RPS DIV 4 SCRAM SOL VLV 4A AND 4B lights ON (7C1)

Standard: Observes white scram solenoid valve lights lit

. Cue: Notes:

SAT / UNSAT

Step 3: 06-OP-1C71-W-0001 Data Sheet 1 step 5.3

  • ARM the Div 1 MAN SCRAM Switch (5C1) by rotating the collar clockwise. VERIFY alarm RPS MAN SWITCH PERM is received (5A

-B3) RPS MAN SWITCH SCRAM PERM alarm is ON Standard: Rotates switch collar.

Cue: Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C7105 Revision: 0 Page: 6 of 10 Step 4: 06

-OP-1C71-W-0001 Data Sheet 1 step 5.4

  • Depress the MAN SCRAM Switch which was previously Armed.

Standard: Depress MAN SCRAM Switch.

Cue: Notes: When the manual scram switch is depressed, two control rods will scram.

SAT / UNSAT Step 5: 06

-OP-1C71-W-0001 Data Sheet 1 step 5.5 VERIFY the following:

RPS SCRAM SOL VLVs lights 1A, 3A, on (5C1) AND 2A, 4A on (7C1) are OFF RPS SCRAM SOL VLVs lights 1B, 3B, on (5C1)

AND 2B, 4B on (7C1) are ON RX SCRAM TRIP alarm is received (7A

-A2) RX MAN SCRAM TRIP alarm is received (7A

-A3) Standard: Observes indications listed

. Cue: Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C7105 Revision: 0 Page: 7 of 10 Step 6: 06

-OP-1C71-W-0001 Data Sheet 1 step 5.5.4

AND VERIFY that NO scram valves are Open, as indicated by a green LED being OFF for all CRD/HCUs on the rod display map (6D) that are NOT tagged out.

Standard: Determines that tw o Control have scramed.

Cue: Notes: Control Rods 08

-41 and 24-49 have scramed.

Once the operator determines that rods have scramed the operator should enter the Control Rod/Drive Malfunctions ONEP.

SAT / UNSAT Step 7: Control Rod/Drive Malfunctions ONEP step 2.4

  • Reduce Reactor core flow to 67 mlbm/hr.

Standard: Lowers core flow using both Recirc flow control valves in fast detent to 67 mlbm/hr (02

-S-01-27 6.5.6).

Cue: Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C7105 Revision: 0 Page: 8 of 10 Step 8: Operation's Philosophy step 6.6.7 Plot reactor power and core flow on the Power to Flow Map.

Standard: Plots power and flow.

Cue: This completes the task.

Notes:

SAT / UNSAT Task Standard(s)

Reactor core flow is lowered to 67 mlbm/hr and the operator determines the reactor is operating in the Monitored Region of the Power to Flow Map per 05-1-02-IV-1. SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C7105 Revision: 0 Page: 9 of 10 Task: Reactor Manual Scram Switch Test Follow-Up Questions & Answers

Comments:

Give this page to the student Initial Condition(s):

The plant is operating at rated power.

Initiating Cue(s):

The CRS has directed you to perform 06

-OP-1C71-W-0001. All prerequisites are verified met.

Start with Data Sheet 1 and go in order through Data Sheet 4.

This task is not time critical.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-P4271 Revision:

2 Page: 1 of 10 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-CR7 Time Critical Alternate Path Validation Time:

1 0 min TITLE: Rotate CCW Pumps New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

Remove Generic Instructions Sheet. This was removed from 14-S-2-18. THIS DOCUMENT REPLACES
GJPM-OPS-P4271 Rev. 1 REVIEW / APPROVAL (Print Name):

TEAR Approval ( )

Prepared By: Jonathan W. Sparks 12/7/09 **Preparer Date Ops Review

++: Chris Laird 10/4/11 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Keith Huff 10/4/11 Training Representative Date Approved By:

Kane Ryder 10/4/11 +Discipline Training Supervisor Date Approval Date:*

10/4/11

  • Indexing Information
    • The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.

++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS) 04-1-01-P42-1 Rev 47 ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-P4271 Revision: 2 Page: 2 of 10 Task: Rotate CCW Pumps Setting: Simulator Type: RO Task: CRO-P42-007; CRO-P42-004 K&A: 400000 2.1.30: 3.9/3.4; 2.1.31: 4.2/3.9; A4.01: 3.1/3.0; A2.01: 3.3/3.4 295018 AK3.04: 3.3/3.3; AA1.01: 3.3/3.4 Safety Function

Plant Service Systems (8)

Time Required

10 minutes Time Critical: No Faulted: YES Performance
Perform Reference(s)
SOI 04-1-01-P42-1 section 5.2; ONEP 05 02-V-1 section 3.1.1 Handout(s)
SOI 04-1-01-P42-1; ONEP 05 02-V-1 # Manipulations
4 # Critical Steps
4 Group #: 2 Simulator Setup/Required Plant Conditions
Initialize the simulator to any IC (IC-43). Insert Malfunction p42151c CCW Pump C Trip on a unique trigger number (event 1). Ensure CCW Pumps 'A' and 'C' are operating with CCW Pump 'B' in Standby.

Safety Concerns

None ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-P4271 Revision: 2 Page: 3 of 10 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

Electrical Maintenance has requested Component Cooling Water (CCW) Pump A be secured in preparation for preventive maintenance.

CCW Pumps A and C are currently in operation.

Initiating Cue(s):

The CRS directs you to rotate CCW pumps to have CCW Pumps B and C operating, with CCW Pump A secured, per SOI 04 01-P42-1 section 5.2

. An operator is standing by at the CCW pumps ready to rotate pumps.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-P4271 Revision: 2 Page: 4 of 10 Task: Rotate CCW Pumps Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

This task is to rotate CCW Pumps per SOI. During the evolution, a trip will occur on one of the operating CCW pumps requiring the restart of the non-operating CCW pump per the Loss of CCW ONEP. This is an Alternate Path JPM. This is a task that is coordinated from the control room.

Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 04-1-01-P42-1 step 5.2.2a REMOVE Standby pump from STANDBY by PLACING respective pump handswitch listed below to STOP. Standard: Places CCW pump B HS to STOP

. Cue: Notes: Step 5.2.1 prerequisites are met.

SAT / UNSAT Step 2: 04-1-01-P42-1 step 5.2.2b

  • AFTER white STANDBY light for pump goes out, START CCW pump using its respective handswitch listed in Step 5.2.2a.

Standard: Starts CCW pump B.

Cue: If asked to perform pre

-start pump checks, report that pre

-start pump check is performed sat. Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-P4271 Revision: 2 Page: 5 of 10 Step 3: 04-1-01-P42-1 step 5.2.2c CLOSE discharge valve for pump to be shut down.

Standard: Contacts local operator to close P42

-F016A CCW pump A discharge valve.

Cue: Report as local operator P42

-F016A is closed.

Notes: SAT / UNSAT Step 4: 04-1-01-P42-1 step 5.2.2d

  • STOP CCW pump to be placed in STANDBY using its respective handswitch listed in Step 5.2.2
a. Standard: Stops CCW pump A.

Cue: After the trip annunciator comes into alarm, inform the operator as the local operator that a small amount of water is spraying from the CCW C pump seal. CCW pump B and C are getting wet.

The CRS directs you to take Immediate and Subsequent actions per the loss of CCW ONEP

.

If the operator attempts to go to the P680, inform the operator that another operator will perform actions at the P680. Notes: When the operator stops CCW pump A, CCW pump C will trip causing a partial loss of CCW flow.

Simulator Operator, Trip CCW pump C when the CCW pump A has been secured

. SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-P4271 Revision: 2 Page: 6 of 10 Step 5: 05-1-02-V-1 Loss of CCW ONEP step 3.1.1

  • Contact the local operator to open P42

-F016A CCW Pump 'A' discharge valve.

Standard: Contacts local operator to open P42

-F016A. Cue: CCW Pump 'A' discharge valve P42

-F016A is open.

Notes: There are no required immediate actions for the Loss of CCW ONEP.

Do NOT allow the operator to scram the reactor! This task is not critical if P42

-F016A was not previously closed. Step 5 &6 can be done in either order.

SAT / UNSAT Step 6: 05-1-02-V-1 Loss of CCW ONEP step 3.1.1

  • START CCW pump A

. Standard: Start CCW pump A.

Cue: Terminate the JPM Notes: Once the operator moves beyond step 3.1.1 "Verify standby CCW pump starts or start manually" end the JPM.

SAT / UNSAT Task Standard(s)

CCW Pumps 'A' and 'B' are operating with discharge valves open per 05-1-02-V-1. SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-P4271 Revision: 2 Page: 7 of 10 Task: Rotate CCW Pumps Follow-Up Questions & Answers

Comments:

Give this page to the student Initial Condition(s):

Electrical Maintenance has requested Component Cooling Water (CCW) Pump A be secured in preparation for preventive maintenance.

CCW Pumps A and C are currently in operation.

Initiating Cue(s):

The CRS directs you to rotate CCW pumps to have CCW Pumps B and C operating, with CCW Pump A secured, per SOI 04 01-P42-1 section 5.2

. An operator is standing by at the CCW pumps ready to rotate pumps

.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-T4803 Revision:

0 Page: 1 of 12 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-CR8 Time Critical Alternate Path Validation Time:

20 min TITLE: Secure SGTS with One Train in Standby Mode following Automatic Initiation New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

THIS DOCUMENT REPLACES
REVIEW / APPROVAL (Print Name):

TEAR Approval ( )

Prepared By:

Kyle Grillis 12/7/09 **Preparer Date Ops Review

++: Mark Goodwin 10/4/11 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Keith Huff 10/4/11 Training Representative Date Approved By:

Kane Ryder 10/4/11 +Discipline Training Supervisor Date Approval Date:* 10/4/11

  • Indexing Information
    • The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-20 1- DD06, Training Material Checklist.

++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS) 04-1-01-T48-1 Rev 32 ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-T4803 Revision: 0 Page: 2 of 1 2 Task: Security SGTS with One Train in Standby Mode following Automatic Initiation Setting: Simulator Type: RO Task: CRO-T48-004 K&A: 261000 A4.03: 3.0/3.0; Generic 2.1.30: 4.4/4.0 Safety Function

9 - Radioactivity Release Time Required
20 minutes Time Critical
No Faulted: No Performance
Actual Reference(s)
04-1-01-T48-1 section 5.3 Handout(s)
None # Manipulations
18 # Critical Steps
16 Group: 1 Simulator Setup/Required Plant Conditions
Reset to any IC with no SGTS initiation signal Insert Malfunction rm157o and rm157n, once actions have gone to completion delete the malfunctions.

Perform the following on P870

-2B, 2C to place SGTS A in Standby Mode:

PLACE SGTS DIV 1 MODE SEL handswitch on (P870

-2B) to STBY position

. TURN SGTS DIV 1 MAN INIT RESET key

-locked handswitch to RESET position and back to NORM, to reset automatic or manual initiation signal.

PLACE handswitch for ENCL BLDG RECIRC FAN A(B) to STOP.

PLACE handswitch for SGTS FLTR TR A(B) EXH FAN to STOP.

Silence and acknowledge alarms after annunciator SGTS DIV 2 OPER (P87 0-8A-A3) has alarmed.

Safety Concerns

None ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-T4803 Revision: 0 Page: 3 of 1 2 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant is at rated power.

Standby Gas Treatment Systems A and B automatically initiated due to a momentary spike of Fuel Pool Sweep Exhaust Radiation monitors during movement of spent LPRMs on the refuel floor.

The initiating condition is now clear, Fuel Pool Sweep Exhaust Radiation levels are normal.

SGTS A has been placed in Standby Mode using its mode selector switch in accordance with

04-1-01-T48-1 step 5.2.2e.

SGTS B is operating.

Jumpers have not been installed to enable restarting Auxiliary Building fan coil units.

Initiating Cue(s):

The SRO with the Command Function has directed you to shutdown the system, returning SGTS A and B to normal alignment, in accordance with 04 01-T48-1 section 5.3.

Another operator will pick up at step 5.3.2p and restart normal ventilation system fans.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-T4803 Revision: 0 Page: 4 of 1 2 Task: Security SGTS with One Train in Standby Mode following Automatic Initiation Notes: (Notes to Evaluator)

1. All controls will be from panel P870.

Task Overview:

(Detailed description of task)

This task secures SGTS B following automatic initiation and reopens ventilation system isolation valves. SGTS A has already been secured to Standby Mode as an initial condition.

Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 04-1-01-T48-1 step 5.3.2b PLACE SGTS DIV 1(2) MOV TEST switch (P870

-2B) in TEST.

VERIFY annunciator "SGTS DIV 1(2) MOVS IN TEST MODE" is Alarmed.

VERIFY SGTS D1(D2) MOV IN TEST STATUS light is on.

Standard: Place S GTS Div 2 MOV TEST switch in TEST

. Cue: Notes: Step 5.3.1 prerequisites are met and 5.3.2a is NA.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-T4803 Revision: 0 Page: 5 of 1 2 Step 2: 04-1-01-T48-1 step 5.3.2c PLACE the following handswitches to STOP on 1H13P842:

Standard: Cue: Another operator has placed the handswitches in STOP.

Notes: The P842 is not modeled in the simulator.

SAT / UNSAT Step 3: 04-1-01-T48-1 step 5.3.2d

  • IF one SGTS train is in standby, THEN PERFORM the follow:
  • PLACE SGTS DIV 1(2) MODE SEL key locked handswitch for Standby filter train to AUTO position. VERIFY SGTS DIV 1(2) MODE SEL handswitch white light is lit.

VERIFY SGTS DIV 1(2) IN STBY MODE annunciator clears.

Standard: Place SSTS Div 2 MODE SEL switch in AUTO.

Cue: Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-T4803 Revision: 0 Page: 6 of 1 2 Step 4: 04-1-01-T48-1 step 5.3.2e-f

  • Turn SGTS DIV 1(2) MAN INIT RESET key locked handswitch to RESET position and back to NORM, to reset automatic or manual initiation signal.

VERIFY annunciator "SGTS DIV 1(2) OPER" clears.

Standard: Resets SGTS Div 2 initiation logic.

Cue: Notes: SAT / UNSAT Step 5: 04-1-01-T48-1 step 5.3.2g

  • Place handswitch for SGTS FLTR TR A(B) EXH FAN to STOP.

Standard: Stops SGTS B filter train exhaust fan.

Cue: Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-T4803 Revision: 0 Page: 7 of 1 2 Step 6: 04-1-01-T48-1 step 5.3.2h

  • Place handswitch for ENCL BLDG RECIRC FAN A(B) to STOP.

Standard: Stops SGTS B enclosure building recirc fan.

Cue: Notes: SAT / UNSAT Step 7: 04-1-01-T48-1 step 5.3.2i OBSERVE filter train chart recorders deenergize and Enclosure Building pressure chart recorders transfer to slow speed.

Standard: Verify chart recorders operate correctly.

Cue: Notes:

SAT / UNSAT Ste p 8: 04-1-01-T48-1 step 5.3.2j VERIFY that all SGTS A(B) dampers on 1H13

-P870-2C(8C), are CLOSED.

Standard: Verify SGTS Div 2 dampers close.

Cue: Notes: Damper numbers: T48

-F002,3,5,8,10,12,14,16,18,20, and 22.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-T4803 Revision: 0 Page: 8 of 1 2 St ep 9: 04-1-01-T48-1 step 5.3.2k VERIFY "FLTR TR A(B) EXH FAN INL VANE" on 1H13

-P870-2C(8C) is OPEN. Standard: Verify SGTS Div 2 exhaust fan inlet vane opens

. Cue: Notes:

SAT / UNSAT Step 10: 04-1-01-T48-1 step 5.3.2l RECORD stop time(s) in the Accumulative Log Book.

Standard: Cue: Another operator will complete log book entry.

Notes: Accumulative Log Book is kept at SM desk in the control room and is not modeled in the simulator.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-T4803 Revision: 0 Page: 9 of 1 2 Step 11: 04-1-01-T48-1 step 5.3.2m PLACE SGTS DIV 1(2) MOV TEST switch in NORM.

VERIFY annunciator "SGTS DIV 1(2) MOVS IN TEST MODE" is clear.

VERIFY SGTS D1(D2) MOV IN TEST STATUS light is off. Standard: Place MOV TEST switch to NORM.

Cue: Notes: SAT / UNSAT Step 12: 04-1-01-T48-1 step 5.3.2n

  • IF SGTS A was secured, THEN OPEN the following dampers:
  • 1T42F011
  • 1T42F019
  • 1T42F004
  • 1M41F008
  • 1M41F036

Cue: Notes: Dampers located on P870

-2C SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-T4803 Revision: 0 Page: 10 of 1 2 Step 13: 04-1-01-T48-1 step 5.3.2o

  • IF SGTS B was secured, THEN OPEN the following dampers:
  • 1T42F01 2
  • 1T42F0 20
  • 1T42F00 3
  • 1M41F00 7
  • 1M41F03 7
  • 1T42F00 6 Standard: Open dampers. Cue: When complete, End of JPM.

Notes: Dampers located on P870

-8C SAT / UNSAT

Task Standard(s)

Standby Gas Treatment Systems A and B are shutdown and have been placed in normal standby alignment and normal ventilation isolation dampers have been reopened IAW 04 01-T48-1 section 5.3.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-T4803 Revision: 0 Page: 11 of 1 2 Task: Security SGTS with One Train in Standby Mode following Automatic Initiation Follow-Up Questions & Answers

Comments:

Give this page to the student Initial Condition(s):

The plant is at rated power. Standby Gas Treatment Systems A and B automatically initiated due to a momentary spike of Fuel Pool Sweep Exhaust Radiation monitors during movement of spent LPRMs on the refuel floor.

The initiating condition is now clear, Fuel Pool Sweep Exhaust Radiation levels are normal.

SGTS A has been placed in Standby Mode using its mode selector switch in accordance with

04-1-01-T48-1 step 5.2.2e.

SGTS B is operating.

Jumpers have not been installed to enable restarting Auxiliary Building fan coil units.

Initiating Cue(s):

The SRO with the Command Function has directed you to shutdown the system, returning SGTS A and B to normal alignment, in accordance with 04 01-T48-1 section 5.3.

Another operator will pick up at step 5.3.2p and restart normal ventilation system fans.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP23 Revision:

1 Page: 1 of 8 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-PS1 Time Critical Alternate Path Validation Time:

20 min TITLE: Manually Vent the SCRAM Air Header New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

Remove Generic Instructions Sheet. This was removed from 14-S-2-18. THIS DOCUMENT REPLACES
GJPM-OPS-EOP023 Rev 0 REVIEW / APPROVAL (Print Name):

TEAR Approval ( )

Prepared By:

Jonathan W. Sparks 11/25/09 **Preparer Date Ops Review

++: Keith Huff 9/26/2011 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Chris Laird 9/26/2011 Training Representative Date Approved By:

Kane Ryd er 9/28/2011 +Discipline Training Supervisor Date Approval Date:*

9/28/2011

  • Indexing Information
    • The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.

++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS) 04-1-01-P42-1 Rev 47 ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP023 Revision: 1 Page: 2 of 8 Task: Manually Vent the SCRAM Air Header Setting: Plant (Inside CAA)

Type: NLO Task: AON-EP-004 K&A: 295015 AA1.01: 3.8/3.9 Safety Function: 1 - Reactivity Control Time Required

20 minutes Time Critical
No Faulted: No Performance
Simulate Reference(s)
05-S-01-EP-1/Att. 23 Handout(s)
Copy of EOP Att. 23
  1. Manipulations
5 # Critical Steps
6 Group #: 1 Simulator Setup/Required Plant Conditions
Containment HCU floor at Area 11, 135' is accessible Safety Concerns
Wear appropriate personal protective equipment.

Don't forget ALARA No climbing. Point up or down while you explain what you are going to do.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP023 Revision: 1 Page: 3 of 8 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

EOP's have been entered.

Initiating Cue(s):

The CRS directs you to perform steps 2.1 through 2.

4 of EP Attachment 23.

Another operator will complete the remaining steps of this attachment when directed.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP023 Revision: 1 Page: 4 of 8 Task: Manually Vent the SCRAM Air Header Notes: (Notes to Evaluator)

1. This task is performed on the HCU floor in Containment, El. 135'.
2. The valves and pipe plugs are located just south and west of the Hydraulic Control Station, near the Backup Scram Valves.

Task Overview:

(Detailed description of task)

This task provides an alternate method of venting the scram air header to allow control rod insertion. The task consists of physically removing of pipe plugs located on the scram air header using a hack saw, allowing the scram air header to depressurize.

The scram pilot valves would fail open due to a loss of air pressure, allowing the control rods to insert into the reactor.

Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: EOP Att. 23 step 2.1

  • OBTAIN tools from the Control Room emergency locker.

Standard: Verbalizes that the EP kit for Att. 23 is in the Control Room.

Cue: You have the hacksaw from the EP Att. 23 kit.

Notes: In order to meet the critical task, the operator need only verbalize that he has/would obtain a hack saw.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP023 Revision: 1 Page: 5 of 8 Step 2: EOP Att. 23 step 2.2

Standard: Simulate turning CW to close

. Cue: Resistance is felt in the CW direction. Notes: SAT / UNSAT Step 3: EOP Att. 23 step 2.3

  • CUT OFF test connection cap downstream of 1C11

-F307, PI-R013 test connection (above AND to left of Backup Scram valves).

Standard: Simulate cutting off test connection.

Cue: Test connection cap is cut off

. Notes:

SAT / UNSAT Step 4: EOP Att. 23 step 2.3.1

Cue: Resistance is felt in the CCW direction. Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP023 Revision: 1 Page: 6 of 8 Step 5: EOP Att. 23 step 2.4

  • CUT OFF test connection cap downstream of 1C11

-F309, PT-N052 test connection (above AND to left of Backup Scram valves).

Standard: Simulate cutting off test connection.

Cu e: Test connection cap is cut off

. Notes: SAT / UNSAT Step 6: EOP Att. 23 step 2.4.1

Cue: Resistance is felt in the CCW direction. Notes:

SAT / UNSAT

Task Standard(s): Steps 2.1 through 2.

4 of EOP Att. 23 are completed in accordance with the procedure.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-EOP023 Revision: 1 Page: 7 of 8 Task: Manually Vent the SCRAM Air Header Follow-Up Questions & Answers

Comments:

Give this page to the student Initial Condition(s):

EOP's have been entered.

Initiating Cue(s):

The CRS directs you to perform steps 2.1 through 2.4 of EP Attachment 23.

Another operator will complete the remaining steps of this attachment when directed.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-C6101 Revision:

2 Page: 1 of 10 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-PS2 Time Critical Alternate Path Validation Time:

20 min TITLE: Startup RHR in Suppression Pool Cooling From the Remote Shutdown Panel New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

Remove Generic Instructions Sheet. This was removed from 14-S-2-18. THIS DOCUMENT REPLACES
GJPM-OPS-C6101 Rev 1 REVIEW / APPROVAL (Print Name): TEAR Approval ( )

Prepared By:

Jonathan W. Sparks 11/16/09 **Preparer Date Ops Review

++: Keith Huff 9/26/2011 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Chris Laird 9/26/2011 Training Representative Date Approved By:

Kane Ryder 9/28/2011 +Discipline Training Supervisor Date Approval Date:*

9/28/2011

  • Indexing Information
    • The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.

++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS)

ENTERGY NUCLEAR JOB PERFORMANCE MEASU RE Number: GJPM-OPS-C6101 Revision: 2 Page: 2 of 10 Task: Startup RHR in Suppression Pool Cooling from the Remote Shutdown Panels Setting: Plant (Outside CAA)

Type: RO Task: CRO-C61-001; CRO-C61-009; CRO-E12-019; CRO-P41-001 K&A: 295016 2.1.30: 3.9/3.4; AA1.07: 4.2/4.3; AK2.01: 4.4/4.5; AK3.03: 3.5/3.7; 295013 AA1.01: 3.9/3.9; 295026 EA1.01: 4.1/4.1 219000 A4.01: 3.8/3.7; A4.02: 3.7/3.5; A4.05: 3.4/3.4 Safety Function

Instrumentation (7) & Containment (5)

Time Required

15 minutes Time Critical
No Alternate Path
N o Performance
Simulate Reference(s)
ONEP 05-1-02-II-1 Attachment VIII or IX Handout(s)
ONEP 05-1-02-II-1 Attachment VIII or IX # Manipulations
10 # Critical Steps
3 Group #: 2 Simulator Setup/Required Plant Conditions
Area is accessible.

Safety Concerns

Do NOT operate plant equipment

. For Protected Train concerns, use either RHR A or B using Attachment VIII or IX.

Write in on the Initial Conditions Page which RHR and Attachment is to be used.

ENTERGY NUCLEAR JOB PERFORMANCE MEASU RE Number: GJPM-OPS-C6101 Revision: 2 Page: 3 of 10 Name: __________________

_________ Time Start: _______

Time Stop: _______

Initial Condition(s):

The Control Room has been evacuated due to noxious fumes.

Control of the plant has been established at the Remote Shutdown Panels.

An SRO is controlling operations at the remote shutdown panel.

Another operator is assigned for radio communications and is monitoring reactor level and pressure.

A Plant Shutdown Operator is stationed in the Auxiliary Building if needed.

The RSD room cabinet at the remote shutdown panel is unlocked.

The reactor is shutdown RPV water level is within band of +30 to

-30" on wide range level.

RPV pressure is within band of 900 to 1000 psig.

RHR Transfer switches have been placed in EMERG position per step 3.6 of the Shutdown from the Remote Shutdown Panel ONEP. Standby Service Water A and B are not running and are in Standby lineup per the P41 SOI. RCIC will be started after RHR A or B is placed in suppression pool cooling mode.

Initiating Cue(s):

You have been directed to place RHR

____ in Suppression Pool Cooling per Attachment

____ of the Shutdown from the Remote Shutdown Panel ONEP.

Establish maximum cooling.

ENTERGY NUCLEAR JOB PERFORMANCE MEASU RE Number: GJPM-OPS-C6101 Revision: 2 Page: 4 of 10 Task: Startup RHR in Suppression Pool Cooling from the Remote Shutdown Panels Notes: (Notes to Evaluator)

1. Remote Shutdown Panels are located on the 111' elevation of the Control Building.
2. Division 1 Remote Shutdown Panel is H22

-P150. 3. Division 2 Remote Shutdown Panel is H22

-P151. 4. This JPM may be performed using RHR A or B for protected train concerns.

5. Be sure a non

-protected train ESF inverter is selected and recorded on the initiating cues page.

Task Overview:

(Detailed description of task)

This task is to startup RHR A or B in Suppression Pool Cooling from the Remote Shutdown Panels per the ONEP. This includes starting up SSW A or B. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 05-1-02-II1 3.9.1(2)a 1 ENSURE SSW System A(B) in operation, supplying RHR A heat exchangers.

IF SSW A is NOT supplying RHR A heat exchangers, THEN START SSW A [SSD] as follows:

CHECK OPEN/OPEN P41-F068A(B) SSW OUTL FM RHR HX A(B) VLV. Standard: Checks or opens P41

-F068A(B) Cue: Red light on, green light off.

Notes: If step 3.9.1(2)a is not performed, the SSW system will automatically startup and lineup when the RHR pump is started.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASU RE Number: GJPM-OPS-C6101 Revision: 2 Page: 5 of 10 Step 2: 05-1-02-II1 3.9.1(2)a2 START P41-C001A(B), SSW PMP A(B). Standard: Starts SSW pump Cue: Red light on, green light off.

Notes:

SAT / UNS AT Step 3: 05-1-02-II1 3.9.1(2)a3 OPEN P41-F001 A(B) SSW PMP A(B) DISCH VLV. Standard: Open valve.

Cue: Red light on, green light off.

Notes:

SAT / UNSAT Step 4: 05-1-02-II1 3.9.1(2)a4 OPEN P41-F014A (B) SSW INL TO RHR HX A(B) VLV. Standard: Open valve.

Cue: Red light on, green light off.

Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASU RE Number: GJPM-OPS-C6101 Revision: 2 Page: 6 of 10 Step 5: 05-1-02-II1 3.9.1(2)a5 OPEN P41-F005A(B) SSW Loop A(B) RTN TO CLG TWR A(B). Standard: Open valve.

Cue: Red light on, green light off.

Notes:

SAT / UNSAT Step 6: 05-1-02-II1 3.9.1(2)a6 VERIFY CLOSED/CLOSE P41-F006A(B) SSW Loop A(B) RECIRC VLV

. Standard: Verify closed valve.

Cue: Green light on, red light off.

Notes:

SAT / UNSAT Step 7: 05-1-02-II1 3.9.1(2)a7 START P41-C003A(C), SSW CLG TWR FAN A(C) AND P41-C003B(D) SSW CLG TWR FAN B(D) Standard: Start Fans.

Cue: Red light on, green light off.

Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASU RE Number: GJPM-OPS-C6101 Revision: 2 Page: 7 of 10 Step 8: 05-1-02-II1 3.9.1(2)b OPEN OR CHECK OPEN the following valves:

E12-F004A(B) RHR PUMP A(B) SUCT FM SUPP POOL E12-F047A(B) RHR HX A(B) INL VLV E12-F003A(B) RHR HX A(B) OUTL VLV Standard: Checks valves open.

Cue: For all valves, Red light on, green light off.

Notes:

SAT / UNSAT Step 9: 05-1-02-II1 3.9.1(2)c

  • CLOSE E12-F048A(B) RHR HX A(B) BYP VLV Standard: Close valve.

Cue: Green light on, red light off.

Notes: Throttle valve, takes 1

-2 minutes to stroke.

To maintain maximum cooling (as discussed in initiating cues) this valve must remain shut; therefore, 3.9.1(2)f and 3.9.1(2)g are NA.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASU RE Number: GJPM-OPS-C6101 Revision: 2 Page: 8 of 10

Step 10: 05-1-02-II1 3.9.1(2)d

  • START E12-C002A(B), RHR PMP A(B)

Standard: Start pump.

Cue: Red light on, Green light off.

Notes:

SAT / UNSAT Step 11: 05-1-02-II1 3.9.1(2)e

  • OPEN E12-F024A(B) RHR A(B) TEST RTN TO SUPP POOL Standard: Open valve.

Cue: Red light on, Green light off.

This completes the task.

Notes:

SAT / UNSAT

Task Standard(s)

RHR A(B)is operating in Suppression Pool Cooling with E12

-F048 A(B) full closed and E12-F003 A(B) full open and SSW A(B) in service to the RHR A(B) Heat Exchangers.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASU RE Number: GJPM-OPS-C6101 Revision: 2 Page: 9 of 10 Task: Startup RHR in Suppression Pool Cooling from the Remote Shutdown Panels Follow-Up Questions & Answers

Comments:

Give this page to the student Initial Condition(s):

The Control Room has been evacuated due to noxious fumes.

Control of the plant has been established at the Remote Shutdown Panels.

An SRO is controlling operations at the remote shutdown panel.

Another operator is assigned for radio communications and is monitoring reactor level and pressure.

A Plant Shutdown Operator is stationed in the Auxiliary Building if needed.

The RSD room cabinet at the remote shutdown panel is unlocked.

The reactor is shutdown RPV water level is within band of +30 to

-30" on wide range level.

RPV pressure is within band of 900 to 1000 psig.

RHR Transfer switches have been placed in EMERG position per step 3.6 of the Shutdown from the Remote Shutdown Panel ONEP.

Standby Service Water A and B are not running and are in Standby lineup per the P41 SOI. RCIC will be started after RHR A or B is placed in suppression pool cooling mode.

Initiating Cue(s):

You have been directed to place RHR

____ in Suppression Pool Cooling per Attachment

____ of the Shutdown from the Remote Shutdown Panel ONEP.

Establish maximum cooling.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-L62-3 Revision:

1 Page: 1 of 9 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-PS3 Time Critical Alternate Path Validation Time:

15 min TITLE: Startup an ESF Static Inverter (1Y87, 1Y88, 1Y95, 1Y96)

New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

THIS DOCUMENT REPLACES
REVIEW / APPROVAL (Print Name):

TEAR Approval ( )

Prepared By:

Mark Pait 6/13/11 **Preparer Date Ops Review++: Keith Huff 9/26/2011 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Chris Laird 9/26/2011 Training Representative Date Approved By:

Kane Ryder 9/28/2011 +Discipline Training Supervisor Date Approval Date:*

9/28/20 11

  • Indexing Information
    • The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.

++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS)

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-L62-3 Revision: 1 Page: 2 of 9 Task: Startup an ESF Static Inverter Setting: Plant (Outside CAA)

Type: NLO Task: AON-L62-002 K&A: 262002 A4.01 (2.8/3.1)

Safety Function: 6 - Electrical Time Required

15 minutes Time Critical
No Faulted: No Performance
Simulate Reference(s)
04-1-01-L62-1, Static Inverter SOI Handout(s)
04-1-01-L62-1, Static Inverter SOI including Attachment III
  1. Manipulations
4 # Critical Steps
4 Group #: 1 Simulator Setup/Required Plant Conditions
Area 25A , elevation 111' is accessible Shift Manager/CRS permission to conduct JPM's.

Write in on the Initial Conditions Page which INVERTER is to be started.

Safety Concerns

Wear appropriate personal protective equipment.

Do NOT operate plant equipment.

This JPM can be performed on any of 4 ESF inverters, ensure the inverter chosen for this JPM is not part of the protected train.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-L62-3 Revision: 1 Page: 3 of 9 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

All of the following conditions apply to inverter 1Y_____

Inverter is shutdown with both Battery Input Breaker CB1 and Inverter Output Breaker CB2 Open. The Heater breaker is off.

The Alternate Source is supplying loads (Alternate Source Breaker Closed)

. DC Bus is energized with the inverter battery feeder breaker closed.

The Manual Bypass Switch is selected to Alternate Source to Load.

Initiating Cue(s):

The CRS directs you to startup Inverter 1Y_____ and transfer the loads to the normal source per SOI 04 01-L62-1 section 4.2.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-L62-3 Revision: 1 Page: 4 of 9 Task: Startup an ESF Static Inverter Notes: (Notes to Evaluator)

1. Be sure a non

-protected train ESF inverter is selected and recorded on the initiating cues page.

Task Overview:

(Detailed description of task)

This task is to startup an ESF Static Inverter and transfer loads to the inverter per the SOI. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 04-1-01-L62-1 Step 4.2.2 d

  • CLOSE BATTERY INPUT circuit breaker on 1Y87 (1Y88, 1Y95, 1Y96)

AND CHECK the following:

DC input voltmeter reads approximately 105 to 140 volts.

Inverter AC output frequency is reading 60 hertz

+ 0.1 hertz.

INVERTER OUTPUT UNDERVOLTAGE Red indicating light is Off.

INVERTER CURRENT LIMIT Red indicating light is Off.

INVERTER OVERHEATING Red indicating light is Off.

IN SYNC Amber indicating light is On (delayed).

FAN FAILURE Red indicating light is On.

Standard: Close CB1, Battery input breaker.

Cue: DC input voltage and AC frequency are as indicated on the inverter, all other indications are as indicated by the procedure.

Notes: Step 4.2.2a instructs the operator to move to step 4.2.2d.

The inverter will remain in Alternate Supplying Load until the last step where the Inverter to Load pushbutton is depressed.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-L62-3 Revision: 1 Page: 5 of 9 Step 2: 04-1-01-L62-1 Step 4.2.2e

  • CLOSE Inverter Output circuit breaker on 1Y87 (1Y88, 1Y95, 1Y96).

Standard: Close CB2, Inverter output breaker.

Cue: Notes: Closing this breaker does not change indications on the inverter.

SAT / UNSAT Step 3: 04-1-01-L62-1 Step 4.2.2f CHECK IN SYNC light is On; IF OUT OF SYNC light is On, THEN CONTACT Electrical and DO NOT proceed until IN SYNC light is On. There is some time dela y to achieve the IN SYNC light.

Standard: Checks IN SYNC light lit.

Cue: IN SYNC light is on.

Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-L62-3 Revision: 1 Page: 6 of 9 Step 4: 04-1-01-L62-1 Step 4.2.2g

  • IF IN SYNC light is On, Perform the following:
  • TRANSFER Manual Bypass switch to NORMAL OPERATION position ALTERNATE SOURCE AVAILABLE (Amber) - On ALTERNATE SOURCE POWERING LOAD (Red) - On Standard: Places Manual Bypass switch to NORMAL OPERATION Cue: Alternate source available and powering load lights are on.

Notes: SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-L62-3 Revision: 1 Page: 7 of 9 Step 5: 04-1-01-L62-1 Step 4.2.2h

  • DEPRESS INVERTER TO LOAD pushbutton AND CHECK following indications:

INVERTER POWERING LOAD Amber light is On. BATTERY NEAR EXHAUSTION light

- Off INVERTER CURRENT LIMIT light

- Off FAN FAILURE

- Off INVERTER OVERHEATING light

- Off INVERTER OUTPUT UNDERVOLTAGE light - Off INVERTER POWERING LOAD light

- On In SYNC light

- On System AC output (volts)

- approximately 120 Vac

+ 5 volts Inverter AC output (hertz)

- 60 hertz + 0.1 hertz Standard: Depress inverter to load pushbutton.

Cue: If the inverter is already supplying the load, then indications are as seen on the inverter.

Otherwise, system AC output is 120 VAC/60 Hz with all other indications as indicated by the procedure.

This completes the JPM.

Notes:

SAT / UNSAT Task Standard(s)

Inverter is started and supplying the load per 04 01-L62-1 section 4.2.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-L62-3 Revision: 1 Page: 8 of 9 Task: Startup an ESF Static Inverter Follow-Up Questions & Answers

Comments:

Give this page to the student Initial Condition(s

): All of the following conditions apply to inverter 1Y_____

Inverter is shutdown with both Battery Input Breaker CB1 and Inverter Output Breaker CB2 Open. The Heater breaker is off.

The Alternate Source is supplying loads (Alternate Source Breaker Closed). DC Bus is energized with the inverter battery feeder breaker closed.

The Manual Bypass Switch is selected to Alternate Source to Load.

Initiating Cue(s):

The CRS directs you to startup Inverter 1Y_____ and transfer the loads to the normal sourc e per SOI 04 01-L62-1 section 4.2.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR1 Revision: 0 Page: 1 of 7 Rtype:

QA Reco rd Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-AR1 Time Critical Alternate Path Validation Time:

20 min TITLE: Fire Door Surveillance New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

THIS DOCUMENT REPLACES
REVIEW / APPROVAL (Print Name):

TEAR Approval ( )

Prepared By:

Mark Pait 5/2 4/2011 **Preparer Date Ops Review

++: Keith Huff 10/5/2011 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Chris Laird 10/5/2011 Training Representative Date Approved By:

Kane Ryder 10/5/2011 +Discipline Training Supervisor Date Approval Date:*

10/5/2011

  • Indexing Information
    • The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.

++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS) 04-1-01-T42-1 Rev 28 ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR1 Revision: 0 Page: 2 of 7 Admin Task: Fire Doors Surveillance Setting: Classroom Type: RO Task: CRO-P64-NORM-7 K&A: 2.1.20 (4.6/4.6) 2.2.12 (3.7/4.1)

Safety Function

NA Time Required
20 minutes Time Critical
No Faulted: No Performance
Actual Reference(s)
0 6-OP-SP64-M-0043 , Fire Doors Alarm Check Handout(s)
06-OP-SP64-M-0043, Fire Doors Alarm Check (Attachment 1 prepared) # Manipulations
NA # Critical Steps
2 Group: NA Simulator Setup/Required Plant Conditions
None Safety Concerns
None

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR1 Revision: 0 Page: 3 of 7 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The Plant is operating at rated power.

06-OP-SP64-M-0043 step 5.2.1 and 5.2.2 are performed as required by another operator.

The CRS directs you to perform a partial 06-OP-SP64-M-0043, Fire Doors Alarm Check on the following doors: (1) Elect Pen Rm 1A221 door number 1A212, (2) Emerg S/D Rm OC208A door number OC208, and (3) Sec Ctmt Door 1A604.

You note the following items during your inspection:

o Elect Pen Rm 1A221 door 1A212:

Door does not latch after being fully opened and allowing the closure mechanism to pull the door shut; however, when you pull the door it latches.

Alarms after 1 second upon opening.

o Emerg S/D Rm OC208A door OC208:

Has a deep gouge/dent 10" long on one side on the bottom right quadrant but does not penetrate the door skin.

Seam has separated next to the 10" gouge.

Alarms after 30 seconds upon opening.

o Sec Ctmt Door 1A604:

Has a rust patch on the Aux Building Roof side that has left a 3 in 2 hole in the skin of the door (the inside door skin is not damaged).

Has not alarmed 4 minutes afte r opening. Initiating Cue(s):

Complete the attached 06

-OP-SP64-M0043, Fire Doors Alarm Check surveillance, including all portions of Attachment 1 Cover Sheet sections 2.0 and 3.0. Only mark Tech Spec

Acceptance Criteria as Acceptable if REQUIRED by 0 6-OP-SP64-M-0043 surveillance procedure.

Note reasons for marking Tech Spec Acceptance Criteria or other steps/data in the test results section as "Acceptable" or "Unacceptable" on the back of the surveillance coversheet.

All prerequisites are verified met.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR1 Revision: 0 Page: 4 of 7 Admin Task

Fire Doors Surveillance Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The operator will perform a Fire Door Alarm Check using the information provided in the initiating ques. The operator will discover tech spec door OC208 is INOP, tech spec door 1A212 is OPERABLE but requires a WR to fix the closing mechanism, and non

-

tech spec door 1A604 also requires a WR to fix the security alarm timing and a rust patch. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 06-OP-SP64-M-0043

  • The operator evaluates the given conditions for each fire door given in the initiating cues and determines the following:
  • Tech Spec Door 1A 212 Tech Spec Acceptance Criteria is "Acceptable,"

but step 5.2.6 other steps/data is "Unacceptable" because the closing mechanism will not shut the door without assistance (see note for step 5.2.6)

.

  • Tech Spec Door OC208 fails step 5.2.5c; however, the Tech Spec Acceptance Criteria for this surveillance is "Acceptable" (see note for step 5.2.5). The other steps/data is "Unacceptable".

Tech Spec Door OC208 is INOP since it fails step 5.2.5c

.

  • Door 1A604 is not a Tech Spec door; therefore, Tech Spec Acceptance Criteria is NA. Step 5.2.5 a data is "Unacceptable" because the outside door skin is visibly damaged with a hole > 3/16"

. Standard: The deficiencies noted above are recorded on the surveillance cover sheet.

Cue: Notes: This meets the requirement for step 3.2 on the surveillance coversheet.

Any words that demonstrate an equivalent understanding is acceptable.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR1 Revision: 0 Page: 5 of 7 Step 2: 06

-OP-SP64-M-0043

  • Complete the surveillance coversheet sectio n 3.1 by checking boxes for: (1) Partial procedure complete, (2)* Tech Spec Acceptance Criteria Acceptable, and (3)* All other steps/data Unacceptable

. Standard: Checks appropriate boxes.

Cue: Notes: SAT / UNSAT Step 3: 06

-OP-SP64-M-0043 Complete the surveillance coversheet sections 2.1, 2.2 and

3.3 Standard

Circle for the plant being in Mode 1 and record themselves as performer with the date and time.

Cue: Notes: JPM is completed when the operator completes the surveillance package coversheet.

SAT / UNSAT Task Standard(s)

The operator determines that the Tech Spec Acceptance Criteria is "Acceptable" and that All other steps/data is "Unacceptable" per 06-OP-SP64-M-0043. SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR1 Revision: 0 Page: 6 of 7 Admin Task

Fire Doors Surveillance Follow-Up Questions & Answers
Comment s:

Give this page to the student

Initial Condition(s):

The Plant is operating at rated power.

06-OP-SP64-M-0043 step 5.2.1 and 5.2.2 are performed as required by another operator.

The CRS directs you to perform a partial 0 6-OP-SP64-M-0043, Fire Doors Alarm Check on the following doors: (1) Elect Pen Rm 1A221 door number 1A212, (2) Emerg S/D Rm OC208A door number OC208, and (3) Sec Ctmt Door 1A604.

You note the following items during your inspection:

o Elect Pen Rm 1A221 door 1A212: Door does not latch after being fully opened and allowing the closure mechanism to pull the door shut; however, when you pull the door it latches.

Alarms after 1 second upon opening.

o Emerg S/D Rm OC208A door OC208:

Has a deep gouge/dent 10" long on one side on the bottom right quadrant but does not penetrate the door skin.

Seam has separated next to the 10" gouge.

Alarms after 30 seconds upon opening.

o Sec Ctmt Door 1A604:

Has a rust patch on the Aux Building Roof side that has left a 3 in 2 hole in the skin of the door (the inside door skin is not damaged).

Has not alarmed 4 minutes after opening.

Initiating Cue(s):

Complete the attached 06

-OP-SP64-M0043, Fire Doors Alarm Check surveillance, including all portions of Attachment 1 Cover Sheet sections 2.0 and 3.0. Only mark Tech Spec Acceptance Criteria as Acceptable if REQUIRED by 06-OP-SP64-M-0043 surveillance procedure.

Note reasons for marking Tech Spec Acceptance Criteria or other steps/data in the test results section as "Acceptable" or "Unacceptable" on the back of the surveillance coversheet.

All prerequisites are verified met.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR2 Revision: 0 Page: 1 of 7 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-AR2 Time Critical Alternate Path Validation Time:

1 5 min TITLE: Operator Qualification Verification New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

THIS DOCUMENT REPLACES
REVIEW / APPROVAL (Print Name):

TEAR Approval ( )

Prepared By:

Mark Pait 6/1/2011 **Preparer Date Ops Review

++: Keith Huff 10/5/2011 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Chris Laird 10/5/2011 Training Representative Date Approved By:

Kane Ryder 10/5/2011 +Discipline Training Supervisor Date Approval Date:*

10/5/2011

  • Indexing Information
    • The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist. ++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS) 04-1-01-T42-1 Rev 28 ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR2 Revision: 0 Page: 2 of 7 Admin Task: Operator Qualification Verification Setting: Classroom Type: RO Task: CRO-ADMIN-003, AON-ADMIN-002 K&A: 2.1.4 (3.3/3.8)

Safety Function

NA Time Required
1 5 minutes Time Critical
No Faulted: No Performance
Actual Reference(s)
Operations Section Guideline OPG

-35 Handout(s)

None # Manipulations
NA # Critical Steps: 1 Group: NA Simulator Setup/Required Plant Conditions
Requires Entergy Network Access Safety Concerns
None ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR2 Revision: 0 Page: 3 of 7 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

You are returning from three days off to stand shift as Reactor Operator.

Initiating Cue(s):

Demonstrate your ability to check your qualification to stand shift as Reactor Operator in accordance with Operations Section Guideline OPG

-35.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR2 Revision: 0 Page: 4 of 7 Admin Task

Operator Qualification Verification Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

Using computer program Plateau LMS in accordance with Operations Section Guideline OPG-35, the operator will demonstrate the ability to verify his qualificati on s are current to stand shift as Reactor Operator.

Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: Obtain a copy of OPG

-35 Standard: OPG-35 is accessed via the GGNS Operations Department internet homepage by mousing over "Reference Info" and selecting "Ops Section Guidelines". Once on the OPG page, select OPG

-35 to open the document.

Cue: Notes: SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR2 Revision: 0 Page: 5 of 7 Step 2: OPG-35 sections 1.1 and 1.2

  • Access computer program Plateau LMS and Login.

Standard: Logs in to the Plateau LMS program

. Cue: If asked, direct the operator to use his own user name and password. Notes: Three ways to access:

(1) Select START

- All Programs

- Nuclear Corporate Applications

- Plateau LMS.

(2) Operation Dept website homepage by selecting GGNS Homepage - Departments

- Operations

- On the left menu under Plateau LMS select User Access.

(3) Training website homepage by selecting GGNS Homepage - Departments

- Training - Plateau LMS.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR2 Revision: 0 Page: 6 of 7 Step 3: OPG-35 sections 1.3 and 1.4

  • Access the Curriculum Status Screen and verify required curriculum on OPG-35 Table 1 is current in Plateau.

Standard: Looks for matching curriculum (G-OPS-RO-RO Active/Proficient, G

-HAZ-DOT HAZMAT Ops) in plateau with a green check by it and the Next Action Date has not passed. Cue: Notes: JPM complete when the operator demonstrates the ability to determine if personal watchstanding requirements are met.

SAT / UNSAT Task Standard(s)

Demonstrate the ability to determine individual qualifications to meet watchstanding requirements for Reactor Operator in accordance with OPG

-35. SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR2 Revision: 0 Page: 7 of 7 Admin Task

Operator Qualification Verification Follow-Up Questions & Answers
Comments:

Give this page to the student Initial Condition(s):

You are returning from three days off to stand shift as Reactor Operator.

Initiating Cue(s):

Demonstrate your ability to check your qualification to stand shift as Reactor Operator in accordance with Operations Section Guideline OPG-35.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR3 Revision: 0 Page: 1 of 10 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-AR3 Time Critical Alternate Path Validation Time:

25 min TITLE: Determine Tagging Requirements New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

THIS DOCUMENT REPLACES
REVIEW / APPROVAL (Print Name):

TEAR Approval ( )

Prepared By:

Mark Pait 5/2 4/2011 **Preparer Date Ops Review

++: Keith Huff 10/5/2011 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Chris Laird 10/5/2011 Training Representative Date Approved By:

Kane Ryder 10/5/2011 +Discipline Training Supervisor Date Approval Date:*

10/5/2011

  • Indexing Information ** The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.

++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS)

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR3 Revision: 0 Page: 2 of 10 Admin Task: Determine Tagging Requirements Setting: Classroom Type: RO Task: CRO-ADMIN-005 K&A: 2.2.13 (4.1/4.3) 2.2.41 (3.5/3.9)

Safety Function

NA Time Required
2 5 minutes Time Critical
No Faulted: No Performance
Actual Reference(s)
EN-OP-102 , Protective and Caution Tagging EN-OP-102-01 , Protective and Caution Tagging Forms and Checklist 04-S-01-P64-1, Fire Protection Water System SOI M-0035A , E-0231-02 Handout(s)
EN-OP-102, Protective and Caution Tagging 04-S-01-P64-1, Fire Protection Water System SOI M-0035A, E-0231-02 Blank Tagout Tags Sheets
  1. Manipulations
NA # Critical Steps: 2 Group: NA Simulator Setup/Required Plant Conditions
None Safety Concerns
None ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR3 Revision: 0 Page: 3 of 10 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The Plant is operating at rated power.

The Motor Driven Fire Pump C002

-N needs a new impeller

. The pump motor will need to be removed for access.

Initiating Cue(s):

The CRS directs you to prepare a Tagout Tags Sheet using EN-OP-102-01 Attachment 9.3 (Provided) to De-energize and mechanicall y isolate the Motor Driven Fire Pump C002

-N. Restoration Configuration is not required.

The next sequential tag serial number is "01."

Use the closest available mechanical isolations to the component to be isolated.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR3 Revision: 0 Page: 4 of 10 Admin Task

Determine Tagging Requirements Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The operator will determine the proper isolations for the Motor Driven Fire Pump.

Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: EN-OP-102 5.3 [2] (e)

/ Att. 9.2

  • The operator must determine minimum Tagout boundaries to include
  • NSP64-F160 (Mtr Driven Fw Pmp Casing Dr)
  • NSP64-F108 (Mtr Driven Fw Pmp Suct)
  • NSP 64-F177 (Mtr Driven Fw Pmp Test Loop Isol)
  • NSP64-F016 (Mtr Driven Fw Pmp Disch)
  • 52-11305 (MD Fire Pump Breaker

)

  • 52-1P13229 (STRIP HEATER MOTOR DRIVEN FIRE PUMP)

HS M 602 (Control Room Manual Start Pushbutton

) NSP64-F093D (Mtr Driven Fw Pump Suct Hdr Vent)

Standard: Determines appropriate boundaries.

Cue: Notes: The components listed are the minimum required to perform work. Any combination of valves that adequately isolates the MDFP will meet the requirements of this step.

Additional components are allowed.

See the attached KEY for details.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR3 Revision: 0 Page: 5 of 10 Step 2: EN-OP-102 5.3 [4]

  • Complete the Tagout Tags Sheet of EN

-OP-102-01 Attachment 9.3 See attached Tagout Tags Sheet KEY Standard: Completes the Tagout Tags Sheet with required components from Step 1

. Cue: Notes: EN-OP-102 Attachment 9.2 section 7.0 contains the Tagging Sequence guidance.

JPM complete when the operator completes the Tagout Tags Sheet. SAT / UNSAT Task Standard(s)

All required isolations and vent paths are identified and correctly documented on the Tagout Tags Sheet in accordance with EN

-OP-102. SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR3 Revision: 0 Page: 6 of 10 Admin Task

Determine Tagging Requirements Follow-Up Questions & Answers
Comments:

NUCLEAR MANAGEMENT MANUAL N ON-Q UALITY R ELATED EN-OP-102-01 REV. 7 I NFORMATIONAL USE PAGE 7 OF 26 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: ___MANUAL___________

TAGOUT: ___XXXX________ Tag Serial No. Tag Type Equipment Equipment Description Equipment Location Place. Seq. Placement Configuration Place. 1st Verif Date/Time Place. 2nd Verif Date/Time Rest. Seq. Restoration Configuration Rest. 1st Verif Date/Time Rest. 2nd Verif Date/Time Placement/Removal Tag Notes 1 *D

  • NSP64-F160 Mtr Driven Fw Pmp Casing Dr BLDG FW PUMP HOUSE ELEV 132' 6 *OPEN 2 *D
  • NSP64-F108 Mtr Driven Fw Pmp Suction BLDG FW PUMP HOUSE ELEV 132' 5 *CLOSE 3 *D
  • NSP64-F177 Mtr Driven Fw Pmp Test Loop Isol BLDG FW PUMP HOUSE ELEV 132' 4 *CLOSE 4 *D
  • NSP64-F016 Mtr Driven Fw Pmp Disch BLDG FW PUMP HOUSE ELEV 132' 4 *CLOSE 5 *D
  • 52-11305 MD Fire Pump 11BD3 2 *OPEN 6 *D
  • 52-1P13229 STRIP HEATER MOTOR

DRIVEN FIRE PUMP 11P32 3 *OPEN 7 D HS M602 MD Fire Pump Remote Start PB SH13-P862 1 Not Depressed 7 D NSP64-F093D Mtr Driven Fw Pmp Suct Hdr Vent BLDG FW PUMP HOUSE ELEV 132' 6 OPEN ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR3 Revision: 0 Page: 8 of 10 Give this page to the student Initial Condition(s):

The Plant is operating at rated power.

The Motor Driven Fire Pump C002

-N needs a new impeller.

The pump motor will need to be removed for access.

Initiating Cue(s):

The CRS directs you to prepare a Tagout Tags Sheet using EN

-OP-102-01 Attachment 9.3 (Provided) to De

-energize and mechanically isolate the Motor Driven Fire Pump C002-N. Restoration Configuration is not required.

The next sequential tag serial number is "01."

Use the closest available mechanical isolations to the component to be isolated.

NUCLEAR MANAGEMENT MANUAL N ON-Q UALITY R ELATED EN-OP-102-01 REV. 7 I NFORMATIONAL USE PAGE 7 OF 26 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: ___MANUAL___________

TAGOUT: ___XXXX________ Tag Serial No. Tag Type Equipment Equipment Description Equipment Location Place. Seq. Placement Configuration Place. 1st Verif Date/Time Place. 2nd Verif Date/Time Rest. Seq. Restoration Configuration Rest. 1 st Verif Date/Time Rest. 2nd Verif Date/Time Placement/Removal Tag Notes NUCLEAR MANAGEMENT MANUAL N ON-Q UALITY R ELATED EN-OP-102-01 REV. 7 I NFORMATIONAL USE PAGE 7 OF 26 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: ___MANUAL___________

T AGOUT: ___XXXX________ Tag Serial No. Tag Type Equipment Equipment Description Equipment Location Place. Seq. Placement Configuration Place. 1st Verif Date/Time Place. 2nd Verif Date/Time Rest. Seq. Restoration Configuration Rest. 1st Verif Date/Time Rest. 2nd Verif Date/Time Placement/Removal Tag Notes ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR4 Revision: 0 Page: 1 of 7 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-AR4 Time Critical Alternate Path Validation Time:

15 min TITLE: Primary Containment Water Level Determination EOP Attachment 29 New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

Original electronic copy was lost.

THIS DOCUMENT REPLACES

GJPM-OPS-ADMR94 REVIEW / APPROVAL (Print Name):

TEAR Approval (

) Prepared By:

Mark Pait 6/1/2011 **Preparer Date Ops Review

++: Keith Huff 10/5/2011 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Chris Laird 10/5/2011 Training Representative Date Approved By:

Kane Ryder 10/5/2011 +Discipline Training Supervisor Date Approval Date:*

10/5/2011

  • Indexing Information
    • The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.

++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS) 04-1-01-T42-1 Rev 28 ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR4 Revision: 0 Page: 2 of 7 Admin Task

Primary Containment Water Level Determination Setting: Classroom Type: RO Task: CRO-EP-29 K&A: 295029 EA2.01 (3.9/3.9) EA2.03 (3.4/3.5) 2.4.21 (4.0/4.6) 2.1.25 (3.9/4.2) 2.1.20 (4.6/4.6)

Safety Function

5 - Containment Integrity Time Required
15 minute s Time Critical
No Faulted: No Performance
Actual Reference(s)
05-S-01-EP-1 Attachment 29 Handout(s)
05-S-01-EP-1 Attachment 29 SPDS Screen shot, Panel photo for E51

-R604 # Manipulations

N/A # Critical Steps
1 Group: N/A Simulator Setup/Required Plant Conditions
None Safety Concerns
None ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR4 Revision: 0 Page: 3 of 7 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

A LOCA has occurred.

Suppression Pool water level indication is off scale high. RCIC is shut down with suction aligned to the suppression pool.

Initiating Cue(s):

The CRS directs you to determine Primary Containment water level IAW EP Attachment 29.

Use the attached images for current plant conditions.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR4 Revision: 0 Page: 4 of 7 Admin Task

Primary Containment Water Level Determination Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

Using EP Attachment 29 and the attached images to obtain RCIC Suction Pressure and Containment Pressure, determine Primary Containment Water Level from the Delta Pressure to Ctmt Level Conversion Table, EP Attachment 29 Table 1.

Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: EP-1 Att. 29 step 2.4

  • Determine RCIC Pump Suction Pressure indicated on E51

-R604 is 15 psig.

Standard: Determine from attached photo RCIC Pump Suction Pressure.

Cue: Notes: Steps 2.1

- 2.3 are NA since RCIC is already secured and aligned for suction from the suppression pool.

SAT / UNSAT Step 2: EP

-1 Att. 29 step 2.5

  • Determine Containment Pressure indicated on SPDS is 2.2 psig.

Standard: Determine from attached screen shot Containment Pressure.

Cue: Notes: SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR4 Revision: 0 Page: 5 of 7 Step 2: EP

-1 Att. 29 step 2.6

  • Determine delta pressure to be 12.8 psig by subtracting Containment Pressure from RCIC Pump Suction Pressure.

Standard: Determines delta pressure to be 12.8 psig

. Cue: Notes: SAT / UNSAT Step 2: EP

-1 Att. 29 step 2.7

Standard: Determines Primary Containment water level using EP Attachment 29 Table 1. Cue: Notes: SAT / UNSAT

Task Standard(s)

Determine Containment Water level using Containment pressure and RCIC Suction pressure and 05-S-01-EP-1 Attachment 29

. SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AR4 Revision: 0 Page: 6 of 7 Admin Task

Primary Containment Water Level Determination Follow-Up Questions & Answers
Comments:

Give this page to the student Initial Condition(s):

A LOCA has occurred.

Suppression Pool water level indication is off scale high.

RCIC is shut down with suction aligned to the suppression pool.

Initiating Cue(s):

The CRS directs you to determine Primary Containment water level IAW EP Attachment 29.

Use the attached images for current plant conditions.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011A S 1 Revision: 0 Page: 1 of 7 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-A S 1 Time Critical Alternate Path Validation Time:

15 min TITLE: Determine Fire Watch Requirements New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

THIS DOCUMENT REPLACES
REVIEW / APPROVAL (Print Name):

TEAR Approval ( )

Prepared By:

Mark Pait 5/2 4/2011 **Preparer Date Ops Review

++: Mark Goodwi n 10/4/2011 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Keith Huff 10/4/2011 Training Representative Date Approved By:

Kane Ryder 10/5/2011 +Discipline Training Supervisor Date Approval Date:*

10/5/2011

  • Indexing Information
    • The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist. ++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS) 04-1-01-T42-1 Rev 28 ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AS 1 Revision: 0 Page: 2 of 7 Admin Task: Determine Fire Watch Requirements Setting: Classroom Type: RO Task: CRO-P64-NORM-7 K&A: 2.1.2 (4.1/4.0) 2.1.8 (3.4/4.1) 2.1.20 (4.6/4.6) 2.2.12 (3.7/4.1) 2.2.22 (4.0/4.7) 2.4.25 (3.3/3.7)

Safety Function

NA Time Required
20 minutes Time Critical
No Faulted: No Performance
Actual Reference(s)
0 6-OP-SP64-M-0043 , Fire Doors Alarm Check TRM 6.2.8, Fire Maps Handout(s)
06-OP-SP64-M-0043, Fire Doors Alarm Check Copy of Tech Specs/TRM Fire Watch Maps for Auxiliary Building elevations 119' and 245' and control building elevation 111'
  1. Manipulations
NA # Critical Steps
2 Group: NA Simulator Setup/Required Plant Conditions
None Safety Concerns
None ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AS 1 Revision: 0 Page: 3 of 7 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The Plant is operating at rated power.

All fire detection devices are functioning properly.

A partial 06

-OP-SP64-M-0043, Fire Doors Alarm Check was just performed on the following doors: (1) Elect Pen Rm 1A221 door number 1A212, (2) Emerg S/D Rm OC208A door number OC208, and (3) Sec Ctmt Door 1A604. An operator reports the following after completing the 06

-OP-SP64-M-0043: o Elect Pen Rm 1A221 door 1A212:

Door does not latch after being fully opened and allowing the closure mechanism to pull the door shut; however, when you pull the door it latches. Alarms after 1 second upon opening.

o Emerg S/D Rm OC208A door OC208:

Has a deep gouge/dent 10" long on one side on the bottom right quadrant but does not penetrate the door skin.

Seam has separated next to the 10" gouge.

Alarms after 30 seconds upon opening. o Sec Ctmt Door 1A604:

Has a rust patch on the Aux Building Roof side that has left a 3 in 2 hole in the skin of the door (the inside door skin is not damaged).

Has not alarmed 4 minutes after opening.

Initiating Cue(s):

The Shift Manager asks you to determine the fire watch requirements associated with the indications given.

Use the provided references.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AS 1 Revision: 0 Page: 4 of 7 Admin Task

Determine Fire Watch Requirements Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The operator will determine that tech spec fire door OC208 is INOP and set a fire watch in accordance with TR 6.2.8 for the Division 1 ESF Switchgear Room (Control Building Elevation 111').

Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 06-OP-SP64-M-0043

  • The operator evaluates the given conditions for each fire door given in the initiating cues and determines the following:

Tech Spec Door 1A 212 is OPERABLE

.

  • Tech Spec Door OC20 8 is INOP because it fails step 5.2.5c

. Door 1A604 is not a Tech Spec door; therefore, Tech Spec Acceptance Criteria is NA. Standard: Determine Door OC208 is INOP Cue: Notes:

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AS 1 Revision: 0 Page: 5 of 7 Step 2: TR 6.2.8

JPM is complete when Fire Watch requirements are determined.

SAT / UNSAT Task Standard(s)

The operator establishes a fire watch at least hourly for the Division 1 ESF Switchgear Room due to declaring tech spec door OC208 INOP in accordance with 06

-OP-SP64-M-0043and TR 6.2.8 Condition A

. SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AS 1 Revision: 0 Page: 6 of 7 Admin Task

Determine Fire Watch Requirements Follow-Up Questions & Answers
Comments:

Give this page to the student Initial Condition(s):

The Plant is operating at rated power.

All fire detection devices are functioning properly.

A partial 06

-OP-SP64-M-0043, Fire Doors Alarm Check was just performed on the following doors: (1) Elect Pen Rm 1A221 door number 1A212, (2) Emerg S/D Rm OC208A door number OC208, and (3) Sec Ctmt Door 1A604.

An operator reports the following after completing the 06

-OP-SP64-M-0043: o Elect Pen Rm 1A221 door 1A212:

Door does not latch after being fully opened and allowing the closure mechanism to pull the door shut; however, when you pull the door it latches.

Alarms after 1 second upon opening.

o Emerg S/D Rm OC208A door OC208:

Has a deep gouge/dent 10" long on one side on the bottom right quadrant but does not penetrate the door skin.

Seam has separated next to the 10" gouge.

Alarms after 30 seconds upon opening.

o Sec Ctmt Door 1A604:

Has a rust patch on the Aux Building Roof side that has left a 3 in 2 hole in the skin of the door (the inside door skin is not damaged).

Has not alarmed 4 minutes after opening.

Initiating Cue(s):

Determine the fire watch requirements associated with the indications given.

Use the provided references.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AS2 Revision: 0 Page: 1 of 7 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-A S2 Time Critical Alternate Path Validation Time:

15 min TITLE: Determine the plant EOOS Factor New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

THIS DOCUMENT REPLACES
REVIEW / APPROVAL (Print Name):

TEAR Approval ( )

Prepared By:

Mark Pait 6/2/2011 **Preparer Date Ops Review

++: Mark Goodwin 10/4/2011 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Steve Reeves 10/5/2011 Training Representative Date Approved By:

Kane Ryder 10/5/2011 +Discipline Training Supervisor Date Approval Date:*

10/5/2011

  • Indexing Information
    • The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist. ++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS) 04-1-01-T42-1 Rev 28 ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AS2 Revision: 0 Page: 2 of 7 Admin Task: Determine the plant EOOS Factor Setting: Classroom Type: S RO Task: S RO-ADMIN-15 K&A: 2.1.19 (3.9/3.8)

Safety Function

NA Time Required
1 0 minutes Time Critical
No Faulted: No Performance
Actual Reference(s)
GGNS EOOS Risk Monitor User's Guide Handout(s)
GGNS EOOS Risk Monitor User's Guide
  1. Manipulations
NA # Critical Steps
1 Group: NA Simulator Setup/Required Plant Conditions
Computer with the Training EOOS program (SM desk in the Simulator)

. Safety Concerns

None ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AS2 Revision: 0 Page: 3 of 7 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The Plant is operating at rated power.

Service Transformer 11 is out of service.

SLC A is out of service.

Division 3 Diesel Generator is out of service.

Initiating Cue(s):

The Shift Manager directs you to determine the EOOS Risk Factor and Plant Safety Index.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AS2 Revision: 0 Page: 4 of 7 Admin Task

Determine the plant EOOS Factor Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

This task is to use the EOOS Computer to assess the Plant Safety Index and Risk Factor for out of service equipment and plant work.

Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: EDP-045 Using EDP-045, log into the EOOS program and enter out of service information from the initial condition s Standard: Enter the correct data.

Cue: Notes:

SAT / UNSAT Step 2: EDP-045

  • Determine Plant Safety Index is 9.0 YELLOW.

Standard: Determines the correct Plant Safety Index.

Cue: Notes: SAT / UNSAT

Task Standard(s): The operator determines the correct Plant Safety Index using the EOOS computer program.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AS2 Revision: 0 Page: 5 of 7 Admin Task

Determine the plant EOOS Factor Follow-Up Questions & Answers
Comments:

Give this page to the student Initial Condition(s):

The Plant is operating at rated power. Service Transformer 11 is out of service.

SLC A is out of service.

Division 3 Diesel Generator is out of service.

Initiating Cue(s):

The Shift Manager directs you to determine the EOOS Risk Factor and Plant Safety Index.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AS3 Revision: 0 Page: 1 of 8 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-AS3 Time Critical Alternate Path Validation Time:

25 min TITLE: Review Adequacy of a Tagout New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

THIS DOCUMENT REPLACES
REVIEW / APPROVAL (Print Name):

TEAR Approval ( )

Prepared By:

Mark Pait 5/2 4/2011 **Preparer Date Ops Review

++: Mark Goodwin 10/6/2011 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Keith Huff 10/6/2011 Training Representative Date Approved By:

Kane Ryder 10/6/2011 +Discipline Training Supervisor Date Approval Date:*

10/6/2011

  • Indexing Information ** The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.

++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS) 04-1-01-T42-1 Rev 28 ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011A S3 Revision: 0 Page: 2 of 8 Admin Task: Review Adequacy of a Tagout Setting: Classroom Type: S RO Task: S RO-ADMIN-ADMIN-48 K&A: 2.2.13 (4.1/4.3) 2.2.41 (3.5/3.9)

Safety Function

NA Time Required
2 5 minutes Time Critical
No Faulted: No Performance
Actual Reference(s)
EN-OP-102, Protective and Caution Tagging EN-OP-102-01, Protective and Caution Tagging Forms and Checklist 04-S-01-P64-1, Fire Protection Water System SOI M-0035A, E-0231-02 , J-0204-2 Handout(s)
EN-OP-102, Protective and Caution Tagging 04-S-01-P64-1, Fire Protection Water System SOI M-0035A, E-0231-02 , J-0204-2 Tagout Tags Sheet (Attached)
  1. Manipulations
NA # Critical Steps
1 Group: NA Simulator Setup/Required Plant Conditions
None Safety Concerns
None ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011A S3 Revision: 0 Page: 3 of 8 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The Plant is operating at rated power.

The Motor Driven Fire Pump C002

-N needs a new impeller.

The pump motor will need to be removed for access.

Initiating Cue(s):

As CRS you are tasked to verify the adequacy of the proposed tagout for work on the Motor Driven Fire Pump C002-N. Document errors or inadequate boundaries.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011A S3 Revision: 0 Page: 4 of 8 Admin Task

Review Adequacy of a Tagout Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The operator will determine the proper isolations work on the MDFP.

Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: EN-OP-102 5.3 [2] (e)

/ Att. 9.2 The operator must determine minimum Tagout boundaries to include

NSP64-F160 (Mtr Driven Fw Pmp Casing Dr)

NSP64-F108 (Mtr Driven Fw Pmp Suct)

NSP64-F177 (Mtr Driven Fw Pmp Test Loop Isol)

NSP64-F016 (Mtr Driven Fw Pmp Disch) 52-11305 (MD Fire Pump Breaker) 52-1P13229 (STRIP HEATER MOTOR DRIVEN FIRE PUMP

) HS M 602 (Control Room Manual Start Pushbutton

) Standard: Determines appropriate boundaries.

Cue: Notes: The valves listed are the minimum required valves required to perform work. Any combination of valves that adequately isolates the MDFP and provides a drain or vent path will meet the requirements of this step.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011A S3 Revision: 0 Page: 5 of 8 Step 2:

  • The Operator documents the following:
  • NSP64-F177 is required to isolate the test loop from the MDFP.
  • 52-1P13229 is required to isolate the strip heater power.

HS-M 602 is required by EN-OP-102 Att 9.2 section 1.1 (this tag is not required for safety of personnel

). HS-M002 is not necessary (or practical since it is a pushbutton)

. Standard: Documents deficiencies.

Cue: Notes: These requirements can be specifically found in EN

-OP-102 Attachment 9.2 sections 1.1 and 2.1 and Attachment 9.3 sections 1.1 and 1.

4. Any words that demonstrate an equivalent understanding is acceptable.

The task is complete when the operator determines the adequacy for this Tagout.

SAT / UNSAT Task Standard(s)

The operator indentifies the tagout lacks the required isolations per EN-OP-102. SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011A S3 Revision: 0 Page: 6 of 8 Admin Task

Review Adequacy of a Tagout Follow-Up Questions & Answers
Comments:

Give this page to the student Initial Condition(s):

The Plant is operating at rated power.

The Motor Driven Fire Pump C002

-N needs a new impeller.

The pump motor will need to be removed for access.

Initiating Cue(s):

As CRS you are tasked to verify the adequacy of the proposed tagout for work on the Motor Driven Fire Pump C002

-N. Document errors or inadequate boundaries.

NUCLEAR MANAGEMENT MANUAL N ON-Q UALITY R ELATED EN-OP-102-01 REV. 7 I NFORMATIONAL USE PAGE 7 OF 26 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.3 TAGOUT T AG S SHEET CLEARANCE: ___MANUAL___________

TAGOUT: ___XXXX________ Tag Serial No. Tag Type Equipment Equipment Description Equipment Location Place. Seq. Placement Configuration Place. 1st Verif Date/Time Place. 2nd Verif Date/Time Rest. Seq. Restoration Configuration Rest. 1st Verif Date/Time Rest. 2nd Verif Date/Time Placement/Removal Tag Notes 1 D NSP64-F160 Mtr Driven Fw Pmp Casing Dr BLDG FW PUMP HOUSE ELEV 132' 5 OPEN 2 D NSP64-F108 Mtr Driven Fw Pmp Suction BLDG FW PUMP HOUSE ELEV 132' 4 CLOSE 4 D NSP64-F016 Mtr Driven Fw Pmp Disch BLDG FW PUMP HOUSE ELEV 132' 3 CLOSE 5 D 52-11305 MD Fire Pump 11BD3 2 OPEN 6 D HS M 002 MD Fire Pump Local Stop PB SH 22-P 134 1 Depressed ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AS 4 Revision: 0 Page: 1 of 6 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-AS4 Time Critical Alternate Path Validation Time:

1 5 min TITLE: Review Radwaste Discharge Permit New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

THIS DOCUMENT REPLACES
REVIEW / APPROVAL (Print Name):

TEAR Approval ( )

Prepared By:

Mark Pait 6/2/2011 **Preparer Date Ops Review

++: Mark Goodwin 10/6/2011 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Keith Huff 10/6/2011 Training Representative Date Approved By:

Kane Ryder 10/6/2011 +Discipline Training Supervisor Date Approval Date:*

10/6/2011

  • Indexing Information ** The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklis

t. ++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS) 04-1-01-T42-1 Rev 28 ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011A S4 Revision: 0 Page: 2 of 6 Admin Task: Review Radwaste Discharge Permit Setting: Classroom Type: S RO Task: SRO-ADMIN-ADMI N-22 K&A: 2.3.6 (2.0/3.8) Safety Function

NA Time Required
1 5 minutes Time Critical
No Faulted: No Performance
Actual Reference(s)
ODCM, 01-S-08-11 Radioactive Discharge Controls Handout(s)
01-S-08-11 including a prepared Attachment 1 (attached) ODCM (Available)
  1. Manipulations
NA # Critical Steps
1 Group: NA Simulator Setup/Required Plant Conditions
None Safety Concerns
None ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011A S4 Revision: 0 Page: 3 of 6 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

Radwaste is preparing for a Batch Liquid Discharge of the Floor Drain Sample Tank "B" A009B.

Initiating Cue(s):

Radwaste has asked you to review the Batch Liquid Radwaste Discharge Permit.

Record 4 errors on provided discharge permit. All ODCM calculations were performed correctly.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011A S4 Revision: 0 Page: 4 of 6 Admin Task

Review Radwaste Discharge Permit Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

This task is to perform the SRO review of the Batch Liquid Radwaste Discharge Permit performed by the Shift Manager to authorize a controlled release of liquid radwaste

. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: EN-OP-102 5.3 [2] (e)

/ Att. 9.2

  • The operator must identify four of the following errors
  • The current dilution flow in Part 1 is less than the minimum required dilution flow in Part 2.
  • The Pre-Release Analysis sample time of Part 2 should be after the Radwaste monitor background reading verified time of Part 1.
  • The minimum Blowdown Flow Rate Setpoint of Part 3 is 100 gpm vice 6800 gpm.
  • The maximum Tank Discharge Flow Rate Setpoint is 6800 gpm vice 100 gpm.
  • The Effluent Monitor Alarm Setpoint is 45,200 cpm vice 4,520 cpm.
  • The Effluent Monitor Trip Setpoint is 116,000 cpm vice 11,600 cpm.

Standard: Identifies at least 4 listed errors

. Cue: Notes: Task is complete when the operator identifies errors SAT / UNSAT Task Standard(s)

The operator indentifies 4 of the 5 errors in the Batch Liquid Radwaste Discharge Permit.

SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011A S4 Revision: 0 Page: 5 of 6 Admin Task

Review Radwaste Discharge Permit Follow-Up Questions & Answers
Comments:

Give this page to the student Initial Condition(s):

Radwaste is preparing for a Batch Liquid Discharge of the Floor Drain Sample Tank "B" A009B.

Initiating Cue(s):

Radwaste has asked you to review the Batch Liquid Radwaste Discharge Permit.

Record 4 errors on provided discharge permit

. All ODCM calculations were performed correctly.

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 0 1-S-08-11 Revision: 112 Attachment I Page 1 of 4 BATCH LIQUID RADWASTE DISCHARGE PERMIT

YY-MM-DD-01

Part 1 Pre-Relea se Processing Release Number

Date Today Time 0300 Tank to be released Floor Drain A00 9B Volume 28,560 gal Tank is isolated. Recirculation started Yesterday/1500 Date/Time Dilution flow 6,200 gpm Radwaste monitor background reading 1,700 cpm Monitor reading is less than 10,800 cpm Mark Pait____________

Operator

Radwaste monitor background reading verified Kane Ryder

_________Today/0417

___

Radwaste Specialist or /Date/Time

Control Room Supervisor

_________________________

______________________________

_______________

Part 2 Pre-Release Analysis

20YY-XXX

Batch Number Sample Date Today Time 0345 One Total Suspended Solids (TSS) sample has been collected and analyzed for the month:

Yes X Initials MR No TSS mg/l (< 30mg/l)

Minimum dilution factor 3.2

Minimum dilution flow rate setpoint 6,800 gpm Maximum tank discharge flow rate setpoint 100 gpm Effluent Monitor Alarm Setpoint 4.52 E +3 cpm (Hi)

Effluent Monitor Trip Setpoint 1.16 E +4 cpm (Hi-Hi)

The radioactive liquid from the tank designated above is within the ALARA criteria of 10CFR50 App I as defined by surveillance 06

-CH-SG17-P-0041 and 06

-CH-SP41-P-0035 and may be released.

All significant peaks were identified.

Michael Rash

Radiochemist

Independent Verification if Effluent Radiation Monitor Inoperable.

NA Radiochemist Comments:

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 0 1-S-08-11 Revision: 112 Attachment I Page 2 of 4 BATCH LIQUID RADWASTE DISCHARGE PERMIT Part 3 Monito r Setpoint Calibration Batch Number (from Part 2) 20YY-XXX Setpoints Adjusted to:

Minimum Blowdown Flow Rate Setpoint

(Circ Water Blowdown Flow Setpoint) 100 gpm Maximum Tank Discharge Flow Rate Setpoint (Liquid Radwaste Effluent Flow Setpoint) 6,800 gpm Effluent Monitor Alarm Setpoint 45,200 cpm (Hi)

Effluent Monitor Trip Setpoint

116,000 cpm (Hi-Hi) David A Cooper

/ Today I&C Technician Date

Carlos Dawson

/ Today Verified

Date Copies of Pages 1 and 2 of this permit have been placed in the Control Room Setpoint Logbook, and The previous Pages 1 and 2 have been removed.

David A Cooper

/ Today I&C Technician Date Carlos Dawson

/ Today Verified

Date Part 4 Releas e Authorization The designated tank may be released provided the discharge and dilution flows meet the criteria of Part 2.

/ Shift Manager Date

Part 5 Release Valve lineup Verified

________________________________

/

_______________

Independent Verification

if Radiation Monitor Inop From Step 6.4.2e(2): On the date of release , prior to opening SG17

-F355 DRAIN BASIN ISOL VLV, have chemistry verify the Total Suspended Solids analysis for this tank has been completed or is not required.

The Total Suspended Solids analysis for this tank has been completed.

_____________

/

Radiochemist

Date Radiation Monitor Reading

Before release cpm Maximum during release cpm Average during release cpm GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 0 1-S-08-11 Revision: 112 Attachment I Page 3 of 4 BATCH LIQUID RADWASTE DISCHARGE PERMIT Part 5 (Cont.) Release Tank Level Before

__

After

__ Gallons Released

Average Release Rate (Tank Discharge Rate GPM)

Flo w Rate Indication During Discharge

a) Maximum Radwaste Tank Effluent Flow gpm b) Average Dilution Flow

gpm

1) Circulation Water Blowdown Flow

, ,

gpm 2)* Discharge Canal Flow

, ,

gpm

  • Flow must be estimated at intervals not to exceed every four hours during discharge; N/A if normal indication is operable.

c) If either a) or b) is inop, flow must be estimated at intervals not to exceed every four hours (N/A if normal indication/monitor is operable)

/

Start

/

Approx. Middle

/

End Flow Time LCO No.

DATE AND TIME

ELAPSED TIME VALVES OPEN VALVES SHUT

TOTAL

Monitor flushed

__________

______

Initials Operator

__________________________ Radwaste Specialist or Control Room Supervisor

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 0 1-S-08-11 Revision: 112 Attachment I Page 4 of 4 BATCH LIQUID RADWASTE DISCHARGE PERMIT Par t 6 Post-Release Analysis The post-release analysis is based on actual data recorded during the release

Comments:

/

Radiochemist Date

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AS5 Revision: 0 Page: 1 of 6 Rtype:

QA Record Number of pages

Date Initials TRAINING PROGRAM:

NRC Operating Exam JPM-AS5 Time Critical Alternate Path Validation Time:

1 5 min TITLE: D C Electrical Failures

- EAL Determination New Material Minor Revision Major Revision Cancellation REASON FOR REVISION

THIS DOCUMENT REPLACES
REVIEW / APPROVAL (Print Name):

TEAR Approval ( )

Prepared By:

Mark Pait 6/2/2011 **Preparer Date Ops Review

++: Mark Goodwin 10/4/2011 Technical Reviewer (e.g., SME, line management)

Date Validated By:

Keith Huff 10/5/2011 Training Representative Date Approved By:

Kane Ryder 10/5/2011 +Discipline Training Supervisor Date Approval Date:*

10/5/2011

  • Indexing Information
    • The requirements of the Training Material Checklist have been met.

+ Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on TQJA-201- DD06, Training Material Checklist.

++ Indicates that Operations has reviewed and approved this material for exam use.

FLEET/REGIONAL PROGRAM CONCURRENCE

Fleet ENS ENN Not Applicable DATE TRANSMITTED TO RM INITIAL RECEIPT BY RM (DATE/INITIAL)

RETURNED FOR CORRECTIONS (DATE/INITIAL)

RETURN RECEIPT (DATE/INITIAL)

FINAL ACCEPTANCE BY RM (DATE/INITIALS) 04-1-01-T42-1 Rev 28 ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AS5 Revision:

0 Page: 2 of 6 Admin Task: DC Electrical Failures

- EAL Determination Setting: Classroom Type: S RO Task: S RO-A&E-015 K&A: 2.4.41 (2.9/4.6)

Safety Function

NA Time Required
15 minutes Time Critical
Yes Faulted: No Performance
Actual Reference(s)
10-S-01-1, Activation of the Emergency Plan Handout(s)
10-S-01-1 Flow Charts
  1. Manipulations: NA # Critical Steps
1 Group: NA Simulator Setup/Required Plant Conditions
None Safety Concerns
None ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AS5 Revision:

0 Page: 3 of 6 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The Plant is operating in Mode 3 with a plant shutdown in progress due to loss of DC bus 11DA. A bus fault occurred on ESF bus 16AB. Electrical estimates that the bus may be re

-energized in approximately 45 minutes.

An operator reported 20 minutes ago that 11DB bus voltage is 104 VDC and trending down.

A fire that began 18 minutes ago continues to burn in the Division 3 battery room. The fire has caused damage to the 11DC bus and the bus was de

-energized.

Initiating Cue(s):

Classify the event.

This is a time critical task.

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AS5 Revision:

0 Page: 4 of 6 Admin Task

DC Electrical Failures

- EAL Determination Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

Event classification JPM in accordance with Emergency Preparedness Plan.

Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 10-S-01-1

  • Classify the event as a SITE AREA EMERGENCY Standard: EAL SS4, Site Area Emergency Cue: Notes: Requirements to satisfy HA4, Alert are also met.

SAT / UNSAT Task Standard(s)

Within 15 minutes, classify the event as a Site Area Emergency in accordance with EAL SS4. SAT / UNSAT

ENTERGY NUCLEAR JOB PERFORMANCE MEASURE Number: GJPM-OPS-2011AS5 Revision:

0 Page: 5 of 6 Admin Task

DC Electrical Failures

- EAL Determination Follow-Up Questions & Answers

Comments:

Give this page to the student Initial Condition(s):

The Plant is operating in Mode 3 with a plant shutdown in progress due to loss of DC bus 11DA. A bus fault occurred on ESF bus 16AB. Electrical estimates that the bus may be re

-energized in approximately 45 minutes.

An operator reported 20 minutes ago that 11DB bus voltage is 104 VDC and trending down.

A fire that began 18 minutes ago continues to burn in the Division 3 battery room. The fire has caused damage to the 11DC bus and the bus was de

-energized.

Initiating Cue(s):

Classify the event.

This is a time critical task.

Appendix D Scenario Outline Form ES-D-1 Scenario 1 Page 1 of 3 Revision 1 Facility:

Grand Gulf Nuclear Station Scenario No.: 1 Op-Test No.:

12/11 Examiners: ____________________________ Operators:

_____________________________

____________________________

_____________________________ ____________________________

_____________________________

Objectives:

To evaluate the candidates' ability to operate the facility in response to the following evolutions:

1. Inoperable Primary Containment Air Lock
2. Rotate CRD Pumps.
3. Respond to a CRD Pump Trip.
4. Lower reactor power using Recirc Flow Control.
5. Respond to a Recirc Pump Trip.
6. Respond to ST

-11 and 15AA lockout.

7. Take actions for RPS fails to scram.
8. Take actions for an ATWS. 9. Respond to a FW Line A Break in the Drywell.

Initial Conditions:

Operating at 100% power.

Inoperable Equipment:

None Turnover: The plant is at rated power. Rotate CRD pumps in accordance with the C11

-1 SOI in preparation for CRD pump "A" maintenance

. There is no out of service equipment and EOOS is GREEN. It is a division 1 work week.

Scenario Notes:

This scenario was written from lesson plan GSMS

-RO-EP033 revision 6. Attributes have been altered in order to meet the requirements of NUREG 1021 ES

-301 section D.5.b , and is considered significantly modified

. Validation Time:

60 minutes

Appendix D Scenario Outline Form ES-D-1 Scenario 1 Page 2 of 3 Revision 1 Event No. Malf. No. Event Type f Event Description 1 TS (CRS) Primary Containment Air Lock seal fails to inflate (TS 3.6.1.2) 2 N (BOP) Rotate CRD pumps (SOI 04-1-01-C11-1 section 5.5) 3 C11028b C (BOP) A (CREW) CRD pump Trip (CRD Malfunctions (05-1-02-IV-1) ONEP section 2.1.2) 4 N (BOP) R (ACRO) Lower generator load by 200 MWe using FCV's (IOI 03-1-01-2 Attachment VIII) 5 rr012a C (ACRO) R (BOP) A (CREW) Recirc Pump Trip (Reduction in Recirc Flow (05-1-02-III-3) ONEP) 6 r21133a r21139e M (CRS, BOP) Service Transformer 11 and ESF 15AA bus lockout (Loss of AC Power (05-1-02-I-4) ONEP) 7 c71076 I (ACRO) RPS fails to scram the reactor when the second Recirc pump trips and the Exclusion Region of the power to flow map is entered (Reduction in Recirc Flow (05-1-02-III-3) ONEP) Second Recirculation pump trips. Crew inserts manual reactor scram as observed by control rods inserted and scram annunciators received. Criterion is to give the highest priority to insert a manual scram.

Appendix D Scenario Outline Form ES-D-1 Scenario 1 Page 3 of 3 Revision 1 8 c11164 e51044 M (All) ATWS <4% power with reduced feed capability (EP-2A) When EP-2A requires Emergency Depressurization, Crew terminates and prevents all injection except boron, CRD, and RCIC per 02

-S-01-27 Operations Philosophy. Feedwater and ECCS system alignments prevent injection into the RPV as evidenced by available instrumentation. Criterion is to give the highest priority to prevent all injection except boron, CRD, and RCIC until reaching MSCP.

Reactor pressure decreases to MSCP. Crew commences and slowly raises injection utilizing available EP

-2A Table 4 and/or Table 5 systems with RPV level restored and maintained to greater than

-191". Criterion is to give the highest priority to restore RPV level greater than

-191". 9 fw171a rr063a M (ACRO) Feedwater Line A rupture inside the Drywell.

f (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

, (A)bnormal (TS) Tech Spec

  • Critical Task (As defined in NUREG 1021 Appendix D)

Quantitative Attributes Table Normal Events 2 Abnormal Events 2 Reactivity Manipulations 2 Total Malfunctions 7 Instrument/Component Failures 3 EP Entries (Requiring substantive action) 1 Major Transients 3 EP Contingenci es 1 Tech Spec Calls 1 Critical Tasks 4

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 1 of 21 Revision 1 Simulator Setup:

A. Initialization

1. Startup the simulator using Simulator Instructor's Job Aid section 6.3

.

2. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
3. Set the Simulator to IC-31 and perform switch check (Using Quick Reset in Director)

. 4. Click on "Open" in the Schedule window and Open Schedule File "2011 NRC Scenario 1.sch

" (in the Schedule Directory)

5. In Schedule window, click on the "Stopped" red block. The red block will change to a green arrow and indicate the scenario is active ("Running"). 6. Click the Summary tab in the Director window. Verify the schedule files are loaded and opened per Section B below. (Note: Any actions in the schedule file without a specific time will not load into the director until triggered.)
7. Take the simulator out of freeze.

Note: Prior to running the Schedule File, ensure no Event Files are Open.

If an existing Event File is Open prior to running the Schedule File, then any associated Event Files will not automatically load.

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 2 of 21 Revision 1 8. Clear any graphs and trends off of SPDS.

9. Ensure the correct rod movement sequence available at the P680.
10. Advance all chart recorders and ensure all pens inking properly.
11. Verify or perform the following: IC

-31 12. Run through any alarms and ensure alarms are on. (Note: On T

-Rex, to verify alarms are ON, the indicator will indicate "Alarms On").

13. Place the simulator in Freeze.

B. File loaded verification:

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 3 of 21 Revision 1 Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 4 of 21 Revision 1 Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 5 of 21 Revision 1 Crew Turnover:

A. Assign the candidates crew positions.

B. Turnover the following conditions:

Power 100% Pressure 10 25 psig B OC EOOS GREEN Planned Evolutions this shift

Mechanical will be performing maintenance on CRD pump "A" later this shift. Rotate CRD pumps per the C11

-1 SOI when you take the shift

. Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1 will not be provided for this scenario.

C. Allow the crew to perform pre

-shift brief and review procedures for planned evolutions.

D. Bring the crew into the Simulator , place the simulator is in RUN.

E. Allow the crew to walk down panels.

F. When the crew assumes the shift begin Scenario Activities.

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 6 of 21 Revision 1 SCENARIO ACTIVITIES:

Rotate CRD Pumps (Normal)/Containment door seal failure(tech spec call only)

A. The crew will start CRD pump B and stop CRD pump A using 04 01-C11-1, Control Rod Drive Hydraulic System SOI.
1. When directed by the Control Room to perform pre

-pump start checks:

a. Report that CRD pump "B" oil sump, motor and gearbox oil levels are normal and pre-pump start check is complete.
2. When directed by the Control Room to CLOSE C11-F217B: a. Wait 30 seconds then report to the Control Room "C11

-F217B is closed." 3. When directed to vent CRD pump "B" by opening then closing C11

-F109B: a. Wait 30 seconds then report "C11

-F109B was cycled open then shut. CRD pump B is vented." 4. When directed by the Control Room to OPEN C11-F217B: a. Wait 45 seconds then report to the Control Room "C11

-F217B is open."

b. Call the Control Room and report as the Aux Building Rover that you were unable to get the seal to inflate for the Aux Building door Air Lock on 119' elevation.
c. The CRS will enter TS 3.6.1.2 condition A.
d. If directed by the CRS, report that Containment door in the 119' elevation Air Lock is closed with the seal inflated.
5. When directed by the Control Room to CLOSE C11-F217A: a. Wait 30 seconds then report to the Control Room "C11

-F217A is closed."

6. When directed by the Control Room to OPEN C11-F217A: a. Wait 45 seconds then report to the Control Room "C11

-F217A is open."

7. When directed by the Control Room to Check CRD purge flows are 1.5 to 2.5 gpm on C11-FI-R020A & B:
a. Report to the Control Room that CRD purge flows are 2 gpm on both CRD pumps.

CRD Pump Trip (Control Rod/Drive Malfunctions ONEP): B. CRD pump "B" will trip 2 minute s after CRD pump "A" is stopped (Auto Event 5)

. C. The crew will take Immediate Operator Action per CRD malfunctions ONEP to restart CRD pump A.

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 7 of 21 Revision 1 D. If asked as the local operator to investigate the pump trip, wait 3 minutes and report back to the Control Room that CRD pump "B" breaker 152

-1605 tripped on over current. If sent to the pump to investigate, report that CRD pump "B" is hotter than normal and is not running.

E. Give the crew time to allow them to perform a transient brief before moving to the next step.

Reduce reactor power using FCVs (Normal/Reactivity):

F. Call the control room as the Shift Manager and direct the CRS to lower generator output by 200 MWe for a temporary down power requested by the Load Dispatcher. All notifications have been made.

1. The crew will lower power using 03 01-2, Power Operations IOI, Attachment VIII.

Recirc Pump Trip (Reduction in Recirc ONEP):

G. When generator output is below 1275 MWe, Auto Event 8 will cause Recirc Pump "A" to trip. 1. The crew will take actions for Reduction in Recirc Flow Rate ONEP (THI watch, one Recirc pump stopped, and Exit Restricted Region).

SCRAM/FW Line Rupture/ATWS:

H. When the Restricted Region is exited and the lead evaluator is ready to move on, trigger Event 10 to insert malfunctions r2133a and r21139e to cause a lockout on Service Transformer 11 and 15AA

. (Install EP Attachments as directed

). 1. With no Recirc Pumps running, the reactor will enter the Exclusion Region of the power to flow map. An automatic scrams are disabled; therefore, the ACRO must manually insert a scram.

2. The BOP will reenergize 12HE and 13AD with the Alternate Feeder Breakers.
3. When directed by the control room, trigger EVENT 11 to reset Under Voltage Lockouts on 12HE and 13AD. Wait 3 minutes to report that the lockouts were reset.
4. When the ACRO inserts a scram, the leak on the "A" FW line (fw171 a) will be inserted after a 7 minute delay. This will prevent using Feed and Condensate to feed the reactor.
5. When the CRS directs Attachment 12 to be installed, install attachment 12 as "Done." Wait until reactor level is below

-160" and then take the attachment paperwork to the CRS and report that attachment 12 is installed with the exception of B21

-F065A being closed.

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 8 of 21 Revision 1 Termination:

I. Once emergency depressurization has been conducted and reactor water level is stabilized above TAF, using RHR B E12

-F053B, or as directed by Lead Evaluator

, take the simulator to Freeze and turn horns off

. Critical Tasks:

Second Recirculation pump trips. Crew inserts manual reactor scram as observed by control rods inserted and scram annunciators received. Criterion is to give the highest priority to insert a manual scram.

When EP-2A requires Emergency Depressurization, Crew terminates and prevents all injection except boron, CRD, and RCIC per 02

-S-01-27 Operations Philosophy. Feedwater and ECCS system alignments prevent injection into the RPV as evidenced by available instrumentation. Criterion is to give the highest priority to prevent all injection except boron, CRD, and RCIC until reaching MSCP.

Reactor pressure decreases to MSCP. Crew commences and slowly raises injection utilizing available EP

-2A Table 4 and/or Table 5 systems with RPV level restored and maintained to greater than

-191". Criterion is to give the highest priority to restore RPV level greater than

-191". Emergency Classification:

Site Area Emergency on SS3 and FS1

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 9 of 21 Revision 1 Op-Test No: 12/11 Scenario No:

1 Event No:

1 Event

Description:

Inoperable Primary Containment Air Lock TIME Positio n Applicant's Actions or Behavior CRS When the Auxiliary Building Rover reports that the Containment air lock on the 119' elevation fails to inflate:

Declares Primary Containment Air Lock on 199' elevation INOPERABLE and enters TS 3.6.1.2 Condition A.

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 10 of 21 Revision 1 Op-Test No: 12/11 Scenario No:

1 Event No:

2 Event

Description:

Rotate CRD Pumps TIME Position Applicant's Actions or Behavior CRS Directs the BOP to Rotate CRD pumps in accordance with SOI 04 01-C11-1. BOP Rotates CRD pumps using SOI 04 01-C11-1 section 5.5:

Notifies the local operator to perform pump pre

-start checks.

Notifies the local operator to CLOSE C11

-F217B. Notifies the local operator to cycle OPEN and SHUT C11

-F109B to vent CRD pump B. Starts CRD pump B.

(The BOP should alert the ACRO that he is starting the CRD B pump)

Notifies the local operator to SLOWLY OPEN C11

-F217B. Check CRD system flow has stabilized between 54 to 66 gpm.

Notifies the local operator to CLOSE C11

-F217A. Stops CRD pump A.

Notifies the local operator to OPEN C11

-F217A. Check CRD system flow is between 54 to 66 gpm.

Notifies the local operator to check CRD purge flows are 1.5 to 2.5 gpm on C11-FI-R020A & B. Check that Reactor Recirculation Seal pressure has not changed.

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 11 of 21 Revision 1 Op-Test No: 12/11 Scenario No:

1 Event No:

3 Event

Description:

CRD Pump Trip TIME Position Applicant's Actions or Behavior BOP Recognizes and reports that CRD Pump B has tripped off.

As indicated by annunciator P601

-22A-C-3, CRD PMP A/B AUTO TRIP.

CRS Enters the CRD Malfunctions ONEP.

Ensures immediate actions for CRD pump trip are performed.

ACRO Monitor for HCU faults.

BOP Take immediate operator actions per CRD malfunctions ONEP (from memory).

Place CRD SYS FLO CONT (C11-R600 on P601

-22B) in MANUAL and REDUCE output to zero.

Start CRD pump A.

Slowly adjust CRD SYS FLO CONT to 54

-66 gpm after charging pressure returns to normal. (~1700 psig)

Return CRD SYS FLO CONT to AUTO with tapeset at 54

-66 gpm. THERE ARE NO REQUIRED SUBSEQUENT ACTIONS FOR THIS EVENT CREW Ensure that an operator or electrician is sent to investigate the cause of the pump trip.

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 12 of 21 Revision 1 Op-Test No: 12/11 Scenario No:

1 Event No:

4 Event

Description:

Lower Generator Output 200 MWe TIME Position Applicant's Actions or Behavior CRS Conducts reactivity brief for the planned power reduction.

Power Reduction is per IOI-2 attachment VIII.

Directs the ACRO to lower reactor power using the Recirc FCV's in slow detent.

Directs the BOP to maintain Load Demand +/

- 25 MW of Load Demand Limited.

ACRO Lowers power by closing the Recirc FCVs A & B using loop flow controllers B33K603A & B in slow detent on P680

-3B (IOI-2 attachment VIII step 12.3)

. BOP Lowers Load Demand as power is reduced by depressing EHC LOAD REF DEMAND LOWER pushbutton (P680

-9C) to maintain generator actual load within +/

- 25 MW of the load demand limited value during power reduction (IOI-2 attachment VIII step 12.2).

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 13 of 21 Revision 1 Op-Test No: 12/11 Scenario No:

1 Event No:

5 Event

Description:

Recirc Pump Trip TIME Position Applicant's Actions or Behavior ACRO Recognizes and reports that Recirc Pump A has tripped off.

As indicated by annunciator P680

-3A-B-4, RECIRC PMP A OVERLD/TRIP CRS Enters the Reduction in Recirculation ONE P. ACRO Reports Entry into the Restricted Region of the power to flow map.

Establishes THI watch without concurrent duties.

CRS Directs the BOP to Close the B33

-F067A (Recirc Pump A discharge valve).

BOP Shuts B33-F067A (P680

-3C). CRS Initiate actions to exit the Restricted Region by either opening Recirc FCV B or inserting CRAM rods.

Conducts reactivity brief for unplanned power change.

BOP Exits the Restricted Region by either opening Recirc FCV B or inserting CRAM rods as directed by the CRS

. ACRO Peer checks the BOP if CRAM rods are inserted.

CRS Once the Restricted Region is exited, direct the following actions (per the Reduction in Recirc ONEP subsequent actions)

Ensure the operating Recirc Loop flow is <44,600gpm.

Re-open B33-F067A after it is closed for 5 minutes.

Open the Recirc "A" FCV to the maximum position.

Inform the Reactor Engineer that Single Loop set points need to be established and surveillance 06

-RE-1J11-V-001 must be performed

. The CRS will not have time to address each of these actions since the scenario will move forward once the Restricted Region is exited.

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 14 of 21 Revision 1 Op-Test No: 12/11 Scenario No:

1 Event No:

7 Event

Description:

Lockout on ST11 and 15AA TIME Position Applicant's Actions or Behavior BO P Recognizes and reports to the CRS a lockout on ST11.

As indicated by annunciators P807

-2A-A-4/5, SVC XFMR 11 PRI/SEC LOCKOUT TRIP.

The ST11 lockout will cause a loss of the remaining Recirc pump Takes Immediate Actions for Loss of AC Power.

Re-energizes the 12HE and 13AD busses using the Alternate Feeders (P807

-1C/2C). Directs the local operator to RESET under voltage lockouts on 13AD and 12HE busses.

CRS / BOP Ensure that Electrical Maintenance is dispatched to recover the 15AA bus.

CRS Enters the Loss of AC Power ONEP.

Ensures immediate actions for Loss of AC Power ONEP are performed.

Ensure 12HE and 13AD are reenergized.

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 15 of 21 Revision 1 Op-Test No: 12/11 Scenario No:

1 Event No:

8 Event

Description:

Failure of RPS to Scram TIME Position Applicant's Actions or Behavior ACRO

(The RPS automatic scram has been disabled)

Report to CRS that he is placing the Mode SW in SHUTDOWN.

Place the Mode SW to SHUTDOWN.

Provides a scram report:

Reactor Mode SW in SHUTDOWN.

All Rods are NOT Inserted (Hyd Block ATWS).

Reactor power is below 4%.

Reactor water level and trend.

Reactor pressure and trend.

Feedwater is recoverable (but will be lost when the MSIV's close on loss of air to containment).

Bypass valves are available.

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 16 of 21 Revision 1 Op-Test No: 12/11 Scenario No:

1 Event No:

9 Event

Description:

ATWS TIME Position Applicant's Actions or Behavior CRS Enter the SCRAM ONEP and the Turbine and Generator Trips ONEP.

Enter EP-2, when ATWS is discovered Enter EP

-2A. CRS Direct actions of EP

-2A steps 1 - 4: Directs ACRO to Verify Recirc Pumps transferred to LFMG.

Directs ACRO to Verify ARI/RPT initiation.

Directs BOP to inhibit ADS.

Directs BOP to Override HPCS injection.

ACRO Verify Recirc Pumps transferred to LFMG.

Verify/Initiate ARI/RPT.

BOP Inhibits ADS.

Place ADS "A" and ADS "B" keylock switches to "INHIBIT" Override HPCS injection.

Place the HPCS pump handswitch to the "STOP" position.

Place the E22

-F004, HPCS injection valve, handswitch to the "CLOSE" position. CRS Direct the ACRO or BOP to verify Division 3 generator running with cooling water and that Isolations for Reactor Level 2 are completed.

ACRO / BOP Verify Division 3 Diesel Generator is running with cooling water.

Isolations for Reactor Level 2 are completed.

CRS Enter EP-2A step L-6 or L-7 and direct the ACRO to e stablish level band

-70 to -130" (The CRS may initially establish a band of 11.4 to 53.5", but since the ATWS is producing significant heat, he should opt to lower level to lower power

). Enter EP-2A step P-4 and direct the BOP to establish a pressure band 80 0 - 1060 psig using IPC and BCV Manual Jack (The CRS may establish a pressure band of 450 - 600 psig when the MSIV's close and the Feed pumps subsequently trip

). Call for EP Attachments 8 , 12, 18, 19, 20, and 28 (only attachment 12b and 28 will be useful, the CRS may opt to only call for these attachments).

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 17 of 21 Revision 1 Op-Test No: 12/11 Scenario No:

1 Event No:

9 Event

Description:

ATWS BOP If directed by the CRS, Reduce reactor pressure using IPC (by depressing the "PRESS REF LOWER" PB) and BCV Manual Jack (by depressing the "MAN BYP ON/OFF" PB and then the "MAN BYP CONT LOWER" PB) to pressure band 450

- 600 psig. ACRO Line up Feed and Condensate systems for Startup Level Control using hard card.

If two Feed pumps are running, trip one.

Close N21-F009A and N21

-F009B. Open N21-F001, N21-F010A and N21

-F010B. Verify Closed N21

-F513, N21-F510, N21-F040. If no Feed pumps are in operation, start one.

o Ensure RFPT A(B) controls "Manual" pushbutton is backlit.

o Verify AC lube oil pump is running o Open N2 1-F014A(B) o Depress the TRIP RESET pushbutton o Depress the RAISE pushbutton to establish Feed pump discharge pressure above reactor pressure by approx. 250 psig.

Open/Verify Open N21

-F014A or N21

-F014B Maintain reactor level in Auto or Manual using the Startup level controller or Manually using N21

-F040 or N21

-F009A(B). Feed the reactor using the Startup Level Controller to maintain reactor level within the set level band (11.4 to 53.5" or

-70 to -130").

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 18 of 21 Revision 1 Op-Test No: 12/11 Scenario No:

1 Event No:

10 Event

Description:

Feedwater Line A rupture in the Drywell TIME Position Applicant's Actions or Behavior ACRO Recognize symptoms of a FW Line A rupture in the Drywell.

As indicated by uneven feed flow to the reactor between the "A" and "B" feed water lines.

Also indicated by rising DW pressure and temperature.

Report the Feed water leak to the CRS.

Trip all condensate pumps. (This is necessary to stop the leak in the drywell since the feed water line isolations to the reactor have lost power, N21

-F065A and N21

-F065B.)

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 19 of 21 Revision 1 Op-Test No: 12/11 Scenario No:

1 Event No:

9 cont. Event

Description:

ATWS TIME Position Applicant's Actions or Behavior ACRO Keep CRS updated with reactor level as it trends down (following the loss of feed).

CRS When EP Attachment 12 is installed or reactor level reaches

-191", Exit Level and Pressure Legs of EP

-2A and Enter Emergency Depressurization.

When EP-2A requires Emergency Depressurization, Crew terminates and prevents all injection except boron, CRD, and RCIC per 02

-S-01-27 Operations Philosophy. Feedwater and ECCS system alignments prevent injection into the RPV as evidenced by available instrumentation. Criterion is to give the highest priority to prevent all injection except boron, CRD, and RCIC until reaching MSCP. CRS Verify SP level is above 10.5 ft.

Direct the BOP or ACRO operator to verify/perform Terminate and Prevent injection into the RPV by overriding low pressure systems (LPCS/LPCI)

Direct BOP to Open 8 ADS valves.

ACRO / BOP When directed, Terminate and Prevent injection into the RPV.

Verify HPCS is initiated with annunciators P601-16A-B-5, HPCS MTR CONT MAN OVERRD, and P601

-16A-D-5, HPCS INJ VLV F004 MAN OVERRD in.

Verify/perform low pressure ECCS systems overridden by ensuring division 2 ECCS initiation signal is present and placing the LPCI B and C pump hand switches to off and placing the E12

-F042B and C handswitches to CLOSE.

o This is verified by annunciators P601

-17A-B-1, RHR INJ VLV F042B MAN OVERRD, P601

-17A-C-2, RHR PMP B MAN OVERRD, P601

-17A-B-4, RHR INJ VLV F042C MAN OVERRD, and P601-17A-C-5, RHR PMP C MAN OVERRD in.

BOP Opens at least 7 ADS valves.

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 20 of 21 Revision 1 Op-Test No: 12/11 Scenario No:

1 Event No:

9 cont. Event

Description:

ATWS CRS Enter EP-2A step L-10 (following the Emergency Depressurization).

Establish reactor pressure as critical parameter for the ACRO.

ACRO Keep CRS updated with reactor pressure as it trends down.

CRS When reactor pressure is below MSCP (219 psig) direct ACRO to feed the reactor using RHR B via the E12

-F053B with 4000 gpm and then at intervals of 1000 gpm until reactor level begins to trend up.

  • Reactor pressure decreases to MSCP. Crew commences and slowly raises injection utilizing available EP

-2A Table 4 and/or Table 5 systems with RPV level restored and maintained to greater than

-191". Criterion is to give the highest priority to restore RPV level greater than

-191". Enter EP-2A step L-6 or L-7 and establish level band

-70 to -130". CRS Enter EP-3 on Suppression Pool Temperature and Drywell pressure; however, no substantial operator actions are expected for this entry during the scenario.

Appendix D Required Operator Actions Form ES-D-2 Scenario 1 Page 21 of 21 Revision 1 Give this page to the CRS Turnover the following conditions:

Power 100% Pressure 10 25 psig B OC EOOS GREEN Planned Evolutions this shift:

Mechanical will be performing maintenance on CRD pump "A" later this shift. Rotate CRD pumps per the C11

-1 SOI when you take the shift

. Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1 will not be provided for this scenario.

Appendix D Scenario Outline Form ES-D-1 Scenario 2 Page 1 of 3 Revision 0 Facility:

Grand Gulf Nuclear Station Scenario No.: 2 Op-Test No.:

12/11 Examiners: ____________________________ Operators:

_____________________________

____________________________

_____________________________ ____________________________

_____________________________

Objectives:

To evaluate the candidates' ability to operate the facility in response to the following evolutions:

1. Place SSW "A" in STANDBY.
2. Raise reactor power using Recirc Flow Control.
3. RPS "A" MG failure.
4. Electric Power Monitoring Assembly INOPERABLE

. 5. Two APRM channel failures.

6. Fuel cladding leak.
7. RCIC fails to start on initiation

. 8. RCIC room unisolable steam leak.

Initial Conditions: Operating at 85% power.

Inoperable Equipment:

APRM "F" is failed downscale and bypassed.

Turnover: A plant startup is in progress with all steps complete up to step 6.8 of Attachment II in 03 01-2 (Power Ascension From 60% to Full Power). The crew will place SSW "A" in STANDBY upon assuming the shift. When SSW "A" is in STANDBY, raise reactor power to 100% of rated.

Scenario Notes:

This scenario was written from lesson plan GSMS

-RO-EP015 rev. 8. Attributes have been altered in order to meet the requirements of NUREG 1021 ES

-301 section D.5.b , but is not considered significantly modified.

Validation Time:

50 minutes

Appendix D Scenario Outline Form ES-D-1 Scenario 2 Page 2 of 3 Revision 0 Event No. Malf. No. Event Type f Event Description 1 N (BOP) Place SSW "A" in Standby (SOI 04 01-P41-1 section 4.6) 2 N (BOP) R (ACRO) Raise Reactor power using FCV's (IOI 03 01-2 Att. 2 step 6.8) 3 c71077a C (BOP) A (CREW) RPS "A" MG failure (Loss of One or Both RPS Buses (05-1-02-III-2) ONEP) 4 TS (CRS) Electric Power Monitoring Assembly INOPERABLE (TS 3.3.8.2) 5 c51010f c51010d I (ACRO) TS (CRS) A (CREW) Two APRM channel failures (ARI/TS 3.3.1.1) 6 rr071 rm157a rrd21k648a_d rrd21k648 b_d rrd21k648 c_d rrd21k648 d_d M (CREW) R (ACRO) Fuel cladding leak (Off

-Gas Activity High (05-1-02-II-2) and SCRAM (05-1-02-I-1) ONEP) Fuel failure is occurring and main steam line radiation is greater than 3 times normal full power background as indicated by MSL B / MSL C RAD HI

-HI or MSL A / MSL D RAD HI-Hi alarms, the crew closes MSIVs and MSL drains per EP-4. The crew closes the MSIVs and MSL drains and observes valve position indications and lowering pressure trend downstream of the MSIVs. Criterion is to give the highest priority to close the four inboard MSIVs or the four outboard MSIVs and MSL drains when MSL radiation is greater than 3 times normal full power background.

7 e51043 DI_1E51M625D I (ACRO / BOP) RCIC fails to start on initiation (SOI 04 01-E51-1)

Appendix D Scenario Outline Form ES-D-1 Scenario 2 Page 3 of 3 Revision 0 8 e51187a e51187b rrd21k603 rrd21k613 M (CREW) I/C (ACRO / BOP) RCIC room unisolable steam leak (EP

-4) A primary system is discharging outside primary containment and area temperatures, radiation levels, or water levels are above their max safe values in two or more areas. The crew opens 8 ADS/SRVs and observes lowering pressure trend and valve position indications (tailpipe pressure indication lamps or solenoid valve energized). Criterion is to give the highest priority to open at least seven SRVs when area temperatures, radiation levels, or water levels are above their maximum safe values in two or more areas.

f (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec

  • Critical Task (As defined in NUREG 1021 Appendix D)

Quantitative Attributes Table Normal Events 2 Abnormal Events 2 Reactivity Manipulations 2 Total Malfunctions 5 Instrument/Component Failures 4 EP Entries (Requiring substantive action) 2 Major Transients 2 EP Contingencies 1 Tech Spec Calls 2 Critical Tasks 2

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 1 of 20 Revision 0 Simulator Setup:

A. Initialization

1. Startup the simulator using Simulator Instructor's Job Aid section 6.3

.

2. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
3. Set the Simulator to IC-3 3 and perform switch check (Using Quick Reset in Director)

. 4. Click on "Open" in the Schedule window and Open Schedule File "2011 NRC Scenario 2.sch" (in the Schedule Directory)

5. In Schedule window, click on the "Stopped" red block. The red block will change to a green arrow and indicate the scenario is active ("Running"). 6. Click the Summary tab in the Director window. Verify the schedule files are loaded and opened per Section B below. (Note: Any actions in the schedule file without a specific time will not load into the director until triggered.)
7. Take the simulator out of freeze.

Note: Prior to running the Schedule File, ensure no Event Files are Open.

If an existing Event File is Open prior to running the Schedule File, then any associated Event Files will not automatically load.

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 2 of 20 Revision 0

8. Clear any graphs and trends off of SPDS.
9. Ensure the correct rod movement sequence available at the P680.
10. Advance all chart recorders and ensure all pens inking properly.
11. Verify or perform the following:

IC-33 SSW "A" started APRM "F" is bypassed and caution tagged

12. Run through any alarms and ensure alarms are on. (Note: On T

-Rex, to verify alarms are ON, the indicator will indicate "Alarms On").

13. Place the simulator in Freeze.

B. File loaded verification:

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 3 of 20 Revision 0

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 4 of 20 Revision 0

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 5 of 20 Revision 0 Crew Turnover:

A. Assign the candidates crew positions.

B. Turnover the following conditions:

Power 85% Pressure 10 10 psig B OC EOOS GREEN A reactor startup is in progress with all steps complete up to step 6.8, Attachment II of 03-1-01-2 (Power Ascension from 60% to full power)

SSW "A" is in servic

e. APRM "F" has failed downscale and is in BYPASS (a tracking LCO was written).

Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1.b will not be provided for this scenario

. Planned Evolutions this shift

Place SSW "A" in STANDBY using 04 01-P41-1 SSW SOI. Once SSW "A" is in STANDBY, continue with plant startup and raise reactor power to 100%.

Ramp rates are not required until reactor power reaches 95%.

C. Allow the crew to perform pre

-shift brief and review procedures for planned evolutions.

D. Bring the crew into the Simulator , place the simulator is in RUN.

E. Allow the crew to walk down panels.

F. When the crew assumes the shift begin Scenario Activities.

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 6 of 20 Revision 0 SCENARIO ACTIVITIES:

Place SSW "A" in STANDBY A. The crew will place SSW "A" in STANDBY.

1. No operations outside the control room are required.

Raise reactor power to 100%:

B. The crew will raise reactor power to 100% using FCVs.

1. No operations outside the control room are required.
2. When APRM "A" reaches 90% power, RPS "A" MG will Trip (Auto Event 1).

RPS "A" MG set failure C. The crew will enter the Loss of One or Both RPS Buses ONEP and:

1. Re-energize RPS "A" by placing the MG Set "A" transfer switch to Alternate "A".
2. Reset the Half

-Scram 3. Ensure MSIVs are open.

a. When the BOP comes to the booth and asks the status of the pilot solenoids amperage on the back panels, reply that all MSIVs indicate normally.

D. When asked to investigate the cause of the bus trip, when the half

-scram is reset, inform the control room that

1. the RPS "A" MG EPA breaker C71S003A (located on the Control Building, 189' el.) is tripped and the undervoltage flag is tripped.
2. you have also noted that the alternate feeder EPA breaker C71S003G underfrequency flag is tripped, but the breaker is still closed (ensure that the CRS understands that this is the breaker currently powering the RPS "A" Bus).

APRM "D" fails upscale

E. When the CRS enters LCO 3.3.8.2 Condition "A," insert malfunction c51009d by triggering Event 2 to cause APRM "D" to fail full scale

. 1. Since APRM "F" is already in bypass, no operator action is required for this situation; however, the CRS may opt to place APRM "F" in service and bypass APRM "D" in order to clear the Half

-Scram.

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 7 of 20 Revision 0

2. When the CRS enters LCO 3.3.1.1 Condition "A," insert malfunction rr071 by triggering Event 3 to insert a Fuel Cladding Leak.

Fuel Cladding Leak F. When the OG PRE

-TREAT RAD HI annunciator alarms, the crew will enter the Off

-Gas Activity High ONEP.

1. If asked as RP to report local Pre

-treat rad levels, report them as above normal and trending up.

2. Prior to Pre

-treat radiation levels reaching 1,400 mR/hr, the CRS will direct the ACRO to lower core flow to 67 mlbm/hr.

3. When core flow is below 68.5 mlbm/hr, Auto Event 4 will trigger causing the Fuel Cladding Leak to worsen. a. The crew will enter the Reduction in Recirc Flow ONEP and the ACRO will become the THI watch with concurrent duties.
4. When the crew determines that Pre

-treat radiation levels cannot be maintained below 14,000 mR/hr, the crew will manually scram the reactor and enter the Reactor Scram and Turbine Trip ONEPs and EP

-2. Insert EP Attachments as directed by the Control Room. 5. 15 seconds after the scram Auto Event 5 will trigger causing Condensate Pumps to trip on low condenser level (due to failed trip unit, this is unrecoverabl e) 6. 2 minutes after the scram, MSL RAD HI annunciator will alarm and the CRS will enter

EP-4. 7. 4 1/2 minutes after the scram, MSL A

-D HI-HI annunciators will alarm. The CRS will direct the BOP operator to close all MSIVs per EP

-4 step 1. Unisolable steam leak RCIC room/RCIC fail to start on initiation G. After all MSIVs are closed the CRS will direct the ACRO/BOP operator to control reactor level using RCIC and HPCS.

1. The CRS should establish a reactor pressure band of 800

-1060 psig using ADS/SRV valves and a reactor level band of +30" to

-30". 2. Once the operating feed pump trips, RCIC will fail to initiate (when started by the operator or on low level). The operator must manually line up RCIC.

H. When E51-F045 opens, an unisolable steam leak will occur in the RCIC room. 1. The crew will receive RCIC room high temperature and radiation alarms. The E51

-F063 and E51-F064 will fail to close (loss of power, motor pinion key failed respectively).

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 8 of 20 Revision 0

2. The crew should enter the reduced pressure band 450

-600 psig to reduce driving head of the steam leak.

3. Five minutes after RCIC is started, report to the control room as Security that there is a plume of steam coming from the Auxiliary Building Roof.
4. When 2 max safe values (Rad levels) from EP-4 Table 10 are reached, the crew will enter the emergency depressurization procedure of EP

-2. Termination:

I. Once emergency depressurization has been conducted and reactor water level is stabilized above TAF, or as directed by Lead Evaluator

, take the simulator to Freeze and turn horns off

. Critical Tasks: Fuel failure is occurring and main steam line radiation is greater than 3 times normal full power background as indicated by MSL B / MSL C RAD HI

-HI or MSL A / MSL D RAD HI-Hi alarms, the crew closes MSIVs and MSL drains per EP

-4. The crew closes the MSIVs and MSL drains and observes valve position indications and lowering pressure trend downstream of the MSIVs. Criterion is to give the highest priority to close the four inboard MSIVs or the four outboard MSIVs and MSL drains when MSL radiation is greater than 3 times normal full power background.

A primary system is discharging outside primary containment and area temperatures, radiation levels, or water levels are above their max safe values in two or more areas. The crew opens 8 ADS/SRVs and observes lowering pressure trend and valve position indications (tailpipe pressure indication lamps or solenoid valve energized). Criterion is to give the highest priority to open at least seven SRVs when area temperatures, radiation levels, or water levels are above their maximum safe values in two or more areas.

Emergency Classification:

Site Area Emergency FS1 Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 9 of 20 Revision 0 Op-Test No: 12/11 Scenario No:

2 Event No:

1 Event

Description:

Place SSW "A" in Standby TIME Position Applicant's Actions or Behavior CRS Directs the BOP operator to place SSW "A" in standby.

BOP Places SSW "A" in Standby using SOI 04 01-P41-1 section 4.6:

Verifies all prerequisites are met N/A's steps 4.6.2a

- 4.6.2h. Places the SSW "A" MOV test switch to TEST Open/check open P41

-F006A. Close P41-F005A Ensure open P41

-F068A. Close/check close P41

-F014A. Close P41-F001A. Stop SSW Pump A.

Stop cooling tower fans A and B if running.

Stop O/A Fan Y47

-C001A.

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 10 of 20 Revision 0 Op-Test No: 12/11 Scenario No:

2 Event No: 2 Event

Description:

Raise reactor power using Recirc Flow Control TIME Position Applicant's Actions or Behavior CRS Conducts reactivity brief for the planned power change. (May be performed prior to taking the shift)

Directs the ACRO to raise reactor power to 100% using Recirc FCV's.

ACRO Raises power by opening the Recirc FCVs A & B using loop flow controllers B33K603A & B in slow detent on P680

-3B (IOI-2 attachment VIII step 12.3).

BOP Raises Load Demand as power is raised by depressing EHC LOAD REF DEMAND RAISE pushbutton (P680

-9C) to maintain generator actual load within +/

- 25 MW of the load demand limited value during power ascension (IOI-2 attachment VIII step 12.2).

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 11 of 20 Revision 0 Op-Test No: 12/11 Scenario No:

2 Event No:

3 Event

Description:

RPS "A" MG failure TIME Position Applicant's Actions or Behavior ACRO Recognizes and reports a half

-scram with no additional annunciators and a trip of the RPS bus has occurred

. As indicated by annunciator P680

-7A-A-2, RX SCRAM TRIP coupled with a 1/2 scram and no other indications for why the 1/2 scram occurred.

The GENERATOR A NORMAL FEED AVAILABLE light is out on the back panel. CRS Enters the Loss of One or Both RPS Buses ONEP

. Direct the BOP to re

-energize the A RPS bus using the alternate power source

. Direct the ACRO to reset the half

-scram. Send a local operator to investigate the cause of the RPS A MG failure.

BOP When directed, Re

-energize the A RPS Bus using the Alternate power source.

Place the MG SET A TRANSFER switch on P610 to ALT "A" ACRO When directed, reset the half

-scram. Place the division 1 scram RESET switches to RESET on the P680.

CRS Direct the BOP to ensure all MSIVs are energized.

BOP When directed, ensure all MSIV solenoid lights are on and all MSIV pilot solenoids indicate amperage on the P622 and P623 panels

. (This is not modeled in the simulator. The operator should go to the instructor booth behind the P807 and simulate performance by stating to the instructor his intentions to perform the step.

The instructor will provide the operator with a verbal cue concerning indications the operator observes).

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 12 of 20 Revision 0 Op-Test No: 12/11 Scenario No:

2 Event No:

4 Event

Description:

Electric Power Monitoring Assembly INOPERABLE TIME Position Applicant's Actions or Behavior CRS Recognizes entry conditions and enters TS 3.3.8.2 Condition A.

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 13 of 20 Revision 0 Op-Test No: 12/11 Scenario No:

2 Event No:

5 Event

Description:

Two APRM channel failures TIME Position Applicant's Actions or Behavior ACRO Recognizes and reports APRM D has failed upscale

. As indicated by annunciators P680

-7A-A-2, RX SCRAM TRIP, and P680

-7A-B-3, NEUTRON MON SYS TRIP APRM Ch-D will be "pegged" high and will have the UPSC ALM light on.

This will also cause a 1/2 scram. CRS Recognizes entry conditions and enters TS 3.3.1.1 Condition A and TRM 3.1.5 Conditions A & B

.

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 14 of 20 Revision 0 Op-Test No: 12/11 Scenario No:

2 Event No:

6 Event

Description:

Fuel Cladding Leak TIME Position Applicant's Actions or Behavior BOP Recognizes and reports to the CRS when the OG PRE

-TREAT RAD HI annunciator alarms. Directs the CRS to the Off

-Gas Activity High ONEP per the OG PRE-TREAT RAD HI ARI. CRS Enters the Off

-Gas Activity High ONEP.

Establish Off

-Gas Pre-Treat Radiation Level as a critical parameter.

ACRO / BOP Monitor Off

-Gas Pre-Treat Radiation Level.

Report Off

-Gas Pre-Treat Radiation Levels as directed by the CRS.

CRS When the CRS anticipates exceeding the limits of step 3.1 Pre

-Treatment Monitor Limit (70 0 mR/hr), directs the ACRO to lower core flow to 67 mlbm/hr in fast detent.

ACRO Lower core flow to 67 mlbm/hr using Recirc "A" and "B" FCV flow controllers in fast detent when directed by the CRS.

CRS Enters the Reduction in Recirculation Flow Rate ONE P. Ensures THI watch with concurrent duties is established.

ACRO Plot the power to flow map.

Recognize and report to the CRS entry into the Monitored Region as determined by the power to flow map plot.

Establish THI watch with concurrent duties.

CRS Perform subsequent actions of the Off

-Gas Activity High ONEP.

Consult with the Reactor Engineer or Duty Manager for further power reductions.

Activate the Emergency Plan when limits of step 3.3 are exceeded.

Notify Chemistry to monitor ventilation release points. CRS When the CRS determines that Off

-Gas Pre-Treat Radiation Levels cannot be maintained below 14,000 mR/hr, direct the ACRO to scram the reactor.

Enter the Scram ONEP, Turbine/Generator Trip ONEP, EP

-2 Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 15 of 20 Revision 0 Op-Test No: 12/11 Scenario No:

2 Event No:

6 cont. Event

Description:

Fuel Cladding Leak TIME Position Applicant's Actions or Behavior ACRO Places the Reactor Mode Switch to SHUTDOWN when directed by the CRS.

Provides a scram report:

Reactor Mode SW in SHUTDOWN.

Reactor power is 0%. Reactor water level and trend.

Reactor pressure and trend.

Feedwater is NOT available. Bypass valves are available.

ACRO / BOP Start RCIC by arming and depressing the RCIC initiation push button (RCIC will fail to start; see event 7 on page 17). BOP Recognizes and reports EP

-4 entry condition when MSL RAD HI annunciator alarms on P601-19A-D4. CRS Enters EP-4 when any entry condition is met.

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 16 of 20 Revision 0 Op-Test No: 12/11 Scenario No:

2 Event No:

6 cont. Event

Description:

Fuel Cladding Leak ACRO / BOP Recognize and report when MSL A

-D HI-HI radiation annunciators alarm.

Close all MSIVs (per EP

-4 step 1).

CRS When MSL A

-D HI-HI radiation annunciators alarm, direct the ACRO/BOP to close all MSIVs.

  • Fuel failure is occurring and main steam line radiation is greater than 3 times normal full power background as indicated by MSL B / MSL C RAD HI

-HI or MSL A / MSL D RAD HI

-Hi alarms, the crew closes MSIVs and MSL drains per EP-4. The crew closes the MSIVs and MSL drains and observes valve position indications and lowering pressure trend downstream of the MSIVs. Criterion is to give the highest priority to close the four inboard MSIVs or the four outboard MSIVs and MSL drains when MSL radiation is greater than 3 times normal full power background.

Establish reactor pressure band of 800

- 1060 psig using ADS/SRV valves.

Establish reactor level band of +30" to

-30" using Feed and Condensate system (this band is established per Ops Philosophy Level Band Strategies since reactor pressure is now being controlled with ADS/SRV's)

. BOP Maintain pressure band of 800

- 1060 psig using ADS/SRV valves (cycle open and closed as required to stay within band)

. ACRO Maintain level band of +30" to

-30" using HPCS (May use the Startup Level Controller in Auto or Manual)

.

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 17 of 20 Revision 0 Op-Test No: 12/11 Scenario No:

2 Event No:

7 Event

Description:

RCIC fails to start on initiation TIME Position Applicant's Actions or Behavior ACRO / BOP Recognizes that RCIC does not start when manually initiated using Initiate push button.

As indicated when nothing happens after the Initiate PB is depressed.

Manually starts RCIC using SOI 04 01-E51-1 Attachment VI.

Shift RCIC Flo controller to manual and reduce output to minimum.

Open E51-F046. Start Gland Seal Compressor.

Open E51-F095. After 6 seconds, Open E51

-F045. Raise turbine speed using flow controller in manual to develop pressure greater than reactor pressure.

Open E51-F013. Adjust flow as necessary with Flo controller.

Verify SSW A is running with adequate flow path.

Establish and maintain reactor water level in the established band (11.4" to 53.5")

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 18 of 20 Revision 0 Op-Test No: 12/11 Scenario No:

2 Event No:

8 Event

Description:

RCIC room unisolable steam leak TIME Position Applicant's Actions or Behavior ACRO / BOP Recognize and report unisolable steam leak in the RCIC room after RCIC is initiated.

As indicated by annunciators P601

-21A-G-3, RCIC EQUIP AREA TEMP HI, P601-21A-H-2, RCIC PIPE/EQUIP AMBIENT TEMP HI, and P601-21A-H-3, RCIC EQUIP AREA dT HI.

E51-F063 loss of power and E51

-F064 will not close.

RCIC room temperature remains high.

CRS Enter EP-4 at 22 (will be on step 10 until 2 max safe values are reached).

Direct the BOP to monitor EP

-4 parameters.

BOP Monitor EP

-4 parameters using EP

-4 table 3. Monitor for 2 Max Safe values CRS Establish a reduced pressure band of 450

- 600 psig to reduce the driving head of the steam leak in accordance with the Ops Philosophy Pressure Control Strategy.

Establish a level band of +30" to -30" in accordance with Ops Philosophy Level Control Strategy.

BOP Control reactor pressure in the 450

- 600 psig band using ADS/SRV valves when directed. ACRO Manually initiate HPCS to maintain reactor water level within the established band by arming and depressing the HPCS initiation pushbutton.

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 19 of 20 Revision 0 Op-Test No: 12/11 Scenario No:

2 Event No:

8 cont Event

Description:

RCIC room unisolable steam leak BOP / ACRO Recognize and report to the CRS when 2 max save values of EP

-4 Table 10 are exceeded. CRS When 2 max save values of EP

-4 Table 10 are exceeded, enters the Emergency Depressurization procedure of EP

-2. *A primary system is discharging outside primary containment and area temperatures, radiation levels, or water levels are above their max safe values in two or more areas. The crew opens 8 ADS/SRVs and observes lowering pressure trend and valve position indications (tailpipe pressure indication lamps or solenoid valve energized). Criterion is to give the highest priority to open at least seven SRVs when area temperatures, radiation levels, or water levels are above their maximum safe values in two or more areas.

Verify SP level is above 10.5 ft.

Direct the BOP operator to open 8 ADS valves.

BOP Opens at least 7 ADS valves when directed by the CRS.

ACRO Maintain reactor level band of +30" to

-30" following Emergency Depressurization. (The CRS may establish a level band of 11.4" to 53.5"

)

Appendix D Required Operator Actions Form ES-D-2 Scenario 2 Page 20 of 20 Revision 0 Give this page to the CRS Turnover the following conditions:

Power 85% Pressure 10 10 psig B OC EOOS GREEN A reactor startup is in progress with all steps complete up to step 6.8, Attachment II of 03-1-01-2 (Power Ascension from 60% to full power)

SSW "A" is in service.

APRM "F" has failed downscale and is in BYPASS (a tracking LCO was written).

Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1.b will not be provided for this scenario

. Planned Evolutions this shift:

Place SSW "A" in STANDBY using 04 01-P41-1 SSW SOI. Once SSW "A" is in STANDBY, continue with plant startup and raise reactor power to 100%. Ramp rates are not required until reactor power reaches 95%.

Appendix D Scenario Outline Form ES-D-1 Scenario 3 Page 1 of 2 Revision 1 Facility:

Grand Gulf Nuclear Station Scenario No.: 3 Op-Test No.:

12/11 Examiners: ____________________________ Operators:

_____________________________

____________________________

_____________________________ ____________________________

_____________________________

Objectives:

To evaluate the candidates' ability to operate the facility in response to the following evolutions:

1. Place the Mode Switch in Run

. 2. Start a second Condensate Booster Pump.

3. Suppression Pool level transmitter failure.
4. Spurious Division 1 ECCS initiation.
5. LPCS pump trips on ECCS initiation.
6. Loss of Main Condenser Vacuum.
7. Suppression Pool leak in the RHR C Room.
8. Startup Level Controller C34

-R602 automatic control fails.

Initial Conditions:

Operating at 5% power.

Inoperable Equipment:

None Turnover: A plant startup is in progress with all steps complete up to step 6.2.16.b in 03-1-01-1 (Cold Shutdown to Generator Carrying Minimum Load) and step 1.3.17 of Attachment 1 in 03 01-1 and step 163A of the cycle 18 BOC rod sequence movement sheet. The Crew will pull control rods to complete step 163B of the rod sequence movement sheet and then place the Mode Switch in RUN.

When the Mode Switch is in Run, the Crew will give priority to starting a second Condensate Booster Pump prior to continuing with the Turbine Startup Procedure.

Scenario Notes:

This is a new scenario.

Validation Time:

60 minutes

Appendix D Scenario Outline Form ES-D-1 Scenario 3 Page 2 of 2 Revision 1 Event No. Malf. No. Event Type f Event Description 1 R (ACRO) Place the Mode Switch to RUN (IOI 03-1-01-1 section 6.2.16.b

-h) 2 N (BOP) Start a second Condensate Booster Pump (SOI 04-1-01-N19-1 section 4.3) 3 1te30n003b_b TS (CRS) A (CREW) Suppression Pool Level Transmitter Failure (TS 3.3.3.1 Condition A) 4 e21_lpcs I (BOP) A (CREW) Spurious Division 1 ECCS initiation (SOI 04-1-01-E12-1 Attachment IX)

When Division 1 ECCS spuriously initiates, the crew secures the Division 1 Drywell Purge Compressor prior to the Drywell reaching 1.23 psig causing a reactor scram.

5 e21051 TS (CRS) LPCS pump trips on ECCS initiation (TS 3.5.1 Condition A) 6 fw163c M (Crew) Loss of Main Condenser Vacuum (Loss of Condenser Vacuum (05-1-02-V-8) ONEP) 7 ct218e ct219b M (Crew) Suppression Pool Leak in RHR C Room (EP-3) When it is determined that Suppression Pool level cannot be maintained above 14.5', the crew opens 8 SRVs and observes lowering pressure trend and valve position indications (tailpipe pressure indication lamps or solenoid valve energized). Criterion is to open at least seven SRVs prior to Suppression Pool level reaching 14.5'.

8 c34r602_b I (ACRO) Startup Level Controller C34

-R602 automatic control fails (Ops Philosophy 02

-S-01-27 section 6.1.1.d

) f (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec

  • Critical Task Quantitative Attributes Table Normal Events 1 Abnormal Events 2 Reactivity Manipulations 1 Total Malfunctions 6 Instrument/Component Failures 2 EP Entries (Requiring substantive action) 2 Major Transients 2 EP Contingencies 1 Tech Spec Calls 2 Critical Tasks 2

Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 1 of 18 Revision 1 Simulator Setup:

A. Initialization

1. Startup the simulator using Simulator Instructor's Job Aid section 6.3

.

2. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
3. Set the Simulator to IC-9 and perform switch check (Using Quick Reset in Director)

. 4. Click on "Open" in the Schedule window and Open Schedule File "2011 NRC Scenario 3.sch" (in the Schedule Directory) 5. In Schedule window, click on the "Stopped" red block. The red block will change to a green arrow and indicate the scenario is active ("Running"). 6. Click the Summary tab in the Director window. Verify the schedule files are loaded and opened per Section B below. (Note: Any actions in the schedule file without a specific time will not load into the director until triggered.)

7. Take the simulator out of freeze.

Note: Prior to running the Schedule File, ensure no Event Files are Open.

If an existing Event File is Open prior to running the Schedule File, then any associated Event Files will not automatically load.

Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 2 of 18 Revision 1 8. Clear any graphs and trends off of SPDS.

9. Ensure the correct rod movement sequence available at the P680.
10. Advance all chart recorders and ensure all pens inking properly.
11. Verify or perform the following:

IC-9 Place RC&IS in the Individual Drive Mode Ensure one RFPT is running and one is TRIPPED Condensate Booster Pump C is off and discharge valve closed Ensure that Cycle 18 BOC rod sequence binder is available Update startup IOI and rod sequence sheets with initials o IOI-1 step 6.2.16 a 1

-8 also IOI-1 steps 6.2.16.e and 6.2.16.f o IOI-1 Attachment 1 step 1.3.16 o Rod sequence sheets step 161 and 162

. 12. Run through any alarms and ensure alarms are on. (Note: On T

-Rex, to verify alarms are ON, the indicator will indicate "Alarms On").

13. Place the simulator in Freeze.

Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 3 of 18 Revision 1 B. File loaded verification:

Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 4 of 18 Revision 1 Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 5 of 18 Revision 1 Crew Turnover:

A. Assign the candidates crew positions.

B. Turnover the following conditions:

Power 5% Pressure 950 psig B OC EOOS GREEN A plant startup is in progress with all steps complete up to step 6.2.16.b in 03-1-01-1 (Cold Shutdown to Generator Carrying Minimum Load) and step 1.3.17 of Attachment 1 in 03 01-1 and step 163A of the cycle 18 BOC rod sequence movement sheet. Planned Evolutions this shift

The Crew will pull control rods to complete step 163B of the rod sequence movement sheet and then place the Mode Switch in RUN.

(Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1.b will not be provided for this scenario)

When the Mode Switch is in RUN, the CRO will start a second Condensate Booster Pump prior to continuing with the Turbine Startup Procedure.

C. Allow the crew to perform pre

-shift brief and review procedures for planned evolutions.

D. Bring the crew into the Simulator , place the simulator is in RUN.

E. Allow the crew to walk down panels.

F. When the crew assumes the shift begin Scenario Activities.

Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 6 of 18 Revision 1 SCENARIO ACTIVITIES:

Raise Power and Place the Mode Switch to RUN A. The crew will pull control rods using the rod sequence pull sheet and place the Mode Switch to RUN when all APRM downscale annunciators are clear

. 1. If asked for Chemistry results for continuing the startup, respond that all samples have been taken and that Chemistry is ready for Mode 1 operation.

Start a 2 nd Condensate Booster Pump B. The CRS will direct the BOP to start a second Condensate Booster Pump (Condensate Booster Pump C is preferred for redundant power supplies).

1. When directed as the local operator by the Control Room to perform pre

-start pump checks: a. Report that Condensate Booster Pump C002C oil reservoir is normal and pre

-start pump check is complete.

2. If asked as the Rad Waste Operator, report that 4 deep bed filters are in service.
3. When directed as the local operator by the Control Room:
a. Report that you have closed N19

-FX225. b. Report that you have opened N19

-FX225. Suppression Pool Level Transmitter Failure C. When the crew has started a second Condensate Booster pump, trigger Event 1 to insert malfunction lte30n003b_b to fail Suppression Pool Level Transmitter N003B downscale.

D. If asked the status of the trip unit, report that 1E30

-LIS-N600B is in a tripped condition. Div 1 ECCS spurious initiation

E. When the CRS enters LCO 3.3.3.1 Condition "A," trigger Event 2 to insert malfunction s e21_lpcs and e21051 to cause a spurious Division 1 ECCS initiation and trip the LPCS pump when it starts

. 1. The BOP will use 04 01-E12-1 Attachment IX (Recovery from a Division 1 ECCS Initiation Signal) to recover from the spurious imitation signal; OR

Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 7 of 18 Revision 1 If the crew chooses to use the E61 SOI, when directed to depress the manual trip PB on breaker 52

-15105 and pull the lockout tab (to stop DW purge compressor A) insert remote function ct026 by triggering Event 7. 2. If asked for the status of the following lights on the LLS panel, report the lights as ON:

a. ESF Power on
b. BOP Power on Loss of Main Condenser Vacuum F. When the CRS enters LCO 3.5.1 Condition "A," trigger Event 3 to insert malfunction fw163c to cause a loss of condenser vacuum.
1. When it becomes apparent that the main turbine low condenser vacuum trip set point will be reached, the crew will initiate a reactor scram.
2. If sent as the local operator to investigate the reason for loss of vacuum, acknowledge the order but do not report back a reason. If the control room makes subsequent contact, tell them you are still investigating.

Suppression Pool Leak in RHR room C.

G. When the crew scrams the reactor, Auto Trigger 5 will cause an unisolable suppression pool leak in RHR C room concurrent with a failure of the water tight door to RHR C room. Also, the automatic startup level control will fail causing reactor water level to trend up.

1. If sent as the local operator to investigate the location of the leak or to shut the RHR C room door, wait 3 minutes and report back that the leak appears to be upstream of the RHR C suction valve and/or you are unable to close the RHR C room watertight door because the closing mechanism is jammed.
2. If necessary for time compression, lower suppression pool level using the ThunderView "Operator" screen (at the lead evaluator's discretion).

Termination:

H. Once emergency depressurization has been conducted and reactor water level is stabilized above TAF, or as directed by Lead Evaluator

, take the simulator to Freeze and turn horns off

. Critical Tasks:

When Division 1 ECCS spuriously initiates, the crew secures the Division 1 Drywell Purge Compressor prior to the Drywell reaching 1.23 psig causing a reactor scram.

When it is determined that Suppression Pool level cannot be maintained above 14.5', the crew opens 8 SRVs and observes lowering pressure trend and valve position indications Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 8 of 18 Revision 1 (tailpipe pressure indication lamps or solenoid valve energized). Criterion is to open at least seven SRVs prior to Suppression Pool level reaching 14.5'.

Emergency Classification:

Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 9 of 18 Revision 1 Op-Test No: 12/11 Scenario No:

3 Event No:

1 Event

Description:

Change the plant from Mode 2 to Mode 1 operation TIME Position Applicant's Actions or Behavior CRS Conducts reactivity brief for the planned power ascension. (May be performed prior to taking the shift)

Directs the ACRO to withdraw control rods through step 163A of the control rod movement sheet in preparation for placing the Mode Switch to run per IOI

-1 step 6.2.16.b using the control r od movement sequence sheets. ACRO Withdraws control rods.

Verify/select INDIVIDUAL mode using the DRIVE MODE push button.

Select the rod to be move by depressing the corresponding rod select push buttons on the P680.

Verify the correct rod is selected on the Full Core Display.

Notch each rod by momentarily depressing the WITHDRAW push button on the P680. CRS Per IOI-1 steps 6.2.16.d and h Direct the ACRO to transfer one IRM/APRM recorder in each RPS division to the APRM position.

And then- Direct the ACRO to place the Mode Switch to RUN.

ACRO Transfer one IRM/APRM recorder in each RPS division to the APRM position.

Place the Mode Switch to RUN.

Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 10 of 18 Revision 1 Op-Test No: 12/11 Scenario No:

3 Event No:

2 Event

Description:

Start a second Condensate Booster Pump TIME Position Applicant's Actions or Behavior CRS Directs the BOP operator to start the B or C Condensate Booster Pump Note: The CRS should opt for starting the C Condensate Booster Pump since it is power from an alternate power source. See Note above 04 01-N19-1 step 4.1.2.a(2).

BOP Directs the local operator to perform pre

-start pump checks.

Ensure that at least 4 deepbed demineralizers are in service (contacts Rad Waste).

Directs the local operator to close N19

-FX212 or N19

-FX225 (discharge pressure gauge isolation valve).

Start the B or C Condensate Booster Pump (The C Condensate Booster Pump is preferred; see note above)

. Ensures the Condensate Booster Pump discharge valve opens.

Directs the local operator to open N19

-FX212 or N19

-FX225.

Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 11 of 18 Revision 1 Op-Test No: 12/11 Scenario No:

3 Event No:

3 Event

Description:

Suppression Pool level transmitter failure TIME Position Applicant's Actions or Behavior BOP Recognizes and reports that Division 2 Suppression Pool Level Wide Range has failed downscale.

As indicated by annunciator P870

-10A-A-3, SUPP POOL LVL LO

-LO The Wide Range SP level indicator 1E30-LR-R600B will be downscale. All other SP level indications will read normally.

CRS Recognizes entry conditions and enters TS 3.

3.3.1 Condition A and TS 3.3.6.4 Condition C

.

Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 12 of 18 Revision 1 Op-Test No: 12/11 Scenario No:

3 Event No:

4 Event

Description:

Spurious Division 1 ECCS Initiation TIME Position Applicant's Actions or Behavior BOP Recognizes and reports the spurious ECCS initiation to the CRS.

As indicated by LPCS/RHR A initiation when no reason for the initiation present (Reactor level above

-151.3" and Drywell pressure < 1.39 psig)

(The BOP will use various Control Room indications to determine reactor water level is above -150.3" and drywell pressure is below 1.39 psig)

CRS Direct the BOP to recover from Division 1 ECCS initiation using SOI 04 01-E12-1 Attachment IX

. OR Direct the BOP to secure the A DW purge compressor using SOI 04 01-E61-1 section 5.2.2 step a.

(Note that if this path is taken, the CRS should enter TS 3.6.3.3)

  • When Division 1 ECCS spuriously initiates, the crew secures the Division 1 Drywell Purge Compressor prior to the Drywell reaching 1.23 psig causing a reactor scram.

Enter the Control Rod/Drive Malfunctions ONEP.

Direct the BOP to ensure the Division 1 diesel generator is running with cooling water.

Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 13 of 18 Revision 1 Op-Test No: 12/11 Scenario No:

3 Event No:

4 cont. Event

Description:

Spurious Division 1 ECCS Initiation BOP Complete actions of SOI 04 01-E12-1 Attachment IX.

Press the LPCS/RHR A INIT RESET pushbutton (on P601-21B). Press the DIV 1 LSS PNL RESET pushbutton (on P864-1C). Reset the Division 1 CGCS logic using the keylock switch (on P870

-4B). Stop the Drywell Purge Compressor "A" (on P870

-4C). Close E61-F003A (on P870

-4C). OR Complete actions of SOI 04 01-E61-1 section 5.2 Direct the local plant operator to manually trip the 52

-15105 A DW purge compressor breaker and pull the lockout tab.

Take immediate operator actions per CRD malfunctions ONEP (from memory).

Place CRD SYS FLO CONT (C11

-R600 on P601

-22B) in MANUAL and REDUCE output to zero.

Start CRD pump A.

Slowly adjust CRD SYS FLO CONT to 54

-66 gpm after charging pressure returns to normal. (~1700 psig)

Return CRD SYS FLO CONT to AUTO with tapeset at 54

-66 gpm. Ensure that the Division 1 diesel generator is running with cooling water and sends a local operator to verify proper operation.

CRS Develops a plan of action to restore affected systems to standby lineup

. Refers to Automatic Isolations ONEP (05 02-III-5) to recover from isolations.

Refers to SSW SOI (04 01-P41-1) to place SSW A in standby.

Note: The CRS will not have time to implement these actions prior to the next event, but the CRS should pursue these actions.

Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 14 of 18 Revision 1 Op-Test No: 12/11 Scenario No:

3 Event No:

5 Event

Description:

LPCS pump trip TIME Position Applicant's Actions or Behavior BOP Recognizes and reports that the LPCS pump tripped when Division 1 ECCS initiated.

As indicated by the amber pump trouble light above the LPCS hand switch being illuminated (indicates pump trip when an auto start signal is present).

LPCS PMP AUTO TRIP status light is lit.

Annunciators P601

-21A-A-7, LPCS PMP OVERLD, and P601

-21A-H-8, LPCS SYS OOSVC will be in also.

CRS Recognizes entry conditions and enters TS 3.5.1 Condition A.

Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 15 of 18 Revision 1 Op-Test No: 12/11 Scenario No:

3 Event No:

6 Event

Description:

Loss of Main Condenser Vacuum TIME Position Applicant's Actions or Behavior ACRO Recognizes and reports lowering vacuum to the CRS

. As indicated by annunciator P680

-4A2-E-3, OG PNL P845 TROUBLE and lowering condenser vacuum.

The BOP operator will also note increased offgas flow.

CRS Enters the Loss of Condenser Vacuum ONEP.

Carryout steps of the ONEP to determine the cause of Loss of Condenser Vacuum.

Verify SJAE has not malfunctioned Check that offgas flow is not obstructed (this is determined not to be the cause by the increased offgas flow rate)

Check that Seal Steam is operating properly Send a local operator to check for condenser inleakage Check Circ Water system for proper operati on Check Condenser Vacuum Breaker valves are closed Send a local operator to ensure Condenser Vacuum Breaker valves have adequate seal water When it is apparent that the Condenser Low Vacuum trip set point will be reached, direct the ACRO to insert a Manual Scram (the turbine is not online; however, the RFPT will trip at 16" condenser vacuum requiring a manual reactor scram).

ACRO When directed:

Verify SJAE has not malfunctioned by checking the SJAE lineup on the P680-10C (the "A" SJAE valves should all be open). Check that Seal Steam is operating properly by checking for normal indications on the P680

-10B for normal SS indications.

Check Circ Water system for proper operation by checking that both Circ Water pumps are running on the P680

-10C. BOP When directed, check Condenser Vacuum Breaker valves are closed on the P870

-6C. ACRO When directed or before reactor water level is 11.4" (in the event that the CRS does not direct a scram before the RFPT trips on low vacuum; 16"), insert a manual scram

.

Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 16 of 18 Revision 1 O p-Test No: 12/11 Scenario No:

3 Event No:

6 cont. Event

Description:

Loss of Main Condenser Vacuum TIME Position Applicant's Actions or Behavior CRS Enters the Scram ONEP and EP

-2. Establishes reactor level band of 11.4" to 53.5".

ACRO Provides a scram report:

Reactor Mode SW in SHUTDOWN.

Reactor power is 0%.

Reactor water level and trend.

Reactor pressure and trend.

Feedwater is available.

Bypass valves are available.

Maintains reactor water level in the normal band of 11.4" to 53.5" using the startup level controller in automatic (when the RFPT finally trips on low vacuum, the operator may reset the vacuum trip on the RFPT and continue to feed the reactor until the MSIV's go closed at 9" vacuum).

Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 17 of 18 Revision 1 Op-Test No: 12/11 Scenario No: 3 Event No:

7 Event

Description:

Suppression Pool leak in the RHR C Room.

TIME Position Applicant's Actions or Behavior BOP / ACRO Recognizes and reports to the CRS EP-4 entry condition RHR C Room Flooded and/or RHR C Room Sump Level Hi-Hi with the RHR C room water tight door open

. As indicated by annunciators P680

-8A1-C-2, RHR RM C SMP LVL HI

-HI, or P870-10A-G-2, RHR C PMP RM FLOODED.

Suppression Pool level will be lowering.

The RHR C water tight door being open is indicated by annunciator P680-8A1-E-3, AUX BLDG N FLOOR DR SMP LVL HI

-HI. Shut E12-F004C CRS Enters EP-4 and EP-3. Direct the BOP operator to shut the RHR C pump suction valve E12

-F004C. Establish Suppression Pool level as a critical parameter.

Direct the BOP operator to manually initiate Suppression Pool Makeup.

BOP When directed, manually initiate SPMU (each division) per SOI 04 01-E30-1 Attachment V by: Place the SPMU MODE SEL switch to AUTO Place the SPMU DUMP TEST switch to TEST Depress both SPMU MAN INIT pushbuttons CRS Before Suppression Pool level reaches 14.5 ft, enter the Emergency Depressurization procedure of EP

-2. Direct the BOP operator to open 8 ADS/SRV valves.

  • When it is determined that Suppression Pool level cannot be maintained above 14.5', the crew opens 8 SRVs and observes lowering pressure trend and valve position indications (tailpipe pressure indication lamps or solenoid valve energized). Criterion is to open at least seven SRVs prior to Suppression Pool level reaching 14.5'.

BOP When directed, opens at least 7 ADS/SRV valv e s. CRS After the Emergency Depressurization, ensures reactor water level is restored to a level band of 11.4" to 53.5" (the operator should use the Condensate system for level control). ACRO After the Emergency Depressurization, maintains reactor water level in the normal level band of 11.4" to 53.5".

Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 18 of 18 Revision 1 Op-Test No: 12/11 Scenario No:

3 Event No:

8 Event

Description:

Startup Level Controller C34

-R602 automatic control failure ACRO Recognizes C34-R602 automatic control fails and places the controller in manual to maintain reactor water level in the normal band of 11.4" to 53.5" or uses the startup level bypass valve N21

-F040. This is indicated by rising reactor water level and the startup level controller output rising.

Appendix D Required Operator Actions Form ES-D-2 Scenario 3 Page 19 of 18 Revision 1 Give this sheet to the CRS Turnover the following conditions:

Power 5% Pressure 950 psig B OC EOOS GREEN A plant startup is in progress with all steps complete up to step 6.2.16.b in 03-1-01-1 (Cold Shutdown to Generator Carrying Minimum Load) and step 1.3.17 of Attachment 1 in 03 01-1 and step 163A of the cycle 18 BOC rod sequence movement sheet. Planned Evolutions this shift:

The Crew will pull control rods to complete step 163B of the rod sequence movement sheet and then place the Mode Switch in RUN. (Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1.b will not be provided for this scenario)

When the Mode Switch is in RUN, the CRO will start a second Condensate Booster Pump prior to continuing with the Turbine Startup Procedure.

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 1 of 17 Revision 1 Facility:

Grand Gulf Nuclear Station Scenario No.: 4 Op-Test No.:

12/11 Examiners: ____________________________ Operators:

_____________________________

____________________________

_____________________________ ____________________________

_____________________________

Objectives:

To evaluate the candidates' ability to operate the facility in response to the following evolutions:

1. Place Suppression Pool Cooling in service

. 2. Lower main generator output to 1280 MWe with +100 MVAR

. 3. Trip of the 16BB3 electric bus

. 4. Control Rod drift

. 5. Unisolable LOCA with limited injection capabilities

. 6. Division 3 Diesel Generator failure to start

. 7. Division 2 Diesel Generator running without cooling water.

8. Loss of power to E22

-F004 HPCS injection valve

. Initial Conditions:

Operating at 100% power.

Inoperable Equipment:

None Turnover: A plant is operating at rated power. Suppression Pool temperature is elevated due to a weeping SRV.

The Crew will start Suppression Pool Cooling on RHR B using the 04 01-E12-1 RHR system SOI. When Suppression Pool Cooling is in service, the Crew will lower generator output to 1280 MWe with

+100 MVAR.

Scenario Notes:

This is a new scenario.

Validation Time:

Not Validated

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 2 of 17 Revision 1 Event No. Malf. No. Event Type f Event Description 1 N (BOP) TS (CRS) Place Suppression Pool Cooling in Service (SOI 04 01-E12-1 section 5.2, TS 3.5.1 Condition A

) 2 R (ACRO) N (BOP / ACRO) Lower main generator output to 1280 MWe with +100 MVAR (IOI 03-1-01-2 Attachment VIII, 04-1-01-N40-1 section 4.4

) 3 r21142z TS (CRS) A (CREW) Trip of the 16BB3 electric bus (TS 3.6.1.3 Condition A, TS 3.5.1 Condition C, TS 3.6.4.3 Condition A, TS 3.6.3.2 Condition A) 4 z161161_24_33 z022022_24_33 z021021_28_33 R (ACRO) M (CREW) Control Rod Drift (Control Rod/Drive Malfunctions (05-1-02-IV-1) ONEP) 5 rr063a r21139e xml1r21191 xml1r2119 2 e12050c M (Crew) Unisolable LOCA with limited injection capabilities (Scram (0 5-1-02-I-1) and Turbine Trip (05-1-02-I-2) ONEPs, EP-2, EP-3) The crew injects HPCS to the reactor before reactor water level lowers to

-191". 6 n41140c C (BOP) Division 3 Diesel Generator failure to start (Loss of AC Power (05-1-02-I-4) ONEP) When Division 3 Diesel Generator fails to start, the crew re

-energizes the 17AC bus with an alternate feeder (ESF 12).

HPCS is the only recoverable system and power to this bus is required to run the HPCS pump.

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 3 of 17 Revision 1 7 p41f018b_i C (BOP) Division 2 Diesel Generator running without cooling water (02-S-01-27 Ops Philosophy section 6.1.1.c) 8 e22159a C (ACRO) Loss of power to E22

-F004 HPCS injection valve (02-S-01-27 Ops Philosophy section 6.1.1.d)

When E22-F004 loses power, the crew sends an operator to manually open the valve. HPCS is the only recoverable system and this valve must be manually opened in order to allow injection to the reactor. Criteria is that this valve is opened prior to reactor water level reaching

-191". f (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec

  • Critical Task (As defined in NUREG 1021 Appendix D)

Quantitative Attributes Table Normal Events 2 Abnormal Events 1 Reactivity Manipulations 2 Total Malfunctions 6 Instrument/Component Failures 3 EP Entries (Requiring substantive action) 1 Major Transients 2 EP Contingencies 1 Tech Spec Calls 2 Critical Tasks 3

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 1 of 17 Revision 1 Simulator Setup:

A. Initialization

1. Startup the simulator using Simulator Instructor's Job Aid section 6.3

.

2. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
3. Set the Simulator to IC-31 and perform switch check (Using Quick Reset in Director)

. 4. Click on "Open" in the Schedule window and Open Schedule File "2011 NRC Scenario 4.sch" (in the Schedule Directory)

5. In Schedule window, click on the "Stopped" red block. The red block will change to a green arrow and indicate the scenario is active ("Running"). 6. Click the Summary tab in the Director window. Verify the schedule files are loaded an d opened per Section B below. (Note: Any actions in the schedule file without a specific time will not load into the director until triggered.)
7. Take the simulator out of freeze.

Note: Prior to running the Schedule File, ensure no Event Files are Open.

If an existing Event File is Open prior to running the Schedule File, then any associated Event Files will not automatically load.

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 2 of 17 Revision 1

8. Clear any graphs and trends off of SPDS.
9. Ensure the correct rod movement sequence available at the P680.
10. Advance all chart recorders and ensure all pens inking properly.
11. Verify or perform the following:

IC-31 APRM's are turned on (4,1,2,3)

Suppression Pool Temperature is 85.6F Startup SSW B normally

12. Run through any alarms and ensure alarms are on. (Note: On T

-Rex, to verify alarms are ON, the indicator will indicate "Alarms On").

13. Place the simulator in Freeze.

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 3 of 17 Revision 1 B. File loaded verification:

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 4 of 17 Revision 1

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 5 of 17 Revision 1 Crew Turnover:

A. Assign the candidates crew positions.

B. Turnover the following conditions:

Power 100% Pressure 1030 psig B OC EOOS GREEN SSW B is in service.

Suppression Pool temperature is elevated because of a weeping SRV.

The Load Dispatcher has requested a temporary down power and MVAR adjustment.

Planned Evolutions this shift

The Crew will place Suppression Pool Cooling in service on RHR B.

The Crew will adjust generator loading to 1280 MWe with +100 MVAR.

All notifications have been made.

Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1 will not be provided for this scenario.

C. Allow the crew to perform pre

-shift brief and review procedures for planned evolutions.

D. Bring the crew into the Simulator , place the simulator is in RUN.

E. Allow the crew to walk down panels.

F. When the crew assumes the shift begin Scenario Activities.

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 6 of 17 Revision 1 SCENARIO ACTIVITIES:

Place Suppression Pool Cooling in service on RHR B A. The crew will place Suppression Pool Cooling in service on RHR B using 04 01-E12-1. 1. If asked to perform pre

-start pump checks, wait 2 minutes and report back to the Control Room that pre

-start pump checks are complete.

2. No actions outside the Control Room are required for this evolution.

Lower Main Generator Output B. The Crew will lower generator output to 1280 MWe with +100 MVARs. 1. No actions outside the Control Room are required for this evolution.

Trip of the 16BB3 electric bus C. When generator output has been adjusted to 1280 MWe and +100MVARs, trigger Event 1 to insert malfunction r21142z. This will cause 16BB3 to trip on over current.

1. When directed by the Control Room to investigate breaker 52

-16301, wait 2 minutes and report that the breaker has tripped on over current.

2. When enters TS 3.6.1.3 Condition A, TS 3.5.1 Condition C, and TS 3.6.4.3 Condition A, trigger Event 2 to insert malfunction z161161_24_33. This will cause control rod 24

-33 to drift out.

Control Rod Drift D. The CRS will enter the Control Rod/Drive Malfunctions ONEP

1. When control rod 24

-33 FH is inserted below position 8 it will become stuck (Auto trigger 3) and core flow will be lowered to 67 mlbm/hr.

2. If sent as the Aux Building Operator to isolate rod 24

-33 FH by closing the 103 and 105 valve, wait 45 seconds and report that rod 24

-33 FH is isolated.

3. Four minutes later, control rod 28

-33 GH will begin to drift inward (Auto trigger 3). The ACRO will scram the reactor

. Unisolable LOCA with limited injection capabilities

E. When the reactor is scramed, Auto trigger 4 will cause the following to occur:

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 7 of 17 Revision 1

1. Electric bus 15AA will trip on over current.
a. This bus is not recoverable. When the control room sends an operator and/or an electrician to investigate, report back after 3 minutes that the bus is damaged.
b. If directed to place the Division 1 diesel in Maintenance Mode, coordinate with the control room and trigger Event 7 when directed to place in maintenance mode.
2. Division 3 Diesel Generator will fail to start.
3. The 500KV switchyard will be lost.
4. RHR C pump will trip.
a. This pump is not recoverable. When the control room sends an operator and/or an electrician to investigate breaker 152

-1609, wait 3 minutes and report the beaker is tripped on thermal device.

b. If sent to the pump, report that it is very hot and that the motor casing is discolored.
5. P41-F018B (SSW to Div 2 DG) will lose power on stroke.
a. When directed by the control room to place division 2 diesel in MAINT, coordinate with the control room and trigger Event 6 to place the diesel in MAINT.
6. E22-F004 (HPCS injection valve) will lose power on stroke. This valve CAN be manually opened if an operator is sent to open it. a. When the control room sends an operator to open this valve, wait until RPV water level is -100" wide range, then trigger Event 5 to manually open E22

-F004. Do not report the opening of E22

-F004 to the Control Room.

F. Insert EP Attachments as requested by the Control Room.

Termination:

G. When reactor water level is stabilized in the

-30 to 30" level band using HPCS, or as directed by Lead Evaluator

, take the simulator to Freeze and turn horns off

. Critical Tasks:

When Division 3 Diesel Generator fails to start, the crew re

-energizes the 17AC bus with an alternate feeder (ESF 12). HPCS is the only recoverable system and power to this bus is required to run the HPCS pump.

The crew injects HPCS to the reactor before reactor water level lowers to

-191". When E22-F004 loses power, the crew sends an operator to manually open the valve. HPCS is the only recoverable system and this valve must be manually opened in order to allow injection to the reactor. Criteria is that this valve is opened prior to reactor water level reaching

-191".

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 8 of 17 Revision 1 Emergency Classification:

SA1 Alert Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 9 of 17 Revision 1 Op-Test No: 12/11 Scenario No:

4 Event No:

1 Event

Description:

Place Suppression Pool Cooling in Service TIME Position Applicant's Actions or Behavior CRS Directs the BOP operator to place Suppression Pool Cooling "B" in service per SOI 04-1-01-E12-1 section 5.2.2.b.

BOP Place Suppression Pool Cooling "B" in service using SOI 04-1-01-E12-1 section 5.2.2.b as follows:

Place the RHR B MOV TEST switch to TEST Start RHR RM B FAN COIL UNIT on P870 Check open E12

-F003B on P601 Start RHR B Pump Open E12-F024B (This step INOPs RHR B, TS 3.5.1)

Inform the CRS of the time RHR B is INOP Close E12-F048B (optional, this is to maximize cooling

) CRS When E12-F024B is opened, Enter TS 3.5.1 Condition A.

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 10 of 17 Revision 1 Op-Test No: 12/11 Scenario No:

4 Event No:

2 Event

Description:

Lower Main Generator Output TIME Position Applicant's Actions or Behavior CRS Conducts reactivity brief for the planned power change. (May be performed prior to taking the shift)

Directs the ACRO to lower power and the BOP to adjust load demand per IOI-2 attachment VIII.

ACRO Lowers generator output by closing the Recirc FCVs A & B using loop flow controllers B33K603A & B in slow detent on P680-3B until generator output is 1280 MWe (IOI-2 attachment VIII step 12.3).

BOP Lowers Load Demand as generator output is lowered by depressing EHC LOAD REF DEMAND LOWER pushbutton (P680

-9C) to maintain generator actual load within +/

- 25 MW of the load demand limited (IOI-2 attachment VIII step 12.2).

CRS Directs the ACRO to raise reactive load per SOI 04 01-N40-1 section 4.4.2.

ACRO Adjust generator reactive load using the TVR CONT RAISE and LOWER pushbuttons on P680-9C as required to achieve

+100 MVAR (SOI 04-1-01-N40-1 section 4.4.2)

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 11 of 17 Revision 1 Op-Test No: 12/11 Scenario No:

4 Event No:

3 Event

Description:

Trip of the 16BB3 electric bus TIME Position Applicant's Actions or Behavior BOP Recognize and report that 16BB3 is de

-energized and that breaker 52

-16301 is tripped.

As indicated by annunciator P864

-2A-E-3, 480V LCC 16BB3 UNDERVOLT.

Various Division 2 components will be de

-energized including

o E12-F028B, E12

-F042B, and E12

-F053B o SLC Pump B o CCW Pump B o Div 2 D/G Aux LO Pum p (not required for operability) o SBGT Enclosure Building Recirc Fan o The entire load list is in 04 01-R21-16, ESF Bus 16AB SOI, Attachment 1 pages 15

-17. Determine and report what equipment is without power (directed by the alarm response instruction for 16BB3). CRS Directs the BOP to evaluate Control Room panels to determine what equipment is affected the loss of 16BB3 (this is directed by the alarm response instruction for the loss of 16BB3)

. Directs local operator to determine the cause for the breaker trip. Uses SOI 04 01-R21-16 to determine what equipment is affected by the loss of 16BB3. Enters the following Tech Specs (due to the completion time constraints and expected plant response organization to this event, only the bolded TS is required for credit in this case):

TS 3.6.1.3 Condition A (4 hr

) TS 3.6.5.3 Condition A (8 hr)

TS 3.8.7 Condition A (8 hr)

TS 3.1.7 Condition B (7 day)

TS 3.6.4.3 Condition A (7 day)

TS 3.6.3.2 Condition A (30 day)

TS 3.5.1 Condition A (previously entered)

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 12 of 17 Revision 1 Op-Test No: 12/11 Scenario No:

4 Event No:

4 Event

Description:

Control Rod Drift TIME Position Applicant's Actions or Behavior ACRO Recognizes and reports that Control Rod 24

-33 FH is drifting out.

As indicated by annunciator P680

-4A2-E-4, CONT ROD DRIFT.

The operator will depress the ROD DRIFT RC&IS push button to determine which rod is drifting. The operator will then select that control rod for display on the full core display and determine the direction of the rod drift.

(This action is described in the ARI for the above annunciator)

Applies a continuous insert signal for control rod 24

-33 FH per the Control Rod/Drive Malfunctions ONEP immediate operator actions.

CRS Enters the Control Rod/Drive Malfunctions ONEP.

Ensures all immediate operator actions are carried out.

ACRO When Control Rod 24

-33 FH becomes stuck, reduces reactor core flow to 67 mlbm/hr per the Control Rod/Drive Malfunctions ONEP immediate operator actions.

Reset the rod drift annunciator by depressing the rod drift reset pushbutton on RC&IS (This action is described in the ARI for the CONT ROD DRIFT annunciator and is required in order to detect a second rod drift)

ACRO / BOP Plot reactor power and flow on the power to flow map after the reduction in Recirc Flow and determine entry into the Monitored Region. Set THI watch with concurrent duties. Report entry into the Monitored Region of the power to flow map to the CRS.

CRS Enter the Reduction in Recirc Flow ONEP.

Direct the ACRO to monitor for THI (set THI watch with concurrent duties).

ACRO Recognize and report that a second control rod, 28

-33GH, is drifting inward.

This is indicated the same as the original rod drift CRS Directs the ACRO to insert a manual scram (per CRD malfunctions ONEP subsequent

actions). Enter Scram and Turbine Trip ONEPs.

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 13 of 17 Revision 1 Op-Test No: 12/11 Scenario No:

4 Event No:

4 Cont. Event

Description:

Control Rod Drift When directed, inserts a manual scram by placing the Mode Switch to SHUTDOWN.

Provides a scram report: Reactor Mode SW in SHUTDOWN.

Reactor power is 0%.

Reactor water level and trend.

Reactor pressure and trend.

Feedwater is available until the main turbine trips (this is when ST

-11 goes away and both RFPT's lose lube oil and trip)

. Bypass valves are not available.

BOP / ACRO Initiate HPCS and RCIC in anticipation of a loss of feedwater (this is part of the crew's responsibility to maintain reactor water level within the desired band and is primarily the responsibility of the ACRO)

.

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 14 of 17 Revision 1 Op-Test No: 12/11 Scenario No:

4 Event No:

5 Event

Description:

Unisolable LOCA with limited injection capabilities TIME Position Applicant's Actions or Behavior BOP Recognize and report 15AA bus lockout as indicated by the 4.16KV BUSS 15AA TRIP annunciator and no power to the bus.

The BOP should attempt to energize the bus using the ESF 12 feeder breaker

. CRS Enter EP-2 and EP-3 Direct actions of EP

-2: Verify isolations for Reactor Level 2 and Drywell Pressure 1.39 psig.

Enter the Alternate Level Control procedure of EP

-2. Establish a pressure band of 800

-1060 psig.

Establish a level band of +30 to

-30 in. Inhibit ADS Maximize CRD for flow.

ACRO When directed, maximize CRD for flow (only CRD B pump is available).

Re-energize 16B42 on P864 Start the CRD B Aux Oil Pump Start the CRD B Pump Although there are other actions per the procedure, only these listed will accomplish anything.

Update the CRS with reactor water level as it continues to lower.

BOP When directed, Inhibit ADS by placing both ADS inhibit switches to INHIBIT

. Dispatch operators to recover out of service water injection sources.

Evaluate and deliver ECCS Status Report to the CRS (hard card).

ACRO When E22-F004 HPCS injection valve is manually opened, control reactor water leve l in the established level band by starting and stopping the HPCS pump as required

. *The crew injects HPCS to the reactor before reactor water level lowers to

-191".

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 15 of 17 Revision 1 Op-Test No: 12/11 Scenario No:

4 Event No:

6 Event

Description:

Division 3 Diesel Generator failure to start TIME Position Applicant's Actions or Behavior BOP Recognizes that electric bus 17AC is de

-energized (HPCS diesel has failed to start and take the bus) and shuts the feeder breaker from ESF 12 transformer to re-energize the 17AC bus. *When Division 3 Diesel Generator fails to start, the crew re

-energizes the 17AC bus with an alternate feeder (ESF 12).

HPCS is the only recoverable system and power to this bus is required to run the HPCS pump.

This is indicated by many indications, but primarily the following annunciators P601-16A-H-3, HPCS SYS OOSVC P601-16A-H-1, HPCS SYS NOT READY FOR AUTO START P601-16A-D-3, HPCS DSL ENG TROUBLE P601-16A-F-2, HPCS SYS UNDERVOLT Many indicating lights will be de

-energized on the P601-16 section of the P601. Report the status of Division 3 Diesel Generator and 17AC to the CRS.

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 16 of 17 Revision 1 Op-Test No: 12/11 Scenario No:

4 Event No:

7 Event

Description:

Division 2 Diesel Generator running without cooling water TIME Position Applicant's Actions or Behavior BOP Recognizes that Division 2 Diesel Generator is running without cooling water and places the Division 2 Diesel Generator in Maintenance Mode.

As indicated by P41-F018B being de

-energized and a lack of annunciator P870-7A-A-2, SSW DIV 2 OPER (this annunciator is expected when SSW auto initiates and all valves have repositioned to their required position).

Re-energizes electrical bus 16AB using ESF 12 feeder breaker.

Report the status of Division 2 Diesel Generator and 16AB to the CRS.

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 17 of 17 Revision 1 Op-Test No: 12/11 Scenario No:

4 Event No:

8 Event

Description:

Loss of power to E22

-F004 HPCS injection valve TIME Position Applicant's Actions or Behavior Crew Ensure an operator is sent to manually open E 22-F004. *When E22-F004 loses power, the crew sends an operator to manually open the valve. HPCS is the only recoverable system and this valve must be manually opened in order to allow injection to the reactor. Criteria is that this valve is opened prior to reactor water level reaching

-191". Ensure an operator is sent to restore electrical power to E22

-F004.

Appendix D Required Operator Actions Form ES-D-2 Scenario 4 - Alternate Page 18 of 17 Revision 1 Give this sheet to the CRS Turnover the following conditions:

Power 100% Pressure 1030 psig B OC EOOS GREEN SSW B is in service.

Suppression Pool temperature is elevated because of a weeping SRV.

The Load Dispatcher has requested a temporary down power and MVAR adjustment.

Planned Evolutions this shift:

The Crew will place Suppression Pool Cooling in service on RHR B.

The Crew will adjust generator loading to 1280 MWe with +100 MVAR. All notifications have been made.

Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1 will not be provided for this scenario.

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