ML091030041

CGS-2009-03 - Final Operating Test

ML091030041
Person / Time
Site:	Columbia
Issue date:	03/20/2009
From:	Operations Branch IV
To:	Energy Northwest
References
50-397/09-301
Download: ML091030041 (200)

Text

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001587 Rev. No. 1 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 5/11/06 REVISED BY Ron Hayden DATE 10/6/08 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

LO001587 Rev. 1 Page 1 of 6 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

Make a copy of the current pull sheet from the simulator. Determine where Minimum ECP is and indicate it on copy of pull sheet by placing an *1 next to the step and at the bottom of the column indicate that a *1 is Minimum ECP. Ensure it is AFTER step indicated in initial conditions.

Have a copy of PPM 3.1.2 startup flowchart available for reference.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: N/A Safety Items: N/A Task Number: RO-0156; SRO-0118 Validation Time: 15 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

PPM 3.1.2 Rev. 68 Location: Simulator/Plant/Table Top NUREG 1123 Ref: 2.1.7 4.4 / 4.7 Performance Method: Perform

DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

LO001587 Rev. 1 Page 2 of 6 JPM CHECKLIST PROCEDURE VALIDATION:

Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

A plant startup is in progress. PPM 3.1.2 has been completed as follows: Step L11 has been completed, waiting at step L12 ; Step P1 has not yet been completed; Step Q10 has been completed and step Q11 is in progress.

You are the RO pulling control rods and you note the following indications:

• Time 0953

• Coolant Temp 205°F

• Control rod 10-47

• Control rod position 18

• Neutron level 8,000 CPS and rising

• Period 145 seconds and stable You have been pulling control rods steadily since starting Group 1 of the Pull Sheet.

Control rod motion stopped approximately 1 minute ago.

INITIATING CUE:

Using the given information, PPM 3.1.2, and the supplied pull sheets, determine your next action.

When you have determined your next action, write it on the page provided along with the basis for the decision and hand it to the examiner.

DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

LO001587 Rev. 1 Page 3 of 6

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

If SRO position is being evaluated Using given information, determines that the reactor is critical or will be critical before the minimum ECP has been reached.

Directs RO to (stop control rod withdrawal and to) drive control rods in the reverse order until all control rods are fully inserted.

S / U

• If RO position is being evaluated Using given information, determines that the reactor is critical or will be critical before the minimum ECP has been reached.

Notifies the CRS that he has stopped control rod withdrawal due to reactor being critical prior to the minimum allowable ECP.

S / U

• Termination Criteria: Student completes the attached answer sheet and hands it to the examiner.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

LO001587 Rev. 1 Page 4 of 6 RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: SRO Candidate: To pass the JPM the candidate must indicate that direction is to be given to the RO to drive control rods in the reverse order until all control rods are fully inserted.

RO Candidate: To pass the JPM the candidate must indicate that control rod withdrawal must be stopped and the CRS must be notified that the reactor is critical prior to the indicated minimum allowable ECP.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 15 Minutes / NA COMMENTS:

Evaluator's Signature:

Date:

Page 5 of 6 STUDENT JPM INFORMATION CARD Initial Conditions:

A plant startup is in progress. PPM 3.1.2 has been completed as follows:

Step L11 has been completed; Step P1 has not yet been completed; Step Q9 has been completed and step Q10 is in progress.

The following indications are observed:

• Time 0953

• Coolant Temp 205° F

• Control rod 10-47

• Control rod position 18

• Neutron level 8,000 CPS and rising

• Period 145 seconds and stable Control rods have been steadily pulled since starting Group 1 of the Pull Sheet. Control rod motion stopped approximately 1 minute ago.

Cue:

Using the given information, PPM 3.1.2, and the supplied pull sheets, determine your next action.

When you have determined your next action, write it on the page provided along with the basis for the decision and hand it to the examiner.

JPM ANSWER SHEET Page 6 of 6 NEXT ACTION TO BE TAKEN:

BASIS FOR ACTION:

INSTRUCTIONAL COVER SHEET PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE - ADMIN LESSON TITLE RRC-P-1B DELTA T CAVITATION ALARM VERIFICATION (Time Critical)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001629 Rev. No.

0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

JPM ANSWER SHEET Page 1 of 6 LO001629 Rev.0 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

Have a copy of the following:

4.602.A6.3-7 Alarm Response (3 Pages total)

JPM Instructions:

Verify the current revisions of the procedure against the JPM. If the procedure revisions are different than listed in the JPM, ensure the JPM is still technically correct. If the JPM is not technically correct, the JPM should be revised.

The evaluator document results on the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-1171 Validation Time: 7 minutes Prerequisite Training: N/A Time Critical: YES - 10 Minutes PPM

Reference:

4.602.A6.3-7 Rev. 16 Location: CLASSROOM OR SIMULATOR NUREG 1123 Ref: 2.1.25 (2.8 / 3.1)

Performance Method: PERFORM

JPM ANSWER SHEET Page 2 of 6 LO001629 Rev.0 JPM CHECKLIST PROCEDURE VALIDATION Regarding procedure copies for evaluator and student, if the procedure revision is different from that listed on the JPM, verify that the critical task steps are the same.

Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

Columbia is operating in MODE 1 with the following information given: RRC-P-1A and RRC-P-1B are operating at 60 Hz. Annunciator 4.602.A6.3-7 is illuminated. Per the ARP, the delta-T indication and counter on the FANUC and ASD Diagnostic display has been displayed. The display indicates the delta-T is LT 10.7°F and the counter is counting down. B RRC Suction Temperature as indicated on RRC-TR-650 point 2 is 540°F. Steam Dome pressure as indicated on MS-PI-9 is 1020 psig.

INITIATING CUE: You have been directed to calculate the delta-T and determine what actions you should take. Indicate if the delta-T is or is not a valid alarm and what actions would be taken based on your calculation. When done, hand the completed sheet to the examiner. This is a TIME CRITICAL JPM and your time starts NOW.

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and student actions Display the delta-T indication and counter on the FANUC &

ASD Diagnostic display (RRC-VD-R673, H13-P602) by pressing CONTROL STATION on the ASD main menu.

Given in Initial Conditions S / U Verify that delta-T is LT 10.7°F with the counter counting down Given in Initial Conditions S / U Calculate delta-T by comparing B RRC suction temperature (RRC-TR-650 point 2 or TDAS X310) to (REFER TO NEXT PAGE)

Calculates B RRC suction temperature which is given:

RRC-TR-650 point 2 is reading 540°F S / U

JPM ANSWER SHEET Page 3 of 6 LO001629 Rev.0

• Items are Critical Steps Comments Element Standard Sat/Unsat Calculates Steam Dome pressure saturation temperature by taking the pressure reading on MS-PI-9 which is given as being 1020 psig, referring to Attachment 1 to ARP and finding the saturation temperature.

Saturation temperature for 1020 psig is 549°F per Attachment 1 of ARP.

S / U

• Steam Dome pressure saturation temperature (MS-PI-9) to determine if the low delta-T indication is valid.

Calculates the Delta-T by subtracting 540°F from 549°F and coming up with a 9°F Delta-T.

S / U

• Determines the alarm is a VALID alarm.

S / U

• If the delta-T signal is not valid, then place the dT Cavitation Limit Bypass switch to BYPASS (Key 19)

(H13-P634) Otherwise, N/A.

Refers to ARP Automatic Actions, 10 minutes after annunciation, both RRC pumps will run back to 15 Hz.

Student circles choice #2 on attached sheet.

S / U

• Termination Criteria: Student completes JPM, circles answer and hands completed sheet to the exam proctor.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

JPM ANSWER SHEET Page 4 of 6 LO001629 Rev.0 RESULTS OF JPM:

DETERMINE VALIDITY OF DELTA T CAVITATION LIMIT ANNUNCIATOR Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Circles the choice indicating the delta-T is a valid signal and indicates that power would be lowered until both RRC pumps frequency is 15 Hz.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 7 Minutes / 10 Minutes COMMENTS:

Evaluator's Signature:

Date:

JPM ANSWER SHEET Page 5 of 6 LO001629 Rev.0 STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is operating in MODE 1 with the following information given:

RRC-P-1A and RRC-P-1B are operating at 60 Hz.

Annunciator 4.602.A6.3-7 is illuminated.

Per the ARP, the delta-T indication and counter on the FANUC and ASD Diagnostic display has been displayed and indicates the delta-T is LT 10.7°F and the counter is counting down.

B RRC Suction Temperature as indicated on RRC-TR-650 point 2 is 540°F.

Steam Dome pressure as indicated on MS-PI-9 is 1020 psig.

Cue:

You have been directed to calculate the delta-T and determine what actions you should take. Indicate if the delta-T is or is not a valid alarm and what actions would be taken based on your calculation.

When done, hand the completed sheet to the examiner.

This is a TIME CRITICAL JPM and your time starts NOW.

JPM ANSWER SHEET Page 6 of 6 LO001629 Rev.0

JPM ANSWER SHEET Page 7 of 6 LO001629 Rev.0 THIS IS A TIME CRITICAL JPM Circle the choice of actions that you would take:

1. Calculations indicate the low delta-T IS NOT VALID.

2. Calculations indicate the low delta-T IS VALID.

Actions to be taken based on your calculation:

When completed, hand this sheet to the examiner.

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-1A (ADMIN)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001644 Rev. No. 0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/6/08 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-1A LO001644 Rev. 0 Page 1 of 6 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

Have the following drawings ready for candidate to reference:

M-526 Sheet 1 E-503 Sheet 7 and Sheet 12 EWD-38E-001 EWD-38E-021 JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: N/A Safety Items: N/A Task Number: RO-1181 Validation Time: 15 minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

PPM 1.3.64; SWP-OPS-3; M-526-1; E-503-7 E-503-12; EWD-38E-001; EWD-38E-021 Location: Simulator / Classroom NUREG 1123 Ref: 2.2.13 4.1 / 4.3 Performance Method: Perform

DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-1A LO001644 Rev. 0 Page 2 of 6 JPM CHECKLIST PROCEDURE VALIDATION:

Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

Columbia is operating at full power. It is a Division 1 work week. Maintenance wants to replace the pipe coupling (3 inch to 6 inch) located at the discharge of FPC-P-1A.

INITIATING CUE:

You have been directed to determine the clearance order boundary component, required component position, and component tagging requirement necessary to perform work on the coupling downstream of FPC-P-1A.

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Identifies boundary and valve position required to isolate coupling downstream of FPC-P-1A References M-526-1 and determines the following valves should be closed to isolate FPC-P-1A:

• FPC-V-114

• FPC-V-115A

• FPC-V-116A

• FPC-V-181A S / U Determines tagging requirements Determines the following valves should be danger tagged:

• FPC-V-114

• FPC-V-115A

• FPC-V-116A

• FPC-V-181A S / U

• Identifies FPC-P-1A Vent and Drain valves Refers to M-526-1 Detail 3 and determines vent and drain valves for FPC-P-1A:

• FPC-V-187A (Vent)

• FPC-V-150A (Drain)

S / U

DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-1A LO001644 Rev. 0 Page 3 of 6

• Items are Critical Steps Comments Element Standard Sat/Unsat Determines tagging requirements Determines that either FPC-V-187A AND/OR FPC-V-150A should be danger tagged opened S / U

• Identifies breaker and position required to isolate FPC-P-1A electrically References E-503 sheet 12 and determines breaker 9B on MC-7B-B should be open S / U Determines tagging requirements Determines that breaker 9B on MC-7B-B should be danger tagged S / U

• Identifies breaker and position required for FPC-V-181A References E-503 sheet 7 and determines breaker 1C on MC-7B-A should be open S / U Determines tagging requirements Determines that breaker 1C on MC-7B-A should be danger tagged S / U

• Identifies Control Switch requirements for FPC-P-1A References EWD-38E-001 for FPC-P-1A and determines switch should be danger or blue tagged in AUTO or AUTO after STOP position S / U

• Identifies Control Switch requirements for FPC-V-181A References EWD-38E-021 for FPC-V-181A and determines switch should be danger or blue tagged in the NORM or NORM after CLOSE position S / U

• Termination Criteria: Student completes the attached answer sheet and hands it to the examiner.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-1A LO001644 Rev. 0 Page 4 of 6 ANSWER KEY:

COMPONENT REQUIRED POSITION TYPE OF TAG (Blue/

Danger/Caution)

FPC-V-114 Closed Danger FPC-V-115A Closed Danger FPC-V-116A Closed Danger Breaker 9B for FPC-P-1A on MC-7B-B Open Danger Breaker 1C for FPC-V-181A on MC-7B-A Open Danger FPC-V-150A and / or FPC-V-187A Open Danger Control Switch for FPC-P-1A Auto or Auto after Stop Danger or Blue Control Switch for FPC-V-181A Norm or Norm after Close Danger or Blue

DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-1A LO001644 Rev. 0 Page 5 of 6 RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Student correctly identifies the components, component position, and tagging requirements to mechanically and electrically isolate FPC-P-1A.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 15 Minutes / NA COMMENTS:

Evaluator's Signature:

Date:

Page 5 of 6 STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is operating at full power.

It is a Division 1 work week.

Maintenance wants to replace the pipe coupling (3 inch to 6 inch) located at the discharge of FPC-P-1A.

Cue:

You have been directed to determine the clearance order boundary component, required component position, and component tagging requirement necessary to perform work on the coupling downstream of FPC-P-1A.

JPM ANSWER SHEET Page 6 of 6 The following is required to perform work on coupling downstream of FPC-P-1A:

COMPONENT REQUIRED POSITION TYPE OF TAG (BLUE/DANGER/CAUTION

)

When completed, hand this sheet to the examiner.

INSTRUCTIONAL COVER SHEET PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE - ADMIN LESSON TITLE DETERMINE MINIMUM AND MAXIMUM STAY TIMES LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001632 Rev. No.

0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 5/29/08 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

JPM ANSWER SHEET LO001632 Rev. 0 Page 1 of 6 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

Each student should have access to a calculator.

Have a copy of the RWP for student.

JPM Instructions:

Verify the current revisions of the procedure against the JPM. If the procedure revisions are different than listed in the JPM, ensure the JPM is still technically correct. If the JPM is not technically correct, the JPM should be revised.

The evaluator document results on the Results of JPM page.

Tools/Equipment: Calculator Safety Items: None Task Number: RO-0022 Validation Time: 10 minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

N / A Location: CLASSROOM NUREG 1123 Ref: 2.3.2 (2.5 / 2.9)

Performance Method: PERFORM

JPM ANSWER SHEET LO001632 Rev. 0 Page 2 of 6 JPM CHECKLIST PROCEDURE VALIDATION Regarding procedure copies for evaluator and student, if the procedure revision is different from that listed on the JPM, verify that the critical task steps are the same.

Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

Columbia is operating in MODE 1 at full power. You have been selected to work with maintenance personnel on a valve located in contaminated zone in the North East corner of Reactor Building 422 by the R5 sump. Your accumulated dose for the year is 1800 mrem.

INITIATING CUE: Using the high and low values associated with the radiation field you will be working in, answer the questions on the attached sheet. When completed, hand the sheet to the examiner.

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and student actions Determines R5 sump location on Survey Map Refers to RWP and determines the valve is in a High Radiation area.

S / U

• High rad area radiation levels are 100 mrem/hr to 1000 mrem/hr S / U

• Administrative dose limit at Columbia is 2 Rem (2000 mrem)

S / U

• Calculates remaining dose to achieve admin dose limit in a high radiation area 2000 - 1800 = 200 mrem to dose admin limit S / U

• Calculates minimum time to exceeding admin dose limit Question #1 - The minimum time to get 200 mrem in a 1000 mrem area is 1/5th of an hour which is 12 minutes.

Start time is 0800, therefore you could exceed your admin dose limit at 0812 (accept 0811 to 0814)

S / U

• JPM ANSWER SHEET LO001632 Rev. 0 Page 3 of 6

• Items are Critical Steps Comments Element Standard Sat/Unsat Calculates maximum time to exceeding admin dose limit Question #2 - The maximum time to get 200 mrem (at 100 mrem/hr) would be 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Start time is 0800 therefore the maximum stay time is until 1000 (accept 0955 to 1005).

S / U

• Termination Criteria: Student hands the completed form to the examiner.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

JPM ANSWER SHEET LO001632 Rev. 0 Page 4 of 6 RESULTS OF JPM:

DETERMINE MINIMUM AND MAXIMUM STAY TIMES Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Fills in blanks on attached sheet indicating that 0812 is the earliest time and 1200 is the latest time before exceeding Admin Dose Limit.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 10 Minutes / N / A COMMENTS:

Evaluator's Signature:

Date:

JPM ANSWER SHEET LO001632 Rev. 0 Page 5 of 6 STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is operating in MODE 1 at full power.

You have been selected to work with maintenance personnel on a valve located in the contamination zone in the North East corner of Reactor Building 422 by the R5 sump.

Your accumulated dose for the year is 1800 mrem.

Cue:

Using the high and low values associated with the radiation field you will be working in, answer the two questions on the attached sheet.

When completed, hand the sheet to the examiner.

JPM ANSWER SHEET LO001632 Rev. 0 Page 6 of 6 Use the HIGH and LOW values associated with the radiation field you will be working in to answer the following questions:

If the job starts at 0800.

3. what time represents the earliest time that you could exceed Columbias administrative dose limit?

4. what time represents the latest time that you could stay in the area and still not exceed Columbias administrative dose limit?

When completed, hand this sheet to the examiner.

INSTRUCTIONAL COVER SHEET PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE - SRO ADMIN LESSON TITLE DETERMINATION OF SHIFT STAFFING AND OVERTIME RESTRICTIONS LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001643 Rev. No.

0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/2/08 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

JPM ANSWER SHEET LO001643 Rev. 0 Page 1 of 7 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

JPM Instructions:

Verify the current revisions of each drawing against the JPM. If the drawings are a different revision than listed in the JPM, ensure the JPM is still technically correct. If the JPM is not technically correct, the JPM should be revised.

The evaluator document results on the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: SRO-0002 Validation Time: 15 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

PPM 1.3.27 Rev. 27 Location: CLASSROOM OR SIMULATOR NUREG 1123 Ref: 2.1.5 (3.9)

Performance Method: PERFORM

JPM ANSWER SHEET LO001643 Rev. 0 Page 2 of 7 JPM CHECKLIST PROCEDURE VALIDATION Regarding procedure copies for evaluator and student, if the procedure revision is different from that listed on the JPM, verify that the critical task steps are the same. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

Columbia is operating in MODE 1 and has been on line for 100 days. One of the required on-shift Reactor Operators for the upcoming 0700-1900 shift has called in sick. You have been assigned to find a replacement Reactor Operator.

INITIATING CUE: Given the days and number of hours per day previously worked, determine if any of the following three Reactor Operators could be called into work on the upcoming day shift (0700 - 1900 on October 21st) without prior authorization. On the answer sheet provided, circle your choice for the three operators. When done, hand the completed sheet to the examiner.

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Evaluates work history of RO#1 against hours worked restrictions:

An individual shall not be permitted to work more than:

Third bullet: 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period Determines that RO#1 has worked 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> on October 20th and would exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period requirement if called into work S / U

• Evaluates work history of RO#2 against hours worked restrictions:

An individual shall not be permitted to work more than:

Fourth bullet: 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 168-hour (seven day) period Determines that RO#2 has worked 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in the previous 6 days (October 14 thru October 20th) and would exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 168-hour period requirement if called into work S / U

• Evaluates work history of RO#3 against hours worked restrictions:

An individual shall not be permitted to work more than:

16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 168-hour period Determines that RO#3 would not exceed any of the hours worked restrictions if called into work S / U

• JPM ANSWER SHEET LO001643 Rev. 0 Page 3 of 7 Termination Criteria: Student circles either Can or Cannot be called into work for the three Reactor Operators and hands completed sheet to the exam proctor.

RECORD TERMINATION TIME: _________

Transfer the following information to the Results of JPM page: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.

JPM ANSWER SHEET LO001643 Rev. 0 Page 4 of 7 RESULTS OF JPM:

DETERMINATION OF SHIFT STAFFING AND OVERTIME RESTRICTIONS Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Circles CAN NOT be called into work for RO#1 and RO#2 and CAN be called into work for RO#3.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 10 Minutes / NA COMMENTS:

Evaluator's Signature:

Date:

JPM ANSWER SHEET LO001643 Rev. 0 Page 5 of 7 STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is operating in MODE 1 and has been on line for 100 days.

One of the required on-shift Reactor Operators for the upcoming 0700-1900 shift has called in sick.

You have been assigned to find a replacement Reactor Operator.

Cue:

Given the days and number of hours per day previously worked, determine if any of the following three Reactor Operators could be called into work on the upcoming day shift (0700 - 1900 on October 21st) without prior authorization.

On the answer sheet provided, circle your choice for the three Reactor Operators.

When done, hand the completed sheet to the examiner.

JPM ANSWER SHEET LO001643 Rev. 0 Page 6 of 7 Work history for Reactor Operator #1:

October 14 Worked 0700 - 2200 October 15 OFF October 16 Worked 0700 - 1900 October 17 Worked 0700 - 1900 October 18 Worked 0700 - 1900 October 19 OFF October 20 Worked 0700 - 2200 Work history for Reactor Operator #2:

October 14 OFF October 15 Worked 0700 - 1500 October 16 Worked 0700 - 1900 October 17 Worked 0700 - 1900 October 18 Worked 0700 - 1900 October 19 Worked 0700 - 1900 October 20 Worked 0700 - 1900 Work history for Reactor Operator #3:

October 14 Worked 0700 - 2200 October 15 Worked 0700 - 1500 October 16 Worked 0700 - 1900 October 17 OFF October 18 Worked 0700 - 1900 October 19 Worked 0700 - 1900 October 20 Worked 0700 - 1900

JPM ANSWER SHEET LO001643 Rev. 0 Page 7 of 7 ANSWER SHEET Circle your choice:

Reactor Operator #1:

CAN BE CALLED INTO WORK OR CAN NOT BE CALLED INTO WORK Reactor Operator #2:

CAN BE CALLED INTO WORK OR CAN NOT BE CALLED INTO WORK Reactor Operator #3:

CAN BE CALLED INTO WORK OR CAN NOT BE CALLED INTO WORK When completed, hand this sheet to the examiner.

JPM ANSWER SHEET INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE DETERMINE IF MODE CHANGE IS ALLOWED (ADMIN)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001639 Rev. No. 0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 06/23/08 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

DETERMINE IF MODE CHANGE IS ALLOWED LO001639 Rev. 0 Page 1 of 6 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

ADMIN JPM, NO SETUP NEEDED Special Setup Instructions:

Need a copy of PPM 3.1.2 Startup Flow Chart; Need a copy of current Technical Specifications Volume.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: N/A Safety Items: N/A Task Number: SRO-0116 Validation Time: 10 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

TS 3.8.1 and PPM 3.1.2 Location: ANY NUREG 1123 Ref: 2.4.40 2.3 / 4.0 Performance Method: PERFORM

DETERMINE IF MODE CHANGE IS ALLOWED LO001639 Rev. 0 Page 2 of 6 JPM CHECKLIST PROCEDURE VALIDATION Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

Columbia is operating in MODE 4. A startup is underway following a short maintenance outage. The following conditions exist:

• SRMs have normal indications and recorder speed is at 1,000 mm/hr

• All IRM indications are normal on Range 1 except IRM-A which has an upscale trip and is bypassed and recorder speed is at 1,000 mm/hr

• The Minimum and Maximum ECPs have been entered on the Control Rod Sequence Pull Sheet in the Control Room

• A complete set of PPM 3.1.10 readings have been taken

• OSP-INST-H101s have been completed and satisfied to enter MODE 2

• The Barrier Impairment Log has no MODE change limiting conditions

• The Surveillance in Progress Log shows no MODE change limiting conditions

• The LCO/INOP/RFO Log shows no limiting conditions for a MODE change

• HPCS-P-2 is out of service for motor oil replacement

• All surveillances are completed and up to date

• There are 3 inoperable control rods that are disarmed at position 00

• A panel walk down has been completed

• Offgas system warmup is in progress per SOP-OG-START

• All ECCS systems are in a standby lineup

• RRC-P-1A and RRC-P-1B are operating at 15 hz.

• Containment was de-inerted

• A risk assessment has been completed which established risk management actions for the following Out Of Service equipment:

o Remote Shutdown Panel Power Transfer Switch associated with MS-RV-4A, MS-RV-4B, and MS-RV-4C o Lower Drywell Spray Outboard Isolation Valve, RHR-V-16B INITIATING CUE:

A mode change to MODE 2 is planned. Determine if the change to MODE 2 is allowed.

Notify the Shift Manager (examiner) of your determination and justifications by filling out your justification on the attachment provided.

DETERMINE IF MODE CHANGE IS ALLOWED LO001639 Rev. 0 Page 3 of 6

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Review PPM 3.1.2, Startup flow chart Notes HPCS-P-2 being OOS inops the HPCS DG.

S / U

• Review PPM 3.1.2, Startup flow chart Reviews Tech Spec 3.8.1 and determines that LCO B is applicable which requires HPCS DG to be restored to operable status in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Notes that HPCS DG is required to be operable in MODE 2 and that TS 3.0.4b is not applicable to DGs.

Determines that a Mode change is NOT allowed and fills out this reason on attachment provided.

S / U

• Termination Criteria: Student hands filled out attachment to examiner.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

DETERMINE IF MODE CHANGE IS ALLOWED LO001639 Rev. 0 Page 4 of 6 RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Attachment is filled out indicating that a mode change is NOT allowed because HPCS-P-2 is out of service.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev.

Validation/Critical JPM Completion 10 Minutes / NA COMMENTS:

Evaluator's Signature:

Date:

LO001639 Rev. 0 Page 5 of 6 STUDENT JPM INFORMATION CARD Initial Conditions: Columbia is operating in MODE 4. A startup is underway following a short maintenance outage. The following conditions exist:

• SRMs have normal indications and recorder speed is at 1,000 mm/hr

• All IRM indications are normal on Range 1 except IRM-A which has an upscale trip and is bypassed and recorder speed is at 1,000 mm/hr

• The Minimum and Maximum ECPs have been entered on the Control Rod Sequence Pull Sheet in the Control Room

• A complete set of PPM 3.1.10 readings have been taken

• OSP-INST-H101s have been completed and satisfied to enter MODE 2

• The Barrier Impairment Log has no MODE change limiting conditions

• The Surveillance in Progress Log shows no MODE change limiting conditions

• The LCO/INOP/RFO Log shows no limiting conditions for a MODE change

• HPCS-P-2 is out of service for motor oil replacement

• All surveillances are completed and up to date

• There are 3 inoperable control rods that are disarmed at position 00

• A panel walk down has been completed

• Offgas system warmup is in progress per SOP-OG-START

• All ECCS systems are in a standby lineup

• RRC-P-1A and RRC-P-1B are operating at 15 hz.

• Containment was de-inerted

• A risk assessment has been completed which established risk management actions for the following Out Of Service equipment:

o Remote Shutdown Panel Power Transfer Switch associated with MS-RV-4A, MS-RV-4B, and MS-RV-4C o Lower Drywell Spray Outboard Isolation Valve, RHR-V-16B Cue:

A mode change to MODE 2 is planned.

Determine if the change to MODE 2 is allowed.

Notify the Shift Manager (examiner) of your determination by filling in your justification on the attachment provided.

LO001639 Rev. 0 Page 6 of 6 MODE CHANGE IS ALLOWED:

MODE CHANGE IS NOT ALLOWED:

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE JOB PERFORMANCE MEASURE - ADMIN LESSON TITLE DETERMINATION IF MOVEMENT OF HEAVY LOAD OVER SPENT FUEL POOL CAN OCCUR LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001630 Rev. No. 0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 5/27/08 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

DETERMINE IF LOAD CAN BE MOVED OVER SPENT FUEL POOL LO001630 Rev. 0 Page 1 of 6 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

Have a copy of the following for each student:

PPM 1.3.40 pages 1-7 and attachment 7.5 LCS 1.9.2 including graph JPM Instructions:

Verify the current revisions of each drawing against the JPM. If the drawings are a different revision than listed in the JPM, ensure the JPM is still technically correct. If the JPM is not technically correct, the JPM should be revised.

The evaluator document results on the Results of JPM page.

Tools/Equipment: N/A Safety Items: N/A Task Number: SRO-0059; SRO-0096 Validation Time: 15 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

PPM 1.3.40 Rev. 18 LCS 1.9.2 Rev. 44 Location: CLASSROOM OR SIMULATOR NUREG 1123 Ref: 2.2.26 2.5 / 3.7 Performance Method: PERFORM

DETERMINE IF LOAD CAN BE MOVED OVER SPENT FUEL POOL LO001630 Rev. 0 Page 2 of 6 JPM CHECKLIST PROCEDURE VALIDATION:

Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

Columbia is shutdown for a refueling outage with the following plant parameters given:

Fuel shuffle has been completed with core verification taking place The Spent Fuel Pool has been verified to be subcritical for GT 24 Hrs The following equipment is OOS:

RHR-P-2C HPCS System including the HPCS-DG RRA-RIS-3 Reactor Building In-Plant Air Particulate Monitor REA-RIS-609A/B & C/D Reactor Building Exhaust Plenum RMS PRM-RE-1A, 1B & 1C Reactor Building Low, Intermediate, and High Range Stack Monitor TRA-RIS-1 Turbine Building In-Plant Air Particulate Monitor INITIATING CUE:

The Refueling Floor Supervisor has just requested permission for a load of 1190 lbs to be carried 5 feet over the Spent Fuel Pool.

On the next page, indicate your intention of allowing the move over the Spent Fuel Pool by initialing where indicated OR indicate your intention of disallowing the move over the Spent Fuel Pool and your associated reason.

When done, hand the completed sheet to the examiner.

DETERMINE IF LOAD CAN BE MOVED OVER SPENT FUEL POOL LO001630 Rev. 0 Page 3 of 6

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Refers to PPM 1.3.40 Attachment 7.5 and determines:

1. 1 is answered yes - the requirement is satisfied (SPF is subcritical for GT 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> - given in initial conditions)

1. 2 is answered yes - the load meets height and weight restrictions of LCS 1.9.2 1190 lbs at a height of 5 ft. puts you in the permitted area of graph

1. 3 is answered NO as there are no operational instruments to monitor an offsite release S / U S / U S / U

• Termination Criteria: Student hands the examiner the completed attached sheet.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

DETERMINE IF LOAD CAN BE MOVED OVER SPENT FUEL POOL LO001630 Rev. 0 Page 4 of 6 RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Candidate indicates that the move of 1190 lbs 5 ft. over the spent fuel pool is NOT allowed due to answering question #3 of PPM 1.3.40 attachment 7.5 as the requirement is NOT satisfied.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 15 Minutes / N / A COMMENTS:

Evaluator's Signature:

Date:

LO001630 Rev. 0 Page 5 of 6 STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is shutdown for a refueling outage with the following plant parameters given:

Fuel shuffle has been completed with core verification taking place The Spent Fuel Pool has been verified to be subcritical for GT 24 Hrs The following equipment is OOS:

RHR-P-2C HPCS System including the HPCS-DG RRA-RIS-3 Reactor Building In-Plant Air Particulate Monitor REA-RIS-609A/B & C/D Reactor Building Exhaust Plenum RMS PRM-RE-1A, 1B & 1C Reactor Building Low, Intermediate, and High Range Stack Monitor TRA-RIS-1 Turbine Building In-Plant Air Particulate Monitor Cue:

The Refueling Floor Supervisor has just requested permission for a load of 1190 lbs to be carried 5 feet over the Spent Fuel Pool.

On the next page, indicate your intention of allowing the move over the Spent Fuel Pool by initialing where indicated OR indicate your intention of disallowing the move over the Spent Fuel Pool and your associated reason.

When done, hand the completed sheet to the examiner.

LO001630 Rev. 0 Page 6 of 6 YES - I would give permission for the 1190 lb load to be moved 5 foot over the Spent Fuel Pool as requested by the Refueling Floor Supervisor.

Initials NO - I would NOT give permission for the 1190 lb load to be moved 5 foot over the Spent Fuel Pool as requested by the Refueling Floor Supervisor for the following reason:

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE PERFORM QEDPS (ADMIN) (TC)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001631 Rev. No.

0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 05/28/08 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

LO001631 Rev. 0 Page 1 of 5 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Any IC. If in classroom need access to ARP for moisture alarm.

Special Setup Instructions:

Log onto a Computer that has the QEDPS program on it.

The computer should be connected to a printer. Ensure paper is loaded in the printer.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: Computer / Printer Safety Items: None Task Number: SRO-0029 Validation Time: 10 Minutes Prerequisite Training: N/A Time Critical: Yes - 15 Minutes PPM

Reference:

PPM 13.8.1 Rev. 28 Location: Simulator / Classroom NUREG 1123 Ref: 2.3.10 (2.9 / 3.3)

Performance Method: Perform

LO001631 Rev. 0 Page 2 of 5 JPM CHECKLIST PROCEDURE VALIDATION:

Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

The plant has experienced an event that has resulted in the following conditions:

Columbia scrammed one hour and 45 minutes ago. An unisolable leak in the RWCU system has existed for the past two hours and 25 minutes. B SGT train is tagged out for maintenance. There is a HEPA A-1 OUTLET MOIST HIGH annunciator alarmed on H13-P827. Reactor Building radiation levels on RE-RMS-1A indicate 1.0 E+06 cps and RE-RMS-1B indicates 1.9 E+04 cps. Standby Gas Treatment flow is 4850 cfm. Wind direction is from 130°, wind speed is 7 mph, and the stability class is F.

INITIATING CUE: You have been directed to perform a QEDPS using the computer based QEDPS program. Print out the QEDPS and associated map and hand them to your examiner.

When done - quit the QEDPS program and log off of the computer.

This is a time critical JPM and your time starts now.

• Items are Critical Steps Comments ELEMENT Standard Sat/Unsat RECORD START TIME: __________

Low range off scale high Indicates Monitor used Checks RB Stack Intermediate Range S / U

• Enters Monitor reading Enters RE-RMS-1B indication of 1.9e+04 (or 19000)

S / U

• SM-8 locked out STANDBY GAS TREATMENT Checks One Train S / U

• SGT FILTER STATUS Checks Damaged S / U

• Moisture alarm SGT FLOW RATE Enters 4850 S / U

• PROJECTED RELEASE DURATION Enters 5 hrs 0 minutes S / U

• Release duration is 2 hr 25 min.

rounded up to three hrs and 2 hrs added for a total of 5 hrs TIME SINCE REACTOR SHUTDOWN Enters 1 hr and 45 minutes S / U

• LO001631 Rev. 0 Page 3 of 5

• Items are Critical Steps Comments ELEMENT Standard Sat/Unsat METEOROLOGICAL DATA:

Wind Direction Wind Speed Stability Class Enters:

130 7

F S / U

• S / U

• S / U

• RUNS QEDPS Depresses RUN icon S / U

• Prints QEDPS Depresses PRINT icon on QEDPS screen S / U

• Prints associated Map Depresses MAP icon then the PRINT icon S / U

• Termination Criteria: Student hands the printed out QEDPS and associated MAP to the examiner.

IF NOT DONE - INFORM THE STUDENT TO QUIT THE QEDPS PROGRAM AND LOG OFF OF THE COMPUTER.

RECORD TERMINATION TIME: _________

Transfer the following information to the Results of JPM page: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.

LO001631 Rev. 0 Page 4 of 5 RESULTS OF JPM:

PERFORM QEDPS AND DETERMINE EAL Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Accurately enters given plant parameters in the QEDPS program to calculate thyroid CDE Rate of 50.8 at 1.2 miles and associated map shows release into Section 4.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 10 Minutes / N/A COMMENTS:

Evaluator's Signature:

Date:

LO001631 Rev. 0 Page 5 of 5 STUDENT JPM INFORMATION CARD Initial Conditions:

The plant has experienced an event that has resulted in the following conditions:

• Columbia was scrammed one hour and forty five minutes ago

• An unisolable leak in the RWCU system has existed for the past two hours and twenty five minutes

• B SGT train is tagged out for maintenance

• There is a HEPA A-1 OUTLET MOIST HIGH annunciator alarmed on H13-P827

• Reactor Building radiation levels on RE-RMS-1A indicate 1.0 E+06 cps

• Reactor Building radiation levels on RE-RMS-1B indicate 1.9 E+04 cps

• SGT flow is 4850 cfm

• Wind direction is from 130°

• Wind speed is 7 mph

• Stability Class is F Cue:

You have been directed to perform a QEDPS using the computer based QEDPS program.

Print out the QEDPS and associated map and hand them to your examiner.

When done - quit the QEDPS program and log off of the computer.

THIS IS A TIME CRITICAL JPM AND YOUR TIME START NOW

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE RECLASSIFY A SECURITY EVENT (SAE) (TC) (ADMIN)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001569 Rev. No. 1 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 06/20/06 REVISED BY Ron Haydenf DATE 05/28/08 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

LO001569 Rev. 1 Page 1 of 6 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

Have a blank CNF form, a copy of PPM 13.1.1 EAL Chart, and PPM 13.1.1A available.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: SRO-0529 Validation Time: 15 minutes Prerequisite Training: None Time Critical: 30 minutes PPM

Reference:

13.1.1 Rev. 36; PPM 13.1.1A Rev. 19 Location: Any NUREG 1123 Ref: 2.4.28 2.3 / 3.3 Performance Method: Perform

LO001569 Rev. 1 Page 2 of 6 JPM CHECKLIST PROCEDURE VALIDATION Regarding procedure copies for evaluator and student, if the procedure revision is different from that listed on the JPM, verify that the critical task steps are the same.

Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

The plant is operating at 100% power. One hour ago, the FBI notified security and plant management that a mid-western terrorist group has threatened to interfere with the operation of Columbia Generating Station. The FBI considers this a credible threat. An Unusual Event was declared 50 minutes ago.

INITIATING CUE:

Five minutes ago, security called and notified you that an explosive device has been discovered in the A Service Water Pump House. The device is of sufficient size that if it should detonate, SW-P-1A would be destroyed. All personnel have been evacuated from the area.

Meteorological data:

• Stability class E

• Wind direction is from 245°

• Wind speed 4 mph

• No precipitation You are the Emergency Director. Determine if an EAL change is required. The electronic CNF form is not available. Complete a paper CNF form if necessary and present the completed form to the examiner. If a CNF is not required, initial the line where indicated on the attached sheet and present that sheet to the examiner.

THIS IS A TIME CRITICAL JPM AND YOUR TIME STARTS NOW Candidate is allowed 15 minutes to determine if a change in classification is needed and 15 minutes to complete the CNF form for a total of 30 minutes.

LO001569 Rev. 1 Page 3 of 6

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CNF Form is completed as follows:

Block 1 - checks Emergency or Drill S / U Block 2 - Fills in 2 S / U Block 3 - Fills in his/her name and a phone number S / U Checks block 4.b (Reclassification) and fills in current Date and Time S / U

• Checks block 5.c (Site Area Emergency)

S / U

• Block 6 left blank S / U Block 7: Enters Wind Speed = 4 Wind Direction: from = 245° Precipitation = No block checked Stability Class = E S / U S / U S / U S / U Block 8 checks No Release S / U Block 9 checks N/A S / U Block 10 checks N/A S / U Block 11 checks No S / U Block 12:

EAL # 9.1.S.1 or 9.1.S.2 Description - Similar to Bomb in SW pump house S / U

• S / U

• Complete the CNF Form Block 13: Checks a, b or c S / U Termination Criteria: Student presents the completed CNF to the examiner.

LO001569 Rev. 1 Page 4 of 6

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD TERMINATION TIME: _________

RESULTS OF JPM:

RECLASSIFY A SECURITY EVENT Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Reclassifies the security event as a Site Area Emergency (9.1.S.1 or 9.1.S.2) and completes the CNF with required information.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 15 Minutes / 30 minutes COMMENTS:

LO001569 Rev. 1 Page 5 of 6 Evaluator's Signature:

Date:

STUDENT JPM INFORMATION CARD Initial Conditions:

The plant is operating at 100% power. One hour ago, the FBI notified security and plant management that a mid-eastern terrorist group has threatened to interfere with the operation of Columbia Generating Station. The FBI considers this as a credible threat. An Unusual Event was declared 50 minutes ago.

LO001569 Rev. 1 Page 6 of 6 Cue:

Five minutes ago, security called and notified you that an explosive device has been discovered in the A Service Water Pump House. The device is of sufficient size that, if it should detonate, SW-P-1A would be destroyed. All personnel have been evacuated from the area.

Meteorological data:

• Stability class is E

• Wind direction is from 245°

• Wind speed is 4 mph

• No precipitation You are the Emergency Director. Determine if an EAL change is required.

The electronic CNF form is not available. Complete a paper CNF form if necessary and present the completed form to the examiner.

If a CNF is not required, initial the line where indicated on the attached sheet and present that sheet to the examiner.

THIS IS A TIME CRITICAL JPM AND YOUR TIME STARTS NOW

LO001569 Rev. 1 Page 7 of 6 Based on the event presented, I have determined that an upgrade from the Unusual Event is required and I have completed a CNF Form.

Initials Based on the event presented, I have determined that an upgrade from the Unusual Event is not required.

Initials

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE SHUTDOWN DG-2; FAILURE TO STOP; TRIP DG-2 USING MECHANICAL OVERSPEED TRIP (Plant, Faulted)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LR001663 Rev. No. 3 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 11/2/05 REVISED BY Ron Hayden DATE 6/10/08 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

LR001663 Rev.3 Page 1 of 7 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

N/A JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: PPE Task Number: RO-0429; 1297 EO-0671; 2091 Validation Time: 15 Minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

SOP-DG2-SHUTDOWN Section 5.1 Rev. 7 Location: PLANT - DG-2 Room NUREG 1123 Ref: 264000A4.04 (3.7 3.7)

Performance Method: Simulate

LR001663 Rev.3 Page 2 of 7 JPM CHECKLIST PROCEDURE VALIDATION Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

DG-2 was started as part of an engineering test procedure. There are no ECCS Signals present. Munro Control Center has been informed of the intent to remove DG-2 from service. DG-2 is not required to be operable.

INITIATING CUE: The CRS has directed you to locally shutdown DG-2 per SOP-DG2-SHUTDOWN.

Inform the CRS when DG-2 has been shutdown. The performance of this JPM will be simulated. Control manipulations will not be performed.

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and student actions.

Step 5.1.1 VERIFY there are no ECCS signals present (Annunciator 4.800.C5-1.2 clear)

Given in Initial Conditions N / A Step 5.1.2 Notify the Munro Control Center, Mead, WA, of the intent to remove the diesel generator from the distribution system Given in Initial Conditions N / A Step 5.1.3 If shutting down from the Control Room..

Diesel Room Shutdown - N / A N / A Step 5.1.4a IF shutting down from the DIESEL ROOM, THEN PERFORM the following:

Otherwise, N/A VERIFY the Diesel Engine Control Selector is in the LOCAL position (E-CP-DG/RP2)

Observes the Diesel Engine Control Selector is in the CONTROL ROOM position S / U CUE: When checked - cue that the Diesel Engine Control Selector is in the Control Room position.

Simulates placing the Diesel Engine Control Selector in the LOCAL position S / U

• LR001663 Rev.3 Page 3 of 7

• Items are Critical Steps Comments Element Standard Sat/Unsat Step 5.1.4b PLACE CB-DG2/8 Mode Selector switch in the LOCAL position (H13-P800)

Simulates contacting the Control Room and requests they place CB-DG2/8 Mode Selector switch in the LOCAL position S / U CUE: When checked inform the student the mode selector switch is in the Local position.

CUE: When checked DG-W-DG2/L indicates 400 KW.

Step 5.1.4c GRADUALLY REDUCE DG-2 output to 200 KW, over approximately a one minute period, using Diesel Gen 2 Governor control switch Simulates lowering output to 200 KW using the governor control switch S / U CUE: If lowered properly inform student DG-W-DG2/L now indicates 200 KW.

CUE: When checked DG-VARM-DG2/LOC indicates 300 KVAR.

Step 5.1.4d REDUCE reactive load to 200 KVAR using Diesel Gen 2 Voltage Regulator control switch Simulates lowering reactive load to 200 KVAR using Voltage Regulator control switch S / U CUE: If lowered properly inform student DG-VARM-DG2/LOC now indicates 200 KVAR.

Step 5.1.5 OPEN CB-DG2/8, Diesel Gen 2 output breaker (at the controlling location)

Simulates opening CB-DG2/8 by turning E-CB-DG2/8 local control switch to the TRIP position (CCW)

S / U

• Step 5.1.6 Verify E-CB-DG2/8 close permit light is illuminated (H13-P800)

Simulates contacting the Control Room and verifies the close permit light is illuminated on E-CB-DG2/8 S / U CUE: When checked - inform the student the close permit light is illuminated.

Step 5.1.7 If E-CB-DG2/8 close permit light is illuminated, then enter DG-2 as operable in the Plant Logging System Contacts Control Room to inform them DG-2 is operable and to enter it in Plant Logging System S / U CUE: When checked output voltage indicates 4300 volts.

Step 5.1.8 ADJUST the generator output voltage to 4200 volts using Diesel Gen 2 Voltage Regulator Simulates adjusting output voltage to 4200 volts using the Voltage Regulator S / U CUE: If lowered properly inform student output voltage now indicates 4200 volts.

LR001663 Rev.3 Page 4 of 7

• Items are Critical Steps Comments Element Standard Sat/Unsat CUE: When checked frequency indicates 62 Hz.

Step 5.1.9 ADJUST frequency to 60 Hz using Diesel Gen 2 Governor control switch Simulates adjusting frequency to 60 Hz using the Governor control switch S / U CUE: If lowered properly inform student frequency now indicates 60 Hz.

Step 5.1.10 PLACE Engine Speed Selector switch to IDLE Simulates placing the Engine Speed Selector to IDLE S / U

• Step 5.1.11 LOG the time in the DG Log in the Plant Logging System Simulates contacting the Control Room to log time S / U Step 5.1.12 VERIFY DG-2 speed at 375-425 RPM on DG-SI-DG2 (E-CP-DG/RP2)

Verifies speed is between 375 and 425 S / U CUE: When checked engine speed is 400 rpm.

Step 5.1.13 ALLOW the diesel to idle for at least 15 minutes Verbalizes intention to wait 15 minutes S / U CUE: TIME COMPRESSION - Inform student 15 minutes has elapsed.

Step 5.1.14 STOP DG-2 by one of the following methods: N/A the other.

• IF DG-2 is being operated from the Control Room, THEN PLACE the Diesel Gen 2 control switch to STOP

• IF DG-2 is being operated from E-CP-DG/RP2, THEN DEPRESS the Diesel Engine 1B1/1B2 Stop pushbutton Simulates depressing the green 1B1/1B2 stop pushbutton S / U

• CUE: Inform the student that DG2 continues to operate.

CUE: If the Control Room is contacted, acknowledge the report and as the CRS, direct the student to trip DG2 utilizing the Mechanical Overspeed Trip.

Student will go to where procedure is in the room and find that section 5.3 should now be performed.

When student selects section 5.3 hand him section 5.3.

LR001663 Rev.3 Page 5 of 7

• Items are Critical Steps Comments Element Standard Sat/Unsat Step 5.3.1 LOCATE the mechanical overspeed trip mechanism on engine 1B2, preferred (engine 1B1, alternate)

Locates overspeed trip mechanism on engine 1B2 S / U

• Step 5.3.2 UNLATCH the engine overspeed trip reset lever by pushing it down onto the overspeed trip limit switch.

HOLD the reset lever in this downward unlatched position Simulates unlatching the engine overspeed trip reset lever by pushing it down onto the overspeed trip limit switch and holds it in this position S / U

• Step 5.3.3 While holding the reset lever in the unlatched position, PUSH/ROTATE the small trip lever away from the solenoid trip mechanism. The trip lever must be rotated in the CW direction when looking at it from the governor actuator's position Simulates holding the reset lever in the unlatched position and pushing/rotating the small trip lever away from the solenoid trip mechanism.

Verbalizes that the lever is rotated in the clockwise direction when looking at it from the governor actuator's position S / U

• Step 5.3.4 RELEASE the reset lever and it should rotate to the TRIPPED position Simulates releasing lever and verbalizes that it should rotate to the TRIPPED position S / U

• Step 5.3.5 VERIFY both engines trip. If engine 1B1 (1B2) fails to trip, MECHANICALLY TRIP the engine using the method described above Verifies both engines tripped S / U Cue: If checked inform student that both engines are tripped.

Step 5.3.6 VERIFY both engines coast down, and stop rotating Verifies both engines coast down and eventually stop S / U Termination Criteria: When the student verbalizes that he would verify both engines have coasted down and have stopped rotating - inform the student that the termination point of the JPM has been reached.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

LR001663 Rev.3 Page 6 of 7 RESULTS OF JPM:

SHUTDOWN DG-2; FAILURE TO STOP; TRIP DG-2 USING MECHANICAL OVERSPEED TRIP Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: DG-2 is tripped utilizing the mechanical overspeed trip mechanism per SOP-DG2-SHUTDOWN.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 15 Minutes / NA COMMENTS:

Evaluator's Signature:

Date:

LR001663 Rev.3 Page 7 of 7 STUDENT JPM INFORMATION CARD Initial Conditions:

DG-2 was started as part of an engineering test procedure.

There are no ECCS signals present.

Munro Control Center has been informed of the intent to remove DG-2 from service.

DG-2 is not required to be operable.

Cue:

The CRS has directed you to locally shutdown DG-2 per SOP-DG2-SHUTDOWN.

Inform the CRS when DG-2 has been shutdown.

THE PERFORMANCE OF THIS JPM WILL BE SIMULATED.

CONTROL MANIPULATIONS WILL NOT BE PERFORMED.

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE RESTART OF RPS-MG-1 AND REPOWER RPS BUS (FAULTED) (PLT)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001641 Rev. No. 1 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Donald Hughes DATE 06/10/08 REVISED BY Ron Hayden DATE 10/21/08 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

LO001641 Rev. 0 Page 1 of 7 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

None Special Setup Instructions:

None JPM Instructions:

Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.

Evaluator and student shall use the current procedure. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.

Tools/Equipment: None.

Safety Items: None Task Number: RO-0248 Validation Time: 12 Minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

SOP-RPS-START Section 5.1 and 5.3 Rev. 0 Location: Plant NUREG 1123 Ref: 212000A2.01 (3.7/3.9)

Performance Method: Simulate

LO001641 Rev. 0 Page 2 of 7 JPM CHECKLIST PROCEDURE VALIDATION Verify the revision number of procedure copies for evaluator and student. If the procedure revision is different from that listed on the JPM, the critical tasks must be verified. The evaluator copy may be used for marking step completion and comments.

INITIAL CONDITIONS:

RPS Division A has been de-energized due to a fault. The fault has been identified and corrected. The RPS-MG-1 supply breaker (RPS-DISC-7A1B) on MC-7A is closed.

INITIATING CUE:

The CRS has directed you to restart RPS-MG-1 and repower the Division 1 RPS bus in accordance with SOP-RPS-START section 5.1 and 5.3. Inform the CRS when the RPS bus has been re-powered. The performance of this JPM is simulated. Control manipulations will not be performed.

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and operator actions for steps without a separate cue Step 5.1.1 Verify RPS-D1SC-7A1B is CLOSED (RPS Bus Mtr Gen MG-1 Supply Bkr) (E-MC-7A)

Given in initial conditions N / A Step 5.1.2a Perform the following at E-CP-C72/S001A (RPS-MG-1 Control Panel):

Verify the MOTOR OFF indicating light illuminated (green)

Observes the green MOTOR OFF indicating light is illuminated S / U CUE: Green light is illuminated, red light is extinguished Step 5.1.2b Verify RPS-CB-MG1 OPEN (Generator Output Breaker)

Observes RPS-CB-MG1 is open with lever in OFF position S / U CUE: The lever for RPS-CB-MG1 is in the OFF position Step 5.1.2c DEPRESS and HOLD RPS-RMS-MG1/ START, pushbutton (MOTOR ON)

Simulates depressing and holding RPS-RMS-MG1/

START, MOTOR ON pushbutton depressed S / U

• Step 5.1.2d Verify the following:

• MOTOR OFF indicating light extinguished (green)

Observes the green MOTOR OFF indicating light extinguishes and the red MOTOR ON indicating light S / U

LO001641 Rev. 0 Page 3 of 7

• Items are Critical Steps Comments Element Standard Sat/Unsat

• MOTOR ON light illuminates (red) is illuminated CUE: Red light is illuminated, Green light is extinguished CUE: If asked, the RPS MG set is up to speed (should take LT 5 seconds)

Step 5.1.2e When RPS-MG-1 has come up to speed, then release RPS-RMS-MG1/START pushbutton Simulates releasing the MOTOR ON pushbutton when cued that RPS-MG-1 is up to speed S / U

• Step 5.1.2f If voltage is not indicated at rated speed, then momentarily depress RPS-RMS-MG1/START, MOTOR ON pushbutton to reset the trip Verbalizes that voltage indication would be expected S / U

• Cue: When the operator checks voltage, cue that no voltage is indicated.

Step 5.1.2f If voltage is not indicated at rated speed, then momentarily depress RPS-RMS-MG1/START, MOTOR ON pushbutton to reset the overvoltage trip Simulates momentarily depressing the RPS-RMS-MG1/START, MOTOR ON pushbutton S / U

• Cue: When the operator checks voltage, cue that voltage is now indicated on RPS-VM-MG1A.

Step 5.1.2g Verify RPS-VM-MG1A voltage stabilizes at about 120 VAC Observes voltage stabilizes at 120 VAC S / U Cue: When the operator checks voltage, cue that voltage is stable at 120 VAC on RPS-VM-MG1A.

Step 5.1.2h Close RPS-CB-MG1 Simulates closing RPS-CB-MG1 by pushing up on lever to ON S / U

• Step 5.1.3 PROCEED to Section 5.3 Performs section 5.3 as follows:

S / U Step 5.3.1 VERIFY Section 5.1 completed Section 5.1 just completed S / U Step 5.3.2 Obtain required EPA breaker keys from the control room key locker Obtains breaker key# 166 and

1. 168 from CR key locker S / U

• NOTE: The student does not have to go to the control room to obtain keys. Ask where the keys are kept - student should verbalize the keys are in the key locker outside the Shift Manages office.

Step 5.3.3a CLOSE RPS-EPA-3A as follows (EPA Breaker) (RPS-MG2 Room):

VERIFY breaker keylock switch S1 in NORMAL Observes switch S1 on RPS-EPA-3A is in NORMAL S / U

LO001641 Rev. 0 Page 4 of 7

• Items are Critical Steps Comments Element Standard Sat/Unsat Step 5.3.3b VERIFY breaker keylock switch S2 in OPER Observes switch S2 on RPS-EPA-3A is in OPER S / U Step 5.3.3c VERIFY the POWER IN indicator illuminated Observes POWER IN light illuminated S / U CUE: When step below (5.3.3d) is done, the under voltage and under frequency lights are illuminated.

Step 5.3.3d IF any of the following indicators are not extinguished, THEN ROTATE keylock switch S2 to the RESET AND RETURN to OPER:

• OVER VOLTAGE

• UNDER VOLTAGE

• UNDER FREQUENCY

• POWER OUT Rotates the breaker key lock S2 switch to RESET Rotates S2 back to OPER S / U

• CUE: When step below (5.3.3e) is done and if properly reset, the undervoltage and under frequency lights are not illuminated.

Step 5.3.3e VERIFY the following indicators extinguished:

• OVERVOLTAGE

• UNDERVOLTAGE

• UNDERFREQUENCY

• POWER OUT Observes all lights extinguished S / U Step 5.3.3f OPEN RPS-EPA-3A to reset it Resets RPS-EPA-3A by pushes lever fully downward S / U

• Step 5.3.3g Close RPS-EPA-3A Closes RPS-EPA-3A by lifting up on lever S / U

• Step 5.3.3h VERIFY POWER OUT indicator illuminated Observes POWER OUT light illuminated S / U CUE: When checked, the POWER OUT indicator is illuminated.

Step 5.3.4 IF the UNDERVOLTAGE light is illuminated and the breaker is closed, THEN INITIATE a work request Observes UNDERVOLTAGE light out S / U Step 5.3.5a CLOSE RPS-EPA-3C as follows (EPA Breaker) (RPS-MG2 Room):

VERIFY breaker keylock switch S1 in NORMAL Observes switch S1 on RPS-EPA-3C is in NORMAL S / U

LO001641 Rev. 0 Page 5 of 7

• Items are Critical Steps Comments Element Standard Sat/Unsat Step 5.3.5b VERIFY breaker keylock switch S2 in OPER Observes switch S2 on RPS-EPA-3C is in OPER S / U CUE: When checked, the POWER IN indicator is illuminated.

Step 5.3.5c VERIFY the POWER IN indicator illuminated Observes POWER IN light illuminated S / U CUE: When checked, the undervoltage and under frequency lights are illuminated.

Step 5.3.5d IF any of the following indicators are not extinguished, THEN ROTATE keylock switch S2 to the RESET AND RETURN to OPER:

• OVERVOLTAGE

• UNDERVOLTAGE

• UNDERFREQUENCY

• POWER OUT Rotates the breaker key lock S2 switch to RESET Rotates S2 back to OPER S / U

• CUE: If reset properly, the undervoltage and under frequency lights are not illuminated.

Step 5.3.5e VERIFY the following indicators extinguished:

• OVERVOLTAGE

• UNDERVOLTAGE

• UNDERFREQUENCY

• POWER OUT Observes all lights extinguished S / U Step 5.3.5f OPEN RPS-EPA-3C to reset it Resets RPS-EPA-3C by pushes lever fully downward S / U

• Step 5.3.5g Close RPS-EPA-3C Closes RPS-EPA-3C by lifting up on lever S / U

• CUE: When checked, the POWER OUT indicator is illuminated.

Step 5.3.5h VERIFY the POWER OUT indicator illuminated Observes POWER OUT light illuminated S / U Step 5.3.5i IF the UNDERVOLTAGE light is illuminated and RPS-EPA-3C is CLOSED, THEN INITIATE a work request to evaluate Observes UNDER VOLTAGE light out S / U Step 5.3.6 Verify Generator A Feed white power available indicating light illuminated (H13-P610)

Contacts the Control Room and asks if the light is illuminated S / U CUE: When checked, the power available light is illuminated.

Termination Criteria: Student informs the CRS that Division 1(A) RPS bus is powered.

LO001641 Rev. 0 Page 6 of 7

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD TERMINATION TIME: _________

Transfer to JPM Results Page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. Marked Up procedure and remaining JPM pages may be discarded.

LO001641 Rev. 0 Page 7 of 7 RESULTS OF JPM RESTART RPS MG-1 AND REPOWER THE RPS BUS Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: RPS-MG-1 is running and RPS Bus has been re-energized per SOP-RPS-START.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial box)

Validation/Critical Time JPM Completion Time 12 Minutes / NA COMMENTS:

Evaluator's Signature:

Date:

LO001641 Rev. 0 Page 8 of 7 STUDENT JPM INFORMATION CARD Initial Conditions:

RPS Division A has been de-energized due to a fault The fault has been identified and corrected The RPS-MG-1 supply breaker (RPS-DISC-7A1B) on MC-7A is closed.

Cue:

The CRS has directed you to restart RPS-MG-1 and repower the RPS bus in accordance with SOP-RPS-START section 5.1 and 5.3.

Inform the CRS when the RPS bus has been re-powered.

THE PERFORMANCE OF THIS JPM IS SIMULATED.

CONTROL MANIPULATIONS WILL NOT BE PERFORMED.

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE START SW-P-1A ON A CONTROL ROOM EVACUATION (Plant)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001640 Rev. No.

0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 06/10/08 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

Page 1 of 5 LO001640 Rev.0 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

N/A JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: Hardhat, Safety Glasses Task Number: RO-1057 Validation Time: 10 Minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

ABN-CR-EVAC Section 7.13 Rev. 12 Location: Plant NUREG 1123 Ref: 400000 A4.01 (3.1 / 3.0)

Performance Method: Simulate

Page 2 of 5 LO001640 Rev.0 JPM CHECKLIST PROCEDURE VALIDATION Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

The Control Room has been evacuated. Only the immediate actions of ABN-CR-EVAC were completed.

INITIATING CUE: You have been directed to start SW-P-1A per ABN-CR-EVAC attachment 7.13.

Inform the CRS when Attachment 7.13 is completed. Control manipulations will not be performed. All actions and steps will be simulated.

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Step 7.13.1 DETERMINE the discharge pressure of SW-P-1A (SW-PI-32AR)

Observes SW-P-1A discharge pressure on SW-PI-32AR S / U

• CUE: When checked inform student the is no pressure indicated on SW-PI-32AR Step 7.13.2 IF SW-P-1A is already operating, THEN PLACE SW-P-1A control switch to START Determines SW-P-1A is NOT operating and does NOT turn control switch S / U Step 7.13.3 PLACE the following power transfer switches in the EMERG position:

• 46

• 56

• 57

• 58 Simulates turning power transfer switch labeled

• 46

• 56

• 57

• 58 to the EMERG position S / U

• S / U

• S / U

• S / U

• CUE: When checked inform student that SW-V-2A is closed.

Step 7.13.4a IF SW-P-1A is not operating, THEN START SW-P-1A as follows:

If SW-V-2A is open, THEN CLOSE SW-V-2A.

Observes green light illuminated and does not turn switch as valve is closed S / U

Page 3 of 5 LO001640 Rev.0

• Items are Critical Steps Comments Element Standard Sat/Unsat Step 7.13.4b PLACE the control switch for SW-P-1A in START.

Turns control switch for SW-P-1A clockwise to the START position (pump does not start until SW-V-12A is off its closed seat)

S / U

• Step 7.13.4c PLACE the control switch for SW-V-12A to the OPEN position.

Turns control switch for SW-V-12A clockwise to the OPEN position S / U

• CUE: When checked inform student that SW-V-12A indicates mid-position and SW-P-1A starts.

Step 7.13.4d VERIFY SW-P-1A STARTS (when SW-V-12A indicates intermediate position).

Observes red light illuminates and green light extinguishes for SW-P-1A S / U Step 7.13.4e PLACE the control switch for SW-V-2A in the OPEN position Turns control switch for SW-V-2A clockwise to the OPEN position S / U

• CUE: When checked inform student that SW-V-2A indicates mid-position. To simulate timing sequence, wait a minute and then inform student that SW-V-2As green light has gone out. If asked, pump discharge pressure is slowly rising as SW-V-2A goes full open. End pressure will be 180 psig.

Step 7.13.4f ENSURE SW-V-2A FULLY OPENS (after timing sequence)

Ensures SW-V-2A green light goes out S / U Step 7.13.4g ENSURE adequate discharge pressure on SW-PI-32AR.

Observes discharge pressure on SW-PI-32AR indicates normal.

S / U CUE: When checked inform student that discharge pressure on SW-PI-32AR indicates 180 psig.

Termination Criteria: Student informs CRS that Attachment 7.13 is complete and SW-P-1A is running.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 4 of 5 LO001640 Rev.0 RESULTS OF JPM:

START SW-P-1A ON CONTROL ROOM EVACUATION Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: SW-P-1A is started per Attachment 7.13 of ABN-CR-EVAC.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 10 Minutes / NA COMMENTS:

Page 5 of 5 LO001640 Rev.0 Evaluator's Signature:

Date:

Page 6 of 5 LO001640 Rev.0 STUDENT JPM INFORMATION CARD Initial Conditions:

The Control Room has been evacuated.

Only the immediate actions of ABN-CR-EVAC were completed.

Cue:

You have been directed to start SW-P-1A per ABN-CR-EVAC attachment 7.13.

Inform the CRS when Attachment 7.13 is completed.

Control manipulations will NOT be performed.

All actions and steps will be simulated.

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE Start RRC-P-1B; Inadvertent RRC Flow Increase (Faulted) (Sim)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001642 Rev. No.

0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/02/08 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

Page 1 of 9 LO001642 Rev.0 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

An IC set where only the B RRC Pump is running and you are ready to start RRC-P-1B. Ensure RRC-P-1A flow is GT 20800 gpm.

Insert a fault on RRC-P-1B channel 1B1 and then delete the fault.

Turn OFF the lower pushbutton for individual Loop B controller Load the following into the IC set: IOR OVR-RFC030P (1) ON; TRGSET 1 X02I137T.GT.0 which depresses the RAISE P/B for RRC-P-1B when the START P/B is depressed to start channel 1B1.

Could also use TRGSET 1 X02O130R.GT.0 which is red light for ASD channel running.

Insert malfunction to have the ASD 15 second P/B Stuck overridden off - IMF MAL-RFC016E TRUE Special Setup Instructions:

Reset to an IC where power is about 50% and RRC pump speed is LT 35Hz.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-1162; RO-0083 Validation Time: 20 Minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

SOP-RRC-START Rev. 7; ABN-POWER Rev. 9 Location: Simulator NUREG 1123 Ref: 202001 A2.05 (3.8 / 4.0)

Performance Method: Perform

Page 2 of 9 LO001642 Rev.0 JPM CHECKLIST PROCEDURE VALIDATION Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

The plant was operating at 99% power when RRC-P-1B tripped. The cause has been corrected and RRC-P-1B is ready to be started. The SNE is in the control room and has evaluated Core conditions and RPV inlet temperature as satisfactory per PPM 9.3.12. A Reactivity Plan / Startup Plan is in place. The reactor is below the 70% rod line. RRC seal purge has been in service for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> per SOP-RRC-SEAL.

OSP-RRC-C103 has been completed for steps 5.1.15 and 5.1.16. No computer substitute value for Single Loop Operation has been entered. Both Channel Selector Switches are in the ON positions at panels: RRC-IMD-ASD1B/1 and RRC-IMD-ASD1B/2 (Local Control and Diagnostics Panels). OPS 4 is standing by in the ASD Building.

INITIATING CUE: The CRS has directed you to start RRC-P-1B per SOP-RRC-START section 5.2.

Notify the CRS when RRC-P-1B has been started and is operating at 15 Hz.

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and student actions Starts at step 5.2.1 Verify the SNE has evaluated the following parameters per PPM 9.3.12:

1. Core conditions are consistent with the requirements specified in-the Reactivity Control Plan

2. RPV Inlet temperature, as indicated on RFW-TI-5 (H13-P840) (or the average of computer points F018 and F019), is to the left of the curve on the Minimum Feedwater Temperature Verses Power Prior to Recirc Pump Start curve in Attachment 6.3 Refers to turnover information to verify SNE review of Core Conditions and RPV Inlet Temperature.

S / U

Page 3 of 9 LO001642 Rev.0

• Items are Critical Steps Comments Element Standard Sat/Unsat Lower and maintain the operating recirculation loop drive flow at 20,800 (This is for improved core stability)

Observes flow on P602 indicates 21,000 and depresses the lower P/B to reduce RRC-P-1B flow to approximately 20,800 S / U

• Verify the Reactor is below the 70% rod line Refers to turnover information (or computer screen) to verify rod line LT 70%

S / U Verify reactor water level is GT level 4 Observes RPV level indication and determines RPV/L is GT Level 4 S / U Verify recirculation pump seal purge injection has been in service for at least 30 minutes prior to starting an idle pump per SOP-RRC-SEAL Verifies RRC seal purge in service for GT 30 minutes per turnover sheet information S / U NOTE: Rod Line on Computer screen may not be below 70%. If simulator is checked refer student to initial conditions or cue that rod line is LT 70%.

Verify the following:

• RWCU-V-106 OPEN

• RRC-V-23B OPEN

• RRC-V-67B OPEN

• RCC-V-17B OPEN

• RRC-M/A-R676Bin MANUAL

• RRC-M/A-R676B is set at 15 Hz demand

• RRC-M/A-R676B status lights EXTINGUISHED:

• Feed Pump Trip

• dT Cavitation

• Reactor Low Level Note: It is acceptable for the thrust monitor to be in alarm when the RRC pump is shutdown Observes red light illuminated and green light extinguished for RWCU-V-106, RRC-V-23B, RRC-V-67B, and RCC-V-17B Observes manual light illuminated for RRC-M/A-R676B Observes RRC-M/A-R676B is set at 15 Hz demand Observes lights for Feed pump trip, Delta T Cavitation and Low RPV Level extinguished S / U

Page 4 of 9 LO001642 Rev.0

• Items are Critical Steps Comments Element Standard Sat/Unsat

• H13-P602.A6-2.8, RECIRC B SYSTEM VIB HIGH is clear

• H13-P602.A6.2-5, RECIRC A PUMP SEAL COOLING WATER FLOW LOW is clear

• H13-P602.A6.3-6, RECIRC A MOTOR WINDING COOLANT FLOW LOW is clear Observes annunciator extinguished for H13-P602. A6-2.4, RECIRC A SYSTEM VIB HIGH Observes annunciator extinguished for H13-P602. A6.2-5, RECIRC B PUMP SEAL COOLING WATER FLOW LOW Observes annunciator extinguished for H13-P602.A6.3-6, RECIRC B MOTOR WINDING COOLANT FLOW LOW S / U CLOSE CB-RRB (RRC-P-1B Bus Tie breaker) (H13-P602)

Places control switch for CB-RRB to the CLOSE position and observes the red light illuminated and the green light extinguished S / U

• CLOSE CB-RPT-4B (RRC-P-1B Motor Interlock Breaker)

(H13-P602)

Places control switch for CB-RPT4B to the CLOSE position and observes the red light illuminated and the green light extinguished S / U

• CLOSE CB-RPT-3B (RRC-P-1B Motor Interlock Breaker)

(H13-P602)

Places control switch for CB-RPT-3B to the CLOSE position and observes the red light illuminated and the green light extinguished S / U

• NOTE: White lights DS-6A and 6B may be pulsing at the rate of approximately once per second.

VERIFY following white lights DIMLY LIT (RPT trip system A):

• DS 6C (H13-P609)

• DS 6D (H13-P611)

Observes lights dimly illuminated for DS-6C on H13-P609 and DS-6D on H13-P611 S / U CUE: If comment is made about the lights on P609 and P611 appear more than DIMLY LIT - cue student that the lights ARE dimly lit (Simulator Vs. Plant difference)

Page 5 of 9 LO001642 Rev.0

• Items are Critical Steps Comments Element Standard Sat/Unsat DEPRESS the RESET pushbutton at the control and diagnostic panel for each drive Communicates with OPS4 and directs depressing the RESET pushbutton at the control and diagnostic panel for each drive S / U CUE: Reset pushbuttons have been depressed for each drive at the control and diagnostic panel IF starting an RRC pump on the master channel 1B1, then verify the following:

• Channel Selector Switch for Channel 1B1 is ON

• Channel Selector Switch for Channel 1B2 is OFF N/A N/A IF starting an RRC pump on the master channel 1B2, then verify the following:

• Channel Selector Switch for Channel 1B1 is OFF

• Channel Selector Switch for Channel 1B2 is ON N/A N/A IF starting an RRC pump on both drive channels, then verify both Channel Selector Switches for that drive are ON.

• RRC-IMD-ASD1B/1 (Local Control and Diagnostics Panel)

• RRC-IMD-ASD1B/2 (Local Control and Diagnostics Panel)

Communicates with OPS4 and directs verification that both Channel Selector Switches are in the ON positions at panels: RRC-IMD-ASD1B/1 (Local Control and Diagnostics Panel) and RRC-IMD-ASD1B/2 (Local Control and Diagnostics Panel).

S / U CUE: Report as OPS4 that both channel selector switches are in the ON position.

VERIFY temperature limitations within 15 minutes prior to starting an idle recirculation pump per OSP-RRC-C103 Verifies information in turnover (OSP-RRC-C103 has been completed for steps 5.1.15 and 5.1.16)

S / U

Page 6 of 9 LO001642 Rev.0

• Items are Critical Steps Comments Element Standard Sat/Unsat IF starting an idle pump with the other pump in operation, then verify the operating loop flow is LT 50% of rated loop flow (30 Hz) within 15 minutes prior to pump start per OSP-RRC-C103 Verifies information in turnover (OSP-RRC-C103 has been completed for steps 5.1.14 and 5.1.15.)

S / U IF applicable, then remove the B18 computer substitute value for Single Loop Operation Verifies information in turnover (No computer substitute value for Single Loop Operation has been entered)

S / U Verify the ASD "READY" light for the drive channels to be started are illuminated Observes ASD ready lights illuminated for each drive channel S / U Note: A momentary GTO Freeze alarm.

Note: Frequency indication may be momentarily Note: If the pump has been idle.

Start RRC-P-1B by momentarily depressing the ASD START pushbutton Momentarily depresses the ASD start Pushbutton for RRC-P-1B S / U

• VERIFY the RRC-P-1B starts and continues to operate at approximately 450 RPM (15 Hz)

Observes red lights illuminated and white lights extinguished for drives No.1 and No.2. Observes RPMs for RRC-P-1B rise to 450 rpm within 50 seconds S / U Fault occurs when channel Start button is depressed Recognizes that the speed for RRC-P-1B continues to go up past 15 Hz / 450 rpm without operator demand.

Informs CRS that RRC-P-1B speed is rising without demand S / U S / U CUE: If CRS is informed of the rise in RRC-P-1B speed, only repeat back the communication - do not give any direction.

Page 7 of 9 LO001642 Rev.0

• Items are Critical Steps Comments Element Standard Sat/Unsat ABN-POWER step 3.2.1 Per immediate actions of ABN-POWER, If RRC pump speed is rising for one pump and cannot be controlled, then stop the affected pump May attempt to stop the rising pump speed by depressing the lower button for RRC-P-1B but notes that this does not stop pump speed increase Depresses the STOP pushbutton for RRC-P-1B and verifies it stops S / U S / U

• Termination Criteria: When the student informs the CRS that RRC-P-1B was stopped due to speed rising without operator action inform the student that the termination point of the JPM has been reached.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 8 of 9 LO001642 Rev.0 RESULTS OF JPM:

START RRC-P-1B; INADVERTENT RRC FLOW INCREASE Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: RRC-P-1B was started per SOP-RRC-START and was stopped per the immediate actions of ABN-POWER.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 20 Minutes / NA COMMENTS:

Page 9 of 9 LO001642 Rev.0 Evaluator's Signature:

Date:

Page 10 of 9 LO001642 Rev.0 STUDENT JPM INFORMATION CARD Initial Conditions:

The plant was operating at 99% power when RRC-P-1B tripped.

The cause has been corrected and RRC-P-1B is ready to be started.

The SNE is in the control room and has evaluated Core conditions and RPV inlet temperature as satisfactory per PPM 9.3.12.

A Reactivity Plan / Startup Plan is in place.

The reactor is below the 70% rod line.

RRC seal purge has been in service for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> per SOP-RRC-SEAL. OSP-RRC-C103 has been completed for steps 5.1.15 and 5.1.16.

No computer substitute value for Single Loop Operation has been entered.

Both Channel Selector Switches are in the ON positions at panels: RRC-IMD-ASD1B/1 and RRC-IMD-ASD1B/2 (Local Control and Diagnostics Panels).

OPS 4 is standing by in the ASD Building.

Cue:

The CRS has directed you to start RRC-P-1B per SOP-RRC-START section 5.2.

Notify the CRS when RRC-P-1B has been started and is operating at 15 Hz.

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE BYPASS CONTROL RODS IN RSCS (SIM)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001639 Rev. No. 0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 06/09/08 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

Page 1 of 7 LO001639 Rev. 0 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Setup the simulator to have RSCS card bypass light illuminate when the switch is taken to bypass position.

Special Setup Instructions:

Ensure Sequence B and Rods Full In are selected on Rod Sequence Controller on P603.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0134 Validation Time: 10 Minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

SOP-RSCS-OPS Rev. 1 Location: Simulator NUREG 1123 Ref: 201004 A4.01 (3.4/3.5)

Performance Method: PERFORM

Page 2 of 7 LO001639 Rev. 0 JPM CHECKLIST PROCEDURE VALIDATION Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

Due to two failed reed switches on control rod 42-15 it has been determined that bypassing the control rod in RSCS is required. The CRS has verified bypassing control rod 42-15 is in compliance with Technical Specifications. The Control Room Supervisor has given permission to bypass this control rod.

INITIATING CUE: The CRS has directed you to bypass control rod 42-15 in the RSCS cabinet per SOP-RSCS-OPS. Inform the CRS when you have bypassed control rod 42-15 and the bypassed rod identifier cabinet has been locked back up.

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and student actions Step 5.1.1 OBTAIN the Control Room Supervisors permission to bypass a control rod Permission given in initiating cue N / A Step 5.1.2 IDENTIFY the binary equivalent locations from.1 Identifies binary equivalent locations from Attachment 6.1 42 = 00110 (X0 - X4) 15 = 10100 (X0 - X4)

S / U Step 5.1.3 DEPRESS the Rod Display Control Pushbutton on the RSCS display to illuminate the Bypass light (H13-P603)

Depresses the Rod Display Control Pushbutton on the RSCS display to illuminate the Bypass light S / U Step 5.1.4 IDENTIFY the current sequence illuminated on the Seq A/Seq B Pushbutton (H13-P603)

Identifies the current sequence as being Sequence B S / U Step 5.1.5 IDENTIFY the control rods presently bypassed (RSCS Display)

Notes that there are no other control rods bypassed.

S / U

Page 3 of 7 LO001639 Rev. 0

• Items are Critical Steps Comments Element Standard Sat/Unsat Step 5.1.6 CIRCLE the control cell for each bypassed rod on a copy of Attachment 6.2 (SEQUENCE A) or.3 (SEQUENCE B)

No control rods are bypassed

- Does NOT circle any control cells on Attachment 6.3 S / U Step 5.1.7 UNLOCK the bypassed rod identifier cabinet (Key 81 or

82) (H13-P659)

Gets keys 81 and/or 82 from lockbox and at H13-P659, unlocks the bypassed rod identifier cabinet S / U

• Step 5.1.8 VERIFY that the control rods presently bypassed are the same rods recorded above on.2 or Attachment 6.3 No rods are bypassed S / U Step 5.1.9 CIRCLE the control rod to be bypassed on the same copy of.2 or.3 Circles control rod 42-15 on.3 S / U Step 5.1.10 IDENTIFY the RSCS binary equivalent X and Y coordinates from.1, Control Rod Location Equivalents.

• X4 Y4

• X3 Y3

• X2 Y2

• X1 Y1

• X0 Y0 Identifies binary equivalent X and Y coordinates and records them on procedure 42 = 00110 (X0 - X4) 15 = 10100 (X0 - X4)

S / U Step 5.1.11 SELECT a card currently not in use to bypass a control rod (H13-659)

Selects a card not currently in use S / U

• CUE: Inform the student to use the second card in from the left which is CARD 7.

Page 4 of 7 LO001639 Rev. 0

• Items are Critical Steps Comments Element Standard Sat/Unsat Step 5.1.12 PERFORM the following for the card selected to bypass the control rod:

• Verify the BYPASSED/NOT BYPASSED Toggle Switch at the top of the card is in the NOT BYPASSED position

• Verify the red light just below the Toggle Switch is OFF Observes the BYPASSED/NOT BYPASSED Toggle Switch at the top of the card is in the NOT BYPASSED position Observes the red light just below the Toggle Switch is OFF S / U S / U Step 5.1.13 Place the X4 through Xo, and Y4 through Yo Switches in the 0 or 1 position consistent with the desired rod's binary equivalent as identified in step 5.1.10 Places toggle switches as follows:

• X4 0 Y4 0

• X3 1 Y3 0

• X2 1 Y2 1

• X1 0 Y1 0

• X0 0 Y0 1 S / U

• Step 5.1.14 Obtain an independent verification of the Rod Toggle Switch positions from a second licensed operator or technically qualified individual Student may verbalize intent of obtaining an independent verification S / U CUE: If required, inform student that independent verification is complete Step 5.1.15 Place the BYPASSED/NOT BYPASSED Toggle Switch at the top of the card in the BYPASSED position Places the bypassed/not bypassed Toggle Switch at the top of the card in the bypassed position S / U

• Step 5.1.16 Verify the red light just under the switch is illuminated Verifies the red light just under the switch is illuminated S / U Step 5.1.17 Lock the bypassed rod identifier cabinet (H13-P659)

Locks the bypassed rod identifier cabinet S / U Termination Criteria: Student informs CRS that control rod 42-15 is bypassed.

Page 5 of 7 LO001639 Rev. 0

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 6 of 7 LO001639 Rev. 0 RESULTS OF JPM:

BYPASS A CONTROL RODS IN RSCS Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Control Rod 42-15 is bypassed per SOP-RSCS-OPS.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 10 Minutes / NA COMMENTS:

Evaluator's Signature:

Date:

Page 7 of 7 STUDENT JPM INFORMATION CARD Initial Conditions:

Due to two failed reed switches on control rod 42-15, it has been determined that bypassing the control rod in RSCS is required.

The CRS has verified bypassing control rod 42-15 is in compliance with Technical Specifications.

The Control Room Supervisor has given permission to bypass this control rod.

Cue:

The CRS has directed you to bypass control rod 42-15 in the RSCS cabinet per SOP-RSCS-OPS.

Inform the CRS when you have bypassed control rod 42-15 and the bypassed rod identifier cabinet has been locked back up.

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE RE-ESTABLISH SECONDARY CONTAINMENT/START RB HVAC (Sim)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LR001637 Rev. No.

0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 06/03/08 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

Page 1 of 5 LO001637 Rev.0 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

None Special Setup Instructions:

Reset to any IC. Turn off both ROA and REA fans. Acknowledge the annunciator for high RB dP.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0497 Validation Time: 8 Minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

SOP-RB HVAC-RESTART-QC Rev. 0 Location: Simulator NUREG 1123 Ref: 290001 A4.01 (3.3 / 3.4)

Performance Method: Perform

Page 2 of 5 LO001637 Rev.0 JPM CHECKLIST PROCEDURE VALIDATION Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

A series of events occurred that resulted in no running Reactor Building Supply or Exhaust fan. EOP PPM 5.2.1 was entered due to Reactor Building dP high. Prior to starting Standby Gas Treatment, the Control Room received information that Reactor Building HVAC could be restarted.

INITIATING CUE: The Control Room Supervisor has directed you to restart RB HVAC by starting ROA-FN-1A and REA-FN-1A per SOP-RBHVAC-QC. Inform the CRS when Secondary Containment may be declared operable.

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Step 2.1 PLACE REA-DPIC-1A(1B) (P Control RX Bldg/Outside) in MANUAL Places toggle for REA-DPIC-1A to Manual position S / U

• Step 2.2 SET REA-DPIC-1A(1B) output signal at approximately 60% of scale Depresses closed pushbutton to have red indicator at approximately 60% of scale S / U

• Step 2.3 PLACE the control switch for the following fans in PULL-TO-LOCK:

• ROA-FN-1A (Reactor Bldg Supply Fan)

• ROA-FN-1B (Reactor Bldg Supply Fan)

• REA-FN-1A (Reactor Building Exhaust Fan)

• REA-FN-1B (Reactor Building Exhaust Fan)

Turns the black handles counter-clockwise and pulls out to engage the Pull-To-Lock position for:

ROA-FN-1A ROA-FN-1B REA-FN-1A REA-FN-1B S / U

• S / U

• S / U

• S / U

• Page 3 of 5 LO001637 Rev.0

• Items are Critical Steps Comments Element Standard Sat/Unsat Step 2.4 VERIFY the following valves are OPEN:

• ROA-V-1 (RB Supply Outboard Isolation)

• ROA-V-2 (RB Supply Inboard Iso)

• REA-V-1 (RB Exhaust Inboard Iso)

• REA-V-2 (RB Exhaust Outboard Isol)

Observes the red light illuminated and green light out for:

ROA-V-1 ROA-V-2 REA-V-1 REA-V-2 S / U S / U S / U S / U Step 2.5 - 2 handed operation is authorized/expected SIMULTANEOUSLY START REA-FN-1A(1B) and ROA-FN-1A(1B)

Depresses black handles and allows switches to go to neutral position.

Simultaneously turns the black handled control switches for ROA-FN-1A and REA-FN-1A clockwise to the START position and then releases them S / U

• Step 2.6 MANUALLY ADJUST REA-DPIC-1A(1B) controller output until Reactor Building pressure on REA-DPR-1A(1B) is approximately -0.6O W.G.

Adjusts REA-DPIC-1A to achieve approximately -0.6W.G.. on REA-DPR-1A S / U

• Step 2.7 NULL REA-DPIC-1A (1B), AND PLACE it in AUTO Turns thumbwheel until REA-DPIC-1A is nulled or waits until red arrow lines up with green band and then moves lever to AUTO position S / U

• Step 2.8 PLACE the control switch for the following non-running fans in the NORMAL-after-STOP position.

• ROA-FN-1B(1A)

• REA-FN-1B(1A)

Turns the black handled switches for:

ROA-FN-1B REA-FN-1B

.from PTL to the neutral position and observes the green flag visible S / U S / U Termination Criteria: Student informs CRS that Secondary Containment may be declared operable.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 4 of 5 LO001637 Rev.0 RESULTS OF JPM:

RESTART RB HVAC TO ESTABLISH SECONDARY CONTAINMENT Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: RB HVAC has been restarted per SOP-RBHVAC-RESTART-QC.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 8 Minutes / NA COMMENTS:

Page 5 of 5 LO001637 Rev.0 Evaluator's Signature:

Date:

Page 6 of 5 LO001637 Rev.0 STUDENT JPM INFORMATION CARD Initial Conditions:

A series of events occurred that resulted in no running Reactor Building Supply or Exhaust fan.

EOP PPM 5.2.1 was entered due to Reactor Building dP high.

Prior to starting Standby Gas Treatment, the Control Room received information that Reactor Building HVAC could be restarted.

Cue:

The Control Room Supervisor has directed you to restart RB HVAC by starting ROA-FN-1A and REA-FN-1A per SOP-RBHVAC-QC.

Inform the CRS when Secondary Containment may be declared operable.

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE LOWER RPV PRESSURE USING DEH (Simulator)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LR001827 Rev. No.

0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 9/05/07 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

LR001827 Rev.0 Page 1 of 5 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Reset to IC with Reactor scrammed and level is stable on the Startup Flow Control Valves.

Special Setup Instructions:

N/A JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0348 Validation Time: 10 minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

SOP-DEH-OPS Section 5.4 Rev. 5 Location: Simulator NUREG 1123 Ref: 241000A4.02 4.1/4.1 Performance Method: Perform

LR001827 Rev.0 Page 2 of 5 JPM CHECKLIST PROCEDURE VALIDATION Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

Columbia has just experienced a reactor scram due to a control rod drifting out of the core. Efforts are underway to secure the Reactor Feed Pumps.

INITIATING CUE: The Control Room Supervisor has directed you to lower RPV pressure to 800 psig at 50 psig per minute with bypass valves. Inform the CRS when RPV pressure is 800 psig.

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Step 5.4.1 Initiate Pressure setpoint change as follows (Menu Turbine Start Up):

a. Verify AUTO mode is illuminated in Throttle Pressure section On Turbine Start Up screen, verifies that AUTO mode is illuminated in the Throttle Pressure selection S / U

b. Select Pressure Target Selects Pressure Target S / U *

c. Enter desired pressure Enters 8, 0, 0 psig S / U *

d. Select OK Selects OK S / U *

e. Verify entered target pressure in Press Target window Verifies 800 is displayed in the Press Target window S / U

f. Select Pressure Rate Selects Pressure Rate S / U *

g. Enter desired Pressure rate Enters 5, 0 psig S / U *

h. Select OK Selects OK S / U *

i. Verify entered pressure rate appears in Press Rate window Verifies 50 psig is displayed in the Pressure Rate window S / U

j. Select GO Selects GO S / U

• LR001827 Rev.0 Page 3 of 5

• Items are Critical Steps Comments Element Standard Sat/Unsat

k. Select YES Selects YES S / U *

l. Verify GO illuminated Verifies the green GO is illuminated S / U

m. Verify Press Demand and Throttle Press change at the entered rate.

Verifies Press Demand and Throttle Press change at 100 psig per minute S / U

n. When the Pressure Target is reached, then verify GO extinguishes When RPV pressure is 800 psig, verifies the green GO extinguishes S / U

o. When the Pressure and Pressure Demand are approximately equal Verifies Throttle Pressure and Pressure Demand are approximately equal S / U These last two steps should not be performed

p. If a hold is desired, then perform the following:

1) Select hold

2) Verify hold illuminates

3) Verify throttle pressure stabilizes Step should not be performed N / A

q. When hold is no longer desired, then perform the following:

1) Select go

2) 2) Select yes

3) 3) Verify go illuminated

4) Verify press demand and throttle pressure change at the entered rate Step should not be performed N / A Termination Criteria: Student informs CRS that RPV pressure has been lowered to 800 psig.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

LR001827 Rev.0 Page 4 of 5 RESULTS OF JPM:

LOWER RPV PRESSURE USING DEH Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: RPV pressure has been lowered to 800 psig at 50 psig per minute.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 12 Minutes / NA COMMENTS:

Evaluator's Signature:

Date:

LR001827 Rev.0 Page 5 of 5 STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia has just experienced a reactor scram due to a control rod drifting out of the core.

Efforts are underway to secure the Reactor Feed Pumps.

Cue:

The Control Room Supervisor has directed you to lower RPV pressure to 800 psig at 50 psig per minute with bypass valves.

Inform the CRS when RPV pressure is 800 psig.

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE INITIATE RCIC FOR RPV INJECTION - ARM AND DEPRESS (FAULTED)(SIM)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LR000302 Rev. No. 9 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Staff DATE 1997 REVISED BY Ron Hayden DATE 06/05/08 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager

Page 1 of 5 LR000302 Rev. 9 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Any low power IC in which RCIC will NOT cause a reactor scram from a turbine trip Special Setup Instructions:

Insert the following malfunction prior to starting the JPM:

RCIC CONTROLLER AUTO OUTPUT FAILURE IMF CNH-RCI002E 50 JPM Instructions:

Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.

The evaluator and student shall use the current procedure. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0268; RO-0656 Validation Time: 6 min.

Prerequisite Training: N/A Time Critical: No PPM

Reference:

SOP-RCIC-INJECTION-QC Rev. 4 Location: SIMULATOR NUREG 1123 Ref: 217000A2.10(3.1/3.1) 217000A2.11(3.1/3.2)

Performance Method: PERFORM

Page 2 of 5 LR000302 Rev. 9 JPM CHECKLIST PROCEDURE VALIDATION Regarding procedure copies for evaluator and student, if the procedure revision is different from that listed on the JPM, verify that the critical task steps are the same.

Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

Columbia was scrammed due to an electrical problem associated with the Main Generator. PPM 5.1.1, RPV Level Control has been entered due to low RPV Level. As RPV level started to recover, both Reactor Feed Pumps tripped.

INITIATING CUE:

The CRS has directed you to initiate the RCIC system for RPV injection. Return RPV level to a +13 inch to +54 level band. Inform the CRS when you have established injection flow of 600 gpm.

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Page 3 of 5 LR000302 Rev. 9 Step 2.1.1 IF not already operating, THEN ARM and DEPRESS the RCIC MANUAL INITIATION pushbutton.

Note: When RCIC initiates the following occurs:

RCIC-V-45 (Steam to Turbine) opens RCIC-V-46 (Lube Oil Cooler Water Supply) opens RCIC-P-2 (Barometric Condsr Vacuum Pump) starts RCIC-V-13 (RPV Injection) opens RCIC-V-25 and RCIC-V-26 (Steam Line Warmup Drains to Mai n Condenser) close RCIC-V-4 and RCIC-V-5 (Cond Pump Discharge to EDR) close SW-P-1B starts (20 second time delay)

RCIC-RMS-S36 to ARM and then depresses the initiation pushbutton Verifies:

RCIC-V-45 opens (red light on, green light out)

RCIC-V-46 opens (red light on, green light out)

RCIC-P-2 starts (red light on, green light out)

RCIC-V-13 opens (red light on, green light out)

RCIC-V-25 and RCIC-V-26 close (green light on, red light out)

RCIC-V-4 and RCIC-V-5 close (red light on, green light out)

SW-P-1B starts (red light on, green light out)

S / U

• S / U S / U S / U S / U S / U S / U S / U

• Items are Critical Steps Comments Element Standard Sat/Unsat Recognizes failure of RCIC to deliver water to the RPV Notes no flow has started to RPV. Diagnoses problem is associated with the flow controller that will not rise above 50%

scale in AUTO S / U

• Cue: If operator informs CRS of controller failure, cue as CRS: Understand you have a controller problem. Take actions as necessary to deliver 600 gpm to the RPV.

Manually adjusts RCIC system flow.

Places RCIC-FIC-600 in MANUAL and increases system flow to 600 gpm using controllers open pushbutton S / U

• Page 4 of 5 LR000302 Rev. 9 Termination Criteria: Operator informs the CRS when RCIC injection flow is established at 600 gpm.

RECORD TERMINATION TIME: _________

Transfer the following information to the Results of JPM page: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.

Page 5 of 5 LR000302 Rev. 9 RESULTS OF JPM:

INITIATE RCIC FOR RPV INJECTION - ARM AND DEPRESS Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: RCIC is initiated and is injecting at 600 gpm per SOP-RCIC-INJECTION-QC.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM Validation/Critical Time JPM Completion Time 6 Minutes / NA COMMENTS:

Page 6 of 5 LR000302 Rev. 9 Evaluator's Signature:

Date:

Page 7 of 5 LR000302 Rev. 9 STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia was scrammed due to an electrical problem associated with the Main Generator.

PPM 5.1.1, RPV Level Control has been entered due to low RPV Level.

As RPV level started to recover, both Reactor Feed Pumps tripped.

Cue:

The CRS has directed you to initiate the RCIC system for RPV injection.

Return RPV level to a +13 inch to +54 level band.

Inform the CRS when you have established injection flow of 600 gpm.

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE START B SGT FOR CONTAINMENT VENTING (FAULTED) (SIM)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001636 Rev. No. 0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 06/05/08 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

Page 1 of 6 LO001636 Rev. 0 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Any IC Special Setup Instructions:

Shutdown RB HVAC Close SGT-V-2B Silence annunciators on panels not used.

JPM Instructions:

Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: R0-0287 Validation Time: 8 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

SOP-CN-CONT-VENT, Rev. 14; SOP-SGT-START Rev. 3 Location: SIMULATOR NUREG 1123 Ref: 261000 A4.07 (3.1, 3.2)

Performance Method: PERFORM

Page 2 of 6 LO001636 Rev. 0 JPM CHECKLIST PROCEDURE VALIDATION Regarding procedure copies for evaluator and student, if the procedure revision is different from that listed on the JPM, verify that the critical task steps are the same.

Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

Columbia is entering a refueling outage and is in Mode 4. Purging per SOP-CN-CONT-VENT Section 5.3 has been completed (Section 5.3 has been completed).

Reactor Building HVAC is shutdown.

INITIATING CUE:

You have been directed by the CRS to ventilate containment with SGT per SOP-CN-CONT-VENT section 5.7. You are directed to start SGT "B" Lead Fan (at the subsystem level). Inform the CRS when you are ready to close SGT-V-2B.

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: If, prior to starting the JPM, the student identifies SGT-V-2B is closed and should be open allow him to open the valve and then inform him that the CRS has been informed and SGT has been verified to be in a standby lineup and to continue with the task assigned.

SOP-CN-CONT-VENT Step 5.7.1 Verify the following:

• Drywell has been purged through SGT for GT 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

• Wetwell has been purged through SGT for GT 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

• Reactor is in Modes 4 or 5 Given in Initial Conditions N / A Step 5.7.2 Verify purge shutdown, per Section 5.3 Given in Initial Conditions N / A Step 5.7.3 Start one train of SGT per SOP-SGT-START Refers to SOP-SGT-START section 5.2.1 then section 5.2.5 S / U

• SOP-SGT-START Step 5.2.1 (FAULTED)

Verify there are no paint fumes, chemical fumes or combustion products (welding, cutting, fire, etc.) in the areas that communicate with SGT Verbalizes that this step needs to be performed.

S / U

• Page 3 of 6 LO001636 Rev. 0

• Items are Critical Steps Comments Element Standard Sat/Unsat CUE: When student verbalizes that this step needs to be performed, inform him that there is welding ongoing in the Reactor Building 572 on the North East wall on a fire-protection line.

Student should inform the CRS of the ongoing welding activities and NOT continue with the procedure.

CUE: When student informs the CRS of condition, inform him that time compression has occurred and the welding activities have been secured. Permission is given to continue with SOP-CN-CONT-VENT procedure.

Step 5.2.5a (FAULTED)

Verify SGT-V-2B is OPEN (Inlet from Reactor Building)

Notes green light illuminated as valve is closed. Turns black handle switch in the clockwise direction to OPEN. Verifies red light illuminates and green light extinguishes S / U

• Step 5.2.5b Momentarily turn SGT-FN-1B2 fan control switch from AUTO to PTL SYS. START Turns black handle for SGT-FN-1B2 clockwise from AUTO, past START, to the PTL SYS START position S / U

• EVALUATOR: During performance of the following step, SGT-V-5B2 has sometimes not opened automatically. If SGT-V-5B2 does not open automatically the student should take actions to manually open which would be a critical step.

Step 5.2.5c Verify the following:

• Main Heaters ENERGIZE as indicated by Main Heater ON light and B2 amp meters

• SGT-V-5B2 OPENS (Exhaust to Stack).

• SGT-FN-1B2 STARTS (within 10 seconds)

Observes blue heater ON lights illuminate for SGT-EHC-1B-2 and amps indicated on the three amp meters (bottom left)

Observes red light illuminates and green light out for SGT-V-5B2 Observes red light illuminates and green light out for SGT-FN-1B2 starts within 10 seconds S / U S / U (*)

S / U Step 5.2.5d IF required to operate in manual flow control, then perform the following.

Otherwise, N/A Determines that Manual flow control not required as Auto flow control works N / A

Page 4 of 6 LO001636 Rev. 0

• Items are Critical Steps Comments Element Standard Sat/Unsat SOP-CN-CONT-VENT Step 5.7.4 Open CEP-V-1A (Upper DW Exhaust Valve) (H13-P813)

On H13-P813, turns control switch for CEP-V-1A clockwise to the OPEN position. Verifies red light illuminates and green light extinguishes S / U

• Step 5.7.5 Open CEP-V-2A (Upper DW Exhaust Valve) (H13-P813)

On H13-P813, turns control switch for CEP-V-2A clockwise to the OPEN position. Verifies red light illuminates and green light extinguishes S / U

• Step 5.7.6 IF SGT-SYS-A is running, THEN PERFORM the following..

SGT-B is running - step is N / A N / A Step 5.7.7 IF SGT-SYS-B is running, then perform the following:

a. Open SGT-V-1B (Inlet from Containment Building) (H13-P811).

b. Close SGT-V-2B (Inlet from Reactor Building) (H13-P811)

Turns black handle switch for SGT-V-1B clockwise to the OPEN position. Verifies red light illuminates and green light extinguishes S / U

• Termination Criteria: Student informs CRS that he is ready to close SGT-V-2B. Inform the student that the termination point of the JPM has been reached.

RECORD TERMINATION TIME: _________

Transfer the following information to the Results of JPM page: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.

Page 5 of 6 LO001636 Rev. 0 RESULTS OF JPM:

START B SGT FOR CONTAINMENT VENTING Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: SGT train B is running and lined up for venting the Containment per SOP-CN-CONT-VENT up to closing SGT-V-2B.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 8 Minutes / NA COMMENTS:

Page 6 of 6 LO001636 Rev. 0 Evaluator's Signature:

Date:

Page 7 of 6 LO001636 Rev. 0 STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is entering a refueling outage and is in Mode 4.

Purging per SOP-CN-CONT-VENT Section 5.3 has been completed (Section 5.3 has been completed).

Reactor Building HVAC is shutdown.

Cue:

You have been directed by the CRS to ventilate containment with SGT per SOP-CN-CONT-VENT section 5.7.

You are directed to start SGT "B" Lead Fan (at the subsystem level).

Inform the CRS when you are ready to close SGT-V-2B.

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE OPEN INBOARD MSIVs TO RE-ESTABLISH THE MAIN CONDENSER AS A HEAT SINK (SIM)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001638 Rev. No. 0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 06/05/08 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager

Page 1 of 6 LO001638 Rev. 0 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Any IC with the reactor at rated pressure Ensure Stopwatch is available if timing is desired Special Setup Instructions:

Post scram. Close the Inboard MSIVs (MS-V-22A -D). MS-V-146 may have to be closed to get dP within 50 psig.

JPM Instructions:

Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: Stopwatch Safety Items: None Task Number: RO-0311 Validation Time: 7 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

SOP-MSIV-OPS Section 5.2 Rev. 9 Location: SIMULATOR NUREG 1123 Ref: 239001A4.01 (4.2/4.0)

Performance Method: PERFORM

Page 2 of 6 LO001638 Rev. 0 JPM CHECKLIST PROCEDURE VALIDATION Regarding procedure copies for evaluator and student, if the procedure revision is different from that listed on the JPM, verify that the critical task steps are the same.

Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

A loss of CIA pressure caused the CRS to direct a manual scram. The inboard MSIVs went closed due to low CIA pressure. CIA pressure has been restored.

TDAS not available. Health Physics has been notified of this evolution.

INITIATING CUE: The CRS has directed you to equalize around and open the Inboard MSIVs per SOP-MSIV-OPS Section 5.2. Do NOT record the stroke time using Attachment 6.1. You have permission to N/A those steps. Notify the CRS when all of the MSIVs are open.

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Step 5.2.1 IF not in Modes 1 or 2, THEN VERIFY DEH pressure setpoint is GT RPV pressure prior to opening MSIVs Observes RPV pressure on MS-PR-1C (or other recorder)

Observes DEH touch screen and notes DEH pressure setpoint Verifies DEH setpoint is GT RPV Pressure S / U Step 5.2.2 NOTIFY Health Physics the equalizing/opening of the MSIVs has the potential of changing radiological conditions Given in Initial Conditions as being completed N / A Step 5.2.3 VERIFY the applicable MSIV control switch is CLOSED Observes all switches for the Inboard MSIVs are in the closed position S / U Step 5.2.4 IF TDAS is available TDAS not available, given in initial conditions N / A

Page 3 of 6 LO001638 Rev. 0

• Items are Critical Steps Comments Element Standard Sat/Unsat Step 5.2.5 VERIFY the differential pressure across the MSIV is LT 50 psid.

Observes pressure on MS-LR/PR-623A/B on P601 and MS-PR-1C on P820 and verifies LT 50 psid S / U

• Step 5.2.6 IF the reactor is in Mode 1 or 2, Not in MODE 1 or 2 N / A Step 5.2.7 RESET the isolation logic as follows:

DEPRESS MS-RMS-S33 (Channel A and B Isolation Reset Pushbutton)

(H13-P601).

DEPRESS MS-RMS-S32 (Channel C and D Isolation Reset Pushbutton)

(H13-P601)

Depresses both Channel A and B, and Channel C and D Isolation Reset Pushbuttons S / U*

Step 5.2.8 PERFORM the following to OPEN the OUTBOARD MSIV: N/A those not opened.

All Outboard MSIVs are opened N / A

Page 4 of 6 LO001638 Rev. 0

• Items are Critical Steps Comments Element Standard Sat/Unsat Step 5.2.9 PERFORM the following to OPEN the INBOARD MSIV: N/A those not opened.

a. PLACE MS-V-22A control switch in AUTO

1) VERIFY MS-V-22A OPENS

2) RECORD open time on.1

b. PLACE MS-V-22B control switch in AUTO

1) VERIFY MS-V-22B OPENS

2) RECORD open time on.1 Turns the control switches for each Inboard MSIV to the AUTO position:

MS-V-22A MS-V-22B MS-V-22C MS-V-22D S / U

• S / U

• S / U

• S / U

• Step 5.2.9 Continued

c. PLACE MS-V-22C control switch in AUTO

1) VERIFY MS-V-22C OPENS

2) RECORD open time on.1.

d. PLACE MS-V-22D control switch in AUTO

1) VERIFY MS-V-22D OPENS

2) RECORD open time on.1 Verifies each valve opens by observing the red light illuminates and the green light extinguishes:

MS-V-22A MS-V-22B MS-V-22C MS-V-22D S / U S / U S / U S / U Termination Criteria: Student informs CRS that all MSIVs are open.

Page 5 of 6 LO001638 Rev. 0

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD TERMINATION TIME: _________

Transfer the following information to the Results of JPM page: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.

Page 6 of 6 LO001638 Rev. 0 RESULTS OF JPM:

OPEN INBOARD MSIVs TO RE-ESTABLISH MAIN CONDENSER AS A HEAT SINK Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Open the Inboard MSIVs in accordance with SOP-MSIV-OPS.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 7 Minutes / NA COMMENTS:

Page 7 of 6 LO001638 Rev. 0 Evaluator's Signature:

Date:

Page 8 of 6 LO001638 Rev. 0 STUDENT JPM INFORMATION CARD Initial Conditions:

A loss of CIA pressure caused the CRS to direct a manual scram.

The inboard MSIVs went closed due to low CIA pressure.

CIA pressure has been restored.

TDAS not available.

Health Physics has been notified of this evolution.

Cue:

The CRS has directed you to equalize around and open the Inboard MSIVs per SOP-MSIV-OPS Section 5.2.

Do NOT take and record the stroke times. You have permission to N/A those steps.

Notify the CRS when all of the MSIVs are open.

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE TRANSFER SM-8 FROM SM-3 TO TR-B (Sim)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001635 Rev. No.

0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 06/03/08 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

Page 1 of 5 LO001635 Rev.0 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

Reset to any IC where SM-8 is powered from SM-3 and TR-B is available.

Ensure Syn Selector switch is in the DG2 slot.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-1244 Validation Time: 7 Minutes Prerequisite Training: N / A Time Critical: No PPM

Reference:

SOP-ELEC-4160V-OPS Section 5.8 Rev. 1 Location: Simulator NUREG 1123 Ref: 262001 A4.01 (3.4/ 3.7)

Performance Method: Perform

Page 2 of 5 LO001635 Rev.0 JPM CHECKLIST PROCEDURE VALIDATION Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

To facilitate maintenance on Bus 3 and 8 tie breaker, CB-3/8, SM-8 needs to be transferred to Backup Transformer.

INITIATING CUE: The Control Room Supervisor has directed you to transfer SM-8 from SM-3 to TR-B. Inform the CRS when SM-8 is being powered from TR-B.

• Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Step 5.8.1 VERIFY CB-TRB CLOSED Observes red light illuminated and red flag visible for CB-TRB S / U Step 5.8.2 VERIFY the following:

• TR-B voltage GE 115 KV

• SM-7 is not being supplied from TR-B Observes TR-B voltage on meter to be GT 115 KV Observes the B-7 breaker open S / U S / U Step 5.8.3 VERIFY CB-B8 white LOCKOUT CIRCUIT AVAIL light illuminated Observes white lockout circuit available light illuminated above CB-B8 control switch S / U Step 5.8.4 VERIFY CB-B8 READY TO XFR light illuminated Observes Ready to transfer light above Lockout Circuit available light is illuminated S / U Step 5.8.5 VERIFY CB-B8 green light illuminated and green flag displayed Observes green light illuminated and green flag displayed for CB-B8 S / U Step 5.8.6 VERIFY CB-8/3 white LOCKOUT CIRCUIT AVAIL light illuminated Observes white Lockout Circuit Avail light illuminated for CB-8/3 S / U Step 5.8.7 VERIFY CB-8/3 red light illuminated Observes red light illuminated for CB-8/3 S / U

Page 3 of 5 LO001635 Rev.0

• Items are Critical Steps Comments Element Standard Sat/Unsat Step 5.8.8 PLACE CB-B8 Sync Selector switch in MANUAL Turns black handled CB-B8 SYNC Selector switch to the MAN position by turning it counter-clockwise S / U

• Step 5.8.9 VERIFY voltage present on both incoming and running buses Observes voltage reading on both incoming and running bus meters located above the Diesel Generator 2 plackard S / U Step 5.8.10 CLOSE CB-B8 Turns black handled control switch for CB-B8 clockwise to the CLOSE position S / U

• Step 5.8.11 VERIFY CB-8/3 auto trips Observes CB-8/3 breakers green light illuminates and red light goes out S / U Step 5.8.12 PLACE CB-8/3 control switch in TRIP Turns the black handled control switch for CB-8/3 counter-clockwise to the Trip position and releases the switch S / U Step 5.8.13 VERIFY CB-8/3 green light illuminated and green flag displayed Observes the green light illuminated and green flag displayed for CB-8/3 S / U Step 5.8.14 PLACE CB-B8 Sync Selector switch in OFF Turns black handled CB-B8 SYNC Selector switch to the OFF position by turning it clockwise S / U Termination Criteria: Student informs CRS that SM-8 has been transfer and is now being powered from the backup transformer.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 4 of 5 LO001635 Rev.0 RESULTS OF JPM:

TRANSFER SM-8 FROM SM-3 TO TR-B Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: SM-8 has been transferred from SM-3 to the Backup Transformer per SOP-ELEC-4160V-OPS.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 8 Minutes / NA COMMENTS:

Page 5 of 5 LO001635 Rev.0 Evaluator's Signature:

Date:

Page 6 of 5 LO001635 Rev.0 STUDENT JPM INFORMATION CARD Initial Conditions:

To facilitate maintenance on Bus 3 and 8 tie breaker, CB-3/8, SM-8 needs to be transferred to Backup Transformer.

Cue:

The Control Room Supervisor has directed you to transfer SM-8 from SM-3 to TR-B.

Inform the CRS when SM-8 is being powered from TR-B.

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE COLUMBIA GENERATING STATION SIMULATOR EXAMINATION LESSON TITLE Raise Power with Flow; Place MT into Gov. Valve Optimization; SRV Fails Open; HPCS-P-3 Fails; ASD Channel Fails; ASD Loss - Manual Scram; RFW & RCIC Loss; Lower Pressure For CBP Injection; EQ; SP Rupture: ED on Low SP/L LENGTH OF LESSON 1.5 Hours INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code LO001625 Rev. No. 0 JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 6/12/08 REVISED BY DATE VALIDATED BY DATE TECHNICAL REVIEW DATE INSTRUCTIONAL REVIEW DATE APPROVED DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

Appendix D NRC SCENARIO #1 FORM ES-D-1 Columbia Generating Station ILC NRC Exam March, 2009 Page 1 of 20 Facility: Columbia NRC Scenario No: 1 Examiners: _______________ Operators: _______________

Initial conditions:

The plant is operating at approximately 95% power due to economic dispatch.

Turnover Information:

Immediately after shift turnover, reactor power is to be raised with RRC Flow until Generator Output reaches 1150 MWe. At that point stop the power increase and place the Main Turbine into Governor Valve Optimization.

A reactivity brief for the power increase has been held. There are no pre-conditioning limits. The STA has verified average nodal ramp rates are below preconditioning ramp rate limits. TDAS points B031 & B032 are operational.

Event No.

Timeline Event Type*

Event Description

1.

T=0 R

(SRO/RO)

Increase power with flow to 1150 MWe.

2.

T=10 N

(BOP)

Place Main Turbine into Governor Valve Optimization.

3.

T=20 C

(SRO/BOP)

R (RO)

MS-RV-4A Fails Open - Pull Fuses to close (Tech Spec).

4.

T=25 N

(BOP)

Place RHR-B in Suppression Pool Cooling.

5.

T=35 C

(SRO/BOP)

HPCS-P-3 Failure (HPCS Keepfill Pump) (Tech Spec).

6.

T=45 C

(SRO/RO)

ASD Channel A2 alarm and fault.

7.

T=50 C (ALL)

ASD UPS trouble simulating both inverters on battery power requiring RRC flow reduction and manual scram.

8.

T=55 C (ALL)

RCIC shaft coupling breaks on initiation. Both RFW Pumps trip and can not be reset.

9.

T=60 M (ALL)

OBE and RHR-B Suction Break. Emergency Depressurization when SP Level cannot be maintained GT 192.

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

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 1 of 20 The scenario starts with Columbia at 95% power. One ADS SRV is tagged out due it opening during plant startup.

After shift turnover, reactor power will be raised with RRC Flow until Generator Output reaches 1150 MWe.

At that point the power increase will stop and the crew will place the MT into GV optimization.

The next event is a spurious opening of MS-RV-4A. ABN-SRV will be entered. When the SRV control switch is taken to close the valve will remain open. RHR will be placed in Suppression Pool Cooling per SOP-RHR-SPC. Fuses will have to be pulled to close the SRV. Tech Spec 3.5.1E will be applicable as this the second ADS SRV that is inop and the first required SRV being inop.

The next event is a failure of the HPCS keep fill pump, HPCS-P-3. The crew will take actions and pull the control power fuses for HPCS-P-1. This failure renders HPCS inoperable and Tech Specs will be referenced.

TS 3.5.1H is applicable due to HPCS and one required ADS SRV being inoperable which requires entry into TS LCO 3.0.3 immediately. A problem with re-installation of the fuses later in the scenario will render HPCS not available for the scenario.

When the brief associated with the shutdown is completed the next event will be initiated. This event is a GTO Freeze alarm on ASD channel 1A/2. RRC-P-1A will run back to 51 Hz. The crew will take action to match loop flows.

When flows are matched the next event is a failure of E-TR-ASD 1. An ASD UPS trouble alarm will be received and the crew will investigate. The transformer failure puts both ASD inverters on battery power. The report from the field will indicate that normal power can not be restored to the inverters. Per ABN-ADS-INV, the crew should reduce RRC flow, scram the reactor and carry out the actions of PPM 3.3.1. PPM 5.1.1 will be entered on low RPV level.

All rods will insert and as RPV level rises above +13, both RFW pumps will trip. When RFW pump resets are attempted they will not reset. RCIC will be initiated and a shaft shear will occur when turbine speed reaches 300 rpm. This effectively is a loss of HP injection sources.

The crew should lower RPV pressure with BPVs to facilitate feeding with condensate booster pumps. RPV level will be returned to +13 to +54 inch band.

After level has been returned to normal band, an OBE will occur. Due to the earthquake the suppression pool will develop a crack in the B RHR pump room. The crew should pull the control power fuses for RHR-P-2B.

ABN-FLOODING will be entered along with EOP PPM 5.2.1 and EOP PPM 5.3.1.

When it is determined that suppression pool level cannot be maintained GT 192 the crew should anticipate Emergency Depressurization is required and per PPM 5.1.1 override, fully open the BPVs. When suppression pool level reaches 192, the crew should exit to PPM 5.1.3 and open 7 ADS SRVs to perform an emergency depressurization.

The scenario will be terminated when the ED is performed and RPV level is being returned to normal band.

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 2 of 20 Event No. 1

==

Description:==

Increase reactor power with flow to achieve 1150 MWe.

This event is initiated by the turnover information.

Time Position Applicants Actions or Behavior T = 0 SRO Directs the RO to increase reactor power to achieve 1150 MWe with RRC flow at the rate of 10 MWe/minute.

RO Increases reactor power with RRC flow as directed at the rate directed.

Checks individual controllers in Auto and depresses raise pushbutton on Master Controller.

BOP Monitors plant equipment and peer checks RO.

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 3 of 20 Event No. 2

==

Description:==

Place the Main Turbine into Governor Valve Optimization This event is initiated by the turnover information and will take place when output reaches 1150 MWe Time Position Applicants Actions or Behavior T = 10 SRO Directs BOP operator to place the Main Turbine into Governor Valve Optimization per SOP-MT-GV/OPTIMIZATION.

BOP Per SOP-MT-GV/OPTIMIZATION performs the following:

Step 5.1.1 Verifies SNE info, TDAS points not inop, DEH in Turbine follow Reactor Mode; MWe GE 1092 and Reactor Power and Pressure stable Step 5.1.2a Verifies LOAD TARGET at 1370 MW Step 5.1.2b Sets VPL demand to 100%

Step 5.1.2c Verifies OK TO SELECT light illuminated Step 5.1.2d Selects OPTIMIZED VALVE MODE Step 5.1.2e Selects yes Step 5.1.2f Verifies valve movement Step 5.1.2g Sets VPL demand 10% GT GV Demand (GV demand at 80%)

Step 5.1.2h Verifies VPL Demand ramps to target value Step 5.1.2i Verifies VPL demand is 10% above GV Demand BOP Informs SRO that the MT is in Governor Valve Optimization Mode of operation.

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 4 of 20 Event No. 3

==

Description:==

MS-RV-4A spurious open - Fuses pulled to close SRV This event occurs when the MT has been placed in Governor Valve Optimization by activating TRIGGER 1.

Time Position Applicants Actions or Behavior T = 20 BOP Acknowledges SRV Open alarm, observes MS-RV-4A is open and refers to ARP.

Informs SRO and refers him to ABN-SRV.

SRO Enters ABN-SRV and:

Verify SRV open by tail pipe temp rise or SP Temp/level rise or MG output reduction With Reactor Power being GT 90% directs:

• MS-RV-4A switch be placed to open

• Reactor power be reduced with flow to LE 90%

When power is LT 90% - directs BOP to place the control switch for MS-RV-4A to OFF.

RO Reduces Reactor power to LE 90% with recirc flow.

BOP Places MS-RV-4A control switch to OPEN as directed.

Places control switch to OFF when directed (Power LT 90%) and observes that the SRV is still open and informs the SRO.

SRO Directs placing RHR in Suppression Pool Cooling per SOP-RHR-SPC (Refer to Event 4).

SRO Directs fuses be pulled per Attachment 7.1.

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 5 of 20 BOP Takes all watches/rings off, wears safety glasses and using small yellow fuse pullers, removes Fuses BB-F11 and BB-F12 in H13-P628 (SRV still open); Fuses AA-F11 and AA-F12 in H13-P631 (SRV still open); Fuses BB-F49 and BB-F50 in H13-P628 which closes the SRV.

BOP Verifies indication on P601 and informs SRO that MS-RV-4A is closed.

SRO Refers to Tech Specs and notes that TS 3.5.1E applies which requires restoration of ADS valve to operable status in 14 days.

Contacts Work Week Manager and conducts brief.

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 6 of 20 Event No. 4

==

Description:==

Place RHR B in Suppression Pool Cooling per SOP-RHR-SPC The event is initiated by ABN-SRV performance Time Position Applicants Actions or Behavior T = 25 SRO Directs placing RHR-B in Suppression Pool Cooling per SOP-RHR-SPC.

BOP Verify RHR-A operable.

Verify SW-P-1B running - otherwise N / A.

Start RHR-P-2B by taking C/S to start.

Verifies RHR-FCV-64B opens.

Verifies SW-P-1B running.

Throttle open RHR-V-24B to between 2500 - 7000 gpm, as determined by the CRS.

Verify RHR-V-64B closes.

If maximum cooling is desired, closes RHR-V-48B.

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 7 of 20 Event No. 5

==

Description:==

HPCS System Keep fill pump, HPCS-P-3, failure.

This event is initiated by activating TRIGGER 2 after Technical Specifications have been referenced and a brief has been completed.

Time Position Applicants Actions or Behavior T = 35 BOP Acknowledges HPCS WATER LEG PUMP DISCH PRESS LOW and HPCS SYSTEM OUT OF SERVICE alarms.

Observes HPCS system pressure and HPCS-P-3 not running.

Refers to ARP and informs SRO of condition.

Directs OPS 2 investigate pump and breaker for HPCS-P-3.

Requests OPS2 provide reading on HPCS-PIS-13 per the ARP.

SRO Per ARP, directs HPCS-P-1 control power fuses be pulled.

Contacts Work Week Manager.

Refers to Tech Spec 3.5.1 and notes that condition H applies. which requires TS LCO 3.0.3 be entered immediately which requires an actions be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit in MODE 2 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, MODE 3 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />; and MODE 4 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.

May direct LPCS, RCIC, and ADS be protected per OI-49.

Booth Operator: Three minutes after being sent, report back as OPS 2 that the pump motor is very hot to the touch.

Cue: If asked, HPCS-PIS-13 on P024 indicates 50 psig and looks to be going down slowly (alarm annunciates at 53 psig)

Booth Operator: Two minutes after request to pull control power fuses on HPCS-P-1 activate TRIGGER 10 and report completion to Control Room.

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 8 of 20 Event No. 6

==

Description:==

ASD Channel A2 alarm and fault.

This event is initiated by activating TRIGGER 3 after brief is completed or as directed.

Time Position Applicants Actions or Behavior T = 45 RO Acknowledges LOOP A ASD CHANNEL FAILURE LIMIT alarm.

Reports trip of ASD 1A/2 alarm and Fault alarms and RECIRC A OR B HIGH FLOW DELTA alarm.

Verifies trip of channel ASD1 A/2.

Ensures RRC-P-1A has runback to 51 Hz.

Reports power drop due to runback. Reports RPV power/level/pressure.

Checks ASD video Display Unit for source of alarm.

Dispatches OPS1/4 to investigate at the ASD Building.

Verifies Power/Flow map position.

SRO Directs actions per ARPs.

Cue: Call 2393 and report as OPS4 that there is a GTO freeze alarm on Channel 1A2. Also inform the RO that there seems to be a burnt electrical smell in the building but you see nothing else wrong.

If asked as OPS4 for the Horse Power on the RRC Pump that value is indicated on the Home Page

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 9 of 20 SRO Per ARP for high delta flow (4.602.A6 6-2):

Refers to ABN-POWER for the unplanned power change.

SRO Refers to Tech Spec 3.4.1, flow mismatch, which is applicable until flows are matched.

Contacts Work Week Manager for ASD Channel fault.

Directs RO to match RRC loop flows by lowering RRC Loop B flow.

RO Reduces RRC-P-1B speed as directed to match flows and clear High Flow Delta alarm.

May reduce RRC-B speed with controllers in Auto or may take manual control of RRC-M/A-R676B.

FLOOR ROLEPLAY: If asked for, report Powerplex shows nodal powers are within preconditioning and thermal limits

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 10 of 20 Event No. 7

==

Description:==

ASD UPS trouble alarm which simulates the loss of E-PP-ASD1/4.

This event is initiated by activating TRIGGER 4 and should be initiated after RRC loop flows are matched or as directed.

Time Position Applicants Actions or Behavior Critical Task is to initiate a Manual Reactor Scram when it is determined both ASD inverters are on battery power T = 50 RO Reports ASD UPS Trouble Alarm (P602.A13 3-5) and refers to ARP.

SRO Refers to ARP and to ABN-ASD-INV.

BOP Sends OPS4 to investigate.

BOOTH OPERATOR: One minute after being sent to investigate, call on the radio and report that there are no lights on in the ASD building. There was electrical arcing occurring in E-TR-ASD-1. The main breaker supplying E-PP-ASD 1/3 opened and E-PP-ASD-1/3 is deenergized.

The arcing has stopped and you have exiting the building.

SRO Acknowledges report and refers to Attachment 7.1.

Determines that E-PP-ASD 1/3 is de-energized and that IN-ASD/1A and 1B panels are on battery power.

Determines that normal AC power is not going to be restored to the inverters and that flow reduction and scram are required SRO Conducts brief.

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 11 of 20 Directs that RRC flow be reduced to 60 Mlbm/hr.

Directs a manual scram of reactor.

RO Lowers Core Flow to 60 Mlbm/hr as directed.

Announces Listen up for the scram report.

Performs immediate scram actions:

• Places Reactor Mode Switch in SHUTDOWN

• Monitors Power, Pressure, and Level

• Verifies all rods inserted

• Inserts IRMs and SRMs by depressing INSERT P/B Reports EOP entry on low RPV water level.

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 12 of 20 Event No. 8

==

Description:==

RCIC Shaft Coupling breaks when 300 rpm is reached. RFW Pumps trip and can not be reset.

The RCIC event is active from the start of the scenario. RFW pumps auto trip when mode switch is taken to shutdown.

Time Position Applicants Actions or Behavior T = 555T SRO Enters (and re-enters) PPM 5.1.1 and directs restoration of RPV level to

+13 inches to +54 inches (a -40 to +50 band should be given) with RCIC and/or Reactor Feed Pump.

RO Reports both Reactor Feed Pumps tripped.

SRO Directs that the second CRD pump be started.

RO Starts second CRD pump when directed.

May direct ABN-CRD-MAXFLOW be performed.

ROLE-PLAY - three minutes after request for ABN-CRD-MAXFLOW, activate TRIGGER 26 and when valves are finished re-positioning, report completion to control room.

ROLE-PLAY - If sent to RCIC room to investigate, report shaft coupling in pieces on the floor.

RO/BOP When RCIC is initiated, reports that no discharge pressure/flow is observed on RCIC. May report that RPMs did rise but are zero now.

When reset of RFW is attempted, reports they cannot be reset.

Performs actions of PPM 3.3.1 (Verify RRC/P speed, Verify 4 IRM/APRM recorders selected to IRM, Announce Rx scram).

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 13 of 20 BOP Reports +13 initiations and isolations sat and monitors pressure.

SRO Directs the BOP to reduce RPV pressure to 550 psig at 50 psig per minute with Bypass Valves to allow injection with the condensate booster pumps.

BOP Reduces pressure as directed with BPVs, using quick card.

RO Sets up feedwater level control for RFW-V-10A/B valve operation.

Injects with condensate booster pumps when pressure has been reduce to 500 psig to 600 psig.

Restores reactor level to +13 inches to + 54 inches.

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 14 of 20 Event No. 9

==

Description:==

OBE and RHR-B Suction Break This event is initiated after RPV pressure has been lowered to 500 to 600 psig band and RPV level is being controlled +13 to +54.

BOOTH OPERATOR: During the remainder of the scenario, if asked to re-install the HPCS-P-1 control power fuses, report the fuse block broke and you have contacted the electricians to come help. HPCS-P-1 will NOT be returned to service during the scenario.

BOOTH OPERATOR: Start earthquake machine at low volume working quickly up to full volume and leave on for a 20 seconds total EQ. When full volume is reached, activate TRIGGER 5.

Time Position Applicants Actions or Behavior Booth Operator: When EQ is completed, as OPS1, call the control room on the radio and report that you felt severe shaking and movement in the turbine building.

T = 60 BOP Reports OBE annunciator, pulls ARP and refers SRO to ABN-EARTHQUAKE.

Investigates and reports indications on Bd. L.

SRO Directs actions for earthquake per ABN-EARTHQUAKE:

• Directs plant announcement

• Directs SAS repeat announcement RO Reports:

• Reactor Sump R2 level Hi Hi alarm

• Suppression Pool level Hi/Low Suppression Pool level low alarm

• Reports lowering trend on Suppression Pool Water Level

• Reports EOP 5.2.1 entry at -2 when it occurs.

• Reports RHR B Room level Hi EOP entry into PPM 5.3.1.

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 15 of 20 ROLE-PLAY - If asked to investigate RHR room leak, wait two minutes and report water coming from a crack down the side of the suppression pool wall that EXTENDS INTO THE FLOOR and water is flowing out of the room through that crack. You have exited the room and closed the hatch behind you.

SRO Enters PPM 5.2.1 on low SP level and directs actions per ABN-FLOODING.

Enters PPM 5.3.1 on RHR B room level Hi.

Directs OPS2 to investigate water level in RHR B room.

Determines that RHR B is not operational due to flooding.

May direct the RO to close RHR-V-4B in an attempt to isolate the leak.

May direct pulling of RHR-P-2B control power fuses.

May direct the control power fuses be re-installed for HPCS-P-1.

Cue: If directed, wait three minutes, then ACTIVATE TRIGGER 6 to pull RHR-P-2B fuses and report completion.

Cue: If HPCS-P-1 control power fuses are directed to be reinstalled, report the fuse block is cracked in half and you have contacted the electricians to help get it fixed (the fuses will NOT get reinstalled for the remainder of the scenario).

RO/BOP If directed, closes RHR-V-4B.

Reports continued lowering trend on Suppression Pool level.

Event No. 10

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 16 of 20

==

Description:==

Emergency Depressurization due to low Suppression Pool level This event is initiated when SP level cannot be maintained GT 192. SP Level drops about 1 foot every 2 minutes.

Time Position Applicants Actions or Behavior Critical Task is to initiate an Emergency Depressurization when Suppression Pool level cannot be maintained GT 192.

Note: SRO may anticipate the ED on low suppression pool level and direct the bypass valves be opened to rapidly reduce pressure.

BOP Continues to give Suppression Pool level reports as level drops.

SRO Determines that Suppression Pool level will not be able to be maintained above 192.

May take override in PPM 5.1.1 pressure leg and anticipate Emergency Depressurization.

May direct BPVs be rapidly opened.

RO/BOP If directed, takes manual control of the Bypass Valves and fully opens them.

SRO When Emergency Depressurization is required due to low suppression pool level, (SP Level LE 192) exits pressure leg of PPM 5.1.1.

Enters PPM 5.1.3 and directs 7 ADS SRVs open.

May direct ECCS injection valve control switches be held in close while pressure drops below 470 psig.

RO/BOP Opens 7 ADS SRVs to depressurize the reactor.

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 17 of 20 SRO Directs injection with systems to return RPV level to +13 to +54.

RO/BOP Returns RPV level to band as directed.

This scenario will be terminated when the reactor has been emergency depressurized and RPV level is under control and stable/increasing.

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 18 of 20 SRO TURNOVER INFORMATION Initial Conditions: The plant is operating at approximately 95% power due to economic dispatch. MS-RV-5C has been de-energized due to it opening during plant startup.

Turnover Information:

Immediately after shift turnover, reactor power is to be raised with RRC Flow until Generator Output reaches 1150 MWe. At that point stop the power increase and place the Main Turbine into Governor Valve Optimization.

A reactivity brief for the power increase has been held and power is to be increased immediately following shift turnover. There are no pre-conditioning limits. The STA has verified average nodal ramp rates are below preconditioning ramp rate limits. TDAS points B031 &

B032 are operational.

SIMULATOR SETUP INSTRUCTIONS Reset to IC-179 Place a Danger tag on MS-RV-5C Set Up Earthquake Machine on Low Volume

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 19 of 20 BAT FILE 2009 NRC Scenario 1

>* Trigger list *

>Trigger 1 MS-SRV-4A Fails Open

>Trigger 2 HPCS-P-3 Shaft break

>Trigger 3 ASD CH A2 alarm/fault

>Trigger 4 ASD UPS Trouble Simulates loss of E-PP-ASD 1/4

>Trigger 5 EQ, Suppression Pool Leak, RHR B Suction break

>Trigger 6 Pull control power fuses for RHR-P-2B

>Trigger 8 Conditional for RCIC Shaft Break (when 300 rpm is reached)

>Trigger 9 Conditional for RFW A/B trip (cannot reset)(on MODE SW in SD)

>Trigger 10 Pull Control Power Fuses for HPCS-P-1

>The following items are set at the beginning of the scenario

>TAG OUT MS-RV-5C IOR OVR-RRS013C ON IOR OVR-RRS013D OFF IOR OVR-RRS013A OFF IOR OVR-RRS013B OFF

>The following items are triggered in the scenario

> TRIGGER 1 SRV-4A fails Open IOR OVR-RRS042C (1) OFF IOR OVR-RRS042D (1) ON

> TRIGGER 2 HPCS-P-3 Shaft Break & Low Press Alarm IRF LOA-EPS137 (2) DISCONNECT IRF PLP-CSS006 (2) 0.01 0 IRF PLP-CSS002 (2) 2.0 0 IOR STL-HPCS31 (2) ON

> TRIGGER 3 ASD CH A2 alarm and Fault IMF MAL-RFC002E (3)

IMF MAL-RFC006A (3)

> TRIGGER 4 ASD UPS Trouble Alarm IMF ANN-602A13C05 (4) 0

> TRIGGER 5 - SUPP CHAMBER LEVEL INDICATION

> SLOWLY DROPS TO BOTTOM OF SCALE (8"/MIN)

IMF XMT-PCN003A (5 5) -25 198 IMF XMT-PCN004A (5 5) -24.94 200 IMF XMT-PCN006A (5 5) 3 3000 IMF XMT-PCN007A (5 5) 2 2999

Appendix D NRC SCENARIO #1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 20 of 20

> LINE BREAK AT RHR-P-2B SUCTION IMF MAL-RHR005 (5 10) 8000

> EARTHQUAKE IMF MAL-RWB001 (5) 0.3

> TRIGGER 6 - PULLS CONTROL POWER FUSES FOR RHR-P-2B IRF LOA-EPS397 (6) 1

> TRIGGER 10 - PULLS CONTROL POWER FUSES FOR HPCS-P-1 IMF BKR-CSS001 (10) 5

>The following are conditionals to initiate triggers

> Causes the RCIC pump shaft to seize when speed exceeds 300 rpm IMF PMP-RCI001S (8) TRUE TRGSET 8 "X01D066M.GT.300"

> Mode switch to shutdown causes RFW pumps to trip cannot be reset TRGSET 9 "X03I102S.GT.0" IOR OVR-FPT002B (9) ON IOR OVR-FPT002C (9) OFF IOR OVR-FPT007B (9) ON IOR OVR-FPT007C (9) OFF

>Local Bat file loads generic triggers for local plant actions bat LOCAL.txt

INSTRUCTIONAL COVER SHEET PROGRAM OPERATIONS TRAINING COURSE TITLE COLUMBIA GENERATING STATION SIMULATOR EXAMINATION LESSON TITLE DG-3 Monthly Surveillance, Failure of HPCS-P-2, LPRM Fails Upscale, FWH-6B High Level Trip, DEH Leak Requiring Manual Scram, Loss of TR-S, DG-1/2 Fails to Auto Start, LOCA, ED on RPV Level LENGTH OF LESSON 1.5 Hours INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code LO001626 Rev. No.

0 JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 06/16/08 REVISED BY DATE VALIDATED BY DATE TECHNICAL REVIEW DATE INSTRUCTIONAL REVIEW DATE APPROVED DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

Appendix D NRC SCENARIO No. 2 FORM ES-D-1 Columbia Generating Station ILC NRC Exam March, 2009 Page 22 of 23 Facility: Columbia NRC Scenario No: 2 Examiners: _______________ Operators: _______________

Initial Conditions:

The reactor has been operating at 100% power for the last 131 days. This is a Division 3 work week. OSP-ELEC-M703, DG-3 Monthly Surveillance, is in progress. OPS 2 is standing by in the HPCS DG room. DG-3 is running and SM-2 is being powered from TR-S per OPS-ELEC-M703. PDIS signal X108 (DG3 voltage) is not available.

Turnover Information:

Continue with DG-3 monthly surveillance which has been completed through step 7.5.49.

Event No.

Timeline Position Applicants Actions or Behavior

1.

T = 0 N (BOP)

Synchronize DG-3 per monthly surveillance OSP-ELEC-M703

2.

T = 10 C (BOP)

C (SRO)

Failure of HPCS-P-2 requiring manual trip of DG-3 SRO - Tech Spec

3.

T = 20 C

(SRO/RO/BOP)

LPRM Fails Upscale SRO - Tech Spec

4.

T = 30 R (RO)

High Level Trip of FWH-6B requiring reducing core flow to LE 92 Mlbm/hr Rod Line GT 100% requiring using Fast Shutdown Sequence to insert rods to lower the rod line May also require core flow be lowered to 75 Mlbm/hr if more rods have to be inserted

5.

T = 45 C (SRO/BOP)

DEH Leak eventually requires a manual scram be inserted

6.

T = 55 C (All)

TR-S Lockout; MSIVs close, Initiate RCIC/CRD for level control

7.

T = 60 C (RO)

DG-1 and DG-2 Fails to Auto Start

8.

T = 65 M (All)

LOCA - Spray Wetwell and Drywell

9.

T - 70 LOCA - RPV level drops to TAF. Initiate Emergency Depressurization on low RPV Level and return level to normal with low pressure ECCS pumps.

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

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 23 of 23 SCENARIO DESCRIPTION The scenario begins with power at 100%. DG-3 is running and SM-2 is powered from Startup to support surveillance testing of DG-3.

Turnover information is that OSP-ELEC-M703, DG-3 Monthly Surveillance, is in progress and DG-3 is running and is ready to be synchronized. The BOP operator will continue with this surveillance and sync DG-3.

A short time after the DG-3 is synchronized, HPCS-P-2 will trip and Service Water to DG-3 will be lost.

Per the immediate actions of ABN-SW, DG-3 will be tripped locally. The SRO will review Tech Specs for HPCS DG being INOP.

The next event is a failure of LPRM 6C-32-09 associated with APRM B. ABN-LPRM will be entered and the LPRN will be bypassed. Tech Spec 3.3.1.1 will be referenced.

The next event is a high level trip of High Pressure Feedwater Heater 6B. Feedwater temperature will drop by GT 6°F requiring entry into ABN-POWER. Reactor Power to rise requiring the RO to lower power with flow and to drive control rods to maintain LT the 100% rod line. When the fast shutdown sequence is used to insert control rods it requires core flow to be lowered to 92 Mlbm/hr and then to 75Mlbm/hr (depending on rod line).

The next event is a leak in the DEH system. ABN-DEH will be entered and the leak rate will require a reactor scram and trip of the Main Turbine and Main Generator.

When TR-S closes in it will lockout. TR-B will power SM-7 and SM-8.

When TR-S is lost the MSIVs will close causing a LOCA to develop. Manual pressure control on SRV will be required. RCIC will be initiated and CRD restarted to feed the RPV but RPV level will continue to drop.

On the High Drywell Pressure initiation signal, DG-1 and DG-2 will fail to auto start. When initiations are checked the RO will take actions and manually start both Diesel Generators.

RPV level will eventually drop to LT -161 and an Emergency Depressurization will be initiated to facilitate feeding with low pressure ECCS pumps.

Containment pressures will rise requiring the crew to spray the wetwell and the drywell. Sprays will be removed from service to allow RPV injection after the Emergency Depressurization occurs.

The scenario will be terminated when RPV level is being returned to normal band and sprays have been re-initiated as appropriate.

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 24 of 23 Event No. 1

==

Description:==

Synchronize DG-3 for monthly surveillance OSP-ELEC-M703.

This event is initiated by the turnover sheet.

Time Position Applicants Actions or Behavior T = 0 SRO Directs the BOP to complete OSP-ELEC-M703 starting at step 7.5.50.

BOP (N)

At H13-P601, places the CB-4DG3 Sync Selector Switch to D.

GEN/BUS.

Raises voltage using Diesel Generator Voltage Reg Control switch until incoming voltage is slightly higher than running voltage.

Raises frequency with the Electric Governor control switch until sync scope is running slow in the fast (Clockwise) direction.

When the sync scope is about 5 minutes before the 12 oclock position, places CB-4DG3 control switch in the CLOSE position.

Verifies breaker closes.

Immediately verifies KVARs are zero or slightly positive.

Immediately loads DG-3 to GE 100 KW using the Electric Governor control switch.

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 25 of 23 Gradually loads DG-3 to 1300KW using the Electric Governor control switch.

Adjust reactive load to approximately 325 KVAR out (to the right) using Diesel Generator Voltage Regulator Control switch.

Places CB-4/DG3 Sync Selector Switch to OFF.

Wait 5 minutes.

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 26 of 23 Event No. 2

==

Description:==

Failure of HPCS-P-2 (DG-3 Service Water pump).

This event is initiated when the 5 minute wait step has been reached (Step 7.5.59) during operability test of DG-3 and is initiated by activating TRIGGER 1.

Time Position Applicants Actions or Behavior T = 10 BOP (C)

Acknowledges alarms associated with the loss of HPCS-P-2.

Scans panel and notes HPCS-P-2 is not running and SW-V-29 is going closed.

Informs SRO of loss of HPCS-P-2. May give ABN reference to SRO and that a local trip of DG-3 is required (immediate action of ABN-SW).

May direct OPS 4 investigate loss of pump.

BOOTH OPERATOR - If requested, three minutes after request inform the Control Room that HPCS-P-2 is hot to the touch and the motor looks scorched.

If required, the breaker is tripped for HPCS-P-2 on MC-4A.

SRO (C)

Announces entry into ABN-SW.

Directs BOP to have DG-3 tripped at the local panel (if BOP has not already performed).

BOOTH OPERATOR - 30 seconds after request to trip DG-3, activate TRIGGER 20 and inform the control room when trip has occurred.

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 27 of 23 SRO Contacts Work Week Manager.

Reviews Technical Specifications:

TS 3.7.2 HPCS SW inoperable - requires the HPCS System be declared inoperable immediately.

TS 3.5.1B HPCS System inoperable - requires RCIC operability be verified immediately and restore HPCS within 14 days May protect systems per OI-49.

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 28 of 23 Event No. 3

==

Description:==

LPRM 6C-32-09 fails upscale.

This event is initiated when the actions for HPCS-P-2 failure are complete and is initiated by activating TRIGGER 2.

Time Position Applicants Actions or Behavior T = 20 RO Acknowledges LPRM Upscale and APRM Upscale alarms: H13-P603 A8 drop 2-5 and 2-6.

Identifies LPRM 32-9C indicated upscale and APRM F reading 107%.

Refers to ARPs.

BOP Investigates back panel P608 and informs SRO of the upscale reading on LPRM 6C-32-09 and APRM B reading.

CUE: When ABN-LPRM is entered and information is being requested, inform the SRO that the SNE has determined that bypassing the APRM is not required.

SRO Refers to ARP and enters ABN-LPRM.

Directs LPRM be bypassed per ABN-LPRM.

Contacts SNE, System Engineer and/or Maintenance Supervisor.

Refers to TS 3.3.1.1 and determines that APRM B is operable.

Directs BOP to bypass the LPRM.

BOP At P608 selects the LPRM to be bypassed on the appropriate APRM/LPRM

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 29 of 23 group meter.

Places the mode switch for 6C-32-09 in BYPASS.

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 30 of 23 Event No. 4

==

Description:==

High Level Trip of High Pressure Feedwater Heater 6B.

This event is initiated when the actions for bypassing the LPRM are completed and is initiated by activating TRIGGER 3.

Time Position Applicants Actions or Behavior T = 30 RO Acknowledges HTR 6B High level alarm and refers to ARP.

BOP Investigates backpanel and notes controllers for dump and drain valves in AUTO and requiring the valves to be open but level continues to rise. Note:

Nothing the operator does will cause level to stop rising.

Reports actions (if any) to SRO and that level in FWH 6B cannot be controlled.

RO (R)

Acknowledges Heater 6B High Level Trip and steam dump valves not fully closed alarms (MSR B heater drain tank alarms may also annunciate).

Reports trip of 6B Heater to SRO and entry into ABN-POWER and ABN-FWH-Hi/Level-trip.

Due to the FWH trip, observes feedwater inlet temperature and notes that it has dropped more than 6°F (begin temp is about 411°F and final temp is about 391°F).

Notes Thermal Power has gone up and when GT 3486 MWT, reduces power with RRC flow to maintain LT 3486 MWT per Immediate actions of ABN-POWER.

(Note: SRO may direct power reduction to LE 92Mlbm/hr prior to RO reducing to LT 3486 MWT.)

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 31 of 23 SRO (C)

Announced entry into ABN-POWER and per step 4.4.1, directs RRC flow be lowered to LE 92 Mlbm/hr core flow.

Ensures plant operating in acceptable region of Attachment 7.1.

Announces entry into ABN-FWH-Hi/Level-trip.

When conditions are stable may request a Mon Run.

RO (R)

Reduces RRC Flow to 92 Mlbm/hr (if GT 92 Mlbm/hr).

Refers to the Fast Shutdown Sequence and inserts control rods to maintain rod line LT 100%.

If rod line still GT 100% when done with first group of rods, reduces RRC flow to LE 76 Mlbm/hr.

If necessary, drives control rods to maintain LT 100% rod line.

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 32 of 23 Event No. 5

==

Description:==

DEH System Leak requiring a Manual Scram be inserted.

This event is initiated when the actions for the trip of FWH 6B are complete and is initiated by activating TRIGGER 4.

Time Position Applicants Actions or Behavior Critical Task is to initiate a Manual Reactor Scram when the DEH Low Low Reservoir Level alarm annunciates within 15 minutes of the Low Reservoir level annunciator.

T = 45 BOP (C)

Acknowledges DEH Reservoir Level Low annunciator and refers to ARP.

Directs OPS3 to investigate locally and report level on DEH-LG-17.

References ABN-DEH-LEAK to SRO.

SRO (C)

Announces entry into ABN-DEH-LEAK.

Directs that OPS1 commence filling the DEH reservoir per SOP-DEH-OPS and look for DEH leaks.

Notes time and starts 15 minute clock for step 4.1.1 of ABN-DEH-LEAK.

BOOTH OPERATOR - Initial tank level will be one minute after request and remainder of reports will be consistent with time since trigger initiation as follows:

Initial report tank level is 16.75; Level report will be 1/2 less each minute after initial level report. It takes 11 minutes to get Low Low Level alarm which required a manual scram If asked to fill reservoir wait a minute and report 2 or 3 gallons are all that is left in barrel and you have called to get another barrel brought in from the warehouse.

BOP Acknowledges DEH Reservoir Level Low Low annunciator and refers to

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 33 of 23 ARP (It takes 11 minutes from low level alarm to get low-low alarm).

SRO Directs manual scram; trip of Main Turbine, and trip of Main Generator per step 4.1.1 of ABN-DEH-LEAK.

RO Announces Listen up for the scram report and places MODE switch to shutdown. Announces APRM downscales in, RPV pressure reading and trend, RPV level reading and trend, and EOP entry on low RPV level.

Announces all-rods-in to SRO.

BOP Initiates trip of the Main Turbine (if not automatically completed) by depressing the two Turbine trip pushbuttons.

Initiates trip of the Main Generator (if not automatically complete) by depressing the two red Unit Emergency and Unit Overall Emergency pushbuttons.

SRO Announces entry into EOP 5.1.1, RPV Control, on low RPV level.

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 34 of 23 Event No. 6

==

Description:==

Lockout of the Startup Transformer. MSIVs close, Initiate RCIC and CRD This event is automatically initiated when CB-S1 breaker closes.

Time Position Applicants Actions or Behavior T = 55 BOP Investigates electrical board status when lights go out after TR-S lockout.

Notes no power to SM-1, SM-2, SM-3, SH-5 or SH-6.

Notes TR-B is powering SM-7 and SM-8.

Updates crew on plants electrical board status.

BOP/RO Notes that MSIVs have closed and announces pressure control with SRVs at a pressure band of 800 to 1000 psig.

SRO Working down the level leg of EOP 5.1.1, notes that no high pressure injection sources are running. Directs RCIC and CRD be initiated and injection to RPV at a level band of +13 to +54 (band should be -40 to +50).

BOP/RO Using the quick card, Arms and Depresses RCIC Manual Initiation pushbutton and verifies injection at 600 gpm.

Starts the second CRD pump as directed. May direct ABN-CRD-MAXFLOW be performed to facilitate running both CRD pumps.

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 35 of 23 BOOTH OPERATOR - If requested, wait 5 minutes and then activate TRIGGER 26 to place both CRD suction and discharge filters on line and report completion to control room.

BOP/RO Notes that no CAS air compressors are running, contacts OPS3 and directs the reset of CAS compressors.

BOOTH OPERATOR - If requested, wait 2 minutes and then initiate trigger (23) to reset CAS Air Compressors.

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 36 of 23 Event No. 7

==

Description:==

Failure of DG-1 and DG-2 to AUTO start on Undervoltage or when DW/P reaches 1.68 psig.

This event is automatically initiated when SM-7 and SM-8 become de-energized or when DW/P rises above 1.68 psig.

Time Position Applicants Actions or Behavior T = 60 BOP/RO (C)

When TR-S locks out of when initiations are checked due to DW/P being GT 1.68 psig, notes that neither DG-1 nor DG-2 are running.

Takes control switches for both DG-1 and DG-2 to start and notes that they did start.

Informs SRO of failure of DGs to auto start.

Directs OPS 3 verify DG operation after auto start.

BOOTH OPERATOR: After requested, wait 5 minutes and report DG 1 and DG2 operating normally.

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 37 of 23 Event No. 8

==

Description:==

LOCA (Containment Sprays).

This event is initiated automatically one minute after the MSIVs close.

Time Position Applicants Actions or Behavior T = 65 RO/BOP Recognizes rising DW Pressure and reports EOP entry at 1.68 psig.

Also reports additional primary containment EOP entries as they occur.

SRO Enters EOP 5.2.1, Primary Containment Control and re-enters 5.1.1 due to high DW pressure.

Directs isolations, initiations and DG starts for +13, -50 and 1.68 psig be verified as parameters occur.

RO/BOP Reports Wetwell pressure when it reaches 2 psig.

SRO Directs Wetwell sprays with RHR. Directs securing sprays if pressure drops below 1.68 psig.

RO/BOP Using quick card, initiates wetwell sprays and supplements with wetwell cooling and reports completion to SRO.

SRO May directs other loop of RHR be placed in suppression pool cooling.

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 38 of 23 RO/BOP Utilizing quick card, places RHR loop in SP Cooling.

RO/BOP Reports Wetwell pressure when it reaches 12 psig.

SRO Directs drywell cooling fans be secured.

RO/BOP Secures drywell cooling fans as directed and reports completion.

SRO Directs DSIL verification and then drywell sprays be initiated. Directs securing sprays if drywell pressure drops below 1.68 psig.

RO/BOP Verifies within DSIL and using quick card, initiates drywell sprays as directed.

Reports Drywell pressure drop as expected.

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 39 of 23 Event No. 9

==

Description:==

LOCA (RPV Level Drop).

This event is initiated automatically one minute after TR-S lockout and the MSIVs close.

Time Position Applicants Actions or Behavior T = 70 BOP/RO Reports RPV level dropping even with RCIC and CRD running.

Gives RPV level reports as level continues to lower.

NOTE - From the time -50 RPV/ Level is reached, it takes about 5 minutes to get to -129 RPV/L and another minute to get to TAF and an additional minute to get to -183 RPV/L.

SRO Directs ADS be inhibited when ADS timers initiate.

As level drops, expands RPV band given.

BOP/RO When RPV/L drops to -129 and the ADS timers intimate, takes both ADS inhibit switches to inhibit and acknowledges BISIs.

Reports ADS inhibited to SRO.

BOP/RO Reports RPV level as it transitions from Wide Range to Fuel Zone indicators.

Reports RPV level at TAF and trend continues down slow.

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 40 of 23

==

Description:==

Initiate Emergency Depressurization.

This is initiated when it is determined that RPV level cannot be restored and maintained GT -183.

Critical Task is to initiate an Emergency Depressurization when TAF is reached at -161 and before RPV Level drops to -183.

Time Position Applicants Actions or Behavior SRO Determines that Emergency Depressurization is required.

Enters PPM 5.1.3, Emergency Depressurization, and determines wetwell level GT 17.

Directs 7 ADS SRVs be opened.

RO/BOP Opens 7 ADS SRVs as directed.

SRO Directs wetwell and drywell sprays and suppression pool cooling be secured to facilitate RPV injection.

RO/BOP Secures DW and WW sprays and SP cooling as directed.

Allows ECCS injection valves to open at 470 psig.

Reports RPV injection as it occurs.

Reports RPV level rising and when GT -161 inches.

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 41 of 23 Event No. 11

==

Description:==

Re-initiation of Wetwell and Drywell Sprays.

This event is initiated by the SRO when RPV level has been raised GT TAF.

Time Position Applicants Actions or Behavior SRO Based on rate of RPV level change, injection systems available, and wetwell pressure, directs re-initiation of wetwell and drywell sprays and suppression pool cooling with RHR as appropriate (Wetwell spray initiation if WW/P GT 2 psig and DW Spray initiation if WW/P GT 12 psig.

RO/BOP Secures injection systems as directed to return RPV level to +13 to +54 inch band.

Reinitiates wetwell and drywell sprays as appropriate.

Reinitiates suppression pool cooling as directed.

Termination Criteria: The scenario will be terminated when RPV level is being returned to normal and wetwell and drywell sprays have been initiated as appropriate.

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 42 of 23 TURNOVER INFORMATION Initial Conditions:

The reactor has been operating at 100% power for the last 131 days. This is a Division 3 work week. OSP-ELEC-M703, DG-3 Monthly Surveillance, is in progress. OPS 2 is standing by in the HPCS DG room. DG-3 is running and SM-2 is being powered from TR-S per OPS-ELEC-M703. PDIS signal X108 (DG3 voltage) is not available.

Turnover Information:

Continue with OSP-ELEC-M703, DG-3 Monthly Surveillance, which has been completed up through step 7.5.49.

SIMULATOR SETUP Reset to IC-180.

Have HPCS DG Surveillance signed off thru step 7.5.49.

Ensure sign at SRO desk indicates a Division 3 work week.

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 43 of 23 BAT FILE

> 2009 NRC Scenario #2

>* Trigger list *

>Trigger 1 HPCS-P-2 Shaft Seizure

>Trigger 2 LPRM Upscale

>Trigger 3 Feedwater Heater 6B Trips

>Trigger 4 DEH Leak

>Trigger 10 Conditional for TR-S Lockout and LOCA on CB S1 closure

>The following items setup conditions for the beginning of the scenario

> DG1 ECCS - FAIL AUTO START IMF MAL-DGN006A TRUE IMF MAL-DGN007A TRUE

> DG2 ECCS - FAIL AUTO START IMF MAL-DGN006B TRUE IMF MAL-DGN007B TRUE

>The following items are triggered in the scenario

>TRIGGER 1 - HPCS-P-2 SHAFT SEIZURE IMF PMP-SSW001S (1) TRUE

>TRIGGER 2 - 6C-32-09 LPRM UPSCALE IMF MAL-NIS008-413 (2) 0

>TRIGGER 3 Feed Water Heater 6B TRIPS ON HIGH LEVEL

> DUMP VALVE LCV-6B2 FAILS CLOSED IMF AOV-FWH050F (3) 1

> DRAIN VALVE LCV-6B1 FAILS CLOSED IMF AOV-FWH049F (3) 1

>TRIGGER 4 - SIMULATES DEH LEAK

> DEH RESERVOIR LEVEL LOW ALARM (P820-B1.6-7)

IMF ANN-820B1F07 (4) 0

> DEH RESERVOIR LEVEL LOW-LOW ALARM (P820-B1.7-7)

IMF ANN-820B1G07 (4 660) 0

>The following are conditionals to initiate triggers

>TRIGGER 10 TR-S TRIP/LOCKS-OUT ON CLOSURE ON CB-S1 IMF MAL-OED001 (10) TRUE IMF MAL-RRS004B (10 60) 2 600 TRGSET 10 "X8CO230R.GT.0"

>Local Bat file loads generic triggers for local plant actions bat local.txt

Appendix D NRC SCENARIO No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam March, 2009 Page 44 of 23