ML17319A652

09 Final Op Test

ML17319A652
Person / Time
Site:	South Texas
Issue date:	10/09/2017
From:	Vincent Gaddy Operations Branch IV
To:	South Texas
References
Download: ML17319A652 (386)

Text

Rev. 3 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 2.1.20 Ability to interpret and execute procedure steps.

RA(1) M,R Determine Reactor Vessel Level K/A Importance: 4.6 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 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. 3 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 2.4.44 Knowledge of the emergency plan Protective Action SA(9) M,R Recommendations.

Determine Appropriate Emergency Plan Protective Action K/A Importance: 4.4 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. 3 STP LOT-21 NRC Admin JPM Description RO (A1) Determine Reactor Vessel Level Demonstrate the ability to perform procedure steps to determine Reactor Vessel level in accordance with 0POP02-II-0002, RVWL Monitoring System, when QDPS is not displaying RVWL level.

(A2) Calculate RCS Refill Volume 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 Protective Action Recommendation 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 DETERMINE REACTOR VESSEL LEVEL JPM Number: NRC RA(1)

Revision Number: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on LOT 21 NRC Exam.

Revision 1, Changed JPM to Determine Reactor Vessel Water Level.' (8/17/17)

Page 2 of 9

NRC RA(1) - rev 1 SIMULATOR SETUP INSTRUCTIONS

1. This is an Admin JPM.

Page 3 of 9

NRC RA(1) - rev 1 INITIAL CONDITIONS Unit 1 has experienced a Loss of Offsite Power. The crew has implemented the Emergency Operating Procedures (EOPs) and is currently in 0POP05-EO-ES03, Natural Circulation Cooldown with Steam Void in Vessel.

QDPS indication for RVWL has been lost. RVWL thermocouple temperature indications are available at local Panel ZRR-050, however, Channel A of RVWL was out of service when the event occurred.

Data was collected from Channel C of RVWL in accordance with 0POP02-II-0002, RVWL Monitoring System, Section 6.2, RVWL Test Mode.

INITIATING CUE The Unit Supervisor asks you to determine RVWL Sensor status, Reactor Vessel Upper Head water level and Reactor Vessel Plenum water level from the data recorded for Channel C of RVWL by performing 0POP02-II-0002, RVWL Monitoring System, Section 7.1 & 7.2 and completing Data Sheet 2, Channel C RVWL System Data Sheet.

Record your answer on 0POP02-II-0002, RVWL Monitoring System, Data Sheet 2, Channel C RVWL System Data Sheet.

Page 4 of 9

NRC RA(1) - rev 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:

Determines RVWL is as follows or per the KEY:

• Sensors 2, 4 to 8 are WET

• Sensor 1 is DRY

• Reactor Vessel Upper Head level is 64% and Reactor Vessel Plenum level is 100% or FULL

• Sensor 3 is Inoperable and all other Sensors are Operable

• Reactor HEAD has 2 Sensors and Reactor PLENUM has 5 Sensors

• TS 3.3.3.6 for Channel C of RVWL is SAT and marked YES JPM Step 2 Page 5 of 9

NRC RA(1) - rev 1 JPM Start Time:

Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Hand out Student Copy of 0POP02-II-0002, RVWL Monitoring System.

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 Completes Section 7.1 of Reviews the data collected on ___ ___ ___

0POP02-II-0002, RVWL Data Sheet 2 of 0POP02-II-Monitoring System. 0002, RVWL Monitoring System, to determine reactor vessel water level.

Page 6 of 9

NRC RA(1) - rev 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number

• 2 Completes section 7.2 and Determines that Sensors 2, 4 ___ ___ ___

determines Reactor RVWL to 8 are WET & Sensor 1 is Sensor status, Vessel Upper DRY, Reactor Vessel Upper Head water level and Reactor Head water level is 64% and Vessel Plenum water level Reactor Vessel Plenum water using the Channel 'C' RVWL level is 100% or FULL. Marks data collected on 0POP02-II- Sensor 3 NO for operability and 0002, RVWL Monitoring the other Sensors YES. Marks System, Data Sheet 2. the Reactor HEAD with 2 Sensors Operable and the Reactor PLENUM with 5 Sensors Operable. Marks TS 3.3.3.6 YES for Channel C RVWL with only Sensor 3 inoperable.

NOTE: 0POP02-II-0002, RVWL Monitoring System, Addendum 1, RVWL Sensor Elevations, is used while performing Step 7.1, however, Data Sheet 2, Channel C RVWL Data Sheet, will contain the required information to satisfy the Task Standard.

CUE This JPM is complete JPM Stop Time:

Page 7 of 9

NRC RA(1) - rev 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

DETERMINE REACTOR VESSEL LEVEL JPM Number: NRC RA(1) Revision Number: 1 Task Number and

Title:

91008, Knowledge of the purpose and principle of operation of the Reactor Vessel Water Level (RVWL) System 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): 0POP02-II-0002, RVWL Monitoring System, Rev 19 CRs 05-14324 and 09-18717, RVWL Sensors NOT Reading Correctly.

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 8 of 9

Student Handout INITIAL CONDITIONS Unit 1 has experienced a Loss of Offsite Power. The crew has implemented the Emergency Operating Procedures (EOPs) and is currently in 0POP05-EO-ES03, Natural Circulation Cooldown with Steam Void in Vessel.

QDPS indication for RVWL has been lost. RVWL thermocouple temperature indications are available at local Panel ZRR-050, however, Channel A of RVWL was out of service when the event occurred.

Data was collected from Channel C of RVWL in accordance with 0POP02-II-0002, RVWL Monitoring System, Section 6.2, RVWL Test Mode.

INITIATING CUE The Unit Supervisor asks you to determine RVWL Sensor status, Reactor Vessel Upper Head water level and Reactor Vessel Plenum water level from the data recorded for Channel C of RVWL by performing 0POP02-II-0002, RVWL Monitoring System, Section 7.1 & 7.2 and completing Data Sheet 2, Channel C RVWL System Data Sheet.

Record your answer on 0POP02-II-0002, RVWL Monitoring System, Data Sheet 2, Channel C RVWL System Data Sheet.

Page 9 of 9

EXAMINER INFORMATION 0POP02-II-0002

-

• indicates critical Rev. 19 of task step Page 1 of 1

• 7.1.1 Sensors 2, 4 - 8 should be RVWL markedMonitoring System WET because their Delta Ts are less than 200°F.

• 7.1.2 Sensors 1 should be marked DRY because its Delta T is greater than 200°F.

Data Sheet 2 Channel C RVWL System Data Sheet{TC "Data Sheet 2, Page 1 of 1

• (No specific step for this.)Channel Sensor C 3 is NOT operable because it has RVWL System Data Sheet" \f C \l "2"}2 Error Codes and the Delta T is less than 25°F. The block can be left blank. (Sensor 3 Heated TC not working.)

UNIT 1

• 7.1.3, 7.1.4 Based on the last bullet in the NOTE (circle UNIT 2 in Addendum 1, RVWL is at the location of the one) first DRY sensor, which is sensor 1 in this case. Therefore RVWL is at 64% for the Upper Head and 100% or FULL for the Plenum. (Sensor 3 being inoperable would only affect the indicated 1.0level HEAD onLevel if level dropped PLENUM QDPS_____N/A______ Level3.)

below sensor _____N/A______

• 2.07.1.5 ErrorOperator notifies Shift Codes ______E07, E08Manager that Reactor Vessel Upper Head is NOT full.

• 7.2.1, 7.2.2, 7.2.3 Sensor 3 will be marked NO for operability and the rest will be marked YES.

• 7.2.4 The HEAD has 2 operable sensors and the PLENUM has 5 operable sensors. NO. OF

• Test Mode

• 7.2.5 TS SENSOR 3.3.3.6 is SAT and markedVALUE PARAMETER YES for WET/DRY RVWL withSENSOR Channel C ofLEVEL only Sensor OPERABLE 3 inoperable.

Data Table No. OPERABLE

• 7.2.6 Operator Sign and Date the PERFORMED BY. SENSORS TEST I.D.

No.

1 1 Delta T 310 HEAD HEAD 2 1 T Heated 767 DRY YES 3 1 T Unheated 457 64%

4 2 Delta T 188 2 5 2 T Heated 639 WET YES 6 2 T Unheated 450 7 3 Delta T 21 PLENUM PLENUM 8 3 T Heated 469 NO 9 3 T Unheated 449 10 4 Delta T 178 11 4 T Heated 627 WET 100% OR YES 12 4 T Unheated 450 FULL 13 5 Delta T 178 14 5 T Heated 626 WET YES 15 5 T Unheated 448 5 16 6 Delta T 174 17 6 T Heated 625 WET YES 18 6 T Unheated 450 19 7 Delta T 177 20 7 T Heated 624 WET YES 21 7 T Unheated 447 22 8 Delta T 177 23 8 T Heated 626 WET YES 24 8 T Unheated 448 4.0 Technical Specification 3.3.3.6 [ITS 3.3.3] is SATISFIED: YES ___ NO ___

Performed by: ___Sign Here ***

Date Time

Reviewed by:

Date This procedure, when complete, SHALL be retained for five years

STPNOC Job Performance Measure CALCULATE RCS REFILL VOLUME JPM Number: NRC RA(2)

Revision Number: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on LOT 21 NRC Exam.

Revision 1, Updated task standard. (9/6/17)

Added pictures of vacuum gauge and RVWL indicator to initiating cue.

Revised RWST levels to begin within allowable T.S. limits.

Revised JPM to be calculated with vacuum instead of without vacuum.

NRC RA(2) - rev 1 SIMULATOR SETUP INSTRUCTIONS

1. This is an Admin JPM.

NRC RA(2) - rev 1 INITIAL CONDITIONS Unit 2 is performing a fill of the RCS per 0POP03-RC-0100, RCS Vacuum Fill, from the RWST.

INITIATING CUE You have been given a copy of 0POP03-RC-0100, RCS Vacuum Fill, and the Unit Supervisor directs you to perform Addendum 3 and the following:

• Calculate the required RCS Floodup Volume, to 50% Pressurizer level, without interpolating.

AND

• Determine if the RWST level change was within 200 gallons of the calculated amount for RCS fill.

NOTE: Initial RWST level was 510,000 gallons. AFTER the RCS fill was completed, RWST level was at 453,000 gallons.

NRC RA(2) - rev 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:

Correctly calculates the volume of water needed (57,154 gal) to refill the RCS to 50%

Pressurizer level in accordance with 0POP03-RC-0100, Addendum 3 per the key. Also, correctly determines the RWST level change IS within 200 gallons of the calculated amount for RCS fill.

NRC RA(2) - rev 1 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" or NR Hot leg Lvl +6 (Addendum 3 step 1.1) inches.

NOTE: Initial sightglass level will have to be obtained by reading the attached Hot Leg level indicator.

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 With 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.

Page 6 of 9

NRC RA(2) - rev 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number Record expected final RCS Records expected final RCS 3 ___ ___ ___

volume in gallons. (Addendum 3 volume as 89,790 gallons using step 1.3) Addendum 3 Table - RCS Floodup Volume With Vacuum column for Pressurizer level at 50%.

NOTE: The attached picture of the vacuum gauge readings will be required to determine that RCS conditions are acceptable to perform floodup with vacuum.

(Procedure requires RCS Pressure to be > 20 Hg for 15 minutes and shall not exceed 22.3 Hg.)

Calculate Total RCS volume to Determines 57,154 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 (89,790 gal).

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) 57,000 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

NRC RA(2) - rev 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

CALCULATE RCS REFILL VOLUME JPM Number: NRC RA(1) Revision Number: 1 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.

INITIATING CUE You have been given a copy of 0POP03-RC-0100, RCS Vacuum Fill, and the Unit Supervisor directs you to perform Addendum 3 and the following:

• Calculate the required RCS Floodup Volume, to 50% Pressurizer level, without interpolating.

AND

• Determine if the RWST level change was within 200 gallons of the calculated amount for RCS fill.

NOTE: Initial RWST level was 510,000 gallons. AFTER the RCS fill was completed, RWST level was at 453,000 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 Reactor Vessel Flange Beginning 39 ft 3 in and ending values 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" or NR Hot leg Lvl +6 in 1.2 DETERMINE current RCS volume in gallons. 32,636 1.3 RECORD expected final RCS volume in gallons. 89,790 1.4 CALCULATE Total RCS volume to be added by subtracting Step 1.2 from Step 1.3. 57,154 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.

510,000 RWST _________ N/A RHT ________

2.2 RECORD stop level for RCS fill water source in gallons.

453,000 RWST _________ N/A RHT ________

2.3 CALCULATE RCS fill water source level change by subtracting Step 2.2 from Step 2.1.

57,000 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: 57,154 gal Actual change in level: 57,000 gal Difference: 154 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: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on LOT 21 NRC Exam.

Revision 1, Updated task number and title. (8/15/17)

Page 2 of 8

NRC RA(3) - rev 1 SIMULATOR SETUP INSTRUCTIONS

1. This is an Admin JPM.

Page 3 of 8

NRC RA(3) - rev 1 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 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:

Determines Hydrogen Recombiner power setting per the key as follows: Recombiner 1A:

71.91 (+/- 1.02) kW and Recombiner 1B: 66.98 (+/- 1.02) kW Page 5 of 8

NRC RA(3) - rev 1 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 1.39 -1.43. 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 71.91 Recombiner by multiplying the (+/- 1.02) kW Pressure Factor (Cp) times the reference power. Determines Recombiner 1B power setting should be 66.98

(+/- 1.02) 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

NRC RA(3) - rev 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

DETERMINE H2 RECOMBINER POWER SETTINGS JPM Number: NRC RA(3) Revision Number: 1 Task Number and

Title:

12150, PERFORM LINEUPS OF THE HYDROGEN RECOMBINER 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 1.41 (+/- 0.02)

_____________________ 51 KW = 71.91 (+/- 1.02) KW

__________________________ KW X

Pressure Factor (Cp) Ref Pwr (Required PWR Setting)

Hydrogen Recombiner 1B Power Setting 1.41 (+/- 0.02)

_____________________ 47.5 KW = 66.98 (+/- 1.02) 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: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on LOT 21 NRC Exam.

Revision 1, Updated revision for final exam. (8/15/2017)

Page 2 of 8

NRC RA(4) - rev 1 SIMULATOR SETUP INSTRUCTIONS

1. This is an Admin JPM.

Page 3 of 8

NRC RA(4) - rev 1 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 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:

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 1 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 7 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

NRC RA(4) - rev 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

COMLETE AN OFFSITE AGENCY NOTIFICATION MESSAGE FORM JPM Number: NRC RA(4) Revision Number: 1 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 seven (7) 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

5. Message#: 1 Originating From: X CR TSC EOF

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 DETERMINE CLOSE CONTACT FUEL ASSEMBLY MOVEMENT JPM Number: NRC SA(5)

Revision Number: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on LOT 21 NRC Exam.

Revision 1, Updated Title of JPM and the task standard to be more specific. (8/15/17)

Page 2 of 9

NRC SA(5) - rev 1 SIMULATOR SETUP INSTRUCTIONS

1. This is an Admin JPM.

Page 3 of 9

NRC SA(5) - rev 1 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 9

NRC SA(5) - rev 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:

Determines the correct Close Contact Movement for the identified Fuel Assemblies per the key. The first assembly to be moved is to core location B4, lowering on index in slow speed (Case 2). The second assembly to be moved is to core location H8, lowering off index in open water to open water jog height, then jog to on index and lower rest of way in slow speed (Case 3). The third assembly to be moved is to core location H7, lowering on index in slow speed (Case 2).

Page 5 of 9

NRC SA(5) - rev 1 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.

Page 6 of 9

NRC SA(5) - rev 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number Determine correct Close Determines that Fuel Assembly

• 3 ___ ___ ___

Contact Movement for Fuel to be placed in core location H7 Assembly to be placed in core should be LOWERED on-index location H7. at slow speed. (Case 2)

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 7 of 9

NRC SA(5) - rev 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

DETERMINE CLOSE CONTACT FUEL ASSEMBLY MOVEMENT JPM Number: NRC SA(5) Revision Number: 1 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: 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 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 9 of 9

LOT 21 NRC JPM SA(5) Rev. 1 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 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 KEY in open water to 'open water BRIDGE BRIDGE LEFT RIGHT jog height' (approximately 12 inches), jog to on index and TROLLEY 3rd Fuel Assembly H7 lower rest of way in slow REVERSE Lower on index in slow speed.

speed. Case 2 Case 3

STPNOC Job Performance Measure REVIEW ESF POWER AVAILABILITY SURVEILLANCE RESULTS JPM Number: NRC SA(6)

Revision Number: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on LOT 21 NRC exam.

Revision 1, Deleted the 15 minute completion time requirement. (8/15/17)

Page 2 of 8

NRC SA(6) - rev 1 SIMULATOR SETUP INSTRUCTIONS

1. This is an Admin JPM.

Page 3 of 8

NRC SA(6) - rev 1 INITIAL CONDITIONS Unit 1 is at 100% power with a Train A outage week in progress. The following plant conditions exist:

• #11 ESF D/G was taken OOS for scheduled maintenance at 0600 yesterday.

• 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 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:

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 1 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 JPM Stop Time:

Page 6 of 8

NRC SA(6) - rev 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

REVIEW ESF POWER AVAILABILITY SURVEILLANCE RESULTS JPM Number: NRC SA(6) Revision Number: 1 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:

• #11 ESF D/G was taken OOS for scheduled maintenance at 0600 yesterday.

• 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: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on LOT 21 NRC exam.

Revision 1, Updated revision for final exam. (8/15/17)

Page 2 of 8

NRC SA(7) - rev 1 SIMULATOR SETUP INSTRUCTIONS

1. This is an Admin JPM.

Page 3 of 8

NRC SA(7) - rev 1 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 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:

Identifies two Critical errors in the Equipment Clearance Order (ECO) IAW with Section 6.5 of 0PGP03-ZO-ECO1A, Equipment Clearance Order Instructions.

1. The wrong power supply is listed for AFW Pump 22. Should be 4160 V SWGR E2B Cubicle

1. 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 1 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

1. 3) is carried over to Line Items #4 and #5 for consistency and realism.

CUE This JPM is complete JPM Stop Time:

Page 6 of 8

NRC SA(7) - rev 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

REVIEW A FAULTED ECO FOR AFW PUMP JPM Number: NRC SA(7) Revision Number: 1 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: 30 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 Y Hang 3 Fuse Removed AF-FV-7516 AF-0061 SG 2B AFW Reg Vlv 7 D 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 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 5 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: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on LOT 21 NRC exam.

Revision 1, Updated task number and title. (8/15/17)

Page 2 of 9

NRC SA(8) - rev 1 SIMULATOR SETUP INSTRUCTIONS

1. This is an Admin JPM.

Page 3 of 9

NRC SA(8) - rev 1 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 Johns total annual exposure if he worked the outage job.

2) Identify whose approval is required for the dose extension.

Page 4 of 9

NRC SA(8) - rev 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:

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 1 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 1 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

NRC SA(8) - rev 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

INITIATE A DOSE EXTENSION JPM Number: NRC SA(8) Revision Number: 1 Task Number and

Title:

20200 (SRO), Coordinate Work Activities within Operations and With Other Departments 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 Johns total annual exposure if he worked the outage job.

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 ANNUAL EXPOSURE = 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: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on LOT 21 NRC exam.

Revision 1, Updated task number and title. (8/15/17)

Page 2 of 9

NRC SA(9) - rev 1 SIMULATOR SETUP INSTRUCTIONS

1. This is an Admin JPM.

Page 3 of 9

NRC SA(9) - rev 1 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 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:

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 1 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)

OR

• 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 1 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

NRC SA(9) - rev 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

DETERMINE APPROPRIATE PROTECTIVE ACTION RECOMMENDATION JPM Number: NRC SA(9) Revision Number: 1 Task Number and

Title:

221375 (SRO), Determine protective action recommendations (PARs)

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. 2 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

d. (S4) Roll 13.8 KV buses KA: 062 A4.07 (3.1/3.1) D,S 6

e. (S5) Transfer MFW from LPFRVs to MFRVs KA: 035 A4.01 D,P,S 4S (3.7/3.6)

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. 2 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

d. (S4) Roll 13.8 KV buses KA: 062 A4.07 (3.1/3.1) D,S 6

e. (S5) Transfer MFW from LPFRVs to MFRVs KA: 035 A4.01 D,P,S 4S (3.7/3.6)

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. 2 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.

d. (S4) Roll 13.8 KV buses KA: 062 A4.07 (3.1/3.1) D,S 6 e.

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. 2 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) Roll 13.8 KV buses Demonstrate the ability to shift auxiliary busses between the Unit Aux XFMR and the Standby XFMR.

(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. 2 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: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on the LOT 21 NRC exam.

Revision 1, Updated Task Standard to be more specific.

Updated the validation time. (8/14/2017)

Page 2 of 9

NRC S1 - rev 1 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. Store the IC After IC is Stored and ready to perform JPM

1. For LOT 21 NRC Exam this JPM uses the same IC as S3 but must be performed separately.

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 1 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. All critical JPM steps (#1, 4, 6, 7 & 8) are completed.

Page 4 of 9

NRC S1 - rev 1 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 1 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 1 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 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

PLACE CONTAINMENT H2 MONITORING SYSTEM IN SERVICE JPM Number: NRC S1 Revision Number: 1 Task Number and

Title:

12150, Perform lineups of the Hydrogen Recombiner 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: 10 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: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on the LOT 21 NRC exam.

Revision 1, Updated Task Standard to be more specific.

Enhanced the cue for step 8.

Made step 13 a critical step. (8/14/2017)

Page 2 of 10

NRC S2 - rev 1 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 1 CCW and 2 ECW Pumps running.

2. Store the IC After IC is Stored and ready to perform JPM

1. For LOT 21 NRC Exam this JPM is scheduled to be performed with JPM S7

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 10

NRC S2 - rev 1 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

• The Unit Supervisor directs CCW Mode Select Switches to be aligned as follows:

o Train A - Off o Train B -Standby o Train C - Run 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 (CCW) Pump 1C and aligns CCW Pump 1B for standby. All critical JPM steps (#7, 8, & 13) are completed.

Page 4 of 10

NRC S2 - rev 1 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 10

NRC S2 - rev 1 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).

(Step 10.5)

• 7 OPEN RHR HX CCW OUTL Opens FV-4565 ___ ___ ___

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 asks if SWGR room is clear, inform him/her that the SWGR room is clear.

o If the operator contacts 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 10

NRC S2 - rev 1 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 10

NRC S2 - rev 1 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 asked, inform student to place B Train in STANDBY as stated in the initiating cue.

14 ENSURE CCW/ECW mode o Places CCW/ECW Train C ___ ___ ___

selector switch for running CCW MODE SEL switch to the pump(s) in "OFF" or "RUN". RUN position.

(Step 10.18) o Leaves CCW/ECW Train A Cue: MODE SEL switch in the OFF position.

If asked, inform student to align the mode selector switches for Train C in Run and Train A in Off as stated in the initiating cue.

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 8 of 10

NRC S2 - rev 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

START CCW TRAIN JPM Number: NRC S2 Revision Number: 1 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: 2 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, & 13 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 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

• The Unit Supervisor directs CCW Mode Select Switches to be aligned as follows:

o Train A - Off o Train B -Standby o Train C - Run Page 10 of 10

STPNOC Job Performance Measure ISOLATE SI ACCUMULATORS JPM Number: LOT 21 NRC S3 Revision Number: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on the LOT 21 NRC exam.

Revision 1, Updated Task Standard to be more specific.

Updated step 1 to reflect temperature in new revision of procedure.

(8/14/2017)

Page 2 of 8

NRC S3 - rev 1 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 Post large break LOCA

2. Have ES13 complete

3. Ensure Hot leg temps less than 435°F

4. Insert malfunction to keep Train A Accumulator Isolation Valve open.

5. Store the IC After IC is Stored and ready to perform JPM

1. For LOT 21 NRC Exam this JPM uses the same IC as S1 but must be performed separately.

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

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 1 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. All critical JPM steps

(#2, 3, 5 & 6) are completed.

Page 4 of 8

NRC S3 - rev 1 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 435°F.

435°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 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" NOTE: Train A valve does not close. 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 1 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 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

ISOLATE SI ACCUMULATORS JPM Number: NRC S3 Revision Number: 1 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 ROLL13.8 KV ELECTRICAL BUSES JPM Number: LOT 21 NRC S4-REP Revision Number: 0 Date: 09/26/2017 Developed By:

Instructor (Print/Sign) Date Approved By:

Training Supervisor (Print/Sign) Date Approved By:

Line Management (Print/Sign) Date

NRC S4-REP - rev 0 Revision Record (Summary)

Revision 0, Drafted JPM for use on LOT 21 NRC exam.

Page 2 of 9

NRC S4-REP - 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.

After IC is Stored and ready to perform JPM

1. Ensure Radio volume for both stations are set to a reasonable level.

2. 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.}

3. Reset the simulator to IC 193 and verify the following:

• Step counter position annunciator light is out on CP-005

• Red light at the end of CP-010 is out

4. Check and clean the following procedures (JPM specific):

• 0POP02-AE-0002, Transformer Normal Breaker and Switch Lineup

5. 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.

6. 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 S4-REP - rev 0 INITIAL CONDITIONS Unit 1 is at 100% Power.

Emergent work was performed on AUX TO STBY BUS 1G TIE BKR and STBY XFMR 2 TO STBY BUS 1G SPLY Handswitches in the Control Room on CP010.

The Handswitches have been repaired and are ready for PMT.

In preparation for the PMT, 13.8KV STBY Bus 1H has been aligned to the Unit 1 STBY Transformer so that all ESF Buses will not be aligned to the Unit Aux Transformer at one time and the Train B ESF Load Tap Changer is in MANUAL with a the Tap Changer at N as verified by the Head Plant Operator.

INITIATING CUE Steps for performing the PMT have been developed, recorded, reviewed and approved by the Unit Supervisor on 0POP02-AE-0002, Transformer Normal Breaker and Switch Lineup, Addendum 4, Transferring 13.8 KV Bus Power Supply Checklist.

The Unit Supervisor directs you to perform procedure step 16.9 of 0POP02-AE-0002, Transformer Normal Breaker and Switch Lineup, to complete the PMT.

NOTE: TS 3.8.1.1 has been evaluated and implemented for this ALTERNATE LINEUP of the 13.8KV 1G BUS. The electrical alignment performed will be placed back to the NORMAL LINEUP on the next shift.

Page 4 of 9

NRC S4-REP - 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:

Performs the following 13.8 KV bus transfers without causing an automatic breaker actuation:

• 13.8 KV STBY Bus 1G from the STBY XFMR 1 to the Unit 1 UAT via the TIE BKR.

• 13.8 KV STBY Bus 1G from the Unit 1 UAT via the TIE BKR to the STBY XFMR 2.

All critical JPM steps (#1, 2, 3, 5, 6 and 7) are completed.

Page 5 of 9

NRC S4-REP - rev 0 JPM Start Time:

Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE 0POP02-AE-0002, 0POP02-AE-0002, Transformer Normal Breaker and Switch Lineup, Addendum 4, Transferring 13.8 KV Bus Power Supply Checklist is filled out and attached with this JPM. It is to be given to the Operator along with the portions of procedure section 16 leading up to step 16.9.

13KV BUS BKR PARALLELED Alarm 10M1 B-3 will annunciate if a 13.8KV Bus is paralleled more than 15 seconds.

Depending on the breaker lineup at the time of parallel breaker operation, supply breakers will trip open to separate the AUX and STBY Bus after 30 to 30.5 seconds of being paralleled.

1* 13.8 KV Bus 1G Tie Breaker Places TIE BKR SYNC SW T- ___ ___ ___

Sync Switch to ON 0140 to ON 2* Closes 13.8 KV Bus 1G Tie Places AUX TO STBY BUS 1G ___ ___ ___

Breaker. TIE BKR T-0140 to CLOSE 3* Opens STBY Transformer 1 Places STBY XFMR 1 TO ___ ___ ___

Supply to 13.8 KV STBY Bus STBY BUS 1G SPLY ST-0160 1G Breaker. to TRIP 4 13.8 KV Bus 1G Tie Breaker Places TIE BKR SYNC SW T- ___ ___ ___

Sync Switch to OFF 0140 to OFF 5* 13.8 KV Bus 1G STBY 2 Supply Places SPLY BKR SYNC SW ___ ___ ___

Breaker Sync Switch to ON ST-0180 to ON 6* Closes 13.8 KV STBY Bus 1G Places STBY XFMR 2 TO ___ ___ ___

STBY 2 Supply Breaker. STBY BUS 1G SPLY ST-0180 to CLOSE Page 6 of 9

NRC S4-REP - rev 0 Comment STEP ELEMENT STANDARD SAT UNSAT Number 7* Opens 13.8 KV Bus 1G Tie Places AUX TO STBY BUS 1G ___ ___ ___

Breaker. TIE BKR T-0140 to TRIP 8 13.8 KV Bus 1G STBY 2 Supply Places SPLY BKR SYNC SW ___ ___ ___

Breaker Sync Switch to OFF ST-0180 to OFF CUE This JPM is complete JPM Stop Time:

Page 7 of 9

NRC S4-REP - rev 0 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

ROLL 13.8 KV ELECTRICAL BUSES JPM Number: NRC S4-REP Revision Number: 0 Task Number and

Title:

62800, Shift Auxiliary Busses between the Unit Aux XFMR and the Standby XFMR.

K/A Number and Importance: 062 A4.07 3.1/3.1 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-AE-0002, Transformer Normal Breaker and Switch Lineup, Rev 68 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 5 minutes Actual Time Used: minutes Critical Steps: JPM steps 1, 2, 3, 5, 6 and 7 are critical.

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 1 is at 100% Power.

Emergent work was performed on AUX TO STBY BUS 1G TIE BKR and STBY XFMR 2 TO STBY BUS 1G SPLY Handswitches in the Control Room on CP010.

The Handswitches have been repaired and are ready for PMT.

In preparation for the PMT, 13.8KV STBY Bus 1H has been aligned to the Unit 1 STBY Transformer so that all ESF Buses will not be aligned to the Unit Aux Transformer at one time and the Train B ESF Load Tap Changer is in MANUAL with a the Tap Changer at N as verified by the Head Plant Operator.

INITIATING CUE Steps for performing the PMT have been developed, recorded, reviewed and approved by the Unit Supervisor on 0POP02-AE-0002, Transformer Normal Breaker and Switch Lineup, Addendum 4, Transferring 13.8 KV Bus Power Supply Checklist.

The Unit Supervisor directs you to perform procedure step 16.9 of 0POP02-AE-0002, Transformer Normal Breaker and Switch Lineup, to complete the PMT.

NOTE: TS 3.8.1.1 has been evaluated and implemented for this ALTERNATE LINEUP of the 13.8KV 1G BUS. The electrical alignment performed will be placed back to the NORMAL LINEUP on the next shift.

Page 9 of 9

STPNOC Job Performance Measure TRANSFER MFW FROM LPFRV TO MFRV JPM Number: LOT 21 NRC S5 Revision Number: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on LOT21 NRC exam.

Revision 1, Updated Task Standard to be more specific.

Added note prior to step 1 to handout the Student Handout. (8/14/2017)

Page 2 of 9

NRC S5 - rev 1 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. Store the IC After IC is Stored and ready to perform JPM

1. For LOT 21 NRC Exam this JPM this JPM is scheduled to be performed with JPM S6

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 1 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 SGFP #14 is in service.

INITIATING CUE The Unit Supervisor hands you Addendum 11 of 0POP03-ZG-0005, Plant Startup to 100%,

and 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.

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 (MFRV) by manually closing the Low Power Feed Regulating Valve (LPFRV) while manually and simultaneously opening the MFRV until the LPFRV is closed in manual and the MFRV is in AUTO controlling SG 1C level. All critical JPM steps (#4, 5 & 6) are completed.

Page 4 of 9

NRC S5 - rev 1 JPM Start Time:

Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Student Handout of 0POP03-ZG-0005 Addendum 11, Transferring feed from AFW to Main Feed, will be handed out with the initiating cue.

1 Ensure that SG 1C narrow Verifies that SG 1C narrow ___ ___ ___

range level is stable between range level indication is stable 65% and 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 1 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

• 5 Begin transfer from low power Maintains SG 1C Feedwater ___ ___ ___

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 1 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 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

TRANSFER MFW FROM LPFRV TO MFRV JPM Number: NRC S5 Revision Number: 1 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 SGFP #14 is in service.

INITIATING CUE The Unit Supervisor hands you Addendum 11 of 0POP03-ZG-0005, Plant Startup to 100%,

and 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.

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: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on LOT 21 NRC exam.

Revision 1, Updated Task Standard to be more specific.

Added a note to JPM step 12 to clarify operation of handswitch.

Added a note to JPM step 15 to clarify operation of handswitch.

Changed JPM step 18 to non-critical. (8/14/2017)

Page 2 of 11

NRC S6 - rev 1 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.

3. Store the IC After IC is Stored and ready to perform JPM

1. For LOT 21 NRC Exam this JPM this JPM is scheduled to be performed with JPM S6

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 1 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 by bypassing CVCS Demineralizers and closing CV-FV-0013. Then the operator places CVCS Demineralizers back in service and secures Charging Pump 1A. All critical JPM steps (#4, 6 - 8, 12, 15 - 17) are completed.

Page 4 of 11

NRC S6 - rev 1 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:

If asked, 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 1 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)

• 7 CLOSE the appropriate letdown Closes FV-0013,85-100 GPM ___ ___ ___

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.

Page 6 of 11

NRC S6 - rev 1 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:

• Current RCS Boron concentration is within 25 Bullet #1 is met because there ppm of Boron concentration hasnt been a change to the in when bypassed service CVCS Demineralizer.

• Current RCS Boron Bullet #2 is met because the concentration is greater than CVCS in service Demineralizer 25 ppm should have been isolated only a short time.

(Step 7.4.1)

Bullet #3 is met because boron NOTE: RCS Boron concentration has not changed concentration per initiating cue by more than 25 ppm.

was 950 ppm at the start.

Bullet #4 is met because boron Cue: concentration is NOT less than When asked, Chemistry reports 25 ppm.

current Boron concentration is now 935 ppm.

11 ENSURE that the demineralizer Determines no changes have ___ ___ ___

being restored to service is the been made to the CVCS same demineralizer that was in Demineralizers.

service at the time it was bypassed, OTHERWISE PLACE the demineralizer in service per Section 33.0, 36.0, 38.0, or 62.0as appropriate.

(Step 7.4.2)

• 12 PLACE DIVERT TCV-0143 in Places DIVERT TCV-0143 in ___ ___ ___

the DEMIN position. the DEMIN position.

(Step 7.4.3) NOTE:

TCV-0143 handswitch will spring return to AUTO.

Page 7 of 11

NRC S6 - rev 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number 13 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.

14 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.

• 15 ENSURE open the Centrifugal Opens CCP 1A Recirc FCV- ___ ___ ___

Charging Pump miniflow valve 0201 for pump to be secured: NOTE:

• CCP 1A(2A) RECIRC FCV- Operator must hold FCV-0201 0201 handswitch in OPEN until (Step 6.2) valve is fully opened.

• 16 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)

Page 8 of 11

NRC S6 - rev 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number

• 17 STOP Centrifugal Charging Stops CCP 1A. ___ ___ ___

Pump by momentarily turning its handswitch to the STOP position:

• CCP 1A(2A)

(Step 6.4) 18 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.

19 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 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

LOWER CVCS CHARGING AND LETDOWN FLOW JPM Number: NRC S6 Revision Number: 1 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: 20 minutes Actual Time Used: minutes Critical Steps (*) 4, 6 - 8, 12, 15 - 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: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on LOT 21 NRC exam.

Revision 1, Updated Task Standard to be more specific.

Revised JPM steps to specify placing Train A FHB Exhaust Filter in service.

(8/14/2017)

Page 2 of 10

NRC S7 - rev 1 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.

3. Reset the FHB HVAC Rad Actuation and then place FHB HVAC back to a normal lineup.

4. Store the IC After IC is Stored and ready to perform JPM

1. For LOT 21 NRC Exam this JPM this JPM is scheduled to be performed with JPM S2

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. Ensure both FHB HVAC dampers are in auto.

6. Check and clean the following procedures (JPM specific):

• 0POP04-RA-0001, Radiation Monitoring System Alarm Response

7. 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.

8. 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 1 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 Train A to the emergency mode. All critical JPM steps (#1-4, 6, 8, 9, & 11) are completed.

Page 4 of 10

NRC S7 - rev 1 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.

NOTE Alternate path starts here.

• 3 Check FHB HVAC operating in Determines FHB HVAC is NOT ___ ___ ___

Emergency Mode. operating in Emergency Mode (Addendum 10, Step 2) and goes to procedure Addendum 28.

Page 5 of 10

NRC S7 - rev 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Only one Filter Train is to be placed into service per the procedure.

The examiner will need to cue the student to place Train A FHB Exhaust Filter in service prior to the student taking actions in the next JPM step.

• 4 Open the Inlet Isolation Damper Opens FV-9549 (Train A) ___ ___ ___

for one FHB Exhaust Filter Note:

Train to be placed in service.

Various alarms will come in and (Addendum 28, Step 1) clear on the panel where the Cue: applicant is performing o As the Unit Supervisor, procedure steps. If the operator direct the operator to place wishes to consult Annunciator Train A FHB Exhaust Filter Response procedures, inform in service. 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 Note:

Student may start any 2 of the fans.

7 Place the FHB Exhaust Flow Train B - EXH AIR FROM ___ ___ ___

Controller in Manual and TRAIN B FLTRS HV-9507A:

manually close outlet damper Places in Manual using the for FHB Exhaust Filter train Manual/Auto button and NOT being placed in service. depresses the CLOSE button (Addendum 28, Step 4) until the exhaust air damper is closed.

Page 6 of 10

NRC S7 - rev 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number

• 8 Place the FHB Exhaust Filter Train A - EXH AIR FROM ___ ___ ___

Train Outlet Damper in the TRAIN A FLTRS HV-9507:

AUTO after MOD position for Places the FHB Exhaust Filter the FHB Exhaust Filter Train Train Outlet Damper control in being placed in service. the MOD position and then (Addendum 28, Step 5) returns the switch to AUTO.

• 9 Close both FHB Exhaust Filter Closes FHB Exhaust Filter ___ ___ ___

Bypass Dampers. Bypass Dampers:

(Addendum 28, Step 6) o FV-9549D o FV-9549C 10 Ensure the FHB Exhaust Air Train A - EXH AIR FROM ___ ___ ___

Flow Controller for the train TRAIN A FLTRS HV-9507:

placed in service modulating to Determines the FHB Exhaust maintain flow between 26,100 Air Flow Controller is controlling and 31,900 CFM. 26,100 - 31,900 cfm.

(Addendum 28, Step 7)

NOTE Opening the relief dampers in the following step will automatically secure the operating FHB Main Supply Fans.

• 11 Open a Relief Damper. Opens Relief Damper: ___ ___ ___

(Addendum 28, Step 8) o FV-9500 OR o FV-9500A 12 Verify all FHB Main Supply Verifies all FHB Main Supply ___ ___ ___

Fans stopped. Fans are stopped (Addendum 28, Step 9)

Page 7 of 10

NRC S7 - rev 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number 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 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

RESPOND TO AN FHB RAD MONITOR ALARM JPM Number: NRC S7 Revision Number: 1 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, 8, 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: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on LOT 21 NRC exam.

Revision 1, Updated Task Standard to be more specific.

Added note about CIP actions.

Revised several JPM steps for clarity. (8/14/2017)

Page 2 of 12

NRC S8 - rev 1 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.

4. Store the IC After IC is Stored and ready to perform JPM

1. For LOT 21 NRC Exam this JPM is scheduled to be performed with JPM S4.

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. Reset ICS computer used by previous applicant so that U1118 is displayed on Point Info

7. 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.

8. 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 12

NRC S8 - rev 1 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. All critical JPM steps (#2, 3, 5, 11, 13, 14, 16, & 19) are completed.

Page 4 of 12

NRC S8 - rev 1 JPM Start Time:

Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE

• 4M08 C-6 PRZR LEVEL DEV HI B/U HTRS ON may come in while performing this JPM due to seal injection. All 0POP09-AN-04M8 actions for this alarm are covered in the steps being performed by the operator already in 0POP04-CV-0004.

• Student may perform CIP actions for Complete Loss of Letdown prior to starting at Step 1 of the procedure. If these steps are not performed per the CIP, then they will be performed during Step 2 RNO actions (JPM step 3). The applicable CIP actions are listed below:

COMPLETE LOSS OF LETDOWN FLOW IF RCS Temperature is greater than 350°F AND all Letdown is lost, THEN PERFORM the following:

a. ENSURE LETDN ORIF HDR ISOL FV-0011 is closed. {CP004}

b. ENSURE CHG FLOW CONT FK-0205 in MAN and CLOSED. {CP004}

c. ENSURE the inservice Centrifugal Charging Pump recirc valve is OPEN. {CP004}

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 step 2

• ICIV MOV-0023 RNO actions.

• OCIV MOV-0024 (Step 2)

Page 5 of 12

NRC S8 - rev 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number PERFORM the following:

• 3 ___ ___ ___

• CLOSE LETDN ORIF HDR

• Closes LETDN ORIF HDR ISOL FV-0011. ISOL FV-0011.

• ENSURE CHG FLOW CONT

• Places CHG FLOW CONT FK-0205 in MAN and FK-0205 in MAN and zero CLOSED. demand.

• OPEN Centrifugal Charging

• Opens CCP 1B(2B)

Pump miniflow valve for RECIRC FCV-0202 operating pump:

• CCP 1A(2A) RECIRC FCV-0201

• CCP 1B(2B) RECIRC FCV-0202

• MAINTAIN RCP seal injection

• Adjusts FLOW CONT HCV-between 6 and 13 gpm using 0218 to lower seal injection FLOW CONT HCV-0218.

• ENSURE all letdown orifice

• Closes 120-150 GPM isolation valves are closed: ORIFICE ISOL VLV 1(2)-CV-FV-0012

• 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-

• Closes LETDN ISOL LCV-0465. 0465

• CLOSE LETDN ISOL LCV-

• Closes LETDN ISOL LCV-0468. 0468

• GO TO Step 4.0.

(Step 2 RNO)

Page 6 of 12

NRC S8 - rev 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number VERIFY Containment Isolation 4 Verifies Containment Isolation ___ ___ ___

Phase A - CLEAR Phase A has not actuated.

(Step 4)

VERIFY Plant Computer Points

• 5 Determines CVTD0024 is NOT ___ ___ ___

CVCS LTDN AREA TEMP TRN normal and performs Step 5

- NORM RNO actions.

• CVTD0023

• CVTD0024 (Step 5) 6 CHECK the following radiation Continues with Step 5 RNO ___ ___ ___

monitors for rising trends or actions.

alarm conditions: (RM-11)

• RT-8010A or RT-8010B, NOTE:

Unit Vent Stack The leak would have been

• RT-8015, MAB Ventilation isolated while performing Step 2 (Step 5 RNO a) RNO.

CUE:

Tell operator another RO checked trends on RT-8010A, 8010B & 8015 and all are currently stable.

7 DISPATCH an Operator and HP Continues with Step 5 RNO ___ ___ ___

to locate the source of the actions.

letdown line break per Addendum 1, HELB Local Actions.

(Step 5 RNO b)

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 7 of 12

NRC S8 - rev 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number 8 IF a break in the letdown line is Goes to Addendum 6, Securing ___ ___ ___

found OR normal letdown can Normal Letdown.

NOT be restored, THEN PERFORM the following:

NOTE:

• SECURE Normal Letdown per Addendum 6, Securing Step 5 RNO c is not applicable.

Normal Letdown.

• PLACE Excess Letdown in service per Addendum 5, Placing Excess Letdown In Service.

• GO TO Step 9.0.

(Step 5 RNO d) 9 Perform Addendum 6

• Performs Addendum 6, ___ ___ ___

NOTE: Securing Normal Letdown Addendum 6 steps will all have

• Then goes to Addendum 5, been previously performed Placing Excess Letdown in during Step 2 RNO actions. Service.

There will be no required valve manipulations during Addendum 6.

NOTE The Caution at the beginning of Addendum 5 states that U1118 will become unreliable when Excess Letdown is put in service. If student informs the Unit Supervisor of the caution, then acknowledge as the US that U1118 will become unreliable while placing Excess Letdown in service.

CHECK CCW In Service To 10 Checks CCW is in service to the ___ ___ ___

The Excess Letdown Heat Excess Letdown Heat Exchanger. Exchanger.

(Addendum 5 Step 1)

PLACE Excess Letdown

• 11 Places DIVERT FV-3123 In ___ ___ ___

DIVERT FV-3123 In The The RCDT Position.

RCDT Position (Addendum 5 Step 2)

Page 8 of 12

NRC S8 - rev 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number CHECK EXCESS/NORMAL 12 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:

As the Plant Operator, report CV-HS-0469 is closed.

OPEN Excess Letdown Heat Opens Excess Letdown Heat

• 13 ___ ___ ___

Exchanger Inlet Isolation Valve Exchanger Inlet Isolation Valve LOOP D ISOL MOV-0083 LOOP D ISOL MOV-0083 (Addendum 5 Step 4)

OPEN Excess Letdown Heat Opens Excess Letdown Heat

• 14 ___ ___ ___

Exchanger Inlet Isolation Valve Exchanger Inlet Isolation Valve ISOL MOV-0082 ISOL MOV-0082 (Addendum 5 Step 5)

MAINTAIN Both Of The 15 Maintains temperature and ___ ___ ___

Following Parameters While pressure within band at the Flushing Excess Letdown Heat Excess Letdown HX while Exchanger: performing the next step.

• Excess Letdown HX OUTL (Addendum 5 step 7)

TEMP TI-0229 - LESS THAN 175°F

• Excess Letdown HX OUTL PRESS PI-0228 - LESS THAN 145 psig (Addendum 5 Step 6)

• 16 Slowly OPEN Excess Letdown Slowly Opens TEMP CONT ___ ___ ___

TEMP CONT HCV-0227 To HCV-0227 to maintain Avoid Thermal Transients temperature and pressure within band at the Excess (Addendum 5 Step 7)

Letdown HX.

Page 9 of 12

NRC S8 - rev 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number ADJUST Excess Letdown And 17 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%) NOTE:

• RCDT pressure (< 6 psig) RCDT level is read on LI-4901 and RCDT pressure is read on (Addendum 5 Step 8) PI-4900 on CP-004. Neither are expected to be out of range.

FLUSH Excess Letdown To The Flushes Excess Letdown to the 18 ___ ___ ___

RCDT For At Least Six (6) RCDT for 6 minutes.

Minutes (Addendum 5 Step 9)

CUE: Time compression 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:

• 19 Places excess letdown ___ ___ ___

• PLACE excess letdown DIVERT FV-3123 in the VCT DIVERT FV-3123 in the position.

VCT position (Addendum 5 Step 10)

CUE This JPM is complete JPM Stop Time:

Page 10 of 12

NRC S8 - rev 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

PLACE EXCESS LETDOWN IN SERVICE JPM Number: NRC S8 Revision Number: 1 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, 11, 13, 14, 16, 19 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 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 12 of 12

STPNOC Job Performance Measure LOCALLY RE-ALIGN CRITICAL MOTOR OPERATED VALVES DURING A LOSS OF ALL AC POWER JPM Number: NRC P1 Revision Number: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on LOT 21 NRC exam.

Revision 1, Removed step for closing CV-MOV-0079 due to this valve being behind a closed door in a contaminated area. (PROC Step 4.c)

Updated Task Standard to be more specific.

Lowered Level of difficulty from 3 to 2. (8/12/2017)

Page 2 of 8

NRC P1 - rev 1 SIMULATOR SETUP INSTRUCTIONS

1. This JPM is performed in the plant.

Page 3 of 8

NRC P1 - rev 1 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 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 by locally manually opening CV-MOV-0112C, CVCS Charging Pumps Suction from the RWST, and locally manually closing CV-MOV-0112B or CV-MOV-0112A, CVCS Volume Control Tank Outlet. All critical JPM steps (#1 & 2) are completed.

Page 4 of 8

NRC P1 - rev 1 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 CV-MOV- ___ ___ ___

MOV-0112C, CVCS 0112C and opens the valve by CHARGING PUMPS SUCTION performing the 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 8

NRC P1 - rev 1 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 CV-MOV- CLOSES either of the following:

0112B, CVCS VOLUME o 1(2)-CV-MOV-0112B, CVCS CONTROL TANK OUTLET VOLUME CONTROL TANK MOV OPERATOR, OR CV- OUTLET MOV OPERATOR MOV-0113A, CVCS VOLUME CONTROL TANK OUTLET o 1(2)-CV-MOV-0113A, CVCS MOV OPERATOR. VOLUME CONTROL TANK OUTLET MOV OPERATOR (Step 3.i)

By performing the following:

Cue:

o Simulates depressing the o Initial Position - OPEN (as declutch lever (the declutch found, for either valve) lever may be held down, but o Final Position - CLOSED 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).

CUE This JPM is complete JPM Stop Time:

Page 6 of 8

NRC P1 - rev 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

LOCALLY RE-ALIGN CRITICAL MOTOR OPERATED VALVES DURING A LOSS OF ALL AC POWER JPM Number: NRC P1 Revision Number: 1 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: 2 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: 10 minutes Actual Time Used: minutes Critical Steps (*) 1 & 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 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 of 0POP05-EO-EC00, Loss of All AC Power.

Page 8 of 8

STPNOC Job Performance Measure STARTUP OF GWPS FOLLOWING PMT JPM Number: NRC P2 Revision Number: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on LOT 21 NRC exam.

Revision 1, Updated Task Standard to be more specific.

Updated cue for JPM step 9.

Added Attachment 1.a for JPM step 6. (8/14/2017)

Page 2 of 15

NRC P2 - rev 1 SIMULATOR SETUP INSTRUCTIONS

1. This JPM is performed in the plant.

Page 3 of 15

NRC P2 - rev 1 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. All critical JPM steps (#4-6, 8, & 9) are completed.

Page 4 of 15

NRC P2 - rev 1 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 15

NRC P2 - rev 1 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 15

NRC P2 - rev 1 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 15

NRC P2 - rev 1 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 this JPM.

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.

• 6 If inlet header oxygen is greater Determines that inlet header ___ ___ ___

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 15

NRC P2 - rev 1 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 15

NRC P2 - rev 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number ATTACHMENT 1 STUDENT HANDOUT Page 10 of 15

NRC P2 - rev 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number ATTACHMENT 1.a STUDENT HANDOUT Page 11 of 15

NRC P2 - rev 1 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 12 of 15

NRC P2 - rev 1 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 is initially CLOSED 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 initial pressure of 0.5 psig. Then report pressure gradually rising, at 0.5 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 13 of 15

NRC P2 - rev 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

STARTUP OF GWPS FOLLOWING PMT JPM Number: NRC P2 Revision Number: 1 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: 15 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 14 of 15

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 15 of 15

STPNOC Job Performance Measure PLACE A 1E BATTERY CHARGER IN SERVICE JPM Number: NRC P3 Revision Number: 1 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 1 Revision Record (Summary)

Revision 0, Drafted JPM for use on LOT 21 NRC exam.

Revision 1, Updated Task Standard to be more specific.

Updated various cues and notes. (8/14/2017)

Page 2 of 12

NRC P3 - rev 1 SIMULATOR SETUP INSTRUCTIONS

1. This JPM is performed in the plant.

Page 3 of 12

NRC P3 - rev 1 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. All critical JPM steps (#5 - 8) are completed.

Page 4 of 12

NRC P3 - rev 1 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.

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.

Page 5 of 12

NRC P3 - rev 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number 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:

Note:

INITIAL: Breaker Handle UP (ON position) Located in 35 EAB, Switchgear Room.

FINAL: Breaker Handle UP (ON position)

• 5 Ensure CLOSED the DC Closes the DC OUTPUT CB-2 ___ ___ ___

OUTPUT CB-2 breaker for the breaker on Battery Charger battery charger being placed in E1B11(E2B11) - 2.

service.

(Step 7.2.4)

Note:

Cue:

If asked about digital DC INITIAL: Breaker Handle voltage indication, the meter will DOWN be blank. At this step there is FINAL: Breaker Handle UP still no power on the battery charger.

Page 6 of 12

NRC P3 - rev 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number

• 6 Ensure CLOSED the AC Closes the AC INPUT CB-1 ___ ___ ___

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 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE Alternate Path Starts Here.

NOTE 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 1 Comment STEP ELEMENT STANDARD SAT UNSAT Number Float Voltage Adjustment Knob Page 9 of 12

NRC P3 - rev 1 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 1 JPM

SUMMARY

Operators Name: Job

Title:

RO SRO JPM

Title:

PLACE A 1E BATTERY CHARGER IN SERVICE JPM Number: NRC P3 Revision Number: 1 Task Number and

Title:

63900, Monitor the DC Electrical Distribution System (Battery, Chargers, Distribution and Power Panel)

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: 20 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

Rev. 3 Appendix D Scenario Outline Form ES-D-1 Facility: South Texas Project Scenario No.: 1 (Spare) Op-Test No.: LOT 21 NRC Examiners: Operators:

Initial Conditions:

• Unit 1 is at 100% Reactor Power. BOL (IC #189)

Turnover:

• The Crew will start FWBP #13 and place FWBP #12 in Auto.

• ESF DG #12, Starting Air Receiver #14 is OOS for Maintenance.

Event Malf. Event Event No. No. Type* Description 1 N/A BOP (N) Start FWBP #13 and place FWBP #12 in Auto.

(0 min)

POSBBARI 2T 30352TCC SRO (TS Breaker trips open on CV-MOV-0079, CVCS SEAL RTN OCIV.

(10 min) (1) Only) 3T See NOTE RO (C) EAB Battery Room Exhaust Fan 11C develops sheared shaft. When (17 min) below SRO (C, RO tries to start Battery Room Exhaust Fan 11B the fan trips.

TS) 4T 05-14-01 BOP (I) Main Steam Header Pressure Transmitter PT-557 Fails to a lower (27min) SRO (I) intermediate position. (Ramped in over 60 seconds) 0.4 5T 50-HV-01 RO (C) PZR PORV RC-PCV-0655A fails open. The block valve for this PZR 1.0 SRO (C) PORV, RC-MOV-001A will have to be closed to prevent a Reactor (37 min) Trip.

(Critical Task) 02-07-03 6 ALL (M) RCS Loop C Low Flow due to RCP 1C sheared shaft. (60 seconds (N/A) 1 after RC-MOV-0001A is closed.)

01-12-02 1 ATWT- Reactor does not trip until Crew manually opens Load Center Breakers for Rod Drive MG Sets (Auto Rx Trip failure is initial condition of Lesson Plan)

(Critical Task) 7 08-06-03 ALL (M) SG 1C Loss of Feedwater inside containment. (6 minutes after (N/A) Reactor Trip breakers are open) 0.5 (Critical Task) 8 Manually RO (C) RCB Atmosphere Radiation Monitor Isolation Valves fail to (N/A) Inserted SRO (C) automatically close. (Initial condition of Lesson Plan)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specification Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 3

3. Major transients (1-2) 2

4. EOPs entered/requiring substantive actions (1-2) 1

5. Entry into a contingency EOP with substantive actions (>1 per 1 scenario set)

6. Preidentified critical tasks (>2) 3 NOTE: Malfunction numbers for Event #3 - Cl_3V111VFM012TFShear - 1 & POSBBARV32733TCC - 1

Rev. 3 STP LOT-21 NRC Scenario #1 Description Initial Conditions: Unit 1 is at 100% Reactor Power. In preparation for an Engineering evaluation of FWBP #12, the Crew is to start FWBP #13 and place FWBP #12 in Auto after taking the watch.

ESF DG #12, Starting Air Receiver #14, is OOS for Maintenance.

Event 1: The BOP will start FWBP #13 and place FWBP #12 in Auto using 0POP02-FW-0001, Main Feedwater.

Event 2: The breaker will trip open for CVCS SEAL RTN OCIV, CV-MOV-0079. The SRO will address Tech Spec implications.

Event 3: EAB Battery Room Exhaust Fan 11C develops sheared shaft. When RO tries to start Battery Room Exhaust Fan 11B the fan trips. The crew will respond using 0POP09-AN-22M3, C3 and D3, BATT ROOM EXH FAN TRBL & BATT RM EXH FLOW LO. The SRO will address Tech Spec implications.

Event 4: Main Steam Header Pressure Transmitter PT-557 Fails to an intermediate position. The Crew will respond using 0POP04-FW-0002, Steam Generator Feed Pump Trip.

Event 5: PZR PORV, RC-PCV-0655A, fails open. The Crew will close the PZR PORV block valve, RC-MOV-0001A, to stop the RCS inventory loss and prevent a Reactor Trip by using 0POP04-RP-0001, Loss of Automatic Pressurizer Pressure Control, and/or 0POP09-AN-04M8 E-5, PRZR PORV OPEN COMMAND. (Critical Task)

Event 6: 60 seconds after RC-MOV-001A is closed in Event 5, RCP 1C develops a sheared shaft but the reactor does not trip. The reactor will trip from the control room when the Crew opens the 480 volt LC breakers that feed the Rod Control MG sets. The Crew will respond using 0POP05-EO-EO00, Reactor Trip or Safety Injection and transition to 0POP05-EO-ES01, Reactor Trip Response if an SI does not occur. (Critical Task)

Event 7: Six (6) minutes after the Reactor trip breakers are opened, a feedwater rupture will develop in containment on SG 1C. The leak will ramp in over 4 minutes. The Crew will transition back to or stay in 0POP05-EO-EO00, Reactor Trip or Safety Injection and then transition to 0POP05-EO-EO20, Faulted Steam Generator Isolation. (Critical Task)

Event 8: During performance of 0POP05-EO-EO00, Reactor Trip or Safety Injection, the crew will notice that the RCB Atmosphere Radiation Monitor Isolation Valves failed to automatically close and will have to use the RNO step to manually close the valves.

Rev. 3 STP LOT-21 NRC Scenario #1 Description Termination: Exit 0POP05-EO-EO20, Faulted Steam Generator Isolation.

Critical Tasks:

• CT-10, With the reactor in an At Power condition, close the block MOV upstream of the stuck open PZR PORV prior to receiving an automatic reactor trip signal.

• CT-1, Manually trips the Reactor from the Control Room before completing Step 1 of 0POP05-EO-EO00, Reactor Trip or Safety Injection.

• CT-17, Isolate a Faulted Steam Generator before transitioning out of 0POP05-EO-EO20, Faulted Steam Generator Isolation.

Source: New

Rev. 3 Appendix D Scenario Outline Form ES-D-1 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:

• ESF DG #12 is OOS for Maintenance.

Event Malf. Event Event No. No. Type* Description 1

N/A RO (C) SFP Pump 1A trips. (60 seconds after crew takes the watch.)

(1 min) SRO (C) 2T 05-22-01 BOP (I) SG 1A controlling Steam pressure channel PT-0514 fails high.

(15 min) SRO (I, TS) 1 3T 01-07-07 RO (R) One Dropped Control Rod M12. The Crew will start a down power to (30 min) BOP (R) less than 75%.

1 SRO (R, TS) 4T 10-14-01 ALL (M) Loss of Offsite Power, 345KV, causes a Reactor Trip.

(50 min) 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 AC (N/A) Power (SBO). (Trips 10 minutes after LOOP)

ALL (M)

(2 Critical Tasks)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specification Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 3

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. Entry into a contingency EOP with substantive actions (>1 per 1 scenario set)

6. Preidentified critical tasks (>2) 3

Rev. 3 STP LOT-21 NRC Scenario #2 Description Initial Conditions: Unit 1 is at 100% Reactor Power. ESF DG #12 is OOS for Maintenance.

Event 1: Spent Fuel Pool (SFP) Cooling Pump 1A will trip. The Crew will respond using 0POP09-AN-22M2, F-6, SFP TROUBLE and start SFP Cooling Pump 1B per 0POP02-FC-0001, Spent Fuel Pool Cooling and Cleanup System.

Event 2: SG 1A controlling Steam pressure channel PT-0514 fails high. The Crew will respond using 0POP04-FW-0001, Loss of Steam Generator Level Control. The SRO will address Tech Spec implications.

Event 3: The unit will experience a dropped Control Rod (M12). The Crew will respond using 0POP04-RS-0001, Control Rod Malfunction. The Crew will start a down power to less than 75%. The SRO will address Tech Spec implications.

Event 4: Loss of Offsite Power (LOOP) causes a Reactor Trip. The Crew will respond using 0POP05-EO-EO00, Reactor Trip or Safety Injection.

Event 5: On the LOOP, ECW PUMP 1A fails to re-start forcing the Crew to have to emergency stop ESF DG #11. (Critical Task)

Event 6: After transitioning to 0POP05-EO-ES01, Reactor Trip Response, ESF DG #13 trips.

This forces the crew to enter 0POP05-EO-EC00, Loss of All AC Power. The 138 KV Emergency Transformer will be available. (2 Critical Tasks)

Rev. 3 STP LOT 21 NRC Scenario #2 Description Termination: When the Crew establishes AFW flow to at least 2 SGs from AFW Pump 14 at a rate of at least 576 gpm.

Critical Tasks:

• CT-9, Manually Trip Diesel Generator prior to the Diesel Generator automatically tripping from an emergency mode trip signal.

• EC00-H, Establishes seal injection flow to RCP seals that have Seal 1 inlet temperatures that are less than 230°F.

• CT-23, Establish 576 GPM AFW flow to the SGs prior to completing step 5.b of 0POP05-EO-EC00, Loss of All AC Power.

Source: New

Rev. 3 Appendix D Scenario Outline Form ES-D-1 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 #189)

Turnover:

• ESF DG #12, Starting Air Receiver #14 is OOS for Maintenance.

Event Malf. Event Event No. No. Type* Description 1 04-01-01 RO (C) Component Cooling Water Pump 1A Sheared Shaft. (60 seconds (0 min) SRO (C, TS) after crew takes the watch.)

1 2T 05-12-03 RO (I)

(20 min) BOP (C) Power Range NI Channel 43 Fails High.

1 SRO (I, TS) 3T 11-01-07 All (R) ISO-Phase Fans trip. Crew will have to perform a Fast Load (45 min) reduction to about 50% power.

0.063 4T 02-01-02 ALL (M) SBLOCA on LOOP B Cold Leg.

(55 min)

.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 Pump (1) 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 and Containment Spray Pumps fail to Auto Start. (Occurs 6 (N/A) minutes after the RCPs have stopped and CCW Pump 1B has been 0.4 started.)

(Critical Task)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specification Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 4

3. Major transients (1-2) 2

4. EOPs entered/requiring substantive actions (1-2) 1

5. Entry into a contingency EOP with substantive actions (>1 per 2 scenario set)

6. Preidentified critical tasks (>2) 3

Rev. 3 STP LOT-21 NRC Scenario #3 Description Initial Conditions: Unit 1 is at 100% Reactor Power. ESF DG #12 is OOS for Maintenance.

Event 1: Component Cooling Water Pump 1A sheared shaft. The Crew will respond using 0POP09-AN-02M3 E-5, CCW HX 1A(2A) OUTL PRESS LO. The SRO will address Tech Spec implications.

Event 2: Power Range Channel NI 43 will fail high. The Crew will respond using 0POP04-NI-0001, Nuclear Instrument Malfunction. The SRO will address Tech Spec implications.

Event 3: ISO Phase Fan 1A trips and ISO Phase Fan 1B fails to start. The Crew will respond by performing a turbine load reduction to about 50% power using 0POP04-TM-0005, Fast Load Reduction.

Event 4: During the load reduction a SBLOCA will occur which will require the Crew to trip the Reactor and perform a Safety Injection. The Crew will respond using 0POP05-EO-EO00, Reactor Trip or Safety Injection and 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant.

(Critical Task)

Event 5: On the Safety Injection, CCW Pump 1B fails to Auto start and CCW fails to transfer to the RCFC coolers on Train B. The Crew must manually start CCW Pump 1B and align CCW to RCFC coolers if RCB temperature is 116°F. (Critical Task)

Event 6: The SBLOCA turns into a LBLOCA with the Containment Spray Pumps failing to Auto Start. The crew will use 0POP09-EO-FRZ1, Response to High Containment Pressure, to manually start the Containment Spray Pumps. (Critical Task)

Rev. 3 STP LOT-21 NRC Scenario #3 Description Termination: When the Crew starts at least 2 Containment Spray Pumps and ensures they are properly aligned with flow to containment.

Critical Tasks:

• CT-16, Manually trip the Reactor Coolant Pumps when RCS pressure is less than 1430 psig and at least one HHSI Pump is injecting during a SBLOCA.

• CT-8, Manually start CCW pump 1B so that two CCW Pumps provide adequate cooling to safeguards trains during a SBLOCA.

• CT-3, Manually start at least one containment spray pump to provide Containment Cooling Source: New

Rev. 3 Appendix D Scenario Outline Form ES-D-1 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 Open Loop Pump #11 and secure Open Loop Pump #12.

• ESF DG #12 is OOS for Maintenance.

Event Malf. Event Event No. No. Type* Description 1

(1 min) N/A BOP (N) Start Open Loop Pump #11 and Secure Open Loop Pump #12. (60 seconds after crew takes the watch.)

2T 02-19-03 RO (I) Controlling Channel of Pressurizer Pressure, PT-0457, fails low.

(6 min)

SRO (I, TS) 0.0 3 POSBBA (N/A) RG2290 SRO (TS) PZR PORV isolation valve, RC-MOV-0001B, loses control power.

4TCC (This malfunction will be inserted 1 minute after PT-0457 fails high.)

1 4T HCPD96 23REV RO (C) CRDM Vent Fan 11A Trouble.

(20 min) 1 SRO (C) 5T 08-28-01 1 BOP (C) LPHD Pump #11 Trip.

(30 min)

SRO (C) 6T 05-03-04 ALL (M) SG 1D Tube Rupture. (~450 GPM & Ramps in over 2 minute period.)

(40 min) 0.44 (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, (TS) Technical Specification Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2 2 Abnormal events (2-4) 4

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. Entry into a contingency EOP with substantive actions (>1 per 0 scenario set)

6. Preidentified critical tasks (>2) 3

Rev. 3 STP LOT-21 NRC Scenario #4 Description Initial Conditions: Unit 1 is at 100% Reactor Power. Due to an issue with Seal Water to Open Loop Pump #12, the Crew is to secure Open Loop Pump #12 after taking the watch.

ESF DG #12 is OOS for Maintenance.

Event 1: The BOP will start Open Loop Pump #11 and secure Open Loop Pump #12 using 0POP02-OC-0001, Open Loop Auxiliary Cooling System.

Event 2: The controlling channel of Pressurizer Pressure, PT-0457, will fail low. The Crew will respond using 0POP04-RP-0001, Loss of Automatic Pressurizer Pressure Control. The SRO will address Tech Spec implications.

Event 3: PZR PORV RC-PCV-0656A isolation valve RC-MOV-0001B loses control power. The SRO will address Tech Spec implications.

Event 4: CRDM Vent Fan 11A will develop a problem that causes a reduction in air flow and require starting CRDM Vent Fan 11C. The Crew will respond using 0POP09-AN-22M1, F-2, CRDM VENT FAN TRBL.

Event 5: LPHD Pump #11 trips. The Crew will respond using 0POP04-CD-0001, Loss of Condensate Flow.

Event 6: A SGTR will occur on SG 1D. The Crew will respond using 0POP05-EO-EO00, Reactor Trip or Safety Injection, and transition to 0POP05-EO-EO30, Steam Generator Tube Rupture.

Event 7: SG 1D FWIV, FW-FV-7144, will fail to automatically close. The crew will have to manually close the valve as part of isolating SG 1D.

Event 8: The Steam Dumps will have an integral failure of the Group 1 cooldown valves. The crew will have to use the SG PORVs to perform the SGTR cooldown below 563°F in 0POP05-EO-EO30, Steam Generator Tube Rupture.

Rev. 3 STP LOT-21 NRC Scenario #4 Description Termination: After the crew secures HHSI pumps Critical tasks:

• CT-18, Isolate Steam and Feedwater to a Ruptured SG.

• CT-20, Depressurize RCS to SI Termination Criteria.

• CT-21, Terminate SI by stopping HHSI Pumps.

Source: New

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 1 of 43 LOT 21 NRC EXAM SIMULATOR OPERATING TEST SCENARIO #1 (SPARE)

Revision 1 Week of 09/25/2017

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 2 of 43 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 #189)

Turnover:

• The Crew will start FWBP #13 and place FWBP #12 in Auto.

• ESF DG #12, Starting Air Receiver #14 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)

POSBBARI30 2T 352TCC SRO (TS Only) Breaker trips open on CV-MOV-0079, CVCS SEAL RTN OCIV.

(10 min) (1) 3T See NOTE RO (C) EAB Battery Room Exhaust Fan 11C develops sheared shaft.

(17 min) below SRO (C, TS) When RO tries to start Battery Room Exhaust Fan 11B the fan trips.

4T 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) 0.4 5T 50-HV-01 RO (C) PZR PORV RC-PCV-0655A fails open. The block valve for this 1.0 SRO (C) PZR PORV, RC-MOV-001A will have to be closed to prevent a (37 min) Reactor Trip.

(Critical Task) 02-07-03 6 ALL (M) RCS Loop C Low Flow due to RCP 1C sheared shaft. (60 (N/A) 1 seconds after RC-MOV-0001A is closed.)

01-12-02 1 ATWT-Reactor does not trip until Crew manually opens Load Center Breakers for Rod Drive MG Sets (Auto Rx Trip failure is initial condition of Lesson Plan)

(Critical Task) 7 08-06-03 ALL (M) SG 1C Loss of Feedwater inside containment. (6 minutes after (N/A) Reactor Trip breakers are open) 0.5 (Critical Task) 8 Manually RO (C) RCB Atmosphere Radiation Monitor Isolation Valves fail to (N/A) Inserted 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 1 Page 3 of 43 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 3

3. Major transients (1-2) 2

4. EOPs entered/requiring substantive actions (1-2) 1

5. Entry into a contingency EOP with substantive actions (>1 per scenario 1 set)

6. Preidentified critical tasks (>2) 3 SCENARIO MISCELLANEOUS INFORMATION INSTRUCTOR NOTES:

• Critical Tasks are indicated by "C-##" in the position column and indicated in bold type. In some instances an

• will indicate that only a portion of the task listed is considered critical.

• Shaded cells indicate procedural entry points.

RECORDED PARAMETERS:

Recorded parameters will be determined during NRC Validation week.

The parameters identified for recording may be of value in evaluating crew performance. Once the scenario is complete for each crew, printout the recorded parameters and label the printout with date, time, crew number and scenario number. See Scenario Instructions section for further details on how to save the Recorded Parameters.

• PZR PORV Block Valve, RC-MOV-0001A Red Light

• OTDT Bistable Light LOOP 1

• OTDT Bistable Light LOOP 3

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 4 of 43 SCENARIO OBJECTIVES Event 1 Objective

• Start a FWBP in accordance with 0POP02-FW-0001.

• Stop a FWBP in accordance with 0POP02-FW-0001.

Event 2 Objective

• Given that a condition exists requiring entry into a Technical Specification, interpret Technical Specifications accurately.

Event 3 Objective

• Respond as the Reactor Operator to EAB HVAC system alarms per the appropriate annunciator response procedures.

• Given that a condition exists requiring entry into a Technical Specification, interpret Technical Specifications accurately.

Event 4 Objective

• Respond to a loss of Steam Generator Feed Pump speed control per 0POP04-FW-0002.

Event 5 Objective

• Respond as the Reactor Operator to Pressurizer Pressure Control system alarms per 0POP09-AN-04M8.

Event 6 Objective

• Respond to a Reactor Trip or Safety Injection in accordance with 0POP05-EO-EO00.

Event 7 Objective

• Respond to a faulted Steam Generator in accordance with 0POP05-EO-EO20.

• Respond to a Containment high pressure condition in accordance with 0POP05-EO-FRZ1.

Event 8 Objective

• Given a Safety Injection, perform Addendum 5 in accordance with 0POP05-EO-EO00.

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 5 of 43 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 Crew will use procedure 0POP02-FW-0001, Main Feedwater, Section 13 & 14, to start FWBP

1. 13 and place FWBP #12 in Auto.

AO Contacts a Plant Operator to verify FWBP #13 Lube Oil and Seal Water are in service.

(Step 13.1)

(CP Watch will report Lube Oil and Seal Water in service.)

BOP Verifies adequate Lube Oil conditions for FWBP

1. 13 by observing Annunciator FW BOOST PMP 13 L.O. AUX PMP TRBL is cleared (not in an alarm condition).

(Step 13.2)

BOP Verifies Deareator Storage Tank level is > 30%

(Step 13.3)

AO May contact a Plant Operator to verify FWBP

1. 13 Lube Oil Reservoir temperatures are > 60

°F.

(This action is from a Procedure NOTE.)

(CP Watch will report Lube Oil Reservoir temperature is 85°F.)

BOP Verifies FWBP #13 is within 50°F of Deareator and downstream temperatures.

(Step 13.4)

AO WHEN starting a FWBP, THEN ENSURE Seal Water Temperature Control Valves are maintaining a relatively constant seal water outlet temperature.

(Step 13.5)

(CP Watch will monitor seal water temperatures after FWBP #13 starts.)

(TGB watch reports they are ready at recirc valve for FWBP #13.)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 6 of 43 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 discharge valve MOV-0456 for FWBP

1. 13.

(Step 13.6)

Verifies the FWBP #13 Start Permissive circuit indicates start permissives are met by:

• Checking Annunciator FW BOOST BOP PUMP TRIP/TROUBLE is NOT in alarm.

7M03 A-8

• Blue Permissive light is ON at 13.8 KV AO Swgr. 1J, Cubicle 9.

BOP

• Plant computer point for FWBP #13 TRIP/TROUBLE indicates Norm.

(Step 13.7)

(CP Watch reports that the Blue Permissive light on 13.8 SWGR 1J, Cubicle 9, is illuminated.)

BOP Starts FWBP #13 using CP-008 control switch and informs Unit Supervisor Pump has been started.

(Step 13.8)

(The BOP operator may contact a Plant Operator to ensure the FWBP is ready for starting before actually starting it.)

AO (CP reports that 13.8 KV SWGR room is clear.)

(TGB watch reports they are ready at recirc AO valve for FWBP #13.)

(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.)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 7 of 43 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 AO Contacts Plant Operator to verify the status of certain auxiliary systems on FWBP #13:

• Aux Oil Pump and Shaft-driven oil pump

• Recirc valve

• Lube Oil Temperature

• Seal Water Temperature Control Valves.

(Steps 13.9 - 13.14)

(CP and TGB watch reports that FWBP #13 is running SAT and Steps 13.9 through 13.14 have been completed SAT with no issues.

These are the last actions associated with starting FWBP #13.)

AO Contacts the Plant Operator to ensure FWBP #12 Aux. Oil Pump is available for securing FWBP

1. 12.

(Step 14.1)

(CP Watch reports that Step 14.1 has been completed SAT with no issues.)

(TGB watch reports they are ready at the recirc valve for FWBP #12.)

BOP Closes FWBP #12 discharge valve, MOV-0457.

(Step 14.2)

BOP After FWBP #12 discharge valve is closed, BOP stops FWBP #12 and informs the Unit Supervisor that the pump has been secured.

(Step 14.3)

(Event # 2 can occur here on signal from Lead Examiner.)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 8 of 43 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 AO Contacts Plant Operator to ensure FWBP #12 Aux Oil Pump has started.

(Step 14.4)

(CP reports that Step 14.4 for FWBP #12 has been completed SAT with no issues.)

BOP Ensures FWBP #12 discharge valve MOV-0457 is closed.

(Step 14.6)

(Step 14.5 was N/A)

(The operator may reopen FWBP #12 discharge valve, MOV-0457, per section 15, Placing a FWBP in Standby)

AO (CP watch reports Blue Permissive light on SWGR 1G, Cubicle 8, is illuminated.)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 9 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 2 (Examiner Trigger)

Event

Description:

Breaker trips open on CV-MOV-0079, CVCS SEAL RTN OCIV.

(No procedure to enter. Used for Technical Specifications ONLY.)

Time Position Required Operator Actions Notes RO Acknowledges By-Pass INOP Alarm on ESF Status Monitoring Lampbox 2M62, CP-002, for CV-MOV-0079, CVCS RCP SL RET MOV-0079.

Also, notices that the position indication lights for the valve have gone out.

AO May call EAB Operator to check status of breaker for C. Breaker E1B2/T2.

(If called, the EAB Operator reports back that the breaker for CV-MOV-0079 has tripped open.)

RO May determine that CV-MOV-0079, CVCS RCP SL RET MOV-0079, has remained open by looking at valve position on the ICS computer.

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 10 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 2 (Examiner Trigger)

Event

Description:

Breaker trips open on CV-MOV-0079, CVCS SEAL RTN OCIV.

(No procedure to enter. Used for Technical Specifications ONLY.)

Time Position Required Operator Actions Notes SRO Determines Technical Specification and/or Technical Requirements Manual (TRM) requirements.

TS 3.6.3 The containment isolation valves shall be OPERABLE with isolation times less than or equal to the required isolation times.

ACTION:

With one or more of the isolation valve(s) inoperable, maintain at least one isolation barrier OPERABLE in each affected penetration that is open AND within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:

a. Restore the inoperable valve(s} to OPERABLE status, or

b. Isolate each affected penetration by use of at least one deactivated automatic valve secured in the isolation position, or check valve with flow through the valve secured or

c. Isolate each affected penetration by use of at least one closed manual valve or blind flange, or

d. Apply the requirements of the CRMP.

(Event 3 can be triggered after the SRO checks Technical Specifications or at the discretion of the Lead Examiner.)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 11 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 3 (Examiner Trigger)

Event

Description:

EAB Battery Room Exhaust Fan 11C develops sheared shaft. When RO tries to start Battery Room Exhaust Fan 11B the fan trips. (TS)

Time Position Required Operator Actions Notes RO Acknowledges and announces the following annunciators on 22M3:

• BATT ROOM EXH FAN TRBL (C-3)

• BATT RM EXH FLOW LO (D-3)

• NON 1E BATT RM EXH FLOW LO (D-4)

(Battery Room exhaust fan trouble will have the operator start the standby fan.)

RO Operator uses 0POP09-AN-22M3, C-3, BATT ROOM EXH FAN TRBL.

RO Determines affected EAB battery room exhaust fan using Plant Computer points.

• HEPD9572 {Train C, EAB BATTERY ROOM EXH FAN 11C(21C)}

(Window C-3, Step 1)

AO Dispatches an operator to the affected EAB battery room exhaust fan to check local fan DP indication.

• 1(2)-HE-PDIS-9572 {72 ft EAB Rm 410}

(Window C-3, Step 2)

(Plant Operator reports back that fan DP is low and EAB Battery Room Exhaust Fan 11C motor is running but the fan is not rotating.)

RO Initiates a Condition Report to investigate the cause of fan trouble.

(Window C-3, Step 3)

RO May transition to 0POP02-HE-0001, Electrical Auxiliary Building HVAC System, to start a backup train and secure the affected train.

(Window C-3, Step 4)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 12 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 3 (Examiner Trigger)

Event

Description:

EAB Battery Room Exhaust Fan 11C develops sheared shaft. When RO tries to start Battery Room Exhaust Fan 11B the fan trips. (TS)

Time Position Required Operator Actions Notes RO Starts BATTERY ROOM EXH FAN 11B (Window C-3, Step 4.a OR 0POP02-HE-0001, Step 7.2.1)

(Fan will trip shortly after starting)

AO (If asked to check EAB Battery Room Exhaust Fan 11B after it has tripped, EAB Watch reports that they dont see any reason why the fan is not running locally, however, the breaker is in the tripped position.)

RO Stops BATTERY ROOM EXH FAN 11C and, after determining that 11B tripped, places both Handswitches in PTL.

(Window C-3, Step 4.b OR 0POP02-HE-0001, Step 7.2.2 and 7.3.2)

(Bypass-INOP alarm windows will illuminate when handswitches are placed in PTL)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 13 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 3 (Examiner Trigger)

Event

Description:

EAB Battery Room Exhaust Fan 11C develops sheared shaft. When RO tries to start Battery Room Exhaust Fan 11B the fan trips. (TS)

Time Position Required Operator Actions Notes SRO Refers to TS 3.3.3.5 for required actions.

(Window C-3, Step 5)

TS 3.3.3.5 (5.e. for EAB HVAC Fans, including Electrical Penetration Space Fans and Battery Room Fans)

The Remote Shutdown System Functions shall be OPERABLE.

ACTION With one or more required channels of one or more Remote Shutdown System Functions inoperable, restore the inoperable Function(s) to OPERABLE status within 30 days, or be in 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

(Per Table B 3.3.5-1, located in the Bases section of TSs, 2 Battery Room Fans are required.

Event 4 can be triggered after SRO has checked TS or at the discretion of the lead examiner.)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 14 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 4 (Examiner Trigger)

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:

• SG STM/FW FLOW MSMTCH on all SGs (The combination of these four alarms is a direct entry for 0POP04-FW-0002, SGFPT Trip.)

BOP Determines Steam Header Pressure PT-0557 has failed.

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 match feedwater flow to steam flow.

(Steps 1 and 2 are immediate action steps. No SGFPTs are tripped for step 1.)

SRO Directs performance of 0POP04-FW-0002, Steam Generator Feed Pump Trip.

BOP Checks SGFPTs - required number running.

(Step 1.0)

BOP Checks SGFP Master Speed Controller:

• Operable in Automatic - determines it is not.

• Places the controller in manual and adjusts output to raise feed flow to match steam flow.

(Step 2.0)

(The PT-557 failure should be revealed during this step if not already done.)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 15 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 4 (Examiner Trigger)

Event

Description:

Main Steam Header Pressure Transmitter PT-557 Fails to a lower intermediate position.

Time Position Required Operator Actions Notes BOP Checks if Feed flow is adequate for current steam demand.

(Step 3.0)

(By now, the BOP operator should have raised the output of the SGFP Master Speed Controller sufficiently to raise feed flow above steam flow.)

(If the operator feeds the SGs at too fast a rate to raise SG levels, annunciator 4M08 B-5, PZR DNBR PRESS LOW, may come in. TS 3.2.5, DNB PARAMETERS, applies while the alarm is in. The ACTION is to restore PZR Pressure within limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce power to

<5% within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.)

BOP Checks SGFP Recirculation Valve status.

(Step 4.0)

(Should be responding in Automatic)

BOP Checks reactor power >5%.

(Step 5.0)

BOP Monitors SG Levels trending to program.

(Step 6.0)

BOP Checks Feedwater/Steam Header DP per Addendum 3 requirements (Step 7.0)

(BOP may have to make manual adjustments to SGFP Master Speed Controller to maintain Feedwater/Steam Header DP per Addendum 3.

For 100% power the DP needs to be about 170psi.)

RO Checks Delta-I is within the required band.

(Step 8.0)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 16 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 4 (Examiner Trigger)

Event

Description:

Main Steam Header Pressure Transmitter PT-557 Fails to a lower intermediate position.

Time Position Required Operator Actions Notes BOP Checks Steam Dumps status:

• 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 C7 TURB IMP PRESS STM DUMP PERMISSIVE (5M24 D-2) light is extinguished.

• Check STEAM DUMP UNBLOCK AVAILABLE light is extinguished.

(Step 9.0)

(The operator will reset C7 if it actuated during the event.)

BOP Checks SGFP speeds are:

• 5400 rpm OR

• 5500 rpm with a flow > 8250 gpm (Step 10.0)

(Event #5 can occur here since SRO and BOP have essentially completed the steps of 0POP04-FW-0002, Steam Generator Feed Pump Trip.)

SRO INITIATE Corrective Action For Failed Component.

(Step 11.0)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 17 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 5 (Examiner Trigger)

Event

Description:

PZR PORV RC-PCV-0655A fails open. The block valve for this PZR PORV, RC-MOV-001A will have to be closed to prevent a Reactor Trip.

Time Position Required Operator Actions Notes RO Acknowledges and announces annunciator on 04M8:

• PRZR PORV OPEN COMMAND E-5 04M7:

• PRT TEMP HI E-1 (Other Annunciators will come in as PZR pressure lowers.)

RO Determines PZR PORV RC-PCV-0655A is open with PZR Pressure Control demand indication less than the opening demand percent output.

(Less than the PZR Pressure Setpoint)

SRO Enters 0POP09-AN-04M8, E-5, for PRZR PORV OPEN COMMAND.

(The SRO may not enter the Annunciator Response Procedure because of the critical nature of having a PZR PORV stuck open at power. Instead the following actions may be directed by the SRO)

RO CHECK Pressurizer Pressure.

(Step 1)

RO IF COMS is armed AND has actuated, THEN GO TO 0POP04-RP-0005, COMS Actuation or Failure.

(Step 2)

(COMS is NOT armed)

RO WHEN Pressurizer pressure decreases to less than 2315 psig, THEN ENSURE the PORV closes.

(Step 3)

(PZR PORV RC-PCV-0655A is open and will NOT close)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 18 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 5 (Examiner Trigger)

Event

Description:

PZR PORV RC-PCV-0655A fails open. The block valve for this PZR PORV, RC-MOV-001A will have to be closed to prevent a Reactor Trip.

Time Position Required Operator Actions Notes RO IF PORV(s) does NOT CLOSE, THEN (CT-10) CLOSE associated PORV Isolation MOV.

(Step 4)

(The operator has about 40 seconds to close RC-MOV-0001A before the reactor will receive an Auto Trip signal on the OTDT setpoint.)

(The critical task is to have closed RC-MOV-001A before getting an Automatic Reactor Trip)

(Annunciator 04M8 D-5, PRZR PORV BLK VLV NOT OPEN, will come in when block valve closes.)

(The next event will be triggered 60 seconds after RC-MOV-0001A is closed.

If the crew does not close RC-MOV-0001A, the reactor will get an auto trip signal. If this occurs the booth operator will insert the next event manually.)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 19 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 6 (Triggers 60 seconds after closing RC-MOV-0001A)

Event

Description:

RCP 1C Sheared Shaft. 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)

RO Determines RCP 1C sheared shaft and the reactor should have tripped but did not.

(The crew will stop RCP 1C)

(If the crew does not diagnose RCP 1C sheared shaft, the Main Turbine still trips from the SSPS signal. The crew may determine the Main Turbine tripped and the reactor should have tripped but did not.)

RO/BOP VERIFY Reactor Trip:

(CT-1) RNO

• Manually TRIP reactor using both denotes reactor trip switches.

critical IF reactor will NOT trip, THEN:

step of * *OPEN 480V LC 1K1(2K1) and 1L1(2L1)

CT feeder breakers.*

• IF reactor will NOT trip, THEN GO TO 0POP05-EO-FRS1, RESPONSE TO NUCLEAR POWER GENERATION -

ATWS, Step 1 AND MONITOR Critical Safety Functions.

• IF reactor trip and bypass breakers DO NOT AO OPEN, THEN DISPATCH an operator to OPEN reactor trip and bypass breakers.

• WHEN the reactor is verified tripped, THEN CLOSE 480V LC 1K1(2K1) and 1L1(2L1) feeder breakers.

(Manual trip will only be successful by de-energizing the Rod Drive MG Sets.)

(Immediate action of Reactor Trip Procedure.)

(After 1 to 2 minutes the EAB watch reports that the Reactor Trip Breakers have been manually opened.)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 20 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 6 (Triggers 60 seconds after closing RC-MOV-0001A)

Event

Description:

RCP 1C Sheared Shaft. Reactor does not trip until Crew manually opens Load Center Breakers for Rod Drive MG Sets.

Time Position Required Operator Actions Notes SRO Directs actions of 0POP05-EO-EO00, Reactor Trip or Safety Injection.

(Event #6 will begin ramping in when Rx trip breakers are open. Crew will re-enter E0 when Event #6 is recognized.)

RO Completes immediate actions of 0POP05-EO-EO00 and determines:

• Reactor is tripped

• Turbine is tripped

• AC ESF Busses are energized

• SI is not actuated (RO will complete immediate actions.

BOP Operator will monitor the plant and make an announcement of the Reactor trip.)

(During a pause between performing immediate actions and verifying immediate actions, the BOP will throttle AFW to reduce the RCS cooldown by:

• Resetting the AFW Reg Valves BOP

• Throttling the AFW Reg Valves to lower total AFW flow.

Total AFW flow must remain above 576 gpm until at least one SG level is >14% NR {34% for adverse containment})

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 Trip Response.

(The crew will continue in ES01 until the feedwater break is recognized and transition is made back to E0)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 21 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 6 (Triggers 60 seconds after closing RC-MOV-0001A)

Event

Description:

RCP 1C Sheared Shaft. Reactor does not trip until Crew manually opens Load Center Breakers for Rod Drive MG Sets.

Time Position Required Operator Actions Notes RO CHECK RCS Temperature Control:

• CHECK RCPs - ANY RUNNING (Step 1.a)

(RCPs 1A, 1B and 1D are only pumps providing forced flow.)

RO MONITOR RCS Temperatures

• WITH ANY RCP RUNNING, RCS TAVG STABLE AT OR TRENDING TO 567oF (Step 1.b)

(RCS temperature should be trending to 567oF if AFW has been throttled to a lower rate.)

BOP Checks RCS TAVG less than 574oF (Step 2.a)

BOP Verifies the following valves CLOSED:

• FWIVs

• FWIBs

• FW preheater bypass valves

• FW regulating valves

• Low Power FW regulating valves (Step 2.b)

BOP Trips all SGFPTs (Step 2.c)

BOP Verifies Feedwater flow to at least 3 steam generators (Step 3)

(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)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 22 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 7 (Triggers 6 minutes after the Reactor Trip Breakers open.)

Event

Description:

SG 1C Loss of Feedwater inside containment.

Time Position Required Operator Actions Notes ALL Recognizes faulted 1C Steam Generator (SG 1C level has been lowering. Tavg and PZR level start to trend back down.)

SRO/RO Manually initiates Safety Injection and Main Steam Line Isolation.

(Auto Safety Injection may occur depending on crew response.)

SRO Re-enters 0POP05-EO-EO00, Reactor Trip or Safety Injection.

RO Completes read through of 0POP05-EO-EO00, Reactor Trip or Safety Injection.

• Reactor Tripped.

• Turbine Tripped.

• AC ESF Busses energized.

• SI is actuated.

(0POP05-EO-EO00, Reactor Trip or Safety Injection Steps 1-4. Read through only.)

BOP VERIFY Proper SI Equipment Operation Per ADDENDUM 5, VERIFICATION OF SI EQUIPMENT OPERATION (Step 5)

(See Actions on pages 29-33)

BOP Per the CIP of 0POP05-EO-EO00, Reactor Trip (CT-17) 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).

If this action is taken the crew will place AFW Pump #13 handswitch in PTL OR close the Train C AFW OCIV, AF-FV-7523, to isolate feedwater flow to SG 1C.

Also see Page 27

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 23 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 7 (Triggers 6 minutes after the Reactor Trip Breakers open.)

Event

Description:

SG 1C Loss of Feedwater inside containment.

Time Position Required Operator Actions Notes RO MONITOR If Containment Spray Is Required:

• Containment pressure GREATER THAN 9.5 PSIG (QDPS)

(RNO)

• PERFORM the following:

• CHECK Containment pressure - HAS EXCEEDED 9.5 PSIG (CP - 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.

(Step 6)

(Containment pressure will be less than 9.5 psig.)

RO CHECK RCP Seal Cooling:

• ENSURE seal injection flow between 6 and 13 gpm (Step 7)

(RO may have to adjust seal injection.)

RO MONITOR RCS Temperatures

• WITH ANY RCP RUNNING, RCS TAVG STABLE AT OR TRENDING TO 567°F OR

• WITHOUT ANY RCP RUNNING, RCS TCOLD STABLE AT OR TRENDING TO 567°F (Step 8)

(RCS temperature may be trending down at this point due to the faulted SG 1C. With Main Steam Isolated there is nothing else the crew can do.)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 24 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 7 (Triggers 6 minutes after the Reactor Trip Breakers open.)

Event

Description:

SG 1C Loss of Feedwater inside containment.

Time Position Required Operator Actions Notes RO CHECK Pressurizer Status:

• PORVs CLOSED RNO

• IF pressure LESS THAN 2235 PSIG AND lowering, THEN:

• Manually close PZR PORVs

• 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 (Step 9)

(Crew should have closed PZR PORV block valve, RC-MOV-0001A, by this time.)

RO MONITOR If RCPs Should Be Stopped:

• HHSI pump - AT LEAST ONE RUNNING

• RCS pressure - LESS THAN 1430 PSIG (RNO)

• GO TO Step 11 (Step 10)

(Reactor Coolant Pump Trip Criteria will probably NOT be met.)

(If the PZR PORV block valve, RC-MOV-0001A, was not closed then RCS pressure will be low enough to require tripping of the RCPs.)

RO VERIFY The Following Containment Isolation Valve - CLOSED

• Seal return isolation valves CLOSE the following valves:

• Containment atmosphere radiation monitor isolation valves (Step 11)

(Event #8 will be realized here. The Containment Atmosphere Radiation Monitor Isolation Valves will have to be manually closed.)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 25 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 7 (Triggers 6 minutes after the Reactor Trip Breakers open.)

Event

Description:

SG 1C Loss of Feedwater inside containment.

Time Position Required Operator Actions Notes RO CHECK If SG Secondary Pressure Boundary Intact:

• CHECK pressures in all SGs -

• CONTROLLED OR RISING

• GREATER THAN 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.

(Step 12)

(Will not transition to a Functional Recovery Procedure until Addendum 5 is complete.)

SRO This next transition is time dependent. It will be done when the following conditions exist:

• After Exiting 0POP05-EO-EO00, Reactor Trip or Safety Injection.

• Addendum 5 of 0POP05-EO-EO00, Reactor Trip or Safety Injection, is completed.

• An ORANGE PATH on the CSF for Containment comes in.

Informs the crew of transition to 0POP05-EO-FRZ1, Response to Containment High Pressure.

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 26 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 7 (Triggers 6 minutes after the Reactor Trip Breakers open.)

Event

Description:

SG 1C Loss of Feedwater inside containment.

Time Position Required Operator Actions Notes RO VERIFY Containment Spray - ESTABLISHED

• Containment Pressure LESS THAN 56.5 PSIG.

• At least one Containment Spray pump -

RUNNING

• Discharge valve OPEN

• FLOW indication

• RETURN TO procedure step in effect and PERFORM this procedure as time permits.

(Step 1)

(Only 2 CS Pumps may be running. The crew may have stopped one per the CIP steps of 0POP05-EO-EO00, Reactor Trip or Safety Injection.)

SRO Informs crew of transition to 0POP05-EO-EO20, Faulted SG Isolation, and to monitor Critical Safety Functions BOP Checks MSIVs and MSIBs closed.

(CT-17)

Note:

This step of the CT is only critical if the MSIVs and MSIBs have not automatically closed yet.

(Step 1)

(0POP05-EO-EO20, Faulted SG Isolation, Step 1)

(This step may already be performed (see page 28, performing EO00 Add 5)

BOP CHECK If Any SG Secondary Pressure Boundary Intact:

• CHECK pressures in all SGs - ANY SG PRESSURE CONTROLLED OR RISING (Step 2)

(SGs A, B and D pressures are controlled. SG C pressure is NOT controlled.)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 27 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 7 (Triggers 6 minutes after the Reactor Trip Breakers open.)

Event

Description:

SG 1C Loss of Feedwater inside containment.

Time Position Required Operator Actions Notes SRO/BO IDENTIFY Faulted SG(s):

P

• CHECK pressure in all SGs -

o ANY SG PRESSURE LOWERING IN AN UNCONTROLLED MANNER OR o ANY SG COMPLETELY DEPRESSURIZED (Step 3)

(SG 1C is faulted)

SRO/BO Isolates the faulted SG (1B)

P

• Verifies all FWIVs closed.

(CT-17)

• Verifies all FWIBs closed.

• Verifies all FW Preheater bypass valves denotes closed.

critical

• Verifies all FW Regulating and Low Power steps of FW Regulating Valves closed.

CT

• Isolates AFW flow to C SG

• Resets SI*

• Resets ESF load sequencers*

• Resets SG LO-LO level AFW actuations*

• Checks SG 1D intact

• Closes C SG AFW OCIV, AF-MOV-0085*

• Verifies SG C PORV closed

• Verifies SG C Blowdown and sample isolation valves closed (Step 4)

(All valves listed get an automatic closed signal.

No malfunctions are inserted on these valves.

AF-MOV-0085 is the only one that requires action by the operator to close.)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 28 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: 7 (Triggers 6 minutes after the Reactor Trip Breakers open.)

Event

Description:

SG 1C Loss of Feedwater inside containment.

Time Position Required Operator Actions Notes BOP Check Secondary Radiation:

• Resets SI

• Resets SG LO-LO level AFW actuations

• Resets SG Blowdown and Sampling Isolations

• Notifies Chemistry to sample all SGs hourly for activity.

• Checks the following Rad Monitors:

o Main Steamline o SG Blowdown o CARS Pump

• WHEN SG sample results are received, THEN VERIFY SG sample activity -

NORMAL (Step 5)

The first 2 resets have already been done so the operator will just check that they are still reset.

SRO Check if SI flow should be terminated

• RCS subcooling - >35°F [45°F]

• Secondary heat sink - NR level in one SG >

14% [34%] OR total AFW Flow > 576 gpm.

• RCS pressure > 1745 psig and stable or rising

• Pressurizer level > 8% [44%]

(Step 6)

If conditions are met, a transition to 0POP05-EO-ES11, SI Termination, will be made.

Conditions will likely NOT be 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 1 Page 29 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: N/A Event

Description:

0POP05-EO-EO00, Addendum 5 Actions.

(Event 8 - The Containment Atmosphere Radiation Monitor Isolation Valves will be manually closed by Addendum 5, Step 13 if not already done.)

Time Position Required Operator Actions Notes BOP VERIFY FW isolation:

• SGFPTs - TRIPPED

• SU SGFP - TRIPPED

• VERIFY the following valves -CLOSED o FWIVs o FWIBs o FW preheater bypass valves o FW regulating valves o Low power FW regulating valves o SG blowdown isolation valves o SG sample isolation valves (EO00 Addendum 5, Step 1)

(0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 5, Verification of Equipment Operation.)

(This addendum is performed in parallel with Steps 5 to 14 of 0POP05-EO-EO00, Reactor Trip or Safety Injection.)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 30 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: N/A Event

Description:

0POP05-EO-EO00, Addendum 5 Actions.

(Event 8 - The Containment Atmosphere Radiation Monitor Isolation Valves will be manually closed by Addendum 5, Step 13 if not already done.)

Time Position Required Operator Actions Notes BOP CHECK if main steamline should be isolated:

(CT-17)

• 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

• VERIFY Main Steamline Isolation:

o MSIVs - CLOSED o MISBs - CLOSED (Step 2)

Note:

This step of the CT is only critical if the MSIVs and MSIBs have not automatically closed yet.

BOP VERIFY AFW system status:

• Motor-driven pump - RUNNING

• Turbine-driven pump - RUNNING (Step 3)

BOP VERIFY AFW valve alignment - PROPER EMERGENCY ALIGNMENT (Step 4)

BOP VERIFY total AFW Flow - GREATER THAN 576 GPM (Step 5)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 31 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: N/A Event

Description:

0POP05-EO-EO00, Addendum 5 Actions.

(Event 8 - The Containment Atmosphere Radiation Monitor Isolation Valves will be manually closed by Addendum 5, Step 13 if not already done.)

Time Position Required Operator Actions Notes BOP VERIFY containment isolation phase A:

• Phase A - ACTUATED

• Phase A valves - CLOSED, REFER TO ADDENDUM 1, PHASE A ISOLATION VERIFICATION (Step 6)

BOP VERIFY ECW status:

• ECW pumps - RUNNING

• ECW pump discharge isolation valves -

OPEN (Step 7)

BOP VERIFY CCW pumps - RUNNING (Step 8)

BOP VERIFY RCFC status:

• RCFCs - RUNNING

• Cooling water - TRANSFERRED TO CCW (Step 9)

BOP VERIFY SI pump status:

• HHSI pumps - RUNNING

• LHSI pumps - RUNNING (Step 10)

BOP VERIFY SI valve alignment - PROPER EMERGENCY ALIGNMENT (Step 11)

BOP VERIFY SI flow:

• RCS pressure - LESS THAN 1745 PSIG

• HHSI pump flow - INDICATED

• RCS pressure - LESS THAN 415 PSIG (RNO)

• GO TO Step 13 of this Addendum.

(Step 12)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 32 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: N/A Event

Description:

0POP05-EO-EO00, Addendum 5 Actions.

(Event 8 - The Containment Atmosphere Radiation Monitor Isolation Valves will be manually closed by Addendum 5, Step 13 if not already done.)

Time Position Required Operator Actions Notes BOP VERIFY containment ventilation 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 (Step 13)

Event #8 failed the Containment atmosphere radiation monitor isolation valves open. The SRO/RO may have already closed the valves when the BOP reaches this step, otherwise the BOP will be required to close the valves now.

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 33 of 43 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 1 Event No.: N/A Event

Description:

0POP05-EO-EO00, Addendum 5 Actions.

(Event 8 - The Containment Atmosphere Radiation Monitor Isolation Valves will be manually closed by Addendum 5, Step 13 if not already done.)

Time Position Required Operator Actions Notes BOP VERIFY ventilation actuation:

• 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 (Step 14)

BOP NOTIFY Unit Supervisor that Addendum 5 is COMPLETE (Step 15)

SRO IMPLEMENT Functional Restoration Procedures as required (Step 16)

SRO RETURN TO procedure step in effect.

(Step 17)

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 34 of 43 CRITICAL TASK

SUMMARY

ACCEPTANCE SAT/

POSITION EXPECTED RESPONSE CRITERIA UNSAT SRO/BOP CT-10 With the reactor in an At CLOSE A PZR PORV BLOCK RC- Power condition, close the MOV-0001A TO ISOLATE STUCK block MOV upstream of the OPEN PZR PORV RC-PCV-0655A stuck open PZR PORV prior to receiving an automatic reactor trip signal.

Failure to close the block MOV under this condition represents a demonstrated inability by the crew to take an action or combination of actions that would prevent a challenge to plant safety.

ALL CT-1 Manually trips the Reactor MANUALLY TRIP THE REACTOR from the Control Room BY OPENING 480V LC 1K1 & 1L1 before completing Step 1 of FEEDER BREAKERS 0POP05-EO-EO00, Reactor Trip or Safety Injection.

Failure to manually trip the reactor causes a challenge to the subcriticality CSF beyond that irreparably introduced by the postulated conditions.

Additionally, it constitutes an incorrect performance that necessitates the crew taking compensating action which complicates the event mitigation strategy and demonstrates the inability by the crew to recognize a failure of the automatic actuation of the RPS.

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 35 of 43 SRO/BOP CT-17 Isolate a Faulted Steam ISOLATE FAULTED SG 1C BY Generator before PERFORMING THE FOLLOWING: transitioning out of 0POP05-

• RESET SI EO-EO20, Faulted Steam

• RESET ESF LOAD SEQUENCER Generator Isolation.

• RESET LO-LO LEVEL AFW ACTUATION Failure to isolate a faulted

• CLOSE SG 1C AFW OCIV, AF- SG that can be isolated MOV-0085 causes challenges to CSFs beyond those irreparably OR introduced by the postulated PLACE AFW PUMP 1C conditions. Also, depending HANDSWITCH IN PTL OR CLOSE upon the plant conditions, it AFW PUMP 1C REG VALVE, AF- could constitute a FV-7523 demonstrated inability by the crew to recognize a failure of Note: 0POP05-EO-EO00, Reactor Trip the automatic actuation of an or Safety Injection CIP has a step to ESF system or component.

isolate a faulted SG early if the crew determines that a Faulted SG needs to Failure to isolate a faulted be isolated. SG can result in challenges to the following CSFs:

• Integrity

• Subcriticality

• Containment (if the break is inside containment)

NOTE: (Per NUREG-1021, Appendix D)

If an operator or the Crew significantly deviates from or fails to follow procedures that affect the maintenance of basic safety functions, those actions may form the basis of a CT identified in the post-scenario review.

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 36 of 43 EXPECTED BOOTH COMMUNICATIONS EVENT 1:

• The Booth Operator should follow along in 0POP02-FW-0001, Main Feedwater, Section 13 and 14.

• CP Watch is stationed at the FWBPs and TGB Watch is at the FWBP recirc valves.

• As a Plant Operator, when called:

• Step 13.1. CP Watch will report Lube Oil and Seal Water in service.

• Procedure Note. CP Watch will report Lube Oil Reservoir temperature is 85°F.

• Step 13.5. CP Watch will monitor seal water temperatures after FWBP #13 starts.

• Step 13.5. TGB watch reports they are ready at recirc valve for FWBP #13.

• Step 13.7. CP Watch reports that the Blue Permissive light on 13.8 SWGR 1J, Cubicle 9, is illuminated.

• Step 13.8. CP reports that 13.8 KV SWGR room is clear. (This is true at any time.)

• Step 13.8. TGB watch reports they are ready at recirc valve for FWBP #13.

• Step 13.9 through Step 13.14. CP and TGB watch reports that FWBP #13 is running SAT and all steps have been completed SAT with no issues.

• Step 14.1. CP Watch reports that Step 14.1 has been completed SAT with no issues.

• Step 14.1. TGB watch reports they are ready at the recirc valve for FWBP #12.

• Step 14.4. CP reports that Step 14.4 for FWBP #12 has been completed SAT with no issues.

• Step 14.6. CP watch reports Blue Permissive light on SWGR 1G, Cubicle 8, is illuminated.

• For this event, communications cues for the TGB and CP watch are listed with the steps for the event starting on Page 5.

EVENT 2:

• As a Plant Operator, when called, report back that the breaker for CV-MOV-0079, Breaker E1B2/T2, has tripped open.

• As Electrical Maintenance or the Duty Maintenance Supervisor, if notified of the issues with CV-MOV-0079, report back that an electrical crew will be assembled for support. No further action is necessary.

• As Operations Manager, acknowledge the issues with CV-MOV-0079. No further action is necessary.

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 37 of 43 EXPECTED BOOTH COMMUNICATIONS (contd.)

EVENT 3:

• As a Plant Operator, when called:

• Window C-3, Step 2. Plant Operator reports back that fan DP is low and EAB Battery Room Exhaust Fan 11C motor is running but the fan is not rotating.

• If asked to check EAB Battery Exhaust Fan 11B after it has tripped, report that you dont see any reason why the fan is not running locally. If asked to check the breaker report that the breaker is in the tripped position.

• As Electrical Maintenance or the Duty Maintenance Supervisor, if notified of the EAB Battery Room Exhaust Fan status, report that an electrical maintenance crew is being assembled for support. No further action is necessary.

• As Operations Manager, acknowledge the EAB Battery Room Exhaust Fan status. No further action is necessary.

EVENT 4:

• There are no expected communications for the Plant Operator with this event.

• As I&C Maintenance or the Duty Maintenance Supervisor, if notified of the status of PT-557, report that an I&C maintenance crew is being assembled for support. No further action is necessary.

• As Operations Manager, acknowledge the failed MS header PT-557 failure. No further action is necessary.

EVENT 5:

• There are no communications expected with this event as it is of very short duration and then event triggers the next even after about 60 seconds.

EVENT 6:

• As a Plant Operator, if asked to open the Reactor Trip Breakers locally, then wait about 1 to 2 minutes and then trigger the lesson plan step to open the Reactor Trip Breakers. See Expected Booth Actions.

EVENT 7:

• There are no communications expected with this event.

EVENT 8:

• There are no communications expected with this event.

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 38 of 43 EXPECTED BOOTH ACTIONS

1. If asked to open the DA High level Dump Valves then trigger the step for DA High Level Dump Valves.

2. If asked to fill the AFWST then trigger the step for AFWST Makeup.

3. When directed to open the Reactor Trip Breakers wait about 1 to 2 minutes, then trigger the step for Open Reactor Trip Breakers.

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 39 of 43 SIMULATOR SETUP NOTE ALL Annunciator Response Procedures (ARPs) must be checked if this scenario is the first to be run on this day. Setup for subsequent runs of this scenario only requires those ARPs that were actually marked in to be checked.

Instructors running the scenario must keep track of which ARPs these are, otherwise, all will have to be checked for subsequent scenarios as well.

Check and clean the following procedures:

0POP02-FW-0001, Main Feedwater 0POP09-AN-22M3, Annunciator Lampbox 22M03 Response Instructions, for C-3, BATT ROOM EXH FAN TRBL, D-3, BATT RM EXH FLOW LO and D-4, NON 1E BATT RM EXH FLOW LO 0POP02-HE-0001, Electrical Auxiliary Building HVAC System 0POP04-FW-0002, Steam Generator Feed Pump Trip 0POP05-EO-EO00, Reactor Trip or SI 0POP05-EO-ES01, Reactor Trip Response 0POP05-EO-EO20, Faulted Steam Generator Isolation 0POP05-EO-FRZ1, Response to High Containment Pressure Additional Annunciator Response Procedures that were used by the Crew during the Scenario.

NOTE SIMULATOR SETUP (contd.)

The LogScenario Lesson Plan into Instructor MUST be Workstation asrun fromuser, lotnrc the left openmost Instructor Orchid (nstpsStation in then server), Simulator Booth to allow for recording and storing of Unlock Initial Conditions Group lotnrc. recorded parameter data.

Log into Instructor Workstation as lotnrc user, open Orchid (nstps server), then Unlock Initial Conditions Group lotnrc.

Reset to IC #189 and perform the following:

Switch Check Ensure red light on end of CP-010 off Ensure ICS Annunciators have stopped counting up

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 40 of 43 SIMULATOR SETUP (contd.)

Go to RUN and perform the following:

Ensure Simulator is ready by performing applicable checkoffs from LOR-GL-0006, LOR Conduct of Simulator Training Guidelines, Addendum 5, Simulator Readiness Checklist.

Ensure VCT Makeup Integrators are set as follows:

Momentarily place RC M/U CONT to STOP and then START to reset BA BATCH/GALLONS and TOT M/U BATCH/GALLONS counters to zero.

Reset BA BATCH/GALLONS setpoint to 0 gallons and reset TOT M/U BATCH/GALLONS setpoint to 10 gallons.

Verify BA Controller Pot setting is 3.85 Hang following ECO Caution Tags:

Tape an ECO Caution Tag next to PI-5532A for Starting Air Receiver #14 on ESF DG #12.

Open lesson plan for Scenario 1 in lotnrc directory for LOT 21, then EXECUTE lesson plan. These actions will set up any initial conditions for the scenario.

If this scenario IC has changing conditions (i.e. Xenon is changing, etc.), then place the simulator in FREEZE, otherwise it is OK to leave in RUN.

Run the scenario in accordance with the next section, Scenario Instructions.

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 41 of 43 SCENARIO INSTRUCTIONS NOTE Steps 1 to 4 below can be performed in the LOR Debrief Room prior to the crew coming into the Simulator provided exam security measures are taken.

1. Provide Shift Turnover sheets to the crew and review the information.

2. Have the Crew perform a Pre-Job Brief for swapping FWBPs from #12 to #13. Ensure the candidates dont have any other questions about the Shift Turnover.

3. Ensure the Beacon book from the simulator is available to the crew if they are in the LOR Debrief Room.

4. Review the Simulator Differences list with the crew if needed.

5. When signaled by Simulator Staff, have the crew perform their board walkdown and inform the floor instructor when ready to take the watch.

6. Ensure the simulator is in RUN and verify simulator clock is set correctly. Note the time that the Crew takes the watch. ________________ Start Time.

NOTE Malfunction Step and/or Lesson Plan Steps (Events) are triggered upon the Lead Examiners signal during the scenario unless an agreed upon time is discussed with the examiner prior to the start of the scenario.

Always TRIGGER events in the Simulator Scenario Lesson Plans. This way delays associated with events will take place as intended.

Refer to EXPECTED BOOTH COMMUNCATIONS and EXPECTED BOOTH ACTIONS Sections for instructions for Instructor actions during the scenario.

7. Trigger the step titled Start Chart and ensure specified Recorded Parameters for the scenario begin recording as the scenario runs. If the chart speed is NOT set to 5400 seconds (90 minutes) then perform the following:

Under CHARTS click on SET TIME In the dialog box enter 5400 seconds (90 minutes)

Click OK.

8. The crew will perform Event #1. (Booth operator needs to have 0POP02-FW-0001, Main Feedwater, Section 13 and 14 available. See Booth Communications)

9. Trigger MALFUNCTION STEP - This will insert Step #1, Event #2.

10. Trigger STEP 2 - Event #3

11. Trigger STEP 3 - Event #4

12. Trigger STEP 4 - Event #5

13. Place simulator in FREEZE when cued by the Lead Examiner to terminate scenario.

14. DO NOT RESET simulator until the steps on the next page are completed and all Examiners have completed Follow-Up Questioning.

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 42 of 43 SCENARIO INSTRUCTIONS (contd.)

NOTE Some scenarios will have more than one chart. For these, each chart file must be separately saved with a unique filename.

15. Saving Recorded Parameters Data Click on the Charts icon on the left side of the screen Select Pause icon, then select All Click on the Print Chart icon, then select All This will bring up a window in the TASK BAR called PRIMOPDF.

Click on Create PDF This will bring up a File Save As window.

Save to folder c:\Users\lotnrc\Desktop\LOT21 Charts. The file name will be LOT21 Scenario 1 followed by a name that identifies the crew (e.g. Crew A).

Save the new file. It will be saved in a folder already on the desktop. LOT21 Charts.

16. Saving Scenario SAM (Simulator Action Monitor)

Under TOOLS click on SAM In the dialog box that comes up click on SAVE TO Save as a TEXT FILE to folder c:\Users\lotnrc\Desktop\LOT21 Charts. The file name will be LOT21 SAM INFO Scenario 1 followed by a name that identifies the crew (e.g. Crew A).

LOT 21 NRC OP-TEST SCENARIO #1 Rev 1 Page 43 of 43 TURNOVER INFORMATION Reactor Power is at 100%.

• In preparation for an Engineering evaluation of FWBP #12 next shift, the Crew is to start FWBP #13 and place FWBP #12 in Auto after taking the watch.

CP and TGB watch have been briefed on the start of FWBP #13 and securing FWBP #12.

All FWBP #13 pre-start conditions have been verified by the CP watch. (i.e. Steps 13.1, Lube Oil & Seal Water in service with Lube Oil Reservoir temperature 85°F, 13.5, All Seal Water temperatures are 140°F and stable, 13.7, Blue Permissive Light on 13.8 SWGR cubical is aluminated.)

13.8 KV SWGR is clear of personnel.

The TGB watch is standing by FWBP #13 recirc valve.

• ESF DG #12, Starting Air Receiver #14 is out of service for maintenance.

• 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.

• RCS Boron Concentration is 1408 ppm.

• 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.

• No ESF DG FOSTs are on recirc.

LCO Actions:

None.

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 1 of 39 LOT 21 NRC EXAM SIMULATOR OPERATING TEST SCENARIO #2 Revision 1 Week of 09/25/2017

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 2 of 39 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:

• ESF DG #12 is OOS for Maintenance.

Event No. Malf. No. Event Type* Event Description 1

N/A RO (C) SFP Pump 1A trips. (60 seconds after crew takes the watch.)

(1 min) SRO (C) 2T 05-22-01 BOP (I) SG 1A controlling Steam pressure channel PT-0514 fails high.

(15 min) SRO (I, TS) 1 3T 01-07-07 RO (R) One Dropped Control Rod M12. The Crew will start a down (30 min) BOP (R) power to less than 75%.

1 SRO (R, TS) 4T 10-14-01 ALL (M) Loss of Offsite Power, 345KV, causes a Reactor Trip.

(50 min) 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 (M) ESF DG #13 trips. Crew will enter 0POP05-EO-EC00, Loss of All (N/A) AC Power. (Trips 10 minutes after LOOP)

(2 Critical Tasks)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor.

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 3 of 39 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 3

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. Entry into a contingency EOP with substantive actions (>1 per scenario 1 set)

6. Preidentified critical tasks (>2) 3 SCENARIO MISCELLANEOUS INFORMATION INSTRUCTOR NOTES:

• Critical Tasks are indicated by "C-##" in the position column and indicated in bold type. In some instances an

• will indicate that only a portion of the task listed is considered critical.

• Shaded cells indicate procedural entry points.

RECORDED PARAMETERS:

Recorded parameters will be determined during NRC Validation week.

The parameters identified for recording may be of value in evaluating crew performance. Once the scenario is complete for each crew, printout the recorded parameters and label the printout with date, time, crew number and scenario number. See Scenario Instructions section for further details on how to save the Recorded Parameters.

• Diesel Generator 11 PTL Switch

• Diesel Generator 11 RPMs

• Positive Displacement Pump Red Light

• Seal 1 Inlet Temp for RCP 1A

• Seal 1 Inlet Temp for RCP 1B

• Seal 1 Inlet Temp for RCP 1C

• Seal 1 Inlet Temp for RCP 1D

• Seal Flow for RCP 1A

• Seal Flow for RCP 1B

• Seal Flow for RCP 1C

• Seal Flow for RCP 1D

• AFW Train A Flow

• AFW Train B Flow

• AFW Train C Flow

• AFW Train D Flow

• AFW Pump 14 Cross-Connect Valve, AF-FV-7518 Red Light

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 4 of 39 SCENARIO OBJECTIVES Event 1 Objective

• Respond as the Reactor Operator to Spent Fuel Pool Cooling and Cleanup system alarms per the appropriate annunciator response procedures.

Event 2 Objective

• Respond to a loss of Steam Generator Level Control per 0POP04-FW-0001.

• As necessary, transfer controlling Steam Flow channels per 0POP04-FW-0001.

• Given that a condition exists requiring entry into a Technical Specification, interpret Technical Specifications accurately.

Event 3 Objective

• Respond to a stuck or dropped Control Rod in accordance with 0POP04-RS-0001.

• Given that a condition exists requiring entry into a Technical Specification, interpret Technical Specifications accurately.

Event 4 Objective

• Respond to a Reactor Trip or Safety Injection in accordance with 0POP05-EO-EO00.

• Respond to a Reactor Trip per 0POP05-EO-ES01.

Event 5 Objective

• Determine from indications that an Essential Cooling Water Pump has tripped.

Event 6 Objective

• Respond to a Loss of All AC Power in accordance with 0POP05-EO-EC00.

• Start the Positive Displacement Charging Pump when required during Loss of All AC Power event.

• During all modes of plant operating conditions, operate the Auxiliary Feedwater System in accordance with the plant operating procedures.

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 5 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 1 (Will trigger 60 seconds after taking the watch.)

Event

Description:

Spent Fuel Pool (SFP) Cooling Pump 1A trips.

Time Position Required Operator Actions Notes RO Acknowledges and announces the following annunciator from 22M2:

• SFP TROUBLE (F-6)

SRO Determines that SFP Pump 1A has tripped and performs the steps in the Annunciator Response procedure for SFP TROUBLE.

(0POP04-FC-0001, Loss of Spent Fuel Pool Level or Cooling, may be entered but this procedure is better used for an extended period of a loss of SFP cooling when SFP temperatures are starting to rise.)

RO CHECK the following Plant Computer points:

• FCQD1406A (SFP Cooling Pump 1A(2A) Trip)

(Step 1)

(There are several other ICS points to check for this step.)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 6 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 1 (Will trigger 60 seconds after taking the watch.)

Event

Description:

Spent Fuel Pool (SFP) Cooling Pump 1A trips.

Time Position Required Operator Actions Notes AO IF the alarm is due to a trip of the Spent Fuel Pool Cooling Pump, THEN PERFORM the following:

• 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 RO Cooling Pump Per 0POP02-FC-0001, Spent Fuel Pool Cooling and Cleanup System.

(Step 5)

AO (MAB Watch will report that SFP Pump 1A has an acrid smell at the motor.)

(EAB Watch will report that the breaker is open and has an over current flag actuated.)

SRO 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 Section 6.2, Securing Spent Fuel Pool Cooling Pumps.

(Step 6.1.1)

AO ENSURE Purification is secured per Section 7.3, Securing SFPCCS Purification.

(Step 6.2.1)

(The MAB Watch will report that the SFPCCS purification is NOT in service.)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 7 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 1 (Will trigger 60 seconds after taking the watch.)

Event

Description:

Spent Fuel Pool (SFP) Cooling Pump 1A trips.

Time Position Required Operator Actions Notes RO STOP the desired SFP 1A AND PLACE its handswitch in "PTL"

• "SFPCP 1A(2A)"

(Step 6.2.2)

(Since SFP Pump 1A had already tripped the operator will put the handswitch in PTL.)

(A By-Pass INOP alarm will come in when the handswitch is placed in PTL.)

AO ENSURE the "SFP COOLING PUMP DISCHARGE VALVE" in the train which will remain idle is CLOSED.

• Pump 1A(2A) [idle] "1(2)-FC-0010A" (Step 6.2.3)

(The MAB Watch will report that 1-FC-0010A is closed after about 1 minute.)

RO RESTORE auto operation of the 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)

(Step 6.2.4)

RO ENSURE the applicable plant computer point is off scan for SFPCP that is secured, as applicable:

• "SFPCP 1A(2A)" FCUD1406A (Step 6.2.5)

(This step will clear the BYPASS INOP alarm that came in when SFP Pump 1A was placed in PTL.)

(After this step operator will transition back to step 6.1.2.)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 8 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 1 (Will trigger 60 seconds after taking the watch.)

Event

Description:

Spent Fuel Pool (SFP) Cooling Pump 1A trips.

Time Position Required Operator Actions Notes AO ENSURE the "SFP COOLING PUMP DISCHARGE VALVE"(s) for the train(s) being placed in service is OPEN.

• SFPCP 1B(2B) "1(2)-FC-0010B" (Step 6.1.2)

(The MAB Watch will report that 1-FC-0010B is open after about 1 minute.)

AO VERIFY the pump shaft has stopped rotating for the SFPC Pump that will be started.

• "SFPCP 1B(2B)"

(Step 6.1.4)

(Step 6.1.3 was already performed in Step 6.2.3 so it is N/A.)

(The MAB Watch will report that the shaft for SFP Pump 1B is NOT rotating.)

RO START the desired SFPCP, as follows:

IF single train operation is desired, THEN START the selected SFPCP.

• "SFPCP 1B(2B)"

(Step 6.1.5.2)

AO THROTTLE the applicable "SFP HEAT 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)

• SFP HX 1B(2B) "1(2)-FC-0011B" on "1(2)-FC-FI-1408" (Step 6.1.6)

(The MAB Watch will report that SFP Pump 1B discharge flow has been throttled to 2800gpm. After about 1 minute.)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 9 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 1 (Will trigger 60 seconds after taking the watch.)

Event

Description:

Spent Fuel Pool (SFP) Cooling Pump 1A trips.

Time Position Required Operator Actions Notes AO VERIFY the applicable SFP HX outlet temperature(s) less than 110°F. (36 ft FHB SFPC HX Rm)

• SFP HX 1B(2B) "1(2)-FC-TI-1410" (Step 6.1.7)

(The MAB watch will report that SFP HX outlet temperature is 90°F.)

RO ENSURE the applicable plant computer point(s) are on scan for running SFPCP(s) AND off scan for secured pump(s), as applicable.

• "SFPCP 1B(2B)" FCUD1408A (Step 6.1.8)

(ICS point for SFP Pump 1A was taken off scan in step 6.2.5.)

(The crew will put SFP Pump 1B computer point back on scan.)

AO PERFORM Lineup 3, Restoration of SFPC Pumps.

(Step 6.1.9)

(Lineup 3 ensures the SFP Pump discharge valves are closed unless the associated pump is running. The MAB Watch will report that they will perform lineup 3.)

(Event 2 can be triggered on a signal from the lead examiner.)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 10 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 2 (Examiner Trigger)

Event

Description:

SG 1A controlling Steam pressure channel PT-0514 fails high. (TS)

Time Position Required Operator Actions Notes BOP Acknowledges and announces the following annunciator from 06M3:

• SG 1A STM/FW FLOW MSMTCH (E-3)

(The Annunciator Response procedure will send the crew to 0POP04-FW-0001, Loss of Steam Generator Level Control, since this is the only alarm that came in.)

BOP Determines SG 1A Controlling Pressure Channel PT-0514 fails low.

Performs immediate actions of 0POP04-FW-0001:

• 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%.

(Immediate Action)

SRO Directs actions of 0POP04-FW-0001, Loss of Steam Generator Level Control.

BOP CHECK SG Feedwater Regulating Valve(s) - RESPONDING IN AUTOMATIC

• SG 1A(2A) "NORM FCV-0551" (Step 1.0)

(This step was an immediate action and should already be performed.)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 11 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 2 (Examiner Trigger)

Event

Description:

SG 1A controlling Steam pressure channel PT-0514 fails high. (TS)

Time Position Required Operator Actions Notes BOP CHECK SGFP Speed Controllers -

RESPONDING IN AUTOMATIC (Step 2.0)

(This step is an immediate action and the failure does affect the SGFP Master Speed Controller P setpoint. However, the failure only slightly affects the setpoint for the controller. The crew may decide to leave the controller in auto to keep from having two controllers in manual. The controller setpoint will return to normal when SG 1C MFRV steam flow input is selected to the alternate channel.)

BOP CHECK Main Feedwater Regulating 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 (Step 3.0)

BOP CHECK Low Power Feedwater Regulating Valves:

(Step 4.0)

(LPFRVs are not in service.)

SRO/BOP CHECK SGFP Master Speed Controller -

IN MANUAL (Step 5.0)

(If the crew placed the SGFP Master Speed controller in manual they will ensure it is working properly in manual per Step 6.0. Otherwise the crew will continue to Step 7.0.)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 12 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 2 (Examiner Trigger)

Event

Description:

SG 1A controlling Steam pressure channel PT-0514 fails high. (TS)

Time Position Required Operator Actions Notes BOP CHECK SGFP Master Speed Controller

- RESPONDING IN MANUAL (Step 6.0)

(This step is skipped if the controller is still in AUTO.)

BOP CHECK Individual SGFP Speed Controllers - ANY IN MANUAL (Step 7.0)

(Controllers should be in Auto.)

BOP MONITOR Feedwater/Steam Header DP-

• GREATER THAN OR EQUAL TO DP REQUIRED BY Addendum 1 OR

• SGFP Master Speed Controller At 100%

(Step 9.0)

(If the Master Speed Controller was placed in Manual then the crew may adjust to the correct P. However, this failure does not create a drastic effect on controller response if left in Auto.)

(P for 100% power is about 170psid.)

BOP RESTORE Affected SG NR Level(s) To Between 68% And 74%

(Step 10.0)

BOP MONITOR SG NR Levels - GREATER THAN 20%

(Step 11.0)

BOP MONITOR SG NR Levels - LESS THAN 87.5%

(Step 12.0)

BOP CHECK SG NR Level Indicators - ALL OPERABLE (Step 13.0)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 13 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 2 (Examiner Trigger)

Event

Description:

SG 1A controlling Steam pressure channel PT-0514 fails high. (TS)

Time Position Required Operator Actions Notes BOP CHECK Feedwater Flow Transmitters -

ALL OPERABLE (Step 14.0)

BOP CHECK Steam Flow Transmitters - ALL OPERABLE RNO SELECT the operable steam flow channel for affected SG(s) level control.

(Step 15.0)

(A failure of the steam pressure transmitter will affect the steam flow transmitter. Select FT-513 for control in one of the next 2 steps.)

BOP CHECK Steam Pressure Transmitters -

ALL OPERABLE RNO SELECT the operable steam flow channel for affected SG(s) level control.

(Step 16.0)

BOP CHECK SG NR Levels - BETWEEN 68% And 74%

(Step 17.0)

BOP CHECK Main Feedwater Regulating And Low Power Feedwater Regulating Valves Automatic Control - OPERABLE (Step 18.0)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 14 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 2 (Examiner Trigger)

Event

Description:

SG 1A controlling Steam pressure channel PT-0514 fails high. (TS)

Time Position Required Operator Actions Notes BOP CHECK Main Feedwater Regulating OR Low Power Feedwater Regulating Valve(s) - IN AUTO

• SG 1A(2A) "NORM FCV-0551" (RNO)

WHEN SG levels return to between 68% and 74%, THEN PERFORM the following:

• PLACE in-service Feedwater Regulating Valve(s) with operable Automatic Control in Auto.

• MONITOR proper operation of Feedwater Regulating Valve(s) in Auto.

(Step 19.0)

BOP CHECK SGFP Master Speed Controller -

IN AUTO (Step 20.0)

(If the Master Speed Controller was placed in Manual, then it can now be placed back in Auto.)

SRO TAKE Appropriate Actions Per Technical Specifications.

• TS 3.3.2.1.f Compensated Steam Line Pressure - Low Action 20

• TS 3.3.2.4.e. Compensated Steam Line Pressure - Low Action 20 (Step 21.0)

(Most Limiting Action:

Place the failed channel 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 />. See full action on next page.)

(Event #3 may be triggered after the SRO refers to Tech Specs.)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 15 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 2 (Examiner Trigger)

Event

Description:

SG 1A controlling Steam pressure channel PT-0514 fails high. (TS)

Time Position Required Operator Actions Notes SRO NOTIFY I&C To Place The Affected Channel In Trip Or Bypass. REFER TO Addendum 2, Procedure List For The Appropriate Procedure (Step 22.0)

SRO INITIATE Corrective Actions For Failed Component (Step 23.0)

TS 3.3.2.1.f, 3.3.2.4.e Action 20 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 1 Page 16 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 3 (Examiner Trigger)

Event

Description:

One Dropped Control Rod M12. (TS)

Time Position Required Operator Actions Notes RO Acknowledges and announces the following Annunciators on:

05M2:

• T AVG/AUCT T AVG DEV (C-6)

• DT/AUCT DT DEV (D-6) 05M3:

• PR UPPER DET FLUX DEV HI/AUTO DEF (A-3)

• RPI TROUBLE (A-5)

• PR LOWER DET FLUX DEV HI/AUTO DEF (B-3)

• PR CHANNEL DEV (C-3)

• ROD SUPV MNTR ROD POSITION TRBL (D-5)

• ROD BOTTOM (F-4)

RO Diagnoses Rod M12 has dropped into the core, informs the SRO.

(Rod M12 is in Control Bank D)

RO Performs immediate actions of 0POP04-RS-0001, Control Rod Malfunction.

• Ensures Rod Control in Manual.

• Ensures no rod motion.

• Checks that only 1 rod dropped.

(Step 1.0, 2.0 & 3.0)

SRO Directs the actions of 0POP04-RS-0001, Control Rod Malfunction.

SRO/RO Verify Immediate Actions complete and transitions to Addendum 1, Recovery of a Dropped Rod.

(Steps 1-3)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 17 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 3 (Examiner Trigger)

Event

Description:

One Dropped Control Rod M12. (TS)

Time Position Required Operator Actions Notes 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.)

(The alarm comes in at a PZR pressure less than 2200°F.)

(TS 3.2.5. Raise PZR pressure above 2200°F within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.)

RO VERIFY Reactor Power GREATER THAN 5% Power (Addendum 1, Step 1)

RO Check Tavg Within 1.5oF Of Tref RNO MAINTAIN Tavg Within 1.5oF Of Tref By Adjusting The Following As Necessary While Maintaining Reactor Power Stable:

• ADJUST Turbine load

• ADJUST RCS boron concentration

• IF Turbine is offline, THEN ADJUST demand on the Steam Generator PORVs OR Steam Dumps.

(Addendum 1, Step 2)

(Due to the position of Control Rod M12 in the core, Tavg will not be within 1.5oF of Tref.)

(Crew may also start to adjust turbine load at this time to address T power on 3 channels being 101% power.)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 18 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 3 (Examiner Trigger)

Event

Description:

One Dropped Control Rod M12. (TS)

Time Position Required Operator Actions Notes ALL NOTIFY The Following Of The Rod Malfunction:

• Reactor Engineering Supervisor

• Plant Operations Manager

• I&C Maintenance (Addendum 1, Step 3)

(Plant Operations Manager will report that they have talked to I&C and determined that a downpour should commence to a level determined by the procedure.)

(I&C will report that it will take 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to get a qualified technician for the Rod Control System onsite.)

(Reactor Engineering will report that they can provide support as needed.)

SRO DOCUMENT Appropriate Entry Into Technical Specification Action Statement 3.1.3.1.b.3 In The Control Room Log As Applicable (Addendum 1, Step 4)

(Due to the need to reduce power to less than 75% the lead examiner may need to ask the student about the Tech Spec after the scenario.)

SRO/RO Record data for dropped rod.

• 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 (Addendum 1, Step 5)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 19 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 3 (Examiner Trigger)

Event

Description:

One Dropped Control Rod M12. (TS)

Time Position Required Operator Actions Notes SRO Determine if reactor power reduction is required.

(Addendum 1, Step 6)

(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 75% Per 0POP03-ZG-0006, Plant Shutdown From 100% To Hot Standby or 0POP03-ZG-0008, Power Operations.

(Addendum 1, Step 7)

Event #4 can be triggered after the down power has started and the lead examiner is satisfied with observation.

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 20 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 3 (Examiner Trigger)

Event

Description:

One Dropped Control Rod M12. (TS)

Time Position Required Operator Actions Notes Tech Spec Action: 3.1.3.1.b.3

b. 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 1 Page 21 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 4 & 5 (Examiner Trigger)

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 on 10M1 and 10M2 due to the Loss of Offsite Power and determines the Reactor has tripped.

• 10M1 480V LC TROUBLE F1 to F8

• 10M2 480V LC TROUBLE F1 to F8 SRO Enters and directs the actions of 0POP05-EO-EO00, Reactor Trip or Safety Injection.

RO Completes immediate actions of 0POP05-EO-EO00 and determines:

• Reactor is tripped

• Turbine is tripped

• AC ESF Busses are energized

• SI not actuated or required (Steps 1-4)

(RO will announce status of immediate action steps as he/she performs them.)

(BOP Operator will monitor the plant and make an announcement of the Reactor trip.)

(CIP will have crew isolate Main Steam due to the loss of the secondary.)

RO Recognize ESF DG 11 is running without (CT-9) cooling water and perform the following:

• Attempt to start ECW Pump 1A

• Secure ESF DG 11 (The Crew may perform these actions at any time the condition is recognized and must be performed prior to ESF DG 11 tripping to meet the CT.)

AO (If operators are dispatched, the Yard watch will report that ECW Pump 1A has an acrid smell coming from the motor and the EAB watch will report that the breaker for ECW Pump 1A indicates an over current.)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 22 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 4 & 5 (Examiner Trigger)

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 SRO Directs/ensures the immediate actions of 0POP05-EO-EO00, Reactor Trip or Safety Injection, have been completed by performing a procedure read through of them.

SRO Enters and directs the actions of 0POP05-EO-ES01, Reactor Trip Response.

(This transition is based on 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.)

RO MONITOR RCS Temperatures -

• WITHOUT ANY RCP RUNNING, RCS TCOLD STABLE AT OR TRENDING TO 567°F RNO IF temperature GREATER THAN 567°F AND rising, THEN:

• IF condenser NOT available, THEN ENSURE SG PORVs controlling temperature in AUTO.

(Step1.b)

(RCS temperature will likely be rising after the LOOP. SG A, B & D PORVs will have to be controlled in manual due to no power on A & B ESF Busses.)

(Event #6 may be triggered at the discretion of the Lead Examiner provided ESF DG 11 has been secured. The event is set on a ten minute timer from the time of the LOOP)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 23 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 4 & 5 (Examiner Trigger)

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 BOP CHECK FW Status:

• CHECK RCS TAVG - LESS THAN 574°F

• VERIFY FW isolation:

o FWIVs - CLOSED o FWIBs - CLOSED o FW preheater bypass valves -

CLOSED o FW regulating valves - CLOSED o Low Power FW regulating valves

- CLOSED

• TRIP all SGFPTs (Step 2.a, b & c)

(All valves should be closed and the SGFPTs will already be tripped due to the LOOP.)

BOP VERIFY Feedwater Flow Established To GREATER THAN OR EQUAL TO Three (3) SGs:

• Main Feedwater flow OR

• AFW flow (Step 3)

(Only AFW flow is available.)

RO VERIFY CONTROL Rods Fully Inserted

• All rod bottom lights - LIT (Step 4)

RO/BOP CHECK STBY DG Status:

(CT-9)

• STBY DG - RUNNING

• VERIFY ECW to STBY DG RNO If ECW can NOT be established to the running STBY DG, then TRIP the affected STBY DG.

(Step 5)

(If not already performed, Crew will attempt to start ECW Pump 1A and then secure ESF DG 11.)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 24 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 4 & 5 (Examiner Trigger)

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 CHECK Pressurizer Level CONTROL:

• Pressurizer level - GREATER THAN

• 17%

• VERIFY charging - IN SERVICE

• CHECK RCP seal injection flow -

• NORMAL

• VERIFY letdown - IN SERVICE

• Pressurizer level trending to 25%

(Step 6)

(If not already done, Event #6 is triggered here. The event is set on a ten minute timer from the time of the LOOP)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 25 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 6 (Event is triggered 10 minutes after the LOOP)

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-energized after ESF DG #13 trips.

The following annunciators would reveal the trip of ESF DG #13 on 03M3:

• DG 13 TRBL (A-8)

• 4KV E1C U/V ALERT (C-8)

(If operators are dispatched, the EAB AO watch will report that ESF DG #13 has an annunciator, GENERATOR DIFFERENTIAL, at the local panel.)

SRO Enters and directs the actions of 0POP05-EC-EC00, Loss of All AC Power.

RO Completes immediate actions of 0POP05-EO-EC00 and determines:

• Reactor is tripped

• Turbine is tripped (Steps 1 & 2)

(The reactor and main turbine are already 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.

(Steps 1 & 2)

RO ESTABLISH RCP Seal Injection Flow:

• CHECK power available to PDP

• MONITOR VCT level - GREATER THAN 3%

(Steps 3.a and 3.b)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 26 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 6 (Event is triggered 10 minutes after the LOOP)

Event

Description:

ESF DG #13 trips. Crew will enter 0POP05-EO-EC00, Loss of All AC Power.

Time Position Required Operator Actions Notes RO MONITOR RCP seal 1 inlet and lower seal CT water bearing temperatures on Plant EC00-H Computer display RC-010 - ALL LESS THAN 230°F RNO

• IF RCP seal 1 inlet or lower seal water bearing temperatures are GREATER THAN 230°F for ALL RCPs, THEN GO TO Step 4.

• IF a RCP seal inlet or lower seal water bearing temperature has exceeded 230°F, THEN ENSURE seal injection isolation valves CLOSED for that RCP.

(NOTE: These two RNO steps are procedurally directed, however, CT-EC00-H will NOT be met if Seal 1 temperatures have risen to greater than 230°F.)

AO

• DISPATCH operator to CLOSE applicable RCP seal injection OCIVs (Step 3.c)

(These actions are dependent on how long it takes the crew to get to this step. From the start of the Loss of All AC, it takes about 5 minutes for Seal 1 inlet temperatures to reach 230°F.)

(The MAB watch will report back that the requested RCP seal injection OCIVs are closed after about 1 minute.)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 27 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 6 (Event is triggered 10 minutes after the LOOP)

Event

Description:

ESF DG #13 trips. Crew will enter 0POP05-EO-EC00, Loss of All AC Power.

Time Position Required Operator Actions Notes RO OPEN PDP recirculation valve to 100%

CT

• START PDP EC00-H MONITOR seal water inlet and lower seal water bearing temperatures. (Plant computer RC-010)

PERFORM the following:

• Slowly CLOSE PDP recirculation valve to obtain a cooldown rate LESS THAN 1°F PER MINUTE

• WHEN seal water inlet temperature LESS THAN 135°F, THEN ESTABLISH seal injection flow of between 6 and 8 gpm (Steps 3.d - 3.g)

AO DISPATCH operator to open RWST to charging pump suction isolation valve "1(2)-CV-MOV-0112C" (Step 3.h)

(The MAB watch will report back that the valve has been manually opened after about 2 minutes.)

AO DISPATCH operator to close at least one of the VCT outlet isolation valves

• "1(2)-CV-MOV-0112B"

• "1(2)-CV-MOV-0113A" (Step 3.i)

(The MAB watch will report back that CV-MOV-0112B has been closed after about 1 minute.)

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 28 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 6 (Event is triggered 10 minutes after the LOOP)

Event

Description:

ESF DG #13 trips. Crew will enter 0POP05-EO-EC00, Loss of All AC Power.

Time Position Required Operator Actions Notes RO CHECK If RCS Is Isolated:

• Pressurizer PORVs - CLOSED AO

• Letdown orifice header isolation valve

- CLOSED

• DISPATCH operator to close the RCP seal return OCIV o "1(2)-CV-MOV-0079" (Step 4)

(The MAB watch may be sent to close CV-MOV-0024, however, all 3 letdown orifice header isolation valves will be closed. The MAB watch will report back that CV-MOV-0024 has been closed after about 1 minute.)

(The MAB watch will report back that CV-MOV-0079 has been closed after about 1 minute.)

BOP VERIFY AFW Flow - GREATER THAN CT-23 576 GPM

• AFW pump 14 - IN SERVICE

• ESTABLISH Cross Connections Of Intact SG(s) While Maintaining Flow GREATER THAN 576 GPM (Step 5)

(Basically the critical task is satisfied when SG 1D Cross-Connect, AF-FV-7518, is open AND at least 2 SGs are aligned and being fed from AFWP 14 at a total rate of at least 576 gpm.)

(In addition, an AFW procedural requirement states that total AFW flow from a single pump should not exceed 675 gpm.)

(The SRO may continue with the other RO to align power to an ESF bus from the emergency transformer while the BOP is working with the AO to align AFW.)

Terminate Scenario

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 29 of 39 CRITICAL TASK

SUMMARY

SAT/

POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA UNSAT RO CT-9 Manually Trip Diesel MANUALLY TRIP DIESEL Generator prior to the Diesel GENERATOR 11 Generator automatically tripping from an emergency mode trip signal.

Operation of safeguards equipment without ECW could lead to equipment failure/damage, which would constitute mis-operation or incorrect crew performance which leads to degraded ECCS or emergency power capacity.

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 30 of 39 RO EC00-H Establishes seal injection flow to RCP seals that have Seal 1 MANUALLY START THE PDP inlet temperatures that are less AND ALIGN SEAL INJECTION than 230°F.

TO RCP SEALS PRIOR TO For this scenario Seal 1 inlet SEAL 1 INLET temperatures on the four RCPs TEMPERATURES RISING TO will be tracking very close to GREATER THAN 230°F.

the same temperature.

This task is defined in the STPEGS Probabilistic Risk Assessment, Table 3 Risk Important Actions.

Failure to perform this task correctly could result in a challenge to the Reactor Coolant System boundary due to a failure of a Reactor Coolant Pump Seal. The operator is prompted to take action by alarms and procedural direction. The procedural limit for initiating RCP Seal Injection flow provides a measurable performance indicator for correct performance. Initiating seal flow prior to reaching temperature limits described in the Emergency Operating Procedure will protect the seals from overheating and subsequent damage.

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 31 of 39 BOP CT-23 Establish 576 GPM AFW flow FEED AT LEAST TWO STEAM to the SGs prior to completing GENERATORS FROM AFW step 5.b of 0POP05-EO-EC00, PUMP 14 USING AFW PUMP 14 Loss of All AC Power.

CROSS-CONNECT VALVE AF- Failure to establish minimum MOV-7518 WITH A MINIMUM AFW flow (under the TOTAL AFW FLOW OF 576 postulated conditions) is a GPM. violation of the basic objective of EC00 and of the assumptions of the analyses upon which EC00 is based.

Both intend to mitigate deterioration of RCS conditions while ac emergency power is not available. Per STP analysis, two Steam Generators are needed for a plant cooldown. Without AFW flow, the SGs could not support any significant plant cooldown.

Thus, the crew would lose the ability to delay the adverse consequences of core uncovery.

NOTE: (Per NUREG-1021, Appendix D)

If an operator or the Crew significantly deviates from or fails to follow procedures that affect the maintenance of basic safety functions, those actions may form the basis of a CT identified in the post-scenario review.

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 32 of 39 EXPECTED BOOTH COMMUNICATIONS EVENT 1:

• As a Plant Operator, when called:

• (AR Step 5) MAB watch will report that SFP Pump 1A has an acrid smell at the motor.

• (AR Step 5) EAB watch will report that the breaker is open and has an over current flag actuated.

• (Proc Step 6.1.1) MAB watch will report that SFP Purification was NOT in service.

• (Step 6.2.3) MAB Watch will report that 1-FC-0010A is closed after about 1 minute.

• (Step 6.2.1) MAB Watch will report that 1-FC-0010B is open after about 1 minute.

• (Step 6.1.4) MAB Watch will report that the shaft on SFP Pump 1B is stopped.

• (Step 6.1.6) MAB Watch will report that SFP Pump discharge flow is 2800 gpm.

• (Step 6.1.7) MAB Watch will report that SFP HX outlet temperature is about 90°F

• (Step 6.1.9) MAB watch will report that they will perform lineup 3.

• As Electrical Maintenance or the Duty Maintenance Supervisor, if notified of the status of SFP Pump 1A, report that an electrical maintenance crew is being assembled for support.

No further action is necessary.

• As Operations Manager, acknowledge that SFP Pump 1A has tripped. No further action is necessary.

EVENT 2:

• As I&C Maintenance or the Duty Maintenance Supervisor, if notified of the status of PT-0514, report that an I&C maintenance crew is being assembled for support. No further action is necessary.

• As Operations Manager, acknowledge that SG 1A PT-0514 has failed. No further action is necessary.

• As Operations Manager, acknowledge the issues with CV-MOV-0079. No further action is necessary.

EVENT 3:

• As I&C Maintenance or the Duty Maintenance Supervisor, acknowledge that Control Rod M12 has dropped. State that it will take 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> before a qualified I&C technician is onsite for the Rod Control System. No further action is necessary.

• As Operations Manager, acknowledge that Control Rod M12 has dropped. Report that they have talked to I&C and determined that a downpour should commence to a level determined by the procedure. No further action is necessary.

EVENT 4:

• No communications for this event.

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 33 of 39 EXPECTED BOOTH COMMUNICATIONS (contd.)

EVENT 5:

• As a Plant Operator, when called:

• Yard watch will report that there is an acrid smell around ECW Pump 1A motor.

• EAB watch will report that the breaker for ECW Pump 1A has an over current flag.

• As Duty Maintenance Supervisor, a maintenance team will be dispatched to assist with issues pertaining to ECW Pump 1A.

EVENT 6:

• As a Plant Operator, when/if called:

• To check ESF DG #13, EAB watch will report that a Generator Differential alarm came in.

• To close specific RCP Seal Injection OCIVs, MAB watch will report back that the requested RCP Seal Injection OCIVs have been closed after about 1 minute. (CV-MOVs-0033A, B, C, D.)

• To open RWST to charging pump suction isolation valve, CV-MOV-0112C, report back that the valve has been manually opened after about 2 minutes.

• To close at least one of the VCT outlet isolation valves, CV-MOV-0112B or CV-MOV-0113A, report back that CV-MOV-0112B has been closed after about 1 minute.

• To close Letdown OCIV, CV-MOV-0024, the MAB watch will report back that CV-MOV-0024 has been closed after about 1 minute.

• To close RCP seal return OCIV, CV-MOV-0079, the MAB watch will report back that CV-MOV-0079 has been closed after about 1 minute.

• As Duty Maintenance Supervisor, a maintenance team will be dispatched to assist with issues pertaining to ESF DG #13.

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 34 of 39 EXPECTED BOOTH ACTIONS

1. Perform the following for Event #1: (Steps a), b) & c) need to be performed prior to actuating Event #1) a) From ORCHID on the left computer:

• Ensure INSTRUCTOR mode is selected

• Pull up Schematic SC_RAUX03, SFP Cooling System. (Use the SCHEMATIC icon in the ORCHID tool bar. NOT the ME_Schematic in the BROWSER) b) From ORCHID on the right computer:

• Ensure OPERATOR mode selected

• Pull up SFP Cooling Pump switches from Panel Graphics c) From the ICS screen:

• Pull up computer point FCUD1406A (It will be ON SCAN as seen from the VALUE/STATUS tab) d) Using ORCHID on the left computer and when asked as a Plant Operator to change position of the SFP Pump discharge valves FC-0010A or B, change the position of FC-0011A or B accordingly by right clicking on valve FC-0011A or B in the schematic. This brings up the scratch pad. Insert 1.0 for open and 0 for closed.

(FC-0010A & B are not modeled.)

e) Using ORCHID on the right computer and the ICS screen, perform the following, in rapid order, when the crew takes FCUD1406A OFF SCAN: (This action clears the BYPASS INOP alarm that came in when the crew took SFP Pump 1A to PTL.)

• From the ICS screen put FCUD1406A back ON SCAN (The booth operator will be able to see from the ICS screen exactly when the crew takes FCUD1406A OFF SCAN.)

• From ORCHID on the right computer take SFP Pump 1A from PTL to NORM (The BYPASS INOP will clear)

• From the ICS screen take FCUD1406A back to OFF SCAN

• From ORCHID on the right computer take SFP Pump 1A back to PTL (The BYPASS INOP will stay clear.)

2. When asked then trigger the step for DA High Level Dump Valves

3. When asked then trigger step for AFWST Makeup

4. When asked then trigger step for swapping Charging Pump suction from the VCT to the RWST (open CV-MOV-0112C and close CV-MOV-0112B)

5. If asked to close CV-MOV-0024, then use CVCS under Remote Functions.

6. When asked then trigger step for closing CV-MOV-0079

7. If asked to close specific RCP Seal Injection OCIVs, CV-MOVs-0033A, B, C, D, close the ones requested by going to Browser, Remote Functions for CVCS and close the individual valves requested.

8. If asked to cross connect aux feed to steam generators then use the ME Schematics for Aux Feedwater to position valves as requested by the RO.

9. When asked to position SG PORV Blackout switches to BYPASS then trigger the individual steps for each switch.

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 35 of 39 SIMULATOR SETUP NOTE ALL Annunciator Response Procedures (ARPs) must be checked if this scenario is the first to be run on this day. Setup for subsequent runs of this scenario only requires those ARPs that were actually marked in to be checked.

Instructors running the scenario must keep track of which ARPs these are, otherwise, all will have to be checked for subsequent scenarios as well.

Check and Clean the following procedures:

0POP09-AN-22M2, F-6, SFP TROUBLE 0POP02-FC-0001, Spent Fuel Pool Cooling and Cleanup System 0POP04-FW-0001, Loss of Steam Generator Level Control 0POP04-RS-0001, Control Rod Malfunction 0POP05-EO-EO00, Reactor Trip or SI 0POP05-EO-ES01, Reactor Trip Response 0POP05-EO-EC00, Loss of All AC Power Additional Annunciator Response Procedures that were used by the Crew during the Scenario.

SIMULATOR SETUP (contd.) NOTE Log The into Instructor Scenario Workstation Lesson Plan MUST beasrunlotnrc fromuser, open the left Orchid most (nstpsStation Instructor server),

in then Unlock Initial Conditions Group lotnrc.

Simulator Booth to allow for recording and storing of critical parameter data.

Log into Instructor Workstation as lotnrc user, open Orchid (nstps server), then Unlock Initial Conditions Group lotnrc.

Reset to IC #190 and perform the following:

Switch Check Ensure red light on end of CP-010 off Ensure ICS Annunciators have stopped counting up

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 36 of 39 SIMULATOR SETUP (contd.)

Go to RUN and perform the following:

Ensure Simulator is ready by performing applicable checkoffs from LOR-GL-0006, LOR Conduct of Simulator Training Guidelines, Addendum 5, Simulator Readiness Checklist.

Ensure VCT Makeup Integrators are set as follows:

Momentarily place RC M/U CONT to STOP and then START to reset BA BATCH/GALLONS and TOT M/U BATCH/GALLONS counters to zero.

Reset BA BATCH/GALLONS setpoint to 0 gallons and reset TOT M/U BATCH/GALLONS setpoint to 10 gallons.

Verify BA Controller Pot setting is 3.85 Hang following ECO Caution Tags:

ESF DG #12 stop plunger in PTS position ESF DG #12 Output Breaker handswitch in PTL Open lesson plan for Scenario 2 in lotnrc directory for LOT 21, then EXECUTE lesson plan. These actions will set up any initial conditions for the scenario. Run the scenario in accordance with the next section, Scenario Instructions.

If this scenario IC has changing conditions (i.e. Xenon is changing, etc.), then place the simulator in FREEZE, otherwise it is OK to leave in RUN.

Run the scenario in accordance with the next section, Scenario Instructions.

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 37 of 39 SCENARIO INSTRUCTIONS NOTE Steps 1 to 4 below can be performed in the LOR Debrief Room prior to the crew coming into the Simulator provided exam security measures are taken.

1. Provide Shift Turnover sheets to the crew and review the information.

2. Have the Crew perform a Pre-Job Brief based on any items on the turnover sheet.

Ensure the candidates dont have any other questions about the Shift Turnover.

3. Ensure the Beacon book from the simulator is available to the crew if they are in the LOR Debrief Room.

4. Review the Simulator Differences list with the crew if needed.

5. When signaled by Simulator Staff, have the crew perform their board walkdown and inform the floor instructor when ready to take the watch.

NOTE Event 1 has detailed actions for the booth operator. Review Event 1 actions on Page 34 while the crew is performing the board walkdown.

6. Ensure the simulator is in RUN and verify simulator clock is set correctly. Note the time that the Crew takes the watch. ________________ Start Time.

NOTE Malfunction Step and/or Lesson Plan Steps (Events) are triggered upon the Lead Examiners signal during the scenario unless an agreed upon time is discussed with the examiner prior to the start of the scenario.

Always TRIGGER events in the Simulator Scenario Lesson Plans. This way delays associated with events will take place as intended.

Refer to EXPECTED BOOTH COMMUNCATIONS and EXPECTED BOOTH ACTIONS Sections for instructions for Instructor actions during the scenario.

7. Trigger the step titled Start Chart and ensure specified Critical Parameters for the scenario begin recording as the scenario runs.

8. Trigger MALFUNCTION STEP - This will insert Step #1, Event #1.

9. Trigger STEP 2 - Event #2

10. Trigger STEP 3 - Event #3

11. Trigger STEP 4 - Event #4

12. Place simulator in FREEZE when cued by the Lead Examiner to terminate scenario.

13. DO NOT RESET simulator until the steps on the next page are completed and all Examiners have completed Follow-Up Questioning.

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 38 of 39 SCENARIO INSTRUCTIONS (contd.)

NOTE Some scenarios will have more than one chart. For these, each chart file must be separately saved with a unique filename.

14. Saving Critical Parameters data:

Click on the Charts icon on the left side of the screen Select Pause icon, then select All Click on the Print Chart icon, then select All This will bring up a window in the TASK BAR called PRIMOPDF.

Click on Create PDF This will bring up a File Save As window.

Save to folder c:\Users\lotnrc\Desktop\LOT21 Charts. The file name will be LOT21 Scenario 2 followed by a name that identifies the crew (e.g. Crew A).

Save the new file. It will be saved in a folder already on the desktop. LOT21 Charts.

15. Saving Scenario SAM (Simulator Action Monitor)

Under TOOLS click on SAM In the dialog box that comes up click on SAVE TO Save as a TEXT FILE to folder c:\Users\lotnrc\Desktop\LOT21 Charts. The file name will be LOT21 SAM INFO Scenario 2 followed by a name that identifies the crew (e.g. Crew A).

LOT 21 NRC OP-TEST SCENARIO #2 Rev 1 Page 39 of 39 TURNOVER INFORMATION Reactor Power is at 100%.

• ESF DG #12 was tagged out for an emergent condition. Return to service of ESF DG

1. 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.

• RCS Boron Concentration is 1408 ppm.

• 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.

• No ESF DG FOSTs are on recirc.

LCO Actions:

ESF DG 12 - TS 3.8.1.1 Action b, 0PSP03-EA-0002, ESF Power Availability, was completed 30 minutes ago. TS 3.8.1.1 Action d, was entered in the log 45 minutes ago as SAT.

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 1 of 34 LOT 21 NRC EXAM SIMULATOR OPERATING TEST SCENARIO #3 Revision 1 Week of 09/25/2017

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 2 of 34 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 #189)

Turnover:

• ESF DG #12, Starting Air Receiver #14 is OOS for Maintenance.

Event No. Malf. No. Event Type* Event Description 1 04-01-01 RO (C) Component Cooling Water Pump 1A Sheared Shaft. (60 seconds (0 min) SRO (C, TS) after crew takes the watch.)

1 2T 05-12-03 RO (I)

(20 min) SRO (I, TS) Power Range NI Channel 43 Fails High.

1 3T 11-01-07 All (R) ISO-Phase Fans trip. Crew will have to perform a Fast Load (45 min) reduction to about 50% power.

0.063 4T 02-01-02 ALL (M) SBLOCA on LOOP B Cold Leg.

(55 min)

.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 and Containment Spray Pumps fail to Auto Start.

(N/A) (Occurs 6 minutes after the RCPs have stopped and CCW Pump 0.4 1B has been started.)

(Critical Task)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor.

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 3 of 34 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 4

3. Major transients (1-2) 2

4. EOPs entered/requiring substantive actions (1-2) 1

5. Entry into a contingency EOP with substantive actions (>1 per scenario 2 set)

6. Preidentified critical tasks (>2) 3 INSTRUCTOR NOTES:

• Critical Tasks are indicated by "C-##" in the position column and indicated in bold type. In some instances an

• will indicate that only a portion of the task listed is considered critical.

• Shaded cells indicate procedural entry points.

RECORDED PARAMETERS:

Recorded parameters will be determined during NRC Validation week.

The parameters identified for recording may be of value in evaluating crew performance. Once the scenario is complete for each crew, printout the recorded parameters and label the printout with date, time, crew number and scenario number. See Scenario Instructions section for further details on how to save the Recorded Parameters.

• CET Temperature

• RCP 1A Breaker

• RCP 1B Breaker

• RCP 1C Breaker

• RCP 1D Breaker

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 4 of 34 SCENARIO OBJECTIVES Event 1 Objective

• Respond to CCW System alarms per the associated Annunciator Response Procedure.

• Given that a condition exists requiring entry into a Technical Specification, interpret Technical Specifications accurately.

Event 2 Objective

• Respond to a Loss of Power Range Instrumentation per 0POP04-NI-0001.

• Given that a condition exists requiring entry into a Technical Specification, interpret Technical Specifications accurately.

Event 3 Objective

• With the plant operating in Mode 1 and the SM or US determines that a load reduction is required, perform a fast load reduction per 0POP04-TM-0005.

Event 4 Objective

• Respond to a Reactor Trip or Safety Injection in accordance with 0POP05-EO-EO00.

• Respond to a Loss of Reactor Coolant Accident involving a break size in which Reactor Coolant System pressure drops below HHSI Pump shutoff head per 0POP05-EO-EO10.

Event 5 Objective

• Given a Safety Injection, perform Addendum 5 in accordance with 0POP05-EO-EO00.

Event 6 Objective

• Respond to a Containment high pressure condition in accordance with 0POP05-EO-FRZ1.

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 5 of 34 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 1 (Triggered 60 seconds after the Crew takes the watch.)

Event

Description:

Component Cooling Water Pump 1A Sheared Shaft. (TS)

Time Position Required Operator Actions Notes RO Acknowledges and announces the following annunciators on 2M03:

• CCW HX 1A OUTL FLOW HI/LO (C-5)

• CCW HX 1A OUTL PRESS LO (E-5)

(Annunciator CCW 1A OUTL PRESS LO (E-5) will be used for the sheared shaft of CCW Pump 1A.)

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 6 of 34 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 1 (Triggered 60 seconds after the Crew takes the watch.)

Event

Description:

Component Cooling Water Pump 1A Sheared Shaft. (TS)

Time Position Required Operator Actions Notes RO IF CCW header pressure decreased to 76 psig, THEN perform the following:

• ENSURE the standby CCW train running per 0POP02-CC-0001, Component Cooling Water.

• ENSURE the standby ECW train running per 0POP02-EW-0001, Essential Cooling Water Operations

• STOP CCW Train A per 0POP02-CC-0001, Component Cooling Water

• STOP ECW Train A per 0POP02-EW-0001, Essential Cooling Water Operations

• 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 (ARP Step 1 and sub steps)

(CCW Pump 1C will auto start after a time delay.)

(The crew will stop CCW Pump 1A and if placed in PTL a By-Pass INOP alarm will come in.)

AO (The MAB watch will report that CCW Pump 1A coupling is broken and CCW Pump 1C is running SAT.)

(The EAB watch will report that there is no issues with the breaker for CCW Pump 1A.)

RO (Stop CCW Pump 1A Cooling Fan.)

(The crew will initially place the CCW Mode Select Switches in OFF. When restoring, Train B will be placed in STANDBY and Train C in RUN.)

(The crew will swap CCW Rad Monitor to Train 1C.)

(The crew will refer to the standard operating procedures, 0POP02-CC-0001 and 0POP02-EW-0001 to align and secure equipment as needed.)

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 7 of 34 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 1 (Triggered 60 seconds after the Crew takes the watch.)

Event

Description:

Component Cooling Water Pump 1A Sheared Shaft. (TS)

Time Position Required Operator Actions Notes SRO TAKE appropriate action per Technical Specification 3.7.3, CCW; 3.5.2, SI; 3.5.6, RHR 3.6.2.3, RCFCs.

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 />.

(Event #2 can occur once the SRO has addressed Tech Specs for CCW Pump 1A.)

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 8 of 34 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 2 (Examiner Trigger)

Event

Description:

Power Range NI Channel 43 Fails High. (TS)

Time Position Required Operator Actions Notes RO Acknowledges and announces the following annunciators from 05M3:

• IR/PR ROD WITHDRWL BLKD (D-1)

• PR HI SET PT FLUX HI RX TRIP ALERT (A-2)

• PR FLUX RATE HI RX TRIP ALERT (C-2)

• PR UPPER DET FLUX DEV HI/AUTO DEF (A-3)

• PR LOWER DET FLUX DEV HI/AUTO DEF (A-3)

• AXIAL FLUX DIFFERENCE HI (D-3)

(Annunciator Response Procedures will direct the Crew to 0POP04-NI-0001, Nuclear Instrument Malfunction.)

RO Determines NI Channel 43 has failed high.

Performs immediate actions of 0POP04-NI-0001, Nuclear Instrument Malfunction:

• CHECK Power Range Nuclear Instruments -

NORMAL RNO PERFORM the following:

• ENSURE "ROD BANK SELECTOR SW" in MAN

• PLACE any LPFRVs being used to feed SGs in Manual

• CONTROL SG Levels Between 68 and 74%

NR Level Indication

• GO TO Addendum 3, Power Range Nuclear Instrumentation Malfunction (Step 1 and RNO a, b, & c)

(LPFRVs are not in service.)

SRO Directs actions of 0POP04-NI-0001, Nuclear Instrument Malfunction.

SRO ENSURES RO has performed immediate actions and goes to Addendum 3 of 0POP04-NI-0001, Nuclear Instrument Malfunction.

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 9 of 34 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 2 (Examiner Trigger)

Event

Description:

Power Range NI Channel 43 Fails High. (TS)

Time Position Required Operator Actions Notes SRO STOP Any Main Turbine Load Changes.

(Add. 3 Step 1.0)

RO MAINTAIN RCS Tavg Within 1.5ºF of Tref Using Manual Control Rod Motion (Add. 3 Step 2.0)

RO BYPASS The Malfunctioning Power Range Channel By Selecting The affected Channel On The Following Switches:

• "COMPARATOR CHANNEL DEFEAT"

• "POWER MISMATCH BYPASS"

• "ROD STOP BYPASS"

• "DETECT CURRENT COMPARATOR "

"UPPER SECTION"

• "DETECT CURRENT COMPARATOR "

"LOWER SECTION" (Add. 3 Step 3.0)

(Switches are on CP011)

RO ENSURE The Following Permissives Are In The Correct State Within One Hour Of The Power Range Channel Failure:

• "P-7 POWER OPER RX TRIPS BLKD" Lampbox 5M24 B-2

• "P-8 THREE LOOP OPERATION PERMITTED" Lampbox 5M24 B-3

• "P-9 RX/TURB TRIP BLOCKED" Lampbox 5M24 B-4

• "P-10 MAN BLOCK INT/LO PR RX TRP PERM" Lampbox 5M24 A-2 (Add. 3 Step 4.0)

RO CHECK Reactor Power Meets One of the Following:

• GREATER THAN 75% OR

• WILL BE GREATER THAN 75%

(Add. 3 Step 5.0)

(Reactor power will still be at 100%)

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 10 of 34 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 2 (Examiner Trigger)

Event

Description:

Power Range NI Channel 43 Fails High. (TS)

Time Position Required Operator Actions Notes SRO VERIFY Within One Hour that Beacon Power Distribution Monitoring System (PDMS) Is Available with Reactor Engineering.

(Add. 3 Step 6.0)

(Reactor engineering will report back that PDMS is available.)

SRO DIRECT Reactor Engineering to Commence 0PSP10-II-0004, Determination of QPTR Using a Core Power Distribution Measurement, no later than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after the Channel Inoperability time to ENSURE an adequate amount of time to complete the Beacon PDMS QPTR Surveillance within the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> TS action Statement.

(Add. 3 Step 7.0)

BOP VERIFY SG Level Being - CONTROLLED BY LPFRVs (Add. 3 Step 8.0)

(SG levels being controlled by MFRVs.)

SRO/RO PLACE "ROD BANK SELECTOR SW" in AUTO at Discretion of the Shift Manager/Unit Supervisor.

(Add. 3 Step 9.0)

SRO INITIATE a Condition Report to Repair the Inoperable Channel (Add. 3 Step 10.0)

SRO REVIEW Applicable TSs. REFER TO Addendum 8.

(Add. 3 Step 11.0)

TS 3.3.1 Item 2.a (PR High Setpoint), 2.b (PR Low Setpoint) and Item 3 (PR High Positive Rate), Action 2-a TS 3.3.1 Item 8 (OTDT), Action 6-a 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 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 />.

(TS 3.2.4 (QPTR) and 3.3.1 Item 19 (RX Trip System Interlocks) are referenced but do not apply with only one Power Range NI affected.)

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 11 of 34 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 3 (Examiner Trigger)

Event

Description:

ISO-Phase Fans trip. Crew will have to perform a Fast Load reduction to about 50% power.

Time Position Required Operator Actions Notes BOP Acknowledges and announces annunciator on 10M2:

• ISO PHASE BUS TROUBLE (B-8)

SRO Directs BOP to follow steps of Annunciator Response Procedure.

BOP VERIFY trouble by checking Plant Computer points BD3351 and TD3350.

(ARP Step 1)

(These ICS points do not come in with this failure)

BOP IF a relay flag exists on Relay 51/74, THEN reset the relay. (Back of CP009)

(ARP Step 2)

BOP DISPATCH and Operator to ZLP122, ISO PHASE BUS CONTROL PANEL, to determine cause of the alarm.

(ARP Step 3)

AO IF either COOLING FAN 1A or 1B CONTROL POWER UNDERVOLTAGE red lights are illuminated, THEN DIRECT Operator to start the alternate cooling fan AND stop the affected fan.

IF HIGH AIR DUCT TEMP alarm occurs, THEN ENSURE VFN-005, TGB HVAC TRANSFER FAN, is running.

IF both fans are inoperable, THEN PERFORM the following:

• REDUCE Generator load at 5% per minute.

REFER TO 0POP04-TM-0005, Fast Load Reduction.

• WHEN Generator current is less than or equal to 18,500 amps as indicated on CP007, THEN SECURE fast load reduction.

(ARP Step 3.a, b and c)

(TGB watch will report back that ISO Phase Cooling Fan 1A tripped and Cooling Fan 1B will not start.)

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 12 of 34 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 3 (Examiner Trigger)

Event

Description:

ISO-Phase Fans trip. Crew will have to perform a Fast Load reduction to about 50% power.

Time Position Required Operator Actions Notes SRO Enters and directs actions of 0POP04-TM-0005, Fast Load Reduction All PERFORM the following to reduce turbine load:

• NOTIFY STP Co-Owners Using The EMS Website That Load Reduction Is Commencing

• DETERMINE Amount of Boric Acid To Add To Reduce Reactor Power To Desired Level AND COMMENCE RCS Boration

• CHECK Rod Control System - IN AUTOMATIC

• ENERGIZE Pressurizer Heaters for boron equalization

• PERFORM The Following To Lower Turbine Load:

o CHECK Main Turbine - IN THE IMPULSE PRESSURE FEEDBACK MODE IMP IN o REDUCE Turbine Load at a rate of less than or equal to 5% per minute using Operator Auto (Step 1.0)

(The crew will borate the RCS based on actual plant response but will estimate a total amount of about 600 gallons based on the graph prior to Step 1.0.)

(Turbine IMP IN or IMP OUT can be used but normally IMP IN is used.)

BOP MAINTAIN Main Generator reactive load (VARs) within the following:

• Less Than 450 MVARs

• Guidelines Of The Plant Curve Book, Figure 7.1 (Step 2.0)

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 13 of 34 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 3 (Examiner Trigger)

Event

Description:

ISO-Phase Fans trip. Crew will have to perform a Fast Load reduction to about 50% power.

Time Position Required Operator Actions Notes RO MONITOR Rod Control system 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 (Step 3.0)

RO MAINTAIN Pressurizer Level within the following:

• Trending to Program Level OR

• At Program Level (Step 4.0)

RO MAINTAIN Pressurizer Pressure within the following:

• Trending to between 2220 psig and 2250 psig OR

• Between 2220 psig and 2250 psig (Step 5.0)

BOP MAINTAIN Steam Generator NR Level within the following:

• Trending to between 68% and 74%

OR

• Between 68% and 74%

(Step 6.0)

(EVENT #4 can be triggered on signal from the lead examiner once satisfied with crew observation.)

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 14 of 34 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 4 and 6 Event 4

Description:

SBLOCA (Examiner Triggered)

Event 6

Description:

LBLOCA and Containment Spray Pumps fail to auto Start. (Occurs 6 minutes after the RCPs have stopped and CCW Pump 1B has been started.)

Time Position Required Operator Actions Notes ALL Acknowledges and announces annunciator on 04M8:

• PRZR LEVEL DEV LO (D-7)

• PRZR PRESS DEV LO B/U HTRS ON (D-7)

(The RCS leak will start at a size that will require a quick determination by the crew and they may or may not initiate a manual SI prior to an automatic one. At this time the leak size is still considered a SBLOCA.)

SRO Directs a manual Reactor Trip and Safety Injection and enters 0POP05-EO-EO00, Reactor Trip or Safety Injection.

RO Completes immediate actions of 0POP05-EO-EO00 and determines:

• Reactor is tripped

• Turbine is tripped

• AC ESF Busses are energized

• SI is not actuated (RO will complete immediate actions.

BOP Operator will monitor the plant and make an announcement of the Reactor trip.)

(During a pause between performing immediate actions and verifying immediate actions, the BOP will throttle AFW to reduce the RCS cooldown by:

• Resetting the AFW Reg Valves BOP

• Throttling the AFW Reg Valves to lower total AFW flow.

Total AFW flow must remain above 576 gpm until at least one SG level is >14% NR {34% for adverse containment})

SRO Directs/ensures the immediate actions of EO00, Reactor Trip/SI have been completed by performing a procedure read through of them.

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 15 of 34 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 4 and 6 Event 4

Description:

SBLOCA (Examiner Triggered)

Event 6

Description:

LBLOCA and Containment Spray Pumps fail to auto Start. (Occurs 6 minutes after the RCPs have stopped and CCW Pump 1B has been started.)

Time Position Required Operator Actions Notes ALL WHEN RCS pressure is less than 1430 psig, the (CT-16) crew performs the following:

• Verifies at least one HHSI Pump running

• Stops all RCPs (These steps can be performed using the CIP of 0POP05-EO-EO00, Reactor Trip or Safety Injection. Timing will depend on how quickly and how much AFW is throttled.)

BOP VERIFY Proper SI Equipment Operation Per ADDENDUM 5, VERIFICATION OF SI EQUIPMENT OPERATION (Step 5)

(See Actions on Page 21-25.)

RO MONITOR If Containment Spray Is Required:

• Containment pressure GREATER THAN 9.5 PSIG (QDPS)

(RNO)

• PERFORM the following:

• CHECK Containment pressure - HAS EXCEEDED 9.5 PSIG (CP - 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.

(Step 6)

(Containment pressure will be less than 9.5 psig.)

RO CHECK RCP Seal Cooling:

• ENSURE seal injection flow between 6 and 13 gpm (Step 7)

(RO may have to adjust seal injection.)

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 16 of 34 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 4 and 6 Event 4

Description:

SBLOCA (Examiner Triggered)

Event 6

Description:

LBLOCA and Containment Spray Pumps fail to auto Start. (Occurs 6 minutes after the RCPs have stopped and CCW Pump 1B has been started.)

Time Position Required Operator Actions Notes RO MONITOR RCS Temperatures

• WITH ANY RCP RUNNING, RCS TAVG STABLE AT OR TRENDING TO 567°F OR

• WITHOUT ANY RCP RUNNING, RCS TCOLD STABLE AT OR TRENDING TO 567°F (Step 8)

(Which temperature to monitor will be dependent on if the RCPs have been tripped by this time.

With Main Steam Isolated there is nothing else the crew can do.)

RO CHECK Pressurizer Status:

• PORVs CLOSED

• Normal pressurizer spray valves - CLOSED

• Auxiliary spray valve - CLOSED

• Excess letdown isolation valves - CLOSED (Step 9)

RO MONITOR If RCPs Should Be Stopped:

(CT-16)

• HHSI pump - AT LEAST ONE RUNNING

• RCS pressure - LESS THAN 1430 PSIG

• STOP all RCPs (Step 10)

(RCPs may have already been stopped)

RO VERIFY The Following Containment Isolation Valves - CLOSED

• Seal return isolation valves

• Containment atmosphere radiation monitor isolation valves (Step 11)

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 17 of 34 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 4 and 6 Event 4

Description:

SBLOCA (Examiner Triggered)

Event 6

Description:

LBLOCA and Containment Spray Pumps fail to auto Start. (Occurs 6 minutes after the RCPs have stopped and CCW Pump 1B has been started.)

Time Position Required Operator Actions Notes RO CHECK If SG Secondary Pressure Boundary Intact:

• CHECK pressures in all SGs -

• CONTROLLED OR RISING

• GREATER THAN CONTAINMENT PRESSURE (Step 12)

RO CHECK If SG Tubes Are Intact:

• Main steamline radiation NORMAL

• IF SG blowdown in service, THEN SG blowdown radiation NORMAL

• CARS pump radiation NORMAL

• NO SG level rising in an uncontrolled manner (Step 13)

RO CHECK If RCS Is Intact:

• Containment radiation NORMAL

• Containment pressure NORMAL

• Containment wide range water level NORMAL (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.

(Step 14)

(Will not transition to a Functional Recovery Procedure until Addendum 5 is complete.)

BOP Completes 0POP05-EO-EO00, Addendum 5.

SRO Informs crew of transition to 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant.

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 18 of 34 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 4 and 6 Event 4

Description:

SBLOCA (Examiner Triggered)

Event 6

Description:

LBLOCA and Containment Spray Pumps fail to auto Start. (Occurs 6 minutes after the RCPs have stopped and CCW Pump 1B has been started.)

Time Position Required Operator Actions Notes RO MONITOR If RCPs Should Be Stopped:

• HHSI pumps - AT LEAST ONE RUNNING

• RCS pressure - LESS THAN 1430 PSIG

• STOP all RCPs (Step 1)

(RCPs should have already been stopped.)

NOTE: The LBLOCA occurs 6 minutes after the RCPs have been stooped and CCW Pump 1B has been started. These actions, the 6 minute timer and Addendum 5 will probably have been completed by this time. When the LBLOCA occurs, the Crew may have to enter the Critical Safety Function for Integrity.

ALL Recognize that an ORANGE or possibly a RED path exists for the INTEGRITY Critical Safety Function 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 THAN 415 PSIG (RNO)

IF LHSI pump flow GREATER THAN 500 GPM, THEN RETURN TO procedure step in effect.

(Step 1)

(The LBLOCA will cause RCS pressure to go lower than 415 psig.)

ALL Recognize that an ORANGE path exists for the Containment Critical Safety Function (Greater than 9.5 psig in containment represents and ORANGE path.)

SRO Completes the EOP step in progress, then transitions to and directs the action of 0POP05-EO-FRZ1, Response to High Containment Pressure.

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 19 of 34 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 4 and 6 Event 4

Description:

SBLOCA (Examiner Triggered)

Event 6

Description:

LBLOCA and Containment Spray Pumps fail to auto Start. (Occurs 6 minutes after the RCPs have stopped and CCW Pump 1B has been started.)

Time Position Required Operator Actions Notes RO VERIFY Containment Spray - ESTABLISHED

• Containment Pressure LESS THAN 56.5 PSIG.

• At least one Containment Spray pump -

RUNNING o Discharge valve OPEN o FLOW indication (Step 1)

(The Containment Spray Pumps failed to Auto Start so the crew will go to Step 2)

RO VERIFY Containment Isolation Phase A Valves-CLOSED, REFER TO ADDENDUM 1, PHASE A ISOLATION VERIFICATION.

(Step 2)

RO VERIFY Containment Ventilation 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 (Step 3)

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 20 of 34 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 4 and 6 Event 4

Description:

SBLOCA (Examiner Triggered)

Event 6

Description:

LBLOCA and Containment Spray Pumps fail to auto Start. (Occurs 6 minutes after the RCPs have stopped and CCW Pump 1B has been started.)

Time Position Required Operator Actions Notes RO CHECK If Containment Spray Is Required:

(CT-3)

• Containment pressure - HAS 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" (Step 4)

Terminate the scenario

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 21 of 34 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:

• SGFPTs - TRIPPED

• SU SGFP - TRIPPED

• VERIFY the following valves -CLOSED o FWIVs o FWIBs o FW preheater bypass valves o FW regulating valves o Low power FW regulating valves o SG blowdown isolation valves o SG sample isolation valves (EO00 Addendum 5, Step 1)

(0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 5, Verification of Equipment Operation.)

(This addendum is performed in parallel with Steps 5 to 14 of 0POP05-EO-EO00, Reactor Trip or Safety Injection.)

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 22 of 34 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 CHECK if main steamline should be 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 o VERIFY Main Steamline Isolation:

o MSIVs - CLOSED o MISBs - CLOSED (Step 2)

(If Containment pressure is above 3 psig then MSIVs will have automatically closed.)

BOP VERIFY AFW system status:

o Motor-driven pump - RUNNING o Turbine-driven pump - RUNNING (Step 3)

BOP VERIFY AFW valve alignment - PROPER EMERGENCY ALIGNMENT (Step 4)

BOP VERIFY total AFW Flow - GREATER THAN 576 GPM (Step 5)

BOP VERIFY containment isolation phase A:

• Phase A - ACTUATED

• Phase A valves - CLOSED, REFER TO ADDENDUM 1, PHASE A ISOLATION VERIFICATION (Step 6)

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 23 of 34 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 ECW status:

• ECW pumps - RUNNING

• ECW pump discharge isolation valves -

OPEN (Step 7)

BOP VERIFY CCW pumps - RUNNING (CT-8) RNO Manually start CCW Pump 1B (Step 8)

BOP VERIFY RCFC status:

• RCFCs - RUNNING

• Cooling water - TRANSFERRED TO CCW RNO

• IF RCFC inlet temperatures are LESS THAN OR EQUAL TO 116°F, THEN manually TRANSFER cooling to CCW.

• IF RCFC inlet temperatures are GREATER THAN 116°F, THEN CONTACT the TSC prior to transferring cooling.

(Step 9)

(RCFC inlet temperature will depend on how long it takes the operator to reach this step.)

BOP VERIFY SI pump status:

• HHSI pumps - RUNNING

• LHSI pumps - RUNNING (Step 10)

BOP VERIFY SI valve alignment - PROPER EMERGENCY ALIGNMENT (Step 11)

BOP VERIFY SI flow:

• RCS pressure - LESS THAN 1745 PSIG

• HHSI pump flow - INDICATED

• RCS pressure - LESS THAN 415 PSIG (RNO)

• GO TO Step 13 of this Addendum.

(Step 12)

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 24 of 34 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 containment ventilation 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 (Step 13)

BOP VERIFY ventilation actuation:

• 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 (Step 14)

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 25 of 34 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 NOTIFY Unit Supervisor that Addendum 5 is COMPLETE (Step 15)

SRO IMPLEMENT Functional Restoration Procedures as required (Step 16)

SRO RETURN TO procedure step in effect.

(Step 17)

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 26 of 34 CRITICAL TASK

SUMMARY

SAT/

POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA UNSAT ALL CT-16 Trip all RCPs so that an Orange Path MANUALLY TRIP THE on Core Cooling (CET temperatures REACTOR COOLANT >707°F) does not occur when forced PUMPS WHEN RCS circulation in the RCS stops.

PRESSURE IS LESS SAFETY SIGNIFICANCE -- Failure THAN 1430 PSIG AND to trip the RCPs under the postulated AT LEAST ONE HHSI plant conditions leads to core uncovery PUMP IS INJECTING and to fuel cladding temperatures in DURING A SBLOCA. excess of 2200°F, which is the limit specified in the ECCS acceptance criteria. Thus, failure to perform the task represents mis-operation or incorrect crew performance which leads to degradation of the fuel cladding barrier to fission product release and to violation of the facility license condition.

ALL CT-8 Manually start two CCW Pumps to MANUALLY START provide adequate cooling water for the CCW PUMP 1B SO THAT operating safeguards trains before TWO CCW PUMPS transition past 0POP05-EO-EO00, PROVIDE ADEQUATE Addendum 5, Step 8 COOLING TO SAFETY SIGNIFICANCE -- Failure SAFEGUARDS TRAINS to manually start at least the minimum DURING A SBLOCA. number of CCW pumps required to provide adequate component cooling for the operating safeguards trains represents a demonstrated inability by the crew to:

• Recognize a failure/incorrect auto actuation of an ESF system or component

• Effectively direct/manipulate ESF controls CCW provides cooling to the following safeguards components:

• RCFCs

• RHR heat exchangers (during the recirculation mode of ECCS

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 27 of 34 cooling)

The acceptable results obtained in the FSAR analyses of LOCAs and SGTRs are predicated on the assumption that, at the very least, two trains of safeguards actuate, including the CCW pump in each of the two trains.

ALL CT-3 Manually initiate at least one train of MANUALLY START AT Containment Spray flow prior to LEAST ONE completion of step 4 of 0POP05-EO-CONTAINMENT SPRAY FRZ1.

PUMP TO PROVIDE SAFETY SIGNIFICANCE -- Failure CONTAINMENT to manually actuate CONTAINMENT COOLING. SPRAY or start at least one CONTAINMENT SPRAY Train under the postulated conditions constitutes a demonstrated inability by the crew to recognize a failure/incorrect auto actuation of an ESF system or component.

In this case, at least one train of CONTAINMENT SPRAY can be manually actuated from the control room. Therefore, failure to manually actuate CONTAINMENT SPRAY or start at least one CONTAINMENT SPRAY Train also represents a demonstrated inability by the crew to effectively direct/manipulate ESF controls that would lead to violation of the facility license condition.

NOTE: (Per NUREG-1021, Appendix D)

If an operator or the Crew significantly deviates from or fails to follow procedures that affect the maintenance of basic safety functions, those actions may form the basis of a CT identified in the post-scenario review.

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 28 of 34 EXPECTED BOOTH COMMUNICATIONS EVENT 1:

• As a Plant Operator, when called:

• Report that CCW Pump 1A coupling between the motor and the pump is broken.

• Report that CCW Pump 1A breaker is closed with no other issues. (if pump hasn't been stopped yet.)

• Report that CCW Pump 1C is running SAT.

• As Mechanical Maintenance or the Duty Maintenance Supervisor, if notified of CCW Pump 1A status, report that a mechanical maintenance crew will be assembled for support. No further action is necessary.

• As Operations Manager, acknowledge the status of CCW Pump 1A. No further action is necessary.

EVENT 2:

• As I/C Maintenance or the Duty Maintenance Supervisor, if notified, report that an I/C maintenance crew will be assembled for support of the failed NI Channel. No further action is necessary.

• As Operations Manager, acknowledge the failed NI Channel. No further action is necessary.

EVENT 3:

• As a Plant Operator, when called, report that ISO Phase Cooling Fan 1A tripped and Cooling Fan 1B will not start.

• As Mechanical Maintenance or the Duty Maintenance Supervisor, if notified of the ISO Phase Fan issues, report that a mechanical maintenance team will be assembled for support. No further action is needed.

• As Operations Manager, acknowledge the ISO Phase Fan issues and the associated down power for Unit 1. No further action is necessary.

EVENT 4:

• There are no communications expected with this event.

EVENT 5:

• There are no communications expected with this event.

EVENT 6:

• There are no communications expected with this event.

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 29 of 34 EXPECTED BOOTH ACTIONS

1. If asked to open the DA High level Dump Valves then trigger the step for DA High Level Dump Valves.

2. If asked to fill the AFWST then trigger the step for AFWST Makeup.

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 30 of 34 SIMULATOR SETUP NOTE ALL Annunciator Response Procedures (ARPs) must be checked if this scenario is the first to be run on this day. Setup for subsequent runs of this scenario only requires those ARPs that were actually marked in to be checked.

Instructors running the scenario must keep track of which ARPs these are, otherwise, all will have to be checked for subsequent scenarios as well.

Check and clean the following procedures:

0POP09-AN-02M3-E5, CCW HX 1A OUTL PRESS LO 0POP02-CC-0001, Component Cooling Water 0POP04-NI-0001, Nuclear Instrument Malfunction 0POP09-AN-10M2-B8, ISO PHASE BUS TROUBLE 0POP04-TM-0005, Fast Load Reduction 0POP05-EO-EO00, Reactor Trip or SI 0POP05-EO-ES01, Reactor Trip Response 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant 0POP05-EO-FRP1, Response to Imminent Pressurized Thermal Shock Conditions 0POP05-EO-FRZ1, Response to High Containment Pressure Additional Annunciator Response Procedures that were used by the Crew during the Scenario.

NOTE SIMULATOR SETUP (contd.)

The LogScenario Lesson Plan into Instructor MUST be Workstation asrun fromuser, lotnrc the left openmost Instructor Orchid (nstpsStation in then server), Simulator Booth to allow for recording and storing of Unlock Initial Conditions Group lotnrc. recorded parameter data.

Log into Instructor Workstation as lotnrc user, open Orchid (nstps server), then Unlock Initial Conditions Group lotnrc.

Reset to IC #189 and perform the following:

Switch Check Ensure red light on end of CP-010 off Ensure ICS Annunciators have stopped counting up

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 31 of 34 SIMULATOR SETUP (contd.)

Go to RUN and perform the following:

Ensure Simulator is ready by performing applicable checkoffs from LOR-GL-0006, LOR Conduct of Simulator Training Guidelines, Addendum 5, Simulator Readiness Checklist.

Ensure VCT Makeup Integrators are set as follows:

Momentarily place RC M/U CONT to STOP and then START to reset BA BATCH/GALLONS and TOT M/U BATCH/GALLONS counters to zero.

Reset BA BATCH/GALLONS setpoint to 0 gallons and reset TOT M/U BATCH/GALLONS setpoint to 10 gallons.

Verify BA Controller Pot setting is 3.85 Hang following ECO Caution Tags:

Tape an ECO Caution Tag next to PI-5532A for Starting Air Receiver #14 on ESF DG #12.

Open lesson plan for Scenario 3 in lotnrc directory for LOT 21, then EXECUTE lesson plan. These actions will set up any initial conditions for the scenario.

If this scenario IC has changing conditions (i.e. Xenon is changing, etc.), then place the simulator in FREEZE, otherwise it is OK to leave in RUN.

Run the scenario in accordance with the next section, Scenario Instructions.

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 32 of 34 SCENARIO INSTRUCTIONS NOTE Steps 1 to 4 below can be performed in the LOR Debrief Room prior to the crew coming into the Simulator provided exam security measures are taken.

1. Provide Shift Turnover sheets to the crew and review the information.

2. Have the Crew perform a Pre-Job Brief based on any items on the turnover sheet.

Ensure the candidates dont have any other questions about the Shift Turnover.

3. Ensure the Beacon book from the simulator is available to the crew if they are in the LOR Debrief Room.

4. Review the Simulator Differences list with the crew if needed.

5. When signaled by Simulator Staff, have the crew perform their board walkdown and inform the floor instructor when ready to take the watch.

6. Ensure the simulator is in RUN and verify simulator clock is set correctly. Note the time that the Crew takes the watch. ________________ Start Time.

NOTE Malfunction Step and/or Lesson Plan Steps (Events) are triggered upon the Lead Examiners signal during the scenario unless an agreed upon time is discussed with the examiner prior to the start of the scenario.

Always TRIGGER events in the Simulator Scenario Lesson Plans. This way delays associated with events will take place as intended.

Refer to EXPECTED BOOTH COMMUNCATIONS and EXPECTED BOOTH ACTIONS Sections for instructions for Instructor actions during the scenario.

7. Trigger the step titled Start Chart and ensure specified Recorded Parameters for the scenario begin recording as the scenario runs. If the chart speed is NOT set to 5400 seconds (90 minutes) then perform the following:

Under CHARTS click on SET TIME In the dialog box enter 5400 seconds (90 minutes)

Click OK.

8. Trigger MALFUNCTION STEP - This will insert Step #1, Event #1.

9. Trigger STEP 2 - Event #2

10. Trigger STEP 3 - Event #3

11. Trigger STEP 4 - Event #4 & 6

12. Place simulator in FREEZE when cued by the Lead Examiner to terminate scenario.

13. DO NOT RESET simulator until the steps on the next page are completed and all Examiners have completed Follow-Up Questioning.

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 33 of 34 SCENARIO INSTRUCTIONS (contd.)

NOTE Some scenarios will have more than one chart. For these, each chart file must be separately saved with a unique filename.

14. Saving Recorded Parameters Data Click on the Charts icon on the left side of the screen Select Pause icon, then select All Click on the Print Chart icon, then select All This will bring up a window in the TASK BAR called PRIMOPDF.

Click on Create PDF This will bring up a File Save As window.

Save to folder c:\Users\lotnrc\Desktop\LOT21 Charts. The file name will be LOT21 Scenario 3 followed by a name that identifies the crew (e.g. Crew A).

Save the new file. It will be saved in a folder already on the desktop. LOT21 Charts.

15. Saving Scenario SAM (Simulator Action Monitor)

Under TOOLS click on SAM In the dialog box that comes up click on SAVE TO Save as a TEXT FILE to folder c:\Users\lotnrc\Desktop\LOT21 Charts. The file name will be LOT21 SAM INFO Scenario 3 followed by a name that identifies the crew (e.g. Crew A).

LOT 21 NRC OP-TEST SCENARIO #3 Rev 1 Page 34 of 34 TURNOVER INFORMATION

• Reactor Power is at 100%.

• ESF DG #12, Starting Air Receiver #14 is out of service for maintenance.

• 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.

• RCS Boron Concentration is 1408 ppm.

• 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.

• No ESF DG FOSTs are on recirc.

LCO Actions:

None.

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 1 of 39 LOT 21 NRC EXAM SIMULATOR OPERATING TEST SCENARIO #4 Revision 1 Week of 09/25/2017

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 2 of 39 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 Open Loop Pump #11 and secure Open Loop Pump #12.

• ESF DG #12 is OOS for Maintenance.

Event No. Malf. No. Event Type* Event Description 1

(1 min) N/A BOP (N) Start Open Loop Pump #11 and Secure Open Loop Pump #12.

(60 seconds after crew takes the watch.)

2T (6 min) 02-19-03 RO (I) Controlling Channel of Pressurizer Pressure, PT-0457, fails low.

SRO (I, TS) 0.0 3 POSBBARG (N/A) 22904TCC SRO (TS) PZR PORV isolation valve, RC-MOV-0001B, loses control power.

1 (This malfunction will be inserted 1 minute after PT-0457 fails high.)

4T HCPD9623R (20 min) EV RO (C) CRDM Vent Fan 11A Trouble.

1 SRO (C) 5T 08-28-01 (30 min) 1 BOP (C) LPHD Pump #11 Trip.

SRO (C) 6T 05-03-04 ALL (M) SG 1D Tube Rupture. (~450 GPM & Ramps in over 2 minute (40 min) period.)

0.44 (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 1 Page 3 of 39 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2 2 Abnormal events (2-4) 4

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. Entry into a contingency EOP with substantive actions (>1 per scenario set) 0

6. Preidentified critical tasks (>2) 3 SCENARIO MISCELLANEOUS INFORMATION INSTRUCTOR NOTES:

• Critical Tasks are indicated by "C-##" in the position column and indicated in bold type. In some instances an

• will indicate that only a portion of the task listed is considered critical.

• Shaded cells indicate procedural entry points.

RECORDED PARAMETERS:

Recorded parameters will be determined during NRC Validation week.

The parameters identified for recording may be of value in evaluating crew performance. Once the scenario is complete for each crew, printout the recorded parameters and label the printout with date, time, crew number and scenario number. See Scenario Instructions section for further details on how to save the Recorded Parameters.

• SG 1D AFW OCIV AF-MOV-0019 (Green Light)

• SG 1D AFW Flow

• RCS Press Loop C W/R

• PZR Level

• SG 1D Steam Pressure

• RCS Subcooling

• HHSI Pump 1A (Green Light)

• PZR PORV RC-PCV-0655A (Red Light)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 4 of 39 SCENARIO OBJECTIVES Event 1 Objective

• During all modes of plant operating conditions, operate the Open Loop Auxiliary Cooling Water System in accordance with the plant operating procedures.

Events 2 & 3 Objective

• Respond as the Reactor Operator to Pressurizer Pressure Control system alarms per 0POP09-AN-04M8.

• Respond to a Pressurizer Pressure Control malfunction in accordance with 0POP04-RP-0001.

• Transfer Pressurizer Pressure Control channels per 0POP04-RP-0001.

• Given that a condition exists requiring entry into a Technical Specification, interpret Technical Specifications accurately.

Event 4 Objective

• Respond to Containment Cooling annunciators per appropriate annunciator response procedures.

• Start a CRDM Fan per 0POP02-HC-0001.

Event 5 Objective

• Respond to a Loss of Condensate Flow per 0POP04-CD-0001.

Event 6 Objective

• Respond to a Reactor Trip or Safety Injection in accordance with 0POP05-EO-EO00.

• Respond to a Steam Generator Tube Rupture in accordance with 0POP05-EO-EO30.

Event 7 Objective

• Given a Safety Injection, perform Addendum 5 in accordance with 0POP05-EO-EO00.

Event 8 Objective

• Monitor the Steam Dumps for proper operation by observing applicable Control Room indications.

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 5 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 1 (60 Seconds after taking the watch.)

Event

Description:

Start Open Loop Pump #11 and Secure Open Loop Pump #12.

Time Position Required Operator Actions Notes SRO Directs the BOP operator to start Open Loop Pump #11 and secure Open Loop Pump #12 IAW 0POP02-OC-0001, Open Loop Auxiliary Cooling System, Section 7.0.

(The Yard watch will report that OL Pump 11 seal AO water and oil level is SAT and the pump looks good for a start.)

BOP PLACE the handswitch for the OL-ACW Pump selected to be started in the "START" position.

• 1-HS-6784A OL-ACW Pump 11 (Step 7.1)

AO (Yard watch will report that OL-ACW Pump 11 is running SAT.)

BOP PLACE and HOLD the handswitch for the OL-ACW Pump to be secured in the "STOP" position.

• 1-HS-6785A OL-ACW Pump 12 (Step 7.2)

(Handswitch will be held in "STOP" until step 7.4.)

BOP IF the breaker for the OL-ACW Pump operated in Step 7.2 fails to immediately open, THEN RETURN the selected OL-ACW Pump handswitch to the "AUTO" position.

(Step 7.3)

(OL-ACW Pump #12 will stop with no issues.)

BOP WHEN Open Loop System pressure stabilizes, THEN RETURN the handswitch operated in STEP 7.2 to the "AUTO" position.

• 1-HS-6785A OL-ACW Pump 12 (Step 7.4)

(System pressure will stabilize in about 5 to 10 seconds.)

(EVENT 2 & 3 can be triggered on signal from the lead examiner.)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 6 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 2 and 3 (Examiner Trigger)

Event

Description:

Controlling Channel of PZR 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 Acknowledges and announces the following annunciator from 04M8:

• PRZR DNBR PRESS LOW (B-5)

• PRZR PRESS DEV LO B/U HTRS ON (D-7)

• PRZR PRESS LO RX TRIP ALERT (E-7)

• PRZR PRESS LO SI ALERT (F-7)

• PRZR PRESS LOW PORV BLKD (F-8)

Acknowledges and announces the following annunciator from 05M2:

• OTDT RX PRETRP (A-5)

Acknowledges and announces the following annunciator from 05M3:

• DELTA T ROD WTHDRWL BLK ALERT (A-4)

RO Identifies the failed pressure channel as PT-0457 failed low and performs the following immediate actions:

• Places Pressurizer Master Pressure Controller in MANUAL.

• Removes failed channel PT-0457 from control by selecting 455/456 or 455/458.

• Adjusts Pressurizer pressure Controller to control between 2220 and 2250 psig.

(These are immediate actions for a controlling PZR Pressure channel that has failed low.)

SRO Enters and directs the actions of 0POP04-RP-0001, Loss of Automatic Pressurizer Pressure Control.

SRO Verifies proper actions taken per Step 1 of 0POP04-RP-0001, Loss of Automatic Pressurizer Pressure Control.

(Step 1 RNO b)

RO Checks Pressurizer Pressure Controller operable.

(Step 2)

RO Checks Pressurizer PORVs closed.

(Step 3)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 7 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 2 and 3 (Examiner Trigger)

Event

Description:

Controlling Channel of PZR 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 Normal Pressurizer Spray Valves:

• Normal Pressurizer Spray Valves - CLOSED

• Pressurizer Spray Line temperature -

NORMAL (Step 4)

RO CHECK Pressurizer Auxiliary Spray Valve LV-3119 CLOSED (Step 5)

RO CHECK Pressurizer Pressure - GREATER THAN 2210 PSIG (Step 6)

RO CHECK Pressurizer Pressure - GREATER THAN 2250 PSIG (Step 7)

(Pressure should be less than 2250 psig and the US should go to Step 11.)

RO ENSURE An Operable Pressurizer Pressure Channel Is Selected On The Pressurizer Pressure Recorder Selector Switch (Step 11)

RO CHECK Pressurizer Pressure Controller RC-PK-0655A - OPERABLE (Step 12)

RO CHECK Pressurizer Pressure - BETWEEN 2220 AND 2250 PSIG (Step 13)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 8 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 2 and 3 (Examiner Trigger)

Event

Description:

Controlling Channel of PZR 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 The Following:

• Pressurizer Pressure Controller RC-PK-0655A demand signal - INDICATING NORMAL FOR EXISTING PLANT CONDITIONS

• Pressurizer spray valves - IN AUTO

• Pressurizer heater controls - IN AUTO

• Pressurizer PORVs - IN AUTO

• Pressurizer PORV Isolation Valves - OPEN (Step 14.a - 14.e)

(Event 3 - PZR PORV block valve RC-MOV-0001B will have a loss of control power (blown fuse) and associated BYPASS INOP light in.)

RO PLACE Pressurizer Pressure Controller in AUTO.

(Step 14 RNO 14.f)

RO Pressurizer pressure being maintained -

BETWEEN 2220 AND 2250 PSIG (Step 14.g)

SRO PERFORM the following:

• 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. (Action 21)

(Step 15 RNO 15.a and 15.b)

(NOTE: The P-11 TS is satisfied because only one channel is affected and the other 3 channels satisfy the Minimum Number of Channels OPERABLE)

SRO REFER TO Addendum 3 For Applicable Technical Specifications (Step 16)

(See TS Actions below.)

(Event #4 can occur after the SRO checks Tech Specs and at the discretion of the Lead Examiner.)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 9 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 2 and 3 (Examiner Trigger)

Event

Description:

Controlling Channel of PZR 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 Reactor Coolant Pumps - ALL OPERATING (Step 17)

SRO INITIATE Corrective Action For Failed Component (Step 18)

For PZR Pressure Channel PT-0457:

TS 3.3.1 Items 8, 10 & 11; Action 6-a TS 3.3.2 Item 1E; Action 20-a 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 />.

For RC-MOV-0001B, PZR PORV PCV-0656A Block Valve:

TS 3.4.4 Action d Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> restore the block valve to OPERABLE status or place its associated PORV in closed position; within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> restore the block valve to OPERABLE status or apply the requirements of the CRMP; otherwise, 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 10 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 4 (Examiner Trigger)

Event

Description:

CRDM Vent Fan 11A Trouble Time Position Required Operator Actions Notes RO Acknowledges and announces the following annunciator from 04M8:

• CRDM VENT FAN TRBL (F-2)

RO CHECK the following Plant computer points to determine affected fan:

• HCPD9623, RCB HVAC CRDM VT FAN 11A (22M1 - F2 Step 1)

(Fan 11A computer point.)

RO SECURE affected fan. CRDM Vent Fan 11A (22M1 - F2 Step 2)

RO START a non-affected train fan per 0POP02-HC-0001, Containment HVAC, within 15 minutes following performance of Step 2.

(22M1 - F2 Step 3)

SRO Directs RO to use 0POP02-HC-0001, Containment HVAC, to start CRDM Vent Fan 11C.

RO START selected CRDM vent fan(s).

Train C "VENT FAN 11C HC-VFN019" (0POP02-HC-0001 Step 8.1)

(Event #5 may occur on signal from the Lead Examiner.)

RO INITIATE Condition Report for affected fan.

(22M1 - F2 Step 4)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 11 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 5 (Examiner Trigger)

Event

Description:

LPHD Pump #11 Trip Time Position Required Operator Actions Notes BOP Acknowledges and announces the following annunciator from 08M3:

• LP HDP TRIP (A-4)

BOP Reports that Heater Drip Pump #11 has tripped.

Refers to Annunciator Response Procedure (ARP).

(The ARP will direct the crew to go to 0POP04-CD-0001, Loss of Condensate Flow.)

SRO Enters and directs the actions of 0POP04-CD-0001, Loss of Condensate Flow.

BOP Determines there are sufficient Condensate pumps in service for the current power level.

(Step 1)

(2 are required)

BOP ENSURE Discharge Valve Of Any Secured/Tripped Condensate Pump Is CLOSED (Steps 2)

BOP MONITOR ICS Parameters For Running Condensate Pumps:

• Motor winding temperatures < 266ºF

• Pump thrust bearing temperatures < 200 ºF (Steps 3)

(Condensate Pumps are operating normally)

BOP CHECK LPHD Pump status

• Determines LPHD Pump #11 has tripped.

• SRO Implements procedure Addendum 2.

(Step 4 RNO)

BOP CHECK FWH 15(25) & 16(26) Strings -

INSERVICE (Addendum 2, Step 1)

BOP CHECK DA Level Controller at 100% Demand (Addendum 2, Step 2)

(Demand will be at 100%)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 12 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 5 (Examiner Trigger)

Event

Description:

LPHD Pump #11 Trip Time Position Required Operator Actions Notes BOP START Third Condensate Pump Per Addendum 1, Condensate Pump Start That Requires Venting Prior To Start (Addendum 2, Step 3)

BOP Checks if SGFPT SEAL WTR DP LO Annunciators lit.

• If so, DA Level Control valve is throttled closed to clear SGFPT SEAL WTR DP LO alarms (3) on CP-006.

(Addendum 1, Steps 1 and 2)

(Condensate Pump 13 will be started.)

BOP VERIFY Miniflow Recirc Line Is Full By Dispatching An Operator To Vent The COND PUMP MINIFLOW RECIRC VENT For Pump To Be Started:

• Pump 13 1-CD-0786 (Addendum 1, Step 3)

AO (The TGB watch will report back that the recirc line has been vented.)

BOP Dispatch an operator to ENSURE 1-CD-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 (Addendum 1, Steps 4 and 5)

AO (The TGB watch will report back that CD-801 and CD-802 are open.)

BOP START The Selected Condensate Pump:

• COND PUMP 13 (Addendum 1, Step 6)

BOP Dispatch an Operator to CLOSE 1-CD-0802 COND PUMP 13 DISCH COMMON VENT LINE ISOL VALVE (Addendum 1, Step 7)

AO (The TGB watch will report back that CD-802 has been closed.)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 13 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 5 (Examiner Trigger)

Event

Description:

LPHD Pump #11 Trip Time Position Required Operator Actions Notes BOP PLACE DA Level Controller In Manual AND LOWER Demand To < 80%

(Addendum 1, Step 8)

(Will reduce the chance of a CP Bypass.)

BOP OPEN Condensate PUMP DISCH ISOL Valve For Condensate Pump Started To Place Pump In Service:

• PUMP 13 MOV-0088 (Addendum 1, Step 9)

(With 3 CD Pumps aligned and running there is a chance for a CP Bypass to occur.)

BOP CONTROL DA Level Control Valve To Restore DA Level (Addendum 1, Step 10)

(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 Dump Valve Is Maintaining Flash Tank Level (Addendum 2, Step 5)

BOP PERFORM The Following For The Affected LPHD Flash Tank:

• PLACE the flash tank level control valve controller in manual

• CLOSE the flash tank level control valve

• DISPATCH An Operator To Investigate The Cause For LPHD Pump Trip (Addendum 2, Step 6)

(Since the cause of the LPHD Pump 11 trip is unknown the crew will wait for maintenance investigation prior to trying a restart.)

(The crew will mark their place in Addendum 2 and GO TO procedure step 12.0.)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 14 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 (Examiner Trigger)

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 on ICS computer & RM-11 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-RC-0004, Steam Generator Tube Leakage.

(Only a few actions of 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 -

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 (Step 1)

SRO MAINTAIN Contact With Health Physics To Evaluate Radiological Conditions In The Secondary Plant Prior To Performing Local Operator Actions (Step 2)

SRO NOTIFY Chemistry To:

• SAMPLE SGs For Activity

• MONITOR RT-8041 and RT-8042 (Step 3)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 15 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 (Examiner Trigger)

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 THE BLOWDOWN DEMINERALIZERS (Step 4)

(The Demineralizers are not in service so crew will contact an operator to place them in service.)

AO (The MAB watch will report that they will work on putting the SGBD demins 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-EO-EO00, Reactor Trip or Safety Injection.

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 16 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 (Examiner Trigger)

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 Completes immediate actions of 0POP05-EO-EO00 and determines:

• Reactor is tripped

• Turbine is tripped

• AC ESF Busses are energized

• SI is not actuated (Steps 1 to 4)

(RO will complete immediate actions.

BOP Operator will monitor the plant and make an announcement of the Reactor trip.)

(During a pause between performing immediate actions and verifying immediate actions, the BOP will throttle AFW to reduce the RCS cooldown by:

BOP

• Resetting the AFW Reg Valves

• Throttling the AFW Reg Valves to lower total AFW flow.

Total AFW flow must remain above 576 gpm until at least one SG level is >14% NR {34% for adverse containment})

(Because of the SGTR and before beginning the verification of immediate actions the US may direct the BOP operator to secure AFWP #14 and cross connect AFW to SG 1D, if NR level <

14%{34%}, per the CIP for a faulted SG on 1D.

this is part of CT-18. See Page 19.)

SRO Directs/ensures the immediate actions of EO00, Reactor Trip/SI have been completed by performing a procedure read through of them.

BOP VERIFY Proper SI Equipment Operation Per ADDENDUM 5, VERIFICATION OF SI EQUIPMENT OPERATION (Step 5)

(See Actions on Page 26 - 29)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 17 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 (Examiner Trigger)

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 Required:

• Containment pressure GREATER THAN 9.5 PSIG (QDPS)

(RNO)

• PERFORM the following:

• CHECK Containment pressure - HAS EXCEEDED 9.5 PSIG (CP - 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.

(Step 6)

(Containment pressure will be less than 9.5 psig.)

RO CHECK RCP Seal Cooling:

• ENSURE seal injection flow between 6 and 13 gpm (Step 7)

(RO may have to adjust seal injection.)

RO MONITOR RCS Temperatures

• WITH ANY RCP RUNNING, RCS TAVG STABLE AT OR TRENDING TO 567°F OR

• WITHOUT ANY RCP RUNNING, RCS TCOLD STABLE AT OR TRENDING TO 567°F (Step 8)

(If AFW has been properly throttled from the original Reactor Trip then RCS temperature should be trending to 567°F)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 18 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 (Examiner Trigger)

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 Status:

• PORVs CLOSED

• Normal pressurizer spray valves - CLOSED

• Auxiliary spray valve - CLOSED

• Excess letdown isolation valves - CLOSED (Step 9)

RO MONITOR If RCPs Should Be Stopped:

• HHSI pump - AT LEAST ONE RUNNING

• RCS pressure - LESS THAN 1430 PSIG (RNO)

• GO TO Step 11 (Step 10)

(Reactor Coolant Pump Trip Criteria will probably NOT be met if AFW has been properly throttled.)

RO VERIFY The Following Containment Isolation Valves - CLOSED

• Seal return isolation valves

• Containment atmosphere radiation monitor isolation valves (Step 11)

RO CHECK If SG Secondary Pressure Boundary Intact:

• CHECK pressures in all SGs -

• CONTROLLED OR RISING

• GREATER THAN CONTAINMENT PRESSURE (Step 12)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 19 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 (Examiner Trigger)

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 If SG Tubes Are Intact:

• Main steamline radiation NORMAL

• IF SG blowdown in service, THEN SG

• 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.

(Step 13)

BOP Completes 0POP05-EO-EO00, Addendum 5.

SRO Informs crew of transition to 0POP05-EO-EO30, Steam Generator Tube Rupture, and to monitor Critical Safety Functions ALL Monitors the status of Critical Safety Functions when the crew transitions to 0POP05-EO-EO30.

(Cannot implement FRPs until Addendum 5 of 0POP05-EO-EO00, Reactor Trip or Safety Injection, is completed.)

RO MONITOR If RCPs Should Be Stopped:

• HHSI pumps AT LEAST ONE RUNNING

• RCS pressure LESS THAN 1430 PSIG (Step 1)

(Pressure should be greater than RCP trip criteria.)

BOP Identifies Ruptured SG as SG 1D.

(Step 2)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 20 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 (Examiner Trigger)

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 ISOLATE Flow From Ruptured SG(s):

(CT-18)

• ADJUST ruptured SG(s) PORV controller setpoint to BETWEEN 1260 PSIG AND 1265 PSIG

• CHECK ruptured SG(s) PORV controller IN AUTO

• CHECK ruptured SG(s) PORV CLOSED

• 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

• RESET SG LO-LO level AFW actuations

• TRIP turbine-driven AFW pump

• CLOSE turbine-driven AFW pump steam inlet valve AO

• Denergize turbine-driven steam inlet valve (EAB watch will report back that AFWP 14 Steam Inlet MOV-0143 has been de-energized.)

• ENSURE turbine-driven AFW pump trip/throttle valve closed

• CLOSE ruptured SG(s) MSIV(s) and MSIB(s)

• Verifies SG 1D level is >14% then isolates AFW to SG 1D.

• RESET SI AND SG LO-LO LEVEL SIGNALS.

• CLOSE SG 1D AFW OCIV.

(Steps 3 and 4)

(NOTE: Event #7 does not affect CT-18. See Page 26 for details on Event #7.)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 21 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 (Examiner Trigger)

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 Ruptured SG(s) Pressure GREATER THAN 468 PSIG (Step 5)

RO CHECK Pressurizer PORVs And Isolation Valves:

• Power to isolation valves AVAILABLE

• PORVs CLOSED

• Isolation valves AT LEAST ONE OPEN (Step 6)

SRO DETERMINE required core exit temperature based on ruptured SG pressure.

(Step 7.a)

(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.)

RO CHECK pressurizer pressure LESS THAN 1985 PSIG BLOCK Low Steamline Pressure SI (Steps 7.b and 7.c)

BOP CHECK condenser AVAILABLE (Step 7.d)

BOP CHECK steam dump in steam pressure mode (RNO)

• PLACE steam dump controller in MANUAL with zero demand.

• PLACE steam dump mode selector switch to STEAM PRESSURE mode.

(Step 7.e)

RO CHECK RCS TAVG LESS THAN 563°F (Step 7.f)

(At this time TAVG should be >563°F)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 22 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 (Examiner Trigger)

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 intact SG(s) at maximum rate

• Determines Steam Dumps are not responding (Step 7.h)

(Event #8 - Group 1 steam dumps will fail to open. Crew may not notice until RCS temperature goes below 563°F)

SRO Direct the BOP operator to perform the cooldown by dumping steam at the maximum rate using SG PORV(s).

(RNO 7.d)

(Crew will continue to Step 8 while cooldown commences)

RO RESET the following:

• SI

• SI AUTO RECIRC

• ESF Load Sequencers

• Containment Isolation Phase A

• Containment Isolation Phase B (Steps 8-12)

RO/BOP ESTABLISH IA To Containment:

• IA pressure GREATER THAN 95 PSIG

• OPEN IA OCIV (Step 13)

BOP MONITOR Intact SG Levels:

• NR levels GREATER THAN 14%

• CONTROL AFW to maintain NR levels BETWEEN 22% and 50%

(Step 14)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 23 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 (Examiner Trigger)

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 If RCS Cooldown Should Be Stopped:

• Core exit T/Cs LESS THAN REQUIRED TEMPERATURE

• STOP RCS cooldown

• MAINTAIN core exit TCs LESS THAN REQUIRED TEMPERATURE (Step 15)

(Crew will not continue until target temperature is reached and cooldown is stopped.)

BOP CHECK Ruptured SG(s) Pressure STABLE OR RISING (Step 16)

RO CHECK RCS Subcooling Based On Core Exit T/Cs GREATER THAN 55°F (Step 17)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 24 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 (Examiner Trigger)

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 Flow (CT-19) And Refill Pressurizer:

• Normal pressurizer spray 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:

• RCS pressure LESS THAN RUPTURED SG PRESSURE

• Pressurizer level GREATER THAN 8%

OR

• BOTH of the following:

• RCS pressure WITHIN 300 PSI OF RUPTURED SG PRESSURE

• Pressurizer level GREATER THAN 38%

OR

• Pressurizer level GREATER THAN 70%

OR

• 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 (Step 18.e & f)

(After completion of this step, go to step 21)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 25 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: 6, 7 and 8 (Examiner Trigger)

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:

• RCS subcooling based on core exit T/Cs GREATER THAN 35°F

• Secondary heat sink:

• Total AFW flow to intact SGs GREATER THAN 576 GPM AVAILABLE OR

• NR level in at least one intact SG GREATER THAN 14%

• RCS pressure STABLE OR RISING

• Pressurizer level GREATER THAN 8%

(Step 21)

RO STOP HHSI Pumps And PLACE In AUTO (C-20) (Step 22)

Terminate Scenario

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 26 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: Event 7 and Addendum 5 actions Event

Description:

SG 1D FWIV, FW-FV-7144, fails to auto close.

Time Position Required Operator Actions Notes BOP VERIFY FW isolation:

• SGFPTs - TRIPPED

• SU SGFP - TRIPPED

• VERIFY the following valves - CLOSED

• FWIVs - Event #7

• FWIBs

• FW preheater bypass valves

• FW regulating valves

• Low power FW regulating valves

• SG blowdown isolation valves

• SG sample isolation valves (0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 5, Verification of Equipment Operation.

(Step 1)

(This addendum is performed in parallel with Steps 5 to 14 of 0POP05-EO-EO00, Reactor Trip or Safety Injection.)

(Event #7 - SG 1D FWIV, FW-FV-7144, fails to auto close and operator has to manually close valve using the safety-grade solenoid switches. If NOT closed, CT-18 is NOT affected because the MFRV and LPFRV for SG 1D will be closed due to the FWI signal.)

BOP CHECK if main steamline should be isolated:

• CHECK for any of the following conditions:

• Containment pressure - GREATER THAN OR EQUAL TO 3 PSIG OR

• SG pressure (without low steamline pressure SI blocked) - LESS THAN OR EQUAL TO 735 PSIG OR

• 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 (Step 2)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 27 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: Event 7 and Addendum 5 actions Event

Description:

SG 1D FWIV, FW-FV-7144, fails to auto close.

Time Position Required Operator Actions Notes BOP VERIFY AFW system status:

• Motor-driven pump - RUNNING

• Turbine-driven pump - RUNNING (Step 3)

BOP VERIFY AFW valve alignment - PROPER EMERGENCY ALIGNMENT (Step 4)

BOP VERIFY total AFW Flow - GREATER THAN 576 GPM (Step 5)

BOP VERIFY containment isolation phase A:

• Phase A - ACTUATED

• Phase A valves - CLOSED, REFER TO ADDENDUM 1, PHASE A ISOLATION VERIFICATION (Step 6)

BOP VERIFY ECW status:

• ECW pumps - RUNNING

• ECW pump discharge isolation valves -

OPEN (Step 7)

BOP VERIFY CCW pumps - RUNNING (Step 8)

BOP VERIFY RCFC status:

• RCFCs - RUNNING

• Cooling water - TRANSFERRED TO CCW (Step 9)

BOP VERIFY SI pump status:

• HHSI pumps - RUNNING

• LHSI pumps - RUNNING (Step 10)

BOP VERIFY SI valve alignment - PROPER EMERGENCY ALIGNMENT (Step 11)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 28 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: Event 7 and Addendum 5 actions Event

Description:

SG 1D FWIV, FW-FV-7144, fails to auto close.

Time Position Required Operator Actions Notes BOP VERIFY SI flow:

• RCS pressure - LESS THAN 1745 PSIG

• HHSI pump flow - INDICATED

• RCS pressure - LESS THAN 415 PSIG (RNO)

• GO TO Step 13 of this Addendum.

(Step 12)

(RCS pressure may or may not be less than 1745 psig but will be greater than 415 psig so BOP will continue to step 13.)

BOP VERIFY containment ventilation 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 (Step 13)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 29 of 39 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 4 Event No.: Event 7 and Addendum 5 actions Event

Description:

SG 1D FWIV, FW-FV-7144, fails to auto close.

Time Position Required Operator Actions Notes BOP VERIFY ventilation actuation:

• 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 (Step 14)

BOP NOTIFY Unit Supervisor that Addendum 5 is COMPLETE (Step 15)

SRO IMPLEMENT Functional Restoration Procedures as required (Step 16)

SRO RETURN TO procedure step in effect.

(Step 17)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 30 of 39 CRITICAL TASK

SUMMARY

SAT/

POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA UNSAT BOP CT-18 Isolate feedwater flow into and ISOLATE RUPTURED SG D BY: steam flow from the ruptured SG before a transition to EC31

• ADJUST RUPTURED SG(S) occurs.

PORV CONTROLLER SETPOINT TO BETWEEN SAFETY SIGNIFICANCE --

1260 PSIG AND 1265 PSIG Failure to isolate the ruptured

• PLACING SG 1D PORV IN SG causes a loss of differential AUTO. pressure between the ruptured

• ISOLATE STEAM SUPPLY SG and the intact SGs. Upon a TO TURBINE-DRIVEN AFW loss of differential pressure, the PUMP crew must transition to a

• RESET SI contingency procedure that

• RESET SG LO-LO constitutes an incorrect LEVEL AFW performance that ACTUATIONS ...necessitates the crew taking

• TRIP TURBINE-DRIVEN compensating action which AFW PUMP complicates the event mitigation strategy...... If the

• CLOSE TURBINE-leakage continues, the SG DRIVEN AFW PUMP inventory increase leads to STEAM INLET VALVE water release through the

• ENSURE TURBINE-DRIVEN PORV or safety valve(s) or to AFW PUMP SG overfill, which seriously TRIP/THROTTLE VALVE damages the SG as a fission-CLOSED product barrier and

• CLOSE RUPTURED SG(S) complicates mitigation. To stop MSIV(S) AND MSIB(S) the primary-to-secondary

• CLOSE SG 1D AFW OCIV. leakage, the crew must intervene to mitigate excessive (NOTE: Event #7 does not affect inventory increase in the CT-18. See Page 26 for details on ruptured SG.

Event #7.)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 31 of 39 ALL CT-20 Depressurize RCS to meet SI DEPRESSURIZE RCS TO SI termination criteria before TERMINATION CRITERIA PER either of the following occur:

STEP 19 OF 0POP05-EO-EO30, 1) SG PORV or Safety Valve STEAM GENERATOR TUBE opens, 2) SG narrow range RUPTURE. level goes offscale high.

SAFETY SIGNIFICANCE --

Failure to stop reactor coolant leakage into a ruptured SG by depressurizing the RCS (when it is possible to do so) needlessly complicates mitigation of the event. It also constitutes a significant reduction of safety margin beyond that irreparably introduced by the scenario.

The STP FSAR assumes that for a design SGTR (the complete severance of a single Steam Generator tube) that flow from the RCS to the SG is terminated in time to prevent a radioactive discharge through SG PORVs or Safety Valves. If the primary-to-secondary leakage is not stopped, the SG pressure increases until either the SG PORV or the safety valve(s) opens; releasing radioactivity to the environment.

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 32 of 39 RO CT-21 Terminate SI prior to TERMINATE SI BY PLACING radioactive discharge through a ALL THREE HHSI PUMPS IN SG PORV or safety valve.

STOP AND THEN BACK TO SAFETY SIGNIFICANCE --

AUTO. Failure to terminate SI and control RCS pressure and makeup flow during a SGTR (when it is possible to do so) needlessly complicates the mitigation strategy. It also constitutes a significant reduction of safety margin beyond that irreparably introduced by the scenario.

The STP FSAR assumes that flow from the RCS to the SG is terminated in time to prevent a radioactive discharge through SG PORVs or Safety Valves.

If the primary-to-secondary leakage is not stopped, the SG pressure increases until either the SG PORV or the safety valve(s) opens, releasing radioactivity to the environment. If the leakage continues, the SG inventory increase leads to water release through the PORV or safety valve(s) or to SG overfill, which could cause an insoluble fault in the ruptured SG, greatly complicating mitigation. To stop the primary-to-secondary leakage, the crew must intervene.

NOTE: (Per NUREG-1021, Appendix D)

If an operator or the Crew significantly deviates from or fails to follow procedures that affect the maintenance of basic safety functions, those actions may form the basis of a CT identified in the post-scenario review.

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 33 of 39 EXPECTED BOOTH COMMUNICATIONS EVENT 1:

• As a Plant Operator, when called:

• Yard watch will report that Open Loop Pump #11 seal water and oil level is SAT and the pump looks good for a start.

• Yard watch will report that Open Loop Pump #11 is running SAT after it is started.

EVENT 2 & 3:

• As I&C and/or Electrical Maintenance or the Duty Maintenance Supervisor, if notified of PZR PT-0457 failure and RC-MOV-0001B loss of control power, report that an I&C and/or electrical maintenance crews will be assembled for support. No further action is necessary.

• As Operations Manager, acknowledge the failure of PZR PT-0457 and RC-MOV-0001B.

No further action is necessary.

EVENT 4:

• As Electrical Maintenance or the Duty Maintenance Supervisor, if notified of the failure of CRDM Vent Fan 11A, report that an electrical maintenance crew will be assembled for support. No further action is necessary.

• As Operations Manager, acknowledge the failure CRDM Vent Fan 11A. No further action is necessary.

EVENT 5:

• As a Plant Operator, when called to investigate LPHD Pump #11, report that the breaker has an over current flag but that the pump looks OK locally.

• As a Plant Operator, when called to help start CD Pump #13:

• TGB watch will report that CD Pump 13 recirc line has been vented. (No wait time needed as time compression has been allowed.)

• TGB Watch will report that CD-801 and CD802 are open. (No wait time needed as time compression has been allowed.)

• TGB Watch will report that CD-802 has been closed after one minute.

• As Mechanical Maintenance or the Duty Maintenance Supervisor, if notified LPHD Pump

1. 11, report that a mechanical maintenance crew will be assembled for support. No further action is necessary.

• As Operations Manager, acknowledge the trip of LPHD Pump 11. No further action is necessary.

EVENT 6:

• As a Plant Operator, when called:

• About SGBD Demins, report that the demins are not in service and that you will work on putting the demins in service. No further actions are required.

• To de-energize AFWP 14 Steam Inlet MOV, MS-MOV-0143, report back that the MOV has been de-energized after one minute. (See Expected Booth Actions)

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 34 of 39 EXPECTED BOOTH ACTIONS

1. If asked to open the DA High level Dump Valves then trigger the step for DA High Level Dump Valves.

2. If asked to fill the AFWST then trigger the step for AFWST Makeup

3. If asked to de-energize AFWP 14 Steam Inlet MOV then trigger the step 'E1D11/5C MOV-0143'

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 35 of 39 SIMULATOR SETUP NOTE ALL Annunciator Response Procedures (ARPs) must be checked if this scenario is the first to be run on this day. Setup for subsequent runs of this scenario only requires those ARPs that were actually marked in to be checked.

Instructors running the scenario must keep track of which ARPs these are, otherwise, all will have to be checked for subsequent scenarios as well.

Check and clean the following procedures:

0POP02-OC-0001, Open Loop Auxiliary Cooling System 0POP04-RP-0001, Loss of Automatic Pressurizer Pressure Control 0POP09-AN-22M1, F-2, CRDM VENT FAN TRBL 0POP02-HC-0001, Containment HVAC 0POP04-CD-0001, Loss of Condensate Flow 0POP04-RC-0004, Steam Generator Tube Leakage 0POP05-EO-EO00, Reactor Trip or SI 0POP05-EO-EO30, Steam Generator Tube Rupture Additional Annunciator Response Procedures that were used by the Crew during the Scenario.

NOTE SIMULATOR SETUP (contd.)

The LogScenario Lesson Plan into Instructor MUST be Workstation asrun fromuser, lotnrc the left openmost Instructor Orchid (nstpsStation in then server), Simulator Booth to allow Unlock for recording Initial Conditionsand storing Group of recorded parameter data.

lotnrc.

Log into Instructor Workstation as lotnrc user, open Orchid (nstps server), then Unlock Initial Conditions Group lotnrc.

Reset to IC #190 and perform the following:

Switch Check Ensure red light on end of CP-010 off Ensure ICS Annunciators have stopped counting up

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 36 of 39 SIMULATOR SETUP (contd.)

Go to RUN and perform the following:

Ensure Simulator is ready by performing applicable checkoffs from LOR-GL-0006, LOR Conduct of Simulator Training Guidelines, Addendum 5, Simulator Readiness Checklist.

Ensure VCT Makeup Integrators are set as follows:

Momentarily place RC M/U CONT to STOP and then START to reset BA BATCH/GALLONS and TOT M/U BATCH/GALLONS counters to zero.

Reset BA BATCH/GALLONS setpoint to 0 gallons and reset TOT M/U BATCH/GALLONS setpoint to 10 gallons.

Verify BA Controller Pot setting is 3.85 Hang following ECO Caution Tags:

ESF DG#12 stop plunger in PTS position ESF DG#12 Output Breaker handswitch in PTL Open lesson plan for Scenario 4 in lotnrc directory for LOT 21, then EXECUTE lesson plan. These actions will set up any initial conditions for the scenario.

If this scenario IC has changing conditions (i.e. Xenon is changing, etc.), then place the simulator in FREEZE, otherwise it is OK to leave in RUN.

Run the scenario in accordance with the next section, Scenario Instructions.

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 37 of 39 SCENARIO INSTRUCTIONS NOTE Steps 1 to 4 below can be performed in the LOR Debrief Room prior to the crew coming into the Simulator provided exam security measures are taken.

1. Provide Shift Turnover sheets to the crew and review the information.

2. Have the Crew perform a Pre-Job Brief based on any items on the turnover sheet.

Ensure the candidates dont have any other questions about the Shift Turnover.

3. Ensure the Beacon book from the simulator is available to the crew if they are in the LOR Debrief Room.

4. Review the Simulator Differences list with the crew if needed.

5. When signaled by Simulator Staff, have the crew perform their board walkdown and inform the floor instructor when ready to take the watch.

6. Ensure the simulator is in RUN and verify simulator clock is set correctly. Note the time that the Crew takes the watch. ________________ Start Time.

NOTE Malfunction Step and/or Lesson Plan Steps (Events) are triggered upon the Lead Examiners signal during the scenario unless an agreed upon time is discussed with the examiner prior to the start of the scenario.

Always TRIGGER events in the Simulator Scenario Lesson Plans. This way delays associated with events will take place as intended.

Refer to EXPECTED BOOTH COMMUNCATIONS and EXPECTED BOOTH ACTIONS Sections for instructions for Instructor actions during the scenario.

7. Trigger the step titled Start Chart and ensure specified Recorded Parameters for the scenario begin recording as the scenario runs. If the chart speed is NOT set to 5400 seconds (90 minutes) then perform the following:

Under CHARTS click on SET TIME In the dialog box enter 5400 seconds (90 minutes)

Click OK.

8. The Crew will perform Event #1.

9. Trigger MALFUNCTION STEP - This will insert Step #1, Event #2 & 3.

10. Trigger STEP 2 - Event #4

11. Trigger STEP 3 - Event #5

12. Trigger STEP 4 - Event #6, 7 & 8

13. Place simulator in FREEZE when cued by the Lead Examiner to terminate scenario.

14. DO NOT RESET simulator until the steps on the next page are completed and all Examiners have completed Follow-Up Questioning.

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 38 of 39 SCENARIO INSTRUCTIONS (contd.)

NOTE Some scenarios will have more than one chart. For these, each chart file must be separately saved with a unique filename.

15. Saving Recorded Parameters Data Click on the Charts icon on the left side of the screen Select Pause icon, then select All Click on the Print Chart icon, then select All This will bring up a window in the TASK BAR called PRIMOPDF.

Click on Create PDF This will bring up a File Save As window.

Save to folder c:\Users\lotnrc\Desktop\LOT21 Charts. The file name will be LOT21 Scenario 4 followed by a name that identifies the crew (e.g. Crew A).

Save the new file. It will be saved in a folder already on the desktop. LOT21 Charts.

16. Saving Scenario SAM (Simulator Action Monitor)

Under TOOLS click on SAM In the dialog box that comes up click on SAVE TO Save as a TEXT FILE to folder c:\Users\lotnrc\Desktop\LOT21 Charts. The file name will be LOT21 SAM INFO Scenario 4 followed by a name that identifies the crew (e.g. Crew A).

LOT 21 NRC OP-TEST SCENARIO #4 Rev 1 Page 39 of 39 TURNOVER INFORMATION Reactor Power is at 100%.

• Due to an issue with seal water to Open Loop Pump #12, start Open Loop Pump #11 and secure Open Loop Pump #12 after taking the watch. The pump is expected to be out of service for two days.

• The Yard watch has been briefed and is standing by at the CWIS.

• 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.

• RCS Boron Concentration is 1408 ppm.

• 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.

• No ESF DG FOSTs are on recirc.

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.

Rev. 3 ES-301 Transient and Event Checklist Form ES-301-5 Facility: South Texas Project Date of Exam: 09-25-17 Operating Test No.: LOT 21 NRC Scenarios A E P V 1 (spare) 2 3 4 T M P E O I L N T N I T C

A I A T L M N Y U T P M(*)

E CREW POSITION CREW POSITION CREW CREW POSITION POSITION Crew A S A B S A B S A B S A B R I U U1,U2, R T O R T O R T O R T O RO1 O C P O C P O C P O C P U1 3 3 2 1 1 0 RX RO 0 1 1 1 NOR SRO-I 3,4,5 1,2,3 2,5 6 4 4 2 I/C ,8

,5 SRO-U MAJ 6,7 4,6 4,6 4 2 2 1 TS 2,3 2,3 2 0 2 2 U2 3 3 2 1 1 0 RX RO 0 1 1 1 NOR SRO-I 3,5,8 1,5 1,2,5 6 4 4 2 I/C 6,7 4,6 4,6 4,6 4 2 2 1 SRO-U MAJ TS 2,3 1,2 2 0 2 2 RO1 1 1 0 RX 3 3 2 RO NOR 1 1 1 1 1 1 4 2,6 1,2 5,7 7 4 4 2 SRO-I I/C

,8 SRO-U 6,7 4,6 4,6 6 5 2 2 1 MAJ TS 0 0 2 2 NOTE:

TOTALs are added from Scenarios 2, 3 & 4.

Scenario 1 attributes are not included in the totals since it was the spare.

Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (SRO-I) must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an SRO-I additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a one-for-one basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

4. For licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

Rev. 3 ES-301 Transient and Event Checklist Form ES-301-5 Facility: South Texas Project Date of Exam: 09-25-17 Operating Test No.: LOT 21 NRC Scenarios A E P V 1 (Spare) 2 3 4 T M P E O I L N T N I T C

A I A T L M N Y U T P M(*)

E CREW POSITION CREW POSITION CREW CREW POSITION POSITION S A B S A B S A B S A B R I U Crew B R T O R T O R T O R T O U3, I1, O C P O C P O C P O C P I2 U3 3 3 2 1 1 0 RX RO 0 1 1 1 NOR SRO-I 3,4,5 1,2,3 2,5 6 4 4 2 I/C ,8

,5 SRO-U 6,7 4,6 4,6 4 2 2 1 MAJ TS 2,3 2,3 2 0 2 2 I1 RX 3 3 2 1 1 0 RO NOR 0 1 1 1 SRO-I 3,5,8 1,5 1,2,5 2,4 7 4 4 2 I/C SRO-U MAJ 6,7 4,6 4,6 6 5 2 2 1 TS 1,2 2 0 2 2 I2 RX 3 3 2 1 1 0 RO 1 1 1 1 1 1 SRO-I NOR I/C 4 2,6 1,2 2,4 9 4 4 2 5,7, SRO-U 8 MAJ 6,7 4,6 4,6 6 5 2 2 1 TS 2,3 2 0 2 2 NOTE:

TOTALs are added from Scenarios 1, 2 & 3.

Scenario 4 attributes are included but are based on an estimate of what the Crew positions would be and are not included in the TOTAL.

Instructions:

5. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (SRO-I) must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an SRO-I additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

6. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a one-for-one basis.

7. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

8. For licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

Rev. 3 ES-301 Transient and Event Checklist Form ES-301-5 Facility: South Texas Project Date of Exam: 09-25-17 Operating Test No.: LOT 21 NRC Scenarios A E P V 1 (Spare) 2 3 4 T M P E BOP is a O I L N surrogate for T N I T C

this scenario. A I A T L M N Y U T P M(*)

E CREW POSITION CREW POSITION CREW CREW POSITION POSITION S A B S A B S A B S A B R I U Crew C R T O R T O R T O R T O U4, I3, O C P O C P O C P O C P I4 U4 3 3 2 1 1 0 RX RO 0 1 1 1 NOR SRO-I 3,4,5 1,2,3 2,5 6 4 4 2 I/C ,8

,5 SRO-U 6,7 4,6 4,6 4 2 2 1 MAJ TS 2,3 2,3 2 0 2 2 I3 RX 3 3 2 1 1 0 RO NOR 0 1 1 1 SRO-I I/C 3,5,8 1,5 1,2,5 2,4 7 4 4 2 SRO-U MAJ 6,7 4,6 4,6 6 5 2 2 1 TS 1,2 2 0 2 2 I4 RX 3 3 2 1 1 0 RO NOR 1 1 1 1 1 1 SRO-I I/C 4 2,6 1,2 2,4 9 4 4 2 SRO-U 5,7

,8 MAJ 6,7 4,6 4,6 6 5 2 2 1 TS 2 0 2 2 2,3 NOTE:

TOTALs are added from Scenarios 1, 2 & 3.

Scenario 4 attributes are included but are based on an estimate of what the Crew positions would be and are not included in the TOTAL.

Instructions:

9. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (SRO-I) must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an SRO-I additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

10. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a one-for-one basis.

11. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

12. For licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

Rev. 3 Rev. 3 ES-301 Competencies Checklist Form ES-301-6 Facility: South Texas Project Date of Examination: 09-25-17 Operating Test No.: LOT 21 NRC APPLICANTS - Crew A RO RO RO1 RO SRO-I SRO-I SRO-I SRO-I SRO-U1 SRO-U2 SRO-U SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose 3,4, 1,2, 1,3, 2,3, 3,6, 2,3, 5,7, 5,6, 3,5, 4,5, Events and Conditions 7,8 4,6 8 6 6 4,6 8 Comply With and 3,4, 2,3, 1,3, 1,5, 2,3, 3,6, 2,3, 5,6, 4,5, 4,5, 6,7, Use Procedures (1) 7,8 4,6 8 6 6 5,6 8

Operate Control 1,3, 1,5, 2,3, 3,6, 2,3, N/A N/A 4,5, 6,7, Boards (2) 4,6 8 6

4,6 8

Communicate and ALL ALL ALL ALL ALL ALL ALL Interact Demonstrate Supervisory ALL N/A N/A ALL N/A N/A N/A Ability (3)

Comply With and 2,3 N/A N/A 1,2 N/A N/A N/A Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Additional NOTE: Competencies for Scenarios are based on estimate of Crew lineup.

Instructions:

Check the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Forms ES-303-1 and ES-303-3 describe the competency rating factors.)

Rev. 3 ES-301 Competencies Checklist Form ES-301-6 Facility: South Texas Project Date of Examination: 09-25-17 Operating Test No.: LOT 21 NRC APPLICANTS - Crew B RO RO RO RO SRO-I SRO-I1 SRO-I2 SRO-I SRO-U3 SRO-U SRO-U SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose 3,4, 1,2, 1,3, 1,2, 2,3, 1,3, 5,7, 5,6, 3,5, 2,4 4,5, 3,4, Events and Conditions 7,8 4,6 6

5 6 5,6 8

Comply With and 3,4, 2,3, 1,3, 1,3, 1,2, 1,5, 2,3, 5,6, 4,5, 4,5, 2,4 4,5, 3,4, 6,7, Use Procedures (1) 7,8 4,6 6 6 6 5,6 8 Operate Control 1,3, 1,3, 1,3, 2,3, 2,4, N/A 4,5, N/A 4,5, 4,5, N/A Boards (2) 4,6 6

6 6 6 Communicate and ALL ALL ALL ALL ALL ALL ALL ALL Interact Demonstrate Supervisory ALL N/A N/A ALL N/A N/A N/A ALL Ability (3)

Comply With and 2,3 N/A N/A 1,2 N/A N/A N/A 2,3 Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Additional NOTE: Competencies for Scenarios are based on estimate of Crew lineup.

Instructions:

Check the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Forms ES-303-1 and ES-303-3 describe the competency rating factors.)

Rev. 3 ES-301 Competencies Checklist Form ES-301-6 Facility: South Texas Project Date of Examination: 09-25-17 Operating Test No.: LOT 21 NRC APPLICANTS - Crew C RO RO RO RO SRO-I SRO-I3 SRO-I4 SRO-I SRO-U4 SRO-U SRO-U SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose 3,4, 1,2, 1,3, 1,2, 2,3, 1,3, 5,7, 5,6, 3,5, 2,4 4,5, 3,4, Events and Conditions 7,8 4,6 6

5 6 5,6 8

Comply With and 3,4, 2,3, 1,3, 1,3, 1,2, 1,5, 2,3, 5,6, 4,5, 4,5, 2,4 4,5, 3,4, 6,7, Use Procedures (1) 7,8 4,6 6 6 6 5,6 8 Operate Control 1,3, 1,3, 1,3, 2,3, 2,4, N/A 4,5, N/A 4,5, 4,5, N/A Boards (2) 4,6 6

6 6 6 Communicate and ALL ALL ALL ALL ALL ALL ALL ALL Interact Demonstrate Supervisory ALL N/A N/A ALL N/A N/A N/A ALL Ability (3)

Comply With and 2,3 N/A N/A 1,2 N/A N/A N/A 2,3 Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Additional NOTE: Competencies for Scenarios are based on estimate of Crew lineup.

Instructions:

Check the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Forms ES-303-1 and ES-303-3 describe the competency rating factors.)