ML072320335

GG-05-2007-FINAL Operating Exam, Operations Training, Determine Shift Staffing to Meet Shift Requirements

ML072320335
Person / Time
Site:	Grand Gulf
Issue date:	05/30/2007
From:	Entergy Operations
To:	Office of Nuclear Reactor Regulation
References
GJPM-SRO-ADM-11, Rev 00
Download: ML072320335 (257)

Text

GRAND GULF Number: GJPM-SRO-ADM-11 NUCLEAR STATION Revision: 00 Page: 1 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials TRAINING PROGRAM:

OPERATIONS TRAINING

• LESSON PLAN TITLE:

Determine Shift Staffing to Meet Shift Requirements APPROXIMATE TIME REQUIRED: 15 Minutes PREREQUISITES: NONE SUPPORTING LESSONS: NONE New Material Minor Revision Major Revision REASON FOR REVISION:

New JPM REVIEW / APPROVAL (Print Name): Electronic Approval (TEAR # )

Prepared By:

Preparer Date Reviewed By:

Technical Reviewer (e.g., SME, line management) Date Instructional Adequacy Determined By:

ITPL (Rev 0); Qualified Instructor (All other revisions) Date Approved By:

++

Discipline Training Supervisor Date Effective Date:

• Date

++

Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on the Training Development Review Worksheet FLEET/REGIONAL PROGRAM CONCURRENCE:

Fleet ENS ENN Not Applicable ANO PNPS CNPS RBS ECH VY GGNS WF3 IPEC WPO JAF

• Indexing Information GJPM-SRO-ADM11.00 Page 1 of 257

GRAND GULF Number: GJPM-SRO-ADM-11 NUCLEAR STATION Revision: 00 Page: 2 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Generic Instructions

1. Standard cues for valve operation:

a. MOVs:

1) "Full open" = "red light on, green light off"

2) "Full closed" = "red light off, green light on"

b. Manual valves

1) "Full open" = "you feel resistance in the counter-clockwise direction"

2) "Full closed" = "you feel resistance in the clockwise direction"

2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.

3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.

4. Obtain Shift Management's permission before opening any control panel door or instrument cover.

5 It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator.

6. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses.

Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)

Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.

GJPM-SRO-ADM11.00 Page 2 of 257

GRAND GULF Number: GJPM-SRO-ADM-11 NUCLEAR STATION Revision: 00 Page: 3 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials ADMIN Task 11: Determine Shift Staffing to Meet Shift Requirements Setting: Classroom Type: SRO Task: SRO-NO-032 K&A: Generic 2.1.4: 3.4 Safety Function: N/A Time Required: 15 minutes Time Critical: No Faulted: No Performance: Perform Reference(s): Nuclear Management Manual EN-OP-115 Conduct of Operations.

OPG-35 Operator Qualification Verification Handout(s): None

1. Manipulations: N/A

1. Critical Steps: 1 Group #: N/A ADMINISTRATIVE JPM / SRO LEVEL Simulator Setup/Required Plant Conditions: None.

Safety Concerns: None.

Equipment Needed: Computer with Entergy Internet Access GJPM-SRO-ADM11.00 Page 3 of 257

GRAND GULF Number: GJPM-SRO-ADM-11 NUCLEAR STATION Revision: 00 Page: 4 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials ADMIN Task 11: Determine Shift Staffing to Meet Shift Requirements Initial Condition(s):

• The Plant is operating at 100% power.

• An operator has called in sick.

• Your shift is below minimum Fire Brigade staffing.

Initiating Cue(s):

• You are the Control Room Supervisor.

• Determine whether the following operator to be called in meets the requirements to be your replacement Fire Brigade Member USING ON-TRACK ONLINE.

Gary W. Carter

• You already have a Fire Brigade Leader and three other members.

GJPM-SRO-ADM11.00 Page 4 of 257

GRAND GULF Number: GJPM-SRO-ADM-11 NUCLEAR STATION Revision: 00 Page: 5 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials ADMIN Task 11: Determine Shift Staffing to Meet Shift Requirements Notes

1. This is an Administrative JPM.

Task Overview: This task is to determine the staffing qualifications of an oncoming operator for fire brigade status per Nuclear Management Manual EN-OP-115 Conduct of Operations. It is the responsibility of the Control Room Supervisor to ensure he has sufficient qualified personnel for plant operations.

Task Justification: This task is performed at least weekly by Control Room Supervisors.

This is an Administrative JPM.

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

For logging into ON-TRACK ONLINE there are two options either is acceptable.

OPTION 1 Log into the Entergy network.

Standard: Logs onto the Entergy Network from any network computer.

Cue: None.

Notes:

Select the GGNS Home Page.

Standard: Selects the GGNS Home Page.

Cue: None.

Notes:

GJPM-SRO-ADM11.00 Page 5 of 257

GRAND GULF Number: GJPM-SRO-ADM-11 NUCLEAR STATION Revision: 00 Page: 6 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Select DEPARTMENTS.

Standard: Select DEPARTMENTS.

Cue: None.

Notes: Left side of the screen Select TRAINING.

Standard: Selects TRAINING.

Cue: None.

Notes: Left side of the screen OPTION 2 Select START.

Standard: Selects START.

Cue: None.

Notes: Bottom left of the screen Select NUCLEAR CORPORATE APPS.

Standard: Selects NUCLEAR CORPORATE APPS.

Cue: None.

Notes: Drop down menu GJPM-SRO-ADM11.00 Page 6 of 257

GRAND GULF Number: GJPM-SRO-ADM-11 NUCLEAR STATION Revision: 00 Page: 7 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials COMMON Select ON-TRACK ONLINE.

Standard: Selects ON-TRACK ONLINE.

Cue: None.

Notes: Quick link highlighted in blue or listed under Nuclear Corporate Apps Select SUPERVISOR FUNCTIONS.

Standard: Selects SUPVERVISOR FUNCTIONS.

Cue: None.

Notes: top bar.

Login with Network ID and password is SSN Standard: Logsin with Network ID and password is SSN.

Cue: None.

Notes: Candidate may need prompting of this. This is acceptable.

Select FIND STAFF.

Standard: Selects FIND STAFF.

Cue: None.

Notes: folders on left Select BY DEVELOPMENT PLAN.

Standard: Selects BY DEVELOPMENT PLAN.

Cue: None.

Notes: folder under FIND STAFF.

GJPM-SRO-ADM11.00 Page 7 of 257

GRAND GULF Number: GJPM-SRO-ADM-11 NUCLEAR STATION Revision: 00 Page: 8 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Select SELECT DEVELOPMENT PROGRAM AREA.

Standard: Selects SELECT DEVELOPMENT PROGRAM AREA.

Cue: None.

Notes: Tab in main screen.

Select FIRE PROTECTION.

Standard: Selects FIRE PROTECTION.

Cue: None.

Notes: Drop down menu under SELECT DEVELOPMENT PROGRAM AREA.

Select GRAND GULF.

Standard: Selects GRAND GULF.

Cue: None.

Notes: Drop down menu under FIRE PROTECTION.

Select G-FIRE-FB-FIRE BRIGADE.

Standard: Selects G-FIRE-FB-FIRE BRIGADE.

Cue: None.

Notes: Drop down menu under SELECT DEVELOPMENT PROGRAM AREA.

Select CARTER, GARY W.

Standard: Selects CARTER, GARY W.

Cue: None.

Notes: Drop down menu under SELECT DEVELOPMENT PROGRAM AREA.

Select UNIT - Fire Brigade Classroom Training and checks Complete Next Dates.

Standard: Selects UNIT - Fire Brigade Classroom Training and checks Complete Next Dates.

Cue: None.

Notes: dates on the screen should be acceptable.

GJPM-SRO-ADM11.00 Page 8 of 257

GRAND GULF Number: GJPM-SRO-ADM-11 NUCLEAR STATION Revision: 00 Page: 9 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Select UNIT - Respiratory Protection Training and checks Complete Next Dates.

Standard: Selects UNIT - Respiratory Protection Training and checks Complete Next Dates.

Cue: None.

Notes: dates on the screen should be acceptable.

Select UNIT - Fire Brigade Physical and checks Complete Next Dates.

Standard: Selects UNIT - Fire Brigade Physical and checks Complete Next Dates.

Cue: None.

Notes: dates on the screen should be acceptable.

Select UNIT - Quarterly Meetings and checks Complete Next Dates.

Standard: Selects UNIT - Quarterly Meetings and checks Complete Next Dates.

Cue: None.

Notes: dates on the screen should be acceptable.

Select UNIT - Fire Drills and checks Complete Next Dates.

Standard: Selects UNIT - Fire Drills and checks Complete Next Dates.

Cue: None.

Notes: dates on the screen should be acceptable.

Select UNIT - Fire Brigade Practice Session and checks Complete Next Dates.

Standard: Selects UNIT - Fire Brigade Practice Session and checks Complete Next Dates.

Cue: None.

Notes: dates on the screen should be acceptable.

GJPM-SRO-ADM11.00 Page 9 of 257

GRAND GULF Number: GJPM-SRO-ADM-11 NUCLEAR STATION Revision: 00 Page: 10 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials

• Determines Gary W. Carter is Fire Brigade Qualified.

Standard: Determines Gary W. Carter is Fire Brigade Qualified.

Cue: None.

Notes: Based on information found determines the operator meets the requirements for Fire Brigade Task Standard(s):

Determines Gary W. Carter is Fire Brigade Qualified.

Name: __________________________________ Time Start: _______ Time Stop: _______

GJPM-SRO-ADM11.00 Page 10 of 257

GRAND GULF Number: GJPM-SRO-ADM-11 NUCLEAR STATION Revision: 00 Page: 11 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials ADMIN Task 11: Determine Shift Staffing to Meet Shift Requirements Follow-Up Questions & Answers:

Comments:

GJPM-SRO-ADM11.00 Page 11 of 257

GRAND GULF Number: GJPM-SRO-ADM-12 NUCLEAR STATION Revision: 00 Page: 12 of 8 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Determine Shift Staffing to Meet Shift Requirements Give this page to the student Initial Condition(s):

• The Plant is operating at 100% power.

• An operator has called in sick.

• Your shift is below minimum Fire Brigade staffing.

Initiating Cue(s):

• You are the Control Room Supervisor.

• Determine whether the following operator to be called in meets the requirements to be your replacement Fire Brigade Member USING ON-TRACK ONLINE.

Gary W. Carter

• You already have a Fire Brigade Leader and three other members.

GJPM-SRO-ADM12.00 Page 12 of 257

GRAND GULF Number: GJPM-SRO-ADM-12 NUCLEAR STATION Revision: 00 Page: 13 of 8 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials TRAINING PROGRAM:

OPERATIONS TRAINING

• LESSON PLAN TITLE:

DETERMINE THE PLANT EOOS FACTOR APPROXIMATE TIME REQUIRED: 10 Minutes PREREQUISITES: NONE SUPPORTING LESSONS: NONE New Material Minor Revision Major Revision REASON FOR REVISION:

New JPM; Modified from GJPM-SRO-ADM04 REVIEW / APPROVAL (Print Name): Electronic Approval (TEAR # )

Prepared By:

Preparer Date Reviewed By:

Technical Reviewer (e.g., SME, line management) Date Instructional Adequacy Determined By:

ITPL (Rev 0); Qualified Instructor (All other revisions) Date Approved By:

++

Discipline Training Supervisor Date Effective Date:

• Date

++

Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on the Training Development Review Worksheet FLEET/REGIONAL PROGRAM CONCURRENCE:

Fleet ENS ENN Not Applicable ANO PNPS CNPS RBS ECH VY GGNS WF3 IPEC WPO JAF

• Indexing Information GJPM-SRO-ADM12.00 Page 13 of 257

GRAND GULF Number: GJPM-SRO-ADM-12 NUCLEAR STATION Revision: 00 Page: 14 of 8 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Generic Instructions

1. Standard cues for valve operation:

a. MOVs:

1) "Full open" = "red light on, green light off"

2) "Full closed" = "red light off, green light on"

b. Manual valves

1) "Full open" = "you feel resistance in the counter-clockwise direction"

2) "Full closed" = "you feel resistance in the clockwise direction"

2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.

3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.

4. Obtain Shift Management's permission before opening any control panel door or instrument cover.

5 It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator.

6. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses.

Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)

Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.

GJPM-SRO-ADM12.00 Page 14 of 257

GRAND GULF Number: GJPM-SRO-ADM-12 NUCLEAR STATION Revision: 00 Page: 15 of 8 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials ADMIN Task 12: Determine the plant EOOS Factor Setting: Classroom Type: SRO Task: SRO-ADMIN-015 K&A: Generic 2.1.19: 3.0 Safety Function: N/A Time Required: 10 minutes Time Critical: No Faulted: No Performance: Perform Reference(s): EDP-045 GGNS EOOS Risk Monitor Users Guide Handout(s): EDP-045 GGNS EOOS Risk Monitor Users Guide

1. Manipulations: N/A

1. Critical Steps: 1 Group #: N/A ADMINISTRATIVE JPM / SRO LEVEL Simulator Setup/Required Plant Conditions: None.

Safety Concerns: None.

Equipment Needed: Shift Managers Computer in the simulator with the EOOS Program.

GJPM-SRO-ADM12.00 Page 15 of 257

GRAND GULF Number: GJPM-SRO-ADM-12 NUCLEAR STATION Revision: 00 Page: 16 of 8 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials ADMIN Task 12: Determine the plant EOOS Factor Initial Condition(s):

• The Plant is 100% power.

Initiating Cue(s):

• You are the Shift Supervisor.

• Service Transformer 21 is out of service.

• Diesel Driven Fire Pump B is out of service.

• Component Cooling Water Pump B is out of service.

• Determine the EOOS Risk Factor and Plant Safety Index.

Give the candidate a copy of EDP-045 GGNS EOOS Risk Monitor Users Guide USE the Shift Managers Computer in the Simulator for the Training Program.

DO NOT USE A COMPUTER CONNECTED TO THE PLANT.

GJPM-SRO-ADM12.00 Page 16 of 257

GRAND GULF Number: GJPM-SRO-ADM-12 NUCLEAR STATION Revision: 00 Page: 17 of 8 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials ADMIN Task 12: Determine the plant EOOS Factor Notes

1. This is an Administrative JPM.

Task Overview: This task is to use the EOOS Computer to assess the Plant Safety Index and Risk Factor for out of service equipment and plant work.

Task Justification: This task is performed any time equipment is removed from service.

This is an Administrative JPM.

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

Selection of components and calculation are NOT sequence Critical.

Log onto a computer with the EOOS Computer Program.

Standard: Candidate logs onto a computer with the EOOS Computer Program.

Cue: None Notes:

At the Shift Managers Desk the LOGON ID is op and the PASSWORD is left blank.

Select Service Transformer (ST-21) as Out of Service.

Standard: Candidate Select Service Transformer (ST-21) as Out of Service.

Cue: None.

Notes: This can be done by selecting ST-21 as Out of Service or the Take a Component Out/Return to Service button.

GJPM-SRO-ADM12.00 Page 17 of 257

GRAND GULF Number: GJPM-SRO-ADM-12 NUCLEAR STATION Revision: 00 Page: 18 of 8 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Select Component Cooling Water Pump B (CCW B) as Out of Service.

Standard: Candidate Select Component Cooling Water Pump B (CCW B) as Out of Service.

Cue: None.

Notes: This can be done by selecting CCW B as Out of Service or the Take a Component Out/Return to Service button.

Select Diesel Driven Fire Pump B (C3B) as Out of Service.

Standard: Candidate Select Diesel Driven Fire Pump B (C3B) as Out of Service.

Cue: None.

Notes: This can be done by selecting Fire Pump C3 B as Out of Service or the Take a Component Out/Return to Service button.

Select Recalculate Plant Risk Measure button.

Standard: Candidate selects Recalculate Plant Risk Measure button.

Cue: None.

Notes: The EOOS computer will perform the calculations and display the Plant Safety Index and risk color 9.0 YELLOW.

• Plant Safety Index is determined to be 9.0 YELLOW.

Standard: Candidate determines Plant Safety Index is 9.0 YELLOW.

Cue: None.

Notes:

Task Standard(s):

Plant Safety Index is determined to be 9.0 YELLOW.

Name: __________________________________ Time Start: _______ Time Stop: _______

GJPM-SRO-ADM12.00 Page 18 of 257

GRAND GULF Number: GJPM-SRO-ADM-12 NUCLEAR STATION Revision: 00 Page: 19 of 8 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials ADMIN Task 4: Determine the plant EOOS Factor Follow-Up Questions & Answers:

Comments:

GJPM-SRO-ADM12.00 Page 19 of 257

GRAND GULF Number: GJPM-SRO-ADM-13 NUCLEAR STATION Revision: 00 Page: 20 of 8 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Determine the plant EOOS Factor Give this page to the student Initial Condition(s):

• The Plant is 100% power.

Initiating Cue(s):

• You are the Shift Supervisor.

• Service Transformer 21 is out of service.

• Diesel Driven Fire Pump B is out of service.

• Component Cooling Water Pump B is out of service.

• Determine the EOOS Risk Factor and Plant Safety Index.

Give the candidate a copy of EDP-045 GGNS EOOS Risk Monitor Users Guide USE the Shift Managers Computer in the Simulator for the Training Program.

DO NOT USE A COMPUTER CONNECTED TO THE PLANT.

GJPM-SRO-ADM13.00 Page 20 of 257

GRAND GULF Number: GJPM-SRO-ADM-13 NUCLEAR STATION Revision: 00 Page: 21 of 8 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials TRAINING PROGRAM:

OPERATIONS TRAINING

• LESSON PLAN TITLE:

PERFORM OPERATIONS SUPERVISOR REVIEW OF TAGOUT APPROXIMATE TIME REQUIRED: 10 Minutes PREREQUISITES: NONE SUPPORTING LESSONS: NONE New Material Minor Revision Major Revision REASON FOR REVISION:

New JPM; Modified from GJPM-SRO-ADM3 REVIEW / APPROVAL (Print Name): Electronic Approval (TEAR # )

Prepared By:

Preparer Date Reviewed By:

Technical Reviewer (e.g., SME, line management) Date Instructional Adequacy Determined By:

ITPL (Rev 0); Qualified Instructor (All other revisions) Date Approved By:

++

Discipline Training Supervisor Date Effective Date:

• Date

++

Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on the Training Development Review Worksheet FLEET/REGIONAL PROGRAM CONCURRENCE:

Fleet ENS ENN Not Applicable ANO PNPS CNPS RBS ECH VY GGNS WF3 IPEC WPO JAF

• Indexing Information GJPM-SRO-ADM13.00 Page 21 of 257

GRAND GULF Number: GJPM-SRO-ADM-13 NUCLEAR STATION Revision: 00 Page: 22 of 8 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Generic Instructions

1. Standard cues for valve operation:

a. MOVs:

1) "Full open" = "red light on, green light off"

2) "Full closed" = "red light off, green light on"

b. Manual valves

1) "Full open" = "you feel resistance in the counter-clockwise direction"

2) "Full closed" = "you feel resistance in the clockwise direction"

2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.

3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.

4. Obtain Shift Management's permission before opening any control panel door or instrument cover.

5 It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator.

6. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses.

Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)

Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.

GJPM-SRO-ADM13.00 Page 22 of 257

GRAND GULF Number: GJPM-SRO-ADM-13 NUCLEAR STATION Revision: 00 Page: 23 of 8 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials ADMIN Task 13: Perform Operations Supervisor Review of Tagout Setting: Classroom Type: SRO Task: SRO-ADMIN-048 K&A: Generic 2.2.13: 3.8; 2.2.17: 3.5 Safety Function: N/A Time Required: 15 minutes Time Critical: No Faulted: No Performance: Perform Reference(s): NMM EN-OP-102 Protective and Caution Tagging Handout(s): NMM EN-OP-102 Protective and Caution Tagging Candidate copy of Manual Tagout SOI 04-1-01-P11-1 Condensater Storage and Transfer System E-1221 M-1065

1. Manipulations: N/A

1. Critical Steps: 1 Group #: N/A ADMINISTRATIVE JPM / SRO LEVEL Simulator Setup/Required Plant Conditions: None.

Safety Concerns: None.

Equipment Needed: None GJPM-SRO-ADM13.00 Page 23 of 257

GRAND GULF Number: GJPM-SRO-ADM-13 NUCLEAR STATION Revision: 00 Page: 24 of 8 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials ADMIN Task 13: Perform Operations Supervisor Review of Tagout Initial Condition(s):

• The Plant is 100% power.

• Condensate Transfer Pump A (P11-C001A) motor has burned up.

• Condensate Transfer Pump B is in service.

Initiating Cue(s):

• You are the Shift Supervisor.

• A Work Order has been issued to replace the Pump Motor for P11-C001A.

• There will be NO breach of the fluid system portion of the pump.

• The eSOMS Clearance System computer is out of service and the pump must repaired and returned to service ASAP.

• Review the attached Protective clearance as Operations Supervisor for adequacy to hang.

GJPM-SRO-ADM13.00 Page 24 of 257

GRAND GULF Number: GJPM-SRO-ADM-13 NUCLEAR STATION Revision: 00 Page: 25 of 8 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials ADMIN Task 13: Perform Operations Supervisor Review of Tagout Notes

1. This is an Administrative JPM.

Task Overview: This task is to perform the Operations Supervisor review of a tagout for protective tagging.

Task Justification: This task is performed any time equipment is removed from service.

Operations SROs are responsible for releasing ALL plant equipment for maintenance and protective tagging.

This is an Administrative JPM.

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

Selection of components and calculation are NOT sequence Critical.

• Identifies the tagout is missing the P11-C001A Space Heater Breaker 52-1P42214 from the tagout.

Standard: Reviews the tagout and determines the P11-C001A Space Heater Breaker 52-1P42214 is not on the tagout and should be to allow motor work.

Cue: None Notes:

GJPM-SRO-ADM13.00 Page 25 of 257

GRAND GULF Number: GJPM-SRO-ADM-13 NUCLEAR STATION Revision: 00 Page: 26 of 8 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials The following components are present on the tagout as required for P11-C001A Motor Replacement:

______ P11-HS-M604A Handswitch for CNDS XFER PMP A P11-C001A H13-P870-5C STOP

______ P11-F024A CNDS XFER PMP A DISCH valve (Optional) CLOSED

______ P11-F026A CNDS XFER PMP A SUCT valve (Optional) CLOSED

______ 52-142223 CNDS XFER PMP A circuit breaker OPEN

______ P11-F050A CNDS XFER PMP A CSG VENT valve OPEN

______ P11-F139A CNDS XFER PMP A CSG DR valve OPEN Standard: The above components are on the tagout and are acceptable. The Suction and Discharge Valves are there only to keep the pump shaft from potentially turning. The vent and drain valve are to prevent water inside the pump from expanding causing damage to the pump.

Cue: None.

Notes:

GJPM-SRO-ADM13.00 Page 26 of 257

GRAND GULF Number: GJPM-SRO-ADM-13 NUCLEAR STATION Revision: 00 Page: 27 of 8 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Task Standard(s):

Taggout is determined to be inadequate for the work to be done due to P11-C001A Condensate Transfer Pump A Space heater circuit breaker not being opened and tagged.

Name: __________________________________ Time Start: _______ Time Stop: _______

GJPM-SRO-ADM13.00 Page 27 of 257

GRAND GULF Number: GJPM-SRO-ADM-13 NUCLEAR STATION Revision: 00 Page: 28 of 8 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials ADMIN Task 13: Perform Operations Supervisor Review of Tagout Follow-Up Questions & Answers:

Comments:

GJPM-SRO-ADM13.00 Page 28 of 257

GRAND GULF Number: GJPM-SRO-ADM-14 NUCLEAR STATION Revision: 00 Page: 29 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Perform Operations Supervisor Review of Tagout Give this page to the student Initial Condition(s):

• The Plant is 100% power.

• Condensate Transfer Pump A (P11-C001A) motor has burned up.

• Condensate Transfer Pump B is in service.

Initiating Cue(s):

• You are the Shift Supervisor.

• A Work Order has been issued to replace the Pump Motor for P11-C001A.

• There will be NO breach of the fluid system portion of the pump.

• The eSOMS Clearance System computer is out of service and the pump must repaired and returned to service ASAP.

• Review the attached Protective clearance as Operations Supervisor for adequacy to hang.

GJPM-SRO-ADM14.00 Page 29 of 257

GRAND GULF Number: GJPM-SRO-ADM-14 NUCLEAR STATION Revision: 00 Page: 30 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials TRAINING PROGRAM:

OPERATIONS TRAINING

• LESSON PLAN TITLE:

Review Radioactive Waste Discharge Permit APPROXIMATE TIME REQUIRED: 10 Minutes PREREQUISITES: NONE SUPPORTING LESSONS: NONE New Material Minor Revision Major Revision REASON FOR REVISION:

New JPM; Modified from GG-1-JPM-SRO-ADM37 REVIEW / APPROVAL (Print Name): Electronic Approval (TEAR # )

Prepared By:

Preparer Date Reviewed By:

Technical Reviewer (e.g., SME, line management) Date Instructional Adequacy Determined By:

ITPL (Rev 0); Qualified Instructor (All other revisions) Date Approved By:

++

Discipline Training Supervisor Date Effective Date:

• Date

++

Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on the Training Development Review Worksheet FLEET/REGIONAL PROGRAM CONCURRENCE:

Fleet ENS ENN Not Applicable ANO PNPS CNPS RBS ECH VY GGNS WF3 IPEC WPO JAF

• Indexing Information GJPM-SRO-ADM14.00 Page 30 of 257

GRAND GULF Number: GJPM-SRO-ADM-14 NUCLEAR STATION Revision: 00 Page: 31 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Generic Instructions

1. Standard cues for valve operation:

a. MOVs:

1) "Full open" = "red light on, green light off"

2) "Full closed" = "red light off, green light on"

b. Manual valves

1) "Full open" = "you feel resistance in the counter-clockwise direction"

2) "Full closed" = "you feel resistance in the clockwise direction"

2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.

3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.

4. Obtain Shift Management's permission before opening any control panel door or instrument cover.

5 It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator.

6. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses.

Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)

Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.

GJPM-SRO-ADM14.00 Page 31 of 257

GRAND GULF Number: GJPM-SRO-ADM-14 NUCLEAR STATION Revision: 00 Page: 32 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials ADMIN Task 14: Review Radioactive Waste Discharge Permit Setting: Classroom Type: SRO Task: SRO-NO-010 K&A: Generic 2.3.11: 3.2 Safety Function: N/A Time Required: 10 minutes Time Critical: No Faulted: No Performance: Perform Reference(s): Administrative Procedure 01-S-08-11 Radioactive Discharge Controls Handout(s): Administrative Procedure 01-S-08-11 Radioactive Discharge Controls Candidate Copy of Attachment I Batch Liquid Radwaste Discharge Permit

1. Manipulations: N/A

1. Critical Steps: 4 Group #: N/A ADMINISTRATIVE JPM / SRO LEVEL Simulator Setup/Required Plant Conditions: None.

Safety Concerns: None.

Equipment Needed: None.

Initial Condition(s):

• The Radwaste Specialist / Operator has brought a Batch Liquid Radwaste Discharge Permit to the Control Room for approval.

Initiating Cue(s):

• You are the Shift Manager.

• Review the Batch Liquid Radwaste Discharge Permit..

There are 5 critical deficiencies on the Discharge Permit. Typos and spelling errors do NOT count.

GJPM-SRO-ADM14.00 Page 32 of 257

GRAND GULF Number: GJPM-SRO-ADM-14 NUCLEAR STATION Revision: 00 Page: 33 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials ADMIN Task 14: Review Radioactive Waste Discharge Permit Notes

1. This is an Administrative JPM.

Task Overview: This task is to review a Radioactive Waster Discharge permit per Administrative Procedure 01-S-08-11. This is the responsibility of the Shift Manager to review and approve all radioactive discharges from GGNS.

Task Justification: This task is performed any time Radwaster discharges a tank of liquid to the environment. This is an Administrative JPM.

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

• Review the Batch Liquid Radwaste Discharge Permit for readiness for use.

Standard: SEE Attached Evaluator Copy of permit for marked critical errors on the permit.

Errors are circled and marked with *.

The candidate must find 4 or 5 errors for satisfactory completion of JPM.

Cue: None.

Notes:

Task Standard(s):

Four of five Errors are noted from Batch Liquid Radwaste Discharge Permit.

Name: __________________________________ Time Start: _______ Time Stop: _______

GJPM-SRO-ADM14.00 Page 33 of 257

GRAND GULF Number: GJPM-SRO-ADM-14 NUCLEAR STATION Revision: 00 Page: 34 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials ADMIN Task 14: Review Radioactive Waste Discharge Permit Follow-Up Questions & Answers:

Comments:

GJPM-SRO-ADM14.00 Page 34 of 257

GRAND GULF Number: GJPM-SRO-A&E-43 NUCLEAR STATION Revision: 00 Page: 35 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Review Radioactive Waste Discharge Permit Give this page to the student Initial Condition(s):

• The Radwaste Specialist / Operator has brought a Batch Liquid Radwaste Discharge Permit to the Control Room for approval.

Initiating Cue(s):

• You are the Shift Manager.

• Review the Batch Liquid Radwaste Discharge Permit..

There are 5 critical deficiencies on the Discharge Permit. Typos and spelling errors do NOT count.

GJPM-SRO-A&E-43.00 Page 35 of 257

GRAND GULF Number: GJPM-SRO-A&E-43 NUCLEAR STATION Revision: 00 Page: 36 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials TRAINING PROGRAM:

OPERATIONS TRAINING

• LESSON PLAN TITLE:

DETERMINE ENTRY INTO SITE EMERGENCY PLAN AND COMPLETE INITIAL NOTIFICATION FORMS APPROXIMATE TIME REQUIRED: 15 Minutes PREREQUISITES: NONE SUPPORTING LESSONS: NONE New Material Minor Revision Major Revision REASON FOR REVISION:

New JPM; Modified JPM REVIEW / APPROVAL (Print Name): Electronic Approval (TEAR # )

Prepared By:

Preparer Date Reviewed By:

Technical Reviewer (e.g., SME, line management) Date Instructional Adequacy Determined By:

ITPL (Rev 0); Qualified Instructor (All other revisions) Date Approved By:

++

Discipline Training Supervisor Date Effective Date:

• Date

++

Indicates that the LP has been reviewed by the Training Supervisor for inclusion of Management Expectations and items referenced on the Training Development Review Worksheet FLEET/REGIONAL PROGRAM CONCURRENCE:

Fleet ENS ENN Not Applicable ANO PNPS CNPS RBS ECH VY GGNS WF3 IPEC WPO JAF

• Indexing Information GJPM-SRO-A&E-43.00 Page 36 of 257

GRAND GULF Number: GJPM-SRO-A&E-43 NUCLEAR STATION Revision: 00 Page: 37 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials Generic Instructions

1. Standard cues for valve operation:

a. MOVs:

1) "Full open" = "red light on, green light off"

2) "Full closed" = "red light off, green light on"

b. Manual valves

1) "Full open" = "you feel resistance in the counter-clockwise direction"

2) "Full closed" = "you feel resistance in the clockwise direction"

2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.

3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.

4. Obtain Shift Management's permission before opening any control panel door or instrument cover.

5 It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator.

6. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses.

Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)

Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.

GJPM-SRO-A&E-43.00 Page 37 of 257

GRAND GULF Number: GJPM-SRO-A&E-43 NUCLEAR STATION Revision: 00 Page: 38 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials A&E Task 43 Determine Entry into Site Emergency Plan and Complete Initial Notification Forms as applicable Setting: Classroom Type: SRO Task: SRO-A&E-015; SRO-A&E-003 K&A: Generic 2.4.41: 4.1; 2.4.38: 4.0; 2.4.40: 4.0 Safety Function: N/A Time Required: 15 minutes Time Critical: YES Faulted: No Performance: Perform Reference(s): 10-S-01-1 Handout(s): 10-S-01-1; EAL Flow Chart

1. Manipulations: N/A

1. Critical Steps: 2 Group #: N/A ADMINISTRATIVE JPM Simulator Setup/Required Plant Conditions: None.

Safety Concerns: None.

Equipment Needed: None.

GJPM-SRO-A&E-43.00 Page 38 of 257

GRAND GULF Number: GJPM-SRO-A&E-43 NUCLEAR STATION Revision: 00 Page: 39 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials A&E Task 43 Determine Entry into Site Emergency Plan and Complete Initial Notification Forms as applicable Initial Condition(s):

• The Plant is 100% power.

Initiating Cue(s):

• You are the Shift Manager.

• A Dry Fuel Storage Cask is being moved from Unit I to the ISFSI Storage Facility.

• The ISFSI Crawler (Transporter) engine caught on fire at 1010 just as the crawler was going around the Combination Shop on the south side of the building.

• The Site Fire Brigade has responded with the Site Fire Truck and has reported the fire is extinguished at 1035 and a reflash watch has been established.

• There is visible damage to the outside of the Dry Fuel Storage Cask.

• The Radiation Protection Technician monitoring the Fire Brigade and Dry Fuel Storage Cask has stated the Radiation Levels adjacent to the cask are two times pre-fire levels.

• Classify this event and complete any initial notification forms that are required.

GJPM-SRO-A&E-43.00 Page 39 of 257

GRAND GULF Number: GJPM-SRO-A&E-43 NUCLEAR STATION Revision: 00 Page: 40 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials A&E Task 43 Determine Entry into Site Emergency Plan and Complete Initial Notification Forms as applicable Notes

1. This is an Administrative JPM.

2. This is an activity performed by an SRO as Emergency Director per the GGNS Emergency Plan Procedures.

Task Overview: This task is to use the Emergency Plan Procedure and Off Normal Event Procedures for classification of plant conditions per the Emergency Action Levels and complete the Initial Notification forms for contact of State and Local Agencies. This is a TIME CRITICAL JPM based on the requirements of 10 CFR50 Appendix E IV.D.3.

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

This is a TIME CRITICAL JPM.

Identify the CONFINEMENT BOUNDARY of a loaded cask has been damaged.

Standard: Candidate uses 10-S-01-1 Section 5.7 to identify the Confinement Boundary has been damaged due to radiation levels being TWO times the pre-event levels in the area of the cask.

Cue: None Notes: This E-HU1 Unusual Event.

Identify the fire location was within the boundaries of the PROTECTED AREA and lasted for greater than 15 minutes (25 minutes), however, the fire was NOT contiguous to any VITAL AREAS as identified in Table H3 Standard: Candidate uses 10-S-01-1 section 5.42 to identify the Protected Area and determine the fire lasted greater than 15 minutes (25 minutes) but was not contiguous to VITAL AREAS as defined in Table H3, also the fire did not affect structures containing functions or systems required for Safe Shutdown.

Cue: None Notes:

GJPM-SRO-A&E-43.00 Page 40 of 257

GRAND GULF Number: GJPM-SRO-A&E-43 NUCLEAR STATION Revision: 00 Page: 41 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials

• Classify the event as an UNUSUAL EVENT.

Standard: Candidate uses 10-S-01-1 Attachments I and II Initiating Conditions E-HU1 to classify the event as an UNUSUAL EVENT.

Cue: None Notes:

• Complete the Initial Notification form for contact of State and Local Agencies. (SEE Attached form for critical information.)

Standard: Candidate completes Initial Notification form.

Cue: None Notes:

Task Standard(s):

UNUSUAL EVENT is declared per EAL E-HU1 and Initial Notification Form is completed.

Name: __________________________________ Time Start: _______ Time Stop: _______

GJPM-SRO-A&E-43.00 Page 41 of 257

GRAND GULF Number: GJPM-SRO-A&E-43 NUCLEAR STATION Revision: 00 Page: 42 of 257 Rtype:

JOB PERFORMANCE QA Record MEASURE Number of pages Date Initials A&E Task 43 Determine Entry into Site Emergency Plan and Complete Initial Notification Forms as applicable Follow-Up Questions & Answers:

Comments:

GJPM-SRO-A&E-43.00 Page 42 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C11011 Revision: 0 Page: 43 of 257 JOB PERFORMANCE MEASURE Determine Entry into Site Emergency Plan and Complete Initial Notification Forms as applicable Give this page to the student Initial Condition(s):

• The Plant is 100% power.

Initiating Cue(s):

• You are the Shift Manager.

• A Dry Fuel Storage Cask is being moved from Unit I to the ISFSI Storage Facility.

• The ISFSI Crawler (Transporter) engine caught on fire at 1010 just as the crawler was going around the Combination Shop on the south side of the building.

• The Site Fire Brigade has responded with the Site Fire Truck and has reported the fire is extinguished at 1035 and a reflash watch has been established.

• There is visible damage to the outside of the Dry Fuel Storage Cask.

• The Radiation Protection Technician monitoring the Fire Brigade and Dry Fuel Storage Cask has stated the Radiation Levels adjacent to the cask are two times pre-fire levels.

• Classify this event and complete any initial notification forms that are required.

ENTERGY NUCLEAR Number: GJPM-OPS-C11011 Revision: 0 Page: 44 of 257 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

OPERATOR TRAINING TITLE:

Rotating CRD FCV's New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: Clarification for NRC Exam THIS DOCUMENT REPLACES: GJPM-OPS-C11011.00 REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )

Prepared By:

• • Preparer Date Ops Review++: R. T. Errington 7/30/06 Technical Reviewer (e.g., SME, line management) Date Validated By: Mike Harrower Training Representative Date Approved By:

+

Discipline Training Supervisor Date Approval Date:*

• Indexing Information

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

+

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

++

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

FLEET/REGIONAL PROGRAM CONCURRENCE:

Fleet ENS ENN Not Applicable DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS (DATE/INITIAL) BY RM

ENTERGY NUCLEAR Number: GJPM-OPS-C11011 Revision: 0 Page: 45 of 257 JOB PERFORMANCE MEASURE TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)

ENTERGY NUCLEAR Number: GJPM-OPS-C11011 Revision: 01 Page: 46 of 257 JOB PERFORMANCE MEASURE Generic Instructions

1. Standards and cues for valve operation:

a. MOVs:

1) "Turn the valve's handswitch on (panel #)(section#, as applicable) in the (clockwise or counter-clockwise) direction and observe that the valve's red light is (energized or de-energized) and its green light is (energized or de-energized)".

b. Manual valves

1) "Turn the valve's handwheel (or other manual operating device) in the (clockwise or counter-clockwise) direction until resistance is felt."

2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.

3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.

4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator.

5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)

6. Obtain Shift Management's permission before opening any control panel or compartment. Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).

7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).

8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.

Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.

Page 46 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C11011 Revision: 01 Page: 47 of 257 JOB PERFORMANCE MEASURE C1101 Task 1: Rotate CRD FCVs Setting: Plant (Inside CAA)

Type: NLO Task: NOB-C11-007 K&A: 201001: A4.03 - 2.9/2.8 Safety Function: Reactivity Control Time Required: 28 minutes Time Critical: No Faulted: No Performance: Simulated Reference(s): 04-1-01-C11-1, Section 5.4 Handout(s): Sections 1.0, 2.0, 3.0 and 5.4 of SOI 04-1-01-C11-1

1. Manipulations: 6

1. Critical Steps: 6 Group : 2 Required Plant Conditions:

• CRD FCV Station is accessible.

• ALARA notified in advance of performing this JPM for dose accounting Safety Concerns:

• Wear standard safety gear

• Follow FME rules for Containment

• Follow RPs directions for contamination control Initial Condition(s):

• CRD Flow Control Valve A is in service.

Initiating Cue(s):

• Rotate from CRD Flow Control Valve A to CRD Flow Control Valve B.

• Communications are setup at the CRD Flow Control Station.

Page 47 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C11011 Revision: 01 Page: 48 of 257 JOB PERFORMANCE MEASURE C1101 Task 1: Rotate CRD FCVs Notes:

1. This task will be performed at the CRD flow control valve station on the 135 elevation of Containment.

FCV CONTROL LOGIC The local controller's operating mode is selected by a shuttle valve positioned by an AUTO/MAN knob on the top front of the local controller.

1. In the AUTO mode, the shuttle valve connects the FCV's pneumatic positioner to control air coming from the I/P section of the local controller. Input from the remote controller on P601 operates a servo valve in the I/P section to port air to and from the pneumatic postioner and openand close the valve. Remote controller input, in percent, is indicated by the black needle on the left side of the local controller's output meter. It's value is equal to the value indicated by the horizontal meter on the remote controller

2. In the MANUAL mode, the shuttle valve connects the FCV's pneumatic positioner to control air coming from a control valve in back of and outside the local controller. The control valve is positioned by an OUTPUT ADJUST knob on the bottom front of the local controller. The control valve is similar to the I/P in the AUTO mode in that it ports air to and from the FCV's pneumatic postioner to open and close the FCV. Manual output, in percent, is indicated by the red needle on the right side of the local controller's output meter. It's value is determined solely by the position of the manual control valve on that local controller.

Manual output can be raised and lowered regardless of the local controller's operating mode.

Control Room Containment C11-R600 C11-D009A(B)

AUTO MAN M A OUTPUT ADJUST Page 48 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C11011 Revision: 01 Page: 49 of 257 JOB PERFORMANCE MEASURE Page 49 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C11011 Revision: 01 Page: 50 of 257 JOB PERFORMANCE MEASURE C1101 Task 1: Rotate CRD FCVs Tasks : Critical tasks are underlined, italicized, and denoted by an (*)

Note : The sequence for the following steps is critical Establish communications with the Control Room.

Standard: Selects a method of communications (sound-powered headset or pager) and briefly demonstrates how communications would be set up Cue: Evaluator acts as the Control Room operator for communications purposes Notes: Candidate was informed of communications in Initiating Cue.

• Open manual isolation valve F047A(B) for the FCV to be placed in service Standard: Turns the handwheel for valve C11-F047A(B) counter-clockwise until resistance is felt Cue: You feel resistance in the counter clockwise direction Notes:

• Place the local controller for the on-coming FCV in MANUAL.

Standard: Turns the mode switch on the top front of controller C11-FK-D009A(B) to the MAN position Cue: Controller is in manual Notes:

Page 50 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C11011 Revision: 01 Page: 51 of 257 JOB PERFORMANCE MEASURE

• Slowly Open the FCV(F002A/B) being placed in service Standard:

1) Turns the OUTPUT ADJ knob on controller C11-FK-D009A(B) for the on-coming FCV clockwise

2) Watches the on-coming FCV (F002A(B)) open while the off-going FCV (F002B(A)) automatically closes Cue: On-coming valve is going open; off-going valve is going closed Notes:

• Lower the controller D009B(A) OUTPUT for the FCV to be taken out of service to ZERO and transfer the controller to MANUAL Standard:

1) Once the off-going FCV (F002B(A)) is closed, lower its local controllers (D009B(A)) output to zero by turning its MANUAL ADJ knob counter-clockwise until the output (red pointer) indicates zero output

2) Transfer the off-going FCVs local controller (D009B(A)) to MANUAL by turning its mode switch on the top front of the controller to the MAN position Cue:

Off-going FCV is closed Off-going valve controller is in MANUAL at ZERO Notes:

• Close the off-going FCVs manual isolation valve C11-F047B(A)

Standard: Closes off-going FCVs manual isolation valve by turning C11-F047B(A) clockwise until resistance is felt Cue: You feel resistance in the clockwise direction Notes:

Page 51 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C11011 Revision: 01 Page: 52 of 257 JOB PERFORMANCE MEASURE Coordinate with the Control Room to match remote and local output signals.

Standard: Control Room places remote FCV controller C11-FK-R600 in MANUAL and reduces its output (black pointer on local controller) until it matches the output of the on-coming FCVs local controller (red pointer)

Cue: Remote controller is in manual; red and black needles on local controller line up Notes:

• Place the local controller D009A(B) for the on-coming FCV in AUTO.

Standard: Turns the mode switch on the top front of controller C11-FK-D009A(B) for the on-coming FCV counter-clockwise to the AUTO position Cue:

Local controller is in AUTO The CRO has nulled the deviation on C11-FK-R600 on H13-P601 and placed it in AUTO System flow is 60 gpm as indicated on P601 Notes:

Task Standard(s):

The standby FCV is in automatic service and CRD drive flow is between 54 and 66 gpm.

Name: ___________________________ Time Start: _______ Time Stop: _______

Page 52 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C11011 Revision: 01 Page: 53 of 257 JOB PERFORMANCE MEASURE C1101 Task 1: Rotate CRD FCVs Follow-Up Questions & Answers:

Comments:

Page 53 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C7101 Revision: 01 Page: 54 of 257 JOB PERFORMANCE MEASURE Rotate CRD FCVs Give this page to the student Initial Condition(s):

• CRD Flow Control Valve A is in service.

Initiating Cue(s):

• Rotate from CRD Flow Control Valve A to CRD Flow Control Valve B.

Page 54 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C7101 Revision: 01 Page: 55 of 257 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

OPERATOR TRAINING TITLE:

RPS Motor Generator Startup New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: Clarification for NRC Exam.

THIS DOCUMENT REPLACES: GJPM-OPS-C7100, REV. 0 REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )

Prepared By:

• • Preparer Date Ops Review++: R. T. Errington 7/27/06 Technical Reviewer (e.g., SME, line management) Date Validated By: Steve Reeves 7-13-06 Training Representative Date Approved By: M. L. Chase 8/7/06

+

Discipline Training Supervisor Date Approval Date:*

• Indexing Information

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

+

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

++

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

FLEET/REGIONAL PROGRAM CONCURRENCE:

Fleet ENS ENN Not Applicable DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS (DATE/INITIAL) BY RM TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)

Page 55 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C7101 Revision: 01 Page: 56 of 257 JOB PERFORMANCE MEASURE Page 56 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C7101 Revision: 01 Page: 57 of 257 JOB PERFORMANCE MEASURE Generic Instructions

1. Standards and cues for valve operation:

a. MOVs:

1) "Turn the valve's handswitch on (panel #)(section#, as applicable) in the (clockwise or counter-clockwise) direction and observe that the valve's red light is (energized or de-energized) and its green light is (energized or de-energized)".

b. Manual valves

1) "Turn the valve's handwheel (or other manual operating device) in the (clockwise or counter-clockwise) direction until resistance is felt."

2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.

3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.

4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator.

5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)

6. Obtain Shift Management's permission before opening any control panel or compartment. Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).

7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).

8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.

Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.

Page 57 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C7101 Revision: 0 Page: 58 of 257 JOB PERFORMANCE MEASURE C71 Task 1: RPS Motor/Generator Startup Setting: Plant (Outside CAA)

Type: NLO Task: NOB-C71-002; NOB-C71-003; NOB-C71-005; CRO-C71-004 K&A: 212000 A2.01: 3.7/3.9; A1.01: 2.8/2.9; A1.03: 2.4/2.5; G2.1.30: 3.9/3.4 Safety Function: Instrumentation (7)

Time Required: 18 minutes Time Critical: No Faulted: No Performance: Simulate Reference(s): 04-1-01-C71-1 Handout(s): 04-1-01-C71-1

1. Manipulations: 4

1. Critical Steps: 4 Group #: 1 Simulator Setup/Required Plant Conditions:

• Area is accessible Safety Concerns:

• Do NOT operate plant equipment.

• Extreme caution should be taken around the RPS Motor Generator Set to prevent accidental contact with the controls.

• Use care when working around or near rotating equipment.

• Adjust which RPS Room to go to based on plant Protected Train.

Initial Condition(s):

• The plant is operating at 100% power.

• Repairs have been completed on RPS A(B) Motor/Generator.

• 04-1-01-N32-1 Manual Valve Lineup Checksheet has been completed for C71-PT-N005A - D and C71-PT-N006A - H

• 04-1-01-C71-1 Handswitch Lineup Checksheet, Attachment V, has been completed, as required.

• 04-1-01-C71-1 Electrical Lineup Checksheet, Attachment III, has been completed, as required.

• RPS A(B) Bus is being supplied by the Alternate Feed.

Initiating Cue(s):

• You have been directed to perform section 4.1 of the SOI to startup the RPS A(B)

Motor/Generator.

Page 58 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C7101 Revision: 0 Page: 59 of 257 JOB PERFORMANCE MEASURE C71 Task 1: RPS Motor/Generator Startup Notes:

1. JPM may be performed on either RPS A or B Motor/Generator, depending on plant conditions.

2. Att. 1, on page 10, is a drawing of a typical EPA.

Task Overview:

This task is to perform a startup of the RPS Motor Generator and align the RPS Bus to the Normal Supply per the SOI. This task is performed to return RPS power to the Normal Supply.

Task Justification The following JPM does not meet the minimum requirements of 14-S-02-18. It either does not have the required number of manipulations or critical steps. However it has been deemed a valid JPM in accordance with 14-S-02-18 step 6.3.13 due to the following:

The task has high importance, significant consequences if improperly performed and/or complexity in controlling important plant parameters such as reactivity or reactor water level during transient conditions.

AND This is a trip critical evolution performed by the non-licensed operators.

Due to a possible loss of offsite power the operator would be required to engerize the RPS system to restore to ability to insert control rods. This task requires the operator to restart the RPS electrical system.

Page 59 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C7101 Revision: 0 Page: 60 of 257 JOB PERFORMANCE MEASURE C71 Task 1: RPS Motor/Generator Startup Tasks : Critical tasks are underlined, italicized, and denoted by an (*)

Note : The sequence for the following steps is not critical.

Check open GENERATOR OUTPUT circuit breaker on panel 1C71-S001A(B) on MG set Standard: Verifies that the circuit breaker's operating handle is in the "down" position, indicating an open breaker Cue: Circuit breaker handle is down.

Notes:

Check open RPS MG A(B) Output Breakers 1C71-S003A(B) and 1C71-S003C(D)

Standard: Verifies that the EPAs' operating handles are in the "OFF/RESET OPEN" position Cue: Circuit breakers are in the OFF position.

Notes:

Check test switches on RPS MG A(B) output breakers are in the NORM position Standard: Verifies that the "Undervoltage", "Overvoltage" and "Underfrequency" test switches on RPS MG A(B) Output Breakers 1C71-S003A(B) and 1C71-S003C(D) are in the NORM position Cue: All switches in NORM Notes:

Note : The sequence for the following steps is critical.

• Starts RPS MG A(B)

Standard: Simulates depressing the "MOTOR ON" pushbutton on panel 1C71- S001A(B) until redlight is lit Cue: Red ON light is lit Notes:

Page 60 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C7101 Revision: 0 Page: 61 of 257 JOB PERFORMANCE MEASURE Check generator output voltage Standard: Observes voltmeter on motor generator control panel 1C71-S001A(B) is indicating between 122 and 128 VAC Cue: As indicated (if MG is running. 124V if not running))

Notes:

• Close GENERATOR OUTPUT circuit breaker Standard: Simulates pulling up on the circuit breaker's operating handle on panel 1C71-S001A(B) to close the breaker Cue: Circuit breaker handle is up.

Notes:

Check 1C71-S003A(B) indicating power coming in and power available to go out Standard Check the ELECT PROT ASSY INPUT and the POWER SUPPLY OUTPUT red lights are lit at the 1C71-S003A(B) ELECTRICAL PROTECTION ASSEMBLY panel Cue: Red lights are lit Notes:

Verify the EPA's trip targets are reset Standard: Verifies the absence of orange "trip target" lights on the following 1C71-S003A(B) relays:

-- UNDER VOLTAGE

-- OVER VOLTAGE

-- UNDER FREQUENCY Cue: No orange lights noticed Notes:

Page 61 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C7101 Revision: 0 Page: 62 of 257 JOB PERFORMANCE MEASURE

• Close breaker 1C71-S003A(B)

Standard: Simulates closing breaker 1C71-S003A(B) by rotating its operating handle counter-clockwise until it snaps into the "ON" position Cue: Circuit Breaker handle is in the ON position.

Notes:

Check that power is going out of EPA 1C71-S003A(B)

Standard: Checks that the red ELECT PROT ASSY OUTPUT light on 1C71-S003A(B) is lit Cue: Red light is lit Notes:

Check 1C71-S003C(D) indicating power coming in and power available to go out Standard Check the ELECT PROT ASSY INPUT and the POWER SUPPLY OUTPUT red lights are lit at the 1C71-S003C(D) ELECTRICAL PROTECTION ASSEMBLY panel Cue: Red lights are lit Notes:

Verify the EPA's trip targets are reset Standard: Verifies the absence of orange "trip target" lights on the following 1C71-S003C(D) relays:

-- UNDER VOLTAGE

-- OVER VOLTAGE

-- UNDER FREQUENCY Cue: No orange lights noticed Notes:

Page 62 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C7101 Revision: 0 Page: 63 of 257 JOB PERFORMANCE MEASURE

• Close breaker 1C71-S003C(D)

Standard: Simulates closing breaker 1C71-S003C(D) by rotating its operating handle counter-clockwise until it snaps into the "ON" position Cue: Circuit Breaker handle is in the ON position.

Notes:

Check that power is going out of EPA 1C71-S003C(D)

Standard: Checks that the red ELECT PROT ASSY OUTPUT light on 1C71-S003C(D) is lit Cue: Red light is lit Notes:

Check GENERATOR A(B) NORMAL FEED AVAILABLE white light are lit on 1H13-P610 Standard: N/A Cue: RO reports that the white light is lit, and he/she will pick up the task from here Notes:

Task Standard(s):

RPS A(B) Motor/Generator is running at rated speed and voltage.

Name: _______________________________ Time Start: _____ Time Stop: _______

Page 63 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C7101 Revision: 0 Page: 64 of 257 JOB PERFORMANCE MEASURE C71 Task 1: RPS Motor/Generator Startup Follow-Up Questions & Answers:

Comments:

Page 64 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-P6404 Revision: 00 Page: 65 of 257 JOB PERFORMANCE MEASURE ELECT PROT ASSY ELECT PROT ASSY POWER SUPPLY INPUT OUTPUT OUTPUT IP OFF TR R ET ON ES EN P

O UNDERVOLTAGE RELAY UNDERVOLTAGE TEST SW 27D SW1D NORM CAL/TEST UV DC TRIP TEST (P/B)

TARGET RESET (P/B)

PICKUP VOLTAGE TIME DIAL  % DROPOUT UNDERVOLTAGE UNDERVOLTAGE TEST INPUT TEST OUTPUT Target turns orange when device is tripped OVERVOLTAGE RELAY OVERVOLTAGE TEST SW 59D SW2D NORM CAL/TEST OV DC TRIP TEST (P/B)

TARGET RESET (P/B)

PICKUP VOLTAGE TIME DIAL  % DROPOUT OVERVOLTAGE OVERVOLTAGE TEST INPUT TEST OUTPUT Target turns orange when device is tripped UNDERFREQUENCY RELAY UNDERFREQUENCY TEST SW 81D SW3D NORM CAL/TEST UF DC TARGET RESET (P/B)

UNDERFREQUENCY UNDERFREQUENCY 15 9 3 13 0 1 TEST INPUT TEST OUTPUT Target turns orange when device is tripped Startup conditions: Startup/reset procedure:

MG is de-energized Startup the MG Push and rotate the breaker H/S Setpoints EPA INPUT and EPA OUTPUT The EPA INPUT and to the RESET-OPEN position lights are off POWER SUPPLY OUTPUT then toON to close the breaker. Parameter S003A/C S003B/D POWER SUPPLY OUTPUT lights should energize The EPA OUTPUT light on Undervoltage < 116.5 V < 117.4 V light is off Depress the TARGET RESET this EPA, and the EPA Overvoltage > 131.3 V > 131.4 V Breaker in the TRIP position pushbuttons on all protective INPUT and POWER Underfrequency < 57.6 Hz < 57.6 Hz relays with activated trip targets. SUPPLY OUTPUT lights on the downstream EPA, All trips have a 3.5 second time delay.

should energize.

Repeat for the next EPA Page 65 of 257 Att. 1 Electric Protective Assembly

ENTERGY NUCLEAR Number: GJPM-OPS-P6404 Revision: 00 Page: 66 of 257 JOB PERFORMANCE MEASURE RPS Motor/Generator Startup Give this page to the student Initial Condition(s):

• The plant is operating at 100% power.

• Repairs have been completed on RPS A(B) Motor/Generator.

• 04-1-01-N32-1 Manual Valve Lineup Checksheet has been completed for C71-PT-N005A - D and C71-PT-N006A - H

• 04-1-01-C71-1 Handswitch Lineup Checksheet, Attachment V, has been completed, as required.

• 04-1-01-C71-1 Electrical Lineup Checksheet, Attachment III, has been completed, as required.

• RPS A(B) Bus is being supplied by the Alternate Feed.

Initiating Cue(s):

• You have been directed to perform section 4.1 of the SOI to startup the RPS A(B)

Motor/Generator.

• This task is not time critical.

Page 66 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-P6404 Revision: 00 Page: 67 of 257 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

OPERATOR TRAINING TITLE:

Perform Control Room Actions in Response to Fire in Plant New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: NEW JPM THIS DOCUMENT REPLACES: N/A REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )

Prepared By:

• • Preparer Date Ops Review++:

Technical Reviewer (e.g., SME, line management) Date Validated By:

Training Representative Date Approved By:

+

Discipline Training Supervisor Date Approval Date:*

• Indexing Information

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

+

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

++

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

FLEET/REGIONAL PROGRAM CONCURRENCE:

Fleet ENS ENN Not Applicable DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS (DATE/INITIAL) BY RM TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)

Page 67 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-P6404 Revision: 00 Page: 68 of 257 JOB PERFORMANCE MEASURE Page 68 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-P6404 Revision: 00 Page: 69 of 257 JOB PERFORMANCE MEASURE Generic Instructions

1. Standards and cues for valve operation:

a. MOVs:

1) "Turn the valve's handswitch on (panel #)(section#, as applicable) in the (clockwise or counter-clockwise) direction and observe that the valve's red light is (energized or de-energized) and its green light is (energized or de-energized)".

b. Manual valves

1) "Turn the valve's handwheel (or other manual operating device) in the (clockwise or counter-clockwise) direction until resistance is felt."

2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.

3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.

4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator.

5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)

6. Obtain Shift Management's permission before opening any control panel or compartment. Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).

7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).

8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.

Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.

Page 69 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-P6404 Revision: 00 Page: 70 of 257 JOB PERFORMANCE MEASURE P64 Task 4: Perform Control Room Actions in Response to Fire in Plant Setting: Control Room Type: RO Task: CRO-P64-004 K&A: 286000 A4.05: 3.3/3.3; A2.09: 2.7/2.8 Generic 2.4.25: 2.9/3.4; 2.4.27: 3.0/3.5; 2.1.30: 3.9/3.4; 2.1.31: 4.2/3.9; 2.1.16: 2.9/2.8 Safety Function: Plant Systems (8)

Time Required: 5 minutes Time Critical: No Faulted: No Performance: Simulate Reference(s): 10-S-03-2 Handout(s): 10-S-03-2

1. Manipulations: 5

1. Critical Steps: 5 Group #: 2 Simulator Setup/Required Plant Conditions:

• Area is accessible

• Do not operate plant equipment.

• Notify the Shift Manager and Control Room Supervisor of JPM Performance.

Safety Concerns:

• DO NOT manipulate Control Room Controls.

Initial Condition(s):

• The plant is operating at 100% power.

• The control room has just been informed there is heavy black smoke in the Auxiliary Building in Area 9 139 ft. elevation.

• All Auxiliary Building air operated isolation valves have failed closed.

Initiating Cue(s):

• You have been directed to perform the Control Room Actions in response to the fire and ensure the Fire Brigade has an adequate supply of water for fire suppression.

• This task is not time critical.

Page 70 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-P6404 Revision: 00 Page: 71 of 257 JOB PERFORMANCE MEASURE P64 Task 4: Perform Control Room Actions in Response to Fire in Plant Notes:

1. JPM is to be simulated in the Unit 1 Control Room at the H13-P862 panel.

2. DO NOT OPERATE CONTROL ROOM CONTROLS.

3. Simulate making Plant PA and Radio announcements.

Task Overview:

This task is to perform a start the Motor Driven Fire Pump and align Fire Water to the Unit 1 Auxiliary Building to support Fire Suppression per 10-S-03-2 Response to Fires.

Page 71 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-P6404 Revision: 00 Page: 72 of 257 JOB PERFORMANCE MEASURE P64 Task 4: Perform Control Room Actions in Response to Fire in Plant Tasks : Critical tasks are underlined, italicized, and denoted by an (*)

Note : The sequence for the following steps is not critical.

• Activate the Fire Alarm and Announce over the plant PA system.

Standard: Makes an announcement over the plant PA system as to the location of the fire and for the Fire Brigade to respond to the scene. During this announcement activate the Site Fire Alarm.

Cue: PA Announcement and activation of alarm are complete.

Notes: Do NOT allow candidate to make PA announcement or sound alarm. This would activate the actual Fire Brigade.

Candidate should locate the Site Fire Alarm and describe its operation.

Announcement should be similar to this:

Attention all personnel! There is a (type if known) fire reported at area 9 139 foot elevation in the Auxiliary Building. Fire Brigade to the scene.

CUE: If asked, as Shift Manager direct the candidate to perform the Control Room Actions of the Repsonse to Fires Procedure.

• Announce over the plant radio system.

Standard: Makes an announcement over the plant radio system as to the location of the fire and for the Fire Brigade to respond to the scene.

Cue: Radio Announcement is complete.

Notes: Do NOT allow candidate to make Radio announcement. This would activate the actual Fire Brigade.

Announcement should be similar to this:

Attention all personnel! There is a (type if known) fire reported at area 9 139 foot elevation in the Auxiliary Building. Fire Brigade to the scene.

Page 72 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-P6404 Revision: 00 Page: 73 of 257 JOB PERFORMANCE MEASURE

• Verify running or start the motor Driven Fire Pump.

Standard: Starts the Motor Driven Fire Pump by depressing the START pushbutton on P862 and observes red light on green light off Cue: If asked prior to manipulation cue candidate the green light is on red light is off. Once the candidate performs the action cue red light on green light off Notes:

DO NOT allow candidate to operate control room controls.

• Check open or open 1P64-F010A Fire Water Header Auxiliary Building Isolation Bypass.

Standard: Observes 1P64-F010A is closed and opens the valve by rotating the handswitch clockwise and observing red light on green light off.

Cue: If asked prior to manipulation cue candidate the green light is on red light is off. Once the candidate performs the action cue red light on green light off Notes: Handswitch is on P862.

• Check open or open 1P64-F010B Fire Water Header Auxiliary Building Isolation Bypass.

Standard: Observes 1P64-F010B is closed and opens the valve by rotating the handswitch clockwise and observing red light on green light off.

Cue: If asked prior to manipulation cue candidate the green light is on red light is off. Once the candidate performs the action cue red light on green light off Notes: Handswitch is on P862.

Page 73 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-P6404 Revision: 00 Page: 74 of 257 JOB PERFORMANCE MEASURE Task Standard(s):

Fire Brigade has been dispatched and the Motor Driven Fire Pump is operating and fire water is aligned to the Auxiliary Building.

Name: _______________________________ Time Start: _____ Time Stop: _______

Page 74 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-P6404 Revision: 00 Page: 75 of 257 JOB PERFORMANCE MEASURE P64 Task 4: Perform Control Room Actions in Response to Fire in Plant Follow-Up Questions & Answers:

Comments:

Page 75 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B2110 Revision: 00 Page: 76 of 257 JOB PERFORMANCE MEASURE Perform Control Room Actions in Response to Fire in Plant Give this page to the student Initial Condition(s):

• The plant is operating at 100% power.

• The control room has just been informed there is heavy black smoke in the Auxiliary Building in Area 9 139 ft. elevation.

• All Auxiliary Building air operated isolation valves have failed closed.

Initiating Cue(s):

• You have been directed to perform the Control Room Actions in response to the fire and ensure the Fire Brigade has an adequate supply of water for fire suppression.

• This task is not time critical.

Page 76 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B2110 Revision: 00 Page: 77 of 257 JOB PERFORMANCE MEASURE ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Grand Gulf Nuclear Station Date of Examination: 21 May 2007 Exam Level (circle one) RO / SRO-I / SRO-U Operating Test Number:

@

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Safety Code* Function

a. 202001 Recirculation System - Startup idle Recirculation Pump w/ S; N; A 4 FCV fails to full open.

b. N/A

c. N/A

d. N/A

e. 223001 Primary Containment System and Auxiliaries - Raise S; N; A 5 Suppression Pool Level using RCIC/HPCS ESF

f. 262001 AC Electrical Distribution - Split BOP/ESF Loads S; M; A 6 followed by loss of transformer. ESF

g. N/A

h. N/A In-Plant Systems@ (3 for RO; 3 for SRO-I; 3or2 for SRO-U)

i. N/A

j. 201001 Control Rod Hydraulic System - Rotate CRD Flow R; N 1 Control Valves

k. 295016 Control Room Abandonment - Start SSW A & B and N; E; L 8 supply loads from Remote Shutdown Panel ESF

@ 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; 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 (L)ow-Power 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 77 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B2110 Revision: 00 Page: 78 of 257 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

OPERATOR TRAINING TITLE:

Operate Turbine Pressure Control / SRVs New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: NEW JPM THIS DOCUMENT REPLACES: N/A REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )

Prepared By:

• • Preparer Date Ops Review++:

Technical Reviewer (e.g., SME, line management) Date Validated By:

Training Representative Date Approved By:

+

Discipline Training Supervisor Date Approval Date:*

• Indexing Information

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

+

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

++

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

FLEET/REGIONAL PROGRAM CONCURRENCE:

Fleet ENS ENN Not Applicable DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS BY RM Page 78 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B2110 Revision: 00 Page: 79 of 257 JOB PERFORMANCE MEASURE TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)

Page 79 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B2110 Revision: 00 Page: 80 of 257 JOB PERFORMANCE MEASURE Generic Instructions

1. Standards and cues for valve operation:

a. MOVs:

1) "Turn the valve's handswitch on (panel #)(section#, as applicable) in the (clockwise or counter-clockwise) direction and observe that the valve's red light is (energized or de-energized) and its green light is (energized or de-energized)".

b. Manual valves

1) "Turn the valve's handwheel (or other manual operating device) in the (clockwise or counter-clockwise) direction until resistance is felt."

2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.

3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.

4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator.

5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)

6. Obtain Shift Management's permission before opening any control panel or compartment. Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).

7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).

8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.

Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.

Page 80 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B2110 Revision: 00 Page: 81 of 257 JOB PERFORMANCE MEASURE B21 Task 10: Operate Turbine Pressure Control / SRVs Setting: Simulator Type: RO Task: CRO-B21-010; CRO-N32(2)-009 K&A: 241000 A2.03 - 4.1/4.2; A3.08 - 3.8/3.8; A4.06 - 3.9/3.9 239002 A4.01 - 4.4/4.4; A4.05 - 4.3/4.3 295025 EA1.02 - 3.8/3.8; EA1.03 - 4.4/4.4 Safety Function: 3 Time Required: 10 minutes Time Critical: No Faulted: YES Performance: Actual Reference(s): 04-1-01-N32-2 Att V; 04-1-01-B21-1 Handout(s): None

1. Manipulations: 4

1. Critical Steps: 4 Group: 1 Simulator Simulator Setups:

• IC 19

• Insert malfunctions o c11164@20% Scram Discharge volumen hydraulic block o tc079@ 0% Pressure Controller failure on Trigger 1 o tc082a@0% Bypass Control Valve A closed Trigger 2 o tc082b@0% Bypass Control Valve B closed Trigger 2 o tc082c@0% Bypass Control Valve C closed Trigger 2

• Take Simulator out of freeze and place the mode switch to SHUTDOWN.

• Initiate ATWS ARI.

• Initiate and override HPCS.

• Inhibit ADS.

Turn simulator over to candidate.

Safety Concerns:

• None Page 81 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B2110 Revision: 00 Page: 82 of 257 JOB PERFORMANCE MEASURE B21 Task 10: Operate Turbine Pressure Control / SRVs Initial Condition(s):

• The plant was operating at 100% power when a scram occurred.

• All Control rods did not fully insert.

• Emergency Operating Procedure 2A has been entered.

Initiating Cue(s):

• You have been directed to take RPV Pressure Control and lower pressure reference setpoint to 900 psig. Maintain RPV pressure 800 - 1060 psig.

• Other operators will control other plant parameters.

• Report when pressure is being controlled on the Main Turbine Bypass Valves at 900 psig.

Page 82 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B2110 Revision: 00 Page: 83 of 257 JOB PERFORMANCE MEASURE B21 Task 10: Operate Turbine Pressure Control / SRVs Notes

1. All controls will be from panels P601 and P680 in the Main Control Room.

Task Overview:

This task places the Turbine Pressure Control System operating on the Manual Bypass Jack followed by a failure of the Bypass Valves to open. This requires an alternate method of RPV pressure control using SRVs and a band of 800 to 1060 psig.

Task Justification:

The following JPM does not meet the minimum requirements of 14-S-02-18. It either does not have the required number of manipulations or critical steps. However it has been deemed a valid JPM in accordance with 14-S-02-18 step 6.3.13 due to the following:

This task involves observing the reaction of the Main Steam Bypass Control Valves under ATWS conditions when they are to be used to control RPV pressure. The candidate will have to evaluate the response of the valves to changing RPV pressure.

Once the valves fail alternate pressure control methods will be employed.

This task is selected because RPV Pressure Control during an ATWS is a critical parameter to limit the cycling of the RPV, the problems presented to the operator controlling RPV water level and the power oscillations that occur when RPV pressure cycles.

In all cases preferred heat sink for the RPV is the Main Condenser either through the Main Turbine, Main Steam Bypass Valves, or Main Steam Line Drains. An accepted means of RPV pressure control is the use of SRVs. This is least desired during an ATWS due to the amount of heat being dumped into Primary Containment and the challenge it may present.

This JPM uses two different means of RPV pressure control.

Page 83 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B2110 Revision: 00 Page: 84 of 257 JOB PERFORMANCE MEASURE B21 Task 10: Operate Turbine Pressure Control / SRVs Tasks: critical tasks are underlined, italicized and denoted by (*)

Note: Sequence is critical for critical tasks unless otherwise noted.

• Lowers Turbine Pressure Reference Setpoint on P680 to 900 psig.

Standard: Uses the LOWER pushbutton on section 9C of P680 for PRESS REF to lower the Pressure Reference Setpoint to 900 psig (+/- 30 psig) (indicated on N32-R610 or N32-R672 section 9B).

Cue: As Indicated Notes:

SIMULATOR OPERATOR: Once candidate reports Turbine Pressure reference is at 900psig (+/- 30 psig), ACTIVATE Trigger 1. (Turbine Bypass Control Valves will fail closed.)

CUE: When candidate reports failure of the Turbine Bypass Valves closed, as Control Room Supervisor order the candidate to attempt to control pressure using the Manual Bypass Jack in a pressure band 800 - 1060 psig.

Page 84 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B2110 Revision: 00 Page: 85 of 257 JOB PERFORMANCE MEASURE

• Energize Manual Bypass Valve Controller by simultaneously depressing MANUAL BYPASS CONTROL RELEASE pushbutton and the MANUAL BYPASS VALVE CONTROLLER ON pushbutton until ON pushbutton remains illuminated.

Standard: On P680 section 9C energizes Manual Bypass Valve Controller by simultaneously depressing MANUAL BYPASS CONTROL RELEASE pushbutton and the MANUAL BYPASS VALVE CONTROLLER ON pushbutton until ON pushbutton remains illuminated Cue: As Indicated Notes: In some cases this may take more than one try, this is acceptable as long as the task is accomplished.

• Using the RAISE and/or LOWER pushbuttons open the Turbine Bypass Control Valves to maintain RPV pressure 800 - 1060psig Standard: Depresses RAISE and /or LOWER pushbuttons to open the Turbine Bypass Control Valves.

Cue: As Indicated Notes: Valve indication is located on P680-9D meters N11-R602A, B, C. These valves are slow to react.

When Bypass valves open slightly demonstrating the candidate can open the valves, SIMULATOR OPERATOR Activate Trigger 2. (Turbine Bypass Control Valves failed closed.)

CUE: When candidate reports failure of the Turbine Bypass Valves closed, as Control Room Supervisor order the candidate to attempt to control pressure using SRVs in a pressure band 800 - 1060 psig.

Page 85 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B2110 Revision: 00 Page: 86 of 257 JOB PERFORMANCE MEASURE

• Manually open SRVs to maintain RPV pressure 800 - 1060psig Standard: Manually opens SRVs on P601 by rotating their handswitches clockwise and observing the red light on and green light off to maintain RPV pressure 800 - 1060psig.

Cue: As Indicated Notes: Valve controls are located on P601-19C. Pressure indication is on P601 section 20B B21-UR-R623A and section 17B B21-UR-R623B Post Accident Recorders.

Candidate may verify Reactor Power and Pressure then observe the already open SRVs then adjust number of open SRVs as required to establish RPV pressure in band.

When the Evaluator is satisfied with control the JPM may be terminated.

Task Standard(s):

RPV Pressure is being maintained using SRVs between 800 -

1060 psig..

Name: _________________________________Time Start: _______Time Stop: _______

Page 86 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B2110 Revision: 00 Page: 87 of 257 JOB PERFORMANCE MEASURE B21 Task 10: Operate Turbine Pressure Control / SRVs Follow-Up Questions & Answers:

Comments:

Page 87 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B3311 Revision: 00 Page: 88 of 257 JOB PERFORMANCE MEASURE Operate Turbine Pressure Control Give this page to the student Initial Condition(s):

• The plant was operating at 100% power when a scram occurred.

• All Control rods did not fully insert.

• Emergency Operating Procedure 2A has been entered.

Initiating Cue(s):

• You have been directed to take RPV Pressure Control and lower pressure reference setpoint to 900 psig. Maintain RPV pressure 800 - 1060 psig.

• Other operators will control other plant parameters.

• Report when pressure is being controlled on the Main Turbine Bypass Valves at 900 psig.

Page 88 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B3311 Revision: 00 Page: 89 of 257 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

OPERATOR TRAINING TITLE:

Return Recirc Loop to Service at Power New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: NEW JPM THIS DOCUMENT REPLACES: N/A REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )

Prepared By:

• • Preparer Date Ops Review++:

Technical Reviewer (e.g., SME, line management) Date Validated By:

Training Representative Date Approved By:

+

Discipline Training Supervisor Date Approval Date:*

• Indexing Information

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

+

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

++

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

FLEET/REGIONAL PROGRAM CONCURRENCE:

Fleet ENS ENN Not Applicable DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS BY RM Page 89 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B3311 Revision: 00 Page: 90 of 257 JOB PERFORMANCE MEASURE TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)

Page 90 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B3311 Revision: 00 Page: 91 of 257 JOB PERFORMANCE MEASURE Generic Instructions

1. Standards and cues for valve operation:

a. MOVs:

1) "Turn the valve's handswitch on (panel #)(section#, as applicable) in the (clockwise or counter-clockwise) direction and observe that the valve's red light is (energized or de-energized) and its green light is (energized or de-energized)".

b. Manual valves

1) "Turn the valve's handwheel (or other manual operating device) in the (clockwise or counter-clockwise) direction until resistance is felt."

2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.

3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.

4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator.

5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)

6. Obtain Shift Management's permission before opening any control panel or compartment. Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).

7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).

8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.

Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.

Page 91 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B3311 Revision: 00 Page: 92 of 257 JOB PERFORMANCE MEASURE B33 Task 11: Return Recirc Loop to Service at Power Setting: Simulator Type: RO Task: CRO-B33(1)-011 K&A: 202001 A2.05 - 3.8/4.0; A2.24 - 3.1/3.1; A3.01 - 3.1/3.1; A3.02 - 3.1/3.0; A3.06 - 3.6/3.6; A4.01 - 3.7/3.7; A4.02 - 3.5/3.4; A4.12 - 3.9/3.8 202002 A1.01 - 3.2/3.2; A1.05 - 3.6/3.6; A1.06 - 3.4/3.3; A1.07 - 3.1/3.1; A1.08 - 3.4/3.4; A3.01 - 3.6/3.4; A4.04 - 3.8/3.8; A4.08 - 3.3/3.3; A4.09 - 3.2/3.3 295014 AA1.02 - 3.6/3.8; AA2.03 - 4.0/4.3 Safety Function: 1/4 Time Required: 30 minutes Time Critical: No Faulted: YES Performance: Actual Reference(s): 04-1-01-B33-1; 05-1-02-III-3; EN-OP-115 Handout(s): 04-1-01-B33-1

1. Manipulations: 6 or 7

1. Critical Steps: 5 or 6 Group: 2 Simulator Simulator Setups:

• IC 13 Raise power with control rods to 45% power and shift Recirc Pump A to Fast Speed.

• Trip Recirc Pump B and close the Flow Control Valve to MIN ED position.

• Depress STOP LOCK pushbutton for Recirc Pump B.

• Insert malfunction o rr173b @ 3% Recirc Flow Control Valve ramp open.

Safety Concerns:

• None Page 92 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B3311 Revision: 00 Page: 93 of 257 JOB PERFORMANCE MEASURE B33 Task 11: Return Recirc Loop to Service at Power Initial Condition(s):

• The plant was operating at 45% power when Recirc Pump B tripped on transfer to Fast Speed.

• Electricians corrected the problem with CB-5B that resulted in the Control Power Fuse blowing.

• Recirc Pump A is operating in Fast Speed.

• Seal Purge to Recirc Pump B has been verified at normal pressures.

• Reactor Engineering has verified the plant is operating at < 75% Rod Line and that FCBB is < 1.0.

• Recirc Flow Control Valve is at the MIN ED position.

• Unit 1 Instrument Air Compressor is in lead.

• FCTR has been placed in the SETUP mode.

• Recirc Loop A is operating < 22,300 gpm.

• ALL annunciators associated with the B Hydraulic Power Unit and cooling to Recirc Pump B are clear.

• Chemistry and Radiation Protection have been notified of the Recirc Pump start.

• The Idle Loop Startup Surveillance 06-OP-1B33-V-0005 is being performed by another operator.

• Reactor Water level has been raised to 40 inches.

• All Recirc Pump Temperatures are normal.

• Feedwater flow is > 4.5 Mlbm/hr.

• Reactor Dome temperature is >7.4 degrees above Recirc Loop B.

Initiating Cue(s):

• You have been directed to return Recirc Loop B to service.

• Other operators will control other plant parameters.

Page 93 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B3311 Revision: 00 Page: 94 of 257 JOB PERFORMANCE MEASURE B33 Task 11: Return Recirc Loop to Service at Power Notes

1. All controls will be from panels P680 and P807 in the Main Control Room.

Task Overview:

This task returns a Reactor Recirc Loop to service with the plant above 30% power with conditions such that the pump should operate in Fast Speed. Following the pump start the Flow Control Valve will ramp to full open on its own. This will require operator action to reduce the impact on the Reactor.

Page 94 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B3311 Revision: 00 Page: 95 of 257 JOB PERFORMANCE MEASURE B33 Task 11: Return Recirc Loop to Service at Power Tasks: critical tasks are underlined, italicized and denoted by (*)

Note: Sequence is critical for critical tasks unless otherwise noted.

Check the following Breaker positions for Recirc Pump B:

____ CB-3B, RECIRC PMP FDR B DRIVE MOTOR BKR 252-1205B CLOSED

____ CB-4B, RECIRC PMP FDR 252-1205C CLOSED

____ CB-1B, LFMG B MTR FDR 152-1411 OPEN

____ CB-2B, LFMG B GEN FDR 252-1205A OPEN

____ CB-5B, RECIRC PMP B FDR 252-1205 OPEN Standard: Observes Breaker indication for Recric Pump B CB-3B and 4B should be red light on green light off, CB-1B, 2B and 5B should be green light on red light off on P680.

Cue: As Indicated Notes: Indications are on P680 section 3C.

NOTE: Candidate may verify Recirc Pump B seal pressures and HPU operation. These were given in the Initial Conditions and are as indicated.

• Raise BOP Transformer tap setting to raise bus voltage on bus 12HE to about 7.2KV.

Standard: On P807 raises tap setting on BOP Transformer for bus 12HE to about 7.2 KV as indicated on R22-R603 section 2B of P807.

Cue: As Indicated Notes:

CUE: Surveillance 06-OP-1B33-V-0005 was just completed one minute ago satisfactorily.

• Depress RELEASE pushbutton on the RECIRC PMP B STOP/STOP LOCK pushbutton.

Standard: Depresses RELEASE pushbutton on Recirc Pump B Stop/Stop Lock pushbutton.

Cue: As Indicated Notes: Pushbutton is located on P680 section 3C.

Page 95 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B3311 Revision: 00 Page: 96 of 257 JOB PERFORMANCE MEASURE

• Depress START pushbutton on RECIRC PMP B TRANS TO LFMG/START pushbutton.

Standard: Depresses START pushbutton on RECIRC PMP B TRANS TO LFMG/START pushbutton.

Cue: As Indicated Notes: Pushbutton is located on P680 section 3C.

Observe the following for Recirc Pump B:

____ CB-5B, RECIRC PMP B FDR 252-1205 CLOSE (red light on green light off)

____ RECIRC PMP B amps increase

____ RECIRC PMP B rpm increase to 1800 rpm Standard: Observes indications for Recric Pump B on P680.

Cue: As Indicated Notes: Indications are on P680 section 3B & C.

Lower BOP Transformer tap setting to lower bus voltage on bus 12HE to about 7KV.

Standard: On P807 lowers tap setting on BOP Transformer for bus 12HE to about 7 KV as indicated on R22-R603 section 2B of P807.

Cue: As Indicated Notes:

Check proper pump and Jet pump operation on P680.

Standard: On P680 section 3B looks at indications for jet pump flows, Recirc Loop Flow, Core Flow, Seeal Pressures.

Cue: As Indicated Notes:

Page 96 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B3311 Revision: 00 Page: 97 of 257 JOB PERFORMANCE MEASURE

• Balance flow between Recirc Loops A and B to establish less than 10% differential by opening on Recirc Pump B Flow Control Valve B.

Standard: Raises Recirc Loop B 0Flow Control Valve position to raise Recirc Loop B flow.

Cue: As Indicated Notes: Slide switch on P680 section 3D indication is on section 3B recorder 1C51-FR-R614 (Loop B is the red pen indication.).

SIMULATOR OPERATOR when candidate raises on Loop Flow, ACTIVATE Trigger 1 The candidate may attempt one of several options.

Attempt to lower on the B Loop Flow Control Valve Control.

Standard: Places Recirc Loop B Flow Control Valve control to LOWER position to lower Recirc Loop B flow.

Cue: As Indicated Notes: Slide switch on P680 section 3D indication is on section 3B recorder 1C51-FR-R614 (Loop B is the red pen indication.). THIS ACTION WILL HAVE NO EFFECT.

Option 1

• Trip Recirc Pump B Hydraulic Power Unit to stop valve movement.

Standard: Arms and depresses HPU B SHUTDN pushbutton on P680.

Cue: As Indicated Notes: Armed collar pushbutton on P680 section 3C. This action will stop valve movement.

This action keeps the Recirc Pump operating, however Reactor Engineering will have to determine the affects on the core.

Page 97 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B3311 Revision: 00 Page: 98 of 257 JOB PERFORMANCE MEASURE Option 2

• Trip Recirc Pump B by depressing STOP or STOP LOCK pushbutton.

Standard: Trips Recirc Pump B by depressing STOP or STOP LOCK pushbutton on P680 indication will be green light on red light off for CB-5B.

Cue: As Indicated Notes: Pushbutton on P680 section 3C. This action will trip the Recirc pump to off.

Option 3 This action will require entry into the Reduction of Recirculation Flow ONEP 05-1 III-3.

• Close RECIRC PMP B DISCH VLV B33-F067B.

Standard: Closes B33-F067B by depressing CLOSE pushbutton on P680 indication will be green light on red light off.

Cue: As Indicated Notes: Pushbutton on P680 section 3C. This action will be performed if the option of Tripping the Recirc pump is taken. If the Recirc Pump remains operating this item is not critical.

Plot operation on Power to Flow map.

Standard: Plots operation using rms and depresses HPU B SHUTDN pushbutton on P680.

Cue: As Indicated Notes: Plot should be in the Monitor Region.

Task Standard(s):

Actions have been taken to limit reactor power rise due to the Recirc Flow Control Valve malfunction.

Page 98 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B3311 Revision: 00 Page: 99 of 257 JOB PERFORMANCE MEASURE Name: _________________________________Time Start: _______Time Stop: _______

Page 99 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-B3311 Revision: 00 Page: 100 of 257 JOB PERFORMANCE MEASURE B33 Task 11: Return Recirc Loop to Service at Power Follow-Up Questions & Answers:

Comments:

Page 100 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C6109 Revision: 00 Page: 101 of 257 JOB PERFORMANCE MEASURE Return Recirc Loop to Service at Power Give this page to the student Initial Condition(s):

• The plant was operating at 45% power when Recirc Pump B tripped on transfer to Fast Speed.

• Electricians corrected the problem with CB-5B that resulted in the Control Power Fuse blowing.

• Recirc Pump A is operating in Fast Speed.

• Seal Purge to Recirc Pump B has been verified at normal pressures.

• Reactor Engineering has verified the plant is operating at < 75% Rod Line and that FCBB is < 1.0.

• Recirc Flow Control Valve is at the MIN ED position.

• Unit 1 Instrument Air Compressor is in lead.

• FCTR has been placed in the SETUP mode.

• Recirc Loop A is operating < 22,300 gpm.

• ALL annunciators associated with the B Hydraulic Power Unit and cooling to Recirc Pump B are clear.

• Chemistry and Radiation Protection have been notified of the Recirc Pump start.

• The Idle Loop Startup Surveillance 06-OP-1B33-V-0005 was completed satisfactorily 1 minute ago.

• Reactor Water level has been raised to 40 inches.

• All Recirc Pump Temperatures are normal.

• Feedwater flow is > 4.5 Mlbm/hr.

• Reactor Dome temperature is >7.4 degrees above Recirc Loop B.

Initiating Cue(s):

• You have been directed to return Recirc Loop B to service.

• Other operators will control other plant parameters.

Page 101 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C6109 Revision: 00 Page: 102 of 257 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

OPERATOR TRAINING TITLE:

Start SSW A & B and supply all loads from Remote Shutdown Panels New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: NEW JPM.

THIS DOCUMENT REPLACES: N/A REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )

Prepared By:

• • Preparer Date Ops Review++:

Technical Reviewer (e.g., SME, line management) Date Validated By:

Training Representative Date Approved By:

+

Discipline Training Supervisor Date Approval Date:*

• Indexing Information

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

+

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

++

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

FLEET/REGIONAL PROGRAM CONCURRENCE:

Fleet ENS ENN Not Applicable Page 102 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C6109 Revision: 00 Page: 103 of 257 JOB PERFORMANCE MEASURE DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS (DATE/INITIAL) BY RM TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)

Page 103 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C6109 Revision: 00 Page: 104 of 257 JOB PERFORMANCE MEASURE Generic Instructions

1. Standards and cues for valve operation:

a. MOVs:

1) "Turn the valve's handswitch on (panel #)(section#, as applicable) in the (clockwise or counter-clockwise) direction and observe that the valve's red light is (energized or de-energized) and its green light is (energized or de-energized)".

b. Manual valves

1) "Turn the valve's handwheel (or other manual operating device) in the (clockwise or counter-clockwise) direction until resistance is felt."

2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.

3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.

4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator.

5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)

6. Obtain Shift Management's permission before opening any control panel or compartment. Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).

7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).

8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.

Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.

Page 104 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C6109 Revision: 00 Page: 105 of 257 JOB PERFORMANCE MEASURE C61 Task 9: Start SSW A & B and supply all loads from Remote Shutdown Panels Setting: Plant (Outside CAA)

Type: RO Task: CRO-C61-009 K&A: 295016 Generic 2.1.30 - 3.9/3.4 400000 A4.01 3.1/3.0 Safety Function: 7/8 Time Required: 10 minutes Time Critical: No Faulted: No Performance: Actual Reference(s): 05-1-02-II-1 Handout(s): 05-1-02-II-1

1. Manipulations: 14

1. Critical Steps: 14 Group: 1 Plant / Low Power / Emergency - Abnormal Operations Simulator Setups:

o N/A Safety Concerns:

• None Initial Condition(s):

• The Control Room has been abandoned due to toxic gas.

• The Reactor has been scrammed and RPS reset.

• All control rods are fully inserted.

• Control is being established at the Remote Shutdown Panels.

Initiating Cue(s):

• You have been directed to start Standby Service Water (SSW) A and B and supply loads in accordance with ONEP 05-1-02-II-1 sections 3.8.1a and 3.8.2a.

Page 105 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C6109 Revision: 00 Page: 106 of 257 JOB PERFORMANCE MEASURE C61 Task 9: Start SSW A & B and supply all loads from Remote Shutdown Panels Notes

1. All controls will be from panels P150 and P151 in the Remote Shutdown Panel Room.

Task Overview:

This task aligns Standby Service Water in operation through all loads from the Remote Shutdown Panels. This action would be taken in the event of Control Room Abandonment for toxic gas, fire, or terrorist control of the Main Control Room.

Page 106 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C6109 Revision: 00 Page: 107 of 257 JOB PERFORMANCE MEASURE C61 Task 9: Start SSW A & B and supply all loads from Remote Shutdown Panels Tasks: critical tasks are underlined, italicized and denoted by (*)

Note: Sequence is critical for critical tasks unless otherwise noted.

May elect to perform SSW A first or B order of systems is NOT critical.

SSW A (Attachment VIII section 3.8.1a)

Panel H22-P150 Check open/open P41-F068A, SSW OUTL FM RHR HX A VLV.

Standard: Observes P41-F068A open red light on green light off.

Cue: Red light on Green light off Notes:

• Start P41-C001A, SSW PMP A.

Standard: Starts SSW Pump A by rotating handswitch on P150 clockwise to START and observing red light on green light off.

Cue: Red light on Green light off Notes:

• Open P41-F001A, SSW PMP DISCH VLV.

Standard: Opens P41-F001A, SSW PMP DISCH VLV by rotating the key lock switch clockwise on P150 and observing red light on green light off.

Cue: Red light on Green light off Notes:

Page 107 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C6109 Revision: 00 Page: 108 of 257 JOB PERFORMANCE MEASURE

• Open P41-F014A, SSW INL TO RHR HX A VLV.

Standard: Opens P41-F014A, SSW INL TO RHR HX A VLV by rotating the handswitch clockwise on P150 and observing red light on green light off.

Cue: Red light on Green light off Notes: The interlock between P41-F006A and F014A is bypassed at the Remote Shutdown Panels.

• Open P41-F005A, SSW LOOP A RTN TO CLG TWR A.

Standard: Opens P41-F005A, SSW LOOP A RTN TO CLG TWR A by rotating the handswitch clockwise on P150 and observing red light on green light off.

Cue: Red light on Green light off Notes:

If asked, Cue P41-F006A is Red Light ON Green Light OFF.

• Close P41-F006A, SSW LOOP A RECIRC VLV.

Standard: Closes P41-F006A, SSW LOOP A RECIRC VLV by rotating the handswitch counter-clockwise on P150 and observing green light on red light off.

Cue: Green light on Red light off Notes: Order NOT Critical. The interlock between P41-F006A and F014A is bypassed at the Remote Shutdown Panels.

• Start P41-C003A, SSW CLG TWR FAN A.

Standard: Starts P41-C003A, SSW CLG TWR FAN A by rotating the handswitch clockwise on P150 and observing red light on green light off.

Cue: Red light on Green light off Notes: Order for Fan A and Fan B is NOT critical.

Page 108 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C6109 Revision: 00 Page: 109 of 257 JOB PERFORMANCE MEASURE

• Start P41-C003B, SSW CLG TWR FAN B.

Standard: Starts P41-C003B, SSW CLG TWR FAN B by rotating the handswitch clockwise on P150 and observing red light on green light off.

Cue: Red light on Green light off Notes: Order for Fan A and Fan B is NOT critical.

Page 109 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C6109 Revision: 00 Page: 110 of 257 JOB PERFORMANCE MEASURE May elect to perform SSW A first or B order of systems is NOT critical.

SSW B (Attachment IX section 3.8.2a)

Panel H22-P151 Check open/open P41-F068B, SSW OUTL FM RHR HX B VLV.

Standard: Observes P41-F068B open red light on green light off.

Cue: Red light on Green light off Notes:

• Start P41-C001B, SSW PMP B.

Standard: Starts SSW Pump B by rotating handswitch on P151 clockwise to START and observing red light on green light off.

Cue: Red light on Green light off Notes:

• Open P41-F001B, SSW PMP DISCH VLV.

Standard: Opens P41-F001B, SSW PMP DISCH VLV by rotating the key lock switch clockwise on P151 and observing red light on green light off.

Cue: Red light on Green light off Notes:

Page 110 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C6109 Revision: 00 Page: 111 of 257 JOB PERFORMANCE MEASURE

• Open P41-F014B, SSW INL TO RHR HX B VLV.

Standard: Opens P41-F014B, SSW INL TO RHR HX B VLV by rotating the handswitch clockwise on P151 and observing red light on green light off.

Cue: Red light on Green light off Notes: The interlock between P41-F006B and F014B is bypassed at the Remote Shutdown Panels.

• Open P41-F005B, SSW LOOP B RTN TO CLG TWR B.

Standard: Opens P41-F005B, SSW LOOP B RTN TO CLG TWR B by rotating the handswitch clockwise on P151 and observing red light on green light off.

Cue: Red light on Green light off Notes:

If asked, Cue P41-F006B is Red Light ON Green Light OFF.

• Close P41-F006B, SSW LOOP B RECIRC VLV.

Standard: Closes P41-F006B, SSW LOOP B RECIRC VLV by rotating the handswitch counter-clockwise on P151 and observing green light on red light off.

Cue: Green light on Red light off Notes: Order NOT Critical. The interlock between P41-F006B and F014B is bypassed at the Remote Shutdown Panels.

• Start P41-C003C, SSW CLG TWR FAN C.

Standard: Starts P41-C003C, SSW CLG TWR FAN C by rotating the handswitch clockwise on P151 and observing red light on green light off.

Cue: Red light on Green light off Notes: Order for Fan C and Fan D is NOT critical.

Page 111 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C6109 Revision: 00 Page: 112 of 257 JOB PERFORMANCE MEASURE

• Start P41-C003D, SSW CLG TWR FAN D.

Standard: Starts P41-C003D, SSW CLG TWR FAN D by rotating the handswitch clockwise on P151 and observing red light on green light off.

Cue: Red light on Green light off Notes: Order for Fan C and Fan D is NOT critical.

Task Standard(s):

SSW A & B are operating through the RHR Heat Exchangers with the Cooling Tower fans operating from the Remote Shutdown Panels H22-P150 and P151.

Name: _________________________________Time Start: _______Time Stop: _______

Page 112 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-C6109 Revision: 00 Page: 113 of 257 JOB PERFORMANCE MEASURE C61 Task 9: Start SSW A & B and supply all loads from Remote Shutdown Panels Follow-Up Questions & Answers:

Comments:

Page 113 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E1201 Revision: 1 Page: 114 of 257 JOB PERFORMANCE MEASURE Start SSW A & B and supply all loads from Remote Shutdown Panels Give this page to the student Initial Condition(s):

• The Control Room has been abandoned due to toxic gas.

• The Reactor has been scrammed and RPS reset.

• All control rods are fully inserted.

• Control is being established at the Remote Shutdown Panels.

Initiating Cue(s):

• You have been directed to start Standby Service Water (SSW) A and B and supply loads in accordance with ONEP 05-1-02-II-1 sections 3.8.1a and 3.8.2a.

Page 114 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E1201 Revision: 1 Page: 115 of 257 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

OPERATOR TRAINING TITLE:

Startup Shutdown Cooling B New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: Update JPM for NRC THIS DOCUMENT REPLACES: N/A REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )

Prepared By:

• • Preparer Date Ops Review++:

Technical Reviewer (e.g., SME, line management) Date Validated By:

Training Representative Date Approved By:

+

Discipline Training Supervisor Date Approval Date:*

• Indexing Information

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

+

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

++

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

FLEET/REGIONAL PROGRAM CONCURRENCE:

Fleet ENS ENN Not Applicable DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS BY RM Page 115 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E1201 Revision: 1 Page: 116 of 257 JOB PERFORMANCE MEASURE TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)

Page 116 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E1201 Revision: 1 Page: 117 of 257 JOB PERFORMANCE MEASURE Generic Instructions

1. Standards and cues for valve operation:

a. MOVs:

1) "Turn the valve's handswitch on (panel #)(section#, as applicable) in the (clockwise or counter-clockwise) direction and observe that the valve's red light is (energized or de-energized) and its green light is (energized or de-energized)".

b. Manual valves

1) "Turn the valve's handwheel (or other manual operating device) in the (clockwise or counter-clockwise) direction until resistance is felt."

2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.

3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.

4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator.

5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)

6. Obtain Shift Management's permission before opening any control panel or compartment. Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).

7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).

8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.

Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.

Page 117 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E1201 Revision: 1 Page: 118 of 257 JOB PERFORMANCE MEASURE E12 Task 1: Startup Shutdown Cooling B Setting: Simulator Type: RO Task: CRO-E12-008 K&A: 205000 A4.01 - 3.7/3.7; A4.02 - 3.6/3.5; A4.03 - 3.6/3.5 Safety Function: 4 Time Required: 15 minutes Time Critical: No Faulted: No Performance: Actual Reference(s): 04-1-01-E12-2 sect 4.2.2c Handout(s): None

1. Manipulations: 10

1. Critical Steps: 8 Group: 1 Simulator / Low Power Simulator Setups:

• IC 1 Secure RHR A SDC and SSW A

• SSW B in operation to the RHR B heat exchangers

• B21-F065A; E12- F004B; F008; F064B; F009; F053B and F006B are closed.

• B21-F065B is open.

Safety Concerns:

• None Initial Condition(s):

• RHR A was previously in service for Shutdown Cooling but was secured.

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

• SSW B is in operation.

• ADHR is not in operation.

Initiating Cue(s):

• You have been directed to place RHR B in Shutdown Cooling through E12-F053B, starting at Step 4.2.2c(12) of SOI 04-1-01-E12-2. Establish RHR flow Page 118 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E1201 Revision: 1 Page: 119 of 257 JOB PERFORMANCE MEASURE with E12-F003B full open and E12-F048B full closed to maximize RPV cooldown rate.

Page 119 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E1201 Revision: 1 Page: 120 of 257 JOB PERFORMANCE MEASURE E12 Task 1: Startup Shutdown Cooling B Notes

1. All controls will be from panels P601 and P680 in the Main Control Room.

2. Unless otherwise indicated, all valves are in the E12 system.

Task Overview:

This task places the RHR system in service for Shutdown Cooling using the normal (E12-F053B) flowpath. This is a Tech Spec Decay Heat Removal method. Throttling of RHR Shutdown Cooling flow caused damage to RHR Instrumentation piping during RF12.

Page 120 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E1201 Revision: 1 Page: 121 of 257 JOB PERFORMANCE MEASURE E12 Task 1: Startup Shutdown Cooling B Tasks: critical tasks are underlined, italicized and denoted by (*)

Note: Sequence is critical for critical tasks unless otherwise noted.

Place the RHR B MOV TEST switch in TEST Standard: Turns the RHR B MOV TEST switch clockwise until it snaps in the TEST position Cue: As Indicated Notes: Indication is on P601-17B. Will receive MOVS IN TEST Status Light and RHR B OOSVC annunciator.

Open or check open the following valves:

E12-F010 INLET TO SHUTDOWN COOLING

• E12-F008 RHR SHUTDN CLG OTBD SUCT VLV

• E12-F009 RHR SHUTDN CLG INBD SUCT VLV

• E12-F006B RHR B PMP SUCT FM SHUTDN CLG E12-F047B RHR HX INL VLV E12-F048B RHR HX BYP VLV Standard: Checks open E12-F010; F047B on P601 by observing their red light on and their green light off. E12-F048B has a valve position indication meter on P601-17B to indicate 100%. OPENS E12-F008; F009 and F006B by turning their handswitches on P601 clockwise in the OPEN direction and observing its red light is on and its green light is off.

Cue: As Indicated Notes: Valves are controlled from P601-17C Page 121 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E1201 Revision: 1 Page: 122 of 257 JOB PERFORMANCE MEASURE

• Close E12-F003B RHR HX B OUTL VLV-Standard: Closes E12-F003B by turning its handswitch on P601 counter -

clockwise in the CLOSE direction and holding while observing position indication meter on P601-17B lower to indicate 0%.

Cue: As Indicated Notes: Valve is controlled from P601-17C

• Close or check closed B21-F065B FW INL SHUTOFF VLV Standard: Checks closed B21-F065B on P680 by observing its green light on and its red light off.

Cue: As Indicated Notes: Valve indication is located on P680-2C NOTE: The Candidate should identify OPTION 1 is the method to be used per NOTE at step 4.2.2c(14).

NOTE: The following two steps have to be performed within 8 seconds to prevent causing E12-F064B from opening for minimum flow which would drain the RPV to the Suppression Pool.

• Start RHR PMP B Standard: Starts RHR pump B by turning its handswitch on P601 clockwise in the START direction and observing its red light is on and its green light is off.

Cue: As Indicated Notes: Pump handswitch is on P601-17C Page 122 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E1201 Revision: 1 Page: 123 of 257 JOB PERFORMANCE MEASURE

• Open E12-F053B RHR B SHUTDN CLNG RTN TO FW Standard: Opens E12-F053B by turning its handswitch on P601 clockwise in the OPEN direction and holding it until its red light is on and its green light is off Cue: As Indicated Notes:

• Slowly opens E12-F003B RHR HX B OUTL VLV Standard: Slowly opens E12-F003B by turning its handswitch on P601 clockwise to jog the valve in the OPEN direction and while observing the valve position indication on P601-17B rise to indicate 100%.

Cue: As Indicated Notes: Candidate should observe RHR Flow on E12-R603B and temperatures on E12-R601.

NOTE: Due to current RPV temperature 100 degree F / Hr cooldown rate cannot be exceeded.

• Slowly throttle E12-F048B RHR HX BYP VLV closed Standard: Throttles E12-F048B closed by turning its handswitch on P601 counter

- clockwise in the CLOSE direction.

Cue: As indicated Notes: Indication on E12-R603B panel P601-17B Page 123 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E1201 Revision: 1 Page: 124 of 257 JOB PERFORMANCE MEASURE Task Standard(s):

Shutdown Cooling B is started IAW SOI 04-1-01-E12-1, with E12-F003B full open and E12-F048B full closed.

Name: _________________________________Time Start: _______Time Stop: _______

Page 124 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E1201 Revision: 1 Page: 125 of 257 JOB PERFORMANCE MEASURE E12 Task 1: Startup Shutdown Cooling B Follow-Up Questions & Answers:

Comments:

Page 125 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E2215 Revision: 0 Page: 126 of 257 JOB PERFORMANCE MEASURE Startup Shutdown Cooling B Give this page to the student Initial Condition(s):

• RHR A was previously in service for Shutdown Cooling but was secured.

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

• SSW B is in operation.

• ADHR is not in operation.

Initiating Cue(s):

• You have been directed to place RHR B in Shutdown Cooling through E12-F053B, starting at Step 4.2.2c(12) of SOI 04-1-01-E12-2. Establish RHR flow with E12-F003B full open and E12-F048B full closed to maximize RPV cooldown rate.

Page 126 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E2215 Revision: 0 Page: 127 of 257 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

OPERATOR TRAINING TITLE:

Raise Suppression Pool Level using RCIC/HPCS New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: New JPM THIS DOCUMENT REPLACES: N/A REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )

Prepared By:

• • Preparer Date Ops Review++:

Technical Reviewer (e.g., SME, line management) Date Validated By:

Training Representative Date Approved By:

+

Discipline Training Supervisor Date Approval Date:*

• Indexing Information

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

+

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

++

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

FLEET/REGIONAL PROGRAM CONCURRENCE:

Fleet ENS ENN Not Applicable DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS BY RM Page 127 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E2215 Revision: 0 Page: 128 of 257 JOB PERFORMANCE MEASURE TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)

Page 128 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E2215 Revision: 0 Page: 129 of 257 JOB PERFORMANCE MEASURE Generic Instructions

1. Standards and cues for valve operation:

a. MOVs:

1) "Turn the valve's handswitch on (panel #)(section#, as applicable) in the (clockwise or counter-clockwise) direction and observe that the valve's red light is (energized or de-energized) and its green light is (energized or de-energized)".

b. Manual valves

1) "Turn the valve's handwheel (or other manual operating device) in the (clockwise or counter-clockwise) direction until resistance is felt."

2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.

3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.

4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator.

5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)

6. Obtain Shift Management's permission before opening any control panel or compartment. Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).

7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).

8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.

Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.

Page 129 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E2215 Revision: 0 Page: 130 of 257 JOB PERFORMANCE MEASURE E22 Task 15: Raise Suppression Pool Level using RCIC/HPCS Setting: Simulator Type: RO Task: CRO-E22-011; CRO-E51-016 K&A: 223001 A2.11: 3.6/3.8; K1.13: 3.4/3.5; K1.14: 3.3/3.6 209002 A1.05: 3.3/3.4; K1.01: 3.4/3.4; K1.02: 3.5/3.5; A4.01: 3.7/3.7; A4.02: 3.6/3.6; A4.14: 3.0/3.0 217000 A4.03: 3.4/3.3 295030 EA1.02: 3.4/3.5; EA1.03: 3.4/3.4 Safety Function: 5 Time Required: 10 minutes Time Critical: No Faulted: YES Performance: Actual Reference(s): 04-1-01-E51-1; 04-1-01-E22-1; 05-1-01-EP-3 Handout(s): 04-1-01-E51-1; 04-1-01-E22-1

1. Manipulations: 8 or 9

1. Critical Steps: 7 or 8 Group: 1/2 Simulator Simulator Setups:

• ANY IC

• Lower Suppression Pool Water Level to 18.13 feet.

• Defeat Suppression Pool Makeup A & B

• Insert Malfuction e51187g on RCIC Minimum Flow Valve Closed (loss of power on stroke)

Safety Concerns:

• None Page 130 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E2215 Revision: 0 Page: 131 of 257 JOB PERFORMANCE MEASURE E22 Task 15: Raise Suppression Pool Level using RCIC/HPCS Initial Condition(s):

• The plant is operating at 100% power.

• Suppression Pool Water Level is low due to a leak in RHR C Pump Room.

• Standby Service Water A is operating.

• Emergency Operating Procedure 3 has been entered.

• Suppression Pool Makeup is out of service.

Initiating Cue(s):

• You have been directed to perform a controlled startup of RCIC and raise Suppression Pool water level to the normal band using RCIC.

Notes

1. All controls will be from panels P601 and P870 in the Main Control Room.

Task Overview:

This task raises Suppression Pool Water Level using methods allowed per 05-1-01-EOP-3 using RCIC / HPCS.

Page 131 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E2215 Revision: 0 Page: 132 of 257 JOB PERFORMANCE MEASURE E22 Task 15: Raise Suppression Pool Level using RCIC/HPCS Tasks: critical tasks are underlined, italicized and denoted by (*)

Note : The sequence for the following steps is critical.

Start RCIC RM FAN COIL UNIT.

Standard: Starts RCIC RM Fan Coil Unit by placing RCIC RM FAN COIL UNIT handswitch to the clockwise direction on P870 and observes red light on green light off.

Cue: As Indicated Notes: Indication is on P870-1C.

Close E51-F268 PRESS LOCK ISOL FOR F013 Standard: Contacts Aux Bldg Operator to close E51-F268 PRESS LOCK ISOL FOR F013.

Cue: E51-F268 is closed.

Notes: Field operation.

• Shift RCIC FLO CONT to MANUAL.

Standard: Shifts RCIC FLO CONT to MANUAL by placing slide switch on controller to left for controller on P601.

Cue: As Indicated Notes: Indication is on P601-21B.

• Reduce RCIC FLO CONT output to minimum.

Standard: Reduces RCIC FLO CONT to output to minimum by depressing left pushbutton on controller until horizontal meter reads zero on P601.

Cue: As Indicated Notes: Indication is on P601-21B.

Page 132 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E2215 Revision: 0 Page: 133 of 257 JOB PERFORMANCE MEASURE

• Open E51-F046 RCIC WTR TO TURB LUBE OIL CLR Standard: Opens E51-F046 by turning its handswitch on P601 clockwise in the OPEN direction and holding while observing red light on and green light off.

Cue: As Indicated Notes: Valve is controlled from P601-21C

• Start Turbine Gland Seal Compressor using RCIC GL SEAL COMPR handswitch.

Standard: Starts RCIC Glans Seal Compressor by turning handswitch clockwise on P601 and observing red light on green light off.

Cue: As Indicated Notes: Indication is on P601-21C.

• Open E51-F095 RCIC STM SPLY BYP VLV Standard: Opens E51-F095 by turning its handswitch on P601 clockwise in the OPEN direction and holding while observing red light on and green light off.

Cue: As Indicated Notes: Valve is controlled from P601-21C NOTE: As soon as the candidate recognizes the failure of the Minimum Flow Valve, the candidate may proceed to secure the RCIC Turbine. If this is the case the following three steps will be N/A.

After 6 seconds open E51-F045 RCIC STM SPLY TO RCIC TURB Standard: After approximately 6 seconds E51-F045 by turning its handswitch on P601 clockwise in the OPEN direction and holding while observing red light on and green light off.

Cue: As Indicated Notes: Valve is controlled from P601-21C NOTE: May not be performed is RCIC is tripped.

Page 133 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E2215 Revision: 0 Page: 134 of 257 JOB PERFORMANCE MEASURE Raise RCIC Turbine speed to greater than 2000 rpm by opening on RCIC FLO CONT output.

Standard: Raises RCIC Turbine speed to > 2000 rpm using RCIC FLO CONT by depressing the OPEN pushbutton and observing E51-R605 on section 21B of P601.

Cue: As Indicated Notes: Indication is on P601-21B.

NOTE: May not be performed if RCIC is tripped.

NOTE: The following steps may be performed in any order.

Open or check open E51-F019 RCIC MIN FLO to SUPP POOL Standard: Opens E51-F019 by turning its handswitch on P601 clockwise in the OPEN direction and holding while observing red light on and green light off.

Cue: As Indicated Notes: Candidate should observe the valve loses power and fails to open.

Valve is controlled from P601-21C CUE: If asked by the candidate to check the valve circuit breaker, report as the Roving Operator circuit breaker 72-11A56 is in the TRIP FREE condition and there is a strange odor in the area.

Candidate should inform the Control Room Supervisor (CRS) of the problem. IF ASKED, CUE the candidate to secure the RCIC Turbine and raise Suppression Pool Level via the HPCS gravity flow. Once the RCIC Turbine is tripped another operator will complete the RCIC shutdown.

Close or check closed E51-F022 RCIC INBD TEST RTN TO CST Standard: Observes indication for E51-F022 as green light on red light off on P601.

Cue: As Indicated Notes: Valve is controlled from P601-21C NOTE: May not be performed.

Close or check closed E51-F059 RCIC OUTBD TEST RTN TO CST Standard: Observes indication for E51-F059 as green light on red light off on P601.

Cue: As Indicated Notes: Valve is controlled from P601-21C NOTE: May not be performed.

Page 134 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E2215 Revision: 0 Page: 135 of 257 JOB PERFORMANCE MEASURE Secure RCIC Observe RCIC INIT RESET pushbutton white light is out.

Standard: Observes RCIC INIT RESET pushbutton white light is out.

Cue: As Indicated.

Notes: Indication is on P601 section 21B.

NOTE: May not be performed. This is acceptable.

Reduce RCIC flow to <100 gpm using RCIC FLO CONT.

Standard: Reduces RCIC flow using RCIC FLO CONT.

Cue: As Indicated Notes: Candidate may not perform, this step since there is no RCIC flow. This is acceptable.

Close E51-F013 RCIC INJ SHUTOFF VLV.

Standard: Observes indication for E51-F013 closed as green light on red light off on P601.

Cue: As Indicated Notes: Candidate may not perform, the valve was never opened. This is acceptable.

RCIC may be secured by option 1 or 2 either is acceptable.

Option 1 to secure RCIC

• TRIP RCIC Turbine Standard: Trips the RCIC Turbine using the RCIC TURBINE TRIP pushbutton on P601 and observes green light on and red light off for the RCIC Trip Throttle valve.

Cue: As Indicated Notes: Controlled from P601-21C Page 135 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E2215 Revision: 0 Page: 136 of 257 JOB PERFORMANCE MEASURE Option 2 to secure RCIC

• Close E51-F095 RCIC STM SPLY BYP VLV Standard: Closes E51-F095 by turning its handswitch on P601 counter-clockwise in the CLOSE direction and holding while observing green light on and red light off.

Cue: As Indicated Notes: Valve is controlled from P601-21C

• Close E51-F045 RCIC STM SPLY TO RCIC TURB Standard: Closes E51-F045 by turning its handswitch on P601 counter-clockwise in the CLOSE direction and holding while observing green light on and red light off.

Cue: As Indicated Notes: Valve is controlled from P601-21C ANOTHER OPERATOR WILL PICKUP THE RCIC OPERATIONS FROM HERE.

May need to cue the candidate to another operator securing RCIC and as Control Room Supervisor direct candidate to raise Suppression Pool Level via HPCS gravity flow.

Page 136 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E2215 Revision: 0 Page: 137 of 257 JOB PERFORMANCE MEASURE HPCS Gravity Flow

• Throttle open E22-F023HPCS TEST RTN TO SUPP POOL Standard: Opens E22-F023 by turning its handswitch on P601 clockwise in the OPEN direction and holding while observing red light on and green light off.

Cue: As Indicated Notes: Valve is controlled from P601-16C Observes CST Level lowering and Suppression Pool Level rising on P870 Standard: Checks CST Level and Suppression Pool Level on P870.

Cue: As Indicated Notes: The candidate may use any of thefollowing indications:

E30-LR-R600A P870 4B Suppression Pool Level E30-LR-R600B P870 10B Suppression Pool Level P11-LI-R601 P870 5B CST Level SPDS for Suppression Pool Level When Suppression Pool Level has been raised to the satisfaction of the Evaluator, the Evaluator may terminate the JPM.

Task Standard(s):

Suppression Pool level is rising using HPCS gravity flow.

Name: _________________________________Time Start: _______Time Stop: _______

Page 137 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E2215 Revision: 0 Page: 138 of 257 JOB PERFORMANCE MEASURE Page 138 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-E2215 Revision: 0 Page: 139 of 257 JOB PERFORMANCE MEASURE E22 Task 15: Raise Suppression Pool Level using RCIC/HPCS Follow-Up Questions & Answers:

Comments:

Page 139 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-G3311 Revision: 00 Page: 140 of 257 JOB PERFORMANCE MEASURE Raise Suppression Pool Level using RCIC Give this page to the student Initial Condition(s):

• The plant is operating at 100% power.

• Suppression Pool Water Level is low due to a leak in RHR C Pump Room.

• Standby Service Water A is operating.

• Emergency Operating Procedure 3 has been entered.

• Suppression Pool Makeup is out of service.

Initiating Cue(s):

• You have been directed to perform a controlled startup of RCIC and raise Suppression Pool water level to the normal band using RCIC.

Page 140 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-G3311 Revision: 00 Page: 141 of 257 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

OPERATOR TRAINING TITLE:

Align RWCU for Vessel Level Control New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: NEW JPM; Modified from GJPM-RO-G3301.

THIS DOCUMENT REPLACES: N/A REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )

Prepared By:

• • Preparer Date Ops Review++:

Technical Reviewer (e.g., SME, line management) Date Validated By:

Training Representative Date Approved By:

+

Discipline Training Supervisor Date Approval Date:*

• Indexing Information

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

+

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

++

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

FLEET/REGIONAL PROGRAM CONCURRENCE:

Fleet ENS ENN Not Applicable DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS BY RM Page 141 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-G3311 Revision: 00 Page: 142 of 257 JOB PERFORMANCE MEASURE TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)

Page 142 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-G3311 Revision: 00 Page: 143 of 257 JOB PERFORMANCE MEASURE Generic Instructions

1. Standards and cues for valve operation:

a. MOVs:

1) "Turn the valve's handswitch on (panel #)(section#, as applicable) in the (clockwise or counter-clockwise) direction and observe that the valve's red light is (energized or de-energized) and its green light is (energized or de-energized)".

b. Manual valves

1) "Turn the valve's handwheel (or other manual operating device) in the (clockwise or counter-clockwise) direction until resistance is felt."

2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.

3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.

4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator.

5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)

6. Obtain Shift Management's permission before opening any control panel or compartment. Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).

7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).

8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.

Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.

Page 143 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-G3311 Revision: 00 Page: 144 of 257 JOB PERFORMANCE MEASURE G33 Task 11: Align RWCU for Vessel Level Control Setting: Simulator Type: RO Task: CRO-G33/36-009 K&A: 204000 A1.01 - 3.1/3.2; A1.04 - 2.8/2.8; A4.02 - 2.9/2.9 A4.06- 3.0/2.9 295008 AA1.02 - 3.3/3.3; AA2.03 - 2.9/3.0 Safety Function: 2 Time Required: 15 minutes Time Critical: No Faulted: YES Performance: Actual Reference(s): 04-1-01-G33-1 Handout(s): 04-1-01-G33-1

1. Manipulations: 11

1. Critical Steps: 7 Group: 2 Simulator / Low Power Simulator Setups:

• IC

• Ensure RWCU is operatingin Pre-Pump mode.

• Ensure G33-F033 contrtoller G33-R606 is set at 0%.

• Insert malfunction o di_1G33-M612 P680/11C G33-F046 CLOSE o di_1G33-M625 P680/11C G33-F041 CLOSE Safety Concerns:

• None Page 144 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-G3311 Revision: 00 Page: 145 of 257 JOB PERFORMANCE MEASURE G33 Task 11: Align RWCU for Vessel Level Control Initial Condition(s):

• The plant is in mode 2 with coolant temperature approximately _140_ degrees F.

• Plant startup is in progress.

• Component Cooling Water is in operation.

• RWCU is in Pre-Pump mode of operation with two pumps and two filters in service.

• Radiation Protection has been notified.

Initiating Cue(s):

• You have been directed to align RWCU for blowdown to the Main Condenser at 60 gpm.

• Other operators will control other plant parameters.

Page 145 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-G3311 Revision: 00 Page: 146 of 257 JOB PERFORMANCE MEASURE G33 Task 11: Align RWCU for Vessel Level Control Notes

1. All controls will be from panels P680 and P870 in the Main Control Room.

Task Overview:

This task aligns Reactor Water Cleanup for reactor vessel level control using blowdown to the Main Condenser/Radwaste. This action is performed during reactor startup/heatup to control reactor water level.

Page 146 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-G3311 Revision: 00 Page: 147 of 257 JOB PERFORMANCE MEASURE G33 Task 11: Align RWCU for Vessel Level Control Tasks: critical tasks are underlined, italicized and denoted by (*)

Note: Sequence is critical for critical tasks unless otherwise noted.

• Adjust G33-F033, RWCU SYS BLWDN F/D CONT VLV to 10 % open.

Standard: Adjusts G33-F033 to 10% open on controller G33-R606 by placing the controller in MANUAL and opening to indicated 10% on the horizontal meter.

Cue: As Indicated Notes: Indications are on P680 section 11D.

Place NSSSS INBD MOV TEST switch to TEST.

Standard: On P601 section 18B places the keylock switch for NSSSS INBD MOV TEST to TEST clockwise and observes annunciator Rx Div 2 Isol Sys OOSVC is received P601-19A-G3.

Cue: As Indicated Notes:

• Open or check open G33-F028, RWCU BLWDN CTMT INBD ISOL.

Standard: Opens G33-F028, RWCU BLWDN CTMT INBD ISOL by rotating the key lock switch clockwise on P680 and observing red light on green light off.

Cue: As Indicated Notes: Pushbutton is located on P680 section 11C.

Page 147 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-G3311 Revision: 00 Page: 148 of 257 JOB PERFORMANCE MEASURE Place NSSSS OUTBD MOV TEST switch to TEST.

Standard: On P601 section 19B places the keylock switch for NSSSS OUTBD MOV TEST to TEST clockwise and observes annunciator Rx Div 1 Isol Sys OOSVC is received P601-19A-H3.

Cue: As Indicated Notes:

• Open or check open G33-F034, RWCU BLWDN CTMT OUTBD ISOL.

Standard: Opens G33-F034, RWCU BLWDN CTMT OUTBD ISOL by rotating the key lock switch clockwise on P680 and observing red light on green light off.

Cue: As Indicated Notes: Pushbutton is located on P680 section 11C.

• Open or check open G33-F046, RWCU BLWDN TO MN CNDSR.

Standard: Opens G33-F046, RWCU BLWDN TO MN CNDSR by depressing the OPEN pushbutton on P680 and observing red light on green light off.

Cue: As Indicated Notes: Pushbutton is located on P680 section 11C.

G33-F046 will not change position when the pushbutton is depressed.

Candidate should inform the Control Room Supervisor of this malfunction. AS CRS, CUE candidate to attempt to use the BYPASS Valve G33-F041.

Page 148 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-G3311 Revision: 00 Page: 149 of 257 JOB PERFORMANCE MEASURE

• Open or check open G33-F041, RWCU BLWDN TO MN CNDSR BYP.

Standard: Opens G33-F041, RWCU BLWDN TO MN CNDSR BYP by depressing the OPEN pushbutton on P680 and observing red light on green light off.

Cue: As Indicated Notes: Pushbutton is located on P680 section 11C.

G33-F041 will not change position when the pushbutton is depressed.

Candidate should inform the Control Room Supervisor of this malfunction. AS CRS, CUE candidate to change the flowpath to blowdown to Radwaste.

Maintenance will be contacted to investigate the problems with G33-F041 and F046.

• Open G33-F035, RWCU BLWDN TO RADWST.

Standard: Opens G33-F035, RWCU BLWDN TO RADWST by depressing the OPEN pushbutton on P680 and observing red light on green light off.

Cue: As Indicated Notes: Pushbutton is located on P680 section 11C.

• Adjust G33-F033, RWCU SYS BLWDN F/D CONT VLV to attain 60 gpm flow as indicated on G33-FI-R602. Opening G33-F031, RWCU BLWDN ORF BYP VLV to obtain additional flow as necessary.

Standard: Adjusts G33-F033, RWCU SYS BLWDN F/D CONT VLV to attain 60 gpm flow as indicated on G33-FI-R602. Opening G33-F031, RWCU BLWDN ORF BYP VLV to obtain additional flow as necessary Cue: As Indicated Notes: Indications are on P680 section 11D.

Candidate may request permission to throttle G33-F042 closed to obtain desired flow. If so, CUE candidate to throttle G33-F042. Candidate may elect to open G33-F031 to obtain additional flow. Either of these methods are acceptable.

Page 149 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-G3311 Revision: 00 Page: 150 of 257 JOB PERFORMANCE MEASURE Place NSSSS OUTBD MOV TEST switch to NORM.

Standard: On P601 section 19B places the keylock switch for NSSSS OUTBD MOV TEST to NORM counter-clockwise and observes annunciator Rx Div 1 Isol Sys OOSVC clears P601-19A-H3.

Cue: As Indicated Notes:

NOTE: Order between INBD and OUTBD is not essential.

Place NSSSS INBD MOV TEST switch to NORM.

Standard: On P601 section 19B places the keylock switch for NSSSS INBD MOV TEST to NORM counter-clockwise and observes annunciator Rx Div 2 Isol Sys OOSVC clears P601-19A-G3.

Cue: As Indicated Notes:

NOTE: Order between INBD and OUTBD is not essential.

Candidate may elect to leave MOV Test Switches in TEST. This is acceptable.

Task Standard(s):

RWCU is aligned to blow down the reactor to Radwaste at 60 gpm as indicated on G33-R602.

Name: _________________________________Time Start: _______Time Stop: _______

Page 150 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-G3311 Revision: 00 Page: 151 of 257 JOB PERFORMANCE MEASURE G33 Task 11: Align RWCU for Vessel Level Control Follow-Up Questions & Answers:

Comments:

Page 151 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 152 of 257 JOB PERFORMANCE MEASURE Align RWCU for Vessel Level Control Give this page to the student Initial Condition(s):

• The plant is in mode 2 with coolant temperature approximately _140_ degrees F.

• Plant startup is in progress.

• Component Cooling Water is in operation.

• RWCU is in Pre-Pump mode of operation with two pumps and two filters in service.

• Radiation Protection has been notified.

Initiating Cue(s):

• You have been directed to align RWCU for blowdown to the Main Condenser at 60 gpm.

• Other operators will control other plant parameters.

Page 152 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 153 of 257 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

OPERATOR TRAINING TITLE:

Distribute Loads between ST-11 and ST-21 New Material Minor Revision Major Revision Cancellation REASON FOR REVISION: New JPM THIS DOCUMENT REPLACES: N/A REVIEW / APPROVAL (Print Name): TEAR Approval (TEAR # )

Prepared By:

• • Preparer Date Ops Review++:

Technical Reviewer (e.g., SME, line management) Date Validated By:

Training Representative Date Approved By:

+

Discipline Training Supervisor Date Approval Date:*

• Indexing Information

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

+

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

++

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

FLEET/REGIONAL PROGRAM CONCURRENCE:

Fleet ENS ENN Not Applicable DATE INITIAL RECEIPT RETURNED FOR RETURN RECEIPT FINAL ACCEPTANCE TRANSMITTED BY RM CORRECTIONS BY RM Page 153 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 154 of 257 JOB PERFORMANCE MEASURE TO RM (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIAL) (DATE/INITIALS)

Page 154 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 155 of 257 JOB PERFORMANCE MEASURE Generic Instructions

1. Standards and cues for valve operation:

a. MOVs:

1) "Turn the valve's handswitch on (panel #)(section#, as applicable) in the (clockwise or counter-clockwise) direction and observe that the valve's red light is (energized or de-energized) and its green light is (energized or de-energized)".

b. Manual valves

1) "Turn the valve's handwheel (or other manual operating device) in the (clockwise or counter-clockwise) direction until resistance is felt."

2. The Evaluator should indicate simulated analog gauge readings by pointing a pen or equivalent to the intended place on the gauge.

3. Other methods of simulating control, operation and data collection is at the discretion of the Evaluator.

4. It is expected that the candidate shall locate controlled copies of any required procedures and describe how copies of these procedures would be prepared for use in the field. Only at this time should the evaluator give the candidate previously prepared copies of the procedure(s). This entire procedure need only be performed or simulated once during the entire exam. These activities are not required for JPMs conducted in the Simulator.

5. Consideration of electrical safety must be made during the performance of certain tasks involving electrical circuits and circuit breakers. The performer should be aware that working on or near energized equipment requires, at a minimum, wearing 100% cotton clothing and low voltage (Class 0) gloves while removing or securing shock hazards such as chains, jewelry, watches and metal-framed eyeglasses. Operating or racking circuit breakers may require additional PPE. Details can be found in Att. 2 of the Electrical Safety Rulebook and General Operating procedure 04-S-04-2 (Operation of Electrical Circuit Breakers)

6. Obtain Shift Management's permission before opening any control panel or compartment. Avoid placing any tools, flashlights, pointing devices or any part of your body inside the panel or compartment in a manner that could disturb the operation of any component within or potentially result in an electric shock).

7. Use of lasers as a pointing tool requires Engineering's prior approval of the specific tool for safe use in the Control area. (specifically, the laser's emissions must be verified as not interfering with any component's intended operation or function).

8. During activities within the CAA, consideration must be given to area dose rates. When in a posted Radiation Area, check your EAD for dose rates and minimize time spent in the area. Entry into High Radiation Areas or Contamination Areas is prohibited.

Under no circumstances is any candidate allowed to operate any equipment outside the simulator without the permission of the Evaluator and Shift Management.

Page 155 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 156 of 257 JOB PERFORMANCE MEASURE R27 Task 32: Distribute Loads between ST-11 and ST-21 Setting: Simulator Type: RO Task: CRO-R20/27-003; CRO-R20/27-008 K&A: 262001 A4.01 - 3.4/3.7; A4.02 - 3.4/3.4; A4.04 - 3.6/3.7; A4.05 - 3.3/3.3; 2.1.30 - 3.9/3.4; 2.1.31 - 4.2/3.9 295003 AA1.01 - 3.7/3.8; AA1.02 - 4.2/4.3; AA2.05 - 3.9/4.2 Safety Function: 6 Time Required: 30 minutes Time Critical: No Faulted: YES Performance: Actual Reference(s): 04-1-01-R21-11; 04-1-01-R21-12; 04-1-01-R21-13; 04-1-01-R21-14; 04-1-01-R21-15; 04-1-01-R21-16; 05-1-02-1-I-4 Handout(s): 04-1-01-R21-12; 04-1-01-R21-13; 04-1-01-R21-15

1. Manipulations: 14

1. Critical Steps: 13 Group: 1 Simulator Simulator Setups:

• ANY IC

• Transfer 12HE; 13AD; and 15AA to ST-21

• In the computer cross tie 18AG and 28AG with 28AG supplying 18AG

• Insert Malfunction r21133b for Service Transformer 21 Lockout on Trigger 2

• Insert Malfunction n41140b for Diesel Generator 12 fail to start on Trigger 2 Safety Concerns:

• None Page 156 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 157 of 257 JOB PERFORMANCE MEASURE R27 Task 32: Distribute Loads between ST-11 and ST-21 Initial Condition(s):

• All electrical buses are being supplied from Service Transformer 21.

• Preventive maintenance on Service Transformer 11 is complete and Entergy -

Mississippi has released the transformer.

• GGNS 34.5 KV switchyard has been restored to a normal configuration with ESF and BOP Transformers energized.

• All Red Tags are cleared.

• All circuit breakers are racked in.

Initiating Cue(s):

• You have been directed to align BOP buses 12HE, 13AD and 15AA in their normal configuration.

• Another operator will transfer bus 18AG.

Notes

1. All controls will be from panels P864 and P807 in the Main Control Room.

Task Overview:

This task transfers buses from all being supplied by a single Service Transformer to a preferred alignment. Following the transfer the on-coming Service Transformer will experience a lockout. Additionally the ESF bus will not be automatically energized by the Diesel Generator requiring operator action to align to an offsite power source.

This task implements SOER 2002-3 Large Power Transformer Reliability.

Page 157 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 158 of 257 JOB PERFORMANCE MEASURE R27 Task 32: Distribute Loads between ST-11 and ST-21 Tasks: critical tasks are underlined, italicized and denoted by (*)

NOTE: The order in which buses are transferred/restored is NOT critical.

BUS 12HE Ensure XFMR 11B energized up to Bus Feeder Breaker 252-1201 by checking the following:

Check closed disconnect J5234 FDR to XFMR ST-11 Standard: Observes disconnect indication on P807 for J5234 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-3B.

Check closed circuit breaker 552-1105 XFMR ST-11 FDR to bus 11R Standard: Observes circuit breaker indication on P807 for 552-1105 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-2C.

Check indicator R25-R603 34.5 bus voltage Standard: Observes indicator R25-R603 on P807 section 1B indicates approximately 34.5KV.

Cue: As Indicated Notes: Indication is on P807-1B.

Check closed circuit breaker 552-1101 11R FDR to bus 12R Standard: Observes circuit breaker indication on P807 for 552-1101 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-1C.

Page 158 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 159 of 257 JOB PERFORMANCE MEASURE Check closed disconnect 589-1101D BOP XFMR 11B disconnect Standard: Observes disconnect indication on P807 for 589-1101D red light on green light off.

Cue: As Indicated Notes: Indication is on P807-1C.

Check ENERGIZED status light is on Standard: Observes ENERGIZED status light (purple light) is on for 252-1201 on P807.

Cue: As Indicated Notes: Indication is on P807-2C.

• Close 252-1201 XFMR 11B FDR to bus 12HE Standard: Closes circuit breaker 252-1201 by turning its handswitch on P807 clockwise in the CLOSE direction and holding while observing Red light on and green light off.

Cue: As Indicated Notes: Circuit Breaker is controlled from P807-2C Observes circuit breaker 252-1208 opens Standard: Checks circuit breaker 252-1208 opens on P807 by observing its green light on and its red light off.

Cue: As Indicated Notes: Circuit breaker indication is located on P807-2C Page 159 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 160 of 257 JOB PERFORMANCE MEASURE BUS 13AD Ensure XFMR 11A energized up to Bus Feeder Breaker 152-1315 by checking the following:

Check closed disconnect J5234 FDR to XFMR ST-11 Standard: Observes disconnect indication on P807 for J5234 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-3B.

Check closed circuit breaker 552-1105 XFMR ST-11 FDR to bus 11R Standard: Observes circuit breaker indication on P807 for 552-1105 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-2C.

Check indicator R25-R603 34.5 bus voltage Standard: Observes indicator R25-R603 on P807 section 1B indicates approximately 34.5KV.

Cue: As Indicated Notes: Indication is on P807-1B.

Check closed circuit breaker 552-1101 11R FDR to bus 12R Standard: Observes circuit breaker indication on P807 for 552-1101 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-1C.

Page 160 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 161 of 257 JOB PERFORMANCE MEASURE Check closed disconnect 589-1101C BOP XFMR 11A disconnect Standard: Observes disconnect indication on P807 for 589-1101C red light on green light off.

Cue: As Indicated Notes: Indication is on P807-1C.

Check ENERGIZED status light is on Standard: Observes ENERGIZED status light (purple light) is on for 152-1315 on P807.

Cue: As Indicated Notes: Indication is on P807-1C.

• Close 152-1315 XFMR 11A FDR to bus 13AD Standard: Closes circuit breaker 152-1315 by turning its handswitch on P807 clockwise in the CLOSE direction and holding while observing Red light on and green light off.

Cue: As Indicated Notes: Circuit Breaker is controlled from P807-1C Observes circuit breaker 152-1302 opens Standard: Checks circuit breaker 152-1302 opens on P807 by observing its green light on and its red light off.

Cue: As Indicated Notes: Circuit breaker indication is located on P807-1C Page 161 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 162 of 257 JOB PERFORMANCE MEASURE BUS 15AA Ensure XFMR ESF 11 energized up to Bus Feeder Breaker 152-1514 by checking the following:

Check closed disconnect J5234 FDR to XFMR ST-11 Standard: Observes disconnect indication on P807 for J5234 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-3B.

Check closed circuit breaker 552-1105 XFMR ST-11 FDR to bus 11R Standard: Observes circuit breaker indication on P807 for 552-1105 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-2C.

Check indicator R25-R603 34.5 bus voltage Standard: Observes indicator R25-R603 on P807 section 1B indicates approximately 34.5KV.

Cue: As Indicated Notes: Indication is on P807-1B.

Check closed circuit breaker 552-1104 11R FDR to XFMR ESF11 Standard: Observes circuit breaker indication on P807 for 552-1104 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-1C.

Page 162 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 163 of 257 JOB PERFORMANCE MEASURE Check closed circuit breaker 152-1901 FDR FRM XFMR ESF 11 Standard: Observes circuit breaker indication on P807 for 152-1901 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-1C.

Check ENERGIZED status light is on Standard: Observes ENERGIZED status light (purple light) is on for 152-1514 on P864.

Cue: As Indicated Notes: Indication is on P864-1C.

• Turn on the Sync switch for breaker 152-1514 BUS 15AA FDR FRM XFMR ESF 11 Standard: Turns on Sync Switch for 152-1514 by turning its handswitch on P864 clockwise in the ON direction.

Cue: As Indicated Notes: Sync Switch is controlled from P864-1C Check sync scope comes to 12 oclock +/- 10°.

Standard: Observes sync scope comes to 12 oclock +/- 10° on for 152-1514 on P864.

Cue: As Indicated Notes: Indication is on P864-1B.

Page 163 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 164 of 257 JOB PERFORMANCE MEASURE

• Close 152-1514 BUS 15AA FDR FRM XFMR ESF 11 Standard: Closes circuit breaker 152-1514 by turning its handswitch on P864 clockwise in the CLOSE direction and holding while observing Red light on and green light off.

Cue: As Indicated Notes: Circuit Breaker is controlled from P864-1C Observes circuit breaker 152-1511 opens Standard: Checks circuit breaker 152-1511 opens on P864 by observing its green light on and its red light off.

Cue: As Indicated Notes: Circuit breaker indication is located on P864-1C Turn off the Sync switch for breaker 152-1514 BUS 15AA FDR FRM XFMR ESF 11 Standard: Turns off Sync Switch for 152-1514 by turning its handswitch on P864 counter-clockwise in the OFF direction.

Cue: As Indicated Notes: Sync Switch is controlled from P864-1C Page 164 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 165 of 257 JOB PERFORMANCE MEASURE ONCE the third bus is transferred (12HE, 13AD and 15AA), INSERT malfunctions on Trigger 1.

r21133b - Lockout Service Transformer 21 n41140b - Failure of Diesel Generator 12 (Division 2 DG)

This results in a loss of power to buses 11HD, 14AE, 16AB, and 17AC.

Bus 17AC will automatically re-energize from DG-13.

Per the Loss of AC Power ONEP (05-1-02-I-4) re-energize buses from available offsite feeders and/or DG.

The order of bus re-energization is NOT Critical.

Page 165 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 166 of 257 JOB PERFORMANCE MEASURE BUS 11HD Ensure XFMR 11B energized up to Bus Feeder Breaker 252-1101 by checking the following:

Check closed disconnect J5234 FDR to XFMR ST-11 Standard: Observes disconnect indication on P807 for J5234 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-3B.

Check closed circuit breaker 552-1105 XFMR ST-11 FDR to bus 11R Standard: Observes circuit breaker indication on P807 for 552-1105 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-2C.

Check indicator R25-R603 34.5 bus voltage Standard: Observes indicator R25-R603 on P807 section 1B indicates approximately 34.5KV.

Cue: As Indicated Notes: Indication is on P807-1B.

Check closed circuit breaker 552-1101 11R FDR to bus 12R Standard: Observes circuit breaker indication on P807 for 552-1101 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-1C.

Page 166 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 167 of 257 JOB PERFORMANCE MEASURE Check closed disconnect 589-1101D BOP XFMR 11B disconnect Standard: Observes disconnect indication on P807 for 589-1101D red light on green light off.

Cue: As Indicated Notes: Indication is on P807-1C.

Check ENERGIZED status light is on Standard: Observes ENERGIZED status light (purple light) is on for 252-1101 on P807.

Cue: As Indicated Notes: Indication is on P807-1C.

NOTE: Candidate may go directly to breaker 252-1101 handswitch and energize the bus.

• Close 252-1101 XFMR 11B FDR to bus 11HD Standard: Closes circuit breaker 252-1101 by turning its handswitch on P807 clockwise in the CLOSE direction and holding while observing Red light on and green light off.

Cue: As Indicated Notes: Circuit Breaker is controlled from P807-1C Observes circuit breaker 252-1108 opens Standard: Checks circuit breaker 252-1108 opens on P807 by observing its green light on and its red light off.

Cue: As Indicated Notes: Circuit breaker indication is located on P807-1C Page 167 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 168 of 257 JOB PERFORMANCE MEASURE

• Close supply circuit breakers for the following Load Control Centers (LCC):

_____ *LCC 11BD7 breaker 52-11701

_____ *LCC 11BD4 breaker 52-11401

_____ *LCC 11BD3 breaker 52-11301

_____ *LCC 11BD2 breaker 52-11201

_____ *LCC 21BD4 breaker 52-21401

_____ *LCC 21BD3 breaker 52-21301 Standard: Closes the above circuit breakers on H13-P807 by placing the handswitch clockwise in the CLOSE direction and holding while observing red light on and green light off.

Cue: As Indicated Notes: Circuit Breakers are controlled from P807 Page 168 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 169 of 257 JOB PERFORMANCE MEASURE BUS 14AE Ensure XFMR 11A energized up to Bus Feeder Breaker 152-1415 by checking the following:

Check closed disconnect J5234 FDR to XFMR ST-11 Standard: Observes disconnect indication on P807 for J5234 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-3B.

Check closed circuit breaker 552-1105 XFMR ST-11 FDR to bus 11R Standard: Observes circuit breaker indication on P807 for 552-1105 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-2C.

Check indicator R25-R603 34.5 bus voltage Standard: Observes indicator R25-R603 on P807 section 1B indicates approximately 34.5KV.

Cue: As Indicated Notes: Indication is on P807-1B.

Check closed circuit breaker 552-1101 11R FDR to bus 12R Standard: Observes circuit breaker indication on P807 for 552-1101 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-1C.

Page 169 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 170 of 257 JOB PERFORMANCE MEASURE Check closed disconnect 589-1101C BOP XFMR 11A disconnect Standard: Observes disconnect indication on P807 for 589-1101C red light on green light off.

Cue: As Indicated Notes: Indication is on P807-1C.

Check ENERGIZED status light is on Standard: Observes ENERGIZED status light (purple light) is on for 152-1415 on P807.

Cue: As Indicated Notes: Indication is on P807-2C.

NOTE: Candidate may go directly to breaker 252-1101 handswitch and energize the bus.

• Close 152-1415 XFMR 11A FDR to bus 14AE Standard: Closes circuit breaker 152-1415 by turning its handswitch on P807 clockwise in the CLOSE direction and holding while observing Red light on and green light off.

Cue: As Indicated Notes: Circuit Breaker is controlled from P807-2C Observes circuit breaker 152-1402 opens Standard: Checks circuit breaker 152-1402 opens on P807 by observing its green light on and its red light off.

Cue: As Indicated Notes: Circuit breaker indication is located on P807-2C Page 170 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 171 of 257 JOB PERFORMANCE MEASURE BUS 16AB There are two options for the candidate. Either Option is acceptable.

Option 1 ESF Transformer 11 Ensure XFMR ESF 11 energized up to Bus Feeder Breaker 152-1601 by checking the following:

Check closed disconnect J5234 FDR to XFMR ST-11 Standard: Observes disconnect indication on P807 for J5234 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-3B.

Check closed circuit breaker 552-1105 XFMR ST-11 FDR to bus 11R Standard: Observes circuit breaker indication on P807 for 552-1105 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-2C.

Check indicator R25-R603 34.5 bus voltage Standard: Observes indicator R25-R603 on P807 section 1B indicates approximately 34.5KV.

Cue: As Indicated Notes: Indication is on P807-1B.

Check closed circuit breaker 552-1104 11R FDR to XFMR ESF11 Standard: Observes circuit breaker indication on P807 for 552-1104 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-1C.

Page 171 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 172 of 257 JOB PERFORMANCE MEASURE Check closed circuit breaker 152-1901 FDR FRM XFMR ESF 11 Standard: Observes circuit breaker indication on P807 for 152-1901 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-1C.

Check ENERGIZED status light is on Standard: Observes ENERGIZED status light (purple light) is on for 152-1601 on P864.

Cue: As Indicated Notes: Indication is on P864-2C.

• Close 152-1601 BUS 16AB FDR FRM XFMR ESF 11 Standard: Closes circuit breaker 152-1601 by turning its handswitch on P864 clockwise in the CLOSE direction and holding while observing Red light on and green light off.

Cue: As Indicated Notes: Circuit Breaker is controlled from P864-2C Page 172 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 173 of 257 JOB PERFORMANCE MEASURE Option 2 ESF Transformer 12 Ensure XFMR ESF 12 energized up to Bus Feeder Breaker 152-1611 by checking the following:

Check closed disconnect J3885 FDR to XFMR ESF 12 Standard: Observes disconnect indication on P807 for J3885 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-1C.

Check closed circuit breaker 152-1903 FDR FRM XFMR ESF 12 Standard: Observes circuit breaker indication on P807 for 152-1903 red light on green light off.

Cue: As Indicated Notes: Indication is on P807-1C.

Check ENERGIZED status light is on Standard: Observes ENERGIZED status light (purple light) is on for 152-1611 on P864.

Cue: As Indicated Notes: Indication is on P864-2C.

• Close 152-1611 BUS 16AB FDR FRM XFMR ESF 12 Standard: Closes circuit breaker 152-1611 by turning its handswitch on P864 clockwise in the CLOSE direction and holding while observing Red light on and green light off.

Cue: As Indicated Notes: Circuit Breaker is controlled from P864-2C Page 173 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 174 of 257 JOB PERFORMANCE MEASURE Orders Turbine Building Operator to reset Bus Undervoltage Lockouts for BOP Buses 11HD and 14AE Standard: Contacts Turbine Building Operator to reset Bus Undervoltage Lockouts for buses 11HD and 14AE Cue: Turbine Building Operator is dispatched.

Notes: This action may be performed any time after the buses have been re-energized.

Task Standard(s):

BOP Buses 11HD & LCCs, 12HE, 13AD and 14AE are energized from Service Transformer 11 ESF Bus 15AA is energized from ESF Transformer 11.

ESF Bus 16AB is energized from either ESF Transformer 11 or 12.

ESF Bus 17AC is energized from Diesel Generator 13.

Name: _________________________________Time Start: _______Time Stop: _______

Page 174 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 175 of 257 JOB PERFORMANCE MEASURE Page 175 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 176 of 257 JOB PERFORMANCE MEASURE R27 Task 32: Distribute Loads between ST-11 and ST-21 Follow-Up Questions & Answers:

Comments:

Page 176 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 177 of 257 JOB PERFORMANCE MEASURE Distribute Loads between ST-11 and ST-21 Give this page to the student Initial Condition(s):

• All electrical buses are being supplied from Service Transformer 21.

• Preventive maintenance on Service Transformer 11 is complete and Entergy - Mississippi has released the transformer.

• GGNS 34.5 KV switchyard has been restored to a normal configuration with ESF and BOP Transformers energized.

• All Red Tags are cleared.

• Allcircuit breakers are racked in.

Initiating Cue(s):

• You have been directed to align BOP buses 12HE, 13AD and 15AA in their normal configuration.

• Another operator will transfer bus 18AG.

REVISION 1 2/20/2007 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 177 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 178 of 257 JOB PERFORMANCE MEASURE Appendix D Scenario Outline Form ES-D-1 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 1 Op-Test No.: Day 0 Examiners: _________________________ Operators:__________________________

_________________________ __________________________

_________________________ __________________________

Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:

1. Startup 2nd RFPT and place on Master Controller.

2. Raise Reactor Power by withdrawing control rods.

3. Respond to failed Reed Switch requiring substitute position.

4. Respond to single control rod stuck per ONEP 05-1-02-IV-1.

5. Respond to APRM D failure upscale.

6. Respond to Pressure Controller fault Reactor Pressure rising.

7. Take actions per the EOPs in response to an ATWS and mitigate the consequences of the ATWS.

8. Respond to failure of Main Steam Bypass Valves to fully function.

9. Respond to a failure of SLC to function properly.

Initial Conditions: Reactor Power is at 50 %. Plant startup is in progress following an outage.

Reactor Recirculation pumps in Fast Speed; a single Reactor Feed Pump in Three element Master Level Control; both Heater Drain Pumps are pumping forward.

INOPERABLE Equipment SRM F are INOP and bypassed.

IRMs A & H are INOP and bypassed.

APRM H is INOP due to failed downscale and is bypassed.

HPCS Pump is tagged out of service for failure of the Jockey Pump.

ESF 12 Transformer is tagged out of service for maintenance.

RPS A is on Alternate Power due to EPA circuit breaker failure.

SBGT A is operating for surveillance.

Appropriate clearances and LCOs are written.

Turnover: Continue plant startup per IOI-2. Ready for startup of RFPT B. There are scattered REVISION 1 2/20/2007 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 178 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 179 of 257 JOB PERFORMANCE MEASURE thunder showers reported in the Tensas Parish area.

Event Malf. No. Event Event No. Type* Description 1 N (RO) Place RFPT B in service on the Master Level Controller. (SOI 04 01-N21-1) 2 R (RO) Raise Reactor power using control rods to 52%. (Control Rod Pull Sheet)

REVISION 1 2/20/2007 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 179 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 180 of 257 JOB PERFORMANCE MEASURE Appendix D Scenario Outline Form ES-D-1 Scenario 1 Day 0 (Continued)

Event Malf. No. Event Event No. Type* Description 3 1 I (RO) Respond to a failed Reed Switch on control rod being moved requiring substitute position to be entered (SOI 04-1-01-C11-2) 4 2 C (RO/ Respond to single control rod immovable taking actions to BOP) move the control rod. (ONEP 05-1-02-IV-1)

TS Disarm Control Rod. Complete Technical Specification (SS) determination.

5 3 C (RO) Respond to failure of APRM D upscale. Complete TS Technical Specification determination.

(SS) (ARI 04-1-02-1H13-P680 7A-B11) 6 4 C(RO) Respond to a failure of the Reactor Pressure Control System with pressure rising.

(ARI 04-1-02-1H13-P680 9A-D2)

C (RO) Recognize a failure to scram using RPS and manually 5 scram the reactor using ATWS ARI.

M 7 6 (ALL) Respond to ATWS with partial Main Steam Bypass Valve availability. (EOP 05-1-01-EP-2A) 8 7 C Respond to a failure of Standby Liquid Control to initiate.

(BOP) (SOI 04-1-01-C41-1 and EOP 05-1-01-EP-2A)

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

- Inserts rods by manual scrams and normal rod insertion using Attachments 18, 19, and 20.

REVISION 1 2/20/2007 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 180 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 181 of 257 JOB PERFORMANCE MEASURE

- When allowed by Level / Power Control leg of EP-2A, restores injection from Condensate /

Feedwater.

- Terminates and prevents all injection except boron, CRD and RCIC when required by steps L-7 or 8 of EP-2A.

- For ATWS above 4% power, injects SLC A/B before Suppression Pool temperature reaches 110 degrees F.

REVISION 1 2/20/2007 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 181 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 182 of 257 JOB PERFORMANCE MEASURE Scenario 1 Day 0 (Continued)

Crew Turnover:

Rx is at 50% CTP.

SRMs F is bypassed.

IRMs A & H are INOP and bypassed.

APRM H is INOP and bypassed due to failed downscale.

HPCS Pump is tagged out of service for failure of the Jockey Pump.

ESF Transformer 12 is tagged out of service for Entergy -Mississippi maintenance.

RPS A is on Alternate Power due to EPA circuit breaker failure.

SBGT A is operating for surveillance 06-OP-1T48-M-0001 section 5.2.11 allowing the System Engineer to obtain data.

Hydrogen Water Chemistry and Alternate Cooling Tower are out of service.

Both Circ Water Pumps are in service.

Appropriate clearances and LCOs are written.

Continue plant startup per IOI-2 step 5.16.1.

Ready for startup of RFPT B.

Control Rod movement is at step 120b for the Startup Sequence.

REVISION 1 2/20/2007 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 182 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 183 of 257 JOB PERFORMANCE MEASURE Plant EOOS factor is 7.3 YELLOW.

There are scattered thunderstorms reported in the Tensas Parish area.

REVISION 1 2/20/2007 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 183 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 184 of 257 JOB PERFORMANCE MEASURE Simulator Setup: (Scenarios may be setup and shot into encrypted ICs and Password protected.)

Start the process from a new simulator load.

Reset to IC-13.

Verify or perform the following:

IC: 13 OOS: APRM H (Place in Bypass w/ Caution tag)

IRMs A & H (Place in Bypass w/ Caution tag)

SRMs F (Place in Bypass w/ Caution tag)

RPS A (Transfer to Alternate Power and reset RPS A w/ Caution tag)

Manually Initiate SBGT A HPCS and HPCS Jockey Pump OOS (Place HPCS OOSVC to OOSVC and place tags on HPCS Pump and Jockey Pump HS)

ESF XFMER 12 (Place tag on J3885, 152-1903, 152-1904, 152-1905, 152-1511, 152-1611, 152-1704 HS)

Active malfunctions: c51002f SRM F incorporated into present simulator load c51005a IRM A incorporated into present simulator load c51005h IRM H incorporated into present simulator load c51010h APRM H downscale c71077a RPS A MG failure (Normal EPA OOS) z022022_36_37 Control rod 36-37 stuck c11164@20% CRD Hydraulic Block c41f004a_d SLC Squib fail to fire c41f004b_d SLC Squib fail to fire Active Remote Functions: p81218 J3885 115KV Disconnect OPEN e22644 HPCS Pump BKR OUT e22646 HPCS JKY pump breaker OPEN 152-1511 lo_1r21m601a_g Bus 15AA FDR FM ESF XFMR 12 OFF di_1r21m601ap864/01c Bus 15AA FDR FM ESF XFMR 12 TRIP 152-1611 lo_1r21m601b_g Bus 16AB FDR FM ESF XFMR 12 OFF REVISION 1 2/20/2007 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 184 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 185 of 257 JOB PERFORMANCE MEASURE di_1r21m601bp864/02c Bus 16AB FDR FM ESF XFMR 12 TRIP 152-1704 lo_1e22m709_g 17AC FDR FM ESF 12 OFF di_1e22m709p601/16c 17AC FDR FM ESF 12 OFF 152-1903 lo_1r21m623_g Bus 15AA/16AB/27AC FDR FM ESF XFMR 12 OFF di_1r21m623p807/01c Bus 15AA/16AB/27AC FDR FM ESF XFMR 12 TRIP 152-1904 lo_1r21m624_g Bus 17AC/25AA/26AB FDR FM ESF XFMR 12 OFF di_1r21m624p807/01c Bus 17AC/25AA/26AB FDR FM ESF XFMR 12 TRIP 152-1905 lo_1r21m637_g SWYD XFMR T3 FDR FM ESF XFMR 12 OFF di_1r21m637p807/01c SWYD XFMR T3 FDR FM ESF XFMR 12 TRIP Active Case File: cae sgtsai.cae SBGT A operating for surveillance Active overrides: None Pending overrides: None Pending malfunctions: c51009d APRM D failed upscale (TRG 4) c71162 Failure to Scram Manual and Automatic (ATWS ARI Available)

(TRG 5) tc079 3 second time delay ramp to 0% over 15 seconds Pressure Control Failure pressure rising (TRG 5) rci035 Reed switch failed open on selected control rod (TRG 2)

Pending component malfunctions: None Trigger files: Trigger 2 Reed Switch failure on selected control rod Trigger 4 APRM D Failed upscale Trigger 5 Pressure Controller Failure - Pressure rising COMPONENT PANEL INDICATION or SIMULATOR STATUS DONE CONTROL CODE APRM H c51010h downscale HPCS PUMP P601-16C e22644_OUT OUT REVISION 1 2/20/2007 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 185 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 186 of 257 JOB PERFORMANCE MEASURE HPCS Jockey Pump P601-16C e22646_OPEN OPEN RPS A on Alternate P610 Handswitch c71077a ALT 152-1511 P864-1C Green light lo_1r21m601a_g OFF P864-1C Handswitch di_1r21m601a STOP 152-1611 P864-2C Green light lo_1r21m601b_g OFF P864-2C Handswitch di_1r21m601b STOP 152-1704 P601-16C Green light lo_1e22m709_g OFF P601-16C Handswitch di_1e22m709 STOP 152-1903 P807-1C Green light lo_1r21m623_g OFF P807-1C Handswitch di_1r21m623 STOP 152-1904 P807-1C Green light lo_1r21m624_g OFF P807-1C Handswitch di_1r21m624 STOP 152-1905 P807-1C Green light lo_1r21m637_g OFF P807-1C Handswitch di_1r21m637 STOP J3885 115 KV Disconnect P807-1C Green Light p81218 OPEN Bypass Division 2 APRM Bypass Joystick to APRM H position.

IRMs A and H, SRM F are bypassed in the IC setup for Cycle 15.

Verify or perform the following:

Verify Reactor Power is above the 75% rod line.

Open Circuit Breakers 152-1903, 1904, 1905, 1511, 1611, and 1704 Place HPCS OOSVC handswitch to OOSVC.

Place RPS A on Alternate Power and RESET RPS A logic on P680.

Verify SBGT A is operating.

Startup all PDS / SPDS screens. Clear any graphs and trends off of SPDS.

Setup the presently used cyclops display and verify it is functional.

Ensure the correct startup sequence is available at the P680 for the present IC.

REVISION 1 2/20/2007 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 186 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 187 of 257 JOB PERFORMANCE MEASURE Install turnover guide, red tag, and LCO paperwork as applicable.

Advance all chart recorders and ensure all pens are inking properly.

(APRM chart recorders must be turned on and settings for scales on pens 0 - 125 scale)

Place tags on ALL circuit breakers associated with the ESF 12 Transformer outage.

Place tags on APRM H, IRM A & H and SRMS F Joysticks.

Place tags on HPCS Pump and Jockey Pump handswitches.

Adjust APRM Gains.

REVISION 1 2/20/2007 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 187 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 188 of 257 JOB PERFORMANCE MEASURE SIMULATOR OPERATION SCENARIO 1 Once simulator is reinitialized and setup complete take the simulator out of Freeze.

Once the Crew has taken control note the simulator time.

Place RFPT B on Master Level controller Start RFPT B per SOI 04-1-01-N21-1 section 4.5.5 and 4.6.5.

Cues:

If asked, as Turbine Building Operator close RFPT Steam line drains on P175.

If asked, biasing on the Reactor Feed Pumps should be balanced.

Cue: The CRS to raise reactor power to 55% for Reactor Engineering data.

When asked open the RFPT steam line drains with remote functions fw102 and fw104.

Raise Reactor Power using control rods The RO will raise reactor power by withdrawing control rod per the Control Rod Movement Sequence.

Cues:

If asked, as Reactor Engineer withdraw control rods per the movement sequence beginning at step 120b.

After the first couple of control rod movements activate TRIGGER 2. This will insert the malfunction on the selected control rod.

Open Reed Switch on selected control rod The RO will receive a control rod block on selected control rod due to a failed reed switch open.

This will most likely be control rod 36-13 if in gang movement.

REVISION 1 2/20/2007 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 188 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 189 of 257 JOB PERFORMANCE MEASURE The RO will enter substitute position from the other channel of RCIS Position Indication.

Cues:

If asked, as I&C the other channel of Rod Position Data is good and may be substituted.

The SS may initiate a potential LOC TR for TS 3.1.3 to track SR 3.1.3.1 position indication failure.

Remove Malfunction when substitution is complete.

REVISION 1 2/20/2007 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 189 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 190 of 257 JOB PERFORMANCE MEASURE Immovable Control Rod When the RO gets to control rod 36-37 the control rod will NOT move. This will prompt entry into ONEP 05-1-02-IV-1 Control Rod/Drive Malfunctions section 3.5.

Cues:

If asked, as Reactor Engineering raising CRD Drive Pressure is acceptable.

If asked, as Auxiliary Building Operator report CRD Drive Filter DP 17 psid, Suction Filter DP is 2.1 psid, Backwash Filter DP is 2.0 psid and the CRD Flow Control Station is functioning properly.

If asked, as Reactor Engineering about individually scramming the control rod inform the CRS that analysis on the effects needs to be performed hold reactor power at this point. Until further analysis individually scramming the control rod is NOT acceptable.

If asked, report as Auxiliary Building Operator Local Drive Water Pressure gages are tagged out for a work order to replace the gages.

SS should consult Tech Specs for TS 3.1.3 and declare the control rod INOP.

SS may consider a Potential LCO for TS 3.1.4 Scram Times APRM D failure Upscale One minute after Reactor Engineering cue, activate TRIGGER 4.

Cues:

If asked, report as I&C the APRM is hard failed upscale with no apparent cause and it will require further investigation.

SS should direct un-bypassing APRM H and bypassing APRM D to clear the scram signal and take the Control Rod Withdrawal Block. Then direct resetting RPS B.

SS will consult Tech Specs for 3.3.1.1 Reactor Protection System Instrumentation is NOT met for RPS B and 3.3.2.1 Control Rod Block Instrumentation is met but a Potential LCO is appropriate.

REVISION 1 2/20/2007 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 190 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 191 of 257 JOB PERFORMANCE MEASURE If APRM H is to be left bypassed with APRM D failed upscale, TR 3.3.2.1 Condition E applies.

REVISION 1 2/20/2007 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 191 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 192 of 257 JOB PERFORMANCE MEASURE Reactor Pressure Control System Failure - RPV Pressure Rising One minute after the Tech Spec call, activate TRIGGER 5.

This will cause a pressure controller failure raising reactor pressure and initiating a Reactor Scram signal (Automatic RPS actuation will fail however the RO can insert a manual reactor scram signal to RPS and subsequent ATWS due to a CRD Scram Discharge Volume Hydraulic Block.

The Main Steam Bypass valves will be available for pressure control for 3 minutes after the Manual Bypass Jack is energized to open Main Steam Bypass Valves.

This is an ATWS with limited Main Steam Bypass Valves available for Reactor Pressure Control.

EP Attachments which may be requested:

Attachment 12 Defeat RHR Shutdown Cooling interlocks 6 minutes to DONE Attachment 19 Defeat RPS 4 minutes to DONE Attachment 20 Defeat RCIS 5 minutes to DONE Attachment 8 Defeat MSIV isolations 9 minutes to DONE If Attachment 8 is requested early by itself - 3 minutes to DONE Attachment 18 Defeat ATWS ARI 3 minutes to DONE REVISION 1 2/20/2007 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 192 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 193 of 257 JOB PERFORMANCE MEASURE TERMINATION Once Control Rods are being inserted and the Lead Evaluator concurs, the scenario may be terminated.

Critical Tasks

- Inserts rods by manual scrams and normal rod insertion using Attachments 18, 19, and 20.

- When allowed by Level / Power Control leg of EP-2A, restores injection from Condensate /

Feedwater.

- Terminates and prevents all injection except boron, CRD and RCIC when required by steps L-7 or L-8 of EP-2A.

- For ATWS above 4% power, injects SLC A/B before Suppression Pool temperature reaches 110 degrees F.

Emergency Plan Procedure - Emergency Action Level Classification Site Area Emergency based on 10-S-01-1 Attachment I EAL SS3 REVISION 1 2/20/2007 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 193 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 194 of 257 JOB PERFORMANCE MEASURE Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __1___ Event No.: ___1__

Event

Description:

Start RFPT B and place on Master Controller (SOI 04-1-01-N21-1)

Time Position Applicant's Actions or Behavior RO Starts up RFPT B and places control of the feed pump on the Master Level Controller SOI 04-1-01-N21-1.

BOP Monitors Reactor Power, Level and Pressure.

Op-Test No.: _____ Scenario No.: __1___ Event No.: ___2__

Event

Description:

Raise Reactor power by withdrawing control rods.

(Control Rod Movement Sequence)

Time Position Applicant's Actions or Behavior SS Conducts Reactivity Brief on expectations for Control Rod movement.

RO Withdraws control rods in accordance with Control Rod Movement Sequence to raise reactor power.

BOP Peer Check Control Rod selection and movement and assist in monitoring Reactor Level, Pressure and Power.

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 194 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 195 of 257 JOB PERFORMANCE MEASURE Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __1___ Event No.: ___3__

Event

Description:

Control Rod withdrawal block due to failed Rod Position indication Enter substitute position to clear fault.

(ARI 04-1-02-1H13-P680 4A2-C5; SOI 04-1-01-C11-2)

Time Position Applicant's Actions or Behavior RO Observes Control Rod Withdrawal Block and loss of position indication for the selected control rod. (ARI 04-1-02-1H13-P680 4A2-C5)

SS Acknowledges the problem and orders entering substitute position to allow movement of the control rod to a position with good indication.

SS May order a potential LCOTR for TS 3.1.3 due to a failed channel.

RO Enters Substitute Position for RCIS on the affected Control Rod and moves the control rod per the movement sequence. (SOI 04-1-01-C11-2)

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 195 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 196 of 257 JOB PERFORMANCE MEASURE Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __1__ Event No.: ___4_

Event

Description:

Control rod 36-37 immovable (ONEP 05-1-02-IV-1; Tech Specs 3.1.3 and 3.1.4)

Time Position Applicant's Actions or Behavior RO Recognizes control rod 36-37 will not move when given a withdraw signal.

SS Enter ONEP 05-1-02-IV-1 and contact Auxiliary Building Operator to verify CRD system parameters.

SS Directs raising CRD Drive Water Pressure in 25 psid increments to attempt to move the control rod.

BOP Throttles C11-F003 CRD Pressure Control Valve to adjust CRD Drive Water Pressure.

RO Attempts to move control rod 36-37 and determines control rod is stuck.

BOP Verify Seal Steam Pressure Extraction Steam pressure Low due to down power.

SS Contacts Reactor Engineering for determination to individually scram the control rod.

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 196 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 197 of 257 JOB PERFORMANCE MEASURE SS Refers to Tech Spec 3.1.3 and criteria for TS 3.1.4.

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 197 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 198 of 257 JOB PERFORMANCE MEASURE Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __1__ Event No.: ___5_

Event

Description:

APRM D fails upscale (ARI 04-1-02-1H13-P680 7A-B11; SOI-04-1-01-C51-1; Tech Specs 3.3.1.1; 3.3.2.1 and TRM 3.3.1.1)

Time Position Applicant's Actions or Behavior RO Responds to and reports the annunciators for APRM D failing upscale and half scram for RPS B. May remind SS that APRM H is bypassed in the Division 2.

BOP Investigates APRM D and reports failed hard upscale.

SS Contacts I&C to investigate APRM D.

SS Reviews Tech Specs 3.3.1.1 and 3.3.2.1 and TRM 3.3.1.1.

Determination that TS3.3.1.1 is not met due to APRM H and D being INOP in Division 2. (3 of 4 must be operable). TS 3.3.2.1 is met by having 6 of 8 APRMs operable. TR 3.3.2.1 Condition E applies if APRM H remains Bypassed with a half scram and upscale due to APRM Upscale Alarm.

SS (Optional)

May decide to un-bypass APRM H and bypass APRM D to take a Control Rod Withdrawal Block but be able to reset the Division 2 Half Scram signal until I&C can repair either APRM H or D.

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 198 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 199 of 257 JOB PERFORMANCE MEASURE RO When directed, un-bypasses APRM H and bypasses APRM D.

RO Resets Division 2 RPS.

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 199 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 200 of 257 JOB PERFORMANCE MEASURE Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __1__ Event No.: ___6_

Event

Description:

Pressure Controller Failure - Reactor Pressure Rising Time Position Applicant's Actions or Behavior RO Responds to Reactor Pressure and Power rising due to failure of Pressure Control System closing Turbine Control Valves. Reactor Pressure will reach RPS Scram setpoint however RPS will fail to actuate.

RO Manually initiate or verify actuation of ATWS ARI to insert control rods and inform SS of failure of RPS actuation.

RO Observes and reports failure of all control rods to fully insert on ATWS ARI actuation. (CRD Scram Discharge Volume Hydraulic Block)

RO Observes and reports Reactor Recirc Pumps Tripped to OFF.

RO Provides SS with Scram Report of status of Feedwater, Control Rods, Recirc, and Pressure control.

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 200 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 201 of 257 JOB PERFORMANCE MEASURE Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __2__ Event No.: __7___

Event

Description:

ATWS with Partial Main Steam Bypass Valves (05-1-01-EP-2; 2A; and 3)

Time Position Applicant's Actions or Behavior SS Enters EP-2A.

BOP On orders inhibits ADS.

HPCS Override is not necessary due to Out of service, may elect to close E22-F004 HPCS Injection valve.

RO Realigns Condensate and Feedwater on Startup Level Control and maintains reactor level within level band specified by the SS.

Initially may operate in a normal lineup then transition to Startup Level Control.

BOP Maintains RPV pressure based on SS orders using Turbine Bypass valves or SRVs as appropriate. (optional) Pressure band 800 -

1060 psig. Should attempt to open Main Steam Bypass Valves using the Manual Bypass Jack. This is manually positioning the Bypass valves to maintain pressure. These are acceptable.

SS May order opening of long and short string Main Steam Drains to supplement pressure control.

SS Order manual initiation and overriding of Low Pressure ECCS.

BOP On orders manually initiates and overrides Low Pressure ECCS.

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 201 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 202 of 257 JOB PERFORMANCE MEASURE BOP/RO When ordered by SS, restores Auxiliary Building, Containment, and Drywell isolation (Instrument Air, Plant Service Water, and Drywell Chilled Water). (Attachment 7 of EP-1)

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 202 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 203 of 257 JOB PERFORMANCE MEASURE Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __1__ Event No.: __7___

Event

Description:

ATWS with Main Steam Bypass Valves (Cont.)

Time Position Applicant's Actions or Behavior SS ** Orders installation of Attachments 18, 19, and 20 of EP-1. (may not order Attachment 18 since RPS is still energized.)

SS Orders installation of Attachments 8 and 12 of EP-1.

BOP Notifies SS of MSL RAD HI (If Alarmed)

SS Enters EP-4 on MSL RAD HI (If Alarmed)

SS ** Based on conditions orders Terminate and Prevent step to lower RPV level to reduce reactor power.

BOP/RO ** Terminates and prevents systems ordered by SS RHR A RHR B RHR C LPCS RO ** On orders of SS, initiates flow to the RPV from Condensate /

Feedwater.

BOP/RO ** Insert Control Rods by inserting rods using CRD/RCIS. CRD Drive Pressure, Instrument Air to Containment and Auxiliary Building, and RPS reset. (Scramming rods is not an option) If low pressure ECCS has been initiated, RPS A has no power because the EPA breakers are tripped due powered from alternate.

• • Critical Task REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 203 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 204 of 257 JOB PERFORMANCE MEASURE Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __1__ Event No.: __7/8___

Event

Description:

ATWS with Main Steam Bypass Valves (Cont.)

Time Position Applicant's Actions or Behavior SS** If Reactor power is above 4%, orders Standby Liquid Control (SLC) initiation. (Must be ordered before 110 degrees F in Suppression Pool.

BOP On orders initiates both trains of Standby Liquid Control.

BOP Observes failure of SLC Squib Valves to fire and reports to SS.

SS Orders injection of boron using Attachment 28 of EP-1 SS If level drops below -191 inches Fuel Zone and cannot be restored, may elect to Emergency Depressurize. (Optional) (SS may continue if systems are available to raise level.)

SS If Emergency Depressurization is required, orders to Initiate Standby Liquid Control will be given.

SS Orders Terminate and Prevent step for Emergency Depressurization. (Optional)

BOP/RO Terminates and prevents injection systems ordered by SS.

(Optional) Boron, CRD and RCIC are acceptable to remain operating and injecting.

BOP/RO If ordered opens 8 ADS SRVs. (Optional)

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 204 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 205 of 257 JOB PERFORMANCE MEASURE SS Upon Reactor pressure drop < 219 psig with 8 SRVs (see Table 6 of EP-2A) open, orders slow injection with Condensate and Feedwater. (Optional)

BOP/RO Injects with Condensate at prescribed rates by SS. (Optional)

• • Critical Task Optionals for Emergency Depressurization leg of EP-2A are only if SS elects to use this based on RP REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 205 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 206 of 257 JOB PERFORMANCE MEASURE Appendix D Scenario Outline Form ES-D-1 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 2 Op-Test No.: Day 0 Examiners: _________________________ Operators:__________________________

_________________________ __________________________

_________________________ __________________________

Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:

1. Shift Main Turbine EHC Pumps.

2. Start RCIC for EPI and respond to RCIC over speed trip.

3. Raise Reactor Power using Reactor Recirc Flow.

4. Respond to a Main Steam Line Radiation Monitor failure downscale.

5. Respond to control rod drifting inward.

6. Respond to a LPRM failure downscale.

7. Respond to a loss of Main Condenser Vacuum.

8. Respond to a loss of Offsite Power with failure of Division 3 Diesel Generator.

Initial Conditions: Reactor Power is at 80 %.

INOPERABLE Equipment SRM F are INOP and bypassed.

IRMs A & H are INOP and bypassed.

Appropriate clearances and LCOs are written.

Turnover: Shift Main Turbine EHC pumps to A and C operating and B in Standby. Once shifted raise Reactor Power to 90%. There are scattered thunder showers reported in the Tensas Parish area.

Event Malf. No. Event Event No. Type* Description 1 N (RO) Shift operating EHC pumps. (SOI 04-1-01-N32-1) 2 R (RO) Raise Reactor Power using Recirc Flow to 90%.

3 1 C Start RCIC per EPI 04-1-03-E51-2 then respond to RCIC REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 206 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 207 of 257 JOB PERFORMANCE MEASURE (BOP) Overspeed Trip.

TS Complete Technical Specification determination. (Tech Spec (SS) 3.5.3)

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 207 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 208 of 257 JOB PERFORMANCE MEASURE Appendix D Scenario Outline Form ES-D-1 Scenario 2 Day 0 (Continued)

Event Malf. No. Event Event No. Type* Description 4 2 TS Respond to Main Steam Line Radiation Monitor failure downscale.

(SS) (ARI 04-1-02-1H13-P601)

Complete Technical Specification determination.(TR 3.3.6.1 Table TR 3.3.6.1-2) 5 3 C (RO) Respond to control rod drifting inward. (ONEP 05-1-02-IV-1)

TS Complete Technical Specification determination.(TS 3.1.3)

(SS)

I 6 4 (RO) Respond to a LPRM failure downscale. (ARI 04-1-02-1H13-P680; TS 17-S-02-40)

(SS) Complete Technical Specification determination.(TS 3.3.1) 7 5 C Respond to a loss of Main Condenser Vacuum.

(ALL) (ONEP 05-1-02-V-8) 8 6 M Respond to a Loss of Offsite Power. (ONEP 05-1-02-I-4)

(ALL) 7 Respond to a failure of Division 3 Diesel Generator operate.

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

- When level drops to <-191 inches or after level drops between TAF and - 191 inches, opens at least seven SRVs before level drops to - 212 inches. Pumps must be running and lined up for injection before reactor pressure drops to 300 psig.

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 208 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 209 of 257 JOB PERFORMANCE MEASURE Scenario 2 Day 0 (Continued)

Crew Turnover:

Rx power is at 80% CTP.

SRMs F is INOP and bypassed.

IRMs A & H are INOP and bypassed.

Appropriate clearances and LCOs are written.

Continue plant operations at rated conditions.

Need to shift Main Turbine EHC pumps to A and C operating and B in Standby.

Once EHC is transferred, raise reactor power to 90%. Reactor Engineering has determined power may be raised to 90% with NO restrictions per thermal limits.

Once power has been raised operate RCIC per EPI 04-1-03-E51-2. GETARS has been setup to run.

Chemistry and Radiation Protection personnel have been notified of the power change and operation of RCIC.

Plant EOOS is 10.0 GREEN.

There are scattered thunderstorms reported in the Tensas Parish area.

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 209 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 210 of 257 JOB PERFORMANCE MEASURE Simulator Setup: (Scenarios may be setup and shot into encrypted ICs and Password protected.)

Start the process from a new simulator load.

Reset to IC-17.

Verify or perform the following:

IC: 17 OOS: IRMs A & H (Place in Bypass w/ Caution tag)

SRMs F (Place in Bypass w/ Caution tag)

Active malfunctions: c51002f SRM F incorporated into present simulator load c51005a IRM A incorporated into present simulator load c51005h IRM H incorporated into present simulator load Active Remote Functions: None Active Case File: None Active overrides: None Pending Remote Function: z300_2635b_BYPASS LPRM 26-35 B bypassed on APRM B (TRG 4)

Pending malfunctions: rm157a_0 Main Steam Line Radiation Monitor fails downscale (TRG 1) e51046 RCIC Overspeed trip on E51-F045 opening (TRG 2) c51008_2635b LPRM 26-35 level B failed downscale (TRG 3) z021021_60_41 Control Rod 60-41 drift in (TRG 5) fw163c@8% Main Condenser Vacuum leak (TRG 6) ramp to 40% on Reactor Scram (TRG 7) r21135 Loss of Offsite Power on Main Generator Trip (TRG 8) n41141c Diesel Generator 13 Trip (TRG 8)

Pending component malfunctions: None Trigger files: Trigger 1 MSL Rad Monitor failure downscale Trigger 2 RCIC Overspeed Trip Trigger 3 LPRM Failed Downscale Trigger 4 LPRM Bypassed Trigger 5 Control rod drift in REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 210 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 211 of 257 JOB PERFORMANCE MEASURE Trigger 6 Loss of Condenser Vacuum Trigger 7 Complete loss of Condenser Vacuum Trigger 8 Loss of Offsite Power/DG 13 Trip REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 211 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 212 of 257 JOB PERFORMANCE MEASURE IRMs A and H, SRMs F are bypassed in the IC setup for Cycle 15.

Verify or perform the following:

Startup all PDS / SPDS screens. Clear any graphs and trends off of SPDS.

Setup the presently used cyclops display and verify it is functional.

Ensure the correct startup sequence is available at the P680 for the present IC.

Install turnover guide, red tag, and LCO paperwork as applicable.

Advance all chart recorders and ensure all pens are inking properly.

(APRM chart recorders must be turned on and settings for scales on pens 0 - 125 scale)

Place tags on IRM A & H and SRMS F Joysticks.

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 212 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 213 of 257 JOB PERFORMANCE MEASURE SIMULATOR OPERATION SCENARIO 2 Once simulator is reinitialized and setup complete take the simulator out of Freeze.

Once the Crew has taken control note the simulator time.

Shift EHC Pumps The operator will start EHC Pump A and secure EHC Pump B and place EHC B in Standby. per SOI 04-1-01-N32-1.

Cues:

If asked, report as Turbine Building Operator pre-start checks are complete for EHC Pump A.

Raise Reactor Power using Recirc Flow.

The SS will perform a Reactivity Brief.

The RO will raise Reactor Power using Recirc Flow Control Valves.

The BOP operator will follow power on Main Generator Load Demand.

Start RCIC/Trip of RCIC The operator will start RCIC per EPI 04-1-03-E51-2, TRIGGER 2 should activate when E51-F045 opens (RCIC Overspeed trip).

Cue:

If asked, report as Auxiliary Building Operator that RCIC Overspeed Trip mechanism will not reset.

The SS should review the Tech Specs for TS 3.5.3 Condition A.

One minute after the Tech Spec determination briefing, activate Trigger 1 (MSL Rad Monitor failed).

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 213 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 214 of 257 JOB PERFORMANCE MEASURE REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 214 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 215 of 257 JOB PERFORMANCE MEASURE Main Steam Line Radiation Monitor failure The crew should respond to the MSL Radiation Monitor downscale annunciator.

The SS should dispatch I&C to investigate the cause of the downscale.

The SS should consult the Tech Spec Loop Logics and TRM TR3.3.6.1 and Table TR3.3.6.1-2 for Condition A.

Cue:

When asked as I&C, Main Steam Line Radiation monitor is failed downscale and will require a work order for further troubleshooting.

One minute after TRM determination, activate TRIGGER 5 (Control Rod drift).

Control Rod Drift Control Rod 60-41 will begin to drift inward.

The RO will receive annunciators indicating the Control Rod drift and identify the drifting control rod and attempt to insert the control rod to position 00.

The SS should dispatch operators to isolate the drifting control rod.

Cues:

If asked, as Auxiliary Building Operator isolate control rod 60-41QK.

Simulator operator remove malfunction.

If asked, report as Reactor Engineering reviews will need to be performed to determine impact.

The SS should be determining based on indications the applicability of Tech Spec 3.1.3.

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 215 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 216 of 257 JOB PERFORMANCE MEASURE One minute after the Tech Spec determination is complete, activate TRIGGER 5 (LPRM failed downscale).

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 216 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 217 of 257 JOB PERFORMANCE MEASURE LPRM Failed Downscale The Crew should recognize alarms for LPRM downscale.

The RO will determine the failed LPRM is 26-35 level B.

The crew should determine the failed LPRM is assigned to APRM B.

Cue:

If asked, report as Reactor Engineering there are no other LPRMs bypassed.

On directions activate trigger 4 to bypass LPRM 26-35 B.

The SS should review Tech Specs for TS 3.3.1.

The RO should reset the drift once the HCU is isolated to allow the control rod to settle and be able to clear the Control Rod Drift annunciator.

One minute after the Tech Spec determination and HCU is isolated, activate TRIGGER 6 (loss of Condenser Vacuum).

Loss of Main Condenser Vacuum.

Crew will respond to annunciators and implement actions of ONEP 05-1-02-V-8.

The BOP and RO should monitor the rate of Condenser vacuum loss.

The SS should reduce Reactor Power using Recirc Flow.

The SS should determine a point on lowering condenser vacuum when the Unit should be scrammed.

Main Turbine Trip 21 inches Hg Reactor Feed Pump Turbine Trip 16 inches Hg (may be overridden per SS)

Main Steam Bypasses close 12 inches Hg Main Steam Isolation Valves close 9 inches Hg Cues:

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 217 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 218 of 257 JOB PERFORMANCE MEASURE If dispatched, report as Turbine Building Operator a high pitched whistling sound coming from the vicinity of the Turbine Building Steam tunnel are on 133 Ft.

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 218 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 219 of 257 JOB PERFORMANCE MEASURE Reactor Scram and Loss of Offsite Power When the Reactor Scrams, the Main Condenser vacuum leak will become worse. (Trigger 7)

When the Main Generator Trips, Offsite power will trip and Diesel Generator 13 will trip on initiation.

(Trigger 8)

The SS should prioritize actions to maintain Reactor Pressure and Level with minimal systems available.

The SS should contact the Entergy System dispatcher to determine when Offsite Power is to be restored.

Cue:

When dispatched report as Outside operator, unknown cause for HPCS Diesel Generator trip.

Possible EOP attachments when requested.

Attachment 12 Defeat SDC interlocks 4 minutes to DONE Attachment 25 RPV makeup with Condensate Transfer Attachment 26 RPV makeup with Fire Systems Attachments 25 (Condensate Transfer) and 26 (Fire Water) can not be installed by any remote functions just acknowledge the request.

TERMINATION Once Reactor level is being restored with Low Pressure ECCS.

Critical Tasks REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 219 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 220 of 257 JOB PERFORMANCE MEASURE

- When level drops to <-191 inches or after level drops between TAF and - 191 inches, opens at least seven SRVs before level drops to - 212 inches. Pumps must be running and lined up for injection before reactor pressure drops to 300 psig.

Emergency Plan Procedure - Emergency Action Level Classification Alert based on 10-S-01-1 Attachment II FS1 Loss or Potential loss of any two fission product barriers.

REVISION 0 2/19/2007 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 220 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 221 of 257 JOB PERFORMANCE MEASURE Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __2___ Event No.: ___1__

Event

Description:

Shift EHC pumps (SOI 04-1-01-N32-1)

Time Position Applicant's Actions or Behavior RO Start EHC Pump A (SOI 04-1-01-N32-1)

RO Secure EHC Pump B and place in Standby Op-Test No.: _____ Scenario No.: __2___ Event No.: ___2__

Event

Description:

Raise Reactor Power using Reactor Recirc Flow.

(IOI 03-1-01-2)

Time Position Applicant's Actions or Behavior SS Conducts Reactivity Brief RO Raises Reactor Recirc Flow to raise Reactor Power.

BOP Monitors Pressure, Level, Power, and Turbine Loading.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 221 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 222 of 257 JOB PERFORMANCE MEASURE Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __2__ Event No.: __3___ (Cont.)

Event

Description:

Start RCIC and respond to RCIC Overspeed Trip.

(EPI 04-1-03-E51-2 and ARI 04-1-02-1H13-P601; TS 3.5.3)

Time Position Applicant's Actions or Behavior BOP Starts RCIC per EPI and recognizes trip of RCIC on overspeed.

SS Determines actions per Tech Spec 3.5.3 for RCIC inoperable.

SS Dispatches operator and maintenance personnel to investigate RCIC Trip.

Op-Test No.: _____ Scenario No.: __2__ Event No.: __4___ (Cont.)

Event

Description:

Respond to Main Steam Line Radiation Monitor failure.

(ARI 04-1-02-1H13-P601; TR 3.3.6.1)

Time Position Applicant's Actions or Behavior BOP Responds to Main Steam Line Radiation Monitor downscale annunciator.

BOP Determines Main Steam Line Radiation Monitor is failed.

SS Determines actions per TR 3.3.6.1 Condition A 1 LPRM inoperable.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 222 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 223 of 257 JOB PERFORMANCE MEASURE SS Dispatches I&C to investigate failure.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 223 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 224 of 257 JOB PERFORMANCE MEASURE Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __2__ Event No.: __5___ (Cont.)

Event

Description:

Respond to drifting control rod (60-41).

(ARI 04-1-02-1H13-P680; ONEP 05-1-02-IV-1; TS 3.1.3)

Time Position Applicant's Actions or Behavior RO Responds to drifting Control Rod and identifies Control Rod 60-41 QK as drifting inward and applies continuous insert signal to control rod and inserts the control rod to 00.

SS Dispatches operator to isolate the HCU for Control Rod 60-41 QK.

RO Resets Control Rod Drift annunciator and indications.

SS Determines applicability of Tech Spec 3.1.3.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 224 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 225 of 257 JOB PERFORMANCE MEASURE Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __2__ Event No.: __6___ (Cont.)

Event

Description:

Respond to LPRM failure.

(ARI 04-1-02-1H13-P601; 17-S-02-40; TS 3.3.1)

Time Position Applicant's Actions or Behavior BOP Responds to LPRM downscale annunciator.

RO Determines using Full Core Display LPRM string 26-35 has the failed LPRM and selects an adjacent control rod and determines level B is failed downscale.

SS/ BOP Determines LPRM 26-35 level B is assigned to APRM B and LPRM may be bypassed using 17-S-02-40.

RO Bypasses APRM B to facilitate bypassing LPRM and returns to normal once bypassed.

SS Determines TS 3.3.1 is met.

SS Dispatches I&C personnel to investigate LPRM failure.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 225 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 226 of 257 JOB PERFORMANCE MEASURE Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __2___ Event No.: ___7__

Event

Description:

Loss of Main Condenser Vacuum (ONEP 05-1-02-V-8)

Time Position Applicant's Actions or Behavior BOP Responds to annunciator for Offgas Panel Trouble and determines Offgas flow is elevated.

RO Monitors Main Condenser Vacuum and determines it is degrading.

SS Orders lowering of Reactor Power per ONEP to 67 Mlbm/hr.

RO Lowers Reactor Power using Reactor Recirc Flow and plots Power to Flow in the Monitored Region of Power to Flow Map.

SS Dispatches personnel to investigate the leak.

SS Determines point at which the Reactor will be scrammed on Loss of Condenser Vacuum RO When Main Condenser Vacuum degrades to point the SS specifies, manually scrams the reactor.

RO Makes Scram Report to include status of Main Steam Bypass valves and Reactor Feed Pumps.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 226 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 227 of 257 JOB PERFORMANCE MEASURE Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __2___ Event No.: ___8__

Event

Description:

Respond to Loss of Offsite Power and failure of Diesel Generator 13 (ONEP 05-1-02-I-4; 05-1-01-EP-2 & 3)

Time Position Applicant's Actions or Behavior RO/BOP Report loss of Offsite Power and determine NO offsite power is available.

BOP Assess and report the status of Emergency Diesel Generators (Divisioin 3 DG tripped. Division 1 and 2 carrying buses)

RO/BOP Reports status of ECCS Systems. LP ECCS available, RCIC tripped, HPCS no power.

SS Assigns responsibility of RPV Level and Pressure control and assigns bands of operation.

RO/BOP Monitors assigned parameters.

SS Orders CRD maximized for flow.

RO/BOP Aligns CRD for Maximum flow SS Orders SLC injection (optional).

RO/BOP Injects SLC (optional)

SS Dispatches personnel to setup Nitrogen for ADS valve operation.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 227 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 228 of 257 JOB PERFORMANCE MEASURE SS Contacts Load Dispatcher to determine when Grid will be restored.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 228 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 229 of 257 JOB PERFORMANCE MEASURE Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __2___ Event No.: ___8__ (Cont)

Event

Description:

Respond to Loss of Offsite Power and failure of Diesel Generator 13 (ONEP 05-1-02-I-4; 05-1-01-EP-2 & 3)

Time Position Applicant's Actions or Behavior SS Orders alignment of Low Pressure ECCS for injection to the Reactor.

BOP/RO Align Low Pressure ECCS for injection.

SS If Reactor Level drops below - 160 inches, orders Emergency

• • Depressurization with 8 SRVs (at least 5 SRVs should be open)

BOP/RO On orders, opens 8 SRVs using handswitches (initiation pushbuttons may

• • be used initially, however should be followed with handswitches.) SRVs B21-F047A and B21-F051B will fail to open. ONLY 6 SRVs are open.

BOP/RO Opens two non-ADS SRVs to make 8 SRVs open (minimum is one other

• • to meet 7 SRVs per EOP-2 step ED-5.

BOP/RO Verifies injection to the RPV with Low Pressure ECCS.

BOP/RO Restores level using LP ECCS with band of +30 inches to -30 inches Wide Range.

• • Critical task REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 229 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 230 of 257 JOB PERFORMANCE MEASURE Appendix D Scenario Outline Form ES-D-1 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 3 Op-Test No.: Day 0 Examiners: _________________________ Operators:__________________________

_________________________ __________________________

_________________________ __________________________

Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:

1. Insert control rods to lower reactor power per control rod movement plan.

2. Respond to a failure of RPS MG B per Loss of One or Both RPS Busses ONEP.

3. Respond to trip of SBGT A.

4. Downshift Reactor Recirc Pumps to Slow Speed.

5. Take actions to mitigate a large break failure of Feedwater piping in the Drywell per EOPs.

(LOCA is NOT severe enough to result in depressurization of RPV.)

6. Respond to a steam leak on RCIC when initiated.

Initial Conditions: Reactor Power is at 53 %. Plant shutdown is in progress in preparation for an outage. Reactor Recirculation pumps in Fast Speed; a single Reactor Feed Pump in Three element Master Level Control; one Heater Drain Pump is pumping forward.

INOPERABLE Equipment SRM F are INOP and bypassed.

IRMs A & H are INOP and bypassed.

APRM H is INOP due to a failed FCTR card.

HPCS Pump is tagged out of service for failure of the Jockey Pump.

ESF 12 Transformer is tagged out of service for maintenance.

RPS A is on Alternate Power due to EPA circuit breaker failure.

SBGT A is operating for surveillance.

Appropriate clearances and LCOs are written.

Turnover: Continue plant shutdown per IOI-2. There are scattered thunder showers reported in the Tensas Parish area.

Event Malf. No. Event Event No. Type* Description 1 R (RO) Lower Reactor power using control rods to 60 - 75% rod line.

(Control Rod Movement Sequence)

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 230 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 231 of 257 JOB PERFORMANCE MEASURE 2 N (RO) Transfer Reactor Recirc Pumps to Slow Speed (SOI 04-1-01-B33-1) 3 1 C (RO) Respond to RPS Motor Generator B trip. (ONEP 05-1-02-III-2).

TS Complete Technical Specification/FSAR determination.

(SS)

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 231 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 232 of 257 JOB PERFORMANCE MEASURE Appendix D Scenario Outline Form ES-D-1 Scenario 3 Day 0 (Continued)

Event Malf. No. Event Event No. Type* Description 2 C Respond to trip of SBGT A trip. (ARI 04-1-02-1H13-P870 4

(BOP) 2A-A2)

TS Complete Technical Specification determination.

(SS)

M 5 3 (ALL) Respond to indications of large break LOCA on Feedwater Line A per EOPs. (B21-F065A will close if attempted.)

4 C RCIC steam leak will isolate by manual means.

(BOP)

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

- Lower RPV Pressure to facilitate restoration of RPV Level using Condensate/Feedwater or ECCS.

- Isolate RCIC following EP-4 entry due to steam leak.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 232 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 233 of 257 JOB PERFORMANCE MEASURE Scenario 3 Day 0 (Continued)

Crew Turnover:

Rx power is at 53% CTP.

The plant is lowering power in preparation for an outage.

Reactor Recirculation Pumps are operating in Fast Speed.

The A Reactor Feed Pump is operating in Three Element Master Level Control.

Circ Water is in Single Pump Dual Train A Pump in service.

SRMs F is INOP and bypassed.

IRMs A & H are INOP and bypassed.

APRM H is failed due to a failed FCTR card and bypassed.

ESF 12 Transformer is tagged out of service for maintenance.

RPS A is on Alternate Power due to an EPA circuit breaker failure.

SBGT A is operating for surveillance 06-OP-1T48-M-0001 holding at step 5.2.11 allowing the System Engineer to obtain data.

Hpcs Pump and Jockey Pump are out of service due to the Jockey Pump motor burned up.

Appropriate clearances and LCOs are written.

Continue plant shutdown to less than 75% Rod Line to Downshift Reactor Recirc Pumps.

At step 8.4 of IOI-2 Attachment IV.

BOC Shutdown Sequence Sheet Step 5.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 233 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 234 of 257 JOB PERFORMANCE MEASURE Plant EOOS is 7.3 YELLOW.

Hydrogen Water Chemistry and Alternate Cooling Tower are secured.

Surveillance 06-RE-1J11-V-002 is complete.

There are scattered thunderstorms reported in the Tensas Parish area.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 234 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 235 of 257 JOB PERFORMANCE MEASURE Simulator Setup: (Scenarios may be setup and shot into encrypted ICs and Password protected.)

Start the process from a new simulator load.

Reset to IC-13.

Verify or perform the following:

IC: 13 OOS: APRM H (Place in Bypass w/ Caution tag)

IRMs A & H (Place in Bypass w/ Caution tag)

SRMs F (Place in Bypass w/ Caution tag)

RPS A (Transfer to Alternate Power and reset RPS A w/ Caution tag)

Manually Initiate SBGT A HPCS and HPCS Jockey Pump OOS (Place HPCS OOSVC to OOSVC and place tags on HPCS Pump and Jockey Pump HS)

ESF XFMER 12 (Place tag on J3885, 152-1903, 152-1904, 152-1905, 152-1511, 152-1611, 152-1704 HS)

Active malfunctions: c51002f SRM F incorporated into present simulator load c51005a IRM A incorporated into present simulator load c51005h IRM H incorporated into present simulator load c71077a RPS A MG failure (Normal EPA OOS)

Active Remote Functions: c51262 APRM H Function Switch to STDBY p81218 J3885 115KV Disconnect OPEN e22644 HPCS Pump BKR OUT e22646 HPCS JKY pump breaker OPEN 152-1511 lo_1r21m601a_g Bus 15AA FDR FM ESF XFMR 12 OFF di_1r21m601ap864/01c Bus 15AA FDR FM ESF XFMR 12 TRIP 152-1611 lo_1r21m601b_g Bus 16AB FDR FM ESF XFMR 12 OFF di_1r21m601bp864/02c Bus 16AB FDR FM ESF XFMR 12 TRIP 152-1704 lo_1e22m709_g 17AC FDR FM ESF 12 OFF di_1e22m709p601/16c 17AC FDR FM ESF 12 OFF 152-1903 lo_1r21m623_g Bus 15AA/16AB/27AC FDR FM ESF XFMR 12 OFF di_1r21m623p807/01c Bus 15AA/16AB/27AC FDR FM ESF XFMR 12 TRIP 152-1904 lo_1r21m624_g Bus 17AC/25AA/26AB FDR FM ESF XFMR 12 OFF di_1r21m624p807/01c Bus 17AC/25AA/26AB FDR FM ESF XFMR 12 TRIP REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 235 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 236 of 257 JOB PERFORMANCE MEASURE 152-1905 lo_1r21m637_g SWYD XFMR T3 FDR FM ESF XFMR 12 OFF di_1r21m637p807/01c SWYD XFMR T3 FDR FM ESF XFMR 12 TRIP Active Case File: cae sgtsai.cae SBGT A operating for surveillance Active overrides: None Pending overrides: remote function e51319 Failure to isolate RCIC remote function e51320 Failure to isolate RCIC Pending malfunctions: c71077b RPS MG failure (TRG 2) t48d001a_a SBGT A Filter Train Fan trip (TRG 3) fw171a@100% Feedwater Line A break in Drywell (TRG 5) rr063a@4.6% Recirc line A leakage to simulate Feedwater Check Valve leakage ramp 1% to 4.6% over 2 minutes (TRG 5) e51050@50% RCIC Steam line rupture five minutes after Feedwater failure (TRG 5) RCIC will fail to automatically isolate.

Pending component malfunctions: None Trigger files: Trigger 2 RPS B MG Failure Trigger 3 SBGT A Trip Trigger 5 Feedwater Line A rupture in Drywell w/ RCIC Steam leak COMPONENT PANEL INDICATION or SIMULATOR STATUS DONE CONTROL CODE APRM H c51262 STDBY HPCS PUMP P601-16C e22644_OUT OUT HPCS Jockey Pump P601-16C e22646_OPEN OPEN RPS A on Alternate P610 Handswitch c71077a ALT 152-1511 P864-1C Green light lo_1r21m601a_g OFF P864-1C Handswitch di_1r21m601a STOP 152-1611 P864-2C Green light lo_1r21m601b_g OFF P864-2C Handswitch di_1r21m601b STOP 152-1704 P601-16C Green light lo_1e22m709_g OFF P601-16C Handswitch di_1e22m709 STOP 152-1903 P807-1C Green light lo_1r21m623_g OFF P807-1C Handswitch di_1r21m623 STOP 152-1904 P807-1C Green light lo_1r21m624_g OFF REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 236 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 237 of 257 JOB PERFORMANCE MEASURE P807-1C Handswitch di_1r21m624 STOP 152-1905 P807-1C Green light lo_1r21m637_g OFF P807-1C Handswitch di_1r21m637 STOP J3885 115 KV Disconnect P807-1C Green Light p81218 OPEN Bypass Division 2 APRM Bypass Joystick to APRM H position.

IRMs A and H, SRMs F are bypassed in the IC setup for Cycle 15.

Verify or perform the following:

Verify Reactor Power is above the 75% rod line.

Open Circuit Breakers 152-1903, 1904, 1905, 1511, 1611, and 1704 Place HPCS OOSVC handswitch to OOSVC.

Place RPS A on Alternate Power and RESET RPS A logic on P680.

Verify SBGT A is operating.

Startup all PDS / SPDS screens. Clear any graphs and trends off of SPDS.

Setup the presently used cyclops display and verify it is functional.

Ensure the correct startup sequence is available at the P680 for the present IC.

Install turnover guide, red tag, and LCO paperwork as applicable.

Advance all chart recorders and ensure all pens are inking properly.

(APRM chart recorders must be turned on and settings for scales on pens 0 - 125 scale)

Place tags on ALL circuit breakers associated with the ESF 12 Transformer outage.

Place tags on APRM H, IRM A & H and SRMS F Joysticks.

Place tags on HPCS Pump and Jockey Pump handswitches.

Place a Caution tag on RPS B Power Handswitch on P610.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 237 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 238 of 257 JOB PERFORMANCE MEASURE SIMULATOR OPERATION SCENARIO 3 Once simulator is reinitialized and setup complete take the simulator out of Freeze.

Once the Crew has taken control note the simulator time.

Lower Reactor Power using Control Rods This step will lower Reactor Power to below the 75% Rod Line per IOI-2 Step 8.4.

Set FCBB less than 1.0 using Remote Function cy_fcbb after crew inserts the first gang of control rods.

Crew will review procedures for lowering power using control rods.

Cues:

If asked, report as Reactor Engineer - follow the instructions in the front of the Control Rod Movement Sequence.

Adjust APRM gains using remote function c51299 as requested.

Place FCTR cards in SETUP using remote function c51310 as requested.

Recirc Pump Downshift to Slow Speed Once power is below the 75% rod line, the crew is ready per the IOI step 8.4 to downshift Reactor Recirc Pumps to Slow Speed per SOI 04-1-01-B33-1 section 4.3.

Cue:

As Turbine Building Operator report the pre-start checks on the LFMG are complete.

Simulator Operator: FCTR to SETUP is Remote Function c51310.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 238 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 239 of 257 JOB PERFORMANCE MEASURE RPS Motor Generator B trip Once Recirc Pumps are in slow speed per SOI and the Lead Examiner concurs, activate TRIGGER 2.

Respond to RPS B Motor Generator trip per ONEP 05-1-02-III-2, Loss of One or Both RPS Buses.

Cue:

When asked, report as Control Building Operator, RPS MG B tripped and is extremely hot to the touch.

If asked report as Auxiliary Building Operator, HCU accumulators for 12-13; 12-53; 20-05; and 20-61 are at 1800 psig.

If dispatched report as Turbine Building Operator, RPS Motor Generator B circuit breaker 52-142229 is in the Trip Free condition.

RPS B CANNOT be transferred to the Alternate Power Source per the SOI Precautions and Limitations (04-1-01-C71-1 section 3.5) due to FSAR 8.3.1.1.5.4 commitment. The FSAR is an appendix of the GGNS Operating License. Tech spec 3.3.8.2 is not applicable. HCU Alarm Instrumentation alarm with RPS B de-energized is sealed in on HCUs 12-13; 12-53; 20-05; and 20-

61. This means TRM 3.1.5 Conditions A and B are applicable.

Cue:

When asked, as Duty Manager continue plant shutdown with the half scram signal, Ill discuss with Plant Licensing the options concerning RPS.

Crew will have to live with a half scram signal the SS should brief the crew accordingly on contingencies.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 239 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 240 of 257 JOB PERFORMANCE MEASURE SBGT A Fan trip Two minutes after the Tech Specs/FSAR briefing have been identified, activate TRIGGER 3.

Standby Gas Treatment Exhaust Fan A will trip.

The BOP operator will have to realign Auxiliary Building Ventilation.

Cues:

If asked, respond as the Auxiliary Building Operator to investigate the SBGT A Exhaust Fan Trip.

Report as the Auxiliary Building Operator that the fan motor is hot to the touch and breaker 52-151117 for T48-D001A SBGT A Exhaust Fan is in the Trip Free condition on bus MCC 15B11.

The SS should direct restoration of Auxiliary Building Ventilation per the SOI 04-1-01-T48-1 section 5.3.

The SS should review Tech Spec 3.6.4.3.

Cues:

As asked, assist in the restoration of systems.

Cue: If contacted, as Assistant Operations Manager -Shift or Duty Manager instruct the shift to continue plant shutdown.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 240 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 241 of 257 JOB PERFORMANCE MEASURE Feedwater rupture in the Drywell Once the Reactor Recirc Pumps are in slow speed and the Lead Evaluator concurs, activate TRIGGER 5.

The reactor will scram on Drywell pressure and will continue to rise from the Feedwater Line Break.

B21-F065A Feedwater Isolation Valve will close when the operator gives it the signal to close.

RCIC can be used to inject to the reactor via Feedwater line B.

Recirc loop leakage simulating check valve leakage will ramp rr063b to 4.6% over 2 minutes.

MSIVs will close due to loss of both RPS buses.

Five minutes after the Feedwater rupture, RCIC will have a steam leak due to packing problems in the RCIC Room. RCIC will fail to automatically isolate on high temperatures, but the operator can manually isolate the system from H13-P601.

Crew will implement actions of EP-2 and EP-3, EP-4 when RCIC Steam Leak occurs.

After the LOCA is detected, perform the following attachments when requested.

Attachment 12 Defeat SDC interlocks 4 minutes to DONE 2 for RHR B can be of use.

EP Attachments which may be requested:

Attachment 8 Defeat MSIV isolations 9 minutes to DONE If Attachment 8 is requested early by itself - 3 minutes to DONE RCIC will be initially available until the time of the steam leak.

RHR A Shutdown Cooling line are not available due to the A Feedwater Line break.

Once RCIC is isolated RPV pressure must be lowered to facilitate injection of Low Pressure ECCS or Condensate.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 241 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 242 of 257 JOB PERFORMANCE MEASURE Once B21-F065A is closed Condensate and Feedwater can be restored through the B Feedwater injection line and level restored. To inject Reactor Pressure will have to be lowered to use Condensate Booster Pumps.

Attachments 25 (Condensate Transfer) and 26 (Fire Water) can not be installed by any remote functions just acknowledge the request.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 242 of 257

ENTERGY NUCLEAR Number: GJPM-OPS-R2732 Revision: 0 Page: 243 of 257 JOB PERFORMANCE MEASURE TERMINATION Once Reactor level is being restored with Condensate/Feedwater or Low Pressure ECCS and the Lead Evaluator concurs the scenario may be terminated.

Critical Tasks

- Lower RPV Pressure to facilitate restoration of RPV Level using Condensate/Feedwater or ECCS.

- Isolate RCIC following EP-4 entry due to steam leak.

Emergency Plan Procedure - Emergency Action Level Classification Alert based on 10-S-01-1 Attachment I FA1 RCS loss.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 243 of 257

Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __3___ Event No.: ___1__

Event

Description:

Lower Reactor Power using control rods to below 75% rod line.

(Control Rod Movement Sequence Sheet)

Time Position Applicant's Actions or Behavior SS Conduct reactivity manipulation brief.

RO Inserts control rods in individual or gang per control rod movement sequence sheet to lower power to below the 75% rod line.

BOP Assists RO in Control Rod selection verification, monitors Pressure, Level, Power, and Turbine Loading.

Op-Test No.: _____ Scenario No.: __3___ Event No.: ___2__

Event

Description:

Downshift Reactor Recirc pumps to slow speed.

(SOI 04-1-01-B33-1)

Time Position Applicant's Actions or Behavior SS Performs Reactivity Briefing.

RO Downshifts Reactor Recirc Pumps to Slow Speed.

Closes Recirc FCV A and B to MIN ED position.

Verifies parameters for downshift.

Depresses both Trans to LFMG pushbuttons and verifies Recirc Pump Circuit Breaker operation.

Opens Recirc FCV A and B to maximum position.

Adjusts tap settings on BOP Transformers 11B and 12B.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 244 of 257

Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __3__ Event No.: __3___

Event

Description:

Respond to RPS Motor Generator B trip.

(ONEP 05-1-02-III-2 and SOI 04-1-01-C71-1)

Time Position Applicant's Actions or Behavior RO Responds to Half Reactor Scram and HCU Trouble annunciators.

(ARI 04-1-02-1H13-P680)

RO Identifies the control rod HCUs 12-13, 12-53, 20-05, 20-61 have trouble alarms and are associated with RPS B power.

BOP Responds to H13-P610 to determine the loss of RPS B normal power supply and the Alternate Power for RPS B is available BOP Verifies RPS A is on its Alternate Power Source.

SS Reviews Precautions and Limitations of SOI 04-1-01-C71-1 and ONEP 05-1-02-III-2 and determines RPS B must remain de-energized.

(FSAR 8.3.1.1.5.4) Tech Spec 3.3.8.2 is NOT applicable.

TR 3.1.5 Conditions A & B are applicable due to loss of ability to monitor HCU Fault Instrumentation for alarms on four HCUs 12-13, 12-53, 20-05, 20-61.

SS Consult with Duty Manager concerning operating with HALF scram due to loss of RPS bus.

SS Briefs Crew on contingencies and situation of operating with a half scram.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 245 of 257

Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __3___ Event No.: ___4__

Event

Description:

Respond to Standby Gas Treatment A Exhaust Fan Trip (ARI 04-1-02-1H13-P870; SOI 04-1-01-T48-1)

Time Position Applicant's Actions or Behavior BOP Responds to SGTS FLTR TR A FAN PROT TRIP alarm.

(ARI 04-S-02-1H13-P870 2A-A2)

SS Dispatches an operator to SBGT Train A to investigate problem.

SS/BOP Determine the circuit breaker number for T48-D001A 52-151117. The Operator will report the circuit breaker is TRIP FREE.

SS Direct restoration of Auxiliary Building Ventilation to normal.

BOP Restores Auxiliary Building Ventilation to normal using Surveillance 06-OP-1T48-M-0001 or SOI 04-1-01-T48-1 SS Determines Tech Spec actions for failed SBGT Train. (Tech Spec 3.6.4.3 Condition A restore within 7 days)

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 246 of 257

Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __3__ Event No.: __5___

Event

Description:

Feedwater Rupture in the Drywell with leakage past check valves from the Reactor / RCIC Steam leak.

(EOP 05-S-01-EP-2; 05-1-01-EP-3 and 05-1-01-EP-4)

Time Position Applicant's Actions or Behavior RO Recognizes scram on High Drywell Pressure/Low Reactor Water level and performs the immediate actions for Reactor Scram.

RO Recognizes loss of ability to feed the reactor with Condensate and Feedwater. Communicates the loss to the SS. Depending on conditions, RO may recognize which feed line has rupture.

Indications on H13-P680 section 2B indicators:

A FW FLO C34-R604A upscale B FW FLO C34-R604B downscale A FW FLO C34-FR-R616 Blue Pen upscale B FW FLO C34-FR-R616 Red Pen downscale RO Secures the Condensate and Feedwater Systems by tripping all operating pumps and attempt to isolate the affected Feedwater line by closing B21-F065A Feedwater Inlet Shutoff Valve on H13-P680 section 2C.

SS Enters EP-2 and EP-3, orders the BOP Operator to initiate RCIC (HPCS is tagged out).

BOP or RO Verifies/initiates RCIC (If RO/SS determine which Feedwater Line is ruptured allows injection of RCIC due to it injects via the unaffected Feedwater line.) Level band should be +30 to -30 inches.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 247 of 257

Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __3__ Event No.: __5___ (Cont.)

Event

Description:

Feedwater Rupture in the Drywell with leakage past check valves from the Reactor / RCIC Steam leak.

(EOP 05-S-01-EP-2; 05-1-01-EP-3 and 05-1-01-EP-4)

Time Position Applicant's Actions or Behavior SS Orders CRD maximized and possible initiation of SLC. (Optional)

RO/BOP Maximizes CRD for FLOW per operator aid.

SS Dispatches EP Attachments to be installed Attachment 12 RHR through Shutdown Cooling (May note not to perform for RHR A)

Attachment 25 Condensate Transfer injection Attachment 26 Fire Water injection RO/BOP Reports the isolation of B21-F065A allowing the restoration of Condensate and Feedwater for injection to the reactor vessel.

SS Orders restoration of Condensate and Feedwater for RPV level

• • control using the Startup Level Control Valve through the B Feedwater Line with a Normal RPV Level Band (+11.4 to 53.5 inches). If +30 inches to -30 inches band was already ordered may remain with this band.

RO Aligns Condensate and Feedwater for injection to the RPV through

• • B Feedwater Line using one or two Condensate and Condensate Booster Pumps through the Startup Level Control Valve.

SS Orders reduced Pressure Band 400-600 psig to allow injection using Condensate and Condensate Booster Pumps.

BOP/RO Lowers Reactor pressure to a band of 400 - 600 psig to allow Condensate and Condensate Booster Pumps to inject to the RPV.

• • Critical Task REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 248 of 257

Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __3__ Event No.: __5___ (Cont.)

Event

Description:

Feedwater Rupture in the Drywell with leakage past check valves from the Reactor / RCIC Steam leak.

(EOP 05-S-01-EP-2; 05-1-01-EP-3 and 05-1-01-EP-4)

Time Position Applicant's Actions or Behavior IF the closure of B21-F065A is not noted or accomplished, the following steps will be taken to restore RPV Level.

SS Orders alignment of Low Pressure ECCS for injection to the

• • Reactor.

BOP or RO Align Low Pressure ECCS for injection.

SS If Reactor Level drops below - 160 inches, orders Emergency

• • Depressurization with 8 SRVs (at least 5 SRVs should be open)

BOP or RO On orders, opens 8 SRVs using handswitches (initiation

• • pushbuttons may be used initially, however should be followed with handswitches.)

SS If conditions require RPV Flooding, orders injection to attain RPV

• • pressure 57 psig above Containment pressure BOP or RO Verifies injection to the RPV with Low Pressure ECCS.

RO Restores level using LP ECCS with band of +30 inches to -30 inches Wide Range.

• • Critical task REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 249 of 257

Appendix D Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __3__ Event No.: __5___ (Cont.)

Event

Description:

Feedwater Rupture in the Drywell with leakage past check valves from the Reactor / RCIC Steam leak.

(EOP 05-S-01-EP-2; 05-1-01-EP-3 and 05-1-01-EP-4)

Time Position Applicant's Actions or Behavior When RCIC Steam Leak occurs, the following actions will be taken.

BOP** Reports RCIC Room Temperatures above isolation setpoint and failure of RCIC to isolate and isolates E51-F063 and F064.

SS Enters EP-4 to verify actions taken for breach of Primary Containment.

SS Orders restoration of Auxiliary Building, Containment and Drywell isolation valves.

BOP When ordered by SS, restores Auxiliary Building, Containment, and Drywell isolation (Instrument Air, Plant Service Water, and Drywell Chilled Water). (Attachment 7 of EP-1)

• • Critical Task REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 250 of 257

Appendix D Scenario Outline Form ES-D-1 Safety Function/Knowledge & Ability/10CFR 55.45 Cross Reference Facility: GRAND GULF NUCLEAR STATION Scenario No.: 4 Op-Test No.: backup Examiners: _________________________ Operators:__________________________

_________________________ __________________________

_________________________ __________________________

Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:

1. Start and parallel Division 3 Diesel Generator to Offsite.

2. Respond to a RFPT HPU Leak and subsequent RFPT Trip.

3. Respond to a Recirc FCV Runback and entry into regions of Power to Flow Map.

4. Insert Control Rods to exit undesired regions of Power to Flow Map.

5. Diagnose and respond to a Recirc Pump Seal Failure.

6. Respond to a Steam Line break in the Turbine Building and LOCA in the Drywell.

7. Respond to a failure of Division 2 ECCS to initiate.

8. Respond to a failure of 2 ADS SRVs to open.

Initial Conditions: Reactor Power is at 100 %.

INOPERABLE Equipment SRM F are INOP and bypassed.

IRMs A & H are INOP and bypassed.

APRM H is INOP due to failed downscale.

HPCS Pump is tagged out of service for failure of the Jockey Pump.

ESF 12 Transformer is tagged out of service for maintenance.

RPS A is on Alternate Power due to EPA circuit breaker failure.

SBGT A is operating for surveillance.

Appropriate clearances and LCOs are written.

Turnover: Start and parallel Division 3 Diesel Generator with offsite for engineering testing. There are scattered thunder showers reported in the Tensas Parish area.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 251 of 257

Appendix D Scenario Outline Form ES-D-1 Scenario 4 Day backup (Continued)

Even Safety 1 10CFR Event Event functio K/A 2 t No. n 55.45 Type* Description 264000 1 6 A4.01: 4, 5, 6 N Start and parallel Division 3 Diesel Generator.

3.3/3.4 (BOP) (SOI 04-1-01-P81-1)

A4.02:

3.4/3.4 A4.04:

3.7/3.7 A4.05:

3.6/3.7 259001 2 2 A2.01: 1, 2, 3, C Respond to a leak on the Hydraulic Power Unit 3.7/3.7 4, 5 (RO) for RFPT A and subsequent RFPT Trip. (ARI A4.04: 04-1-02-1H13-P680; ONEP 05-1-02-V-6) 3.1/2.9 259002 A3.04:

3.2/3.2 A3.02:

3.4/3.4 A4.02:

3.7/3.6 295009 AA1.01:

3.9/3.9 AA1.02:

4.0/4.0 AA1.03:

3.0/3.1 AA2.02:

3.6/3.7 202002 3 1 A3.01: 3; 4; 6; C Respond to Recirc Flow Control Valve runback 3.6/3.4 7 (RO) and entry into undesirable regions of the A2.06: TS Power to Flow Map (ARI 04-1-02-1H13-P680 3.3/3.3 (SS) and ONEP 05-1-02-III-3)

Complete Technical Specification 202001 determination.

A1.08:

3.7/3.7 A3.06:

3.6/3.6 REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 252 of 257

A4.02:

3.5/3.4 G2.1.12: 4.0 (SS) 295001 AA1.01:

3.5/3.6 AA1.05:

3.3/3.3 AA2.01:

3.5/3.8 201005 4 1; 7 A3.01: 1, 2, 3, R Insert Control Rods to exit undesired regions 3.5/3.5 4, 5 (RO) of Power to Flow Map. (Control Rod Movement A3.02: Sheet) 3.5/3.5 A3.03:

3.4/3.3 A3.04:

3.3/3.3 A4.01:

3.7/3.7 A4.02:

3.7/3.7 REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 253 of 257

Scenario 4 Day backup (Continued)

Even Safety 1 10CFR Event Event K/A 2 t No. functio 55.45 Type* Description n

5 5 202001 A1.09: 3; 4; TS Respond to Recirc Pump Seal Failure. (ARI 3.3/3.3 (SS) 04-1-02-1H13-P680)

A1.10: Complete Technical Specification 2.6/2.7 determination.

A2.10:

3.5/3.9 A4.10:

2.8/2.8 A4.11:

3.2/3.3 G2.1.12: 4.0 (SS) 295010 AA1.02:

3.6/3.6 AA1.06:

3.3/3.5 AA2.01:

3.4/3.8 AA2.02:

3.8/3.9 239001 6 2 A2.11: 3, 6; 7 M Respond to indications of large break LOCA 4.1/4.3 (ALL) on Steam Line in the Turbine Building with 295009 Recirc Pump Seal Failure to extreme.

AA1.01:

3.9/3.9 AA1.02:

4.0/4.0 AA2.01:

4.2/4.2 295031 EA1.01:

4.4/4.4 EA1.03:

4.4/4.4 EA1.05:

4.3/4.3 EA1.06:

4.4/4.4 EA1.07:

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 254 of 257

3.7/3.7 EA1.10:

3.6/3.7 EA1.13:

4.3/4.3 EA2.01:

4.6/4.6 EA2.03:

4.2/4.2 EA2.04:

4.6/4.8 203000 2 A2.10: 3; 4; 6; I Respond to a failure of Division 2 ECCS to 3.3/3.5 7 (BOP) initiate.

A2.14:

3.8/3.9 A3.08:

4.1/4.1 A4.05:

4.3/4.1 A4.01:

4.3/4.1 A4.02:

4.1/4.1 A4.09:

4.1/4.0 218000 3; 5; 6; 3 A3.01: 7 C Respond to a failure of 2 ADS SRVs to open.

4.2/4.3 (BOP)

A4.01:

4.4/4.4 239002 A4.01:

4.4/4.4

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 255 of 257

1 K/A G2.1.2: 3.0/4.0 Operator Responsibilities; G2.1.17: 3.5/3.6 Communication; G2.1.19: 3.0/3.0 Plant computer information for system status determination; G2.1.20: 4.3/4.2 Execute Procedural Steps; G2.1.31: 4.2/3.9 Locate and determine correct alignment of Control Room indications are covered during each evolution during the dynamic simulator examination.

2 10 CFR 55.45 (a) (3), (4), (12) and (13) are performed during each evolution during the dynamic simulator examination.

Critical Tasks

- When level drops to < -191 inches or after level drops between TAF and - 191 inches, opens at least seven SRVs before level drops to - 212 inches. Pumps must be running and lined up for injection before reactor pressure decreases to 300 psig.

- Manually initiates Division 2 ECCS when fails to initiate.

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 256 of 257

REVISION 1 2/19/2007 SCENARIO 3 NUREG 1021 REVISION 9 PAGE 257 of 257