ML17319A704
| ML17319A704 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 10/09/2017 |
| From: | Vincent Gaddy Operations Branch IV |
| To: | South Texas |
| References | |
| Download: ML17319A704 (321) | |
Text
Rev. 1 ES-301 Administrative Topics Outline Form ES-301-1 Facility: South Texas Project Date of Examination: 09-25-17 Examination Level: RO SRO Operating Test Number: LOT 21 NRC Administrative Topic (see Type Describe activity to be performed Note) Code*
Conduct of Operations 2.1.32 Ability to explain and apply system limits and RA(1) precautions.
N,R Calculate Time Remaining in Condenser Pressure K/A Importance: 3.8 Restricted Zone Conduct of Operations 2.1.25 Ability to interpret reference materials, such as RA(2) graphs, curves, tables, etc.
D,R Calculate RCS refill volume (without vacuum)
K/A Importance: 3.9 Equipment Control 2.1.23 Ability to perform specific and integrated plant RA(3) procedures during all modes of operation.
D,R Determine H2 Recombiner Power Settings K/A Importance: 4.3 Radiation Control N/A Emergency Plan 2.4.39 Knowledge of RO responsibilities in emergency RA(4) D,P,R plan implementation Complete an Offsite Agency Notification Message Form K/A Importance: 3.9 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
- Type Codes and Criteria: (C)ontrol Room, (S)imulator, Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1, randomly selected)
Rev. 1 ES-301 Administrative Topics Outline Form ES-301-1 Facility: South Texas Project Date of Examination: 09-25-17 Examination Level: RO SRO Operating Test Number: LOT 21 NRC Administrative Topic (see Type Describe activity to be performed Note) Code*
Conduct of Operations 2.1.42 Knowledge of new and spent fuel movement SA(5) procedures.
N,R Determine Close Contact Fuel Assembly Movement K/A Importance: 3.4 Conduct of Operations 2.1.20 Ability to interpret and execute procedure steps SA(6) D,R Review ESF Power Availability K/A Importance: 4.6 Equipment Control 2.2.13 Knowledge of Tagging and Clearance Procedures SA(7) D,R Review faulted ECO for AFW Pump K/A Importance: 4.3 Radiation Control 2.3.13 Knowledge of radiological safety procedures SA(8) pertaining to licensed operator duties, such as response to D,P,R radiation monitor alarms, containment entry requirements, K/A Importance: 3.8 fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
Initiate a Dose Extension Emergency Plan 2.4.41 Knowledge of the emergency action level SA(9) M,R thresholds and classifications.
Determine Appropriate Emergency Plan Protective Action K/A Importance: 4.6 Recommendation.
NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
- Type Codes and Criteria: (C)ontrol Room, (S)imulator, Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1, randomly selected)
Rev. 1 STP LOT-21 NRC Admin JPM Description RO (A1) Calculate Time Remaining in Condenser Pressure Restricted Zone Demonstrate the ability to explain and apply the limits associated with the Main Turbine and Condenser Pressure in accordance with 0POP04-CR-0001, Low Condenser Vacuum, Addendum 3, Main Turbine Exhaust Pressure Limitations.
(A2) Calculate RCS Refill Volume (Without Vacuum)
Demonstrate the ability to calculate the volume needed to fill the RCS from the given conditions.
(A3) Determine H2 Recombiner Power Settings Demonstrate the ability to calculate the required power setting for operation of a Hydrogen Recombiner in a post-LOCA environment.
(A4) Complete An Offsite Agency Notification Message Form Demonstrate the ability to prepare an Offsite Agency Notification Message Form for approval by the Emergency Director per 0ERP01-ZV-IN02, Notifications to Offsite Agencies.
SRO (A5) Determine Close Contact Fuel Assemble Movement Demonstrate the ability to review Fuel Transfer Forms and interpret procedure guidance for Close Contact Fuel Assembly moves in accordance with 0POP08-FH-0001, Refueling Machine Operating Instructions, Addendum 4, Guidelines For Close Contact Fuel Assembly Movements.
(A6) Review ESF Power Availability Surveillance Results Demonstrate the ability to review a completed ESF Power Availability surveillance and determine Technical Specification action requirements.
(A7) Review faulted ECO for AFW Pump Demonstrate the ability perform a technical review of an ECO in accordance with 0PGP03-ZO-EC01A, Equipment Clearance Order Instructions.
(A8) Initiate a Dose Extension Demonstrate the ability to determine the requirements for a dose extension in accordance with 0PGP03-ZR-0050, Radiation Protection Program.
(A9) Determine Appropriate Emergency Plan Protective Action Recommendation Demonstrate the ability to correctly determine an Emergency Action Level for a given condition requiring entry into the STPNOC Emergency Action Plan in accordance with 0ERP01-ZV-IN07, Offsite Protective Action Recommendations.
STPNOC Job Performance Measure CALCULATE ALLOWABLE TIME REMAINING IN CONDENSER PRESSURE RESTRICTED ZONE JPM Number: NRC RA(1)
Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC RA(1) - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on LOT 21 NRC Exam.
Page 2 of 8
NRC RA(1) - rev 0 SIMULATOR SETUP INSTRUCTIONS
- 1. This is an Admin JPM.
Page 3 of 8
NRC RA(1) - rev 0 INITIAL CONDITIONS The Unit is at 48% power and an air leak develops in the Condenser. The Crew has entered 0POP04-CR-0001, Loss of Condenser Vacuum.
INITIATING CUE You are the 3rd RO and the Unit Supervisor tells you to monitor the Main Turbine per 0POP04-CR-0001, Loss of Condenser Vacuum, Addendum 3, Main Turbine Exhaust Pressure Limitations.
You are given the following data on Main Generator Load and Condenser Pressure:
NOTE: Time 0.0 minutes is when the event started.
Time in Load in Condenser Time in Load in Condenser Minutes MWE Pressure in Minutes MWE Pressure in inHg inHg 0.0 600 29.0 0.5 580 27.5 3.5 550 25.75 1.0 555 26.0 4.0 550 25.75 1.5 535 25.5 4.5 535 25.5 2.0 530 25.0 5.0 530 25.0 2.5 535 25.25 5.5 525 24.5 3.0 535 25.5 6.0 520 24.25 After six (6) minutes the Unit Supervisor tells you to determine if there are any applicable restrictions on the Main Turbine per 0POP04-CR-0001, Loss of Condenser Vacuum, Addendum 3, Main Turbine Exhaust Pressure Limitations.
Page 4 of 8
NRC RA(1) - rev 0 Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
Determines that the Main Turbine is operating in the Restricted Zone per 0POP04-CR-0001, Loss of Condenser Vacuum, Addendum 3, Main Turbine Exhaust Pressure Limitations, and the Main Turbine can only be operated in the Restricted Zone for a MAXIMUM of 3.5 more minutes.
Page 5 of 8
NRC RA(1) - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Hand out Student Copy of 0POP04-CR-0001, Loss of Condenser Vacuum, Addendum 3, Main Turbine Exhaust Pressure Limitations.
When the student has reviewed the Initial Conditions & Initiating Cue and they have indicated they are ready to begin the JPM, then record the start time for the JPM.
A KEY is provided for the Examiner.
1 Using the data given, Compares, and/or plots the ___ ___ ___
MONITOR Condenser Pressure points from the given data to and Main Generator Load per 0POP04-CR-0001, Loss of 0POP04-CR-0001, Loss of Condenser Vacuum, Addendum Condenser Vacuum, Addendum 3, Main Turbine Exhaust 3, Main Turbine Exhaust Pressure Limitations.
Pressure Limitations.
- 2 Determine any applicable Determines that the Main ___ ___ ___
restrictions on the Main Turbine Turbine is operating in the per 0POP04-CR-0001, Loss of Restricted Zone per 0POP04-Condenser Vacuum, Addendum CR-0001, Loss of Condenser 3, Main Turbine Exhaust Vacuum, Addendum 3, Main Pressure Limitations. Turbine Exhaust Pressure Limitations, AND the Main Turbine can only be operated in the Restricted Zone for a MAXIMUM of 3.5 more minutes.
CUE This JPM is complete JPM Stop Time:
Page 6 of 8
SUMMARY
Operators Name: Job
Title:
Title:
CALCULATE ALLOWABLE TIME REMAINING IN CONDENSER PRESSURE RESTRICTED ZONE JPM Number: NRC RA(1) Revision Number: 0 Task Number and
Title:
65589, Respond to Loss of Condenser Vacuum K/A Number and Importance: 2.1.32 3.8/4.0 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only ; RO/SRO ; AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0POP04-CR-0001, Loss of Condenser Vacuum, Addendum 3, Main Turbine Exhaust Pressure Limitations, Rev 23 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 10 minutes Actual Time Used: minutes Critical Steps (*) 2 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 7 of 8
Student Handout INITIAL CONDITIONS The Unit is at 48% power and an air leak develops in the Condenser. The Crew has entered 0POP04-CR-0001, Loss of Condenser Vacuum.
INITIATING CUE You are the 3rd RO and the Unit Supervisor tells you to monitor the Main Turbine per 0POP04-CR-0001, Loss of Condenser Vacuum, Addendum 3, Main Turbine Exhaust Pressure Limitations.
You are given the following data on Main Generator Load and Condenser Pressure:
NOTE: Time 0.0 minutes is when the event started.
Time in Load in Condenser Time in Load in Condenser Minutes MWE Pressure in Minutes MWE Pressure in inHg inHg 0.0 600 29.0 0.5 580 27.5 3.5 550 25.75 1.0 555 26.0 4.0 550 25.75 1.5 535 25.5 4.5 535 25.5 2.0 530 25.0 5.0 530 25.0 2.5 535 25.25 5.5 525 24.5 3.0 535 25.5 6.0 520 24.25 After six (6) minutes the Unit Supervisor tells you to determine if there are any applicable restrictions on the Main Turbine per 0POP04-CR-0001, Loss of Condenser Vacuum, Addendum 3, Main Turbine Exhaust Pressure Limitations.
WRITE ANSWER BELOW:
Page 8 of 8
LOT 21 NRC JPM RA(1) Rev 0 PAGE 1 OF 1 Student Handout INITIAL CONDITIONS:
The Unit is at 48% power and an air leak develops in the Condenser. The Crew has entered 0POP04-CR-0001, Loss of Condenser Vacuum.
INITIATING CUE:
You are the 3rd RO and the Unit Supervisor tells you to monitor the Main Turbine per 0POP04-CR-0001, Loss of Condenser Vacuum, Addendum 3, Main Turbine Exhaust Pressure Limitations.
You are given the following data on Main Generator Load and Condenser Pressure:
NOTE: Time 0.0 minutes is when the event started.
Time in Load in Condenser Time in Load in Condenser Minutes MWE Pressure in Minutes MWE Pressure in inHg inHg 0.0 600 29.0 0.5 580 27.5 3.5 550 25.75 1.0 555 26.0 4.0 550 25.75 1.5 535 25.5 4.5 535 25.5 2.0 530 25.0 5.0 530 25.0 2.5 535 25.25 5.5 525 24.5 3.0 535 25.5 6.0 520 24.25 After six (6) minutes the Unit Supervisor tells you to determine if there are any applicable restrictions on the Main Turbine per 0POP04-CR-0001, Loss of Condenser Vacuum, Addendum 3, Main Turbine Exhaust Pressure Limitations.
WRITE ANSWER BELOW:
The shaded areas on the table above represent when the Main Turbine was operating in the Restricted Zone. It is a total time of 3 minutes. However, the Restricted Zone was exited for one minute in between these two times.
The current time for being in the Restricted Zone starts at Time 4.5 minutes. At the six minute mark the time in the Restricted Zone has been 1.5 minutes.
ANSWER:
At the six minute mark (currently) the Main Turbine is operating in the Restricted Zone and can only be in the Restricted Zone for a Maximum of another 3.5 minutes.
STPNOC Job Performance Measure CALCULATE RCS REFILL VOLUME (WITHOUT VACUUM)
Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC RA(2) - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on LOT 21 NRC Exam.
NRC RA(2) - rev 0 SIMULATOR SETUP INSTRUCTIONS
- 1. This is an Admin JPM.
NRC RA(2) - rev 0 INITIAL CONDITIONS Unit 2 is performing a fill of the RCS per 0POP03-RC-0100, RCS Vacuum Fill, from the RWST. RCS sightglass level is 32' 9". RWST level is 400,000 gallons.
INITIATING CUE You have been given a copy of 0POP03-RC-0100 Addendum 3, and the Unit Supervisor directs you to perform the following:
Calculate the required RCS Floodup Volume, WITHOUT VACUUM, to 50% Pressurizer level.
AND Determine if the RWST level change was within 200 gallons of the calculated amount for RCS fill. AFTER the RCS fill was completed, RWST level was at 354,000 gallons.
NRC RA(2) - rev 0 Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
Correctly calculates the volume of water needed to refill the RCS to 50% Pressurizer level in accordance with 0POP03-RC-0100, Addendum 3. Also, correctly determines the RWST level change IS within 200 gallons of the calculated amount for RCS fill.
NRC RA(2) - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Hand out Student Copy of 0POP03-RC-0100, RCS Vacuum Fill, Addendum 3, Determination of RCS Volume to be Filled.
When the student has reviewed the Initial Conditions & Initiating Cue and they have indicated they are ready to begin the JPM, then record the start time for the JPM.
A KEY is provided for the Examiner.
Record current RCS level from Records RCS sightglass level 1 ___ ___ ___
RCS level sightglass. as 32' 9".
(Addendum 3 step 1.1)
NOTE: Initial sightglass level is given as an initial condition.
Determine current RCS volume Determines current RCS 2 ___ ___ ___
in gallons. (Addendum 3 step volume is 32,636 gallons using 1.2) Addendum 3 Table - RCS Floodup Volume Without Vacuum column for RCS level at 32' 9".
NOTE: Both columns show the same RCS Floodup volume until level is raised up to the Rx Vessel Flange.
Record expected final RCS Records expected final RCS 3 ___ ___ ___
volume in gallons. (Addendum 3 volume as 78,463 gallons using step 1.3) Addendum 3 Table - RCS Floodup Volume Without Vacuum column for Pressurizer level at 50%.
Calculate Total RCS volume to Determines 45,827 gallons are
- 4 ___ ___ ___
be added. (Addendum 3 step needed to fill the RCS to 50%
1.4) Pressurizer level by subtracting the Initial RCS Volume (32,636 gal.) from the Final Floodup Volume (78,463 gal).
Page 6 of 9
NRC RA(2) - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number Determine if final RWST LEVEL 1. Subtracts the final RWST
- 5 ___ ___ ___
is within 200 gallons of the level from the initial RWST calculated amount for RCS fill. level to obtain a result of (Addendum 3 Section 2.0) 46,000 gallons.
- 2. Determines the RWST level change is within 200 gallons of the calculated amount for RCS fill CUE This JPM is complete JPM Stop Time:
Page 7 of 9
SUMMARY
Operators Name: Job
Title:
Title:
CALCULATE RCS REFILL VOLUME (WITHOUT VACUUM)
JPM Number: NRC RA(1) Revision Number: 0 Task Number and
Title:
100000, Perform Vacuum Fill of the RCS K/A Number and Importance: 2.1.25 3.9/4.2 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only ; RO/SRO ; AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0POP03-RC-0100, RCS Vacuum Fill, Addendum 3, Determination of RCS Volume to be Filled, Rev 43 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 10 minutes Actual Time Used: minutes Critical Steps (*) 4 & 5 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 8 of 9
Student Handout INITIAL CONDITIONS Unit 2 is performing a fill of the RCS per 0POP03-RC-0100, RCS Vacuum Fill, from the RWST. RCS sightglass level is 32' 9". RWST level is 400,000 gallons.
INITIATING CUE You have been given a copy of 0POP03-RC-0100 Addendum 3, and the Unit Supervisor directs you to perform the following:
Calculate the required RCS Floodup Volume, WITHOUT VACUUM, to 50% Pressurizer level.
AND Determine if the RWST level change was within 200 gallons of the calculated amount for RCS fill. AFTER the RCS fill was completed, RWST level was at 354,000 gallons.
WRITE ANSWER BELOW:
Page 9 of 9
0POP03-RC-0100 Page 57 of 101 Rev. 43 RCS Vacuum Fill Addendum 3 Determination of RCS Volume to be Filled Page 1 of 2 RCS RCS FLOODUP FLOODUP RWST VOLUME RWST LEVEL VOLUME LEVEL PLANT REFERENCE WITHOUT CHANGE (%)(1) WITH CHANGE ELEVATION (%)(1)
VACCUM VACUUM (gallons) (gallons)
(2) (2)
Pressurizer 50% Level 68 ft 10 in 2.0 2.3 78,463 89,790 (2) (2)
Pressurizer 10% Level 55 ft 6 in 4.1 5.3 68,357 77,696 Beginning and ending values Reactor Vessel Flange 39 ft 3 in KEY 47,389 1.5 50,550 2.1 (RVWL Sensor Point 2) (39 ft 5 in) 4.5 ft below Vessel Flange 34 ft 10.1 in 39,589 0.6 39,752 0.7 (RVWL Sensor Point 3) (34 ft 10.25")
Top of Hot Leg Nozzle 33 ft 5.5 in 36,345 0.2 36,345 0.2 (RVWL Sensor Point 4)
Narrow Range Hot Leg 33 ft 2 in 35,468 less than 0.1 35,468 less than 0.1 Level +11 inches (33 ft 5.625")
NR Hot leg Lvl +6 inches 32 ft 9 in 32,636 less than 0.1 32,636 less than 0.1 (alarm)
Hot Leg Centerline 32 ft 3 in 30,281 less than 0.1 30,281 less than 0.1 (RVWL Sensor Pt 5)
Bottom of Narrow Range 31 ft 11.5 in 29,079 --- 29,079 ---
Hot Leg Level Indication (1) REFILL - Level change is percent level lowering from rising RCS level from previous reference point.
(2) VARIANCE - Floodup without vacuum will tend to prevent Steam Generator U-Tubes from filling completely due to entrapped air in the top of the U-Tubes during floodup.
This procedure, when completed, SHALL be retained.
0POP03-RC-0100 Rev. 43 Page 58 of 101 RCS Vacuum Fill Addendum 3 Determination of RCS Volume to be Filled Page 2 of 2 1.0 Calculate gallons to fill RCS to desired level:
1.1 RECORD current RCS level from RCS level sightglass. 32' 9" 1.2 DETERMINE current RCS volume in gallons. 32,636 1.3 RECORD expected final RCS volume in gallons. 78,463 1.4 CALCULATE Total RCS volume to be added by subtracting Step 1.2 from Step 1.3. 45,827 2.0 CALCULATE RCS fill water source level change for the applicable tank:
KEY 2.1 RECORD start level for RCS fill water source in gallons.
400,000 RWST _________ N/A RHT ________
2.2 RECORD stop level for RCS fill water source in gallons.
354,000 RWST _________ N/A RHT ________
2.3 CALCULATE RCS fill water source level change by subtracting Step 2.2 from Step 2.1.
46,000 RWST _________ N/A RHT ________
3.0 VERIFY RCS fill water source level lower from Step 2.3 approximately equal to calculated RCS volume added from Step 1.4. _____
The difference between the estimated change in RWST level and the actual change in level should be within 200 gallons per the initiating cue.
Estimated change in level: 45,827 gal Actual change in level: 46,000 gal Difference: 173 gal So the actual RWST level change WAS within 200 gallons of the estimated RWST level change.
This procedure, when completed, SHALL be retained.
STPNOC Job Performance Measure DETERMINE H2 RECOMBINER POWER SETTINGS JPM Number: NRC RA(3)
Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC RA(3) - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on LOT 21 NRC Exam.
Page 2 of 8
NRC RA(3) - rev 0 SIMULATOR SETUP INSTRUCTIONS
- 1. This is an Admin JPM.
Page 3 of 8
NRC RA(3) - rev 0 INITIAL CONDITIONS Unit 1 was operating at 100% power when it experienced a loss of coolant accident. The Control Room crew is currently in 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant at the step to monitor Containment Hydrogen levels. Hydrogen concentration is reported to be at 0.7%.
Another operator has completed some initial steps to place the Hydrogen Recombiners in service in accordance with 0POP02-CG-0001, Electric Hydrogen Recombiners and has completed steps 5.1 through 5.7.
INITIATING CUE You have been given 0POP02-CG-0001 and the Unit Supervisor directs you to continue in the procedure and determine the appropriate Hydrogen Recombiner power setting for BOTH Recombiner 1A AND Recombiner 1B by performing steps 5.8 and 5.9.
NOTE: DO NOT use a most conservative approach. Perform your determination as accurately as you can.
Page 4 of 8
NRC RA(3) - rev 0 Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
Determines Hydrogen Recombiner power setting as follows: Recombiner 1A: 71.4 - 72.42 kW and Recombiner 1B: 66.5 - 67.45 kW Page 5 of 8
NRC RA(3) - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Hand out Student Copy of 0POP02-CG-0001, Electric Hydrogen Recombiners.
When the student has reviewed the Initial Conditions & Initiating Cue and they have indicated they are ready to begin the JPM, then record the start time for the JPM.
A KEY is provided for the Examiner.
Determine Pressure Factor Cp Determines Pressure Factor Cp 1 ___ ___ ___
from Recombiner Power is 1.41 based on post-LOCA Correction Factor versus containment pressure and pre-Containment Pressure Curve. LOCA containment (Refer to Addendum 1) temperatures provided on the student handout copy of the procedure.
NOTE: The operator may review the Prerequisites and/or the Notes and Precautions of the procedure.
An acceptable range of Cp will be 1.40-1.42. These values will be used to calculate the range of correct power settings.
Calculate required power Determines Recombiner 1A
- 2 ___ ___ ___
settings for the desired power setting should be 71.4 -
Recombiner by multiplying the 72.42 kW Pressure Factor (Cp) times the reference power. Determines Recombiner 1B power setting should be 66.5 -
67.45 kW NOTE: Refer to KEY provided with this JPM for details of calculations.
CUE This JPM is complete JPM Stop Time:
Page 6 of 8
SUMMARY
Operators Name: Job
Title:
Title:
DETERMINE H2 RECOMBINER POWER SETTINGS JPM Number: NRC RA(3) Revision Number: 0 Task Number and
Title:
96200, Respond to a loss of reactor coolant involving a break size in which Reactor Coolant System pressure drops below High Head Safety Injection Pump shutoff head K/A Number and Importance: 2.1.23 4.3/4.4 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only ; RO/SRO ; AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0POP02-CG-0001, Electric Hydrogen Recombiners, Rev 9 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 10 minutes Actual Time Used: minutes Critical Steps (*) 2 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 7 of 8
Student Handout INITIAL CONDITIONS Unit 1 was operating at 100% power when it experienced a loss of coolant accident.
The Control Room crew is currently in 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant at the step to monitor Containment Hydrogen levels. Hydrogen concentration is reported to be at 0.7%.
Another operator has completed some initial steps to place the Hydrogen Recombiners in service in accordance with 0POP02-CG-0001, Electric Hydrogen Recombiners and has completed steps 5.1 through 5.7.
INITIATING CUE You have been given 0POP02-CG-0001 and the Unit Supervisor directs you to continue in the procedure and determine the appropriate Hydrogen Recombiner power setting for BOTH Recombiner 1A AND Recombiner 1B by performing steps 5.8 and 5.9.
NOTE: DO NOT use a most conservative approach. Perform your determination as accurately as you can.
Page 8 of 8
0POP02-CG-0001 Rev. 9 Page 4 of 15 Electric Hydrogen Recombiners NOTE Operation of the Hydrogen Recombiners is done manually from the Main Control Room on CP002.
5.0 Post-LOCA Hydrogen Recombiner Start-up 5.1 VERIFY Hydrogen Recombiners potentiometers labeled PWR ADJ are set at zero (000).
BH 1A(2A) _____ BH 1B(2B) _____
5.2 SELECT which of the Hydrogen Recombiners is to be placed in service.
BH 1A(2A) _____
BH 1B(2B) _____
5.3 VERIFY white lamp labeled PWR AVAIL is lit.
BH 1A(2A) _____ BH 1B(2B) _____
5.4 TURN the switch labeled PWR to the ON position.
BH 1A(2A) _____ BH 1B(2B) _____
5.5 VERIFY red PWR indicator lamp is lit.
BH 1A(2A) _____ BH 1B(2B) _____
NOTE The Post LOCA Containment Pressure and the Pre-LOCA Containment Temperature recorded in Steps 5.6 and 5.7 are the parameters used in Step 5.8 to determine the pressure factor.
5.6 DETERMINE Containment pressure prior to and after a LOCA Provided from on the handout copy Chart Recorder for CONTAINMENT PRESS 1(2)-HC-PR-0934 OR WR PRESS 1(2)-HC-PR-9759. (CP018)
Containment Pressure Prior to LOCA 0.2 psig KEY Post LOCA Containment Pressure 8.5 psig This procedure, when complete, SHALL be retained for five years.
0POP02-CG-0001 Rev. 9 Page 5 of 15 Electric Hydrogen Recombiners 5.7 DETERMINE the Pre-LOCA Containment Temperature from one of the RCFC inlet temperatures recorded on the Operator Logsonfor Provided a RCFC the in operation handout copy prior to the LOCA.
1A(2A): (TI-9661, TI-9664 or TI-9670) 100 qF Temp _____
1B(2B): (TI-9667, TI-9673 or TI-9676) 100 qF Temp _____
5.8 DETERMINE Pressure Factor Cp from Hydrogen Recombiner Power Correction Factor versus Containment Pressure Curve. (Refer To Addendum 1)
Cp _____
5.9 (UNIT 1 ONLY) CALCULATE required power setting for the desired Hydrogen Recombiner by multiplying the Pressure Factor (Cp) times the Reference Power:
Hydrogen Recombiner 1A Power Setting 1.40 - 1.42
_____________________ 51 KW = 71.4 - 72.42 KW
__________________________ KW X
Pressure Factor (Cp) Ref Pwr (Required PWR Setting)
Hydrogen Recombiner 1B Power Setting 1.40 - 1.42
_____________________ 47.5 KW = 66.5 - 67.45 KW
__________________________ KW X
Pressure Factor (Cp) Ref Pwr (Required PWR Setting)
This5.10 range(UNIT 2 ONLY) of values is basedCALCULATE on the required These power setting are thefor the desired correct rangesHydrogen of power Recombiner given information by multiplying of post-LOCA the Pressure Factor pressure (Cp) times the Reference settings for the Recombiners. Power:
of 8.5 psig and pre-LOCA temperature of 100 deg. F.Hydrogen Recombiner 2A Power Setting See Addendum 1 on next page.
_____________________ 43.5 KW = __________________________ KW X
Pressure Factor (Cp) Ref Pwr (Required PWR Setting)
Hydrogen Recombiner 2B Power Setting
_____________________ 43.5 KW = __________________________ KW X
Pressure Factor (Cp) Ref Pwr (Required PWR Setting)
KEY This procedure, when complete, SHALL be retained for five years.
0POP02-CG-0001 Rev. 9 Page 12 of 15 Electric Hydrogen Recombiners Addendum 1 Dry Containment Hydrogen Recombiner Power Correction Page 1 of 1 Factor Versus Containment Pressure 1.7 PRE-LOCA CONTAINMENT 1.6 TEMPERATURE 60qF 90qF 100 Degrees F 120qF
.P R 1.5 E
S S
U CP 1.41 R
E F 1.4 A
C T
O R
(CP) 1.3 1.2 1.1 1.0 0 2 4 6 8 9 10 12 14 8.5 POST-LOCA CONTAINMENT PRESSURE (PSIG)
KEY
STPNOC Job Performance Measure COMPLETE AN OFFSITE AGENCY NOTIFICATION MESSAGE FORM JPM Number: NRC RA(4)
Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC RA(4) - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on LOT 21 NRC Exam.
Page 2 of 8
NRC RA(4) - rev 0 SIMULATOR SETUP INSTRUCTIONS
- 1. This is an Admin JPM.
Page 3 of 8
NRC RA(4) - rev 0 INITIAL CONDITIONS
- The Unit 2 Shift Manager/Emergency Director has just declared an ALERT due to a fire in the Train B 4.16KV switchgear room.
- This was the initial declaration for the event.
- Plant conditions are listed below.
INITIATING CUE This JPM is time-critical. The time limit starts when you (the applicant) understand the Initial Conditions and Initiating Cue.
As an extra Reactor Operator, the Shift Manager/Emergency Director directs you to MANUALLY complete Form 1, Offsite Notification Message, of 0ERP01-ZV-IN02, Notifications to Offsite Agencies.
- Use current date/time as the Emergency Classification declaration date/time.
- Use 361-972-7900 as the Call Back#
THIS IS A DRILL Plant Conditions
- A fire in the Unit 2 Train B 4.16KV switchgear room caused the Shift Manager to declare an ALERT due to Initiating Condition SA9, Hazardous event affecting a SAFETY SYSTEM needed for the current operating mode. (use current date/time as the declaration date/time)
- The Shift Manager/Emergency Director has determined there are no Recommended Protective Actions at this time.
- The Unit continues to operate at 100% power.
- The Department of State Health Services (DSHS) has not yet been contacted.
- No release is in progress.
- Wind speed is 10 mph from 80 degrees THIS IS A DRILL Page 4 of 8
NRC RA(4) - rev 0 Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
Form 1, Offsite Notification Message is correctly completed within 15 minutes of start time.
Refer to KEY.
Page 5 of 8
NRC RA(4) - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Hand out Student Copy of 0ERP01-ZV-IN02, Notifications to Offsite Agencies.
When the student has reviewed the Initial Conditions & Initiating Cue and they have indicated they are ready to begin the JPM, then record the start time for the JPM. This JPM is time critical and must be completed in 15 minutes.
A KEY is provided for the Examiner.
Complete Form 1, Offsite Completes items 1-14 on Form
- 1 ___ ___ ___
Notification Message 1 within 15 minutes. Refer to the KEY for a completed form.
NOTE: There are 6 critical items to be completed and are circled on the KEY.
Present completed Form 1 to Presents completed Form 1 to 2 ___ ___ ___
the Shift Manager/Emergency the Shift Manager/Emergency Director for approval. Director for approval.
CUE This JPM is complete JPM Stop Time:
Page 6 of 8
SUMMARY
Operators Name: Job
Title:
Title:
COMLETE AN OFFSITE AGENCY NOTIFICATION MESSAGE FORM JPM Number: NRC RA(4) Revision Number: 0 Task Number and
Title:
221433, Prepare the notification form.
K/A Number and Importance: 2.4.39 3.9/3.8 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only ; RO/SRO ; AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0ERP01-ZV-IN02, Notifications to Offsite Agencies, Rev 34 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes Critical Steps (*) 1 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 7 of 8
Student Handout INITIAL CONDITIONS
- The Unit 2 Shift Manager/Emergency Director has just declared an ALERT due to a fire in the Train B 4.16KV switchgear room.
- This was the initial declaration for the event.
- Plant conditions are listed below.
INITIATING CUE This JPM is time-critical. The time limit starts when you (the applicant) understand the Initial Conditions and Initiating Cue.
As an extra Reactor Operator, the Shift Manager/Emergency Director directs you to MANUALLY complete Form 1, Offsite Notification Message, of 0ERP01-ZV-IN02, Notifications to Offsite Agencies.
- Use current date/time as the Emergency Classification declaration date/time.
- Use 361-972-7900 as the Call Back#
THIS IS A DRILL Plant Conditions
- A fire in the Unit 2 Train B 4.16KV switchgear room caused the Shift Manager to declare an ALERT due to Initiating Condition SA9, Hazardous event affecting a SAFETY SYSTEM needed for the current operating mode. (use current date/time as the declaration date/time)
- The Shift Manager/Emergency Director has determined there are no Recommended Protective Actions at this time.
- The Unit continues to operate at 100% power.
- The Department of State Health Services (DSHS) has not yet been contacted.
- No release is in progress.
- Wind speed is 10 mph from 80 degrees THIS IS A DRILL Page 8 of 8
0ERP01-ZV-IN02 Rev. 34 Page 32 of 35 Notifications To Offsite Agencies Form 1 Offsite Notification Message Page 1 of 1 STP1690 (10/15)
Rev. 18 SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION OFFSITE NOTIFICATION MESSAGE
- 1. X This is a drill This is NOT a drill There are six (6) items circled which
- 2. Initial Contact Time: are CRITICAL to the task.
- 3. Roll Call: DPS Pierce: Matagorda County:
- 4. Affected Unit: 1 X 2 Both KEY
- 6. Unusual Event X Alert Site Area Emergency General Emergency Terminated
- 7. Declared: Date: Current Time: Current
- 8. Initiating Condition: SA9 (alphanumeric)
- 9. Wind Speed: 10 MPH Wind Direction From: 80 DEG
- 10. Radiological Release In Progress: Yes X No
- 11. Protective Action Recommendations: Yes X No
- a. Evacuate Zones:
- b. Shelter In Place Zones:
- c. Affected Downwind Sectors:
ALL REMAINING ZONES MONITOR AND PREPARE
- 12. Information Reported To and Verified with Both Offsite Agencies: Time:
- 13. Remarks:
- 14. Communicator Name: Applicant Name Call Back#
- 15. Approved: Date: Time:
Emergency Director WHEN COMPLETED, THIS RECORD SHALL BE RETAINED IN ACCORDANCE WITH THE DOCUMENT TYPE LIST (DTL).
STPNOC Job Performance Measure CALCULATE ALLOWABLE TIME REMAINING IN CONDENSER PRESSURE RESTRICTED ZONE JPM Number: NRC SA(5)
Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC SA(5) - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on LOT 21 NRC Exam.
Page 2 of 8
NRC SA(5) - rev 0 SIMULATOR SETUP INSTRUCTIONS
- 1. This is an Admin JPM.
Page 3 of 8
NRC SA(5) - rev 0 INITIAL CONDITIONS Unit 1 is in Mode 6 and core reload is in progress.
The last Fuel Assembly placed in the core was at location C4.
INITIATING CUE You have just relieved the Core Load Supervisor on the Refueling Machine and you have the following:
- 0POP08-FH-0001, Refueling Machine Operating Instructions, Addendum 4, Guidelines For Close Contact Assembly Movements, for reference.
- A copy of the current Fuel Transfer Form.
- A map of all core locations showing the current status of Fuel Assemblies that have been placed in the core.
You are to determine the type of Close Contact movement to be performed for the next three (3) Fuel Assemblies to be moved.
Use area below to describe Close Contact movement for each identified Fuel Assembly.
First Fuel Assembly:
Second Fuel Assembly:
Third Fuel assembly:
Page 4 of 8
NRC SA(5) - rev 0 Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
Determines the correct Close Contact Movement for the identified Fuel Assemblies. See STANDARD for each Performance Step.
Page 5 of 8
NRC SA(5) - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Hand out Student Copy of 0POP08-FH-0001, Refueling Machine Operating Instructions, Addendum 4, Guidelines For Close Contact Assembly Movements; Student Copy of the Fuel Transfer Form; and Student Copy of core map showing current locations of Fuel Assemblies already placed into the core.
When the student has reviewed the Initial Conditions & Initiating Cue and they have indicated they are ready to begin the JPM, then record the start time for the JPM.
A KEY is provided for the Examiner.
Determine correct Close Determines that Fuel Assembly
- 1 ___ ___ ___
Contact Movement for Fuel to be placed in core location B4 Assembly to be placed in core should be LOWERED on-index location B4. at slow speed. (Case 2)
NOTE: Refer to KEY.
Overload/Underload switch position is not required to be identified for this JPM.
Determine correct Close Determines that Fuel Assembly
- 2 ___ ___ ___
Contact Movement for Fuel to be placed in core location H8 Assembly to be placed in core should be LOWERED in open location H8. water until clear of lower core plate pins (equal to open water jog height from bottom). Using manual or jog mode, move in one direction to on-index then the other direction to on-index and then lower at slow speed.
(Case 3)
NOTE: Refer to KEY.
Overload/Underload switch position is not required to be identified for this JPM.
CUE This JPM is complete JPM Stop Time:
Page 6 of 8
SUMMARY
Operators Name: Job
Title:
Title:
DETERMINE CLOSE CONTACT FUEL ASSEMBLY MOVEMENT JPM Number: NRC SA(5) Revision Number: 0 Task Number and
Title:
148344, Supervise Refueling Operations as the Core Load Supervisor.
K/A Number and Importance: 2.1.42 2.5/3.4 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only ; RO/SRO ; AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0POP08-FH-0001, Refueling Machine Operating Instruction, Rev 47, and CR 16-13605 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 10 minutes Actual Time Used: minutes Critical Steps (*) 2 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 7 of 8
Student Handout INITIAL CONDITIONS Unit 1 is in Mode 6 and core reload is in progress.
The last Fuel Assembly placed in the core was at location C4.
INITIATING CUE You have just relieved the Core Load Supervisor on the Refueling Machine and you have the following:
- 0POP08-FH-0001, Refueling Machine Operating Instructions, Addendum 4, Guidelines For Close Contact Assembly Movements, for reference.
- A copy of the current Fuel Transfer Form.
- A map of all core locations showing the current status of Fuel Assemblies that have been placed in the core.
You are to determine the type of Close Contact movement to be performed for the next three (3) Fuel Assemblies to be moved.
Use area below to describe Close Contact movement for each identified Fuel Assembly.
First Fuel Assembly:
Second Fuel Assembly:
Third Fuel assembly:
Page 8 of 8
LOT 21 NRC JPM SA(5) Rev. 0 Student Handout Identify moves in order.
1st - B4 2nd - H8 3rd - H7 1st Fuel Assembly B4 Lower on index in slow speed.
Case 2 W E S T 1 L1 K1 J1 H1 G1 F1 E1 2 N2 M2 L2 K2 J2 H2 G2 F2 E2 D2 C2 3 P3 N3 M3 L3 K3 J3 H3 G3 F3 E3 D3 C3 B3 TROLLEY 4 P4 N4 M4 L4 K4 J4 H4 G4 F4 E4 D4 C4 POSITION R5 P5 N5 M5 L5 K5 J5 H5 5
S 6 R6 P6 N6 M6 L6 K6 J6 H6 N O 7 R7 P7 N7 M7 L7 K7 J7 O U 8 R8 P8 N8 M8 L8 K8 J8 R T 9 R9 P9 N9 M9 L9 K9 J9 H9 T H 10 R10 P10 N10 M10 L10 K10 J10 H10 H 11 R11 P11 N11 M11 L11 K11 J11 H11 12 P12 N12 M12 L12 K12 J12 H12 G12 F12 E12 D12 C12 B12 13 P13 N13 M13 L13 K13 J13 H13 G13 F13 E13 D13 C13 B13 14 N14 M14 L14 K14 J14 H14 G14 F14 E14 D14 C14 KEY 15 L15 K15 J15 H15 G15 F15 E15 R P N M L K J H G F E D C B A E A S T 2nd Fuel Assembly H8 TROLLEY FORWARD (paraphrased) Lower off index in open water to 'open water BRIDGE BRIDGE LEFT RIGHT jog height', jog to on index and lower rest of way in slow TROLLEY 3rd Fuel Assembly H7 speed. REVERSE Lower on index in slow speed.
Case 3 Case 2
STPNOC Job Performance Measure REVIEW ESF POWER AVAILABILITY SURVEILLANCE RESULTS JPM Number: NRC SA(6)
Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC SA(6) - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on LOT 21 NRC exam.
Page 2 of 8
NRC SA(6) - rev 0 SIMULATOR SETUP INSTRUCTIONS
- 1. This is an Admin JPM.
Page 3 of 8
NRC SA(6) - rev 0 INITIAL CONDITIONS Unit 1 is at 100% power with a Train A outage week in progress. The following plant conditions exist:
- At 1145 today, the breaker from 4.16 KV Bus E1C to 4.16 KV/480 V XFMR E1C1 (4.16 KV/480 Volt E1C1 Transformer primary side breaker) tripped open.
- Operations personnel have cross tied Load Centers E1C1 and E1C2 (cross tie breaker is closed).
- 0PSP03-EA-0002, ESF Power Availability, was performed today at 1200, 30 minutes ago, to satisfy the requirements of Technical Specification 3.8.1.1.b. due to #11 ESF D/G being OOS.
INITIATING CUE As the Unit Supervisor in Unit 1, you are to perform the Test Results Second Review for the completed ESF Power Availability Surveillance, and document your review by completing Step 5 of the Data Package Cover Sheet.
NOTE: THE SHIFT MANAGER WILL PERFORM THE REPORTABILITY REVIEW PORTION OF STEP 5.
Page 4 of 8
NRC SA(6) - rev 0 Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
Determines that Surveillance Test results should be unacceptable based on failing to meet surveillance acceptance criteria 6.3, an LCO action statement should be entered (checked YES) and the correct Technical Specification noted.(LCO 3.8.3.1.c is not met & LCO 3.8.3.1 Action a should be entered.)
Page 5 of 8
NRC SA(6) - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Handout the student copy of 0PSP03-EA-0002, ESF Power Availability.
A copy of Technical Specifications will be available to the student.
A KEY is provided for the Evaluator.
1 Review ESF Power The applicant reviews the ESF Power ___ ___ ___
Availability Surveillance. Availability Surveillance for accuracy.
- 2 Complete Test Results Determines the following on the Test ___ ___ ___
Second Review section. Results Second Review section:
- 1) *Test Results - Unacceptable*
Cue:
- 2) *Refer to T.S. - 3.8.3.1. Action If the applicant begins to a applies*
pursue a reportability determination, inform him 3) Is this condition a potentially
/ her that SRO will reportable occurrence? - N/A per determine reportability. Initiating Cue
- 4) *Should an LCO action statement be entered? - YES*
- 5) Fill out REMARKS section with words to the effect of:
Surveillance Acceptance Criteria 6.3 is not satisfied. (480 V Load Center E1C1 is not energized via its respective load center transformer.)
Technical Specification LCO action statement 3.8.3.1.c is not met and 3.8.3.1 Action a should be entered based on the loss of the normal power supply to the 480 V Load Center E1C1.
CUE This JPM is complete (Must be completed within 15 minutes.)
JPM Stop Time:
Page 6 of 8
SUMMARY
Operators Name: Job
Title:
Title:
REVIEW ESF POWER AVAILABILITY SURVEILLANCE RESULTS JPM Number: NRC SA(6) Revision Number: 0 Task Number and
Title:
12000 (SRO), Authorize the start of and review surveillance tests.
K/A Number and Importance: 2.1.20 4.6/4.6 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only ; RO/SRO ; AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0PSP03-EA-0002, ESF Power Availability, Rev 37 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 25 minutes Actual Time Used: minutes Critical Steps (*) 2 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 7 of 8
Student Handout INITIAL CONDITIONS Unit 1 is at 100% power with a Train A outage week in progress. The following plant conditions exist:
- At 1145 today, the breaker from 4.16 KV Bus E1C to 4.16 KV/480 V XFMR E1C1 (4.16 KV/480 Volt E1C1 Transformer primary side breaker) tripped open.
- Operations personnel have cross tied Load Centers E1C1 and E1C2 (cross tie breaker is closed).
- 0PSP03-EA-0002, ESF Power Availability, was performed today at 1200, 30 minutes ago, to satisfy the requirements of Technical Specification 3.8.1.1.b. due to #11 ESF D/G being OOS.
INITIATING CUE As the Unit Supervisor in Unit 1, you are to perform the Test Results Second Review for the completed ESF Power Availability Surveillance, and document your review by completing Step 5 of the Data Package Cover Sheet.
NOTE: THE SHIFT MANAGER WILL PERFORM THE REPORTABILITY REVIEW PORTION OF STEP 5.
Page 8 of 8
0PSP03-EA-0002 Rev. 37 Page 25 of 39 ESF Power Availability Data Package Data Package Cover Sheet Page 2 of 2
- 4. Test Results:
________ Acceptable ________ Unacceptable IF unacceptable, THEN immediately INFORM the Shift Manager.
-RKQ5LFKDUGV
______________________________ 7RGD\
_______ PLQDJR Test Performer Date Time
- 5. Test Results Second Review:
________ Acceptable ________ Unacceptable (complete section below)
ANSWER Refer to Technical Specification __________ LCO Action Requirements KEY Is this condition a potentially reportable occurrence? _____ Yes
_____ No This section N/A per Initiating Cue Should an LCO Action Statement be entered? _____ Yes
_____ No (Words to the effect of...) Surveillance Acceptance Criteria 6.3 is NOT satisfied.
Remarks__________________________________________________________________________
480 volt Load Center E1C1 is NOT energized via its respective Load Center Transformer.
This condition does not meet the requirements of TS LCO 3.8.3.1.c. Action a. will need to be entered. Circled items need to be identified on student copy of Data Package.
Shift Manager Date Time
- 6. Data Review:
Surveillance Coordinator Date Time This procedure, when complete, SHALL be retained for five years.
STPNOC Job Performance Measure REVIEW A FAULTED ECO FOR AFW PUMP JPM Number: NRC SA(7)
Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC SA(7) - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on LOT 21 NRC exam.
Page 2 of 8
NRC SA(7) - rev 0 SIMULATOR SETUP INSTRUCTIONS
- 1. This is an Admin JPM.
Page 3 of 8
NRC SA(7) - rev 0 INITIAL CONDITIONS During the performance of a scheduled AFW Train B surveillance, flow anomalies and noises were noticed just downstream of AFW Pump 22. After a walkdown by the system engineer, AFW Pump 22 auto recirc control flow valve, AF-0058, is suspected of having a detached disk.
It has been decided to internally inspect AF-0058 for damage. Oracle is not available due to problems with the LAN. ECO #2-17-0002 has been manually written to isolate AF-0058.
INITIATING CUE You are directed to perform the Technical Review of the ECO in accordance with 0PGP03-ZO-ECO1A, Equipment Clearance Order Instructions.
You are to take the following into account during your review:
- 1) There are no intended layout errors in the ECO form itself. (i.e., likeness to procedure form)
- 2) Restoration positions and components listed solely for restoration purposes are not included on this ECO. (not required)
- 3) Review of the individual ECO tags will not be required. ECO tags will not be provided.
Page 4 of 8
NRC SA(7) - rev 0 Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
Identifies two Critical errors in the Equipment Clearance Order (ECO) IAW with Section 6.5 of 0PGP03-ZO-ECO1A, Equipment Clearance Order Instructions.
- 8, NOT Cubicle #7 as listed. (ECO Line Item #3)
- 2. The discharge valve should be AF-0059, NOT AF-0078 as listed. (ECO Line Item #8)
Page 5 of 8
NRC SA(7) - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE
- 1) Provide the operator with the following:
- ECO Request Form (Form 2 labeled with STUDENT COPY).
- Faulted ECO Form (Form 3 labeled with STUDENT COPY).
- ECO Preparation Checklist (Form 9 labeled with STUDENT COPY).
- Unmarked copies of the following drawings:
o P&ID Drawing 2-F-00024 SHT #1 Rev 13 o Single Line Diagram 9-E-0PKAB#2 Rev 10 o Elementary Diagram 9-E-0AF08#2 Rev 10
- Equipment Clearance Order Procedure (0PGP03-ZO-ECO1A).
A KEY is provided for the Evaluator. The KEY contains the same incorrect entries on the line items as the Student Handout. The location of the errors will be highlighted and described on the KEY. Do not give this or the KEY to the operator.
1 Ensure adequate personnel Identifies the following ERRORS: ___ ___ ___
and equipment safety is 1. Wrong power supply is listed for provided. AFW Pump 22. Should be 4160 V SWGR E2B Cubicle #8, NOT Cubicle #7 as listed. (ECO Line Item #3)
- 2. Discharge valve should be AF-0059, NOT AF-0078 as listed.
(ECO Line Item #8)
NOTE:
Error #1, wrong AFW Pump breaker power supply (Line Item
- 3) is carried over to Line Items #4 and #5 for consistency and realism.
CUE This JPM is complete (Must be completed within 15 minutes.)
JPM Stop Time:
Page 6 of 8
SUMMARY
Operators Name: Job
Title:
Title:
REVIEW A FAULTED ECO FOR AFW PUMP JPM Number: NRC SA(7) Revision Number: 0 Task Number and
Title:
11500 (SRO), Knowledge of Tagging and Clearance Order Procedures.
K/A Number and Importance: 2.2.13 4.1/4.3 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only ; RO/SRO ; AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0PGP03-ZO-ECO1A, Equipment Clearance Order Instructions, R28 P&ID Drawing 1-F-00024 #2 Rev 12 Single Line Diagram 9-E-0PKAB#2 Rev 10 Elementary Diagram 9-E-0AF08#2 Rev 10 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes Critical Steps (*) 1 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 7 of 8
Student Handout INITIAL CONDITIONS During the performance of a scheduled AFW Train B surveillance, flow anomalies and noises were noticed just downstream of AFW Pump 22. After a walkdown by the system engineer, AFW Pump 22 auto recirc control flow valve, AF-0058, is suspected of having a detached disk.
It has been decided to internally inspect AF-0058 for damage. Oracle is not available due to problems with the LAN. ECO #2-17-0002 has been manually written to isolate AF-0058.
INITIATING CUE You are directed to perform the Technical Review of the ECO in accordance with 0PGP03-ZO-ECO1A, Equipment Clearance Order Instructions.
You are to take the following into account during your review:
- 1) There are no intended layout errors in the ECO form itself. (i.e., likeness to procedure form)
- 2) Restoration positions and components listed solely for restoration purposes are not included on this ECO. (not required)
- 3) Review of the individual ECO tags will not be required. ECO tags will not be provided.
Page 8 of 8
0PGP03-ZO-ECO1A Rev. 28 Page 95 of 117 Equipment Clearance Order Instructions Form 3 (Rev. 0) Equipment Clearance Order Form (Line Items) Page 3 of 3 ECO Number: 2 17 0002
________-_______-_____________ Page 3 of 3 Unit Year Number Line Number BOUNDARY Performed By Verification Exe. Seq Verified By Component ID Type Or Line Number 3 Action Required Position Required?
Instructions The wrong power supply is listed. The correct power 1 Y supply is SWGR E2BPull Cub 8 C AFW Pump 22 CRHS Hang 1 to Lock which is adjacent to this AFW 2B XCONN cubicle on the drawing. The 2 C Y Hang Auto/Close FV-7516 CRHS error is carried 1forward to line SWGR E2B Cub 7 AFW Pump 22 items #4 and #5 for realism.
3 D B Hang 2 Racked Out Hang tag on door Y 4 Closing Fuses for SWGR E2B Cub 7 Y 5 Tripping Fuses for SWGR E2B Cub 7 RR121B DS32 6 D B Y Hang 3 Fuse Removed AF-FV-7516 AF-0061 SG 2B AFW Reg Vlv 7 D B Y Hang 4 Line Number 8 Close FV-7524 Manual Isolation Valve AF-0078 AFW Pump 22 Disch Hang The wrong Close valve number is 8 D B Y 4 Manual Isol Vlv listed. The correct valve FV-7516 Handwheel number4 is AF-0059 9 D B Y Hang Close which is AFW Crossover Valve directly above this valve on AF-0067 AFW Pump 22 Auto the P&ID.
10 D B Y Hang 4 Close Recirc Isol Valve AF-0053 AFW Pump 22 Suction 11 D B Y Hang 4 Close Isol Valve AF-0211 AFW Pump 22 Suction 12 D B Y Hang 5 Open Line Drain Valve AF-0185 AFW Pump 22 Discharge 13 D B Y Hang 6 Open Line Vent Valve THIS FORM, WHEN COMPLETE, SHALL BE RETAINED FOR A MINIMUM OF 5 YEARS. RMS Z10.03
STPNOC Job Performance Measure INITIATE A DOSE EXTENSION JPM Number: NRC SA(8)
Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC SA(8) - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on LOT 21 NRC exam.
Page 2 of 9
NRC SA(8) - rev 0 SIMULATOR SETUP INSTRUCTIONS
- 1. This is an Admin JPM.
Page 3 of 9
NRC SA(8) - rev 0 INITIAL CONDITIONS John King is a recently hired Non Licensed Operator (NLO) from another utility. John received 300 mrem at his previous employer this year prior to coming to STP, and has received 1600 mrem since starting work at STP.
INITIATING CUE Due to manpower shortages, John was asked to perform an outage job in which he would receive an additional 200 mrem. John has agreed to perform the job and has presented you (his supervisor) with Form 2, Personnel Dose Extension Authorization, for your signature.
Additional information for John King:
- Age - 27 years
- Lifetime dose - 2200 mrem
- Year-to-date eye dose - 1900 mrem
- 1) Determine the total annual exposure extension necessary.
- 2) Identify whose approval is required for the dose extension.
Page 4 of 9
NRC SA(8) - rev 0 Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
Determines the requested annual dose extension number to be 2100 mrem and identifies the Responsible Department Manager (Operations Manager) and Radiation Protection Manager as the individuals that must approve the extension.
Page 5 of 9
NRC SA(8) - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Hand out Student Copy of 0PGP03-ZR-0050, Radiation Protection Program, including filled out Form 2, Personnel Dose Extension Authorization.
A KEY is provided for the Examiner.
1 Determine if Form 2 is Reviews 0PGP03-ZR-0050, ___ ___ ___
completed correctly. Radiation Protection Program, Form 2, Personnel Dose Extension Authorization, for accuracy.
NOTE Addendum 1 of 0PGP03-ZR-0050, Radiation Protection Program, has instructions for determining personnel dose extensions.
Extension request must include exposure received at previous employer.
1600 mrem (STP YTD TEDE listed on Form 2) + 300 mrem (Offsite YTD TEDE listed on Form 2) + 200 mrem (Outage Job Dose listed in Initiating Cue) = 2100 mrem annual exposure extension.
A KEY is provided for the Examiner.
- 2 Determine the requested annual Determines the requested ___ ___ ___
exposure extension. annual exposure extension to should be 2100 mrem.
NOTE: 100 mrem more than the new STP annual exposure administrative limit of 2000 mrem.
Page 6 of 9
NRC SA(8) - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number Identifies the following as the
- 3 Identify individuals who must ___ ___ ___
individuals who must approve approve the extension.
the extension:
- Responsible Department Manager (Operations Manager)
AND
- Radiation Protection Manager CUE This JPM is complete (Must be completed within 15 minutes.)
JPM Stop Time:
Page 7 of 9
SUMMARY
Operators Name: Job
Title:
Title:
INITIATE A DOSE EXTENSION JPM Number: NRC SA(8) Revision Number: 0 Task Number and
Title:
20100 (SRO), Supervise Control Room personnel during startup and shutdown.
K/A Number and Importance: 2.3.13 3.4/3.8 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only ; RO/SRO ; AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0PGP03-ZR-0050, Radiation Protection Program, R14 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes Critical Steps (*) 2 & 3 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 8 of 9
Student Handout INITIAL CONDITIONS John King is a recently hired Non Licensed Operator (NLO) from another utility. John received 300 mrem at his previous employer this year prior to coming to STP, and has received 1600 mrem since starting work at STP.
INITIATING CUE Due to manpower shortages, John was asked to perform an outage job in which he would receive an additional 200 mrem. John has agreed to perform the job and has presented you (his supervisor) with Form 2, Personnel Dose Extension Authorization, for your signature.
Additional information for John King:
- Age - 27 years
- Lifetime dose - 2200 mrem
- Year-to-date eye dose - 1900 mrem
- 1) Determine the total annual exposure extension necessary.
- 2) Identify whose approval is required for the dose extension.
WRITE ANSWER BELOW:
Page 9 of 9
File:U28/D43 PDRP DTL 6935 0PGP03-ZR-0050 Rev. 14 Page 26 of 26 Radiation Protection Program Form 2 (Rev 3) Personnel Dose Extension Authorization Page 1 of 1 SECTION 1 (Completed by requesting individual and supervisor) (Note:
that letters are variables for calculation purposes)
John King Name:__________________________ 123-45-6789 SSN:__________________ 27 Age:___(E) STP Ops Co./Dept._____/______
2100 I request an annual exposure extension to______mrem 2017 (A+F) total (STP plus other licensees) for year _______.
Reason To be able to perform outage job STP = current + estimated 1800 = 1600 + 200 John King Today other licenses Applicant Signature Date 300 Supervisor or Employer Date REQUESTED EXTENSION = STP + other licenses SECTION 2 (Completed by Dosimetry Personnel) 2100 = 1800 + 300 Dose History: [X ] Form 4/5 [ ] PADS [ ] Statement 2200 Lifetime TEDE: _________mrem (D) 1600 STP YTD TEDE: ________mrem (A) 1900 EYE DOSE (all sources YTD): ________mrem (typically A+B) 300 Offsite YTD TEDE:_________mrem (B) TEDE=DDE+CEDE or TEDE=EDEx+CEDE 1900 Current YTD TEDE: ____mrem (A+B) = 1600 300 Total 24800 Y
_______mrem (A) + _______mrem Record Estimate (B) 100 Fred Sanford KE AVAILABLE LIFETIME MARGIN: _____mrem (E-D)*1000 [Age - Lifetime TEDE (rem)] x 1000 AVAILABLE ANNUAL MARGIN: ______mrem (X) [2000 - Current YTD TEDE]
[ (X=2000-A-B) ]
Today Completed By:_____________________________Date:___________
REQUIRED SIGNTURES SECTION 3: APPROVALS Signatures/Date Extension Due to Annual Dose Control (1) /
2000 to 3000 mrem/yr: (1)(2) Responsible Department Manager
>3000 to 4000 mrem/yr: (1)(2)(3)
>4000 to 5000 mrem/yr: (1)(2)(3)(4) (2) /
Radiation Protection Manager Extension Due to Lifetime Dose Control
>0 to 1000 mrem/yr with lifetime TEDE > Age in Rem: (3) /
(1)(2)(3)
>1000 mrem/yr with lifetime TEDE > Age in Rem: (1)(2)(3)(4) Plant General Manager This extension permits an additional ______mrem (F) to be (4) /
received. Note F must be > RWP set points STPNOC Vice President Extension granted to _____mrem (A+F) for calendar year_____.
KEY Computer updated by:
Initials Date When completed, this form SHALL be retained in accordance with the Document Type List (DTL).
STPNOC Job Performance Measure DETERMINE APPROPRIATE PROTECTIVE ACTION RECOMMENDATION JPM Number: NRC SA(9)
Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC SA(9) - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on LOT 21 NRC exam.
Page 2 of 9
NRC SA(9) - rev 0 SIMULATOR SETUP INSTRUCTIONS
- 1. This is an Admin JPM.
Page 3 of 9
NRC SA(9) - rev 0 INITIAL CONDITIONS Due to degrading plant conditions a General Emergency has just been declared in Unit 1.
Emergency Plan requirements with the exception of Protective Action Recommendations (PARs) are in progress or have been delegated to other individuals.
INITIATING CUE You are the Emergency Director in the Control Room and, due to rapidly degrading conditions associated with fission product barriers, you have just declared a General Emergency.
You are at Step 1.4 of 0ERP01-ZV-SH01, Shift Manager, Checklist 4, General Emergency Checklist.
You are to determine the PARs for the State/County, including downwind Zones and Sectors, in accordance with 0ERP01-ZV-IN07, Offsite Protective Action Recommendations.
Additional Information:
- A radiological release is NOT in progress.
- Current Weather conditions are:
Wind - Blowing from 120° at 12 mph.
Temperature - 88°F Precipitation - None
- NO conditions exist that would hinder an evacuation.
THIS JPM IS TIME CRITICAL.
Page 4 of 9
NRC SA(9) - rev 0 Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
The applicant determines that the Protective Action Recommendation (PAR) is as follows:
- Evacuate Downwind Zones 10 Miles: 1, 5, 9, 10, 11.
- The affected downwind sectors are N, P, Q, and R.
Page 5 of 9
NRC SA(9) - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Copies of E-Plan Procedures will be provided in the Exam Room.
When the student has reviewed the Initial Conditions & Initiating Cue AND they have indicated they are ready to begin the JPM, then record the start time for the JPM.
1 Determine Protective Action With no radiological release in ___ ___ ___
Recommendations (PARs) at a progress, the operator will go to General Emergency by one of 0ERP01-ZV-IN07, Addendum 2, the following methods: Protective Action
- IF a radiological release is Recommendation Decision ongoing: Flowchart, to determine
- Performing dose protective action assessment recommendations.
(STAMPEDE). (0ERP01-ZV-IN07, Step 5.1.2)
- Manually using procedure 0ERP01-ZV-TP01, Offsite Dose Calculations with Addendum 1, Radiological Release Protective Action Recommendations.
- IF no radiological release, determine using Addendum 2 Protective Action Recommendation Decision Flowchart.
- To Expand a PAR use Addendum 2, Protective Action Recommendation Decision Flowchart.
(0ERP01-ZV-IN07, Step 5.1)
Page 6 of 9
NRC SA(9) - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number 2 With no radiological release in Determines PAR is to evacuate ___ ___ ___
progress, the operator ZONE 1 and downwind zones evaluates PAR flowchart from 10 miles. All others Monitor and 0ERP01-ZV-IN07, Offsite Prepare. Refer to Addendum 3 Protective Action for evacuated zones & affected Recommendations, Addendum downwind sectors.
2, Protective Action Operator goes to 0ERP01-ZV-Recommendation Decision IN07, Offsite Protective Action Flowchart. Recommendations, Addendum 3, Evacuate zones and affected downwind sectors.
- 3 Determine Protective Response Determines PAR as follows: ___ ___ ___
Zones and Affected Downwind
- Evacuate Downwind Zones Sectors to enter on 0ERP01-10 Miles: 1, 5, 9, 10, 11.
ZV-IN02, Form 1, Offsite Notification Message.
- The affected downwind sectors are N, P, Q, and R.
CUE This JPM is complete (Must be completed within 15 minutes.)
JPM Stop Time:
Page 7 of 9
SUMMARY
Operators Name: Job
Title:
Title:
DETERMINE APPROPRIATE PROTECTIVE ACTION RECOMMENDATION JPM Number: NRC SA(9) Revision Number: 0 Task Number and
Title:
74029 (SRO), Classify Emergency Conditions K/A Number and Importance: 2.4.44 2.4/4.4 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only ; RO/SRO ; AO/RO/SRO Time Critical: Yes No Level of Difficulty: 4 Reference(s): 0ERP01-ZV-IN01, Emergency Classification, Rev 10 0ERP01-ZV-IN07, Offsite Protective Action Recommendations, Rev 17 0ERP01-ZV-SH01, Shift Manger, Rev 31 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes Critical Steps (*) 2 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 8 of 9
Student Handout INITIAL CONDITIONS Due to degrading plant conditions a General Emergency has just been declared in Unit 1.
Emergency Plan requirements with the exception of Protective Action Recommendations (PARs) are in progress or have been delegated to other individuals.
INITIATING CUE You are the Emergency Director in the Control Room and, due to rapidly degrading conditions associated with fission product barriers, you have just declared a General Emergency.
You are at Step 1.4 of 0ERP01-ZV-SH01, Shift Manager, Checklist 4, General Emergency Checklist.
You are to determine the PARs for the State/County, including downwind Zones and Sectors, in accordance with 0ERP01-ZV-IN07, Offsite Protective Action Recommendations.
Additional Information:
- A radiological release is NOT in progress.
- Current Weather conditions are:
Wind - Blowing from 120° at 12 mph.
Temperature - 88°F Precipitation - None
- NO conditions exist that would hinder an evacuation.
THIS JPM IS TIME CRITICAL.
WRITE ANSWER BELOW:
Page 9 of 9
0ERP01-ZV-IN07 Rev. 17 Page 12 of 19 Offsite Protective Action Recommendations Addendum 2 Protective Action Recommendation Decision Flowchart Page 1 of 5 ENTRY REQUIREMENTS: General Emergency AND a radiological release is NOT in progress OR a PAR Expansion is required.
General Emergency Declared PAR Flowchart Path (a) Rapidly YES progressing severe Continue accident (FG1 EAL) assessment and the ED is in the maintain PAR Control Room?
NO NO SIP Zone 1 and downwind zones 2 - 5 (b) Do YES miles. All others Monitor and Prepare. Refer to Impediments Impediments to addendum 3 for evacuated cleared?
Evacuation Exist?
zones & affected downwind sectors.
YES NO EVACUATE Zone 1 (c) EVACUATE and downwind zones Zone 1 and SIP 10 miles. All others downwind zones 2 - 5 Monitor and Prepare miles. All others YES (c) GE Refer to addendum 3 Monitor and Prepare. Conditions for evacuated zones Refer to addendum 3 remain?
& affected downwind for evacuated zones &
sectors. affected downwind NO KEY Continue Assessment (d)
(e) (f) Expand PAR only to areas where PAGs could be exceeded
0ERP01-ZV-IN07 Rev. 17 Page 17 of 19 Offsite Protective Action Recommendations Addendum 3 Evacuate Zones and Affected Downwind Sectors Page 1 of 1 AFFECTED ZONES: Determine Protective Response Zones and Affected Downwind Sectors to enter on 0ERP01-ZV-IN02, Form 1, Offsite Notification Message EVACUATE DOWNWIND EVACUATE DOWNWIND WIND ZONES 2 MILES; SIP ZONES 5 MILES; SIP EVACUATE DOWNWIND AFFECTED DOWNWIND ZONES 2 - 5 DOWNWIND ZONES 5 - 10 ZONES 10 MILES DIRECTION DOWNWIND MILES MILES FROM IS SECTORS BETWEEN EVACUATE SIP EVACUATE SIP EVACUATE ZONE ZONE(S) ZONE(S) ZONE(S) ZONE(S) 355º to 5º H,J,K 1 None 1,4 8,9 1,4,8,9 6º to 16º H,J,K,L 1 None 1,4 8,9 1,4,8,9 Use these columns 17º to 28º J,K,L 1 withNone 1,4 wind direction 8,9 1,4,8,9 29º to 39º J,K,L,M 1 4 to determine 1,4 PAR 8,9 1,4,8,9 40º to 50º K,L,M 1 4 1,4 8,9 1,4,8,9 51º to 61º K,L,M,N 1 4,5 1,4,5 8,9,10 1,4,5,8,9,10 62º to 73º L,M,N 1 4,5 1,4,5 9,10 1,4,5,9,10 74º to 84º Wind Direction 120 L,M,N,P 1 4,5 1,4,5 9,10 1,4,5,9,10 Degrees 85º to 95º M,N,P 1 4,5 1,4,5 9,10 1,4,5,9,10 96º to 106º M,N,P,Q 1 4,5 1,4,5 9,10,11 1,4,5,9,10,11 107º to 118º N,P,Q 1 5 1,5 9,10,11 1,5,9,10,11 119º to 129º N,P,Q,R 1 5 1,5 9,10,11 1,5,9,10,11 130º to 140º P,Q,R 1 5 1,5 10,11 1,5,10,11 141º to 151º P,Q,R,A 1 2,5 1,2,5 10,11 1,2,5,10,11 152º to 163º Q,R,A 1 2,5 1,2,5 10,11 1,2,5,10,11 164º to 174º Q,R,A,B 1 2,5 1,2,5 6,10,11 1,2,5,6,10,11 175º to 185º R,A,B 1 2 1,2 6,11 1,2,6,11 186º to 196º R,A,B,C 1 2 1,2 6,11 1,2,6,11 197º to 208º A,B,C 1 2 1,2 6,11 1,2,6,11 209º to 219º A,B,C,D 1 2 1,2 6,11 1,2,6,11 220º to 230º B,C,D 1 2 1,2 6 1,2,6 231º to 241º B,C,D,E 1 2,3 1,2,3 6,7 1,2,3,6,7 242º to 253º C,D,E 1 2,3 1,2,3 6,7 1,2,3,6,7 KEY 254º to 264º C,D,E,F 1 2,3 1,2,3 6,7 1,2,3,6,7 265º to 275º D,E,F 1 2,3 1,2,3 6,7 1,2,3,6,7 276º to 286º D,E,F,G 1 2,3 1,2,3 6,7 1,2,3,6,7 287º to 298º E,F,G 1 3 1,3 7 1,3,7 299º to 309º E,F,G,H 1 3 1,3 7,8 1,3,7,8 310º to 320º F,G,H 1 3 1,3 7,8 1,3,7,8 321º to 331º F,G,H,J 1 3 1,3 7,8 1,3,7,8 332º to 343º G,H,J 1 None 1 8 1,8 344º to 354º G,H,J,K 1 None 1,4 8,9 1,4,8,9
Rev. 0 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 09-25-17 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 21 NRC Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U Safety System / JPM Title Type Code*
Function
- a. (S1) Place H2 Monitoring in Service KA: 028 A4.03 (3.1/3.3) D,L,S 5
- b. (S2) Start a CCW Pump KA: 008 A4.01 (3.3/3.1) D,S 8
- c. (S3) Isolate SI Accumulators KA: 006 A4.02 (4.0/3.8) A,D,EN,L,S 3
- f. (S6) Lower CVCS Charging and Letdown Flow KA: 004 A4.06 N,S 2 (3.6/3.1)
- g. (S7) Respond to a FHB Rad Monitor Alarm KA: 072 A3.01 A,D,EN.S 7 (2.9/3.1)
- h. (S8) Place Excess Letdown in Service KA: 004 A4.05 (3.6/3.1) A,N,S 1 In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i. (P1) Locally Re-Align Critical Motor Operated Valves during a D,E,L,R 2 loss of all AC power. KA: G2.1.20 (4.6/4.6)
- j. (P2) Startup the GWPS following PMT KA: 071 A2.02 (3.3/3.6) A,D,P,R 9
- k. (P3) Place a 1E Battery Charger in Service KA: 063 A3.01 A,D 6 (2.7/3.1)
- All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all 5 SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO/SRO-I/SRO-U (A)lternate Path 4-6 / 4-6 / 2-3 (C)ontrol Room (D)irect from Bank 9/ 8/4 (E)mergency or abnormal in-plant 1/ 1/1 (EN) gineered Safety Features 1/ 1 / 1 (control room system)
(L)ow-Power / Shutdown 1/ 1/1 (N)ew or (M)odified from bank including 1(A) 2/ 2/1 (P)revious 2 exams 3/ 3 / 2 (randomly selected)
(R)CA 1/ 1/1 (S)imulator Page 1 of 5
Rev. 0 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 09-25-17 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 21 NRC Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U Safety System / JPM Title Type Code*
Function a.
- b. (S2) Start a CCW Pump KA: 008 A4.01 (3.3/3.1) D,S 8
- c. (S3) Isolate SI Accumulators KA: 006 A4.02 (4.0/3.8) A,D,EN,L,S 3
- f. (S6) Lower CVCS Charging and Letdown Flow KA: 004 A4.06 N,S 2 (3.6/3.1)
- g. (S7) Respond to a FHB Rad Monitor Alarm KA: 072 A3.01 A,D,EN.S 7 (2.9/3.1)
- h. (S8) Place Excess Letdown in Service KA: 004 A4.05 (3.6/3.1) A,N,S 1 In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i. (P1) Locally Re-Align Critical Motor Operated Valves during a D,E,L,R 2 loss of all AC power. KA: G2.1.20 (4.6/4.6)
- j. (P2) Startup the GWPS following PMT KA: 071 A2.02 (3.3/3.6) A,D,P,R 9
- k. (P3) Place a 1E Battery Charger in Service KA: 063 A3.01 A,D 6 (2.7/3.1)
- All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all 5 SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO/SRO-I/SRO-U (A)lternate Path 4-6 / 4-6 / 2-3 (C)ontrol Room (D)irect from Bank 9/ 8/4 (E)mergency or abnormal in-plant 1/ 1/1 (EN) gineered Safety Features 1/ 1 / 1 (control room system)
(L)ow-Power / Shutdown 1/ 1/1 (N)ew or (M)odified from bank including 1(A) 2/ 2/1 (P)revious 2 exams 3/ 3 / 2 (randomly selected)
(R)CA 1/ 1/1 (S)imulator Page 2 of 5
Rev. 0 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 09-25-17 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 21 NRC Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U Safety System / JPM Title Type Code*
Function a.
b.
c.
f.
- g. (S7) Respond to a FHB Rad Monitor Alarm KA: 072 A3.01 A,D,EN.S 7 (2.9/3.1)
- h. (S8) Place Excess Letdown in Service KA: 004 A4.05 (3.6/3.1) A,N,S 1 In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i. (P1) Locally Re-Align Critical Motor Operated Valves during a D,E,L,R 2 loss of all AC power. KA: G2.1.20 (4.6/4.6)
- j. (P2) Startup the GWPS following PMT KA: 071 A2.02 (3.3/3.6) A,D,P,R 9 k.
- All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all 5 SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO/SRO-I/SRO-U (A)lternate Path 4-6 / 4-6 / 2-3 (C)ontrol Room (D)irect from Bank 9/ 8/4 (E)mergency or abnormal in-plant 1/ 1/1 (EN) gineered Safety Features 1/ 1 / 1 (control room system)
(L)ow-Power / Shutdown 1/ 1/1 (N)ew or (M)odified from bank including 1(A) 2/ 2/1 (P)revious 2 exams 3/ 3 / 2 (randomly selected)
(R)CA 1/ 1/1 (S)imulator Page 3 of 5
Rev. 0 STP LOT-21 NRC Systems JPM Description Control Room Systems JPMs (S1) Place Containment H2 Monitoring in Service Demonstrate the ability to align the Containment H2 Monitoring System in order to monitor H2 concentration in accordance with Addendum 1 of 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant.
(S2) Start CCW Pump 1C Demonstrate the ability to start a 2nd CCW Pump and monitor system flow and pressure in accordance with 0POP02-CC-0001, Component Cooling Water.
(S3) Isolate SI Accumulators Demonstrate the ability to isolate SI Accumulators from the RCS by closing the discharge isolation valve and/or depressurizing the accumulator in accordance with 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant. This is an Alternate Path JPM.
(S4) Transfer 4.16KV Bus from EDG to Offsite Power Demonstrate the ability to control the Emergency Diesel Generators to transfer power to the Standby 13.8KV Bus in accordance with 0POP02-DG-0001, Emergency Diesel Generator 11(21).
(S5) Transfer MFW from LPFRV to MFRV Demonstrate the ability to control Steam Generator levels when aligning Main Feedwater flow from the Low Power Feedwater Regulation Valve to the Main Feedwater Regulation Valve in accordance with 0POP03-ZG-0005, Plant Startup to 100%.
(S6) Lower CVCS Charging and Letdown Flow Demonstrate the ability to control CVCS charging and letdown flow while changing letdown flow through the letdown orifices in accordance with 0POP02-CV-0004, Chemical and Volume Control Subsystem.
(S7) Respond to FHB Radiation Monitor Alarm Demonstrate the ability to properly align and control FHB HVAC after a high radiation actuation in accordance with 0POP04-RA-0001, Radiation Monitoring System Alarm Response. This is an Alternate Path JPM.
(S8) Place Excess Letdown in Service Demonstrate the ability to align and control Excess Letdown when it is determined that Normal Letdown is isolated at the Containment Penetration in accordance with 0POP04-CV-0004, Loss of Normal Letdown. This is an Alternate Path JPM.
NOTE: All Control Room JPMs will be performed dynamically in the Simulator. The following JPMs will can be performed in pairs; S1 & S3 together, S2 & S7 together, S4 & S8 together and S5 & S6 together.
Page 4 of 5
Rev. 0 STP LOT-21 NRC Systems JPM Description In Plant Systems JPMs (P1) Locally Re-Align Critical Motor Operated Valves during a loss of all AC power Demonstrate the ability to locate and then align Charging Pump suction sources and RCP seal return flow path in accordance with 0POP05-EO-EC00, Loss of All AC Power.
(P2) Startup of GWPS following PMT Demonstrate the ability to place a N2 purge on the GWPS prior to system startup in accordance with 0POP02-WG-0001, Gaseous Waste Processing System Operations.
This is an Alternate Path JPM.
(P3) Place a 1E Battery Charger in service Demonstrate the ability to operate and monitor Class 1E Battery Chargers in accordance with 0POP02-EE-0001, ESF (Class1E) DC Distribution System. This is an Alternate Path JPM.
Page 5 of 5
STPNOC Job Performance Measure PLACE CONTAINMENT H2 MONITORING SYSTEM IN SERVICE JPM Number: LOT 21 NRC S1 Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC S1 - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on the LOT 21 NRC exam.
Page 2 of 9
NRC S1 - rev 0 SIMULATOR SETUP INSTRUCTIONS NOTE: The following IC setup may be modified depending on JPMs that may be performed at the same time with this one.
IC Setup
- 1. Set up an IC that has a LBLOCA and work the IC to the step in 0POP05-EO-EO10 where the H2 Monitors are placed in service.
- 2. Ensure Radio volume for both stations are set to a reasonable level.
- 3. Ensure the PA buttons on the communications consoles are taped to help eliminate usage.
NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently. {Delete this NOTE if not applicable.}
- 4. Reset the simulator to IC 191 and verify the following:
- Step counter position annunciator light is out on CP-005
- Red light at the end of CP-010 is out
- 5. Check and clean the following procedures (JPM specific):
- 0POP05-EO-EO10 and Addendum 1
- 6. FROM THE BOOTH, place simulator in run and quickly silence/acknowledge/reset alarms then place the simulator in Freeze again.
- NOTE: It is OK to leave the simulator in run if the IC is stable.
- 7. When the student and the examiners are ready to proceed, place the simulator in RUN.
- No further action will be needed as the malfunction is on a conditional trigger.
Booth Instructor Actions
- 1. None Page 3 of 9
NRC S1 - rev 0 INITIAL CONDITIONS A Large Break LOCA has occurred. The Control Room Crew has completed 0POP05-EO-EO00, Reactor Trip or Safety Injection, and transitioned to 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant. All steps of 0POP05-EO-EO10 have been completed up to Step 12.
INITIATING CUE The Unit Supervisor directs you to check containment hydrogen concentration per Step 12 of 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant, and continue with procedure.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
The Operator places the H2 Monitors in service during a LBLOCA.
Page 4 of 9
NRC S1 - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE RCB H2 concentration on QDPS QUAL PAMS display should read XXXXb or LO.
- 1 Check Containment H2 Determines that Containment ___ ___ ___
concentration - greater than or H2 Concentration on QDPS equal to zero. QUAL PAMS display is not greater than or equal to zero (Step 12) and transitions to Addendum 1 (per step 12 RNO)
NOTE SI was reset at Step 4 of 0POP05-EO-EO10 2 Reset SI Resets SI by depressing the ___ ___ ___
Train A, B, and C RESET (Addendum 1, Step 1) pushbuttons on CP001 OR verifies SI has been reset.
NOTE.
Phase A was reset at Step 6 of 0POP05-EO-EO10 3 Reset Containment Isolation Resets Containment Isolation ___ ___ ___
Phase A Phase A by depressing the Train A, B, and C RESET (Addendum 1, Step 2) pushbuttons on CP002 OR verifies Containment Isolation Phase A has been reset.
- 4 Open H2 sample OCIVs for Opens H2 sample OCIVs for ___ ___ ___
each train each train by placing handswitches to OPEN.
(Addendum 1, Step 3) o Train A handswitch is FV-4101/4127 o Train B handswitch is FV-4104/4133 Page 5 of 9
NRC S1 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number 5 Place CNTMT H2 SAMPLE Places or Checks the sample ___ ___ ___
SELECT for each train to the select switches:
desired position. o Train A to FV-4100 (Addendum 1, Step 4) o Train B to FV-4103 Cue:
If asked, inform operator it is desired to sample the dome area.
- 6 Open selected CNTMT H2 Opens CNMTM H2 SAMPLE ___ ___ ___
SAMPLE valve for each train. valves for each train by placing handswitches to OPEN.
(Addendum 1, Step 5) o Train A handswitch is FV-4100 o Train B handswitch is FV-4103
- 7 Open H2 sample ICIVs for each Opens H2 sample INL/DISCH ___ ___ ___
train. ICIVs for each train by placing handswitches to OPEN.
(Addendum 1, Step 6) o Train A handswitch is FV-4135/4128 o Train B handswitch is FV-4136/4134
- 8 Place mode select switch to Places H2 monitors in operation ___ ___ ___
OPERATE for each train. by placing their respective mode select switch to (Addendum 1, Step 7)
OPERATE.
o Train A handswitch is AE-4102 o Train B handswitch is AE-4105 Page 6 of 9
NRC S1 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number 9 Verify H2 reading on each train o Calls up QDPS DETAIL ___ ___ ___
greater than or equal to zero DATA MENU PAGE 7.
after 1 minute of operation o Checks that H2 on QPDS (QDPS DETAIL DATA MENU QUAL PAMS display is PAGE 7). greater than or equal to (Addendum 1, Step 8) zero.
CUE This JPM is completed JPM Stop Time:
Page 7 of 9
NRC S1 - rev 0 JPM
SUMMARY
Operators Name: Job
Title:
Title:
PLACE CONTAINMENT H2 MONITORING SYSTEM IN SERVICE JPM Number: NRC S1 Revision Number: 0 Task Number and
Title:
96200, Respond to a loss of reactor coolant involving a break size in which Reactor Coolant System pressure drops below High Head Safety Injection Pump shutoff head.
K/A Number and Importance: 028 A4.03 3.1/3.3 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only RO/SRO AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant, Rev 23 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes Critical Steps (*) 1, 4, 6, 7 & 8 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 8 of 9
Student Handout INITIAL CONDITIONS A Large Break LOCA has occurred. The Control Room Crew has completed 0POP05-EO-EO00, Reactor Trip or Safety Injection, and transitioned to 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant. All steps of 0POP05-EO-EO10 have been completed up to Step 12.
INITIATING CUE The Unit Supervisor directs you to check containment hydrogen concentration per Step 12 of 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant, and continue with procedure.
Page 9 of 9
STPNOC Job Performance Measure START CCW TRAIN JPM Number: LOT 21 NRC S2 Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC S2 - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on the LOT 21 NRC exam.
Page 2 of 11
NRC S2 - rev 0 SIMULATOR SETUP INSTRUCTIONS NOTE: The following IC setup may be modified depending on JPMs that may be performed at the same time with this one.
IC Setup
- 2. Ensure Radio volume for both stations are set to a reasonable level.
- 3. Ensure the PA buttons on the communications consoles are taped to help eliminate usage.
NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently. {Delete this NOTE if not applicable.}
- 4. Reset the simulator to IC 192 and verify the following:
- Step counter position annunciator light is out on CP-005
- Red light at the end of CP-010 is out
- 5. Check and clean the following procedures (JPM specific):
- 0POP02-CC-0001, Component Cooling Water
- 6. FROM THE BOOTH, place simulator in run and quickly silence/acknowledge/reset alarms then place the simulator in Freeze again.
- NOTE: It is OK to leave the simulator in run if the IC is stable.
- 7. When the student and the examiners are ready to proceed, place the simulator in RUN.
- No further action will be needed as the malfunction is on a conditional trigger.
Booth Instructor Actions
- 1. None Page 3 of 11
NRC S2 - rev 0 INITIAL CONDITIONS Maintenance has completed work on Component Cooling Water (CCW) Pump 1C motor and would like a post maintenance run.
INITIATING CUE You are directed to start Component Cooling Water (CCW) Train 1C in accordance with Section 10.0 of 0POP02-CC-0001, Component Cooling Water.
- CCW Train C has been filled and vented Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
The Operator starts Component Cooling Water Pump 1C.
Page 4 of 11
NRC S2 - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number 1 Review Notes and Precautions Review procedure Notes and ___ ___ ___
Precautions applicable to this (Section 4.0) evolution.
2 ENSURE CCW train to be Verifies CCW train C is filled ___ ___ ___
started has been filled and and vented (given as part of the vented. Initiating Cue)
(Step 10.1)
Cue:
If the operator seeks to determine that CCW Train B has been filled and vented, inform him/her that it is filled and vented.
3 ENSURE only one "RAD Verifies the following: ___ ___ ___
MONITOR" valve for RT-8040 o Train A valve FV-4524 is is open from a running CCW open train.
o Train B valve FV-4525 is (Step 10.2) closed o Train C valve FV-4526 is closed 4 ENSURE CCW Pump Verifies "PUMP 1C(2C)/RM ___ ___ ___
Supplementary Cooler control 067F SUPP CLR 11C(21C) switch in AUTO for CCW HM-VAH003" handswitch is in pump to be started. AUTO.
(Step 10.3) 5 ENSURE ECW pump running, Verifies ECW Pump 1C is in ___ ___ ___
per 0POP02-EW-0001, service.
Essential Cooling Water Operation, as applicable that is associated with CCW pump to be started.
(Step 10.4)
Page 5 of 11
NRC S2 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE When all mode switches are in OFF, alarm CCW STBY TRN NOT SELECTED will annunciate.
6 ENSURE CCW/ECW mode Places CCW/ECW mode ___ ___ ___
selector switches for all trains in selector switches for Trains A OFF. and C in OFF (Train B is already in OFF).
for CCW Train to be placed in service.
(Step 10.6)
NOTE The operator may want to make a plant announcement prior to starting the pump. DO NOT ALLOW A PLANT ANNOUNCEMENT TO BE MADE (the PA buttons on the communications console have been taped over to prevent this).
- 8 START desired "COMP CLG Starts CCW Pump 1C ___ ___ ___
WTR PUMP".
(Step 10.7)
Cue:
o If the operator acts to contact a plant operator to check out the pump before start, inform him/her that the pump is ready for a start.
o If the operator asks the plant operator if the pump had a satisfactory start, inform him/her that the pump is running satisfactory.
Page 6 of 11
NRC S2 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Steps 10.8 and 10.9 are not applicable.
9 ENSURE the valves associated Ensures the following valves ___ ___ ___
with CCW pump 1C are OPEN. open:
(Step 10.10) o "CCW SPLY HDR ISOL MOV-0312" o "CCW RET HDR ISOL MOV-0192" o "SUPPLY ISOL MOV-0771" o "RET ISOL MOV-0775" 10 OBSERVE CCW header Checks CCW header pressure ___ ___ ___
pressure on each running train greater than 80 psig on CCW and verify greater than 80 psig. trains A and C (Steps 10.11 and 10.12) 11 OBSERVE CCW header flow Checks flow on A and C CCW ___ ___ ___
on each running train and verify trains is 7500-15000 gpm between 7500 and 15000 gpm.
(Steps 10.13 - 10.15) 12 ENSURE the Supplementary Ensures the Supplementary ___ ___ ___
Cooler is running for the Cooler (067F) is running for associated CCW pump that was CCW pump 1C started.
(Step 10.16)
Page 7 of 11
NRC S2 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number 13 IF it is desired to have a CCW Places the CCW/ECW TRAIN ___ ___ ___
train in standby mode of B MODE SEL switch in the operation AND CCW pressure STANDBY position and flow are within limits specified in previous steps, THEN PLACE one non-running CCW pump mode selector switch in STANDBY.
(Step 10.17)
Cue:
If the operator seeks information on which CCW/ECW Train Mode Selector Switch to place in STANDBY, inform him/her to place B Train in STANDBY NOTE The final position of the CCW/ECW Train Mode Selector Switches should be with one train in RUN, one train in STANDBY, and one train in OFF 14 ENSURE CCW/ECW mode o Places one of the following ___ ___ ___
selector switch for running CCW switches to the RUN pump(s) in "OFF" or "RUN". position:
(Step 10.18)
- CCW/ECW TRAIN A Cue: MODE SEL If the operator seeks
- CCW/ECW TRAIN C information on which MODE SEL CCW/ECW Train Mode Selector o Leaves one of the following Switch to place in RUN and switches in the OFF which to leave in OFF, inform position:
him/her to place C Train in RUN
- CCW/ECW TRAIN A MODE SEL
- CCW/ECW TRAIN B MODE SEL Page 8 of 11
NRC S2 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number 15 MAINTAIN CCW System Verifies that CCW System ___ ___ ___
temperature°F and less than or temperature is between 60° and equal to 105°F by regulating 105°F.
CCW HX Bypass and Outlet valves, as necessary, per Section 11.0.
(Step 10.19)
CUE This JPM is complete.
JPM Stop Time:
Page 9 of 11
NRC S2 - rev 0 JPM
SUMMARY
Operators Name: Job
Title:
Title:
START CCW TRAIN JPM Number: NRC S2 Revision Number: ##
Task Number and
Title:
4950, Start a CCW Train K/A Number and Importance: 008 A4.01 3.3/3.1 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only RO/SRO AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0POP02-CC-0001, Component Cooling Water, Rev 50 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes Critical Steps (*) 7 & 8 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 10 of 11
Student Handout INITIAL CONDITIONS Maintenance has completed work on Component Cooling Water (CCW) Pump 1C motor and would like a post maintenance run.
INITIATING CUE You are directed to start Component Cooling Water (CCW) Train 1C in accordance with Section 10.0 of 0POP02-CC-0001, Component Cooling Water.
- CCW Train C has been filled and vented Page 11 of 11
STPNOC Job Performance Measure ISOLATE SI ACCUMULATORS JPM Number: LOT 21 NRC S3 Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC S3 - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on the LOT 21 NRC exam.
Page 2 of 8
NRC S3 - rev 0 SIMULATOR SETUP INSTRUCTIONS NOTE: The following IC setup may be modified depending on JPMs that may be performed at the same time with this one.
IC Setup
- 2. Have ES13 complete
- 3. Ensure Hot leg temps less than 435°F
- 4. Insert malfunction to keep Train A Accumulator Isolation Valve open.
- 2. Ensure Radio volume for both stations are set to a reasonable level.
- 3. Ensure the PA buttons on the communications consoles are taped to help eliminate usage.
NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently. {Delete this NOTE if not applicable.}
- 4. Reset the simulator to IC 191 and verify the following:
- Step counter position annunciator light is out on CP-005
- Red light at the end of CP-010 is out
- 5. Check and clean the following procedures (JPM specific):
- 6. FROM THE BOOTH, place simulator in run and quickly silence/acknowledge/reset alarms then place the simulator in Freeze again.
- NOTE: It is OK to leave the simulator in run if the IC is stable.
- 7. When the student and the examiners are ready to proceed, place the simulator in RUN.
- No further action will be needed as the malfunction is on a conditional trigger.
Booth Instructor Actions
- 1. None Page 3 of 8
NRC S3 - rev 0 INITIAL CONDITIONS A Large Break LOCA has occurred. The crew was performing 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant, when they had to transfer to 0POP05-EO-ES13, Transfer to Cold Leg Recirculation. The Shift Crew is completing the remaining steps of 0POP05-EO-ES13, Transfer to Cold Leg Recirculation.
INITIATING CUE The Unit Supervisor directs you to continue in 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant, at step 23, CHECK If SI Accumulators Should Be Isolated.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
The Operator isolates SI Accumulator 1A by depressurizing the accumulator (alternate path) and isolates SI Accumulators 1B and 1C by closing the discharge valve.
Page 4 of 8
NRC S3 - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number 1 Check if SI Accumulators The operator determines that at ___ ___ ___
should be isolated: least two RCS hot leg temperatures are less than o At least two RCS hot leg temperatures LESS THAN 420°F.
420°F (Step 23.a)
- 2 ENERGIZE all SI Accumulator The operator energizes each SI ___ ___ ___
Isolation Valves. Accumulator Isolation Valve by momentarily placing each (Step 23.b) valve's "ACC PWR LOCKOUT" switch to the "POWER ON" position:
o Train "A" o Train "B" o Train "C" NOTE Train A valve does not close Alternate path starts here
- 3 CLOSE all SI Accumulator The operator closes each "ACC ___ ___ ___
Isolation Valves. DISCH ISOL" valve by using its control room handswitch.
(Step 23.c) o Train "A" (does not close) o Train "B" o Train "C" 4 VENT any unisolated The operator verifies that "N2 ___ ___ ___
accumulators: SPLY OCIV FV-3983" is closed.
o CLOSE N2 supply. "N2 SPLY OCIV FV-3983" (Step 23 RNO c.1)
Page 5 of 8
NRC S3 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number
- 5 OPEN unisolated ("A") The operator opens "ACC ___ ___ ___
accumulator vent isolation 1A(2A) N2 SPLY/VENT PV-valve. 3930".
(Step 23 RNO c.2)
- 6 OPEN accumulator vent to The operator depressurizes "A" ___ ___ ___
containment: SI Accumulator by opening either of the following valves:
o "HDR VENT HV-0899" o HDR VENT HV-0899 OR o "HDR VENT HCV-0900" OR o HDR VENT HCV-0900 NOTE: When properly aligned, Accumulator A pressure will lower but very slowly. (about 1 psig/minute) If the student looks at an ICS trend they will be able to see the lowering of pressure better than on the board meter.
7 DEENERGIZE all SI The operator de-energizes each ___ ___ ___
Accumulator Isolation Valves. SI Accumulator Isolation Valve by momentarily placing each (Step 23.d)
"ACC POWER LOCKOUT" switch to the "POWER OFF" position:
o Train "A" o Train "B" o Train "C" CUE This JPM is complete JPM Stop Time:
Page 6 of 8
NRC S3 - rev 0 JPM
SUMMARY
Operators Name: Job
Title:
Title:
ISOLATE SI ACCUMULATORS JPM Number: NRC S3 Revision Number: 0 Task Number and
Title:
30200, Vent Accumulator Pressure K/A Number and Importance: 006 A4.02 4.0/3.8 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only RO/SRO AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant, Rev 22 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 10 minutes Actual Time Used: minutes Critical Steps (*) 2, 3, 5 & 6 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 7 of 8
Student Handout INITIAL CONDITIONS A Large Break LOCA has occurred. The crew was performing 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant, when they had to transfer to 0POP05-EO-ES13, Transfer to Cold Leg Recirculation. The Shift Crew is completing the remaining steps of 0POP05-EO-ES13, Transfer to Cold Leg Recirculation.
INITIATING CUE The Unit Supervisor directs you to continue in 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant, at step 23, CHECK If SI Accumulators Should Be Isolated.
Page 8 of 8
STPNOC Job Performance Measure TRANSFER 4.16KV BUS FROM EMERGENCY DIESEL GENERATOR TO OFFSITE SUPPLY JPM Number: LOT 21 NRC S4 Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC S4 - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on LOT 21 NRC exam.
Page 2 of 14
NRC S4 - rev 0 SIMULATOR SETUP INSTRUCTIONS NOTE: The following IC setup may be modified depending on JPMs that may be performed at the same time with this one.
IC Setup
- 1. Different power level ICs can be used. Open the feeder breaker from 13.8KV Standby Bus 1F to Train A 4.16KV ESF Bus (E1A/1 SPLY BKR).
- 2. Let the Train A Sequencer time out. (Ess. Chiller 12A is running.)
- 3. Reset Sequencer.
- 4. Place EAB and Control Room HVAC systems back to normal.
- 5. Ensure RCFCs on B & C Trains running with A secured and re-align RCB Chill Water to the RCFC coils.
- 2. Ensure Radio volume for both stations are set to a reasonable level.
- 3. Ensure the PA buttons on the communications consoles are taped to help eliminate usage.
NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently. {Delete this NOTE if not applicable.}
- 4. Reset the simulator to IC 196 and verify the following:
- Step counter position annunciator light is out on CP-005
- Red light at the end of CP-010 is out
- Ensure the breaker control sw. target flags are set as follows:
o STBY Bus 1F to E1A Transformer (CP-010 - RED with breaker closed) o E1A Normal Supply Breaker (CP-003 - RED with breaker open) o DG #11 Output Breaker (CP-003 - GREEN with breaker closed)
- 5. Check and clean the following procedures (JPM specific):
- 6. FROM THE BOOTH, place simulator in run and quickly silence/acknowledge/reset alarms then place the simulator in Freeze again.
- NOTE: It is OK to leave the simulator in run if the IC is stable.
- 7. When the student and the examiners are ready to proceed, place the simulator in RUN.
Booth Instructor Actions
- 1. In browser remote functions under STBY DG Control Systems, have the engine start mode switch ready to be placed in IDLE when requested by the student. (GD-45, 1 = IDLE & 2 =
RATED)
Page 3 of 14
NRC S4 - rev 0 INITIAL CONDITIONS A fault occurred on 4.16KV ESF BUS E1A supply breaker. (E1A/1 SPLY BKR). Emergency Diesel Generator 11 started and loaded normally. The Crew responded using 0POP04-AE-0001, First Response To Loss Of Any Or All 13.8 KV Or 4.16 KV Bus.
Diesel Generator 11 has now been running for 2 hrs. The A ESF BUS supply breaker (E1A/1 SPLY BKR) has been repaired and re-installed.
INITIATING CUE The Unit Supervisor directs you to restore off-site power from Standby Bus 1F to 4.16KV ESF Bus A in accordance with 0POP02-DG-0001, Emergency Diesel Generator 11(21), Section 9.0, Transferring 4.16 KV Bus E1A(E2A) from DG 11(21) to Offsite Supply.
- The requirement for having a second operator available during the synchronization task has been waived by the Shift Manager because the remainder of the crew is involved in an Off Normal event.
- Per the Shift Manager, the time requirements in the unloading rate table of 0POP02-DG-0001 are waived.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
The Operator electrically aligns 4.16KV ESF Bus A to Standby Bus 1F.
Page 4 of 14
NRC S4 - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Throughout this JPM, IF operator asks the local operator to investigate the cause of a DG11 TROUBLE alarm, report alarm is due to Standpipe Level Off-Normal.
1 Review the Notes and The operator reviews the Notes ___ ___ ___
Precautions section of 0POP02- and Precautions section of the DG-0001, Emergency Diesel procedure and goes to Section Generator 11(21). 9.0, Transferring 4.16 KV Bus (Section 4.0) E1A (E2A) from Diesel Generator 11(21) to Offsite Supply.
2 VERIFY Diesel Generator 11 is The operator checks to ensure ___ ___ ___
the only source of power to ESF that Diesel Generator 11 is the Bus E1A. only source of power to ESF (Step 9.1) Bus E1A.
Page 5 of 14
NRC S4 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number 3 IF it is desired to transfer from The operator ENSURES each ___ ___ ___
Diesel Generator 11 to Standby of the following is in the proper Bus 1F THEN ENSURE the position on CP-010:
following: o "EMER BUS 1L TO XFMR o "EMER BUS 1L TO XFMR E1A BKR SW-EMER" E1A BKR SW-EMER" OPEN OPEN o "EMER BUS 1L TO XFMR o "EMER BUS 1L TO XFMR E1A DISC SW-EMER" E1A DISC SW-EMER" OPEN OPEN o "STBY BUS 1F TO XFMR o "STBY BUS 1F TO XFMR E1A DISC SW-NORM" E1A DISC SW-NORM" CLOSED CLOSED o "STBY BUS 1F TO XFMR o "STBY BUS 1F TO XFMR E1A BKR SW-NORM" E1A BKR SW-NORM" CLOSED CLOSED (Step 9.2)
Cue:
If the operator asks for clarification, as the Unit Supervisor, tell him/her that the bus is to be energized from STBY Bus 1F.
NOTE Procedure step 9.3, Transferring ESF DG to Emergency Bus 1L, is N/A.
4 ENSURE any activated The operator directs a Plant ___ ___ ___
protective relays reset (ZLP101) Operator to locally reset any protective relay that may have (Step 9.4) tripped.
Cue:
As Plant Operator, report that all protective relays are reset.
NOTE Computer Indication of sequencer reset is on ICS display 9713 Page 6 of 14
NRC S4 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number 5 ENSURE the Train A Load The operator depresses the ___ ___ ___
Sequencer is reset. white sequencer RESET pushbutton on CP-003 for ESF (Step 9.5)
Diesel Generator 11 or verifies NOTE: The student can verify sequencer is reset using ICS.
the Load Sequencer is reset by checking ICS display 9713.
The sequencer was reset during performance of 0POP04-AE-0001.
6 ENSURE the following loads The operator will ensure the ___ ___ ___
are secured: loads are secured.
o HHSI PUMP 1A (CP001) o LHSI PUMP1A (CP001) o RHR PUMP 1A (CP001) o CSS PUMP 1A (CP001) o RCFC 11A (CP002) o RCFC 12A (CP002)
(Step 9.6)
The operator may place STAR RINGS on the handswitches for these loads.
Page 7 of 14
NRC S4 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number 7 Momentarily DEPRESS the The operator depresses the ___ ___ ___
Diesel Generator 11 "RESET" white RESET pushbutton on pushbutton to ensure the non- CP-003 for Diesel Generator emergency trip logic reset. 11.
(Step 9.7)
Cue:
o If asked, the Unit Supervisor reports that NO non-emergency trip signal was received while the diesel was running in the Emergency Mode.
o If asked, the Unit Supervisor reports that Non-Class 1E 125 VDC control power was NOT lost while the diesel was operating in the Emergency Mode.
8 Verify the MASTER TRIP The operator directs a Plant ___ ___ ___
CIRCUIT RESET light Operator to verify the MASTER illuminated. TRIP CIRCUIT RESET light on (Step 9.8) ZLP102 is illuminated.
Cue:
As Plant Operator, report the Master Trip Circuit Reset light is ON.
Page 8 of 14
NRC S4 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE When DG 11 is supplying the ESF Bus, the operator must anticipate a decrease in DG Frequency and Voltage when releasing from emergency. A procedural note allows the operator to make adjustments to Frequency and Voltage if needed to maintain required parameters and keep from getting another undervoltage actuation.
- 9 WHEN desired THEN The operator depresses the ___ ___ ___
RELEASE DG 11 from white "RELEASE" (from Emergency Mode by Emergency Mode) pushbutton momentarily depressing the DG on CP-003 for ESF Diesel 11 RELEASE pushbutton. Generator 11 and makes (CP003) adjustments to Frequency and Voltage to maintain about 60 (Step 9.9)
HZ and 4.16KV on the bus.
This CT is satisfied if the operator does not allow another undervoltage actuation.
10 Verify the Emergency Mode The operator directs a Plant ___ ___ ___
white light is extinguished. Operator to verify the white Emergency Mode light on (Step 9.10)
ZLP-102 is extinguished.
Cue:
As Plant Operator, report the white Emergency Mode light on ZLP-102 is extinguished.
NOTE Examiner needs to signal the booth operator to place DG 11 ENGINE START MODE switch to the IDLE position in the next step.
Page 9 of 14
NRC S4 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number 11 Ensure the ENGINE START The operator directs a Plant ___ ___ ___
MODE switch is in the IDLE Operator to verify the ENGINE position. START MODE switch on ZLP-102 is in the IDLE position.
(Step 9.11)
Cue:
After signaling the booth operator, then, as a Plant Operator, report the ENGINE START MODE switch is in the IDLE position.
12 ENSURE the GOV MODE SEL The operator ensures the GOV ___ ___ ___
switch in the PARALLEL MODE SEL switch in the position. PARALLEL position.
(Step 9.12)
Page 10 of 14
NRC S4 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number
- 13 Parallel the diesel with off-site The operator performs the ___ ___ ___
power. following for the diesel being shutdown at CP003:
(Steps 9.13 - 9.16)
Cue: *A. PLACES the SYNCHROSCOPE for If asked about a second Diesel Generator 11 in the Operator, the requirement for ON position.
having a second operator available during the *B. ADJUSTS engine speed to synchronization task has been cause the synchroscope to waived by the Shift Manager move slowly in the SLOW because the remainder of the direction using the GOV crew is involved in an Off switch.
Normal event. (per Initiating *C. ADJUSTS DG 11 Output Cue) voltage using DG 11 VOLT ADJ until DG 11 output voltage is equal to XFRMR E1A VOLTS D. MONITORS the DG 11 Voltage Meter for all three phases of voltage.
- E. CLOSES ESF Bus E1A Normal SPLY BKR E1A/1 when the synchroscope is approximately in the 12:05 position.
F. PLACES the SYNCHROSCOPE switch in the OFF position.
- - critical portion Page 11 of 14
NRC S4 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Per the Initiating Cue, the Shift Manager has waived the time requirements in the unloading rate table of 0POP02-DG-0001.
- 14 Unload the diesel. The operator performs ALL of ___ ___ ___
the following for the diesel to be (Steps 9.17 - 9.19) shut down:
o Using the Diesel Generator 11 GOV switch, DECREASES diesel generator load to approximately 100 KW.
o Using the Diesel Generator 11 VOLT ADJ switch, MAINTAIN diesel generator reactive load between 0 and 500 KVAR.
o Opens the Diesel Generator 11 DG OUTP BKR.
CUE This JPM is complete JPM Stop Time:
Page 12 of 14
NRC S4 - rev 0 JPM
SUMMARY
Operators Name: Job
Title:
Title:
TRANSFER 4.16KV BUS FROM EMERGENCY DIESEL GENERATOR TO OFFSITE SUPPLY JPM Number: NRC S4 Revision Number: 0 Task Number and
Title:
44650, Transfer an Emergency Bus from the Emergency Diesel Generator to offsite power.
K/A Number and Importance: 064 A4.01 4.0/4.3 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only RO/SRO AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0POP02-DG-0001, Emergency Diesel Generator 11(21), Rev 68 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes Critical Steps (*) 9, 13 & 14 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 13 of 14
Student Handout INITIAL CONDITIONS A fault occurred on 4.16KV ESF BUS E1A supply breaker. (E1A/1 SPLY BKR). Emergency Diesel Generator 11 started and loaded normally. The Crew responded using 0POP04-AE-0001, First Response To Loss Of Any Or All 13.8 KV Or 4.16 KV Bus.
Diesel Generator 11 has now been running for 2 hrs. The A ESF BUS supply breaker (E1A/1 SPLY BKR) has been repaired and re-installed.
INITIATING CUE The Unit Supervisor directs you to restore off-site power from Standby Bus 1F to 4.16KV ESF Bus A in accordance with 0POP02-DG-0001, Emergency Diesel Generator 11(21), Section 9.0, Transferring 4.16 KV Bus E1A(E2A) from DG 11(21) to Offsite Supply.
- The requirement for having a second operator available during the synchronization task has been waived by the Shift Manager because the remainder of the crew is involved in an Off Normal event.
- Per the Shift Manager, the time requirements in the unloading rate table of 0POP02-DG-0001 are waived.
Page 14 of 14
STPNOC Job Performance Measure TRANSFER MFW FROM LPFRV TO MFRV JPM Number: LOT 21 NRC S5 Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC S5 - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on LOT21 NRC exam.
Page 2 of 9
NRC S5 - rev 0 SIMULATOR SETUP INSTRUCTIONS NOTE: The following IC setup may be modified depending on JPMs that may be performed at the same time with this one.
IC Setup
- 1. Restore to an IC with power at about 15 to 17 percent and the MFRVs in service on SGs A, B & D. Place SG 1C on the LPFR valve.
- 2. Ensure Radio volume for both stations are set to a reasonable level.
- 3. Ensure the PA buttons on the communications consoles are taped to help eliminate usage.
NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently. {Delete this NOTE if not applicable.}
- 4. Reset the simulator to IC 194 and verify the following:
- Step counter position annunciator light is out on CP-005
- Red light at the end of CP-010 is out
- 5. Check and clean the following procedures (JPM specific):
- 0POP03-ZG-0005, Plant Startup to 100%, including Addendum 11
- 6. FROM THE BOOTH, place simulator in run and quickly silence/acknowledge/reset alarms then place the simulator in Freeze again.
- NOTE: It is OK to leave the simulator in run if the IC is stable.
- 7. When the student and the examiners are ready to proceed, place the simulator in RUN.
- No further action will be needed as the malfunction is on a conditional trigger.
Booth Instructor Actions
- 1. None Page 3 of 9
NRC S5 - rev 0 INITIAL CONDITIONS A plant startup is in progress per 0POP03-ZG-0005, Plant Startup to 100%.
- Reactor power is at about 17% by Delta Ts.
- The turbine is on the grid and the SU SGFW Pump is in service.
INITIATING CUE The Unit Supervisor directs you to transfer steam generator water level control from the low power feedwater regulating valve to the main feedwater regulating valve for C Steam Generator in accordance with Addendum 11 of 0POP03-ZG-0005, Plant Startup to 100%.
A pre-job brief has already been performed.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
The Operator feeds SG 1C from the Main Feed Regulating valve in automatic.
Page 4 of 9
NRC S5 - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number 1 Ensure the SG 1C narrow range Verifies that SG 1C narrow ___ ___ ___
level is stable between 65% and range level indication is stable 75%. between 65% and 75%.
(Addendum 11, Step 2.1.1) 2 ENSURE SG 1C main Verifies that SG 1C NORM ___ ___ ___
feedwater regulating valve is in FCV-0553" Main Feed manual and fully closed. Regulating valve is in manual (Addendum 11, Step 2.1.2) and closed.
Page 5 of 9
NRC S5 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE The manual isolation valve is already open.
3 Ensure the SG 1C main Dispatches a Plant Operator to ___ ___ ___
feedwater regulating valve open 1-FW-0093, SG 1C isolation valve is open. Feedwater Reg. Valve Isolation Valve.
(Addendum 11, Step 2.1.3)
Cue:
Plant Operator Reports that 1-FW-0093 is open.
NOTE Recording flow is optional. Other methods such as grease mark on the control board flow instrument may be used (as approved by the Unit Supervisor/Shift Manager).
Flowrate should be approximately .55 - .75 (M lbm/hr)
- 4 Place SG 1C low power o
- Depresses MANUAL ___ ___ ___
feedwater regulating valve in pushbutton on SG 1C LOW manual and NOTE SG PWR FV-7153".
feedwater flow. o Notes SG 1C Flowrate by (Addendum 11, Steps 2.1.4 and recording or marking flow.
2.1.5)
- - critical portion
to main feedwater regulating flowrate approximately constant valve. while transferring control as follows:
(Addendum 11, Steps 2.1.6 -
2.1.9) o Throttles OPEN NORM Cue: FCV-0553" until feed flow increase is noticed.
If permission is requested to use 2 handed operations, as o Throttles CLOSED LOW the Unit Supervisor, give PWR FV-7153" until feed permission to use 2 handed flow returns to initial value.
operation. o Repeats these steps until LOW PWR FV-7153" is approximately 8% to 10%
open.
Page 6 of 9
NRC S5 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number
- 6 Complete transfer from low o *Places NORM FCV-0553" ___ ___ ___
power to main feedwater in AUTO regulating valves. THEN (Addendum 11, Steps 2.1.10 o Slowly CLOSES LOW PWR and 2.1.11) FV-7153", ensuring SG Narrow Range Level is within the normal control band (65%-75%).
CUE This JPM is complete JPM Stop Time:
Page 7 of 9
NRC S5 - rev 0 JPM
SUMMARY
Operators Name: Job
Title:
Title:
TRANSFER MFW FROM LPFRV TO MFRV JPM Number: NRC S5 Revision Number: 0 Task Number and
Title:
21050, Place Main Feed Reg. Valves in Auto K/A Number and Importance: 035 A4.01 3.7/3.6 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only RO/SRO AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0POP03-ZG-0005, Plant Startup to 100%, Rev 105 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes Critical Steps (*) 4, 5 & 6 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 8 of 9
Student Handout INITIAL CONDITIONS A plant startup is in progress per 0POP03-ZG-0005, Plant Startup to 100%.
- Reactor power is at about 17% by Delta Ts.
- The turbine is on the grid and the SU SGFW Pump is in service.
INITIATING CUE The Unit Supervisor directs you to transfer steam generator water level control from the low power feedwater regulating valve to the main feedwater regulating valve for C Steam Generator in accordance with Addendum 11 of 0POP03-ZG-0005, Plant Startup to 100%.
A pre-job brief has already been performed.
Page 9 of 9
STPNOC Job Performance Measure LOWER CVCS CHARGING AND LETDOWN FLOW JPM Number: LOT 21 NRC S6 Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC S6 - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on LOT 21 NRC exam.
Page 2 of 11
NRC S6 - rev 0 SIMULATOR SETUP INSTRUCTIONS NOTE: The following IC setup may be modified depending on JPMs that may be performed at the same time with this one.
IC Setup
- 1. Restore to an IC with normal letdown and charging in service.
- 2. Place an additional CCP and letdown orifice in service and allow flows/levels to stabilize.
- 2. Ensure Radio volume for both stations are set to a reasonable level.
- 3. Ensure the PA buttons on the communications consoles are taped to help eliminate usage.
NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently. {Delete this NOTE if not applicable.}
- 4. Reset the simulator to IC 194 and verify the following:
- Step counter position annunciator light is out on CP-005
- Red light at the end of CP-010 is out
- 5. Check and clean the following procedures (JPM specific):
- 0POP04-CV-0004, Chemical and Volume Control System Subsystem
- 6. FROM THE BOOTH, place simulator in run and quickly silence/acknowledge/reset alarms then place the simulator in Freeze again.
- NOTE: It is OK to leave the simulator in run if the IC is stable.
- 7. When the student and the examiners are ready to proceed, place the simulator in RUN.
- No further action will be needed as the malfunction is on a conditional trigger.
Booth Instructor Actions
- 1. None Page 3 of 11
NRC S6 - rev 0 INITIAL CONDITIONS Charging and Letdown are maximized at the request of Chemistry to clean up the Reactor Coolant System (RCS). Chemistry now reports that RCS conditions are back to normal and current RCS Boron concentration is 950 ppm.
INITIATING CUE The Unit Supervisor directs you to:
First - Secure CVCS letdown flow going through CV-FV-0013,85-100 GPM ORIFICE ISOL VLV.
AND Second - Secure Charging Pump 1A.
In accordance with 0POP02-CV-0004, Chemical and Volume Control System Subsystem.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
The Operator removes the 85-100 GPM letdown orifice and secures CCP 1A from service.
Page 4 of 11
NRC S6 - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number 1 Review Notes and Precautions Reviews applicable notes and ___ ___ ___
precautions associated with the (section 4.0) evolution.
NOTE Throughout this JPM the operator may have to adjust PZR level.
CUE:
The Unit Supervisor has given permission to take manual control of PZR LC-LK-0665 and/or Charging FC-FK-0205 to control PZR level.
2 NOTIFY Health Physics of Notifies Health Physics of ___ ___ ___
pending changes in the letdown upcoming changes in the or charging flow paths to ensure letdown flow path.
they can survey the area that has changed.
(Step 10.1)
Cue:
As Health Physics, acknowledge the information.
3 ENSURE demineralizers Goes to section 7.0 ___ ___ ___
bypassed per Section 7.0.
(Step 10.2)
- 4 ENSURE DIVERT TCV-0143 Places DIVERT TCV-0143 in ___ ___ ___
in the VCT position to bypass the VCT position.
the CVCS Demineralizers.
(Step 7.2)
NOTE: Step 7.1 notifies HP which was performed in step 10.1.
Page 5 of 11
NRC S6 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number 5 NOTIFY Chemistry that the Notifies Chemistry and then ___ ___ ___
CVCS Demineralizers are returns to section 10.0.
bypassed.
(Step 7.3)
Cue:
As Chemistry, acknowledge the information.
- 6 PLACE PRESS CONT PCV- Places PRESS CONT PCV- ___ ___ ___
0135 in MAN and ADJUST to 0135 in MAN and adjusts obtain a letdown pressure of letdown pressure to 400 psig as indicated on approximately 400 psig.
OUTLET PRESS PI-0135.
(Steps 10.3 and 10.4)
orifice isolation valve. ORFICE ISOL VLV.
(Step 10.5)
- 8 WHEN the letdown orifice Adjusts PRESS CONT PCV- ___ ___ ___
isolation valve is full closed, 0135 to obtain a letdown THEN ADJUST PRESS CONT pressure between 350 psig and PCV-0135 to obtain a letdown 380 psig and places in AUTO pressure between 350 psig and 380 psig and PLACE in AUTO.
(Steps 10.6 and 10.7) 9 ENSURE demineralizers in Goes to section 7.0 ___ ___ ___
service per Section 7.0, as desired.
(Step 10.8)
Cue:
If asked, as the Unit Supervisor, direct the operator to place the demineralizers in service if allowed by procedure.
Page 6 of 11
NRC S6 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number 10 ENSURE the CVCS Demins Determines that all CVCS ___ ___ ___
meet the following: Demin conditions are met and continues to Step 7.4.2.
- Previously flushed
- Isolated less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
NOTE: RCS Boron concentration per initiating cue was 950 ppm at the start.
Cue:
When asked, Chemistry reports current Boron concentration is now 935 ppm.
- 11 PLACE DIVERT TCV-0143 in Places DIVERT TCV-0143 in ___ ___ ___
the DEMIN position. the DEMIN position.
(Step 7.4.3) 12 NOTIFY Chemistry that the Notifies Chemistry and then ___ ___ ___
CVCS Demineralizers are in Goes to section 6.0 to secure service. CCP 1A.
(Step 7.4.4)
Cue:
As Chemistry, acknowledge the information.
Page 7 of 11
NRC S6 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number 13 NOTIFY Health Physics of Notifies Health Physics of ___ ___ ___
pending changes in the letdown upcoming changes in the or charging flow paths to ensure charging flow path.
they can survey the area that has changed.
(Step 6.1)
Cue:
As Health Physics, acknowledge the information.
- 14 ENSURE open the Centrifugal Opens CCP 1A Recirc FCV- ___ ___ ___
Charging Pump miniflow valve 0201 for pump to be secured:
- CCP 1A(2A) RECIRC FCV-0201 (Step 6.2)
- 15 ENSURE Centrifugal Charging Closes CCP 1A DISCH ISOL ___ ___ ___
Pump discharge valve for pump MOV-8377A to be secured is CLOSED:
- CCP 1A(2A) DISCH ISOL MOV-8377A (Step 6.3)
- 16 STOP Centrifugal Charging Stops CCP 1A. ___ ___ ___
Pump by momentarily turning its handswitch to the STOP position:
- CCP 1A(2A)
(Step 6.4)
Page 8 of 11
NRC S6 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number
- 17 POSITION discharge valve on Opens CCP 1A DISCH ISOL ___ ___ ___
idle Centrifugal Charging Pump MOV-8377A as required for plant conditions:
- CCP 1A(2A) DISCH ISOL MOV-8377A (Step 6.5)
Cue:
As the Unit Supervisor, direct the operator to open the idle charging pump discharge valve.
18 IF desired, THEN STOP the Stops CCP 1A Supplemental ___ ___ ___
associated Charging Pump Cooling Fan 11A.
cooling fan:
- PUMP 1A(2A) SUPP CLR 11A(21A)
(Step 6.6)
Cue:
As the Unit Supervisor, direct the operator to secure the CCP 1A supplemental cooling fan 11A.
CUE This JPM is complete JPM Stop Time:
Page 9 of 11
NRC S6 - rev 0 JPM
SUMMARY
Operators Name: Job
Title:
Title:
LOWER CVCS CHARGING AND LETDOWN FLOW JPM Number: NRC S6 Revision Number: 0 Task Number and
Title:
502717, Operate alternate charging and letdown flowpaths K/A Number and Importance: 004 A4.06 3.6/3.1 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only RO/SRO AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0POP02-CV-0004, Chemical and Volume Control System Subsystem, Rev 87 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 25 minutes Actual Time Used: minutes Critical Steps (*) 4, 6 - 8, 11, 14 - 17 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 10 of 11
Student Handout INITIAL CONDITIONS Charging and Letdown are maximized at the request of Chemistry to clean up the Reactor Coolant System (RCS). Chemistry now reports that RCS conditions are back to normal and current RCS Boron concentration is 950 ppm.
INITIATING CUE The Unit Supervisor directs you to:
First - Secure CVCS letdown flow going through CV-FV-0013,85-100 GPM ORIFICE ISOL VLV.
AND Second - Secure Charging Pump 1A.
In accordance with 0POP02-CV-0004, Chemical and Volume Control System Subsystem.
Page 11 of 11
STPNOC Job Performance Measure RESPOND TO AN FHB RAD MONITOR ALARM JPM Number: LOT 21 NRC S7 Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC S7 - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on LOT 21 NRC exam.
Page 2 of 10
NRC S7 - rev 0 SIMULATOR SETUP INSTRUCTIONS NOTE: The following IC setup may be modified depending on JPMs that may be performed at the same time with this one.
IC Setup
- 1. RT-8035 is in Alarm (RM11) - Set to .003 in simulator.
- 2. RT-8036 is in Alert (RM11) - Set to .001 in simulator.
INSTRUCTOR NOTE: The desired condition for the RM-11 is to have the audible alarm acknowledged, RT-8035 icon flashing red and RT-8036 icon flashing yellow. If it is not flashing, thats OK as well. Sometimes the Storepoint may not reset to a flashing alarm icon. Check no other RM-11 alarms are in.
- 2. Ensure Radio volume for both stations are set to a reasonable level.
- 3. Ensure the PA buttons on the communications consoles are taped to help eliminate usage.
NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently. {Delete this NOTE if not applicable.}
- 4. Reset the simulator to IC 192 and verify the following:
- Step counter position annunciator light is out on CP-005
- Red light at the end of CP-010 is out
- 5. Check and clean the following procedures (JPM specific):
- 0POP04-RA-0001, Radiation Monitoring System Alarm Response
- 6. FROM THE BOOTH, place simulator in run and quickly silence/acknowledge/reset alarms then place the simulator in Freeze again.
- NOTE: It is OK to leave the simulator in run if the IC is stable.
- 7. When the student and the examiners are ready to proceed, place the simulator in RUN.
- No further action will be needed as the malfunction is on a conditional trigger.
Booth Instructor Actions
- 1. None Page 3 of 10
NRC S7 - rev 0 INITIAL CONDITIONS The Unit is operating at 100% power. Fuel movement is being performed in the Spent Fuel Pool in anticipation for receipt of new fuel.
INITIATING CUE An alarm has come in on Rad Monitor Panel RM-11. The Unit Supervisor directs you to investigate the Rad Monitor that is in an alarm condition in accordance with 0POP04-RA-0001, Radiation Monitoring System Alarm Response, and take appropriate action.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
After determining that FHB HVAC is not in the emergency mode of operation, the Operator manually aligns FHB HVAC to the emergency mode.
Page 4 of 10
NRC S7 - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Per a procedure NOTE, the initial actions before going to Addendum 10 are considered skill of the craft and may be performed before entering the procedure.
- 1 Investigates the alarm on the o *Determines RT-8035 is in ___ ___ ___
RM-11. Alarm (Red) and RT-8036 is in Alert (Yellow)
(Steps 1-4)
Cue: o Calls up a Trend and Status display for RT-8035 If the student starts to evaluate E-Plan classification, inform the o Goes to Addendum 10 of student that another SRO will the procedure evaluate E-Plan status. * - critical portion If asked, another operator is evaluating the need to enter 0POP04-FH-0001, Fuel Handling Accident.
- 2 Check High alarm exists on RT- Determines a High Alarm exists ___ ___ ___
8035 or RT-8036. on RT-8035 (Addendum 10, Step 1)
NOTE The operator will have to evaluate the FHB HVAC status on Control Room Panel CP-022 to determine the system is not operating in Emergency Mode.
Alternate path starts here.
Emergency Mode. operating in Emergency Mode and goes to procedure (Addendum 10, Step 2)
Addendum 28.
Page 5 of 10
NRC S7 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Only one Filter Train is to be placed into service per the procedure.
Note which train is being placed in service. This information will be used to evaluate subsequent JPM steps.
- 4 Open the Inlet Isolation Damper Opens: ___ ___ ___
for one FHB Exhaust Filter o FV-9549 (Train A)
Train to be placed in service.
OR (Addendum 28, Step 1) o FV-9549A (Train B)
Cue:
o If asked which filter train to place in service, as the Unit Supervisor, indicate that you have no preference.
o Various alarms will come in and clear on the panel where the applicant is performing procedure steps.
If the operator wishes to consult Annunciator Response procedures, inform him/her that can be done for any alarms still present after all steps have been completed.
5 Ensure two FHB Main Exhaust Ensures two FHB Main Exhaust ___ ___ ___
Fans are running. Fans are running.
(Addendum 28, Step 2)
- 6 Start two FHB Exhaust Booster Starts two of the following FHB ___ ___ ___
Fans. Exhaust Booster Fans (Addendum 28, Step 3) o EXH BOOSTER FAN 11A o EXH BOOSTER FAN 11B o EXH BOOSTER FAN 11C Page 6 of 10
NRC S7 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE The controller placed in Manual and Closed should NOT be the train whose Inlet Isolation Damper was opened in JPM step 4.
- 7 Place the FHB Exhaust Flow Places the controller in ___ ___ ___
Controller in Manual and Manual using the Manual/Auto manually close outlet damper button and depresses the for the Exhaust Filter train NOT CLOSE button until the exhaust being placed in service. air damper is closed for the Exhaust Train NOT being (Addendum 28, Step 4) placed in service.
o Train A - HV-9507 o Train B - HV-9507A NOTE The FHB Exhaust Filter Train Outlet Damper should be in the same Train as JPM step 4 and the opposite train selected in JPM step 7.
- 8 Place the FHB Exhaust Filter Places the FHB Exhaust Filter ___ ___ ___
Train Outlet Damper in the Train Outlet Damper control in AUTO after MOD position for the MOD position and then the Exhaust Filter Train being returns the switch to AUTO on placed in service. the Exhaust Train to be placed in service:
(Addendum 28, Step 5) o Train A - HV-9507 o Train B - HV-9507A
- 9 Close both FHB Exhaust Filter Closes FHB Exhaust Filter ___ ___ ___
Bypass Dampers. Bypass Dampers:
(Addendum 28, Step 6) o FV-9549D o FV-9549C Page 7 of 10
NRC S7 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE This should be the same train placed in service in JPM steps 4 and 8.
10 Ensure the FHB Exhaust Air Determines the FHB Exhaust ___ ___ ___
Flow Controller for the train Air Flow Controller on the train placed in service modulating to that is in service is controlling maintain flow between 26,100 26,100 - 31,900 cfm.
and 31,900 CFM. o Train A - HV-9507 (Addendum 28, Step 7) o Train B - HV-9507A
- 11 Open a Relief Damper. Opens Relief Damper: ___ ___ ___
(Addendum 28, Step 8) o FV-9500 OR o FV-9500A NOTE These fans should have automatically stopped when a relief damper was opened in JPM step 11 12 Verify all FHB Main Supply Verifies all FHB Main Supply ___ ___ ___
Fans stopped. Fans are stopped (Addendum 28, Step 9) 13 Ensure all FHB Main Supply Ensures FHB Main Supply Fan ___ ___ ___
Fan Inlet Isolation Dampers Inlet Isolation Dampers are closed. closed:
(Addendum 28, Step 10) o FV-9510/9510A o FV-9520/9520A o FV-9530/9530A CUE This JPM is complete JPM Stop Time:
Page 8 of 10
NRC S7 - rev 0 JPM
SUMMARY
Operators Name: Job
Title:
Title:
RESPOND TO AN FHB RAD MONITOR ALARM JPM Number: NRC S7 Revision Number: 0 Task Number and
Title:
86200, Respond to Radiation Monitoring System Alarms K/A Number and Importance: 072 A3.01 2.9/3.1 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only RO/SRO AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0POP04-RA-0001, Radiation Monitoring System Alarm Response, Rev 36 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 10 minutes Actual Time Used: minutes Critical Steps (*) 1-4, 6-9 & 11 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 9 of 10
Student Handout INITIAL CONDITIONS The Unit is operating at 100% power. Fuel movement is being performed in the Spent Fuel Pool in anticipation for receipt of new fuel.
INITIATING CUE An alarm has come in on Rad Monitor Panel RM-11. The Unit Supervisor directs you to investigate the Rad Monitor that is in an alarm condition in accordance with 0POP04-RA-0001, Radiation Monitoring System Alarm Response, and take appropriate action.
Page 10 of 10
STPNOC Job Performance Measure PLACE EXCESS LETDOWN IN SERVICE JPM Number: LOT 21 NRC S8 Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC S8 - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on LOT 21 NRC exam.
Page 2 of 13
NRC S8 - rev 0 SIMULATOR SETUP INSTRUCTIONS NOTE: The following IC setup may be modified depending on JPMs that may be performed at the same time with this one.
IC Setup
- 1. Restore to a 100% IC.
- 2. Insert the following to close CV-MOV-0024, Normal Letdown OCIV:
- BML048_X2LO = 1 delay = 0 ramp = 0 on = 0 off = 0
- ERFDADS_DIP_CVTD0024REV = 0 delay = 0 ramp = 0 on = 0 off = 0
- H_A4_A1_M9_1 = 185 delay = 20 ramp = 0 on = 0 off = 0
- H_A4_A1_M9_1 = 70.00401 cd H_A4_A1_DS17_1 = 1 delay = 0 ramp = 300 0 on = 0 off = 0
- LA04M8-B-4 = 2 delay = 47
- 3. Let the simulator run until PRT PRESS HI comes in and then FREEZE the simulator.
- 2. Ensure Radio volume for both stations are set to a reasonable level.
- 3. Ensure the PA buttons on the communications consoles are taped to help eliminate usage.
NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently. {Delete this NOTE if not applicable.}
- 4. Reset the simulator to IC 196 and verify the following:
- Step counter position annunciator light is out on CP-005
- Red light at the end of CP-010 is out
- 5. Check and clean the following procedures (JPM specific):
- 0POP04-CV-0004, Loss of Normal Letdown
- 6. FROM THE BOOTH, place simulator in run and quickly silence/acknowledge/reset alarms then place the simulator in Freeze again.
- NOTE: It is OK to leave the simulator in run if the IC is stable.
- 7. When the student and the examiners are ready to proceed, place the simulator in RUN.
- No further action will be needed as the malfunction is on a conditional trigger.
Booth Instructor Actions
- 1. When Examiner is ready insert BM_FV0011TVFAILSP = 0. This fails CV-FV-0011 closed.
Page 3 of 13
NRC S8 - rev 0 INITIAL CONDITIONS The Crew has responded to annunciators on CP-004. The annunciator response directed the Crew to implement 0POP04-CV-0004, Loss of Normal Letdown.
INITIATING CUE The Unit Supervisor directs you to perform 0POP04-CV-0004, Loss of Normal Letdown, starting at Step 1.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
After an RCS leak is determined in the CVCS normal letdown flow path, excess letdown is placed in service.
Page 4 of 13
NRC S8 - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number VERIFY Letdown Line Stop 1 Verifies CV-LCV-0465 and 0468 ___ ___ ___
Valves - OPEN are open.
- LETDN ISOL LCV-0465
- LETDN ISOL LCV-0468 (Step 1)
NOTE Alternate Path Starts Here.
VERIFY Letdown Containment
- 2 Determines that CV-MOV-0024 ___ ___ ___
Isolation Valves - OPEN is closed and performs RNO
- ICIV MOV-0023 actions.
- OCIV MOV-0024 (Step 2)
Page 5 of 13
NRC S8 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number PERFORM the following:
- 3 Performs a procedural isolation ___ ___ ___
- CLOSE LETDN ORIF HDR of Normal Letdown.
ISOL FV-0011.
- ENSURE CHG FLOW CONT FK-0205 in MAN and CLOSED.
- OPEN Centrifugal Charging Pump miniflow valve for operating pump:
- CCP 1A(2A) RECIRC FCV-0201
- CCP 1B(2B) RECIRC FCV-0202
- MAINTAIN RCP seal injection between 6 and 13 gpm using FLOW CONT HCV-0218.
- ENSURE all letdown orifice isolation valves are closed:
- 120-150 GPM ORIFICE ISOL VLV 1(2)-CV-FV-0012
- 85-100 GPM ORIFICE ISOL VLV 1(2)-CV-FV-0013
- 25-30 GPM ORIFICE ISOL VLV 1(2)-CV-MOV-0014
- CLOSE LETDN ISOL LCV-0465.
- CLOSE LETDN ISOL LCV-0468.
- GO TO Step 4.0.
(Step 2 RNO)
VERIFY Containment Isolation 4 Verifies Containment Isolation ___ ___ ___
Phase A - CLEAR Phase A has not actuated.
(Step 4)
Page 6 of 13
NRC S8 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number VERIFY Plant Computer Points
- 5 Determines CVTD0024 is NOT ___ ___ ___
CVCS LTDN AREA TEMP TRN normal and performs RNO
- NORM actions.
- CVTD0023
- CVTD0024 (Step 5)
Page 7 of 13
NRC S8 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number PERFORM the following:
6 Determines a letdown line leak ___ ___ ___
- CHECK the following occurred in RM 48, Letdown HX radiation monitors for rising Valve Room, and goes to trends or alarm conditions: Addendum 6, Securing Normal (RM-11) Letdown.
- RT-8015, MAB Ventilation The leak would have been
- DISPATCH an Operator and isolated while performing Step 2 HP to locate the source of the RNO.
letdown line break per Addendum 1, HELB Local Actions.
- IF a letdown line break is NOT found, THEN RESTORE normal letdown per Addendum 4, Placing Normal Letdown In Service.
- IF a break in the letdown line is found OR normal letdown can NOT be restored, THEN PERFORM the following:
- SECURE Normal Letdown per Addendum 6, Securing Normal Letdown.
- PLACE Excess Letdown in service per Addendum 5, Placing Excess Letdown In Service.
- GO TO Step 9.0.
(Step 5 RNO)
CUE:
Another RO will check trends on RT-8010A, 8010B & 8015 CUE:
The Plant Operator sent out with Addendum 1 Reports that Room 48, Letdown HX Valve Room has a large amount of water on the floor.
Page 8 of 13
NRC S8 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number 7 Perform Addendum 6 Performs Addendum 6, ___ ___ ___
Securing Normal Letdown, and NOTE:
the goes to Addendum 5, Addendum 6 has the same Placing Excess Letdown in steps as Step 2 RNO. Service.
CHECK CCW In Service To 8 Checks CCW is in service to the ___ ___ ___
The Excess Letdown Heat Excess Letdown Heat Exchanger.
Exchanger.
(Addendum 5 Step 1)
PLACE Excess Letdown
- 9 Places DIVERT FV-3123 In ___ ___ ___
DIVERT FV-3123 In The The RCDT Position.
RCDT Position (Addendum 5 Step 2)
CHECK EXCESS/NORMAL 10 Contacts a Plant Operator to ___ ___ ___
LETDN CROSS CONNECTION determine the position of CV-N1(2)CV-HS-0469 In The HS-0469, which is reported CLOSE closed.
(Addendum 5 Step 3)
CUE:
A Plant Operator reports that CV-HS-0469 is closed.
OPEN Excess Letdown Heat Opens Excess Letdown Heat
- 11 ___ ___ ___
Exchanger Isolation Valves Exchanger Isolation Valves ISOL MOV-0083 and ISOL MOV-0083 and ISOL ISOL MOV-0082 MOV-0082 (Addendum 5, Step 4 & 5)
Page 9 of 13
NRC S8 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number MAINTAIN Both Of The
- 12 Slowly Opens TEMP CONT ___ ___ ___
Following Parameters While HCV-0227 to maintain Flushing Excess Letdown Heat temperature and pressure Exchanger:
within band at the Excess
TEMP TI-0229 - LESS THAN 175F
- Excess Letdown HX OUTL PRESS PI-0228 - LESS THAN 145 psig Slowly OPEN Excess Letdown TEMP CONT HCV-0227 To Avoid Thermal Transients (Addendum 5, Step 6 and 7)
ADJUST Excess Letdown And
- 13 While adjusting TEMP CONT ___ ___ ___
Seal Injection Flows To HCV-0227, operator monitors Maintain PZR & RCDT level and RCDT
- Pressurizer level pressure.
- RCDT level (8 - 92%)
- RCDT pressure (< 6 psig)
(Addendum 5, Step 8)
FLUSH Excess Letdown To The Flushes Excess Letdown to the 14 ___ ___ ___
RCDT For At Least Six (6) RCDT for 6 minutes.
Minutes (Addendum 5, Step 9)
CUE:
If operator has stabilized parameters prior to the 6 minute flush ending then for time compression the examiner can tell the operator that 6 minutes has elapsed.
PERFORM The Following:
- 15 Places excess letdown ___ ___ ___
VCT position (Addendum 5, RNO 10)
Page 10 of 13
NRC S8 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Reactivity Control using CVCS with Excess Letdown in service is affected by the seal return line up.
DETERMINE IF Excess 16 The operator does NOT have ___ ___ ___
Letdown Will Be In Service: CVCS Seal Return realigned.
- GREATER THAN 24 HOURS OR
- Boration will be DESIRED (Addendum 5, RNO 11)
CUE:
Excess Letdown will NOT be in service for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a Boration is NOT desired.
CUE This JPM is complete JPM Stop Time:
Page 11 of 13
NRC S8 - rev 0 JPM
SUMMARY
Operators Name: Job
Title:
Title:
PLACE EXCESS LETDOWN IN SERVICE JPM Number: NRC S8 Revision Number: 0 Task Number and
Title:
48650, Place the excess letdown system in service K/A Number and Importance: 004 A4.05 3.6/3.1 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only RO/SRO AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0POP04-CV-0004, Loss of Normal Letdown, Rev 13 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes Critical Steps (*) 2, 3, 5, 9, 11-13, 15 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 12 of 13
Student Handout INITIAL CONDITIONS The Crew has responded to annunciators on CP-004. The annunciator response directed the Crew to implement 0POP04-CV-0004, Loss of Normal Letdown.
INITIATING CUE The Unit Supervisor directs you to perform 0POP04-CV-0004, Loss of Normal Letdown, starting at Step 1.
Page 13 of 13
STPNOC Job Performance Measure LOCALLY RE-ALIGN CRITICAL MOTOR OPERATED VALVES DURING A LOSS OF ALL AC POWER JPM Number: NRC P1 Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC P1 - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on LOT 21 NRC exam.
Page 2 of 9
NRC P1 - rev 0 SIMULATOR SETUP INSTRUCTIONS
- 1. This JPM is performed in the plant.
Page 3 of 9
NRC P1 - rev 0 INITIAL CONDITIONS A loss of all offsite power has occurred. All 4.16 KV ESF busses are de-energized. The Positive Displacement Charging Pump (PDP) has been started and is supplying seal injection.
INITIATING CUE You have been handed the procedure and the Unit Supervisor directs you to re-align the Charging Pump suction from the Volume Control Tank (VCT) to the Refueling Water Storage Tank (RWST) in accordance with Step 3.h and 3.i AND isolate RCP Seal Return in accordance with Step 4.c of 0POP05-EO-EC00, Loss of All AC Power.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
Suction flow path to the charging pumps is aligned from the RWST and the RCP seal return flow path is isolated.
Page 4 of 9
NRC P1 - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE This JPM assumes a loss of all AC power, however, the student may ask if power is removed from the motor operated valves due to past OE.
The as found position for this valve in the plant will be CLOSED.
CV-MOV-0112C is located on the 10 MAB Room 44.
- 1 Locate and OPEN 1(2)-CV- The operator locates and opens ___ ___ ___
MOV-0112C, CVCS the valve by performing the CHARGING PUMPS SUCTION following:
FROM RWST MOV o Simulates depressing the OPERATOR.
declutch lever (the declutch (Step 3.h) lever may be held down, but Cue: this is not required).
o Initial Position - CLOSED o Simulates rotating the (as found) handwheel in a counter clockwise direction.
o Final Position - OPEN o Continues simulating counter clockwise rotation of the handwheel until the valve is full open (the handwheel will stop when the valve is on its open seat).
Page 5 of 9
NRC P1 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE The as found position for these valves in the plant will be OPEN.
CV-MOV-0112B and CV-MOV-0113A are located on the 41 MAB Room 226.
- 2 CLOSE at least one of the VCT The operator locates and ___ ___ ___
outlet isolation valves. CLOSES either of the following:
(Step 3.i) o 1(2)-CV-MOV-0112B, CVCS VOLUME CONTROL TANK Cue:
OUTLET MOV OPERATOR o Initial Position - OPEN (as found, for either valve) o 1(2)-CV-MOV-0113A, CVCS VOLUME CONTROL TANK o Final Position - CLOSED OUTLET MOV OPERATOR By performing the following:
o Simulates depressing the declutch lever (the declutch lever may be held down, but this is not required).
o Simulates rotating the handwheel in a clockwise direction.
o Continues simulating clockwise rotation of the handwheel until the valve is full closed (the handwheel will stop when the valve is on its closed seat).
Page 6 of 9
NRC P1 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE The as found position for this valve in the plant will be OPEN.
CV-MOV-0079 is located on the 29 MAB Room 108C.
- 3 CLOSE the RCP seal return The operator locates and closes ___ ___ ___
OCIV. the valve by performing the following:
(Step 4.c) o Simulates depressing the Cue:
declutch lever (the declutch o Initial Position - OPEN (as lever may be held down, but found) this is not required).
o Final Position - CLOSED o Simulates rotating the handwheel in a clockwise direction.
o Continues simulating clockwise rotation of the handwheel until the valve is full closed (the handwheel will stop when the valve is on its closed seat).
CUE This JPM is complete JPM Stop Time:
Page 7 of 9
NRC P1 - rev 0 JPM
SUMMARY
Operators Name: Job
Title:
Title:
LOCALLY RE-ALIGN CRITICAL MOTOR OPERATED VALVES DURING A LOSS OF ALL AC POWER JPM Number: NRC P1 Revision Number: 0 Task Number and
Title:
82044, Respond to a Loss of All AC Power Condition K/A Number and Importance: 2.1.20 4.6/4.6 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only RO/SRO AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0POP05-EO-EC00, Loss of All AC Power, Rev 29 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes Critical Steps (*) 1, 2 & 3 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 8 of 9
Student Handout INITIAL CONDITIONS A loss of all offsite power has occurred. All 4.16 KV ESF busses are de-energized. The Positive Displacement Charging Pump (PDP) has been started and is supplying seal injection.
INITIATING CUE You have been handed the procedure and the Unit Supervisor directs you to re-align the Charging Pump suction from the Volume Control Tank (VCT) to the Refueling Water Storage Tank (RWST) in accordance with Step 3.h and 3.i AND isolate RCP Seal Return in accordance with Step 4.c of 0POP05-EO-EC00, Loss of All AC Power.
Page 9 of 9
STPNOC Job Performance Measure STARTUP OF GWPS FOLLOWING PMT JPM Number: NRC P2 Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC P2 - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on LOT 21 NRC exam.
Page 2 of 14
NRC P2 - rev 0 SIMULATOR SETUP INSTRUCTIONS
- 1. This JPM is performed in the plant.
Page 3 of 14
NRC P2 - rev 0 INITIAL CONDITIONS A one hour PMT was just completed on the GWPS system and it is time to return the system to normal.
INITIATING CUE You have been handed the procedure and the Unit Supervisor requests you to perform a system startup of the GWPS utilizing Section 7 of 0POP02-WG-0001, Gaseous Waste Processing System Operations. All applicable prerequisites have been completed.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
A nitrogen purge is performed on GWPS prior to completion of a system start of the GWPS System due to high O2 levels in the system.
Page 4 of 14
NRC P2 - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE DO NOT HAND OUT ATTACHMENT #1, PICTURE OF O2 MONITOR UNTIL STEP *6 OF JPM.
1 Review the Notes and Reviews the Notes and ___ ___ ___
Precautions. Precautions of 0POP02-WG-0001, Gaseous Waste (Sections 3.0 and 4.0)
Processing System Operations.
Cue:
If asked, inform the operator that all prerequisites have been satisfied as per the Initiating Cue.
NOTE 1(2)-WG-TI-4659 is located on ZLP-116 in the Rad Waste Control Room 41 MAB.
2 Verify Chiller Glycol Verifies Chiller Glycol ___ ___ ___
temperature less than or equal temperature is less than or to 35°F. equal to 35°F on "1(2)-WG-TI-4659 GWPS GLYCOL (Step 7.1)
CHILLER TANK Cue: TEMPERATURE ELEMENT".
Temperature indication on 1(2)-
WG-TI-4659 is 33°F.
Page 5 of 14
NRC P2 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number 3 Inform the Control Room that Informs the Control Room that ___ ___ ___
the inlet O2 monitor will be the inlet O2 monitor will be inoperable when the GWPS inoperable when the GWPS Inlet 1(2)-WG-FV-4657 and Inlet 1(2)-WG-FV-4657 and Outlet 1(2)-WG-FV-4671 Flow Outlet 1(2)-WG-FV-4671 Flow Valve Handswitches are placed Valve Handswitches are placed in the OPEN position and in the OPEN position and TRM requires TRM compensatory compensatory actions are actions. required.
(Step 7.2)
Cue:
As the Control Room, acknowledge that the inlet O2 monitor will be inoperable when the GWPS inlet and outlet flow valve handswitches are placed in the OPEN position and TRM compensatory actions will be taken.
Page 6 of 14
NRC P2 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Located on 41 MAB Radwaste Control Panel ZLP-116.
- 4 Place 1(2)-WG-FV-4671, Places 1(2)-WG-FV-4671, ___ ___ ___
GWPS Discharge Flow Valve GWPS Discharge Flow Valve control switch in OPEN. control switch in OPEN.
(Step 7.3)
Cue:
FV-4671 may already be open, however, use the following cue to simulate that the valve needs to be opened:
FV-4671 Handswitch:
o Initially - CLOSE (Green Light - LIT, Red Light -
OFF) o Finally - OPEN (Green Light - OFF, Red Light -
LIT)
- 5 Place 1(2)-WG-FV-4657, Places 1(2)-WG-FV-4657, ___ ___ ___
GWPS Inlet Header Valve GWPS Inlet Header Valve control switch in OPEN. control switch in OPEN.
(Step 7.4)
Cue:
FV-4657 may already be open, however, use the following cue to simulate that the valve needs to be opened:
FV-4657 Handswitch:
o Initially - CLOSE (Green Light - LIT, Red Light -
OFF) o Finally - OPEN (Green Light - OFF, Red Light -
LIT)
Page 7 of 14
NRC P2 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE 1(2)-WG-AI-4655 Oxygen Monitor is a Tech Spec related piece of equipment and has a hinged cover over the controls.
DO NOT ALLOW THE OPERATOR TO OPEN THE DOOR OF THE OXYGEN MONITOR.
To preclude having the operator open the cover and affect a piece of Tech Spec related equipment, Attachment 1, a picture of the Oxygen Monitor with the cover open, is provided on Page 10 of 15.
The HI scale on the O2 indicator is 0 to 25%. It is harder to read because the color of the scale is red instead of black and has started to fad. The picture provided with has the 0-25% scale enhanced.
DCP 08-18547-2 has been written to completely replace the O2 Monitor/Indicator because the system is obsolete.
than 1%, then start a nitrogen oxygen is greater than 1% and purge. that a nitrogen purge must be performed.
(Step 7.5)
Cue:
Hand out Attachment #1 -
Picture of O2 Monitor. The picture should have the necessary information to proceed with the JPM.
However, if the operator asks questions then the following cues can be given.
o If the operator uses Attachment 1 to determine Oxygen level, it has a black meter needle on 2.5 while in the MED position. (indicating 2.5% oxygen).
Cue continued on next page Page 8 of 14
NRC P2 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number o If the operator uses the meter on the actual Oxygen Monitor, inform the operator that the Range switch is in the MED position and the meter is reading about 0.5 (LO scale) or 2.5 (MED scale) by pointing at the meter.
o If the operator indicates that they would change the range switch to the LO position and asks what the Oxygen Monitor is reading while in this position, inform the operator that the meter is pegged high.
o If the operator indicates that they would change the range switch to the HI position and asks what the Oxygen Monitor is reading while in this position, inform the operator that the meter is reading about 0.1 (LO scale) or 0.5 (MED scale) by pointing at the meter.
o If operator contacts the Control Room informing them of the requirement to start a nitrogen purge, acknowledge that a nitrogen purge must be performed.
Page 9 of 14
NRC P2 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number ATTACHMENT 1 STUDENT HANDOUT Page 10 of 14
NRC P2 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Alternate path starts here.
7 Inform Main Control Room of Informs Main Control Room of ___ ___ ___
increased nitrogen usage increased nitrogen usage during nitrogen purge. during nitrogen purge.
(Step 7.5.1)
Cue:
As the control room, acknowledge that there will be an increased usage of nitrogen during the nitrogen purge.
NOTE The following cue can be given if asked:
WG-PI-4656 would be indicating about 0.8 to 1.0 psig if asked prior to heading out to line up N2.
NL-0116 is located on the 10 MAB Room 068K.
Valve is a 90° turn valve
- 8 Open 1(2)-NL-0116, Low Opens 1(2)-NL-0116, Low ___ ___ ___
Pressure Nitrogen to Gaseous Pressure Nitrogen to Gaseous Waste System Isolation Valve. Waste System Isolation Valve.
(Step 7.5.2)
Cue:
o Initially - CLOSED o Finally - OPEN Page 11 of 14
NRC P2 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Valve is located on MAB 10' in Room 068J.
Pressure Indicator is located on the 41' MAB on the Radwaste Control Panel ZLP-116.
The operator will require assistance from another operator to monitor pressure while nitrogen valve is throttled open.
- 9 Throttle open 1(2)-NL-0029, Slowly throttles open 1(2)-NL- ___ ___ ___
Low Pressure Nitrogen to 0029, LOW PRESSURE Gaseous Waste System NITROGEN TO GWPS Isolation Valve while ISOLATION VALVE, to maintain maintaining system pressure less than 2.5 psig as indicated less than 2.5 psig. on 1(2)WG-PI-4656, GLYCOL CHILLER TANK INLET (Steps 7.5.3 and 7.5.4)
HEADER PRESSURE Cue: INDICATOR.
o NL-0029:
- Initially - CLOSED
- Finally - THROTTLED OPEN o Tell the operator that another plant operator is at PI-4656 to monitor pressure.
o Throttling NL-0029 to about 45% to 50% will produce about 2 psig on PI-4656.
o As the operator monitoring pressure, report pressure gradually rising, at 0.4 psig increments, as the valve is throttled open. Final pressure on PI-4656 is 2.0 to 2.4 psig.
CUE This JPM is complete JPM Stop Time:
Page 12 of 14
NRC P2 - rev 0 JPM
SUMMARY
Operators Name: Job
Title:
Title:
STARTUP OF GWPS FOLLOWING PMT JPM Number: NRC P2 Revision Number: 0 Task Number and
Title:
NLO031200, Operate the Gaseous Waste Processing System K/A Number and Importance: 071 A2.02 3.3/3.6 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only RO/SRO AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0POP02-WG-0001, Gaseous Waste Processing System Operations, Rev 28 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 30 minutes Actual Time Used: minutes Critical Steps (*) 4, 5, 6, 8 & 9 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 13 of 14
Student Handout INITIAL CONDITIONS A one hour PMT was just completed on the GWPS system and it is time to return the system to normal.
INITIATING CUE You have been handed the procedure and the Unit Supervisor requests you to perform a system startup of the GWPS utilizing Section 7 of 0POP02-WG-0001, Gaseous Waste Processing System Operations. All applicable prerequisites have been completed.
Page 14 of 14
STPNOC Job Performance Measure PLACE A 1E BATTERY CHARGER IN SERVICE JPM Number: NRC P3 Revision Number: 0 Date: 09/25/2017 Developed By:
Instructor (Print/Sign) Date Approved By:
Training Supervisor (Print/Sign) Date Approved By:
Line Management (Print/Sign) Date
NRC P3 - rev 0 Revision Record (Summary)
Revision 0, Drafted JPM for use on LOT 21 NRC exam.
Page 2 of 12
NRC P3 - rev 0 SIMULATOR SETUP INSTRUCTIONS
- 1. This JPM is performed in the plant.
Page 3 of 12
NRC P3 - rev 0 INITIAL CONDITIONS The Unit is in Mode 1 at 100% power. Battery Charger E1B11(E2B11) - 1 is scheduled to be taken out of service for maintenance.
INITIATING CUE You have been given 0POP02-EE-0001, ESF (Class 1E) DC Distribution System, Section 7.2, Transfer of Train B Channel III Battery Chargers.
The Unit Supervisor has dispatched you to SWAP the Train B Channel III Battery Chargers by placing Battery Charger E1B11(E2B11) - 2 in service and securing Battery Charger E1B11(E2B11) - 1.
The procedure prerequisites and Addendum 1, Control Loop Alignment, have been completed.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
If Time Critical, estimated time is the Time Critical time.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
Task Standard:
The Battery Charger being placed in service is shut back down due to not being able to adjust Float Voltage to the desired voltage.
Page 4 of 12
NRC P3 - rev 0 JPM Start Time:
Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Notes/Precautions 4.7 through 4.20 (except 4.17, TS reference) apply to battery charger operation.
1 Review procedure Notes and The operator reviews applicable ___ ___ ___
Precautions Notes and Precautions contained in the procedure.
(Section 4.0)
NOTE This Addendum has been completed per the Initiating Cue.
2 Perform Addendum 1, Control- Addendum 1, Control-Loop ___ ___ ___
Loop Alignment Alignment has been completed (Step 7.2.1)
Cue:
If asked, inform the operator that this Addendum has been completed.
Page 5 of 12
NRC P3 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Location: 35 EAB, Room 213, south wall on both Battery Chargers upper panel face 3 Ensure the FLOAT/EQUALIZE Ensures the ___ ___ ___
toggle switch is in the FLOAT FLOAT/EQUALIZE toggle position for both battery switch is in the FLOAT chargers. position for Battery Chargers E1B11(E2B11) - 1 and (Step 7.2.2)
E1B11(E2B11) - 2.
Cue:
When asked, the following are the initial and final switch positions for both Battery Chargers:
INITIAL: FLOAT/EQUALIZE switch is in the FLOAT position.
FINAL: FLOAT/EQUALIZE switch is in the FLOAT position.
NOTE Location: 35 EAB, Switchgear Room.
4 Ensure the 480V AC supply Verifies breaker 125V DC ___ ___ ___
breaker closed for the battery BATT CHGR E1B11(E2B11)-2 charger being placed in service. at 480 V AC Motor Control Center E1B2 (E2B2) breaker (Step 7.2.3)
A6R is closed.
Cue:
INITIAL: Breaker Handle UP (ON position)
FINAL: Breaker Handle UP (ON position)
Page 6 of 12
NRC P3 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Location: On Charger E1B11(E2B11) - 2 lower panel face, right breaker
OUTPUT CB-2 breaker for the breaker on Battery Charger battery charger being placed in E1B11(E2B11) - 2.
service.
(Step 7.2.4)
Cue:
INITIAL: Breaker Handle DOWN FINAL: Breaker Handle UP NOTE Location: On Battery Charger E1B11(E2B11) - 2 lower panel face, left breaker NOTE: The DC Voltage meter is a digital meter. Giving the numerical value of voltage without giving the units (VDC) would be appropriate.
INPUT CB-1 breaker for the breaker on Battery Charger battery charger being placed in E1B11(E2B11) - 2.
service (Step 7.2.5)
Cue:
INITIAL: Breaker Handle DOWN FINAL: Breaker Handle UP If asked:
o After Breaker Closure:
- Battery Charger Current settles at 0 amps.
(Analog Meter)
- DC Voltage settles at 126 VDC. (Digital Meter)
Page 7 of 12
NRC P3 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Alternate Path Starts Here.
Location: On Battery Charger E1B11-1 (E2B11-1) upper panel left side.
Operator will use the FLOAT potentiometer knob to adjust DC volts to within the required limit.
Step 7.2.6.1 is N/A because the Battery Chargers are NOT being SWAPPED due to low DC volts on the inservice Battery Charger.
- 7 Adjust float voltage for the Attempts to adjust ___ ___ ___
battery charger being placed in E1B11(E2B11) - 2 Battery service: (Step 7.2.6) Charger VDC to between 128.5 and 131.6 VDC.
Between 128.5 and 131.6 VDC (Step 7.2.6.2) Determines that E1B11(E2B11)
- 2 Battery Charger VDC will Cue:
NOT adjust properly. Steps If asked, E1B11(E2B11) - 1 7.2.6.2 and 7.2.6.3 can NOT be Battery Charger voltage is performed.
129.5 VDC.
Shuts down the battery charger When asked about per alternate step 7.2.6.4. (See E1B11(E2B11) - 2 Battery next JPM step)
Charger DC voltage, then give the following:
o Initial voltage indication is 126.0 VDC.
o Final voltage indication is 126.0 VDC.
Page 8 of 12
NRC P3 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number Float Voltage Adjustment Knob Page 9 of 12
NRC P3 - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Location: 35 EAB, Room 213, south wall on E1B11(E2B11) Switchboard
- 8 IF charger voltage can NOT be OPENS E1B11(E2B11) - 2 ___ ___ ___
adjusted to the float band of Battery Charger Breakers:
steps 7.2.6.2 and 7.2.6.3 as
- AC INPUT CB-1 applicable, THEN OPEN the following breakers and NOTIFY
- DC OUTPUT CB-2 the Unit Supervisor/Shift Manager.
- AC INPUT CB-1
- DC OUTPUT CB-2 (Step 7.2.6.4)
Cue:
On both breakers:
INITIAL: Breaker Handle UP FINAL: Breaker Handle DOWN CUE This JPM is complete JPM Stop Time:
Page 10 of 12
NRC P3 - rev 0 JPM
SUMMARY
Operators Name: Job
Title:
Title:
PLACE A 1E BATTERY CHARGER IN SERVICE JPM Number: NRC P3 Revision Number: 0 Task Number and
Title:
74950, Respond to DC Electrical Distribution Alarms K/A Number and Importance: 063 A3.01 2.7/3.1 Suggested Testing Environment: Simulator Control Room In-Plant Other Alternate Path: Yes No Task Designed For: SRO Only RO/SRO AO/RO/SRO Time Critical: Yes No Level of Difficulty: 3 Reference(s): 0POP02-EE-0001, ESF (Class 1E) DC Distribution System, Rev 35 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 30 minutes Actual Time Used: minutes Critical Steps (*) 5, 6, 7 & 8 Evaluation Summary:
Were all the Critical Steps performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
Page 11 of 12
Student Handout INITIAL CONDITIONS The Unit is in Mode 1 at 100% power. Battery Charger E1B11(E2B11) - 1 is scheduled to be taken out of service for maintenance.
INITIATING CUE You have been given 0POP02-EE-0001, ESF (Class 1E) DC Distribution System, Section 7.2, Transfer of Train B Channel III Battery Chargers.
The Unit Supervisor has dispatched you to SWAP the Train B Channel III Battery Chargers by placing Battery Charger E1B11(E2B11) - 2 in service and securing Battery Charger E1B11(E2B11) - 1.
The procedure prerequisites and Addendum 1, Control Loop Alignment, have been completed.
Page 12 of 12
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 1 of 25 LOT 21 NRC EXAM SIMULATOR OPERATING TEST SCENARIO #1 Revision 0 Week of 09/27/2017
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 2 of 25 SCENARIO OUTLINE Facility: South Texas Project Scenario No.: 1 Op-Test No.: LOT 21 NRC Examiners: Operators:
Initial Conditions:
- Unit 1 is at 100% Reactor Power. BOL. (IC #190)
Turnover:
- The Crew will start FWBP #13 and place FWBP #12 in Auto.
- ESF DG #12 is OOS for Maintenance Event No. Malf. No. Event Type* Event Description 1 N/A BOP (N) Start FWBP #13 and place FWBP #12 in Auto.
(0 min)
SRO (TS Only) 2 CM-39 RT-8011 malfunction. Condition DARK BLUE loss of sample (10 min) flow.
0 See NOTE 3 below RO (C) EAB Battery Room Exhaust Fan 11C develops sheared shaft.
(17 min) SRO (C, TS) When RO tries to start Battery Room Exhaust Fan 11B the fan trips.
4 05-14-01 BOP (I) Main Steam Header Pressure Transmitter PT-557 Fails to a (27min) SRO (I) lower intermediate position. (Ramped in over 60 seconds) (LOT 0.4 19 Failed High) 02-07-03 5 BOP (C) RCS Loop C Low Flow due to RCP 1C sheared shaft.
(35 min) 1 SRO (C) 01-12-02 Reactor does not trip until Crew manually opens Load Center 1 Breakers for Rod Drive MG Sets (Auto Rx Trip failure is initial condition of Lesson Plan)
(Critical Task) 6 50-HV-01 RO (C) PZR PORV RC-PCV-0655A fails open. (5 minutes after opening 1.0 SRO (C) Load Center Breakers for Rod Drive MG Sets) (LOT 21 Audit &
(N/A) LOT 20 but it was before RX trip and block valve also failed to close)
(Critical Task) 7 08-06-03 ALL (M) SG 1C Loss of Feedwater inside containment. (3 minutes after (N/A) PZR PORV block valve is closed) (LOT 19 Main Steam) 0.5 (Critical Task)
New Failure 8 No Malf. # RO (C) RCB Atmosphere Radiation Monitor Isolation Valves fail to (N/A) SRO (C) automatically close. (Initial condition of Lesson Plan)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor.
NOTE: Malfunction numbers for Event #3 - Cl_3V111VFM012TFShear - 1 & POSBBARV32733TCC - 1
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 3 of 25 SCENARIO MISCELLANEOUS INFORMATION INSTRUCTOR NOTES:
Refer to the Instructor Guide for directions on Simulator Setup, Expected Booth Communications and Expected Booth Actions.
CRITICAL PARAMETERS:
The following parameters may be of value in evaluating crew performance and should be automatically recorded during the scenario. Once the scenario is complete for each crew, printout the Critical Parameters and label the printout with date, time, Crew # and scenario #.
- DRPI for Control Bank D
- Power Range NI-0041
- RC-MOV-001A position
- AF-MOV-0085 position OPERATOR ACTIONS TABLE NOTES:
- 1. Critical Tasks are indicated by "C" in the position column and indicated in bold type.
- 2. Actions required throughout the event are indicated as "(continuous)" in the position column.
- 3. Shaded cells indicate procedural entry points.
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 4 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 1 Event
Description:
Start FWBP #13 and place FWBP #12 in Auto.
Time Position Required Operator Actions Notes BOP Contacts a Plant Operator to verify 0POP02-FW-0001, Main FWBP #13 Lube Oil and Seal Water are Feedwater (Step 13.1) in service.
BOP Verifies adequate Lube Oil conditions for (Step 13.2)
FWBP # 13 by observing Annunciator FW BOOST PMP 13 L.O. AUX PMP TRBL is cleared (not in an alarm condition).
BOP Verifies Deareator Storage Tank level is (Step 13.3)
> 30%
BOP May contact a Plant Operator to verify This action comes from a FWBP #13 Lube Oil Reservoir procedure NOTE and is not temperatures are > 60 °F. an actual step.
BOP Verifies FWBP #13 is within 50 °F of (Step 13.4)
Deareator and downstream temperatures.
BOP May contact a Plant Operator to monitor (Step 13.5) seal water outlet temperatures once BOP operator may not FWBP #13 is started. perform this step until after FWBP has been started.
BOP Closes discharge valve MOV-0456 for (Step 13.6)
FWBP #13.
BOP Verifies the FWBP #13 Start Permissive (Step 13.7) circuit indicates start permissives are met Will have to contact a Plant by: Operator for status of Blue
- Checking Annunciator FW BOOST light.
PUMP TRIP/TROUBLE is NOT in alarm.
- Blue Permissive light is ON at 13.8 kV Swgr. 1J, Cubicle 9.
- Plant computer point for FWBP #13 TRIP/TROUBLE indicates Norm.
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 5 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 1 Event
Description:
Start FWBP #13 and place FWBP #12 in Auto.
Time Position Required Operator Actions Notes BOP Starts FWBP #13 using CP-008 control (Step 13.8) sw. and informs Unit Supervisor Pump The BOP operator may has been started. contact a Plant Operator to ensure the FWBP is ready for starting before actually starting it.
The discharge valve will automatically open when the pump starts.
Once the discharge valve opens there will be an increase in feed flow to the SGs so the BOP operator should monitor SG levels and Feed Reg Valves to determine the SG Water level control system is responding as expected.
BOP Contacts Plant Operator to verify the (Steps 13.9 - 13.14) status of certain auxiliary systems on These are the last actions FWBP #13: associated with starting
- Aux Oil Pump and Shaft-driven oil FWBP #13.
pump See Booth Communications.
- Recirc valve
- Lube Oil Temperature
- Seal Water Temperature Control Valves.
BOP Contacts the Plant Operator to ensure (Step 14.1)
FWBP #12 Aux. Oil Pump is available There are several procedure for securing FWBP #12. steps associated with this action. The BOP may read them to the Plant Operator individually or direct him to perform the required steps using his own procedure and report back the results.
Two Plant Operators are required as well.
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 6 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 1 Event
Description:
Start FWBP #13 and place FWBP #12 in Auto.
Time Position Required Operator Actions Notes BOP Closes FWBP #12 discharge valve, (Step 14.2)
MOV-0457.
BOP After FWBP #12 discharge valve is (Step 14.3) closed, BOP stops FWBP #12 and Event # 2 can occur here on informs the Unit Supervisor that the signal from Lead Examiner.
pump has been secured.
BOP Contacts Plant Operator to ensure FWBP (Step 14.4)
- 12 Aux Oil Pump has started. There are several steps that must be performed in the field to accomplish this action.
BOP Ensures FWBP #12 discharge valve (Step 14.6)
MOV-0457 is closed. Step 14.5 was N/A
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 7 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 2 Event
Description:
RT-8011 malfunction Time Position Required Operator Actions Notes RO/BOP Acknowledges the Radiation Monitoring RT-8011 has a loss of sample System alarm on the RM-11, determines flow.
the monitor in alarm and reports the status to the Unit Supervisor.
SRO Transitions to 0POP04-RA-0001, Steps 1 to 8 are considered Radiation Monitoring System Alarm skill of the craft.
Response. The loss of sample flow for RT-8011 causes the status of the monitor to change from green to dark blue on RM-11.
The SRO will respond by going to Addendum 24, Page 7.
SRO REFER TO The Appropriate Addendum (Addendum 24, Step 1.0)
For The Affected Radiation Monitor A High (red) Alarm does not High Alarm Response, To Check For exist.
Inadvertent Actuation.
SRO CHECK Any Of The Following (Addendum 24, Step 2.0)
Conditions Exist: None apply so SRO will GO
- Process flow is secured TO Step 4.0.
- RMS maintenance in progress
- Alarm occurred during grab sample collection SRO ENSURE Monitor Sample Pump (Addendum 24, Step 4.0)
Running Sample pump is the issue and cannot be restarted.
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 8 of 25 Op-Test No.: 1 Scenario No.: 1 Event No.: 2 Event
Description:
RT-8011 malfunction Time Position Required Operator Actions Notes SRO DETERMINE Technical Specification, (Addendum 24, Step 5.0)
Technical Requirements Manual (TRM)
And Offsite Dose Calculation Manual Event 3 can be triggered after (ODCM) Applicability For The Affected the SRO checks Technical Radiation Monitor Specifications at the discretion of the Lead Examiner.
With the required containment atmosphere radioactivity monitor inoperable perform the following actions or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />s:
- 1) Restore the containment atmosphere monitor (particulate channel) to OPERABLE status within 30 days and,
- 2) Obtain and analyze a grab sample of the containment atmosphere for particulate radioactivity at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or
- 3) Perform a Reactor Coolant System water inventory balance at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SRO CHECK The Affected Monitor Is One Of (Addendum 24, Step 6.0)
The Following:
With the alarm for loss of sample flow still in the SRO will notify the primary user (Health Physics) and initiate a condition report.
SRO GO TO Procedure and Step in Effect. (Addendum 24, Step 10.0)
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 9 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Event
Description:
EAB Battery Room Exhaust Fan 11C develops sheared shaft. When RO tries to start Battery Room Exhaust Fan 11B the fan trips.
Time Position Required Operator Actions Notes RO Acknowledges and announces the RO will refer to 0POP09-AN-following annunciators on 22M3: 22M3.
- BATT ROOM EXH FAN TRBL (C-3)
RO Determines affected EAB battery room (Window C-3, Step 1) exhaust fan using Plant Computer points.
RO Dispatches an operator to the affected (Window C-3, Step 2)
EAB battery room exhaust fan to check local fan DP indication.
RO/BOP Initiates a Condition Report to investigate (Window C-3, Step 3) the cause of fan trouble.
RO Transitions to 0POP02-HE-0001 to start (Window C-3, Step 4) a backup train and secure the affected train.
RO Starts BATTERY ROOM EXH FAN (Step 7.2.1) 11B Fan will trip shortly after starting RO Places BATTERY ROOM EXH FAN 11B and 11C in PTL SRO Refers to TS 3.3.3.5 for required actions. (Window C-3, Step 5)
RESTORE the inoperable Function to Per Table B 3.3.5-1 (located OPERABLE status within 30 days, or in the Bases section), 2 be in HOT STANDBY within the next Battery Room Fans are 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN required.
within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Event 4 can be triggered after SRO has checked TS.
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 10 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event
Description:
Main Steam Header Pressure Transmitter PT-557 Fails to a lower intermediate position.
Time Position Required Operator Actions Notes BOP Acknowledges and announces Annunciators listed are not annunciators: inclusive.
Performs required immediate actions of 0POP04-FW-0002:
- Checks SGFP Master Speed Controller and determines it is NOT responding appropriately in Automatic.
- Takes manual control of SGFP Master Speed Controller and adjusts output to restore SG levels to 68-74%.
SRO Directs performance of 0POP04-FW- A post CT may apply if the (continuous) 0002, Steam Generator Feed Pump Trip. reactor is inadvertently tripped.
BOP Checks SGFPTs - required number (Step 1.0) running.
BOP Checks SGFP Master Speed Controller: (Step 2.0)
- Operable in Automatic - determines The PT-557 failure should be it is not. revealed during this step if not
- Places the controller in manual and already done.
adjusts output to raise feed flow.
BOP Checks if Feed flow is adequate for (Step 3.0) current steam demand. By now, the BOP operator should have raised the output of the SGFP Master Speed Controller sufficiently to raise feed flow above steam flow.
BOP Checks SGFP Recirculation Valve status. (Step 4.0)
Should be responding in Automatic RO Checks reactor power >5%. (Step 5.0)
BOP Monitors SG Levels trending to program. (Step 6.0)
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 11 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event
Description:
Main Steam Header Pressure Transmitter PT-557 Fails to a lower intermediate position.
Time Position Required Operator Actions Notes BOP Checks Feedwater/Steam Header DP per (Step 7.0)
Addendum 3 requirements BOP may have to make manual adjustments to SGFP Master Speed Controller to maintain Feedwater/Steam Header DP per Addendum 3.
RO Checks Delta-I is within the required (Step 8.0) band.
BOP Checks Steam Dumps status: (Step 9.0)
- in Tave mode
- Steam Dump Controller UI-0555 at minimum demand and Steam Dumps are closed.
- Reset C7 by momentarily placing the Steam Dump Mode Sel Sw. to RESET.
- Check STEAM DUMP UNBLOCK AVAILABLE light is extinguished.
BOP Checks SGFP speeds are: (Step 10.0)
- 5500 rpm with a flow > 8250 gpm essentially completed the steps of 0POP04-FW-0002, Steam Generator Feed Pump Trip.
SRO INITIATE Corrective Action For Failed (Step 11.0)
Component.
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 12 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 5 Event
Description:
RCP 1C Trips. Reactor does not trip until Crew manually opens Load Center Breakers for Rod Drive MG Sets.
Time Position Required Operator Actions Notes RO Acknowledges and announces the following annunciator on 05M2:
RC LOOP 3 FLOW LO RX PRETRIP (A-3)
SRO/RO Determines RCP 1C tripped and the reactor should have tripped but did not.
RO/BOP Manually trip the reactor by opening Manual trip will only be (CT-1) 480V Load Center 1K1 and 1L1 feeder successful by de-energizing breakers. the Rod Drive MG Sets.
BOP Closes 480V Load Center 1K1 and 1L1 feeder breakers after control rods have inserted.
SRO Directs actions of 0POP05-EO-EO00, Event #6 will begin (continuous) Reactor Trip or Safety Injection. ramping in when Rx trip breakers are open. Crew will re-enter E0 when Event
- 6 is recognized.
RO Completes immediate actions of 0POP05- (Steps 1-4)
EO-EO00 and determines: RO will announce status of
- Reactor is tripped immediate action steps as
- Turbine is tripped he/she performs them.
- SI is not actuated BOP Operator will monitor the plant and make an announcement of the Reactor trip.
SRO Directs/ensures the immediate actions of EO00, Reactor Trip/SI have been completed by performing a procedure read through of them.
SRO Transitions to 0POP05-EO-ES01, Reactor The crew will continue in Trip Response. ES01 until the feedwater break is recognized and transition is made back to E0 RO CHECK RCPs - ANY RUNNING (Step 1.a)
RCPs 1A, 1B and 1D are running.
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 13 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 5 Event
Description:
RCP 1C Trips. Reactor does not trip until Crew manually opens Load Center Breakers for Rod Drive MG Sets.
Time Position Required Operator Actions Notes RO MONITOR RCS Temperatures (Step 1.b)
- WITH ANY RCP RUNNING, RCS RCS temperature should be TAVG STABLE AT OR TRENDING trending to 567oF if ARW TO 567oF has been throttled.
BOP Checks RCS TAVG less than 574oF (Step 2.a)
BOP Verifies the following valves CLOSED: (Step 2.b)
- FWIBs
- FW preheater bypass valves
- FW regulating valves
BOP Verifies Feedwater flow to at least 3 steam (Step 3) generators AFW has actuated and Main Feedwater has isolated.
RO Verifies all Control Rods fully inserted (Step 4)
BOP Verifies NO ESF diesel generators running (Step 5)
RO Check PZR Level CONTROL: (Step 6)
- PZR Level > 17%
- Verify charging in Service
- Check RCP seal injection normal
- Verify letdown in service
- PZR level trending to 25%
RO Monitor PZR Pressure CONTROL: (Step 7)
(CT-10)
- Pressure > 1857 psig
- Pressure stable at or trending to 2235 Event #6 PZR PORV RC-psig PCV-0655A will stick open RNO about 5 minutes after the Perform the following: LC breakers to the MG sets
- IF pressure LESS THAN 2235 PSIG are opened.
AND lowering, THEN:
- Ensure PZR PORVs closed
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 14 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event
Description:
SG 1C Loss of Feedwater inside containment.
Time Position Required Operator Actions Notes SRO/RO/ Recognizes faulted 1C Steam Generator BOP SRO/RO Manually initiates Safety Injection Auto Safety Injection may occur depending on crew response SRO Re-enters 0POP05-EO-EO00, Reactor After the Safety Injection, the (continuous) Trip or Safety Injection. SRO will transition back to E0, Step 1 RO Completes read through of 0POP05-EO- 0POP05-EO-EO00, Reactor EO00, Reactor Trip or Safety Injection. Trip or Safety Injection Steps
- Reactor Tripped. 1-4.
- Turbine Tripped. Read through only.
- SI is actuated.
BOP VERIFY Proper SI Equipment Operation (Step 5)
Per ADDENDUM 5, VERIFICATION See Actions on pages 20-23 OF SI EQUIPMENT OPERATION BOP Per the CIP of 0POP05-EO-EO00, (CT-17) Reactor Trip or Safety Injection:
IF a faulted SG(s) is NOT required to maintain at least two SGs available for RCS cooldown, THEN the US or SM may direct actions be taken to isolate the faulted SG(s).
Also see Page 17 & 18
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 15 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event
Description:
SG 1C Loss of Feedwater inside containment.
Time Position Required Operator Actions Notes RO MONITOR If Containment Spray Is (Step 6)
Required: Containment pressure will be
- Containment pressure GREATER less than 9.5 psig.
THAN 9.5 PSIG (QDPS)
(RNO)
- PERFORM the following:
- CHECK Containment pressure -
18)
- "PRESS PR0934" OR
- "EXTD RNG PRESS PR9759"
- IF containment pressure HAS EXCEEDED 9.5 PSIG, THEN GO TO Step 6.b.
- IF containment pressure HAS REMAINED LESS THAN 9.5 PSIG, THEN GO TO Step 7.
RO CHECK RCP Seal Cooling: (Step 7)
- ENSURE seal injection flow between RO may have to adjust seal 6 and 13 gpm injection.
RO MONITOR RCS Temperatures (Step 8)
- WITH ANY RCP RUNNING, RCS If AFW has been properly TAVG STABLE AT OR TRENDING throttled from the original TO 567°F Reactor Trip then RCS OR temperature should be
- WITHOUT ANY RCP RUNNING, trending to 567°F.
RCS TCOLD STABLE AT OR TRENDING TO 567°F
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 16 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event
Description:
SG 1C Loss of Feedwater inside containment.
Time Position Required Operator Actions Notes RO CHECK Pressurizer Status: (Step 9)
(CT-10)
- IF pressure LESS THAN 2235 about 5 minutes after the LC PSIG AND lowering, THEN: breakers to the MG sets are
- Manually close PZR PORVs opened.
- If any PZR PORV cannot be closed, then close its associated isolation valve A/ER
- Normal pressurizer spray valves -
CLOSED
- Auxiliary spray valve - CLOSED
- Excess letdown isolation valves -
CLOSED RO MONITOR If RCPs Should Be Stopped: (Step 10)
- HHSI pump - AT LEAST ONE Reactor Coolant Pump Trip RUNNING Criteria will probably NOT be
(RNO)
- GO TO Step 11 RO VERIFY The Following Containment (Step 11)
Isolation Valve - CLOSED Event #8 will be realized
- Seal return isolation valves here. The Containment CLOSE the following valves: Atmosphere Radiation
- Containment atmosphere radiation Monitor Isolation Valves will monitor isolation valves have to be manually closed.
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 17 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event
Description:
SG 1C Loss of Feedwater inside containment.
Time Position Required Operator Actions Notes RO CHECK If SG Secondary Pressure (Step 12)
Boundary Intact: Will not transition to a
- CHECK pressures in all SGs - Functional Recovery
- CONTROLLED OR RISING Procedure until Addendum 5
- GREATER THAN is complete.
CONTAINMENT PRESSURE (RNO)
GO TO 0POP05-EO-EO20, FAULTED STEAM GENERATOR ISOLATION, Step 1.
- MONITOR Critical Safety Functions
- WHEN Addendum 5 of this procedure is complete, THEN Functional Restoration Procedures may be IMPLEMENTED.
BOP Completes 0POP05-EO-EO00, Will not transition to a Addendum 5. Functional Recovery Procedure until Addendum 5 is complete.
SRO Informs crew of transition to 0POP05-(continuous) EO-EO20, Faulted SG Isolation, and to monitor Critical Safety Functions SRO/BOP Checks MSIVs and MSIBs closed. 0POP05-EO-EO20, Faulted (CT-17) SG Isolation, Step 1 (goes with CT on next page) This step may already be performed (see page 20, performing EO00 Add 5)
BOP CHECK If Any SG Secondary Pressure Step 2 Boundary Intact: SGs A, B and D
- CHECK pressures in all SGs - ANY pressures are controlled.
SG PRESSURE CONTROLLED OR RISING SG C pressure is NOT controlled.
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 18 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event
Description:
SG 1C Loss of Feedwater inside containment.
Time Position Required Operator Actions Notes SRO/BOP IDENTIFY Faulted SG(s): Step 3
- CHECK pressure in all SGs - SG 1C is faulted o ANY SG PRESSURE LOWERING IN AN UNCONTROLLED MANNER OR o ANY SG COMPLETELY DEPRESSURIZED SRO/BOP Isolates the faulted SG (1B) Step 4 (CT-17)
- Verifies all FWIVs closed.* CT-Verifies the faulted S/G is
- denotes
- Verifies all FWIBs closed.* isolated, the crew will have to critical
- LO-LO actuation in order to
- Verifies all FW Regulating and be able to close the AFW Low Power FW Regulating Valves OCIV closed.*
May have already been
- completed. See page 13.
- Resets SI
- Resets ESF load sequencers
- Checks SG 1D intact
- Verifies SG C Blowdown and sample isolation valves closed
- LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 19 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event
Description:
SG 1C Loss of Feedwater inside containment.
Time Position Required Operator Actions Notes BOP/SRO Check Secondary Radiation: Step 5
- Resets SI The first 3 resets have already
- Resets SG Blowdown and Sampling reset.
Isolations
- Notifies Chemistry to sample all SGs hourly for activity.
- Checks the following Rad Monitors:
o Main Steamline o SG Blowdown o CARS Pump CARS = Condenser Air
- WHEN SG sample results are Removal System.
received, THEN VERIFY SG sample activity - NORMAL ALL Check if SI flow should be terminated Step 6
- RCS subcooling - >35°F [45°F] If conditions are met, a
- Secondary heat sink - NR level in one transition to 0POP05-EO-SG > 14% [34%] OR total AFW Flow ES11, SI Termination, will be
> 576 gpm. made.
- RCS pressure > 1745 psig and stable or rising Conditions will likely NOT be
- Pressurizer level > 8% [44%] met for transition at this time.
If not met (expected), the crew will transition to 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant.
SRO Announces transition from 0POP05-EO-EO20 (to ES11 or E010, as appropriate). Terminate the scenario.
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 20 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: N/A Event
Description:
0POP05-EO-EO00, Addendum 5 actions Time Position Required Operator Actions Notes BOP VERIFY FW isolation: 0POP05-EO-EO00, Reactor
- SGFPTs - TRIPPED Trip or Safety Injection,
- SU SGFP - TRIPPED Addendum 5, Verification of
- VERIFY the following valves - Equipment Operation.
CLOSED (Step 1) o FWIVs This addendum is performed o FWIBs in parallel with Steps 5 to 14 o FW preheater bypass valves of 0POP05-EO-EO00, o FW regulating valves Reactor Trip or Safety o Low power FW regulating valves Injection.
o SG blowdown isolation valves o SG sample isolation valves BOP CHECK if main steamline should be (Step 2) isolated:
- CHECK for any of the following conditions:
o Containment pressure -
GREATER THAN OR EQUAL TO 3 PSIG OR o SG pressure (without low steamline pressure SI blocked) -
LESS THAN OR EQUAL TO 735 PSIG OR o SG pressure (with low steamline pressure SI blocked) -
LOWERING AT A RATE GREATER THAN OR EQUAL TO 100 PSI/SEC, BY OBSERVANCE OF THE STEAMLINE PRESSURE RATE BISTABLES BOP VERIFY AFW system status: (Step 3) o Motor-driven pump -
RUNNING o Turbine-driven pump -
RUNNING BOP VERIFY AFW valve alignment - (Step 4)
PROPER EMERGENCY ALIGNMENT
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 21 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: N/A Event
Description:
0POP05-EO-EO00, Addendum 5 actions Time Position Required Operator Actions Notes BOP VERIFY total AFW Flow - GREATER (Step 5)
THAN 576 GPM BOP VERIFY containment isolation phase A: (Step 6)
- Phase A - ACTUATED
- Phase A valves - CLOSED, REFER TO ADDENDUM 1, PHASE A ISOLATION VERIFICATION BOP VERIFY ECW status: (Step 7)
- ECW pumps - RUNNING
- ECW pump discharge isolation valves
- OPEN BOP VERIFY CCW pumps - RUNNING (Step 8)
BOP VERIFY RCFC status: (Step 9)
- RCFCs - RUNNING
- HHSI pumps - RUNNING
EMERGENCY ALIGNMENT BOP VERIFY SI flow: (Step 12)
- HHSI pump flow - INDICATED be greater than 415 psig so
PSIG (RNO)
- GO TO Step 13 of this Addendum.
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 22 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: N/A Event
Description:
0POP05-EO-EO00, Addendum 5 actions Time Position Required Operator Actions Notes BOP VERIFY containment ventilation (Step 13) isolation:
Event #8 failed the
- Containment atmosphere radiation Containment atmosphere monitor isolation valves - CLOSED radiation monitor isolation
- Normal purge supply and exhaust fans valves open. The SRO/RO
- STOPPED may have already closed the
- Supplemental purge supply and valves when the BOP reaches exhaust fans - STOPPED this step, otherwise the BOP
- Purge Dampers - CLOSED will be required to close the valves now.
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 23 of 25 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: N/A Event
Description:
0POP05-EO-EO00, Addendum 5 actions Time Position Required Operator Actions Notes BOP VERIFY ventilation actuation: (Step 14)
- Control room HVAC - OPERATING IN EMERGENCY RECIRC
- EAB HVAC - OPERATING IN EMERGENCY RECIRC
- FHB HVAC - OPERATING IN EMERGENCY MODE
- FHB Exhaust Fans - ONLY TWO TRAINS OPERATING o Exhaust booster fans o Main exhaust fans (RNO)
- PERFORM the following:
o IF three trains FHB exhaust fans running, THEN PLACE one train FHB exhaust fans in PULL TO LOCK.
(Back to A/ER)
- SECURE one FHB filter train by PERFORMING the following:
o PLACE the outlet damper Controller in manual o Manually close the outlet damper o VERIFY proper operation of filter train in service
- Essential chilled water pumps -
RUNNING
- Essential chillers - RUNNING
- ECCS pump room fan coolers -
RUNNING
- AFW pump cubicle fans - RUNNING
- FHB truck bay doors - CLOSED BOP NOTIFY Unit Supervisor that Addendum (Step 15) 5 is COMPLETE SRO IMPLEMENT Functional Restoration (Step 16)
Procedures as required SRO RETURN TO procedure step in effect. (Step 17)
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 24 of 25 CRITICAL TASK
SUMMARY
SAT/
POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA UNSAT SRO/RO/ CT-1 Manually trips the Reactor BOP MANUALLY TRIP THE from the Control Room before REACTOR completing Step 1 of 0POP05-EO-EO00, Reactor Trip or Safety Injection.
SRO/BOP CT-10 Close the block MOV CLOSE A PZR PORV BLOCK upstream of the stuck open VALVE TO ISOLATE A STUCK PZR PORV by completion of OPEN PZR PORV Step 7.b RNO of 0POP05-EO-ES01, Reactor Trip Response OR by completion of Step 9.a RNO of 0POP05-EO-EO00, Reactor Trip or Safety Inspection.
SRO/BOP CT-17 Isolate a Faulted Steam ISOLATE FAULTED SG Generator before transitioning out of 0POP05-EO-EO20, Faulted Steam Generator Isolation.
LOT 21 NRC OP-TEST SCENARIO #1 Rev 0 Page 25 of 25 TURNOVER INFORMATION Reactor Power is at 100%.
- Plans are to start FWBP #13 and place FWBP #12 in Auto.
- ESF DG #12 was just tagged out for an emergent condition. Return to service of ESF DG #12 is unknown.
- Cycle Burnup is 150 MWD/MTU. (BOL)
- On the previous shift, RCS dilutions were being performed about every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with 10 gallons of makeup water.
- Boric Acid Tank A is at 7315 ppm and B is at 7309 ppm.
- No liquid waste discharges are in progress or planned.
- No personnel are in containment.
- FHB Truck Bay doors are closed.
LCO Actions:
ESF DG 12 - TS 3.8.1.1 Action b and d. 0PSP03-EA-0002, ESF Power Availability, was completed 30 minutes ago. Action d was entered in the log 45 minutes ago as SAT.
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 1 of 22 LOT 21 NRC EXAM SIMULATOR OPERATING TEST SCENARIO #2 Revision 0 Week of 09/27/2017
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 2 of 22 SCENARIO OUTLINE Facility: South Texas Project Scenario No.: 2 Op-Test No.: LOT 21 NRC Examiners: Operators:
Initial Conditions:
- Unit 1 is at 100% Reactor Power. BOL. (IC #190)
Turnover:
Event No. Malf. No. Event Type* Event Description 1
(0 min) SRO (C) 2 05-22-01 BOP (I) SG 1A controlling Steam pressure channel PT-0514 fails high.
(15 min) SRO (I, TS) (LOT 19 Failed Low on SG 1D PT-0545) 1 3
01-07-07 RO (R) One Dropped Control Rod M12.
(30 min) BOP (R) 1 SRO (R, TS) 4 10-14-01 ALL (M) One Dropped Control Rod M12. The Crew will start a down (50 min) power to less than 75%.
1 5 04-09-01 RO (C) ECW Pump 1A fails to re-start on the LOOP forcing the crew to (N/A) 1 SRO (C) secure ESF DG #11. (Trips on restart after LOOP)
(Critical Task) 6 50-GD-06 1 ALL (C) ESF DG #13 trips. Crew will enter 0POP05-EO-EC00, Loss of All (N/A) AC Power. (Trips 10 minutes after LOOP) The 138 KV Emergency Transformer will be available.
(2 Critical Tasks)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor.
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 3 of 22 SCENARIO MISCELLANEOUS INFORMATION INSTRUCTOR NOTES:
Refer to the Instructor Guide for directions on Simulator Setup, Expected Booth Communications and Expected Booth Actions.
CRITICAL PARAMETERS:
The following parameters may be of value in evaluating crew performance and should be automatically recorded during the scenario. Once the scenario is complete for each crew, printout the Critical Parameters and label the printout with date, time, Crew # and scenario #.
- RCP 1C Seal Injection Flow
- RCP 1C Lower Seal Water Bearing Temp
- 1. Critical Tasks are indicated by "C" in the position column and indicated in bold type.
- 2. Actions required throughout the event are indicated as "(continuous)" in the position column.
- 3. Shaded cells indicate procedural entry points.
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 4 of 22 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 1 Event
Description:
Spent Fuel Pool (SFP) Cooling Pump 1A trips.
Time Position Required Operator Actions Notes RO Acknowledges and announces the SFP COOLING FLOW LO following annunciator from 22M2: may also be entered but has similar steps for a trip of a
SRO/RO Determines that SFP Pump 1A has tripped.
RO CHECK the following Plant Computer (Step 1) points: There are several ICS points
- FCQD1406A (SFP Cooling Pump to check for this step.
1A(2A) Trip)
RO IF the alarm is due to a trip of the Spent (Step 5)
Fuel Pool Cooling Pump, THEN Step 5 has the directions for a PERFORM the following: SFP Pump that has tripped.
- DISPATCH an Operator to investigate cause:
- Spent Fuel Pool Cooling Pump 1A(2A) {22 ft FHB}Power Supply - 480V LC E1B1/4F(E2B1/4F)
- START Standby Spent Fuel Pool Cooling Pump Per 0POP02-FC-0001, Spent Fuel Pool Cooling and Cleanup System.
SRO/RO SRO directs the RO to start SFP Pump 1B using 0POP02-FC-0001, Spent Fuel Pool Cooling and Cleanup System.
RO ENSURE the SFPCPs are secured per (Step 6.1.1)
Section 6.2, Securing Spent Fuel Pool Cooling Pumps.
RO ENSURE Purification is secured per (Step 6.2.1)
Section 7.3, Securing SFPCCS SFPCCS purification was Purification. NOT in service.
RO STOP the desired SFP 1A AND PLACE (Step 6.2.2) its handswitch in "PTL" Since SFP Pump 1A had already tripped the operator will put the handswitch in PTL.
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 5 of 22 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 1 Event
Description:
Spent Fuel Pool (SFP) Cooling Pump 1A trips.
Time Position Required Operator Actions Notes RO ENSURE the "SFP COOLING PUMP (Step 6.2.3)
DISCHARGE VALVE" in the train which will remain idle is CLOSED.
- Pump 1A(2A) [idle] "1(2)-FC-0010A" RO RESTORE auto operation of the (Step 6.2.4) associated SFPCP cubicle fan by momentarily placing the control switch to stop and back to auto, as applicable.
- PMP 1A(2A)/RM 107 SUPP CLR 11A(21A)
RO ENSURE the applicable plant computer (Step 6.2.5) point is off scan for SFPCP that is This step will clear the secured, as applicable: BYPASS INOP alarm that
After this step operator will transition back to step 6.1.2.
RO ENSURE the "SFP COOLING PUMP (Step 6.1.2)
DISCHARGE VALVE"(s) for the train(s) being placed in service is OPEN.
- SFPCP 1B(2B) "1(2)-FC-0010B" RO VERIFY the pump shaft has stopped (Step 6.1.4) rotating for the SFPC Pump that will be Step 6.1.3 was already started. performed in Step 6.2.3.
- "SFPCP 1B(2B)"
RO START the desired SFPCP, as follows: (Step 6.1.5)
IF single train operation is desired, THEN START the selected SFPCP.
- "SFPCP 1B(2B)"
RO THROTTLE the applicable "SFP HEAT (Step 6.1.6)
EXCHANGER OUTLET THROTTLE VALVE" as necessary to maintain SFPCP discharge flow between 2500 AND 3000 gpm. (At Respective 36' FHB SFPC HX AND 22' FHB SFPC Pump Rooms)
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 6 of 22 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 1 Event
Description:
Spent Fuel Pool (SFP) Cooling Pump 1A trips.
Time Position Required Operator Actions Notes RO VERIFY the applicable SFP HX outlet (Step 6.1.7) temperature(s) less than 110°F. (36 ft FHB SFPC HX Rm)
- SFP HX 1B(2B) "1(2)-FC-TI-1410" RO ENSURE the applicable plant computer (Step 6.1.8) point(s) are on scan for running ICS point for SFP Pump 1A SFPCP(s) AND off scan for secured was taken off scan in step pump(s), as applicable. 6.2.5.
- "SFPCP 1B(2B)" FCUD1408A The crew will put SFP Pump 1B computer point back on scan.
RO PERFORM Lineup 3, Restoration of (Step 6.1.9)
SFPC Pumps. Lineup 3 ensures the SFP Pump discharge valves are closed unless the associated pump is running.
Event 2 can be triggered on a signal from the lead examiner.
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 7 of 22 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Event
Description:
SG 1A controlling Steam pressure channel PT-0514 fails high.
Time Position Required Operator Actions Notes BOP Acknowledges and announces the BOP uses annunciator following annunciator from 06M4: response procedures but will also recognize the need to
- SG 1A STM/FW FLOW MSMTCH perform immediate actions.
SRO/BOP Determines SG 1A Controlling Pressure Failed Channel is MS-PT-Channel PT-0514 fails low. 0514.
Performs immediate actions of 0POP04- Immediate Action - BOP FW-0001: takes Manual control of SG
Regulating Valve(s) not properly responding in MANUAL AND ADJUST as necessary to restore affected SG NR level(s) to between 68% and 74%.
SRO Directs actions of 0POP04-FW-0001, (continuous) Loss of Steam Generator Level Control.
BOP CHECK SG Feedwater Regulating (Step 1.0)
Valve(s) - RESPONDING IN Should already have the AUTOMATIC affected MFRV in manual.
BOP CHECK SGFP Speed Controllers - (Step 2.0)
RESPONDING IN AUTOMATIC The Unit Supervisor may elect to place the Master Speed Controller in Manual because the failure will affect the P setpoint.
BOP CHECK Main Feedwater Regulating (Step 3.0)
Valves:
- CHECK Main Feedwater Regulating Valve(s) - IN SERVICE
- CHECK Main Feedwater Regulating Valve(s) - ANY IN MANUAL
- CHECK Affected Main Feedwater Regulating Valve(s) -
RESPONDING IN MANUAL BOP CHECK Low Power Feedwater (Step 4.0)
Regulating Valves: LPFRVs are not in service.
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 8 of 22 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Event
Description:
SG 1A controlling Steam pressure channel PT-0514 fails high.
Time Position Required Operator Actions Notes SRO/BOP CHECK SGFP Master Speed Controller - (Step 5.0)
IN MANUAL The Unit Supervisor may elect to place the Master Speed Controller in Manual because the failure will affect the P setpoint.
BOP CHECK SGFP Master Speed Controller (Step 6.0)
- RESPONDING IN MANUAL This step is skipped if the controller is still in AUTO.
BOP CHECK Individual SGFP Speed (Step 7.0)
Controllers - ANY IN MANUAL Controllers should be in Auto.
BOP MONITOR Feedwater/Steam Header (Step 9.0)
DP- If the Master Speed Controller GREATER THAN OR EQUAL TO DP was placed in Manual then the REQUIRED BY Addendum 1 crew may adjust to the correct OR P. However, this failure does not create a drastic effect SGFP Master Speed Controller At 100%
on controller response if left in Auto.
BOP RESTORE Affected SG NR Level(s) To (Step 10.0)
Between 68% And 74%
BOP MONITOR SG NR Levels - GREATER (Step 11.0)
THAN 20%
BOP MONITOR SG NR Levels - LESS (Step 12.0)
THAN 87.5%
BOP CHECK SG NR Level Indicators - ALL (Step 13.0)
OPERABLE BOP CHECK Feedwater Flow Transmitters - (Step 14.0)
ALL OPERABLE BOP CHECK Steam Flow Transmitters - ALL (Step 15.0)
OPERABLE A failure of the steam pressure
- SELECT the operable steam flow transmitter will affect the channel for affected SG(s) level steam flow transmitter. De-control. select the failed channel in one of the next 2 steps.
BOP CHECK Steam Pressure Transmitters - (Step 16.0)
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 9 of 22 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Event
Description:
SG 1A controlling Steam pressure channel PT-0514 fails high.
Time Position Required Operator Actions Notes ALL OPERABLE
BOP CHECK SG NR Levels - BETWEEN (Step 17.0) 68% And 74%
BOP CHECK Main Feedwater Regulating And (Step 18.0)
Low Power Feedwater Regulating Valves Automatic Control - OPERABLE BOP CHECK Main Feedwater Regulating OR (Step 19.0)
Low Power Feedwater Regulating Valve(s) - IN AUTO (RNO)
WHEN SG levels return to between 68%
and 74%, THEN PERFORM the following:
- MONITOR proper operation of Feedwater Regulating Valve(s) in Auto.
BOP CHECK SGFP Master Speed Controller - (Step 20.0)
IN AUTO If the Master Speed Controller was placed in Manual, then it can now be placed back in Auto.
SRO TAKE Appropriate Actions Per (Step 21.0)
Technical Specifications.
Most Limiting Action:
- TS 3.3.2.1.f Compensated Steam Line Pressure - Low Action 20 Place the failed channel in the tripped condition within 72
- TS 3.3.2.4.e. Compensated Steam hours. (See full action on next Line Pressure - Low Action 20 page.)
Event #3 may be triggered after the SRO refers to Tech Specs.
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 10 of 22 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Event
Description:
SG 1A controlling Steam pressure channel PT-0514 fails high.
Time Position Required Operator Actions Notes SRO NOTIFY I&C To Place The Affected (Step 22.0)
Channel In Trip Or Bypass. REFER TO Addendum 2, Procedure List For The Appropriate Procedure SRO INITIATE Corrective Actions For Failed (Step 23.0)
Component With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
- a. For Functional Units with installed bypass test capability, the inoperable channel may be placed ln bypass, and must be placed in the tripped condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 11 of 22 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Event
Description:
One Dropped Control Rod M12.
Time Position Required Operator Actions Notes RO Acknowledges and announces the following Annunciators:
- RPI TROUBLE
- ROD SUPV MNTR ROD POSITION TRBL
- ROD BOTTOM RO Diagnoses Rod M12 has dropped into the Rod M12 is in Control Bank core, informs the SRO. D RO Performs immediate actions
- Ensures Rod Control in Manual
- Ensures no rod motion
- Checks for dropped rods SRO Directs the actions of 0POP04-RS-0001, (continuous) Control Rod Malfunction.
SRO/RO Verify Immediate Actions complete and (Steps 1-3) transitions to Addendum 1, Recovery of a Dropped Rod.
SRO/RO Addresses DNBR TS if alarm comes in. Lowering RCS temperature and pressure may cause the DNBR alarm to come in but it will clear as soon as PZR Heaters energize to start restoring RCS pressure.
TS 3.2.5 RO VERIFY Reactor Power GREATER (Addendum 1, Step 1)
THAN 5% Power RO Check Tavg Within 1.5oF Of Tref (Addendum 1, Step 2)
(RNO) Due to the position of Control MAINTAIN Tavg Within 1.5oF Of Tref Rod M12 in the core, Tavg By Adjusting The Following As will not be within 1.5oF of Necessary While Maintaining Reactor Tref.
Power Stable:
- ADJUST Turbine load Crew may also start to adjust
- IF Turbine is offline, THEN A JUST address T power on 3 demand on the Steam Generator channels being 101% power.
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 12 of 22 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Event
Description:
One Dropped Control Rod M12.
Time Position Required Operator Actions Notes ALL NOTIFY The Following Of The Rod (Addendum 1, Step 3)
Malfunction:
- Reactor Engineering Supervisor
- Plant Operations Manager
Technical Specification Action Statement Due to the nature of this 3.1.3.1.b.3 In The Control Room Log As Tech Spec the lead examiner Applicable may need to ask the student about the Tech Spec after the scenario.
(See applicable TS action on next page)
SRO/RO Record data for dropped rod. (Addendum 1, Step 5)
- Core location of malfunctioned rod(s)
- Digital Rod Position Indication (DRPI) for malfunctioned rod(s)
- Affected bank(s)
- Group Step Counter Demand position of affected bank(s)
- Type of malfunction (e.g.,
misaligned, immovable, etc)
- Date and time malfunction occurred SRO Determine if reactor power reduction is (Addendum 1, Step 6) required. The procedure note prior to step 6 helps the SRO determine if a reactor power reduction is required.
In reality it would be difficult to restore the Control Rod within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
SRO/RO REDUCE Reactor Power To Less Than (Addendum 1, Step 7) 75% Per 0POP03-ZG-0006, Plant Event #4 can be triggered Shutdown From 100% To Hot Standby or after the down power has 0POP03-ZG-0008, Power Operations started and the lead examiner is satisfied with observation.
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 13 of 22 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Event
Description:
One Dropped Control Rod M12.
Time Position Required Operator Actions Notes Tech Spec Action:
With one full-length rod trippable but inoperable due to causes other than addressed by ACTION a.,
above, or misaligned from its group step counter demand height by more than +/- 12 steps (indicated position), POWER OPERATION may continue provided that within 1 hour:
- 1. The rod is restored to OPERABLE status within the above alignment requirements, or
- 2. The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within +/- 12 steps of the inoperable rod while maintaining the rod sequence and insertion limits as specified in the Core Operating Limits Report (COLR). The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, or
- 3. The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that:
a) A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions; b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; c) A core power distribution measurement is obtained and FQ (Z) and FNH are verified to be within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and d) The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within the next hour and within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the High Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER.
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 14 of 22 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 4 & 5 Event
Description:
Loss of Offsite Power causes a Reactor Trip and ECW Pump 1A fails to re-start on the LOOP forcing the crew to secure ESF DG #11 Time Position Required Operator Actions Notes ALL Respond to multiple alarms due to the One of the crew members Loss of Offsite Power and determines the should announce a crew Reactor has tripped. update, state the Reactor is tripped.
SRO Enters and directs the actions of 0POP05-(continuous) EO-EO00, Reactor Trip or Safety Injection RO Completes immediate actions of (Steps 1-4) 0POP05-EO-EO00 and determines: RO will announce status of
- Reactor is tripped immediate action steps as
- Turbine is tripped he/she performs them.
- SI not actuated or required BOP Operator will monitor the plant and make an announcement of the Reactor trip.
ALL Recognize ESF DG 11 is running The Crew may perform these (CT-9) without cooling water and perform the actions at any time the following: condition is recognized and
- Attempt to start ECW Pump 1A must be performed prior to
SRO Directs/ensures the immediate actions of CIP will have crew isolate EO00, Reactor Trip/SI have been Main Steam due to the loss of completed by performing a procedure the secondary.
read through of them.
SRO Enters and directs the actions of 0POP05- This transition is based on (continuous) EO-ES01, Reactor Trip Response. Safety Injection not being actuated or required.
BOP CHECK RCPs - ANY RUNNING (Step 1.a)
NO RCPs will be running but the steam dumps are NOT available as well due to the LOOP.
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 15 of 22 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 4 & 5 Event
Description:
Loss of Offsite Power causes a Reactor Trip and ECW Pump 1A fails to re-start on the LOOP forcing the crew to secure ESF DG #11 Time Position Required Operator Actions Notes RO MONITOR RCS Temperatures - (Step1.b)
- WITHOUT ANY RCP RUNNING, Event #6 may be triggered at RCS TCOLD STABLE AT OR the discretion of the Lead TRENDING TO 567°F Examiner provided ESF DG RNO 11 has been secured.
IF temperature GREATER THAN 567°F (NOTE: the event is set on a AND rising, THEN: ten minute timer from the time
- IF condenser NOT available, THEN of the LOOP)
ENSURE SG PORVs controlling temperature in AUTO. RCS temperature will likely be rising after the LOOP. SG A
& B PORVs will have to be controlled in manual due to no power on A & B ESF Busses.
BOP CHECK FW Status: (Step 2.a, b & c)
- CHECK RCS TAVG - LESS THAN All valves should be closed 574°F and the SGFPTs will already
o FWIVs - CLOSED o FWIBs - CLOSED o FW preheater bypass valves -
CLOSED o FW regulating valves - CLOSED o Low Power FW regulating valves
- CLOSED
GREATER THAN OR EQUAL TO Only AFW flow is available.
Three (3) SGs:
- AFW flow RO VERIFY CONTROL Rods Fully Inserted (Step 4)
- All rod bottom lights - LIT
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 16 of 22 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 4 & 5 Event
Description:
Loss of Offsite Power causes a Reactor Trip and ECW Pump 1A fails to re-start on the LOOP forcing the crew to secure ESF DG #11 Time Position Required Operator Actions Notes RO/BOP CHECK STBY DG Status: (Step 5)
(CT-9)
- STBY DG - RUNNING If not already performed,
- VERIFY ECW to STBY DG Crew will attempt to start RNO ECW Pump 1A and then If ECW can NOT be established to the secure ESF DG 11.
running STBY DG, then TRIP the affected STBY DG.
RO CHECK Pressurizer Level CONTROL: (Step 6)
- Pressurizer level - GREATER THAN If not already done, Event #6
- 17% is triggered here.
- VERIFY charging - IN SERVICE (NOTE: the event is set on a
- CHECK RCP seal injection flow - ten minute timer from the time
- NORMAL of the LOOP)
- VERIFY letdown - IN SERVICE
- Pressurizer level trending to 25%
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 17 of 22 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event
Description:
ESF DG #13 trips. Crew will enter 0POP05-EO-EC00, Loss of All AC Power.
Time Position Required Operator Actions Notes ALL Recognize all AC ESF Busses are de- Entry conditions for energized 0POP05-EO-EC00 SRO Enters and directs the actions of 0POP05-(continuous) EC-EC00, Loss of All AC Power.
RO Completes immediate actions of 0POP05- (Steps 1 & 2)
EO-EC00 and determines:
- Reactor is tripped
- Turbine is tripped SRO Directs/ensures the immediate actions of EC00, Loss of All AC Power, have been completed by performing a procedure read through of them.
RO ESTABLISH RCP Seal Injection Flow: (Steps 3.a - 3.g)
(CT
- CHECK power available to PDP EC00-H)
- MONITOR VCT level - GREATER THAN 3%
- MONITOR RCP seal 1 inlet and lower seal water bearing temperatures on Plant Computer display RC-010 - ALL LESS THAN 230°F
- OPEN PDP recirculation valve to 100%
- START PDP
- MONITOR seal water inlet and lower seal water bearing temperatures. (Plant computer RC-010)
- PERFORM the following:
o Slowly CLOSE PDP recirculation valve to obtain a cooldown rate LESS THAN 1°F PER MINUTE o WHEN seal water inlet temperature LESS THAN 135°F, THEN ESTABLISH seal injection flow of between 6 and 8 gpm
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 18 of 22 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event
Description:
ESF DG #13 trips. Crew will enter 0POP05-EO-EC00, Loss of All AC Power.
Time Position Required Operator Actions Notes RO/BOP DISPATCH operator to open RWST to (Step 3.h) charging pump suction isolation valve "1(2)-CV-MOV-0112C" RO/BOP DISPATCH operator to close at least one of (Step 3.i) the VCT outlet isolation valves
- "1(2)-CV-MOV-0112B"
- Pressurizer PORVs - CLOSED
- Letdown orifice header isolation valve
- CLOSED
- DISPATCH operator to close the RCP seal return OCIV o "1(2)-CV-MOV-0079" BOP VERIFY AFW Flow - GREATER THAN (Step 5) 576 GPM
- AFW pump 14(24) - IN SERVICE
- ESTABLISH Cross Connections Of Intact SG(s) While Maintaining Flow GREATER THAN 576 GPM SRO/BOP TRY TO Restore Power To Any AC ESF (Step 6)
(RNO)
- ENERGIZE AC ESF bus from the (RNO Step 6.b.1 & 2) emergency transformer per ADDENDUM 1 SRO/BOP Verify power available from the emergency (Addendum 1 Step 1) transformer.
SRO/BOP OPEN feeder breakers from normal power (Addendum 1 Step 2) source to deenergized ESF busses: Crew should energize Train E1C(E2C) C ESF Bus
- "STBY BUS 1H(2H) TO XFMR E1C(E2C) BKR SW - NORM"
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 19 of 22 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event
Description:
ESF DG #13 trips. Crew will enter 0POP05-EO-EC00, Loss of All AC Power.
Time Position Required Operator Actions Notes SRO/BOP OPEN motor operated disconnects from (Addendum 1 Step 3) normal power source to deenergized ESF busses:
E1C(E2C)
- "STBY BUS 1H(2H) TO XFMR E1C(E2C) DISC SW - NORM" SRO/BOP VERIFY OPEN emergency feeder breakers (Addendum 1 Step 4) from 1L(2L) to ESF busses:
E1C(E2C)
- "EMER BUS 1L(2L) TO XFMR E1C(E2C) BKR SW - EMER" SRO/BOP CLOSE motor operated disconnects from (Addendum 1 Step 5) emergency bus 1L(2L) to one deenergized ESF bus:
E1C(E2C)
- "EMER BUS 1L(2L) TO XFMR E1C(E2C) DISC SW - EMER" SRO/BOP CLOSE emergency transformer feeder (Addendum 1 Step 6) breaker to emergency bus 1L(2L)
- "EMER XFMR TO BUS 1K/1L(2K/2L) SPLY" SRO/BOP CLOSE emergency feeder breakers from (Addendum 1 Step 7) emergency bus 1L(2L) to energize desired ESF transformer:
- "EMER BUS 1L(2L) TO XFMR E1C(E2C) BKR SW - EMER" SRO/BOP CLOSE supply breaker from ESF (Addendum 1 Step 8) transformer to ESF bus SRO/BOP Manually ENERGIZE AC ESF bus. (Addendum 1 Step 9)
ADDENDUM 4, VITAL DC BUS Addendum 4 would not MONITORING - INITIATED have been initiated.
(RNO)
Return to procedure step 6.b.
SRO/BOP CHECK AC ESF busses - AT LEAST (Step 6.b)
ONE ENERGIZED
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 20 of 22 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event
Description:
ESF DG #13 trips. Crew will enter 0POP05-EO-EC00, Loss of All AC Power.
Time Position Required Operator Actions Notes SRO/BOP START applicable ECW pump (Step 6.c)
Terminate Scenario
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 21 of 22 CRITICAL TASK
SUMMARY
SAT/
POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA UNSAT ALL CT-9 Manually Trip Diesel Manually Trip Diesel Generator Generator prior to an automatic 11 Diesel Generator Trip RO EC00-H Establishes seal injection flow Manually start the PDP and align prior to #1 seal inlet and lower seal injection during a loss of seal seal water bearing injection event. temperatures exceeding 230°F BOP CT-24 Energize at least one AC Energize Train C ESF 4.16KV Bus emergency bus before from the Emergency Transformer. transition out of EO00, unless the transition is to EC00, in which case the critical task must be performed before placing safeguards equipment handswitches in the PTL position
LOT 21 NRC OP-TEST SCENARIO #2 Rev 0 Page 22 of 22 TURNOVER INFORMATION Reactor Power is at 100%.
- The Crew is to remove Train C FHB HVAC Supply and Exhaust from service and place Train B in service.
- Cycle Burnup is 150 MWD/MTU. (BOL)
- On the previous shift, RCS dilutions were being performed about every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with 10 gallons of makeup water.
- Boric Acid Tank A is at 7315 ppm and B is at 7309 ppm.
- No liquid waste discharges are in progress or planned.
- No personnel are in containment.
- FHB Truck Bay doors are closed.
LCO Actions:
ESF DG 12 - TS 3.8.1.1 Action b and d. 0PSP03-EA-0002, ESF Power Availability, was completed 30 minutes ago. Action d was entered in the log 45 minutes ago as SAT.
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 1 of 28 LOT 21 NRC EXAM SIMULATOR OPERATING TEST SCENARIO #3 Revision 0 Week of 09/27/2017
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 2 of 28 SCENARIO OUTLINE Facility: South Texas Project Scenario No.: 3 Op-Test No.: LOT 21 NRC Examiners: Operators:
Initial Conditions:
- Unit 1 is at 100% Reactor Power. BOL. (IC #190)
Turnover:
Event No. Malf. No. Event Type* Event Description 1 04-01-01 RO (C) Component Cooling Water Pump 1A Sheared Shaft.
(0 min) SRO (C, TS) 1 2 05-12-03 BOP (I)
(20 min) SRO (I, TS) SG 1C Narrow Range Level Transmitter, LT-0539, fails high.
1 3 11-01-07 RO (R) An Open Loop System leak requires the Crew to perform a load (45 min) BOP (R) reduction.
0.063 SRO (R) 4 02-01-02 ALL (M) SBLOCA on LOOP B Cold Leg. (SBLOCA and LBLOCA were (55 min) both on LOT 19 exam but they were in different scenarios.)
.005 (Critical Task) 5 50-KA-05 BOP (C) CCW Pump 1B fails to Auto start and CCW fails to transfer to the (N/A) SRO (C) RCFC coolers on Train B. Operator will manually start CCW (1) Pump 1B and align CCW to RCFC coolers if RCB temperature 116°F. (Initial condition of Lesson Plan)
(Critical Task) 6 02-01-02 ALL (M) LBLOCA on LOOP B Cold Leg. (SBLOCA and LBLOCA were (N/A) both on LOT 19 exam but they were in different scenarios.)
0.4 (Critical Task)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor.
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 3 of 28 SCENARIO MISCELLANEOUS INFORMATION INSTRUCTOR NOTES:
Refer to the Instructor Guide for directions on Simulator Setup, Expected Booth Communications and Expected Booth Actions.
CRITICAL PARAMETERS:
The following parameters may be of value in evaluating crew performance and should be automatically recorded during the scenario. Once the scenario is complete for each crew, printout the Critical Parameters and label the printout with date, time, Crew # and scenario #.
- RCS Wide Range pressure
- RCP 1A breaker position
- CS Pump 1A and 1B breaker position
- MAX QUAD T/C average OPERATOR ACTIONS TABLE NOTES:
- 1. Critical Tasks are indicated by "C" in the position column and indicated in bold type.
- 2. Actions required throughout the event are indicated as "(continuous)" in the position column.
- 3. Shaded cells indicate procedural entry points.
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 4 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 1 Event
Description:
Component Cooling Water Pump 1A Sheared Shaft.
Time Position Required Operator Actions Notes RO Acknowledges and announces annunciator 2M03/E-5, CCW HX 1A OUTL PRESS LO and then references the annunciator response procedure.
RO IF CCW header pressure decreased to 76 (ARP Step 1 and sub steps) psig, THEN perform the following: CCW Pump 1C will auto start
- ENSURE the standby CCW train after a time delay.
running per 0POP02-CC-0001, Component Cooling Water. The crew will stop CCW
- ENSURE the standby ECW train Pump 1A running per 0POP02-EW-0001, The crew will place the CCW Essential Cooling Water Operations Mode Select Switch for Train
- STOP CCW Train A per 0POP02- B in STANDBY CC-0001, Component Cooling Water The crew will refer to the
- STOP ECW Train A per 0POP02-standard operating EW-0001, Essential Cooling Water procedures to align and Operations secure equipment as needed.
- PLACE the remaining ECW train in standby per 0POP02-EW-0001, Essential Cooling Water Operations
- PLACE the remaining CCW train in standby per 0POP02-CC-0001, Component Cooling Water SRO TAKE appropriate action per Technical Event #2 can occur once the Specification 3.7.3, 3.3.3.5, 3.4.1.1, SRO has addressed Tech 3.4.1.2, 3.4.1.3, 3.4.1.4.1, 3.4.1.4.2, 3.5.2, Specs for CCW Pump 1A.
3.5.3.1, 3.5.6, 3.6.2.3 and TRM 3.1.2.1 and 3.1.2.2.
Most limiting action is :
Within 7 days restore at least three loops to OPERABLE status or apply the requirements of the CRMP, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. (TS 3.7.3, 3.5.2, 3.5.6 and 3.6.2.3 are applicable.)
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 5 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 2 Event
Description:
SG 1C Narrow Range Level Transmitter, LT-0539, fails high.
Time Position Required Operator Actions Notes BOP Acknowledges and announces the BOP uses annunciator following annunciator from 06M4: response procedures but will also recognize the need to
- SG 1C STM/FW FLOW MSMTCH perform immediate actions.
SRO/BOP Determines SG 1C Controlling Narrow Failed Channel is FW-LT-Range Level Channel LT-0539 has failed 0539..
high.
Immediate Action - BOP Performs immediate actions of 0POP04- takes Manual control of SG FW-0001: 1C MFRV.
- PLACE any SG Feedwater Regulating Valve(s) not properly responding in MANUAL AND ADJUST as necessary to restore affected SG NR level(s) to between 68% and 74%.
SRO Directs actions of 0POP04-FW-0001, Loss (continuous) of Steam Generator Level Control.
BOP CHECK SG Feedwater Regulating (Step 1.0)
Valve(s) - RESPONDING IN Should already have the AUTOMATIC affected MFRV in manual.
BOP CHECK SGFP Speed Controllers - (Step 2.0)
RESPONDING IN AUTOMATIC BOP CHECK Main Feedwater Regulating (Step 3.0)
Valves:
- CHECK Main Feedwater Regulating Valve(s) - IN SERVICE
- CHECK Main Feedwater Regulating Valve(s) - ANY IN MANUAL
- CHECK Affected Main Feedwater Regulating Valve(s) - RESPONDING IN MANUAL BOP CHECK Low Power Feedwater Regulating (Step 4.0)
Valves: LPFRVs are not in service.
SRO/BOP CHECK SGFP Master Speed Controller - (Step 5.0)
IN MANUAL Controller should be in Auto and proceed to step 7.0
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 6 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 2 Event
Description:
SG 1C Narrow Range Level Transmitter, LT-0539, fails high.
Time Position Required Operator Actions Notes BOP CHECK Individual SGFP Speed (Step 7.0)
Controllers - ANY IN MANUAL Controllers should be in Auto and proceed to step 9.0 BOP MONITOR Feedwater/Steam Header DP- (Step 9.0)
GREATER THAN OR EQUAL TO DP REQUIRED BY Addendum 1 OR SGFP Master Speed Controller At 100%
BOP RESTORE Affected SG NR Level(s) To (Step 10.0)
Between 68% And 74%
BOP MONITOR SG NR Levels - GREATER (Step 11.0)
THAN 20%
BOP MONITOR SG NR Levels - LESS THAN (Step 12.0) 87.5%
BOP CHECK SG NR Level Indicators - ALL (Step 13.0)
OPERABLE Selects LT-0573 for control.
RNO PERFORM the following: Annunciator window 6M03
for affected SG(s) level control.
- CHECK status of "QDPS ALARM SGWLCS" Annunciator Lampbox 6M03, Window A-8.
- IF Annunciator Lampbox 6M03, Window A-8 is illuminated, THEN DETERMINE the alarming channels(s) using the QDPS DETAIL DATA Menu, Page 5 display.
BOP CHECK Feedwater Flow Transmitters - (Step 14.0)
ALL OPERABLE BOP CHECK Steam Flow Transmitters - ALL (Step 15.0)
OPERABLE BOP CHECK Steam Pressure Transmitters - (Step 16.0)
ALL OPERABLE BOP CHECK SG NR Levels - BETWEEN 68% (Step 17.0)
And 74%
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 7 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 2 Event
Description:
SG 1C Narrow Range Level Transmitter, LT-0539, fails high.
Time Position Required Operator Actions Notes BOP CHECK Main Feedwater Regulating And (Step 18.0)
Low Power Feedwater Regulating Valves Automatic Control - OPERABLE BOP CHECK Main Feedwater Regulating OR (Step 19.0)
Low Power Feedwater Regulating Valve(s)
- IN AUTO (RNO)
WHEN SG levels return to between 68%
and 74%, THEN PERFORM the following:
- MONITOR proper operation of Feedwater Regulating Valve(s) in Auto.
BOP CHECK SGFP Master Speed Controller - (Step 20.0)
IN AUTO SRO TAKE Appropriate Actions Per Technical (Step 21.0)
Specifications.
Most Limiting Action:
- TS 3.3.1.14 Steam Generator Water Level Low-Low Action 6 Place the failed channel in the tripped condition within
- TS 3.3.2.5.b. Steam Generator Water 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. (See full action on Level HI-HI P-14 Action 20 next page.)
- TS 3.3.2.6.d. Steam Generator Water Event #3 may be triggered Level Low-Low AFW Actuation after the SRO refers to Tech Action 20 Specs.
SRO NOTIFY I&C To Place The Affected (Step 22.0)
Channel In Trip Or Bypass. REFER TO Addendum 2, Procedure List For The Appropriate Procedure SRO INITIATE Corrective Actions For Failed (Step 23.0)
Component With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
- a. For Functional Units with installed bypass test capability, the inoperable channel may be placed ln bypass, and must be placed in the tripped condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 8 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event
Description:
An Open Loop System leak requires the Crew to perform a load reduction.
Time Position Required Operator Actions Notes BOP Acknowledges/announces annunciator 09M1/F-8, BASEMENT SHELTER PANEL TRBL, and dispatches an operator to investigate.
SRO Enters and directs action of 0POP04-OC- Reports from the field will be (continuous) 0001, Loss of Open Loop Auxiliary a low Open Loop Header Cooling Water. pressure alarm on the local panel and water on the 29 TGB southwest corner.
BOP CHECK OL-ACW Pump Status - ANY (Step 1)
RUNNING RO/BOP DIRECT MAB Operator To Secure Any (Step 2)
Liquid Rad Waste Discharge
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 9 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event
Description:
An Open Loop System leak requires the Crew to perform a load reduction.
Time Position Required Operator Actions Notes BOP MONITOR OL-ACW Pressure - (Step 3)
GREATER THAN 68 PSIG OL-ACW pressure will be
PRESS
- Plant Computer Point P6700 (RNO)
Perform the following:
- Ensure Standby OL-ACW pump running
- IF OL-ACW pressure remains LESS THAN OR EQUAL to 68 psig, THEN:
- CLOSE chiller condenser flow valves on idle MAB and RCB chillers as needed to raise OL-ACW pressure per SM/US direction.
- ADJUST OL-ACW flows to components at the Shift Manager/Unit Supervisor discretion. REFER TO Addendum 2.
- IF OL-ACW pressure remains LESS THAN OR EQUAL to 68 psig, THEN:
- SECURE in-service MAB and RCB chillers AND CLOSE chiller condenser flow valves as needed to raise OL-ACW pressure per SM/US direction.
- IF only one OL-ACW pump running AND pressure can NOT be maintained greater than 68 psig, THEN DISPATCH Operator to throttle OL-ACW pump discharge valve to maintain 80 to 90 psig on pump discharge pressure indicator.
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 10 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event
Description:
An Open Loop System leak requires the Crew to perform a load reduction.
Time Position Required Operator Actions Notes BOP DISPATCH Operator To Check OL- (Step 4)
ACW System Inside Protected Area For The leak will be upstream of Leakage - NO LEAKAGE DETECTED the CL-ACW SW/FW Heat (RNO) Exchangers. The leak will not
- IF a CL-ACW SW/FW Heat affect the ability of the closed Exchanger has an OPEN LOOP leak loop system although open that effects the heat exchangers ability loop temperatures for the to cool Closed Loop, THEN GO TO SW/FW Heat Exchangers will 0POP04-AC-0003, Loss of Closed begin to rise. (See step 6.0)
Loop Auxiliary Cooling Water. The leak is upstream of
- IF a CL-ACW SW/FW Heat isolation valves and cannot be Exchanger has an OPEN LOOP leak isolated.
that DOES NOT affect the heat exchangers ability to cool Closed Loop AND it is necessary to stop the leak by isolating OPEN LOOP to the heat exchanger, THEN GO TO 0POP02- AC-0001, Open Loop Auxiliary Cooling System to isolate the effected heat exchanger.
- DIRECT Operator to isolate leak.
- SECURE any affected load(s) AND ISOLATE the leak.
- ENSURE leakage is routed to appropriate drains.
- CLOSE storm drain spill way gates as necessary.
BOP DISPATCH An Operator To CWIS To (Step 5)
Perform The Following: Seal water flow and pressure
- CHECK seal water - SUPPLIED TO will be within the required CW AND OL-ACW PUMPS range.
- CHECK OL-ACW discharge strainer OL-ACW discharge strainer DP - LESS THAN 12 PSID dp will be high. 10 psid to
- CHECK OL-ACW System for bring in alarm, but less than leakage - NO LEAKAGE 12 psid.
DETECTED
- INVESTIGATE cause of OL-ACW pump trip
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 11 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event
Description:
An Open Loop System leak requires the Crew to perform a load reduction.
Time Position Required Operator Actions Notes BOP MONITOR The Plant Computer Points - (Step 6)
ABOVE ALARM SETPOINT T6703 and T6704, OL-ACW
- T6703, OPENLP ACW HX 11(21) SW/FW Heat Exchanger OUT TEMP (Alarm 118°F) temperatures, will be trending
- T6704, OPENLP ACW HX 12(22) slowly toward the alarm set OUT TEMP (Alarm 118°F) point which requires
- T6705, OPENLP ACW SYS CHLR continuing on to step 7.
OUTL TEMP (Alarm 113°F)
- T6711, GEN HYDROGEN COOLER DISCH TEMP (Alarm 124°F)
- T6713, TURB LUBE OIL CLR ACW OUTL TEMP (Alarm 118°F)
- T6714, SGFPT L.O. ACW OUTL TEMP (Alarm 114°F)
RO CHECK Main Turbine - ONLINE (Step 7)
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 12 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event
Description:
An Open Loop System leak requires the Crew to perform a load reduction.
Time Position Required Operator Actions Notes All PERFORM A Main Turbine Load (Step 8.a)
Reduction To Clear/Prevent Computer Event #4 can occur any time Alarms And To Raise Open Loop Header after the load reduction has Pressure: commenced at the discretion
EMS Website That Load Reduction Is Commencing NOTE: The US is allowed
- DETERMINE Amount of Boric Acid discretion to Trip the reactor To Add To Reduce Reactor Power To and enter 0POP05-EO-EO00, Desired Level AND COMMENCE Reactor Trip or Safety RCS Boration Injection, if felt that the open
- CHECK Rod Control System - IN loop leak is too large.
AUTOMATIC If the decision is made to trip
- ENERGIZE Pressurizer Heaters for the Unit due to excessive boron equalization open loop leakage then, as
- NOTIFY Chemistry to PERFORM time permits, the crew would Isotopic Analysis for Iodine due to also stop all Open Loop possible Thermal Power Change Pumps and perform
>15% RATED THERMAL POWER Addendum 1 of 0POP04-OC-within A 1-Hour Period 0001, Loss of Open Loop
- PERFORM The Following To Lower Auxiliary Cooling Water.
Turbine Load:
o CHECK Main Turbine - IN THE If the crew trips the Unit then IMPULSE PRESSURE the booth operator will FEEDBACK MODE IMP IN trigger Event #4.
o REDUCE Turbine Load at a rate of less than or equal to 5% per minute using Operator Auto BOP MAINTAIN Main Generator reactive (Step 8.b) load (VARs) within the following:
- Less Than 450 MVARs
- Guidelines Of The Plant Curve Book, Figure 7.1 RO MONITOR Rod Control system (Step 8.c) responding to RCS TAVG/TREF deviation by ensuring the following:
- Control Rods are inserting AND RCS Tavg trending to within 3°F of Tref OR
- RCS Tavg within 3°F of Tref
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 13 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event
Description:
An Open Loop System leak requires the Crew to perform a load reduction.
Time Position Required Operator Actions Notes RO MAINTAIN Pressurizer Level within the (Step 8.d) following:
- Trending to Program Level OR
- At Program Level RO MAINTAIN Pressurizer Pressure within (Step 8.e) the following:
- Trending to between 2220 psig and 2250 psig OR
- Between 2220 psig and 2250 psig BOP MAINTAIN Steam Generator NR Level (Step 8.f) within the following:
- Trending to between 68% and 74%
- Between 68% and 74%
SRO REFER TO 0POP04-TM-0005, Fast (Step 8.g)
Load Reduction, for additional actions
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 14 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 4 and 6 Event 4
Description:
SBLOCA Event 6
Description:
LBLOCA Time Position Required Operator Actions Notes ALL The Crew responds to alarms and trends The RCS leak is of size that associated with a SBLOCA will require a quick determination by the crew and they may or may not initiate a manual SI prior to an automatic one.
SRO Directs a manual Safety Injection and enters 0POP05-EO-EO00, Reactor Trip or Safety Injection.
Completes immediate actions of 0POP05- 0POP05-EO-EO00, EO-EO00 and determines: Reactor Trip or Safety
- Reactor is tripped Injection Steps 1-4.
- Turbine is tripped RO will announce status of
- SI is actuated he/she performs them.
BOP Operator will monitor the plant and make an announcement of the Reactor trip.
SRO Directs/ensures the immediate actions of Before beginning the EO00, Reactor Trip/SI have been verification of immediate completed by performing a procedure read actions, the US may direct through of them. the BOP to throttle AFW flow to limit RCS cooldown.
ALL WHEN RCS pressure is less than 1430 Timing will depend on how (CT-16) psig, the crew performs the following: quickly and how much AFW
- Verifies at least one HHSI Pump is throttled.
running
Per ADDENDUM 5, VERIFICATION OF See Actions on Page 22-26.
SI EQUIPMENT OPERATION
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 15 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 4 and 6 Event 4
Description:
SBLOCA Event 6
Description:
LBLOCA Time Position Required Operator Actions Notes RO MONITOR If Containment Spray Is (Step 6)
Required: Containment pressure will
- Containment pressure GREATER be less than 9.5 psig.
THAN 9.5 PSIG (QDPS)
(RNO)
- PERFORM the following:
- CHECK Containment pressure -
18)
- "PRESS PR0934" OR
- "EXTD RNG PRESS PR9759"
- IF containment pressure HAS EXCEEDED 9.5 PSIG, THEN GO TO Step 6.b.
- IF containment pressure HAS REMAINED LESS THAN 9.5 PSIG, THEN GO TO Step 7.
RO CHECK RCP Seal Cooling: (Step 7)
- ENSURE seal injection flow between 6 RO may have to adjust seal and 13 gpm injection.
RO MONITOR RCS Temperatures (Step 8)
- WITH ANY RCP RUNNING, RCS If AFW has been properly TAVG STABLE AT OR TRENDING throttled from the original TO 567°F Reactor Trip then RCS OR temperature should be
- WITHOUT ANY RCP RUNNING, trending to 567°F.
RCS TCOLD STABLE AT OR TRENDING TO 567°F RO CHECK Pressurizer Status: (Step 9)
- PORVs CLOSED
- Normal pressurizer spray valves -
CLOSED
- Auxiliary spray valve - CLOSED
- Excess letdown isolation valves -
CLOSED
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 16 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 4 and 6 Event 4
Description:
SBLOCA Event 6
Description:
LBLOCA Time Position Required Operator Actions Notes RO MONITOR If RCPs Should Be Stopped: (Step 10)
(CT-16)
Isolation Valves - CLOSED
- Seal return isolation valves
- Containment atmosphere radiation monitor isolation valves RO CHECK If SG Secondary Pressure (Step 12)
Boundary Intact:
- CHECK pressures in all SGs -
- CONTROLLED OR RISING
- Main steamline radiation NORMAL
- CARS pump radiation NORMAL
- Containment radiation NORMAL Will not transition to a
- Containment pressure NORMAL Functional Recovery
- Containment wide range water level Procedure until Addendum NORMAL 5 is complete.
(RNO)
GO TO 0POP05-EO-EO10, LOSS OF REACTOR OR SECONDARY COOLANT, Step1.
- MONITOR Critical Safety Functions.
- WHEN Addendum 5 of this procedure is complete, THEN Functional Restoration Procedures may be IMPLEMENTED.
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 17 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 4 and 6 Event 4
Description:
SBLOCA Event 6
Description:
LBLOCA Time Position Required Operator Actions Notes BOP Completes 0POP05-EO-EO00, Addendum Will not transition to a
- 5. Functional Recovery Procedure until Addendum 5 is complete.
SRO Informs crew of transition to 0POP05-EO-(continuous) EO10, Loss of Reactor or Secondary Coolant.
RO MONITOR If RCPs Should Be Stopped: (Step 1)
- STOP all RCPs
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 18 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 4 and 6 Event 4
Description:
SBLOCA Event 6
Description:
LBLOCA Time Position Required Operator Actions Notes BOP DEPRESSURIZE Intact SGs To 1000 (Step 2)
- CHECK pressurizer pressure LESS lower steam generator THAN 1985 PSIG pressures prior to adjusting
- CHECK condenser - AVAILABLE If Main Steam Isolation has
- CHECK steam dump in steam pressure occurred then the crew will mode use the SG PORVs to (RNO) perform the SG
- PLACE steam dump controller in depressurization if needed.
MANUAL with zero demand.
- PLACE steam dump "MODE SEL" switch in the STEAM PRESS position.
- GO TO Step 2.i.
(Back to A/ER)
- PLACE steam dump "INTLK SEL" switches to BYPASS INTERLCK.
- ENSURE "HDR PRESS CONT PK-0557" in AUTO
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 19 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 4 and 6 Event 4
Description:
SBLOCA Event 6
Description:
LBLOCA Time Position Required Operator Actions Notes BOP MONITOR If SG Secondary Pressure (Step 3)
Boundary Intact:
- CHECK pressures in all SGs o CONTROLLED OR RISING o GREATER THAN CONTAINMENT PRESSURE RO RESET SI (Step 4)
RO RESET ESF Load Sequencers (Step 5)
Event #6 will occur approximately 1 minute after sequencers are reset RO RESET Containment Isolation Phase A and (Steps 6 and 7)
B BOP MONITOR INTACT SG Levels: (Step 8)
- NR levels GREATER THAN 14%
[34%]
- CONTROL AFW flow to maintain NR levels BETWEEN 22% [34%] and 50%
ALL Recognize that an ORANGE or possibly a The INTEGRITY Critical RED path exists for the INTEGRITY Safety Function is time Critical Safety Function dependent and may or may not develop. If it does the following will be performed.
SRO Completes the EOP step in progress (ORANGE Path) or Immediately stops EOP in progress (RED Path), then transitions to and directs the actions of 0POP05-EO-FRP1, Response to Imminent Pressurized Thermal Shock Condition.
RO CHECK RCS pressure - GREATER (Step 1)
THAN 415 PSIG The LBLOCA will cause (RNO) RCS pressure to go lower IF LHSI pump flow GREATER THAN than 415 psig.
500 GPM, THEN RETURN TO procedure step in effect.
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 20 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 4 and 6 Event 4
Description:
SBLOCA Event 6
Description:
LBLOCA Time Position Required Operator Actions Notes NOTE: If the crew had to enter 0POP05-EO-FRP1 prior to resetting the load sequencers in 0POP05-EO-EO10, which initiates the LBLOCA, then they will step through 0POP05-EO-FRP1.
Step 9 will reset the load sequencers and then the LBLOCA will be initiated.
ALL Recognize that an ORANGE path exists for Greater than 9.5 psig in the Containment Critical Safety Function containment represents and ORANGE path.
SRO Completes the EOP step in progress, then If 0POP05-EO-FRP1 was transitions to and directs the action of entered early then the 0POP05-EO-FRZ1, Response to High transition to 0POP05-EO-Containment Pressure. FRZ1 will be delayed until 0POP05-EO-FRP1 is completed.
RO VERIFY Containment Spray - (Step 1)
ESTABLISHED Go to Step 2
- Containment Pressure LESS THAN 56.5 PSIG. Scenario can be terminated
- At least one Containment Spray pump - here if Crew started two CS RUNNING Pumps.
o Discharge valve OPEN o FLOW indication RO VERIFY Containment Isolation Phase A (Step 2)
Valves-CLOSED, REFER TO ADDENDUM 1, PHASE A ISOLATION VERIFICATION.
RO VERIFY Containment Ventilation (Step 3)
Isolation:
- Containment atmosphere radiation a.
monitor isolation valves - CLOSED
- Normal purge supply and exhaust fans
- STOPPED
- Supplementary purge supply and exhaust fans - STOPPED
- Purge dampers - CLOSED
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 21 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 4 and 6 Event 4
Description:
SBLOCA Event 6
Description:
LBLOCA Time Position Required Operator Actions Notes RO CHECK If Containment Spray Is Required: (Step 4)
(CT-3)
- Containment pressure - HAS Terminate the scenario EXCEEDED 9.5 PSIG
- STOP ALL RCPs
- VERIFY containment spray pumps -
RUNNING (RNO) o Start a maximum of two containment spray pumps.
- VERIFY containment spray valve alignment - PROPER EMERGENCY ALIGNMENT o Containment sump to SI suction header - CLOSED o RWST to SI suction header isolation - OPEN o Containment spray pump discharge isolation - OPEN
- VERIFY containment isolation phase B valves - CLOSED o "INL OCIV MOV-0318" o "INL OCIV MOV-0291" o "OUTL ICIV MOV-0542" o "OUTL ICIV MOV-0403" o "OUTL OCIV MOV-0404" o "OUTL OCIV FV-4493"
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 22 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 5 and Addendum 5 actions Event
Description:
CCW Pump 1B fails to Auto start and CCW fails to transfer to the RCFC coolers on Train B. Operator must manually start CCW Pump 1B and, if RCB temperature 116°F, manually align CCW to RCFC coolers.
Time Position Required Operator Actions Notes BOP VERIFY FW isolation: 0POP05-EO-EO00, Reactor
- SGFPTs - TRIPPED Trip or Safety Injection,
- SU SGFP - TRIPPED Addendum 5, Verification of
- VERIFY the following valves - Equipment Operation.
CLOSED (Add 5 Step 1) o FWIVs This addendum is performed o FWIBs in parallel with Steps 5 to 14 o FW preheater bypass valves of 0POP05-EO-EO00, o FW regulating valves Reactor Trip or Safety o Low power FW regulating valves Injection.
o SG blowdown isolation valves o SG sample isolation valves BOP CHECK if main steamline should be (Add 5 Step 2) isolated:
- CHECK for any of the following conditions:
o Containment pressure -
GREATER THAN OR EQUAL TO 3 PSIG OR o SG pressure (without low steamline pressure SI blocked) -
LESS THAN OR EQUAL TO 735 PSIG OR o SG pressure (with low steamline pressure SI blocked) -
LOWERING AT A RATE GREATER THAN OR EQUAL TO 100 PSI/SEC, BY OBSERVANCE OF THE STEAMLINE PRESSURE RATE BISTABLES BOP VERIFY AFW system status: (Add 5 Step 3) o Motor-driven pump -
RUNNING o Turbine-driven pump -
RUNNING
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 23 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 5 and Addendum 5 actions Event
Description:
CCW Pump 1B fails to Auto start and CCW fails to transfer to the RCFC coolers on Train B. Operator must manually start CCW Pump 1B and, if RCB temperature 116°F, manually align CCW to RCFC coolers.
Time Position Required Operator Actions Notes BOP VERIFY AFW valve alignment - (Add 5 Step 4)
PROPER EMERGENCY ALIGNMENT BOP VERIFY total AFW Flow - GREATER (Add 5 Step 5)
THAN 576 GPM BOP VERIFY containment isolation phase A: (Add 5 Step 6)
- Phase A - ACTUATED
- Phase A valves - CLOSED, REFER TO ADDENDUM 1, PHASE A ISOLATION VERIFICATION BOP VERIFY ECW status: (Add 5 Step 7)
- ECW pumps - RUNNING
- ECW pump discharge isolation valves
- OPEN BOP VERIFY CCW pumps - RUNNING (Add 5 Step 8)
(CT-8) RNO Manually start CCW Pump 1B BOP VERIFY RCFC status: (Add 5 Step 9)
- RCFCs - RUNNING Will need to manually start
- Cooling water - TRANSFERRED TO CCW Pump 1B and manually CCW transfer Train B RCFC RNO cooling to CCW
- IF RCFC inlet temperatures are LESS RCFC inlet temperature will THAN OR EQUAL TO 116°F, depend on how long it takes THEN manually TRANSFER cooling the operator to reach this to CCW. step.
- IF RCFC inlet temperatures are GREATER THAN 116°F, THEN CONTACT the TSC prior to transferring cooling.
BOP VERIFY SI pump status: (Add 5 Step 10)
- HHSI pumps - RUNNING
EMERGENCY ALIGNMENT
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 24 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 5 and Addendum 5 actions Event
Description:
CCW Pump 1B fails to Auto start and CCW fails to transfer to the RCFC coolers on Train B. Operator must manually start CCW Pump 1B and, if RCB temperature 116°F, manually align CCW to RCFC coolers.
Time Position Required Operator Actions Notes BOP VERIFY SI flow: (Add 5 Step 12)
- HHSI pump flow - INDICATED be greater than 415 psig so
PSIG (RNO)
- GO TO Step 13 of this Addendum.
BOP VERIFY containment ventilation (Add 5 Step 13) isolation: Event #7 failed the
- Containment atmosphere radiation Containment atmosphere monitor isolation valves - CLOSED radiation monitor isolation
- Normal purge supply and exhaust fans valves open. The SRO/RO
- STOPPED may have already closed the
- Supplemental purge supply and valves when the BOP reaches exhaust fans - STOPPED this step, otherwise the BOP
- Purge Dampers - CLOSED will be required to close the valves now.
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 25 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 5 and Addendum 5 actions Event
Description:
CCW Pump 1B fails to Auto start and CCW fails to transfer to the RCFC coolers on Train B. Operator must manually start CCW Pump 1B and, if RCB temperature 116°F, manually align CCW to RCFC coolers.
Time Position Required Operator Actions Notes BOP VERIFY ventilation actuation: (Add 5 Step 14)
- Control room HVAC - OPERATING IN EMERGENCY RECIRC
- EAB HVAC - OPERATING IN EMERGENCY RECIRC
- FHB HVAC - OPERATING IN EMERGENCY MODE
- FHB Exhaust Fans - ONLY TWO TRAINS OPERATING o Exhaust booster fans o Main exhaust fans (RNO)
- PERFORM the following:
o IF three trains FHB exhaust fans running, THEN PLACE one train FHB exhaust fans in PULL TO LOCK.
(Back to A/ER)
- SECURE one FHB filter train by PERFORMING the following:
o PLACE the outlet damper Controller in manual o Manually close the outlet damper o VERIFY proper operation of filter train in service
- Essential chilled water pumps -
RUNNING
- Essential chillers - RUNNING
- ECCS pump room fan coolers -
RUNNING
- AFW pump cubicle fans - RUNNING
- FHB truck bay doors - CLOSED BOP NOTIFY Unit Supervisor that Addendum (Add 5 Step 15) 5 is COMPLETE
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 26 of 28 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 5 and Addendum 5 actions Event
Description:
CCW Pump 1B fails to Auto start and CCW fails to transfer to the RCFC coolers on Train B. Operator must manually start CCW Pump 1B and, if RCB temperature 116°F, manually align CCW to RCFC coolers.
Time Position Required Operator Actions Notes SRO IMPLEMENT Functional Restoration (Add 5 Step 16)
Procedures as required SRO RETURN TO procedure step in effect. (Add 5 Step 17)
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 27 of 28 CRITICAL TASK
SUMMARY
SAT/
POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA UNSAT ALL CT-8 Manually start two CCW Manually start two CCW Pumps Pumps to provide adequate to provide adequate cooling to cooling water for the operating safeguards trains safeguards trains before transition past 0POP05-EO-EO00, Addendum 5, Step 8 ALL CT-16 Trip all RCPs so that an Manually trip the Reactor Coolant Orange Path on Core Cooling Pumps (CET temperatures >707°F) does not occur when forced circulation in the RCS stops.
ALL CT-3 Manually initiate at least one Manually actuate Containment train of Containment Spray Cooling flow prior to completion of step 4 of 0POP05-EO-FRZ1.
LOT 21 NRC OP-TEST SCENARIO #3 Rev 0 Page 28 of 28 TURNOVER INFORMATION
- Reactor Power is at 100%.
- ESF DG #12 was just tagged out for an emergent condition. Return to service of ESF DG #12 is unknown.
- Cycle Burnup is 150 MWD/MTU. (BOL)
- On the previous shift, RCS dilutions were being performed about every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with 10 gallons of makeup water.
- Boric Acid Tank A is at 7315 ppm and B is at 7309 ppm.
- No liquid waste discharges are in progress or planned.
- No personnel are in containment.
- FHB Truck Bay doors are closed.
LCO Actions:
ESF DG 12 - TS 3.8.1.1 Action b and d. 0PSP03-EA-0002, ESF Power Availability, was completed 30 minutes ago. Action d was entered in the log 45 minutes ago as SAT.
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 1 of 30 LOT 21 NRC EXAM SIMULATOR OPERATING TEST SCENARIO #4 Revision 0 Week of 09/27/2017
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 2 of 30 SCENARIO OUTLINE Facility: South Texas Project Scenario No.: 4 Op-Test No.: LOT 21 NRC Examiners: Operators:
Initial Conditions:
- Unit 1 is at 100% Reactor Power. BOL. (IC #190)
Turnover:
- The Crew will start CW Pump #13 and secure CW Pump #14.
Event No. Malf. No. Event Type* Event Description 1
(0 min) N/A BOP (N) Start CW Pump #13 and Secure CW Pump #14.
2 (20 min) 02-19-03 RO (I) Controlling Channel of Pressurizer Pressure, PT-0457, fails low.
SRO (I, TS) (LOT 19 and LOT 20 however, in both cases PT-0457 failed 0.0 high.)
3 POSBBARG (N/A) 22904TCC SRO (TS) PZR PORV isolation valve, RC-MOV-0001B, losses control 1 power. (This malfunction will be inserted 1 minute after PT-0457 fails high.)
4 HCPD9623R (35 min) EV RO (C) CRDM Vent Fan 11A Trouble.
1 SRO (C) 5 08-28-01 (45 min) 1 BOP (C) LPHD Pump #11 Trip.
SRO (C) 6 (60 min) 05-03-04 ALL (M) SG 1D Tube Rupture. (LOT 19 and LOT 20 however, in both cases the SG was ruptured and faulted.) (~450 GPM & Ramps 0.44 in over 2 minute period.)
(3 Critical Tasks) 7 (N/A) Manually BOP (C) SG 1D FWIV fails to close on the Feedwater Isolation Signal.
Inserted (Integrated with SGTR) 8 PV7485 (N/A) PV7489 BOP (C) Group 1 Steam Dumps fail to open. Crew will use SG PORVs to PV7493 SRO (C) perform SGTR cooldown. (Initial condition of Lesson Plan) 0.0
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor.
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 3 of 30 SCENARIO MISCELLANEOUS INFORMATION INSTRUCTOR NOTES:
Refer to the Instructor Guide for directions on Simulator Setup, Expected Booth Communications and Expected Booth Actions.
CRITICAL PARAMETERS:
The following parameters may be of value in evaluating crew performance and should be automatically recorded during the scenario. Once the scenario is complete for each crew, printout the Critical Parameters and label the printout with date, time, Crew # and scenario #.
- RCS Wide Range Pressure
- SG 1D Steam Pressure
- HHSI Pumps Breaker position OPERATOR ACTIONS TABLE NOTES:
- 1. Critical Tasks are indicated by "C" in the position column and indicated in bold type.
- 2. Actions required throughout the event are indicated as "(continuous)" in the position column.
- 3. Shaded cells indicate procedural entry points.
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 4 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 1 Event
Description:
Start CW Pump #13 and Secure CW Pump #14.
Time Position Required Operator Actions Notes SRO Directs the BOP operator to start CW Pump #13 IAW 0POP02-CW-0001, Circulating Water System Pump Operation.
BOP VERIFY CW System has been filled per (Step 6.1)
Section 5.0. System is already running.
BOP VERIFY SEAL WATER PRESSURE (Step 6.3)
GREATER THAN 30 psig at each CW Step 6.2 is N/A. All seal water Pump. pressure greater than 30 psig except CW Pump #14.
BOP CHECK the CASING FILL/SURGE (Step 6.5)
AIR/VACUUM RELIEF VALVE for Step 6.4 is Unit 2 Only.
the CW Pumps to be started to determine if the valves are open and free moving:
CW Pump 13 1-CW-0234 BOP ENSURE Control Room handswitches (Step 6.7) for CW Pumps to be started in Step 6.6 is N/A.
NORMAL:
CW PUMP 13 BOP VERIFY blue PERM SATISFIED light (Step 6.8) for CW Pump to be started has been The blue permissive light will illuminated for GREATER THAN 2 have been lit for more than 2 minutes: minutes.
CW PUMP 13 BOP IF three CW Pumps are running, THEN (Step 6.9)
GO TO Step 6.29.
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 5 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 1 Event
Description:
Start CW Pump #13 and Secure CW Pump #14.
Time Position Required Operator Actions Notes BOP IF a fourth CW Pump is to be started, (Step 6.29)
THEN PERFORM the following:
- ENSURE NO change has been made No CW changes have been to CW System (e.g., pump starts or made yet.
stops, Waterbox valve position changes, CW Outfall vacuum breaker valve position changes) for at least 5 minutes.
- VERIFY blue PERM SATISFIED The blue permissive light will light for fourth CW Pump to be have been lit for more than 2 started has been illuminated for minutes.
GREATER THAN 2 minutes:
PUMP 13
- ENSURE the vacuum breaker isolation valve for the CW Pump to 1-CW-0350 is already closed.
be started is CLOSED: CW Pump 13 1-CW-0350
- PLACE one CW Pump Control Room handswitch in START: PUMP 13
- VERIFY locally that CW PUMP DISCHARGE MOV for CW Pump started goes FULL OPEN: CW Pump 13 1-CW-MOV-0003 BOP WHEN at least 5 minutes has elapsed (Step 6.31) since the start of the CW Pump, THEN Step 6.30 is N/A OPEN the vacuum breaker isolation Time compression can be valve for operating CW Pump: CW Pump used when the crew identifies 13 1-CW-0350 that a 5 minute wait is required.
BOP IF CW Pump 13 or 14 was started, THEN (Step 6.33)
OPEN 1-CW-0733 VACUUM 1-CW-0733 is already open BREAKER ISOLATION VALVE after since CW Pump 14 is running.
at least a 5 minute stabilization period. Step 6.32 is N/A and the rest of section 6.0 steps are N/A.
SRO Directs the BOP operator to secure CW Pump #14 IAW 0POP02-CW-0001, Circulating Water System Pump Operation.
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 6 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 1 Event
Description:
Start CW Pump #13 and Secure CW Pump #14.
Time Position Required Operator Actions Notes BOP IF a liquid radwaste discharge is in (Step 7.1) progress, THEN ENSURE discharge is Per turnover, no discharges secured approximately 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> prior to are in progress.
securing ALL CW flow.
BOP IF securing OR isolating portions of the (Step 7.2)
CW or Seal Water System for Per turnover, pump will be GREATER THAN 7 days, THEN OOS for two days.
NOTIFY Chemistry to treat the CW or Steps 7.3 and 7.4 are NA.
Seal Water System with Sodium Hypochlorite prior to securing or isolating the system.
BOP ENSURE NO change has been made to (Step 7.5.1)
CW System (e.g., pump starts or stops, This 5 minute hold should be Waterbox valve position changes, CW from when 1-CW-0350 was Outfall vacuum breaker valve position closed.
changes) for at least 5 minutes.
If it has been less than 5 minutes then time compression can be used.
BOP STOP selected CW Pump: (Step 7.5.2)
- PUMP 14 BOP ENSURE locally CW PUMP (Step 7.5.3)
DISCHARGE MOV for CW Pump stopped in Step 7.5.2 CLOSED:
- 1-CW-MOV-0004 BOP NOTIFY Chemistry of CW Pump (Step 7.5.4 configuration change in Step 7.5.2.
BOP WHEN at least 5 minutes have elapsed (Step 7.5.5) since the securing of the CW Pump, Time compression can be THEN dispatch an operator to CLOSE used when the crew identifies the vacuum breaker isolation valve for that a 5 minute wait is secured CW Pump: required.
- 1-CW-0351 Transitions to step 7.15
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 7 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 1 Event
Description:
Start CW Pump #13 and Secure CW Pump #14.
Time Position Required Operator Actions Notes BOP IF ANY CW Pump secured in this (Step 7.15)
Section is to remain available, THEN Pump is to be removed from ENSURE the blue PERM SATISFIED service for seal water work.
indication is illuminated for the affected pump(s). (Reference Addendum 1, CW Pump Start Permissive Restoration) Event #2 & 3 can occur at the discretion of the Lead Examiner.
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 8 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 2 and 3 Event
Description:
Controlling Channel of Pressurizer Pressure, PT-0457, fails low. During the channel failure PZR PORV isolation valve, RC-PCV-0001B, loses control power.
Time Position Required Operator Actions Notes RO Acknowledge and announce annunciators Annunciator list is not all on CP004 indicative of a failed inclusive.
Pressurizer pressure channel:
- PRZR PRESS DEV LO B/U HTRS ON
- PRZR PRESS LO RX TRIP ALERT
- PRZR PRESS LO SI ALERT RO Identifies the failed pressure channel as Immediate actions of PT-0457 failed low and performs the 0POP04-RP-0001 for a failed following immediate actions: low channel (RNO 1.b)
- Places Pressurizer Master Pressure Controller in MANUAL.
- Removes failed channel PT-0457 from control by selecting 455/456.
- Adjusts Pressurizer pressure Controller to control between 2220 and 2250 psig.
SRO Enters and directs the actions of 0POP04-(continuous) RP-0001, Loss of Automatic Pressurizer Pressure Control.
SRO/RO Verifies proper actions taken per Step 1 RO Checks Pressurizer Pressure Controller (Step 2) operable.
RO Checks Pressurizer PORVs closed. (Step 3)
RO CHECK Normal Pressurizer Spray (Step 4)
Valves:
- Normal Pressurizer Spray Valves -
CLOSED
- Pressurizer Spray Line temperature -
NORMAL RO CHECK Pressurizer Auxiliary Spray (Step 5)
Valve LV-3119 CLOSED RO CHECK Pressurizer Pressure - (Step 6)
GREATER THAN 2210 PSIG
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 9 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 2 and 3 Event
Description:
Controlling Channel of Pressurizer Pressure, PT-0457, fails low. During the channel failure PZR PORV isolation valve, RC-PCV-0001B, loses control power.
Time Position Required Operator Actions Notes RO CHECK Pressurizer Pressure - (Step 7)
GREATER THAN 2250 PSIG Pressure should be less than 2250 psig and the US should go to Step 11.
RO ENSURE An Operable Pressurizer (Step 11)
Pressure Channel Is Selected On The Pressurizer Pressure Recorder Selector Switch RO CHECK Pressurizer Pressure Controller (Step 12)
RC-PK-0655A - OPERABLE RO CHECK Pressurizer Pressure - (Step 13)
BETWEEN 2220 AND 2250 PSIG RO CHECK The Following: (Step 14.a - 14.e)
- Pressurizer Pressure Controller RC-PK-0655A demand signal -
INDICATING NORMAL FOR EXISTING PLANT CONDITIONS
- Pressurizer spray valves - IN AUTO
- Pressurizer heater controls - IN Event 3 - PZR PORV block AUTO valve RC-MOV-0001B will
- Pressurizer PORVs - IN AUTO have a loss of control power
- Pressurizer PORV Isolation Valves and associated BYPASS
- OPEN INOP light in.
RO PLACE Pressurizer Pressure Controller (RNO 14.f) in AUTO.
RO Pressurizer pressure being maintained - (Step 14.g)
BETWEEN 2220 AND 2250 PSIG SRO PERFORM the following: (RNO 15.a and 15.b)
- NOTIFY I&C to place the affected Channel in trip or bypass. REFER TO Addendum 1, Procedure List for the appropriate procedure.
- CHECK P-11 permissive in proper state for plant conditions per Technical Specification Table 3.3-3, Item 9.a.
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 10 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 2 and 3 Event
Description:
Controlling Channel of Pressurizer Pressure, PT-0457, fails low. During the channel failure PZR PORV isolation valve, RC-PCV-0001B, loses control power.
Time Position Required Operator Actions Notes SRO REFER TO Addendum 3 For Applicable (Step 16)
Technical Specifications Most Limiting Tech Spec action failure of PZR PT-0457:
- TS 3.3.1 action 6 - Items 8, 10 & 11
- TS 3.3.2 action 20 - Items 1E The inoperable channel may be placed in bypass, and must be placed in the tripped condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
SRO REFER TO Addendum 3 For Applicable (Step 16)
Technical Specifications Event #4 can occur after the Most Limiting Tech Spec action for loss SRO checks Tech Specs at the of control power to RC-MOV-0001B: discretion of the Lead
- TS 3.4.4 action d Examiner.
Restore Block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or close the associated PZR PORV.
If associated PZR PORV is closed restore the block valve within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
RO CHECK Reactor Coolant Pumps - ALL (Step 17)
OPERATING SRO INITIATE Corrective Action For Failed (Step 18)
Component
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 11 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 4 Event
Description:
CRDM Vent Fan 11A Trouble Time Position Required Operator Actions Notes RO Acknowledges and announces annunciator 22M1/F-2, CRDM VENT FAN TRBL.
RO CHECK the following Plant computer (22M1 - F2 Step 1) points to determine affected fan: Fan 11A computer point.
- HCPD9625, RCB HVAC CRDM VT FAN 11C RO SECURE affected fan. CRDM Vent Fan (22M1 - F2 Step 2) 11A RO START a non-affected train fan per (22M1 - F2 Step 3) 0POP02-HC-0001, Containment HVAC, within 15 minutes following performance of Step 2.
SRO Directs entry into 0POP02-HC-0001, Containment HVAC, to start CRDM Vent Fan 11C.
RO START selected CRDM vent fan(s). (0POP02-HC-0001 Step 8.1)
Train C "VENT FAN 11C HC-VFN019" Event #5 may occur at the discretion of the Lead Examiner.
RO INITIATE Condition Report for affected (22M1 - F2 Step 4) fan.
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 12 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Event
Description:
LPHD Pump #11 Trip Time Position Required Operator Actions Notes BOP Acknowledges and announces annunciator 08M3/A-4, LP HDP TRIP BOP Reports that Heater Drip Pump #11 has The ARP will direct the crew tripped. Refers to Annunciator Response to go to 0POP04-CD-0001, Procedure (ARP). Loss of Condensate Flow.
SRO Enters and directs the actions of 0POP04-CD-0001, Loss of Condensate Flow.
SRO/BOP Determines there are sufficient (Step 1)
Condensate pumps in service for the 2 are required current power level.
- ENSURE Discharge Valve Of Any (Steps 2 and 3)
Secured/Tripped Condensate Pump Is Condensate Pumps are CLOSED operating normally
- MONITOR ICS Parameters For Running Condensate Pumps:
BOP CHECK LPHD Pump status (Step 4)
- Determines LPHD Pump #11 has tripped.
- SRO Implements procedure Addendum 2.
BOP CHECK FWH 15(25) & 16(26) Strings - (Addendum 2, Step 1)
INSERVICE BOP CHECK DA Level Controller at 100% (Addendum 2, Step 2)
Demand Demand will be at 100%
BOP START Third Condensate Pump Per (Addendum 2, Step 3)
Addendum 1, Condensate Pump Start (Addendum 1, Steps 1 and 2)
That Requires Venting Prior To Start Condensate Pump 13 will be
- Checks if SGFPT SEAL WTR DP started.
LO Annunciators lit.
o If so, DA Level Control valve is throttled closed to clear SGFPT SEAL WTR DP LO alarms (3) on CP-006.
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 13 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Event
Description:
LPHD Pump #11 Trip Time Position Required Operator Actions Notes BOP VERIFY Miniflow Recirc Line Is Full (Addendum 1, Step 3)
By Dispatching An Operator To Vent The COND PUMP MINIFLOW RECIRC VENT For Pump To Be Started:
Pump 13 1-CD-0786 BOP Dispatch an operator to ENSURE 1-CD- (Addendum 1, Steps 4 and 5) 0801, COND PUMPS DISCH COMMON VENT LINE ISOL VALVE Is OPEN and to OPEN 1-CD-0802 COND PUMP 13 DISCH COMMON VENT LINE ISOL VALVE BOP START The Selected Condensate Pump: (Addendum 1, Step 6)
- COND PUMP 13 BOP Dispatch an Operator to CLOSE 1-CD- (Addendum 1, Step 7) 0802 COND PUMP 13 DISCH COMMON VENT LINE ISOL VALVE BOP PLACE DA Level Controller In Manual (Addendum 1, Step 8)
AND LOWER Demand To < 80% Will reduce the chance of a CP Bypass.
BOP OPEN Condensate PUMP DISCH (Addendum 1, Step 9)
ISOL Valve For Condensate Pump With 3 CD Pumps aligned and Started To Place Pump In Service: running there is a chance for
- PUMP 13 MOV-0088 a CP Bypass to occur.
BOP CONTROL DA Level Control Valve To (Addendum 1, Step 10)
Restore DA Level Last step of this addendum, the SRO should go to Addendum 2, Step 5.
Event #6 can occur after this point at the discretion of the Lead Examiner.
BOP CHECK Affected Flash Tank High Level (Addendum 2, Step 5)
Dump Valve Is Maintaining Flash Tank Level
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 14 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Event
Description:
LPHD Pump #11 Trip Time Position Required Operator Actions Notes BOP PERFORM The Following For The (Addendum 2, Step 6)
Affected LPHD Flash Tank: Since the cause of the LPHD
- PLACE the flash tank level control Pump 11 trip is unknown the valve controller in manual crew will wait for
- CLOSE the flash tank level control maintenance investigation valve prior to trying a restart.
- DISPATCH An Operator To The crew will mark their place Investigate The Cause For LPHD in Addendum 2 and GO TO Pump Trip procedure step 12.0.
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 15 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 Event 6
Description:
SG 1D Tube Rupture (3 Critical Tasks)
Event 7
Description:
SG 1D FWIV, FW-FV-7144, fails to auto close.
Event 8
Description:
Group 1 Steam Dumps fail to open. Crew will use SG PORVs to perform SGTR cooldown.
Time Position Required Operator Actions Notes RO/BOP Acknowledges and announces radiation monitoring alarms and begins an investigation into possible tube leak.
SRO Begins investigation of SG tube leakage by directing RO/BOP to monitor RCS leakage and identify the affected SG.
ALL Identifies the affected SG as 1D SG.
SRO Enters and directs the actions of 0POP04- Only a few actions of (continuous) RC-0004, Steam Generator Tube Leakage. 0POP04-RC-0004 will be performed if any at all because the leak rate quickly escalates to a point requiring a Reactor trip and SI.
ALL MONITOR the Following Indications To - (Step 1)
IDENTIFY AFFECTED SG(s):
- Feed flow/Steam flow mismatch
- High radiation levels in SG samples
- High radiation levels on the Main Steam line monitors
- High radiation levels on the SG blowdown radiation monitors
- High leak rate indication on N-16 SG Primary to Secondary Leak monitors SRO MAINTAIN Contact With Health Physics (Step 2)
To Evaluate Radiological Conditions In The Secondary Plant Prior To Performing Local Operator Actions SRO NOTIFY Chemistry To: (Step 3)
- SAMPLE SGs For Activity
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 16 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 Event 6
Description:
SG 1D Tube Rupture (3 Critical Tasks)
Event 7
Description:
SG 1D FWIV, FW-FV-7144, fails to auto close.
Event 8
Description:
Group 1 Steam Dumps fail to open. Crew will use SG PORVs to perform SGTR cooldown.
Time Position Required Operator Actions Notes BOP CHECK SG Blowdown - ALIGNED TO (Step 4)
THE BLOWDOWN DEMINERALIZERS The Demineralizers are not in service so crew will contact an operator to place them in service.
SRO Determines a manual reactor trip and SI are needed otherwise an automatic reactor trip and SI will occur. Directs a manual reactor trip and SI and performance of the immediate actions of E0.
SRO Enters and directs the actions of 0POP05-(continuous) EO-EO00, Reactor Trip or Safety Injection.
RO Completes immediate actions of EO00, 0POP05-EO-EO00, Reactor Trip/SI: Reactor Trip or Safety
- Reactor Tripped. Injection Steps 1-4.
- Turbine Tripped. RO will announce status of
- SI is actuated. they are performed.
BOP Operator will monitor the plant and make an announcement of the Reactor trip.
SRO Directs/ensures the immediate actions of Before beginning the EO00, Reactor Trip/SI have been verification of immediate completed by performing a procedure read actions the US may direct through of them. the BOP operator to secure AFWP #14, cross connect AFW to SG 1D, if NR level
< 14%, and throttle AFW to the other SGs per the CIP.
BOP VERIFY Proper SI Equipment Operation (Step 5)
Per ADDENDUM 5, VERIFICATION OF See Actions on Page 25 - 28 SI EQUIPMENT OPERATION
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 17 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 Event 6
Description:
SG 1D Tube Rupture (3 Critical Tasks)
Event 7
Description:
SG 1D FWIV, FW-FV-7144, fails to auto close.
Event 8
Description:
Group 1 Steam Dumps fail to open. Crew will use SG PORVs to perform SGTR cooldown.
Time Position Required Operator Actions Notes RO MONITOR If Containment Spray Is (Step 6)
Required: Containment pressure will
- Containment pressure GREATER be less than 9.5 psig.
THAN 9.5 PSIG (QDPS)
(RNO)
- PERFORM the following:
- CHECK Containment pressure -
18)
- "PRESS PR0934" OR
- "EXTD RNG PRESS PR9759"
- IF containment pressure HAS EXCEEDED 9.5 PSIG, THEN GO TO Step 6.b.
- IF containment pressure HAS REMAINED LESS THAN 9.5 PSIG, THEN GO TO Step 7.
RO CHECK RCP Seal Cooling: (Step 7)
- ENSURE seal injection flow between 6 RO may have to adjust seal and 13 gpm injection.
RO MONITOR RCS Temperatures (Step 8)
- WITH ANY RCP RUNNING, RCS If AFW has been properly TAVG STABLE AT OR TRENDING throttled from the original TO 567°F Reactor Trip then RCS OR temperature should be
- WITHOUT ANY RCP RUNNING, trending to 567°F.
RCS TCOLD STABLE AT OR TRENDING TO 567°F RO CHECK Pressurizer Status: (Step 9)
- PORVs CLOSED
- Normal pressurizer spray valves -
CLOSED
- Auxiliary spray valve - CLOSED
- Excess letdown isolation valves -
CLOSED
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 18 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 Event 6
Description:
SG 1D Tube Rupture (3 Critical Tasks)
Event 7
Description:
SG 1D FWIV, FW-FV-7144, fails to auto close.
Event 8
Description:
Group 1 Steam Dumps fail to open. Crew will use SG PORVs to perform SGTR cooldown.
Time Position Required Operator Actions Notes RO MONITOR If RCPs Should Be Stopped: (Step 10)
- HHSI pump - AT LEAST ONE Reactor Coolant Pump Trip RUNNING Criteria will probably NOT
(RNO)
- GO TO Step 11 RO VERIFY The Following Containment (Step 11)
Isolation Valves - CLOSED
- Seal return isolation valves
- Containment atmosphere radiation monitor isolation valves RO CHECK If SG Secondary Pressure (Step 12)
Boundary Intact:
- CHECK pressures in all SGs -
- CONTROLLED OR RISING
- Main steamline radiation NORMAL
- blowdown radiation NORMAL
- CARS pump radiation NORMAL
- NO SG level rising in an uncontrolled manner (RNO)
- GO TO 0POP05EOEO30, STEAM GENERATOR TUBE RUPTURE, Step 1.
- MONITOR Critical Safety Functions.
- WHEN Addendum 5 of this procedure is complete, THEN Functional Restoration Procedures may be IMPLEMENTED.
BOP Completes 0POP05-EO-EO00, Addendum Will not transition to a
- 5. Functional Recovery Procedure until Addendum 5 is complete.
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 19 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 Event 6
Description:
SG 1D Tube Rupture (3 Critical Tasks)
Event 7
Description:
SG 1D FWIV, FW-FV-7144, fails to auto close.
Event 8
Description:
Group 1 Steam Dumps fail to open. Crew will use SG PORVs to perform SGTR cooldown.
Time Position Required Operator Actions Notes SRO Informs crew of transition to 0POP05-EO-(continuous) EO30, Steam Generator Tube Rupture, and to monitor Critical Safety Functions ALL Monitors the status of Critical Safety Cannot implement FRPs (continuous) Functions when the crew transitions to until Addendum 5 of 0POP05-EO-EO30. 0POP05-EO-EO00, Reactor Trip or Safety Injection, is completed.
RO MONITOR If RCPs Should Be Stopped: (Step 1)
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 20 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 Event 6
Description:
SG 1D Tube Rupture (3 Critical Tasks)
Event 7
Description:
SG 1D FWIV, FW-FV-7144, fails to auto close.
Event 8
Description:
Group 1 Steam Dumps fail to open. Crew will use SG PORVs to perform SGTR cooldown.
Time Position Required Operator Actions Notes SRO/BOP ISOLATE Flow From Ruptured SG(s): (Steps 3 and 4)
(CT-18)
- VERIFY blowdown isolation valve(s) from ruptured SG(s) CLOSED
- CHECK SG 1D RUPTURED
- VERIFY at least one motor-driven AFW pump - RUNNING
- ISOLATE steam supply to turbine-driven AFW pump
- RESET SI
- TRIP turbine-driven AFW pump
- CLOSE turbine-driven AFW pump steam inlet valve
- Denergize turbine-driven steam inlet valve
- ENSURE turbine-driven AFW pump trip/throttle valve closed
BOP CHECK Ruptured SG(s) Pressure (Step 5)
GREATER THAN 468 PSIG
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 21 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 Event 6
Description:
SG 1D Tube Rupture (3 Critical Tasks)
Event 7
Description:
SG 1D FWIV, FW-FV-7144, fails to auto close.
Event 8
Description:
Group 1 Steam Dumps fail to open. Crew will use SG PORVs to perform SGTR cooldown.
Time Position Required Operator Actions Notes RO CHECK Pressurizer PORVs And Isolation (Step 6)
Valves:
- Power to isolation valves AVAILABLE
- PORVs CLOSED
- Isolation valves AT LEAST ONE OPEN SRO DETERMINE required core exit (Step 7.a) temperature based on ruptured SG pressure If D SG pressure is 1200-1250 psig (expected range),
target temperature will be 524°F. If pressure is not within this range the Evaluator will have to note what SG pressure is and check if correct target temperature was used after scenario termination.
- CHECK pressurizer pressure LESS (Steps 7.b and 7.c)
THAN 1985 PSIG
BOP CHECK steam dump in steam pressure (Step 7.e) mode (RNO)
- PLACE steam dump controller in MANUAL with zero demand.
- PLACE steam dump mode selector switch to STEAM PRESSURE mode.
RO CHECK RCS TAVG LESS THAN (Step 7.f) 563°F TAVG should be >563°F
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 22 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 Event 6
Description:
SG 1D Tube Rupture (3 Critical Tasks)
Event 7
Description:
SG 1D FWIV, FW-FV-7144, fails to auto close.
Event 8
Description:
Group 1 Steam Dumps fail to open. Crew will use SG PORVs to perform SGTR cooldown.
Time Position Required Operator Actions Notes BOP DUMP steam to condenser from (Step 7.h) intact SG(s) at maximum rate Event #6 - Group 1 steam
- Determines Steam Dumps are not dumps will fail to open.
responding Crew may not notice until RCS temperature goes below 563°F SRO Direct the BOP operator to perform the (RNO 7.d) cooldown by dumping steam at the Crew will continue to Step maximum rate using SG PORV(s). 8 while cooldown commences RO RESET the following: (Steps 8-12)
- SI AUTO RECIRC
- ESF Load Sequencers
- Containment Isolation Phase A
- Containment Isolation Phase B RO/BOP ESTABLISH IA To Containment: (Step 13)
- NR levels GREATER THAN 14%
- CONTROL AFW to maintain NR levels BETWEEN 22% and 50%
BOP CHECK If RCS Cooldown Should Be (Step 15)
Stopped: Crew will not continue until
- Core exit T/Cs LESS THAN target temperature is REQUIRED TEMPERATURE reached and cooldown is
- STOP RCS cooldown stopped.
STABLE OR RISING RO CHECK RCS Subcooling Based On Core (Step 17)
Exit T/Cs GREATER THAN 55°F
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 23 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 Event 6
Description:
SG 1D Tube Rupture (3 Critical Tasks)
Event 7
Description:
SG 1D FWIV, FW-FV-7144, fails to auto close.
Event 8
Description:
Group 1 Steam Dumps fail to open. Crew will use SG PORVs to perform SGTR cooldown.
Time Position Required Operator Actions Notes ALL DEPRESSURIZE RCS To Minimize Break (Step 18.e & f)
(CT-19) Flow And Refill Pressurizer: After completion of this
- Normal pressurizer spray step, go to step 21 AVAILABLE
- PLACE group "C" pressurizer heater control switch to PULL TO LOCK
- PLACE all other pressurizer heater group control switches to OFF
- INITIATE maximum pressurizer spray
- CHECK Any of the following conditions SATISFIED
- BOTH of the following:
- Pressurizer level GREATER THAN 8%
- BOTH of the following:
- Pressurizer level GREATER THAN 38%
- Pressurizer level GREATER THAN 70%
- RCS subcooling based on core exit T/Cs LESS THAN 35°F WHEN one of the above conditions are met:
- STOP RCS depressurization:
- Normal spray valves CLOSED
- ENSURE one Loop Isolation valve open.
- Auxiliary spray valve CLOSED
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 24 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 Event 6
Description:
SG 1D Tube Rupture (3 Critical Tasks)
Event 7
Description:
SG 1D FWIV, FW-FV-7144, fails to auto close.
Event 8
Description:
Group 1 Steam Dumps fail to open. Crew will use SG PORVs to perform SGTR cooldown.
Time Position Required Operator Actions Notes ALL CHECK If SI Flow Should Be Terminated: (Step 21)
- RCS subcooling based on core exit T/Cs GREATER THAN 35°F
- Secondary heat sink:
- NR level in at least one intact SG GREATER THAN 14%
- Pressurizer level GREATER THAN 8%
SRO/RO STOP HHSI Pumps And PLACE In (Step 22)
(C-20) AUTO Terminate the scenario
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 25 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: N/A Event
Description:
0POP05-EO-EO00, Addendum 5 actions Time Position Required Operator Actions Notes BOP VERIFY FW isolation: 0POP05-EO-EO00, Reactor
- SGFPTs - TRIPPED Trip or Safety Injection,
- SU SGFP - TRIPPED Addendum 5, Verification of
- VERIFY the following valves - Equipment Operation.
CLOSED (Step 1)
- FWIVs This addendum is performed
- FWIBs in parallel with Steps 5 to 14
- FW preheater bypass valves of 0POP05-EO-EO00,
- FW regulating valves Reactor Trip or Safety
- Low power FW regulating valves Injection.
- SG sample isolation valves FW-FV-7144, fails to auto close and operator has to manually close valve using the safety-grade solenoid switches.
BOP CHECK if main steamline should be (Step 2) isolated:
- CHECK for any of the following conditions:
- Containment pressure -
GREATER THAN OR EQUAL TO 3 PSIG OR
LESS THAN OR EQUAL TO 735 PSIG OR
LOWERING AT A RATE GREATER THAN OR EQUAL TO 100 PSI/SEC, BY OBSERVANCE OF THE STEAMLINE PRESSURE RATE BISTABLES BOP VERIFY AFW system status: (Step 3)
- Motor-driven pump - RUNNING
- Turbine-driven pump - RUNNING
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 26 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: N/A Event
Description:
0POP05-EO-EO00, Addendum 5 actions Time Position Required Operator Actions Notes BOP VERIFY AFW valve alignment - (Step 4)
PROPER EMERGENCY ALIGNMENT BOP VERIFY total AFW Flow - GREATER (Step 5)
THAN 576 GPM BOP VERIFY containment isolation phase A: (Step 6)
- Phase A - ACTUATED
- Phase A valves - CLOSED, REFER TO ADDENDUM 1, PHASE A ISOLATION VERIFICATION BOP VERIFY ECW status: (Step 7)
- ECW pumps - RUNNING
- ECW pump discharge isolation valves
- OPEN BOP VERIFY CCW pumps - RUNNING (Step 8)
BOP VERIFY RCFC status: (Step 9)
- RCFCs - RUNNING
- HHSI pumps - RUNNING
EMERGENCY ALIGNMENT BOP VERIFY SI flow: (Step 12)
- HHSI pump flow - INDICATED be greater than 415 psig so
PSIG (RNO)
- GO TO Step 13 of this Addendum.
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 27 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: N/A Event
Description:
0POP05-EO-EO00, Addendum 5 actions Time Position Required Operator Actions Notes BOP VERIFY containment ventilation (Step 13) isolation:
- Containment atmosphere radiation monitor isolation valves - CLOSED
- Normal purge supply and exhaust fans
- STOPPED
- Supplemental purge supply and exhaust fans - STOPPED
- Purge Dampers - CLOSED
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 28 of 30 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: N/A Event
Description:
0POP05-EO-EO00, Addendum 5 actions Time Position Required Operator Actions Notes BOP VERIFY ventilation actuation: (Step 14)
- Control room HVAC - OPERATING IN EMERGENCY RECIRC
- EAB HVAC - OPERATING IN EMERGENCY RECIRC
- FHB HVAC - OPERATING IN EMERGENCY MODE
- FHB Exhaust Fans - ONLY TWO TRAINS OPERATING
- Exhaust booster fans
- Main exhaust fans (RNO)
- PERFORM the following:
- IF three trains FHB exhaust fans running, THEN PLACE one train FHB exhaust fans in PULL TO LOCK.
(Back to A/ER)
- SECURE one FHB filter train by PERFORMING the following:
- PLACE the outlet damper Controller in manual
- Manually close the outlet damper
- VERIFY proper operation of filter train in service
- Essential chilled water pumps -
RUNNING
- Essential chillers - RUNNING
- ECCS pump room fan coolers -
RUNNING
- AFW pump cubicle fans - RUNNING
- FHB truck bay doors - CLOSED BOP NOTIFY Unit Supervisor that Addendum (Step 15) 5 is COMPLETE SRO IMPLEMENT Functional Restoration (Step 16)
Procedures as required SRO RETURN TO procedure step in effect. (Step 17)
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 29 of 30 CRITICAL TASK
SUMMARY
SAT/
POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA UNSAT SRO/BOP CT-18 Isolate feedwater flow into and Isolate Ruptured SG D steam flow from the ruptured SG before a transition to EC31 occurs.
ALL CT-19 Depressurize RCS to meet SI Depressurize RCS to SI termination criteria before termination criteria. either of the following occur:
SRO/RO CT-20 Terminate SI prior to Terminate SI radioactive discharge through a SG PORV or safety valve.
LOT 21 NRC OP-TEST SCENARIO #4 Rev 0 Page 30 of 30 TURNOVER INFORMATION
- Reactor Power is at 100%.
- Due to an issue with seal water to CW Pump #14, start CW Pump #13 and secure CW Pump
- 14 after taking the watch. The pump is expected to be out of service for two days.
- ESF DG #12 was just tagged out for an emergent condition. Return to service of ESF DG #12 is unknown.
- Cycle Burnup is 150 MWD/MTU. (BOL)
- On the previous shift, RCS dilutions were being performed about every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with 10 gallons of makeup water.
- Boric Acid Tank A is at 7315 ppm and B is at 7309 ppm.
- No liquid waste discharges are in progress or planned.
- No personnel are in containment.
- FHB Truck Bay doors are closed.
LCO Actions:
ESF DG 12 - TS 3.8.1.1 Action b and d. 0PSP03-EA-0002, ESF Power Availability, was completed 30 minutes ago. Action d was entered in the log 45 minutes ago as SAT.