Text

2015-04 Draft Op Test
	ML15167A140
Person / Time
Site:	Columbia
Issue date:	05/05/2015
From:	Vincent Gaddy; Operations Branch IV
To:	;
References
	Download: ML15167A140 (307)
	v • d • e

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE MAIN TURBINE CHANGE OF LOAD RATE DETERMINATION (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 LO001783 Rev. No. 0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/21/14 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE SAT Coordinator APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

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

None Special Setup Instructions:

Ensure student has access to a calculator.

Previous revisions used 10% current load going to 70% load with a 20,000 cycles fatigue index.

JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: SOP-MT-START Safety Items: None Task Number: RO-0325 Validation Time: 8 Minutes Alternate Path: No Time Critical: No PPM

Reference:

SOP-MT-START Rev. 25 Location: Any NUREG 1123 Ref: 245000 K5.07 (2.6 / 2.9) Performance Method: Perform Task Standard: The Time to Change Load has been calculated and written in the space provided on the Student JPM Information Card and is within the range allowed.

LO001783 Rev. 0 Page 1 of 4

JPM CHECKLIST INITIAL Columbia is in the process of starting up. The Main Turbine is on the line and is currently 15% loaded.

CONDITIONS:

INITIATING You have been directed to determine the time required to change load from Columbias current load to a load of 95%. Assume a CUE: fatigue index of 20,000 cycles. Inform the CRS of your determination when complete by writing it in the space provided below and handing the card back to the examiner.

Items are Critical Steps Time Step Task Element Performance Standard Evaluators Cue Results 1 SOP-MT-START Attachment 6.1 Correlates 15% load to a First Stage S/U*

Steam Temperature of 115°F (110°F to 120°F).

2 Correlates 95% load to a First Stage S/U*

Steam Temperature of 285°F (275° to 290°).

3 Calculates difference (285°-115°) to be S/U*

170°F (180° to 155°).

4 Plots First Stage Steam Temperature Accept a range of 2.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months S/U*

Change to Time to Change Load-Hours to 1.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months using the 20,000 cycles curve and determines time to change load is 1.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Termination Criteria: Student hands completed JPM Information Card to the examiner.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LO001783 Rev. 0 Page 2 of 4

RESULTS OF JPM:

MAIN TURBINE CHANGE OF LOAD RATE DETERMINATION Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: The Time to Change Load has been calculated and written in the space provided on the Student JPM Information Card and is within the range allowed.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LO001783 Rev. 0 Page 3 of 4

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is in the process of starting up.

The Main Turbine is on the line and is currently 15% loaded.

Cue:

You have been directed to determine the time required to change load from Columbias current load to a load of 95%.

Assume a fatigue index of 20,000 cycles.

Inform the CRS of your determination when complete by writing it in the space provided below and handing this JPM Information card back to the examiner.

The time required to change load from 15% to 95% is:

Page 4 of 4

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE ALTERNATE DETERMINATION OF DRYWELL IDENTIFIED LEAK RATE MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001726 Rev. No. 2 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 07/15/10 REVISED BY Ron Hayden DATE 12/29/14 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE SAT Coordinator APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

ALTERNATE DETERMINATION OF DRYWELL IDENTIFIED LEAK RATE MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

The student should have access to a calculator.

Copy Section 5.7 of SOP-EDR-OPS for the Student to complete. Fill in Steps 5.7.1 through step 5.7.6 with the information from the initial conditions.

JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: N/A Safety Items: N/A Task Number: RO-0892 Validation Time: 15 minutes Alternate Path: No Time Critical: No PPM

Reference:

SOP-EDR-OPS Section 5.7 Rev. 4 Location: Simulator / Classroom NUREG 1123 Ref: 2.1.20 (4.6 / 4.6) Performance Method: Perform Task Standard: Student determines the Calculated Drywell Identified Leak Rate within required acceptance range.

LO001726 Rev. 2 Page 1 of 5

JPM CHECKLIST INITIAL At 0415 EDR-SUMP-R5 sump pump was manually started and EDR-TQ-5 reading was 0551.0. At 0430, the EDR-SUMP-R5 sump CONDITIONS: pump automatically stopped and EDR-TQ-5 reading was 0551.2. At 1630, EDR-SUMP-R5 sump pump was again manually started and had not auto started since 0430. At 1715, the EDR-SUMP-R5 sump pump automatically stopped and EDR-TQ-5 reading was 0552.0. SOP-EDR-OPS section 5.7 steps 5.7.1 through 5.7.6 have been completed.

INITIATING The CRS directs you to determine the Calculated Identified Drywell Leak Rate per SOP-EDR-OPS section 5.7. Complete the CUE: remainder of section 5.7 (Step 5.7.11 is not required to be done) and when finished, hand the completed procedure section to the examiner.

Items are Critical Steps Time Step Task Element Performance Standard Evaluators Cue Results 1 Step 5.7.7 Enters 1715.

S/U*

Calculate the duration of the monitoring period of this section:

a. Completion Time from step 5.7.5 or 5.7.6 2 Step 5.7.7b Enters 0430.

S/U*

Start Time from step 5.7.2 3 Step 5.7.7c Enters 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 45 minutes.

S/U*

Total Time (a. - b.)

4 Step 5.7.8 Enters 0552.0.

S/U*

Calculate EDR-P-5A/B Elapsed Run Time:

a. EDR-TQ-5 Final Reading from Step 5.7.5 or 5.7.6 5 Step 5.7.8b Enters 0551.2.

S/U*

EDR-TQ-5 Initial Reading from Step 5.7.2 LO001726 Rev. 2 Page 2 of 5

Items are Critical Steps Time Step Task Element Performance Standard Evaluators Cue Results 6 Step 5.7.8c Calculates 0.8 as elapsed run time.

S/U*

Elapsed Run Time (a. - b.)

7 Step 5.7.9 Calculates pumped volume as 3172.8.

S/U*

Calculate the total volume of water pumped (Accept out of EDR-SUMP-R5 during the 3172 to monitoring period of this section using the 3173)

Elapsed Run Time calculated in step 5.7.8, and the following formula:

Pumped Volume = ERT x 60 min/hr x 66.1 gallons/min Pumped Volume = ERT x 3966 gallons/hr Pumped Volume = ________ gallons 8 Step 5.7.10 Enters 3172.8 as pumped volume and 765 minutes as Total time (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Determine the Calculated Identified plus .75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months = 12.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months x 60 Drywell Leak Rate using the Pumped min/hr = 765 min).

Volume calculated in step 5.7.9, and the Total Time calculated in step 5.7.7, as S/U*

follows:

Calculates Calculated Identified (accept 4.0 Calculated Identified Drywell Leak Rate = Drywell Leak Rate as 4.147 gpm. to 4.2 Pumped Volume /Total Time gpm)

Calculated Identified Drywell Leak Rate

= gpm LO001726 Rev. 2 Page 3 of 5

RESULTS OF JPM:

Calculation of Identified Drywell Leak Rate Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Student determines the Calculated Drywell Identified Leak Rate within required acceptance range.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LO001726 Rev. 2 Page 4 of 5

STUDENT JPM INFORMATION CARD Initial Conditions:

At 0415 EDR-SUMP-R5 sump pump was manually started and EDR-TQ-5 reading was 0551.0.

At 0430, the EDR-SUMP-R5 sump pump automatically stopped and EDR-TQ-5 reading was 0551.2.

At 1630, EDR-SUMP-R5 sump pump was again manually started and had not auto started since 0430.

At 1715, the EDR-SUMP-R5 sump pump automatically stopped and EDR-TQ-5 reading was 0552.0.

Cue:

The CRS directs you to determine the Calculated Identified Drywell Leak Rate per SOP-EDR-OPS section 5.7.

Complete section 5.7 (Step 5.7.11 is not required to be done) and when finished, hand the completed procedure section to the examiner.

Page 5 of 5

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)

MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LO001644 Rev. No. 2 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/6/08 REVISED BY Ron Hayden DATE 12/29/14 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 MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date 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. If any steps have changed, the JPM should be revised.

Tools/Equipment: N/A Safety Items: N/A Task Number: RO-1181 Validation Time: 20 minutes Alternate Path: No Time Critical: No PPM

Reference:

PPM 1.3.64; SWP-OPS-3; M-526-1; E-503-7 Location: Simulator / Classroom E-503-12; EWD-38E-001; EWD-38E-021 NUREG 1123 Ref: 2.2.13 (4.1 / 4.3) Performance Method: Perform Task Standard: Student correctly identifies the components, component position, and tagging requirements to mechanically and electrically isolate FPC-P-1A per answer sheet.

LO001644 Rev. 2 Page 1 of 8

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

NS:

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

Items are Critical Steps Time Step Task Element Performance Standard Evaluators Cue Results 1 Identifies boundary and valve position References M-526-1 and determines the required to isolate coupling downstream of S/U*

following valves should be closed to FPC-P-1A. isolate FPC-P-1A:

FPC-V-114

FPC-V-115A

FPC-V-116A

FPC-V-181A 2 Determines tagging requirements. Determines the following valves should S/U*

be danger tagged:

FPC-V-114

FPC-V-115A

FPC-V-116A

FPC-V-181A LO001644 Rev. 2 Page 2 of 8

DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-1A Time Step Task Element Performance Standard Evaluators Cue Results 3 Identifies FPC-P-1A Vent and Drain valves. Refers to M-526-1 Detail 3 and S/U*

determines vent and drain valves for FPC-P-1A:

FPC-V-187A (Vent)

FPC-V-150A (Drain) 4 Determines tagging requirements. Determines that FPC-V-187A AND/OR S/U*

FPC-V-150A should be danger tagged opened or No Tagged (due to valves possible removal to perform work on pump).

5 Identifies breaker and position required to References E-503 sheet 12 and S/U*

isolate FPC-P-1A electrically. determines FPC-42-7BB 9B (disconnect 9B on MC-7B-B) should be open/off.

6 Determines tagging requirements. Determines that FPC-42-7BB 9B S/U*

(disconnect 9B on MC-7B-B) should be danger tagged open/off.

7 Identifies breaker and position required to References E-503 sheet 7 and S/U*

isolate FPC-V-181A electrically. determines FPC-42-7BA 1C (disconnect 1C on MC-7B-A) should be open/off.

8 Determines tagging requirements. Determines that FPC-42-7BA 1C S/U*

(disconnect 1C on MC-7B-A) should be danger tagged.

LO001644 Rev. 2 Page 3 of 8

DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-1A Time Step Task Element Performance Standard Evaluators Cue Results 9 Identifies Control Switch requirements for References EWD-38E-001 for FPC-P-S/U*

FPC-P-1A. 1A and determines the pump control switch, FPC-RMS-P1A/1, should be danger or blue tagged in AUTO, or AUTO after STOP or the PTL IR-71 position.

10 Identifies Control Switch requirements for References EWD-38E-021 for FPC-V-S/U*

FPC-V-181A. 181A and determines switch should be danger or blue tagged in the NORM or NORM after CLOSE position.

Termination Criteria: Student hands completed JPM Answer Sheet to the examiner.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LO001644 Rev. 2 Page 4 of 8

DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-1A ANSWER KEY:

COMPONENT REQUIRED TYPE OF TAG (Blue/

POSITION Danger/Caution)

Control Switch for Auto or Auto Danger or Blue FPC-P-1A after Stop or PTL IR-71 Control Switch for Norm or Norm Danger or Blue FPC-V-181A after Close FPC-42-7BB 9B (Disconnect Open/Off Danger 9B for FPC-P-1A on MC-7B-B)

FPC-42-7BA 1C (Disconnect Open/Off Danger for FPC-V-181A)

FPC-V-114 Closed Danger FPC-V-115A Closed Danger FPC-V-116A Closed Danger FPC-V-150A and / or Open Danger or No Tag FPC-V-187A LO001644 Rev. 2 Page 5 of 8

DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-1A RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

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

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LO001644 Rev. 2 Page 6 of 8

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.

Page 7 of 8

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

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

When completed, hand this sheet to the examiner.

Page 8 of 8

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE RADIOLOGICAL POSTINGS DETERMINATION 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 LO001786 Rev. No. 0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/21/14 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE SAT Coordinator APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

RADIOLOGICAL POSTINGS DETERMINATION MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

The student should have access to PPM 11.2.7.1 Area Posting, and PPM 11.2.13.1 Radiation and Contamination Surveys.

JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: N/A Safety Items: N/A Task Number: RO-0557, SRO-0026 Validation Time: 15 minutes Alternate Path: No Time Critical: No PPM

Reference:

11.2.7.1 Rev. 39 Location: Simulator / Classroom NUREG 1123 Ref: 2.3.4 (3.2 / 3.7) Performance Method: Perform Task Standard: The Radiation Areas, High Radiation Areas, Contaminated Areas, and areas requiring no postings have been correctly identified based on the survey maps given.

LO001786 Rev. 0 Page 2 of 8

RADIOLOGICAL POSTINGS DETERMINATION JPM CHECKLIST INITIAL Radiological Surveys have just been completed to update the baseline data in preparation for scheduled work. HP is short on personnel CONDITIONS: and has requested Operations assistance in preparing for the work by reviewing the surveys and determining the required postings in the areas designated.

INITIATING The CRS directs you to review the survey forms and make recommendations with regards to posting of the identified areas by filling CUE: in the posting requirement on the JPM Answer Sheet provided. When completed, hand the completed form to the examiner.

Items are Critical Steps Time Step Task Element Performance Standard Evaluators Cue Results 1

Radiation Survey Map Area 1 Identifies as a Radiation Area (RA) S/U*

2 Radiation Survey Map Area 2 Identifies as a Radiation Area (RA) S/U*

3 Radiation Survey Map Area 3 Identifies as a High Radiation Area (HRA) S/U*

4 Radiation Survey Map Area 4 Identifies as a Radiation Area (RA) S/U*

5 Identifies no radiological posting required (May Radiation Survey Map Area 5 S/U*

list as RCA) 6 Contamination Survey Map Area 1 Identifies as a High Radiation Area (HRA) S/U*

7 Contamination Survey Map Area 2 Identifies as a Contaminated Area (CA) S/U*

8 Contamination Survey Map Area 3 Identifies as a Contaminated Area (CA) S/U*

9 Identifies no contamination postings required Contamination Survey Map Area 4 S/U*

(May List as a RCA) 10 Contamination Survey Map Area 5 Identifies as a Contaminated Area (CA) S/U*

Termination Criteria: Student hands completed section to the examiner.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LO001786 Rev. 0 Page 3 of 8

RADIOLOGICAL POSTINGS DETERMINATION RESULTS OF JPM:

Radiological Posting Determination Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: The Radiation Areas, High Radiation Areas, Contaminated Areas, and areas requiring no postings have been correctly identified based on the survey maps given.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LO001786 Rev. 0 Page 4 of 8

STUDENT JPM INFORMATION CARD Initial Conditions:

Radiological Surveys have just been completed to update the baseline data in preparation for scheduled work.

HP is short on personnel and has requested Operations assistance in preparing for the work by reviewing the surveys and determining the required postings in the areas designated.

CUE:

The CRS directs you to review the survey maps and make recommendations with regards to posting of the identified areas by filling in the posting requirement on the JPM Answer Sheet provided.

When completed, hand the completed form to the examiner.

Page 5 of 8

RWP map pages (for RO admin JPM A4) removed from Operating test due to potential SUNSI concerns

JPM ANSWER SHEET Radiation Area Survey Map 1 Survey Area Radiation Posting Requirement 1

2 3

4 5

Contamination Survey Map 2 Survey Area Contamination Posting Requirement 1

2 3

4 5

Page 8 of 8

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. 6 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 12/30/14 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE SAT Coordinator APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date 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 a *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 by about four control rods. Place a

2 ten rods later and make that the maximum ECP.

Fill out the pull sheet pages. The performed by column is initialed up to control rod 10-47. The verified column, the coupling check column and the full out light columns are initialed to control rod 10-47 by the verifier. Fill in response noted column with a few Ns but mostly Ys.

Have a copy of PPM 3.1.2 Page 1 of 4 and page 2 of 4, startup flowchart, available for reference.

JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: N/A Safety Items: N/A Task Number: RO-0156; SRO-0118 Validation Time: 15 minutes Alternate Path: No Time Critical: No PPM

Reference:

PPM 3.1.2 Rev. 78 Location: Simulator/Classroom NUREG 1123 Ref: 2.1.37 (4.3 / 4.6) Performance Method: Perform Task Standard: It is determined that criticality will occur prior to reaching the minimum ECP and correctly identified the appropriate (RO or SRO) next action to be taken due to being critical outside of the ECP.

LO001587 Rev. 6 Page 1 of 7

DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

JPM CHECKLIST INITIAL A plant startup is in progress. PPM 3.1.2 has been completed as follows: Step L11 has been completed, waiting at step L12; CONDITIONS: Step P1 has not yet been completed; Step S11 is in progress; Step B5 is in progress; Step A19 has been completed; Step Q12 has been completed and Step Q13 is in progress.

CRO1 is pulling control rods and notes the following indications:

Time 0953

Coolant Temp 205°F

Control rod 18-47

Control rod position 18

Neutron level 8,000 CPS and rising

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

INITIATING Using the given information, PPM 3.1.2, and the supplied pull sheets, determine your next action. When you have determined CUE: your next action, write it on the JPM Answer Sheet, along with the basis for the decision and hand it to the examiner.

LO001587 Rev. 6 Page 2 of 7

DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

Items are Critical Steps Time Step Task Element Performance Standard Evaluators Cue Results Criticality will be determined using the criteria on Startup Flow Chart 3.1.2 page 1 Note N6: Criticality usually occurs in the source range between 1x103 and 1x104 cps. For purposes of this procedure, criticality shall be identified by increasing neutron level, a constant steady period and no simultaneous control rod motion.

If the SRO Position being evaluated:

1 The information given identifies Determine status of Reactor based on 8000 cps and rising (which is S/U*

information given.

between the 1x103 and 1x104 cps) and a constant steady period with no rod motion - these are indications of a critical reactor.

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

2 Indicates that the Reactor Operator Determines actions based on early would be directed to stop control rod S/U*

criticality.

withdrawal direct the CRO to drive control rods in the reverse order until all control rods are fully inserted.

3 Indicates that basis for the above Determines basis for actions.

action is due to reactor being critical S/U*

prior to the indicated minimum ECP (early criticality).

LO001587 Rev. 6 Page 3 of 7

DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

Time Step Task Element Performance Standard Evaluators Cue Results If the RO Position being evaluated:

4 The information given identifies Determine status of Reactor based on 8000 cps and rising (which is S/U*

information given.

between the 1x103 and 1x104 cps) and a constant steady period with no rod motion - these are indications of a critical reactor.

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

5 Indicates that control rod withdrawal Determines actions based on early would be stopped the CRS would be S/U*

criticality.

notified.

6 Indicates that basis for the above Determines basis for actions.

action is due to reactor being critical S/U*

prior to the indicated minimum ECP (early criticality).

Termination Criteria: Student hands the JPM Answer Sheet to the examiner.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LO001587 Rev. 6 Page 4 of 7

RESULTS OF JPM:

DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: It is determined that criticality will occur prior to reaching the minimum ECP and correctly identified the appropriate (RO or SRO) next action to be taken due to being critical outside of the ECP.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LO001587 Rev. 6 Page 5 of 7

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, waiting at step L12; Step P1 has not yet been completed; Step S11 is in progress; Step B5 is in progress; Step A19 has been completed; Step Q12 has been completed and Step Q13 is in progress.

The following indications are observed:

Time 0953

Coolant Temp 205° F

Control rod 18-47

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.

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 JPM Answer Sheet along with the basis for the decision and hand it to the examiner.

Page 6 of 7

JPM ANSWER SHEET NEXT ACTION TO BE TAKEN:

BASIS FOR ACTION:

Page 7 of 7

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE DETERMINE IF VOLUNTARY ENTRY INTO AIA IS ALLOWABLE 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 LO001784 Rev. No. 0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/21/14 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

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

N/A Special Setup Instructions:

Student should have access to SOPs and Volume 3 procedures.

JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: None Safety Items: None Task Number: SRO-0122 Validation Time: 10 Minutes Alternate Path: No Time Critical: N/A PPM

Reference:

PPM 3.2.1 Rev. 78 Location: Classroom NUREG 1123 Ref: 2.1.25 (3.9 / 4.2) Performance Method: Perform Task Standard: The JPM Answer Sheet is initialed for would direct entry into AIA.

LO001784 Rev. 0 Page 1 of 5

JPM CHECKLIST INITIAL Columbia Generating Station is shutting down per PPM 3.2.1. Reactor Power is 30%. Per the Reactivity Control Plan and CRS CONDITIONS: direction, Rod Line is 50%. RFW-TI-5 on H13-P840 is reading 326°F. Core Flow is 42 Mlbm/Hr. A planned entry into the Area Of Increased Awareness is scheduled for your shift.

INITIATING On the page provided indicate if you would or would not direct the planned AIA entry. Fill in all required information based on CUE: your answer on the JPM Answer Sheet and hand the completed sheet to the examiner.

Items are Critical Steps Time Step Task Element Performance Standard Evaluators Cue Results 1 PPM 3.2.1 Step 5.1.28 Refers to PPM 3.2.1 Attachment 7.3, S/U*

plots the parameters given, and Prior to a planned entry into the AIA recognizes that the plant is currently (i.e. Single Loop Operation), then in the Normal Operating region.

verify Reactor Feedwater temperature, as indicated on RFW-TI-5 (H13-P840), is within the Normal Operating Region Attachment 7.3.

2 Determines if would or would not Initials block for would direct S/U*

direct entry into AIA. planned entry into AIA.

Termination Criteria: Student hands the JPM Answer Sheet to the examiner.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LO001784 Rev. 0 Page 2 of 5

RESULTS OF JPM:

PLANNED ENTRY INTO AIA Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: The JPM Answer Sheet is initialed for would direct entry into AIA.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LO001784 Rev. 0 Page 3 of 5

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia Generating Station is shutting down per PPM 3.2.1.

Reactor Power is 30%.

Per the Reactivity Control Plan and CRS direction, Rod Line is 50%.

RFW-TI-5 on H13-P840 is reading 326°F.

Core Flow is 42 Mlbm/Hr.

A planned entry into the Area Of Increased Awareness is scheduled for your shift.

Cue:

On the page provided indicate if you would or would not direct the planned AIA entry.

Fill in all required information based on your answer on the JPM Answer Sheet and hand the completed sheet to the examiner.

Page 4 of 5

JPM ANSWER SHEET YES - I would direct the planned entry into the Area of Increased Awareness.

Initials NO - I would not direct the planned entry into the Area Of Increased Awareness for the following reason:

Initials Page 5 of 5

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE DETERMINATION OF OPERATING POINT AND REQUIRED ACTIONS FOLLOWING FW HEATER TRIP PER ABN-POWER (Admin)

LESSON LENGTH .5 HRS INSTRUCTIONAL MATERIALS INCLUDED LESSON PLAN PQD CODE Rev. No.

SIMULATOR GUIDE PQD CODE Rev. No.

JPM PQD CODE LO001650 Rev. No. 2 EXAM PQD CODE Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 11/18/08 REVISED BY Ron Hayden DATE 12/30/14 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE SAT Coordinator APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

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

N/A Special Setup Instructions:

A copy of ABN-POWER must be available.

JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: None Safety Items: None Task Number: RO-0557; SRO-0318 Validation Time: 10 Minutes Alternate Path: No Time Critical: No PPM

Reference:

ABN-POWER Rev. 13 Location: Any NUREG 1123 Ref: 2.1.7 (4.4 / 4.7) Performance Method: Perform Task Standard: Determination is made and choices are circled for operation in the FWH OOS region of Attachment 7.1 of ABN-POWER and insertion of control rods to below the 100% rod line.

LO001650 Rev. 2 Page 2 of 5

JPM CHECKLIST INITIAL The plant was operating at 92% power when Feedwater Heater 6A tripped. Reactor power is currently 94% and trending up slow.

CONDITIONS: Feedwater temperature is currently 394°F and trending down slow.

INITIATING Based on the above information answer the following questions concerning current plant status. When you have answered the two CUE: question hand the Student JPM Information Card to the examiner.

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 1 Determines procedure to be Determines entry into ABN-POWER is required and S/U*

referenced. refers to section 4.3 and Attachment 7.1.

2 Plots Core Thermal Power versus Plots point for 94% Core Thermal Power and 394°F.

S/U*

FW Temperature (Degrees F).

3 Determines operating region. Determines and indicates the plant is operating in the S/U*

FWH OOS Region (Choice c).

4 Determines actions required for Determines and indicates that insertion of control S/U*

continued operation. rods to maintain below the 100% rod line is required (Choice c).

Termination Criteria: Hands the Student JPM Information Card to examiner.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LO001650 Rev. 2 Page 3 of 5

RESULTS OF JPM DETERMINATION OF OPERATING POINT AND REQUIRED ACTIONS FOLLOWING FW HEATER TRIP PER ABN-POWER Examinee (Print): _________________________________________________________________

Evaluator (Print): _________________________________________________________________

Task Standard: Determination is made and choices are circled for operation in the FWH OOS region of Attachment 7.1 of ABN-POWER and insertion of control rods to below the 100% rod line.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LO001650 Rev. 2 Page 4 of 5

STUDENT JPM INFORMATION CARD Initial Conditions:

The plant was operating at 92% power when Feedwater Heater 6A tripped Reactor power is currently 94% and trending up slow Feedwater temperature is currently 394°F and trending down slow Cue:

Based on the above information answer the following two questions concerning current plant status by circling your answer.

When you have answered the questions, hand the Student JPM Information Card to the examiner.

1. The plant is operating in the:

a. Normal Operating Region

b. Operation Prohibited Region

c. FWH OOS Region

d. Unrestricted Region

2. Continued operation action is:

a. None required

b. Reduce power to LT 25% RTP within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

c. Insert Control Rods to maintain below the 100% rod line

d. Refer CRS to LCS 1.1.6

e. Reduce power to the original power level of 92%

Page 5 of 5

INSTRUCTIONAL COVER SHEET PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY LESSON TITLE RATE AND DETERMINE ACTIONS (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 LO001590 Rev. No. 4 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/21/06 REVISED BY Ron Hayden DATE 12/30/14 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

Candidate needs a calculator and access to ABN-OG.

JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: N/A Safety Items: N/A Task Number: SRO-0658 Validation Time: 10 minutes Alternate Path: No Time Critical: No PPM

Reference:

ABN-OG Rev. 3 Location: Classroom NUREG 1123 Ref: 271000A2.04 (3.7 / 4.1) Performance Method: Perform Task Standard: Candidate fills out the JPM Answer Sheet and has determined that a power reduction per PPM 3.2.4 is required to maintain Main Condenser Gross gamma activity LT 332 mCi/sec.

LO001590 Rev. 4 Page 1 of 5

ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS JPM CHECKLIST INITIAL Columbia is operating at full power. Various alarms are locked in due to suspected fuel pin damage. Offgas system parameters are CONDITIONS: as follows: OFFGAS POST TREATMENT RADIATION MONITOR, OG-RIS-601A, is in alarm. OFFGAS SYSTEM EXHAUST FLOW, OG-FR-620, is reading 43 SCFM. SJAE CONDENSER OUTLET RADIATION MONITOR, OG-RR-604, is reading 7721 mr/hr.

INITIATING Based on the above information, per ABN-OG, determine what action, if any, should be taken. Fill in the result of your conclusion CUE: on the attachment provided.

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 1 ABN-OG Step 4.1.4 Main Condenser Gross gamma activity = 7721 mr/hr Estimate Main Condenser air times 43 SCFM divided by 1000 OR S/U*

ejector gross gamma activity rate Main Condenser Gross gamma activity = 332.03 using the following formula: mCi/sec (GT 332mCi/sec).

2 Based on a Main Condenser Gross gamma activity

[OG Pretreatment (mRem/hr) (OG- S/U*

reading of 332.03 mCi/sec, candidate determines that RR-604)] X [OG System flow a power reduction per PPM 3.2.4 to maintain Main (scfm) (OG-FR-620)] divided by Condenser Gross gamma activity LT 332 mCi/sec is 1000 = Main Condenser Gross required.

gamma activity (mCi/sec).

Termination Criteria: Hands the JPM Answer Sheet to the examiner.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LO001590 Rev. 4 Page 2 of 5

RESULTS OF JPM:

ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Candidate fills out the JPM Answer Sheet and has determined that a power reduction per PPM 3.2.4 is required to maintain Main Condenser Gross gamma activity LT 332 mCi/sec.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LO001590 Rev. 4 Page 3 of 5

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is operating at full power.

Various alarms are locked in due to suspected fuel pin damage.

Offgas system parameters are as follows:

OFFGAS POST TREATMENT RADIATION MONITOR, OG-RIS-601A, is in alarm.

OFFGAS SYSTEM EXHAUST FLOW, OG-FR-620, is reading 43 SCFM.

SJAE CONDENSER OUTLET RADIATION MONITOR, OG-RR-604, is reading 7721 mr/hr.

Cue:

Based on the above, per ABN-OG, determine what action, if any, should be taken.

Fill in the result of your conclusion on the JPM Answer Sheet. Hand the JPM Answer Sheet to your examiner when complete.

Page 4 of 5

JPM ANSWER SHEET INITIAL HERE IF NO ACTIONS ARE REQUIRED:

INITIAL HERE IF ACTIONS ARE REQUIRED:

ACTION(S) IF REQUIRED AND REASON FOR ACTION:

Page 5 of 5

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE CLASSIFY AN EVENT AND COMPLETE A CNF (GE) (SRO) (TC)

LESSON LENGTH .5 HRS INSTRUCTIONAL MATERIALS INCLUDED LESSON PLAN PQD CODE Rev. No.

SIMULATOR GUIDE PQD CODE Rev. No.

JPM PQD CODE LO001811 Rev. No. 0 EXAM PQD CODE Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 2/10/15 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE SAT Coordinator APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

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

N/A Special Setup Instructions:

Run a QEDPS based upon initial conditions. Print (screen print) the QEDPS form and print out the corresponding map showing the release. Give these to the student after reading the initial conditions and cue to him/her. Ensure CDE Thyroid is GT 5000 mrem and all other readings are LT GE levels.

JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: None Safety Items: None Task Number: SRO- 0315, 0529, 0638 Validation Time: 18 Minutes Alternate Path: No Time Critical: Yes 30 Minutes (15 to declare and 15 to initiate CNF)

PPM

Reference:

PPM 13.8.1 Rev. 34 Location: Simulator NUREG 1123 Ref: 2.4.41 (2.9/4.6) Performance Method: Perform Task Standard: Completes Classification Notification Form with required information within the time constraints.

LO001811 Rev. 0 Page 2 of 7

JPM CHECKLIST INITIAL The plant has experienced an event that has resulted in the following conditions: The plant scrammed 55 minutes ago. Wind Speed CONDITIONS: is 4 mph. Wind Direction is from 290°. A release from the Turbine Building started thirty minutes ago. TB HVAC flow rate of 360,000 cfm. The Turbine Building Composite Signal (TEA) is reading 2.50E-02 uCi/cc. The release is expected to last 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

Stability class is E. It is not raining outside. A QEDPS has been performed.

INITIATING The Shift Manager directs you to complete a Classification Notification Form based only on the results of the completed QEDPS.

CUE: This is the initial classification. Present the completed form to the Shift Manager for signature. This is a time critical JPM and your time starts now.

Items are Critical Steps Time Step Task Element Performance Standard Evaluators Cue Results RECORD START TIME: __________

1 Classifies the Event Refers to PPM 13.1.1 Attachment 7.2 S/U*

and classifies event as an General Emergency based upon Table 4 Thyroid CDE at 1.2 miles of GT 5000 mrem.

NOTE: THIS STOPS THE FIRST 15 MINUTE CLOCK AND STARTS THE NEXT 15 MINUTE CLOCK 2 Completes Classification Fills in following information on the S/U Notification Form. CNF:

3 Block 1 Checks b. (Drill) S/U 4 Block 2 Enters a 1 S/U 5 Block 3 Enters a name S/U 6 Block 4 Checks a. (Initial Classification) and S/U*

enters todays date and time LO001811 Rev. 0 Page 3 of 7

Items are Critical Steps Time Step Task Element Performance Standard Evaluators Cue Results 7 Block 5 Checks d. (General Emergency) S/U*

8 Block 6 Checks Evacuate 0-2 miles S/U*

9 Block 6a Checks Evacuate 2-10 miles Section 2 S/U*

10 Block 6a Checks Shelter 2-10 miles Sections 1, S/U*

3, and 4 11 Block 6a Checks Radiological for Basis for Pars S/U 12 Block 6b Checks No for Security Event S/U 13 Block 7 Enters 4 for Wind Speed S/U*

14 Block 7 Enters 290 for degrees S/U*

15 Block 7 Checks No for Precipitation S/U 16 Block 7 Enters E as Stability Classification S/U 17 Block 8 Checks Release S/U*

18 Block 9 Checks Airborne S/U 19 Block 10 Enters a time for Estimated Start of S/U Release 20 Block 11 Checks Yes S/U 21 Block 12 Enters 5.1.G.2 for EAL# S/U*

LO001811 Rev. 0 Page 4 of 7

Items are Critical Steps Time Step Task Element Performance Standard Evaluators Cue Results 22 Block 12 Enters a brief description for Description S/U*

of Incident such as CDE Thyroid at GT 5000 mrem 23 Block 13 Checks a., b., or c. S/U RECORD STOP TIME: __________

Termination Criteria: Student hands in the completed CNF.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LO001811 Rev. 0 Page 5 of 7

RESULTS OF JPM CLASSIFY AN EVENT AND COMPLETE A CLASSIFICATION NOTIFICATION FORM FOR A GE Examinee (Print): _________________________________________________________________

Evaluator (Print): _________________________________________________________________

Task Standard: Completes Classification Notification Form with required information within the time constraints.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LO001811 Rev. 0 Page 6 of 7

STUDENT JPM INFORMATION CARD Initial Conditions:

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

The plant scrammed 55 minutes ago.

Wind Speed is 4 mph.

Wind Direction is from 290°.

A release from the Turbine Building started thirty minutes ago.

TB HVAC flow rate of 360,000 cfm.

The Turbine Building Composite Signal (TEA) is reading 2.50E-02 uCi/cc.

The release is expected to last 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

Stability class is E.

It is not raining outside.

A QEDPS has been performed.

Initiating Cue:

The Shift Manager directs you to complete a Classification Notification Form based only on the results of the completed QEDPS. This is the initial classification.

Present the completed form to the Shift Manager for signature.

THIS IS A TIME CRITICAL JPM and your time starts now.

Page 7 of 7

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE LOWER RPV PRESSURE USING DEH (CR/SIM) (Alt Path)

LESSON LENGTH .5 HRS INSTRUCTIONAL MATERIALS INCLUDED LESSON PLAN PQD CODE Rev. No.

SIMULATOR GUIDE PQD CODE Rev. No.

JPM PQD CODE LO001780 Rev. No. 0 EXAM PQD CODE Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/21/14 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

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

Reset to IC with reactor shutdown and pressure being controlled by bypass valves.

Special Setup Instructions:

Insert MAL-DEH017.

Set Pressure Rate to any value other than 50 psig.

JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: None Safety Items: None Task Number: RO-0348 Validation Time: 7 Minutes Alternate Path: Yes Time Critical: No PPM

Reference:

SOP-DEH-QC Rev. 5 Location: Simulator NUREG 1123 Ref: 241000 A4.02 (4.1 / 4.1) Performance Method: Perform Task Standard: RPV pressure has been lowered at a rate LE 50 psig per minute by taking manual control of the Bypass Valves.

LO001780 Rev.0 Page 2 of 8

JPM CHECKLIST INITIAL Columbia was operating at full power when RFW-P-1A tripped followed by RFW-P-1B tripping five minutes later. CRO1 has lined CONDITIONS: up on the startup flow control valves.

INITIATING The CRS directs you to lower RPV pressure to 550 psig at the rate of 50 psig per minute to facilitate feeding the RPV with the CUE: Condensate Booster pumps per SOP-DEH-QC. Inform the CRS when RPV pressure is 550 psig.

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step NOTE: If the plant is operating in Mode 1 and is GT 25% power, then the DEH set point should be 960 psi. If a reactor pressure change is desired refer to ABN-PRESSURE.

1 Step 2.1.1 Selects a display screen.

S/U Initiate Pressure setpoint change as follows (Turbine Start Up; Reactor Startup Display) or (Main Display):

2 a. Select Pressure Target. Selects Pressure Target. S/U*

3 b. Enter desired pressure. Enters 5,5,0 psig. S/U*

4 c. Select OK. Selects OK. S/U*

5 d. If a change in pressure rate is Observes Pressure Rate is not 50 S/U desired, then perform the psig and performs step.

following:

6 1) Select Pressure Rate. Selects Pressure Rate. S/U*

7 2) Enter desired Pressure rate. Enters 5,0. S/U*

8 3) Select OK. Selects OK. S/U*

9 e. Select GO. Selects GO. S/U*

10 f. Select YES. Selects YES. S/U*

LO001780 Rev.0 Page 3 of 8

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step ALTERNATE 11 g. Verify Press Demand and Throttle Observes no change in Pressure CRS - Take manual control of the PATH STEP S/U*

Press change at the Pressure Rate. Demand or Bypass Valve position. Bypass Valves and lower RPV pressure to 550 psig at 50 psig per Observes green Hold light is still minute.

illuminated.

Informs the CRS.

EVALUATOR: If SOP-DEH-OPS is referenced, when section for manual bypass valve operation is found, cue to use the DEH Quick Card.

12 SOP-DEH-QC Step 2.2 Performs this section.

S/U Manual Bypass Valve Operation.

NOTE: In Manual, raising BPV demand will open the BPVs and cause Reactor pressure to lower. The BPVs will not respond to pressure changes in Manual.

13 Step 2.2.1 Performs this step.

S/U Operate the Bypass Valves Manually as follows (Turbine Start-up, Reactor Start screen):

NOTE: In manual, raising BPV demand will open the BPVs and cause Reactor pressure to lower. The BPVs will not respond to pressure changes in Manual.

14 a. Select BPV MANUAL. Selects BPV Manual. S/U*

15 b. Select YES. Selects Yes. S/U*

16 c. If rapid Bypass Valve movement is Verbalizes step (it is anticipated that desired, then select FAST ACTION. S/U this step will not be performed but it is OK if it is performed).

17 d. If opening Bypass Valves, then Selects BPV Raise.

S/U*

select BPV Raise.

18 e. If closing Bypass Valves, then Does not perform this step.

S/U select BPV Lower.

LO001780 Rev.0 Page 4 of 8

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step NOTE: The JOG button illuminates green when the command is accepted, and extinguishes when the command is complete.

EVALUATOR: Either step f or steps g, h, and i are performed to lower RPV pressure. Whichever is performed makes the other steps not critical steps. It is anticipated that step f will be used to reduce RPV pressure.

19 f. If incremental Bypass Valve Depresses the JOG button to achieve movement is desired, then depress JOG S/U*

approximately a 50 psig pressure button once for each 1% of valve drop per minute.

demand change desired.

If JPM step 19 was performed, skip JPM steps 20, 21, and 22 (which are now NOT critical step).

20 g. Select GO for full range motion to Selects Go.

100% demand or 0% demand.

S/U*

21 h. Select YES. Selects Yes and observes bypass S/U*

valves starting to open.

22 i. If desired to stop BPV motion, then Selects Hold to stop bypass valve depress hold. S/U*

motion.

EVALUATOR: No matter which steps were performed to lower pressure - When you determine that RPV pressure is being lowered in a controlled manner at less than or equal to 50 psig per minute, inform the operator that at the next RPV pressure 50 psig increment to close the Bypass Valves and stop the pressure reduction.

23 Stops RPV pressure reduction and Selects BPV Lower. S/U*

closes Bypass Valves.

LO001780 Rev.0 Page 5 of 8

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step EVALUATOR: Student may perform JPM step 24 or steps 25, 26, and 27 to close the Bypass Valves. Whichever is performed makes the other NOT critical.

24 Selects the JOG button until the S/U*

BPVs are closed.

25 Selects Fast Action. S/U*

26 Selects Go. S/U*

27 Selects Yes. S/U*

Termination Criteria: When the BPVs are closed, inform the Student that the termination point of the JPM has been reached.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LO001780 Rev.0 Page 6 of 8

RESULTS OF JPM LOWER RPV PRESSURE USING BPVs IN MANUAL Examinee (Print): _________________________________________________________________

Evaluator (Print): _________________________________________________________________

Task Standard: RPV pressure has been lowered at a rate LE 50 psig per minute by taking manual control of the Bypass Valves.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LO001780 Rev.0 Page 7 of 8

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia was operating at full power when RFW-P-1A tripped followed by RFW-P-1B tripping five minutes later.

CRO1 has lined up on the startup flow control valves.

Initiating Cue:

The CRS directs you to lower RPV pressure to 550 psig at the rate of 50 psig per minute to facilitate feeding the RPV with the Condensate Booster pumps per SOP-DEH-QC.

Inform the CRS when RPV pressure is 550 psig.

Page 8 of 8

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE RESTORE POWER TO RPS B (ALTERNATE POWER) (CR/SIM) (Alt Path)

LESSON LENGTH .5 HRS INSTRUCTIONAL MATERIALS INCLUDED LESSON PLAN PQD CODE Rev. No.

SIMULATOR GUIDE PQD CODE Rev. No.

JPM PQD CODE LO001779 Rev. No. 0 EXAM PQD CODE Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/21/14 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

RESTORE RPS B FROM ALTERNATE POWER SOURCE MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Any IC with a normal electrical lineup - all load centers energized.

Ensure AR-EX-1B is in service.

Special Setup Instructions:

Open RPS EPA BKR 3B, acknowledge all annunciators, and allow plant to stabilize.

JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: None Safety Items: None Task Number: RO-0248 Validation Time: 15 minutes Alternate Path: Yes Time Critical: No PPM

Reference:

ABN-RPS Rev. 10 Location: Simulator NUREG 1123 Ref: 212000 A4.14 (3.8 / 3.8) Performance Method: Perform Task Standard: RPS B is powered from the alternate power supply, the subsequent actions thru step 4.8 for ABN-RPS have been completed, and FDR-V-4 was recognized to not have opened.

LO001779 Rev. 0 Page 2 of 10

RESTORE POWER TO RPS B FROM ALTERNATE SOURCE JPM CHECKLIST INITIAL A loss of RPS B has just occurred. All maintenance and surveillance testing has been stopped. All automatic actions have been CONDITIONS: verified to have occurred.

INITIATING The CRS directs you to perform the subsequent actions of ABN-RPS. Inform the CRS when RPS B has been repowered and step CUE: 4.9 is ready to be performed.

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step The candidate is given a copy of ABN-RPS.

1 Step 4.1 Observes the Green light for RWCU-S/U*

V-104 on and Red light off.

If power is available to RWCU-V-104 (Cleanup System Bypass), then Turns the control switch clockwise to throttle open RWCU-V-104. open until the Red light comes on, then releases the control switch (both lights should be on to satisfy the critical step).

2 Step 4.2 Observes AR-EX-1A running and S/U does not perform this step.

If the alternate Gland Exhauster (AR-EX-1A(B) is required, then start the alternate Gland Exhauster, and place the tripped Gland Exhauster in off.

3 Step 4.3 Recognizes current plant S/U configuration does not require If the alternate Mechanical Vacuum Mechanical Vacuum Pump operation Pump (AR-P-1A(B)) is required, and does not perform this step.

then start the alternate Mechanical Vacuum Pump.

LO001779 Rev. 0 Page 3 of 10

RESTORE POWER TO RPS B FROM ALTERNATE SOURCE

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 4 Step 4.4 Recognizes this step has been S/U completed per the Initial Conditions Ensure automatic actions have and does not perform.

occurred.

ALTERNATE 5 Step 4.5 Recognizes that RPS MG set The B RPS MG set is not running PATH STEP S/U*

condition is not known and contacts and the motor is hot to the touch.

Perform the following to reenergize an Equipment Operator and requests RPS:

status of RPS B MG set.

6 Step 4.5.1 Determines that the condition of RPS S/U MG Set B is not operable and does If the condition of the RPS MG set is not perform this step.

known to be operable, then restart the RPS MG set, and repower the bus per SOP-RPS-START and SOP-RPS-START.

7 Step 4.5.2 Determines this step is to be S/U performed.

If the condition of the RPS MG set is uncertain then repower RPS A or B Observes the white light is on for from H13-P610 as follows: Alternate RPS Feed at H13-P610.

a. Verify power available from the Reactor Protection System Alternate Power Supply, MC-6B, by observing the Alternate Feed white light illuminated.

CAUTION : The MG Set Transfer switch is break before make and positioning it to the wrong supply will result in a full REACTOR SCRAM.

LO001779 Rev. 0 Page 4 of 10

RESTORE POWER TO RPS B FROM ALTERNATE SOURCE

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 8 Step 4.5.2b Recognizes RPS A is powered and S/U does not perform this step.

If repowering RPS A, then place the RPS power source selector switch in ALT A position.

9 Step 4.5.2c Rotates the RPS Power Source Select switch on H13-P610 S/U*

If repowering RPS B, then place the clockwise to the ALT B position.

RPS power source selector switch in ALT B position.

10 Step 4.6 Recognizes RPS A is powered and S/U does not perform this step.

When RPS power has been restored and stabilized, then perform the following:

Step 4.6.1 If restoring RPS A then perform the following:

11 Step 4.6.2 Performs this step.

S/U If restoring RPS B, then perform the following:

12 Step 4.6.2a Depresses the two Reactor Scram S/U*

Logic A1/B1 and the A2/B2 reset Reset the Half Scram at H13-P603.

P/Bs on H13-P603.

(Observes white RPS Scram group solenoid lights on and amber Backup Scram System lights off).

LO001779 Rev. 0 Page 5 of 10

RESTORE POWER TO RPS B FROM ALTERNATE SOURCE

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 13 Step 4.6.2b At P633, recognizes the reset is not S/U Reset Main Steam Line Rad Monitor available on either Main Steam Line alarms at H13-P633: Rad Monitor and as such does not o MS-RIS-610B require resetting.

o MS-RIS-610D 14 Step 4.6.2c Depresses the reset pushbuttons for S/U*

Isolation Logic A and B and C&D on Depress the following pushbuttons at H13-P601.

H13-P601:

o Isolation logic A & B reset pushbuttons o Isolation logic C & D reset pushbuttons 15 Step 4.6.2d Depresses the black RC-1 reset S/U*

pushbutton WMA-RMS-FAZ/3AXY.

Reset RC-1 by depressing WMA-RMS-FAZ/3AXY pushbutton.

16 Step 4.6.2e Depresses the black RC-2 reset S/U*

pushbutton WMA-RMS-FAZ/3BXY.

Reset RC-2 by depressing WMA-RMS-FAZ/3BXY pushbutton.

17 Step 4.6.2f Recognizes that Shutdown Cooling S/U If RHR SDC was in service, then was not in service and does not refer to ABN-RHR-SDC-LOSS. perform ABN-RHR-SDC-LOSS.

18 Step 4.6.2g At P601, turns the control switch for S/U*

RRC-V-19 clockwise to open.

Open RRC-V-19 Observes the Red light on and the Green light off.

LO001779 Rev. 0 Page 6 of 10

RESTORE POWER TO RPS B FROM ALTERNATE SOURCE

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 19 Step 4.6.2h At P601, turns the control switch for S/U*

RRC-V-20 clockwise to open.

Open RRC-V-20 Observes the Red light on and the Green light off.

20 Step 4.6.2i At P601, turns the control switch for S/U*

EDR-V-19 clockwise to open.

Open EDR-V-19 Observes the Red light on and the Green light off.

21 Step 4.6.2j At P601, turns the control switch for S/U*

EDR-V-20 clockwise to open.

Open EDR-V-20 Observes the Red light on and the Green light off.

(Acknowledges the LEAK DET DRYWELL EQUIP DRAIN FLOW HIGH annunciator).

22 Step 4.6.2k At P601, turns the control switch for S/U*

TIP-V-15 clockwise.

Open TIP-V-15 Observes the Red light on and the Green light off.

23 Step 4.6.2l At backpanel P607, depresses the S/U*

TIP Ball Valve Isolation Reset Depress the TIP Ball Vlv Isolation pushbutton.

Reset.

24 Step 4.6.2m Verbalizes step. When step is verbalized inform the S/U candidate that another operator is Return RWCU to service per SOP-placing RWCU in service.

RWCU-START.

LO001779 Rev. 0 Page 7 of 10

RESTORE POWER TO RPS B FROM ALTERNATE SOURCE

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 25 Step 4.7 Turns the control switch for FDR-V-S/U*

3 clockwise to open and observes the If FDR-V-3 and FDR-V-4 have been Red light on and Green light off.

isolated for LT 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , then open the following (H13-P601):

o FDR-V-3 o FDR-V-4 ALTERNATE 26 Rotates the control switch for FDR- Acknowledge the report and inform PATH STEP S/U*

V-4 clockwise to open and the candidate that the termination recognizes the Green light remains point of the JPM has been reached.

on and the Red light remains off.

Informs the CRS that FDR-V-4 will If candidate does not recognize not open.

failure of FDR-V-4 to open, continue with the remainder of ABN-RPS.

27 Step 4.8 Recognizes FDR-V-3 and FDR-V-4 S/U were just opened in last step and If FDR-V-3 and FDR-V-4 have been does not perform this step.

isolated for GT 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , then open FDR-V-3 and FDR-V-4 as follows:

28 Step 4.9 Informs the CRS to refer to TS THIS STEP IS NOT REQUIRED 3.3.1.1 for RPS and LCS 1.4.1 for TO BE PERFORMED BUT IS Refer to TS 3.3.1.1 for RPS and LCS coolant chemistry control. INCLUDED FOR EVALUATORS 1.4.1 for coolant chemistry control.

REFERENCE ONLY Termination Criteria: Candidate informs CRS that ABN-RPS has been completed up to step 4.9.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LO001779 Rev. 0 Page 8 of 10

RESULTS OF JPM RESTORE RPS B FROM ALTERNATE POWER SOURCE Examinee (Print): _________________________________________________________________

Evaluator (Print): _________________________________________________________________

Task Standard: RPS B is powered from the alternate power supply, the subsequent actions thru step 4.8 for ABN-RPS have been completed, and FDR-V-4 was recognized to not have opened.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LO001779 Rev. 0 Page 9 of 10

STUDENT JPM INFORMATION CARD Initial Conditions:

A loss of RPS B just occurred.

All maintenance and surveillance testing has been stopped.

All automatic actions have been verified to have occurred.

Initiating Cue:

The CRS directs you to perform the subsequent actions of ABN-RPS.

Inform the CRS when RPS B has been repowered and step 4.9 is ready to be performed.

Page 10 of 10

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE RELATCH THE MAIN TURBINE (CR/SIM)

LESSON LENGTH .5 HRS INSTRUCTIONAL MATERIALS INCLUDED LESSON PLAN PQD CODE Rev. No.

SIMULATOR GUIDE PQD CODE Rev. No.

JPM PQD CODE LO001782 Rev. No. 0 EXAM PQD CODE Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/21/14 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

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

Any IC where the MT is tripped and coasting down.

Special Setup Instructions:

None JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: N/A Safety Items: N/A Task Number: RO-0321 Validation Time: 15 min Alternate Path: No Time Critical: No PPM

Reference:

SOP-MT-START Rev. 25 Location: Simulator NUREG 1123 Ref: 245000A4.06 (2.7 / 2.6) Performance Method: Perform Task Standard: The Main Turbine has been relatched, the TV/GV Transfer has been performed and Main Turbine speed is 1800 rpm.

LO001782 Rev. 0 Page 2 of 13

JPM CHECKLIST INITIAL Columbia is starting up and just completed a special test on the Main Turbine.

CONDITIONS:

INITIATING The CRS directs you to relatch the Main Turbine per SOP-MT-START section 5.4. Steps 5.4.1 and 5.4.2 have been verified. Use a CUE: rate of change of 80 rpm throughout the evolution. No Main Turbine holds are required throughout the evolution. Notify the CRS when Main Turbine speed has reached 1800 rpm.

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step NOTE: This section relatches the Main Turbine at less than 1750 RPM following testing or trip off line. Due to the limited time to perform this section familiarization is recommended prior to performance.

1 Step 5.4.1 Recognizes given in initial S/U conditions as being completed.

Verify Generator Power Direction Relay (RLY-67G) is reset (H13-P842).

2 Step 5.4.2 Recognizes given in initial S/U conditions as being completed.

Verify the Generator Lockout Relay (RLY-86G) is reset (H13-P842)

CAUTION To prevent coil damage, Do Not attempt to force reset by holding 86 relays in the Reset position for an excessive period of time.

NOTE: Relays should be reset quickly to avoid coil damage. Lockout reset is accomplished by resetting the master relay first (86XU) and then the slave relay (86X1U).

3 Step 5.4.3 Depresses the black reset pushbutton.

S/U*

Reset the 86XU (86X1U) and Turns the 86XU and 86X1U relay 86XUOA (86X1UOA) as follows: control switches clockwise until they latch in place.

a. Depress and hold the respective reset pushbutton while resetting the Unit Lockout Relays 86XU and 86X1U (primary).

LO001782 Rev. 0 Page 3 of 13

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 4 Step 5.4.3b Releases the black reset pushbutton.

S/U*

When the relays have been reset, then release the reset pushbutton.

5 Step 5.4.3c Depresses and holds the reset S/U*

Depress and hold the Reset pushbutton.

pushbutton while resetting the Unit Turns the 86XUOA and 86X1UOA Overall (Secondary) Lockout Relays relays handles clockwise to the reset 86XUOA and 86X1UOA. position.

6 Step 5.4.3d Releases the reset pushbutton.

S/U*

When the relays have been reset, then release the reset pushbutton.

7 Step 5.4.4 On the First Out display, touches S/U Reset First Out.

Verify all Main Turbine Trips reset as follows (Menu, First Out):

a. Select RESET FIRST OUT.

8 Step 5.4.4b Touches yes.

S/U Select yes.

9 Step 5.4.4c Observes all MT trip alarms are S/U clear.

Verify all Main Turbine Trips are clear.

CAUTION Relatching and/or continued operation at or near critical or resonant speeds is not permitted.

CAUTION If Valve Position Limit indicator does not indicate 0%, do not proceed.

NOTE: The turbine should be latched as soon as possible LT 1750 RPM to avoid approaching a critical speed.

10 Step 5.4.5 Selects a screen and observes VPL S/U Verify VPL DEMAND indicates 0% Demand at 0%.

valve limit position (Turbine Start-Up, Speed Control).

LO001782 Rev. 0 Page 4 of 13

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step CAUTION If the Main Turbine is latched with the Main Turbine speed GT 500 RPM, SPEED DEMAND will ramp to 1750 RPM and the throttle valves will start to ramp open.

NOTE: If latching Main Turbine at LT 500 RPM, VPL DEMAND will need to be set at the DEH Monitor. If latching Main Turbine at GE 500 RPM, VPL DEMAND will ramp to 100% automatically.

11 Step 5.4.6 On the Reactor Start display, touches S/U*

Latch the Main Turbine as follows latch.

(Turbine Start-Up, Reactor Start Display):

a. Select LATCH.

NOTE: Selecting YES will cause the Main Turbine to Latch. The Main Turbine Intercept and Reheat Stop Valves will open fully and the Governor Valves and Throttle Valves will remain fully closed.

12 Step 5.4.6b Touches yes.

S/U*

b. Select YES.

13 Step 5.4.6c Observes Speed Control (in small S/U blue area in middle of screen) is Verify the Turbine Mode indicates displayed.

Speed Control.

NOTE: There will be a time delay of approximately ten seconds from the time the MT is latched until speed will begin to ramp up, in order to allow the trip header to pressurize.

14 Step 5.4.7 Recognizes speed is GT 500 rpm and S/U If Main Turbine speed is GE 500 performs this step.

RPM, then verify the following Observes VPL demand at 100%.

(Turbine Start-Up, Speed Control):

a. VPL DEMAND ramps to 100%.

15 Step 5.4.7b Observes actual speed rising to 1750 S/U rpm.

Actual speed ramps to 1750 rpm.

16 Step 5.4.7c Observes speed rate at 80 rpm.

S/U Speed rate defaults to 80 rpm/min.

LO001782 Rev. 0 Page 5 of 13

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step EVALUATORS NOTE: It is anticipated that MT speed will be GT 500 rpm, but if it is not, this step will be performed.

17 Step 5.4.8 Recognizes speed is GT 500 rpm and S/U If Main Turbine Speed is LT 500 does not perform.

RPM then raise VPL to 100% as follows (Turbine Start-Up, Speed Control): (Touches VPL Auto Ramp)

a. Select VPL Auto Ramp.

18 Step 5.4.8b (Touches Yes)

S/U Select Yes.

19 Step 5.4.8c (Observes VPL demand ramps to S/U Verify VPL Demand ramps to 100%. 100%)

20 Step 5.4.8d (Verifies Speed Demand and Speed S/U Verify Speed Demand and Speed Target display the speed the Main Target display the speed the Main Turbine was latched at)

Turbine was latched at.

21 Step 5.4.8e (Observes Intercept and Reheat S/U Verify Intercept and Reheat valves valves open) are open (Menu, Valve Status Display).

22 Step 5.4.8f (Observes Throttle valves closed or S/U Verify Throttle Valves are closed or controlling speed) controlling speed.

LO001782 Rev. 0 Page 6 of 13

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 23 Step 5.4.9 Observes actual speed. Speed should S/U If Main Turbine Speed is LT 1750 be rising to 1750 rpm if it is not there RPM, then perform the following to already. This step should not be raise Turbine speed to 1750 RPM performed but OK if it is.

(Turbine Start-Up, Speed Control): (Touches speed target).

a. Select Speed Target.

24 Step 5.4.9b (Touches 1, 7, 5, and 0).

S/U Enter 1750 RPM.

25 Step 5.4.9c (Touches OK).

S/U Select OK.

26 Step 5.4.9d (Observes 1750 rpm in the speed S/U Verify 1750 RPM appears in Speed target window).

Target window.

27 Step 5.4.9e (Observes Hold illuminated).

S/U Verify Hold illuminated.

28 Step 5.4.9f (Touches speed rate).

S/U Select Speed Rate.

29 Step 5.4.9g (Observes 80 rpm indicated for speed S/U Enter the desired Speed Rate per rate).

Attachment 6.2. A minimum of 80 rpm/min is recommended to prevent excessive Turbine vibration from 800-1750 RPM.

30 Step 5.4.9h (Touches OK).

S/U Select OK.

LO001782 Rev. 0 Page 7 of 13

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 31 Step 5.4.9i (Observes 80 rpm in the speed rate S/U Verify entered speed rate appears window).

speed rate window.

32 Step 5.4.9j (Touches go).

S/U*

Select GO.

33 Step 5.4.9k (Touches yes).

S/U*

Select YES.

34 Step 5.4.10 (Observes rpm rising).

S/U Verify Turbine speed responds as speed demand changes.

35 Step 5.4.11 (Recognizes no hold is desired and S/U If a hold is desired during Main does not perform this step).

Turbine acceleration, then perform the following..

36 Step 5.4.12 (No hold was performed - does not S/U When HOLD is no longer desired perform this step).

37 Step 5.4.13 (Observers speed rises to 1750 rpm).

S/U Verify Turbine speed ramps to 1750 RPM.

38 Step 5.4.14 (Observes the go extinguishes at S/U Verify GO extinguishes at 1750 1750 rpm).

RPM.

NOTE: The following step will place the Main Turbine under control of the Governor Valves.

NOTE: During the TV/GV transfer, the Governor Valves will begin closing until the DEH Tricon senses a lowering Main Turbine speed (approximately 20 RPM lower), at which time the Throttle Valves will fully open and Governor Valves will throttle as necessary to raise Main Turbine speed back to 1750 RPM. The TV/GV transfer button will flash yellow until the transfer is complete. Full opening of the Throttle Valves will clear H13-P603 A7/A8 TURBINE THROTTLE VALVE CLOSURE TRIP ALARMS.

LO001782 Rev. 0 Page 8 of 13

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 39 Step 5.4.15 Verbalizes this step. When step is verbalized and speed is S/U When Turbine speed has been steady 1750 rpm, cue that two minutes have at 1750 RPM for at least 2 minutes, elapsed.

then transfer control from Throttle to Governor Valves as follows (Turbine Start-Up, Speed Control Display):

NOTE: During the TV/GV transfer, the Governor Valves will begin closing until the DEH Tricon senses a lowering Main Turbine speed (approximately 20 RPM lower), at which time the Throttle Valves will fully open and Governor Valves will throttle as necessary to raise Main Turbine speed back to 1750 RPM. The TV/GV transfer button will flash yellow until the transfer is complete. Full opening of the Throttle Valves will clear H13-P603 A7/A8 TURBINE THROTTLE VALVE CLOSURE TRIP ALARMS.

40 Step 5.4.15a Recognizes that cue indicated two S/U Verify Main Turbine speed has been minutes passed.

steady at 1750 RPM for at least 2 minutes.

41 Step 5.4.15b Touches TV/GV transfer.

S/U*

Select TV/GV transfer.

42 Step 5.4.15c Touches yes.

S/U*

Select yes.

43 Step 5.4.15d Observes Governor valves close and S/U Monitor the transfer from Throttle throttle valves open to control speed.

Valve to Governor Valve control.

44 Step 5.4.16 Touches speed target.

S/U*

Raise Main Turbine speed to 1800 RPM as follows (Turbine Start-Up, Speed Control Display):

a. Select Speed Target.

45 Step 5.4.16b Touches 1, 8, 0, 0.

S/U*

Enter 1800 RPM.

LO001782 Rev. 0 Page 9 of 13

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 46 Step 5.4.16c Touches OK.

S/U*

Select OK.

47 Step 5.4.16d Observes 1800 in the speed target S/U Verify 1800 RPM enter in the Speed window.

Target window.

48 Step 5.4.16e Observes hold illuminated.

S/U Verify hold illuminated.

49 Step 5.4.16f Touches speed rate (May not be S/U Select Speed Rate. performed if it is recognized that speed rate is 80 rpm).

50 Step 5.4.16g Observes 80 rpm as speed rate.

S/U Enter the desired speed rate per Attachment 6.2.

51 Step 5.4.16h Touches OK (May not be performed S/U Select OK. if it is recognized that speed rate is 80 rpm.

52 Step 5.4.16i Observes 80 rpm as speed rate (May S/U Verify the entered speed rate appears not be performed if it is recognized in the speed rate window. that speed rate is 80 rpm.

53 Step 5.4.16j Touches go.

S/U*

Select go.

54 Step 5.4.16k Touches yes.

S/U*

Select yes.

LO001782 Rev. 0 Page 10 of 13

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 55 Step 5.4.16l Observes go illuminated.

S/U Verify go illuminated.

56 Step 5.4.16m Observes MT speed rising.

S/U Verify Main Turbine speed responds as the speed demand value changes.

57 Step 5.4.16n Recognizes no hold is desired and S/U If a hold is desired during does not perform this step.

acceleration of the Main Turbine, then perform the following.

58 Step 5.4.16o Recognizes hold not used and does S/U When hold is no longer desired, then not perform this step.

perform the following:

59 Step 5.4.16p Observes 1800 rpm.

S/U Verify Turbine ramps to the desired speed.

60 Step 5.4.16q Observes go extinguishes at 1800 S/U Verify go extinguishes at entered rpm.

speed.

Termination Criteria: Candidate informs CRS that Main Turbine speed is 1800 rpm.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LO001782 Rev. 0 Page 11 of 13

RESULTS OF JPM RELATCH THE MAIN TURBINE Examinee (Print): _________________________________________________________________

Evaluator (Print): _________________________________________________________________

Task Standard: The Main Turbine has been relatched, the TV/GV Transfer has been performed and Main Turbine speed is 1800 rpm.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LO001782 Rev. 0 Page 12 of 13

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is starting up and just completed a special test on the Main Turbine.

Initiating Cue:

The CRS directs you to relatch the Main Turbine per SOP-MT-START section 5.4.

Steps 5.4.1 and 5.4.2 have been verified. Use a rate of change of 80 rpm throughout the evolution. No Main Turbine holds are required throughout the evolution.

Notify the CRS when Main Turbine speed has reached 1800 rpm.

Page 13 of 13

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE TRANSFER SL-31 TO SL-21 FROM SM-3 (CR/SIM) (Alt Path)

LESSON LENGTH .5 HRS INSTRUCTIONAL MATERIALS INCLUDED LESSON PLAN PQD CODE Rev. No.

SIMULATOR GUIDE PQD CODE Rev. No.

JPM PQD CODE LO001781 Rev. No. 0 EXAM PQD CODE Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/21/14 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE SAT Coordinator APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

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

Any IC where SL-31 is being powered from SM-3.

Special Setup Instructions:

Insert a malfunction for breaker 31/3 not to auto trip - BKR-EPS-13 FAIL AUTO TRIP.

Override ammeter indication for SL-31 (IND-EPS105) to 155 and ammeter indication for SL-21 (IND-EPS071) to 132. Also override ammeter indication for SL-11 (IND-EPS034) to 105 (just to have all three meters reading alike). Open and then Run schedule file LO001781a. DO NOT CLOSE THE FILE - LEAVE IT UP ON THE DESKTOP. Ensure LO001781b is in the schedule folder on the M drive. Ensure that event 4 is in the event window.

Schedule file LO001781a

<ACTION>schedule schedule\LR002077b.sch</ACTION>

</ITEM>

1

<ACTION>Event Events/LR002077.evt</ACTION>

<DESCRIPTION>LR002077 event file</DESCRIPTION>

</ITEM>

</SCHEDULE>

Schedule file LO001781b

<ACTION>Delete override IND-EPS071</ACTION>

<DESCRIPTION>AM-2-21 BUS 21 AMPS METER SIGNAL (M)</DESCRIPTION>

LO001781 Rev. 0 Page 2 of 7

</ITEM>

<ACTION>Delete override IND-EPS034</ACTION>

<DESCRIPTION>AM-1-11 BUS 11 AMPS METER SIGNAL (M)</DESCRIPTION>

</ITEM>

<ACTION>Delete override IND-EPS105</ACTION>

<DESCRIPTION>AM-3-31 BUS 31 AMPS METER SIGNAL (M)</DESCRIPTION>

</ITEM>

</SCHEDULE>

Event file

<EVENT>

</EVENT>

OR Special Setup Instructions:

Override ammeter indication for SL-31 (IND-EPS105) to 155 and ammeter indication for SL-21 (IND-EPS071) to 132. Also override ammeter indication for SL-11 (IND-EPS034) to 105 (just to have all three meters reading alike).

Fail CB-31/3 to auto open.

JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: None Safety Items: None Task Number: R0-0398 Validation Time: 5 minutes Alternate Path: Yes Time Critical: No PPM

Reference:

SOP-ELEC-480V-OPS Section 5.4 Rev. 4 Location: Simulator NUREG 1123 Ref: 262001A4.01 (3.4 / 3.7) / A4.05 (3.3 / 3.3) Performance Method: Perform Task Standard: It was identified prior to power transfer that amps were GT 277 amps, CB 31/3 was manually opened and SL-31 is powered from SL-21.

LO001781 Rev. 0 Page 3 of 7

JPM CHECKLIST INITIAL SL-31 is currently powered from SM-3. Work on the transformer requires SL-31 power be transferred to SL-21. All conditions, CONDITIONS: limitations, and prerequisites for this evolution are completed.

INITIATING The CRS directs you to transfer SL-31 to SL-21 from SM-3. Inform the CRS when SL-31 is being powered from SL-21.

CUE:

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step When the student identifies section 5.4 of SOP-ELEC-480V-OPS as procedure give student a copy.

CAUTION: DO NOT exceed 277 supply amps on any one transformer. NOTE: The controls and indications necessary to perform this section are located at H13-P800 (Bd C).

NOTE: CB-31/3 will trip when CB-31/21 is closed.

ALT 1 Step 5.4.1 Observes amp readings on ammeters I understand that the total amps on E-PATH Verify the sum of ammeters E-AM- E-AM-3/31 and E-AM-2/21 and S/U*

AM-3/31 and E-AM-2/21 are GT STEP 3/31 and E-AM-2/21 is LE 277 recognizes total is GT 277 amps. 277 amps amps. Informs CRS that amp total is GT 277 amps.

EVALUATOR - After cue given in JPM step 1, turn the control switch for the polishing filter DO-RMS-FP/1 to stop and then back to run to remove the amp meter overrides OR BOOTH OPERATOR - When cued by the evaluator remove the overrides associated with SL-11, SL-21 and SL-31 amp readings (IND-EPS034, IND-EPS105 and IND-EPS071) and inform the evaluator.

CUE (When overrides have been removed): The problem has been identified and corrected by electrical maintenance. Transfer power from SL-31 to SL-21 from SM-3.

2 Step 5.4.2 Observes the Green light on and the Verify CB-31/21 green light Red light off and Green flag S/U illuminated and flag displayed. displayed for CB-31/21.

3 Step 5.4.3 Turns the Bus 11, 21, and 31 Trip Place Bus 11, 21, and 31 Trip Permissive Selector switch to the S/U*

Permissive Selector switch in Trip Trip CB-31/3 position.

CB-31/3.

LO001781 Rev. 0 Page 4 of 7

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step NOTE: 4.800.C3.5-4, BKR 31/3 TRIP will alarm when the following step is performed.

4 Step 5.4.4 Turns the control switch for CB-Close CB-31/21. 31/21 to the close position. S/U*

5 Step 5.4.5 Observes the Green light off for CB-Verify CB-31/21 green light 31/21. S/U extinguishes.

6 Step 5.4.6 Observes the Red light on for CB-Verify CB-31/21 red light 31/21. S/U illuminates.

7 Step 5.4.7 Observes Red light lit and Green Verify CB-31/3 auto trips. light off for CB-31/3. S/U ALT 8 Step 5.4.8 Turns the control switch for CB-31/3 PATH Place CB-31/3 control switch in to the Trip position. S/U*

STEP Trip. Observes CB-31/3 Green light on and Red light off.

9 Step 5.4.9 Observes the Green light lit and the Verify CB-31/3 green light Green flag displayed for CB-31/3. S/U illuminated and green flag displayed.

10 Step 5.4.10 Turns the Bus 11, 21, and 31 Trip Place Bus 11, 21, and 31 Trip Permissive Selector switch to an Off S/U Permissive Selector switch in Off. position.

11 Step 5.4.11 Observes amp readings on ammeters E-AM-3/31 and E-AM-2/21 and S/U Verify E-AM-2/21 is LE 277 amps.

recognizes total is LT 277 amps.

Termination Criteria: Student informs CRS that SL-31 has been transferred from SM-3 and is being powered from SL-21.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LO001781 Rev. 0 Page 5 of 7

RESULTS OF JPM TRANSFER SM-3 FROM TR-S TO TR-N Examinee (Print): _________________________________________________________________

Evaluator (Print): _________________________________________________________________

Task Standard: It was identified prior to power transfer that amps were GT 277 amps, CB-31/3 was manually opened, and SL-31 is powered from SL-21.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LO001781 Rev. 0 Page 6 of 7

STUDENT JPM INFORMATION CARD Initial Conditions:

SL-31 is currently powered from SM-3.

Work on the transformer requires SL-31 power be transferred to SL-21.

All conditions, limitations, and prerequisites for this evolution are completed.

Initiating Cue:

The CRS directs you to transfer SL-31 to SL-21 from SM-3.

Inform the CRS when SL-31 is being powered from SL-21.

Page 7 of 7

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

LESSON LENGTH .5 HRS INSTRUCTIONAL MATERIALS INCLUDED LESSON PLAN PQD CODE Rev. No.

SIMULATOR GUIDE PQD CODE Rev. No.

JPM PQD CODE LO001642 Rev. No. 3 EXAM PQD CODE Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/02/08 REVISED BY Ron Hayden DATE 12/31/14 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE SAT Coordinator APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

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

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

Ensure RRC-P-1A flow is about 22,000 gpm (GT 20,800 gpm). Ensure CB-RPT-3B, 4B and CB-RRB are open.

Insert malfunction MAL-RFC016E which overrides off the ASD 15 second P/B Stuck limit.

This is the event file for the schedule file:

<EVENT>

</EVENT>

Run the following schedule files:

!-- This file contains a Thunder Simulations Schedule -->

1

<ACTION>Insert override OVR-RFC030P after 15 to ON on event 1</ACTION>

<DESCRIPTION>Depress RRC-P-1B raise P/B</DESCRIPTION>

</ITEM>

1

<ACTION>Insert override OVR-RFC030N to OFF on event 1</ACTION>

<DESCRIPTION>RRC-M/A-676B LOWER P/B OFF</DESCRIPTION>

</ITEM>

1

LO001642 Rev. 3 Page 2 of 12

<ACTION>Event Events/LO001642.evt</ACTION>

<DESCRIPTION>LO001642 event file</DESCRIPTION>

</ITEM>

</SCHEDULE>

Special Setup Instructions:

See above.

JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: None Safety Items: None Task Number: RO-1162; RO-0083 Validation Time: 20 Minutes Alternate Path: Yes Time Critical: No PPM

Reference:

SOP-RRC-START Rev. 16; ABN-POWER Rev. 13 Location: Simulator NUREG 1123 Ref: 202001 A2.05 (3.8 / 4.0) Performance Method: Perform Task Standard: RRC-P-1B was started and was stopped by depressing the stop pushbutton.

LO001642 Rev. 3 Page 3 of 12

JPM CHECKLIST INITIAL 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 CONDITIONS: 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 54% rod line. RRC seal purge has been in service for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months per SOP-RRC-SEAL. OSP-RRC-C103 has been completed for steps 5.2.15 and 5.2.16. 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 The CRS has directed you to start RRC-P-1B per SOP-RRC-START section 5.2. Notify the CRS when RRC-P-1B is operating at CUE: 15 Hz.

Items are Critical Steps Time JPM Step Task Element Performance Standard Evaluators Cue Results NOTE: An RRC pump start in this condition requires the presence of an SNE in the Control Room and an approved PPM 9.3.12 S/U plan in place. CAUTION Entry into the Area of Increased Awareness may result in core oscillations. CAUTION Do not enter the Area Of Increased Awareness when reducing core flow. CAUTION Due to a crack near Jet Pump 17/18 riser, RRC loop B flow should not exceed 55.9 Mlbm/hr, averaged over a one hour period.

1 Step 5.2.1 Recognizes initial conditions stated SNE review of Core Conditions and S/U Verify the SNE has evaluated the RPV Inlet Temperature was following parameters per complete.

PPM 9.3.12:

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

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 Att. 6.3 LO001642 Rev. 3 Page 4 of 12

Items are Critical Steps Time JPM Step Task Element Performance Standard Evaluators Cue Results 2 Step 5.2.2 Observes pump speed is 33 Hz and depresses the lower P/B to reduce S/U*

Lower the operating recirculation RRC-P-1B speed to LE 30 Hz.

pump speed to LT 30 Hz (~20,800 GPM drive flow or less). Observes flow to be approximately 20,800 gpm.

Caution RRC Pump start in the AIA is prohibited. The lower boundary of the AIA is the 54% rod line as specified in Attachment 6.1.

3 Step 5.2.3 Recognizes initial conditions stated Rod Line on Computer screen may not be rod line LT 54% (May also refer to displayed or be below 54%. If simulator is S/U Verify the Reactor is below the 54% checked refer student to initial conditions or computer screen).

rod line. cue that rod line is LT 54%.

4 Step 5.2.4 Observes RPV level indication and determines RPV/L is GT +31.5 S/U Verify reactor water level is GT level inches.

4.

5 Step 5.2.5 Recognizes initial conditions stated RRC seal purge has been in service S/U Verify recirculation pump seal purge for GT 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

injection has been in service for at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to starting an idle pump per SOP-RRC-SEAL.

LO001642 Rev. 3 Page 5 of 12

Items are Critical Steps Time JPM Step Task Element Performance Standard Evaluators Cue Results 6 Step 5.2.6 Observes the Red light on and the Green light off for: S/U Verify the following:

RWCU-V-106 OPEN RWCU-V-106, RRC-V-23B

RRC-V-23B OPEN RRC-V-67B, RCC-V-17B.

RRC-V-67B OPEN

RCC-V-17B OPEN Observes manual light on for RRC-M/A-R676B.

RRC-M/A-R676B in MANUAL

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

RRC-M/A-R676B status lights extinguished:

Feed Pump Trip Observes lights for Feed pump trip,

dT Cavitation Delta T Cavitation and Low RPV

Reactor Low Level Level are off.

Note: It is acceptable for the thrust monitor to be in alarm when the RRC pump is shutdown 7 Step 5.2.6 (continued) Observes H13-P602. A6-2.8, RECIRC B SYSTEM VIB HIGH not S/U

H13-P602.A6-2.8, RECIRC B alarmed.

SYSTEM VIB HIGH is clear.

Observes H13-P602. A6.2-5,

H13-P602.A6.2-5, RECIRC B RECIRC B PUMP SEAL COOLING PUMP SEAL COOLING WATER WATER FLOW LOW not alarmed.

FLOW LOW is clear.

Observes H13-P602.A6.3-6,

H13-P602.A6.3-6, RECIRC B RECIRC B MOTOR WINDING MOTOR WINDING COOLANT COOLANT FLOW LOW not FLOW LOW is clear. alarmed.

LO001642 Rev. 3 Page 6 of 12

Items are Critical Steps Time JPM Step Task Element Performance Standard Evaluators Cue Results 8 Step 5.2.7 Places control switch for CB-RRB to the Close position. S/U*

Close CB-RRB (RRC-P-1B Bus Tie breaker) (H13-P602). Observes the Red light on and the Green light off.

9 Step 5.2.8 Places control switch for CB-RPT-4B to the Close position. S/U*

Close CB-RPT-4B (RRC-P-1B Motor Interlock Breaker) Observes the Red light on and the (H13-P602). Green light off.

10 Step 5.2.9 Places control switch for CB-RPT-3B to the Close position. S/U*

Close CB-RPT-3B (RRC-P-1B Motor Interlock Breaker) Observes the Red light on and the (H13-P602). Green light off.

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

11 Step 5.2.10 Observes lights lit for DS-6C on H13-P609 and DS-6D on H13-P611. S/U Verify following white lights Dimly lit (RPT trip system A):

DS 6C (H13-P609)

DS 6D (H13-P611) 12 Step 5.2.11 Contacts OPS4 and directs The reset pushbutton for each drive depressing the reset pushbutton at the has been depressed. S/U Depress the reset pushbutton at the control and diagnostic panel for each control and diagnostic panel for each drive.

drive LO001642 Rev. 3 Page 7 of 12

Items are Critical Steps Time JPM Step Task Element Performance Standard Evaluators Cue Results 13 Step 5.2.12 Recognizes that both drive channels If students performs this step, direct will be used - does not perform. a start using both drive channels S/U 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 14 Step 5.2.13 Recognizes that both drive channels If students performs this step, direct will be used - does not perform. a start using both drive channels S/U 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 15 Step 5.2.14 Contacts OPS4 and directs Both channel selector switches are in If starting an RRC pump on both verification that both Channel the on position for ASD-1B/1 and S/U drive channels, then verify both Selector Switches are in the ON ASD-1B/2.

Channel Selector Switches for that positions at panels: RRC-IMD-drive are on. ASD1B/1 (Local Control and Diagnostics Panel) and RRC-IMD-

RRC-IMD-ASD1B/1 (Local ASD1B/2 (Local Control and Control and Diagnostics Panel)

Diagnostics Panel).

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

CAUTION Operation within the prohibited region of the Two Loop Recirculation Pump Speed Mismatch Operating Limits Curve, Attachment 6.4, will result in high vibration levels in the idle Jet Pumps.

LO001642 Rev. 3 Page 8 of 12

Items are Critical Steps Time JPM Step Task Element Performance Standard Evaluators Cue Results 16 Step 5.2.15 Recognizes information given in NOTE: Even if GT 15 minutes has turnover (OSP-RRC-C103 has been passed since starting the JPM, cue S/U Verify temperature limitations within completed for steps 5.1.15 and student the requirements of step 15 minutes prior to starting an idle 5.1.16). 5.1.15 and 5.1.16 have been recirculation pump per completed per OSP-RRC-C103.

OSP-RRC-C103.

17 Step 5.2.16 Recognizes information given in NOTE: Even if GT 15 minutes has turnover (OSP-RRC-C103 has been passed since starting the JPM, cue S/U If starting an idle pump with the completed for steps 5.1.15 and student the requirements of step other pump in operation, then verify 5.1.16). 5.1.15 and 5.1.16 have been the operating loop flow is LT 50% of completed per OSP-RRC-C103.

rated loop flow (30 Hz) within 15 minutes prior to pump start per OSP-RRC-C103.

18 Step 5.2.17 Recognizes information given in turnover (No computer substitute S/U If applicable, then remove the B18 computer substitute value for Single value for Single Loop Operation has been entered) - does not perform.

Loop Operation.

19 Step 5.2.18 Observes ASD ready lights are on for each drive channel. S/U Verify the ASD "READY" light for the drive channels to be started are illuminated.

NOTE: A momentary GTO FREEZE alarm may be expected upon channel start. This alarm may be cleared by depressing the local reset pushbutton. An actual GTO FREEZE alarm will cause the channel to fault and trip.

NOTE: Frequency indication may be momentarily erratic during pump start.

NOTE: If the pump has been idle for an extended period of time, the expected start time of 30-50 seconds may be longer due to no oil film present under the thrust bearing 20 Step 5.2.19 Momentarily depresses the ASD start pushbutton for RRC-P-1B. S/U*

Start RRC-P-1B by momentarily depressing the ASD START pushbutton.

LO001642 Rev. 3 Page 9 of 12

Items are Critical Steps Time JPM Step Task Element Performance Standard Evaluators Cue Results 21 Step 5.2.20 Observes the Red lights on and the White lights off for drives No.1 and S/U Verify the RRC-P-1B starts and No.2.

continues to operate at approximately 450 RPM (15 Hz). Observes RPMs for RRC-P-1B rise to 450 rpm within 50 seconds.

22 ALTERNATE PATH STEP Recognizes that the speed for RRC- If CRS is informed of the rise in P-1B continues to go up past 15 Hz / RRC-P-1B speed, ONLY repeat S/U 450 rpm without operator demand. back the communication - do not give any direction.

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.

May informs CRS that RRC-P-1B speed is rising without demand.

23 ABN-POWER Step 3.2.1 Depresses the STOP pushbutton for RRC-P-1B and verifies it stops. S/U*

If RRC pump speed is rising for one pump and cannot be controlled, then Informs the CRS that RRC-P-1B was stop the affected pump. stopped as pump speed continued to rise GT 15 Hz.

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.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LO001642 Rev. 3 Page 10 of 12

RESULTS OF JPM START RRC-P-1B; INADVERTENT RRC FLOW INCREASE Examinee (Print): _________________________________________________________________

Evaluator (Print): _________________________________________________________________

Task Standard: RRC-P-1B was started and was stopped by depressing the stop pushbutton.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LO001642 Rev. 3 Page 11 of 12

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 54% rod line.

RRC seal purge has been in service for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months per SOP-RRC-SEAL. OSP-RRC-C103 has been completed for steps 5.2.15 and 5.2.16.

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 directs you to start RRC-P-1B per SOP-RRC-START section 5.2.

Notify the CRS when RRC-P-1B is operating at 15 Hz.

Page 12 of 12

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE ALIGN SERVICE WATER TO THE FUEL POOL HEAT EXCHANGERS (CR/SIM)

LESSON LENGTH .5 HRS INSTRUCTIONAL MATERIALS INCLUDED LESSON PLAN PQD CODE Rev. No.

SIMULATOR GUIDE PQD CODE Rev. No.

JPM PQD CODE LO001756 Rev. No. 1 EXAM PQD CODE Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 12/12/12 REVISED BY Ron Hayden DATE 10/31/14 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

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

Any IC where FPC is running.

Special Setup Instructions:

The candidate is given a copy of SOP-FPC-OPS Section 5.6 at the beginning of the JPM.

JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: None Safety Items: None Task Number: RO-0304 Validation Time: 8 Minutes Alternate Path: No Time Critical: No PPM

Reference:

SOP-FPC-OPS Section 5.6 Rev. 7 Location: Simulator NUREG 1123 Ref: 233000 A2.08 (2.9 / 3.1) Performance Method: Simulate Task Standard: Service Water has been aligned to FPC-HX-1A and to FPC-HX-1B.

LO001756 Rev.1 Page 2 of 9

JPM CHECKLIST INITIAL Columbia was operating in Mode 1 when a complete loss of RCC occurred. A reactor scram was inserted and efforts are underway CONDITIONS: to restore RCC cooling. SW-P-1A and SW-P-1B are running. Fuel Pool temperatures are rising. Free release of RCC heat exchanger water to the Service Water spray ponds has been approved. OSP-SW-M101 and OSP-SW-M102 have been referenced for component flow requirements. OPS2 has been briefed and is on station.

INITIATING The CRS directs you to align Service Water to both Fuel Pool Cooling Heat Exchangers per SOP-FPC-OPS Section 5.6. Inform the CUE: CRS when Service Water has been aligned to both Fuel Pool Cooling heat exchangers.

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step NOTE: Standby Service Water to FPC-HX-1A(B) is normally used if RCC flow is lost and restoration is not anticipated prior to 125° F in the Fuel Pool, as indicated on FPC-TI-7/8 at H13-P626 (FPC-1), or for evolutions that require the Fuel Pool to be cooled below the capabilities of the RCC system. Examples: Loading spent fuel into an ISFSI MPC or to raise stay time for divers.

NOTE: If Standby Service Water is aligned to the FPC heat exchanger, it is acceptable to operate below the minimum flow specified in OSP-SW-M101(M102) as long as the minimum operability value specified in PPM 8.4.81 is maintained.

NOTE: If RCC is lined up to SSW for GE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , then it is recommended RCC-RV-34A(B) (FPC-HX-1A(B) Shell Side Relief Valve) be scheduled for replacement and test as soon as possible after swapping back to RCC. This is due to the potential for loose debris in SSW causing RCC-RV-34A(B) to lift and leak.

1 Step 5.6.1 Recognizes that discharge of RCC S/U Verify free release of RCC Heat heat exchanger water into the Service Exchanger water to the Service Water Water spray ponds has been Spray Ponds. approved.

2 Step 5.6.2 Performs this step. S/U If desired, then lineup Standby Service Water Cooling to FPC-HX-1A as follows:

3 Step 5.6.2a Given as complete in the Initial If OSP-SW-M101 is referenced, refer S/U Conditions - does not perform. candidate to Initial Conditions.

Refer to OSP-SW-M101 for Standby Service Water Loop A for component flow requirements.

4 Step 5.6.2b Recognizes that SW-P-1A is given in S/U Initial Conditions as running.

Verify SW-P-1A is running.

LO001756 Rev.1 Page 3 of 9

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step EVALUATORS NOTE: The candidate must perform at least one of the following two steps (Either 5.6.2c or 5.6.2d but may perform both).

5 Step 5.6.2c Turns the control switch for the S/U*

If RCC cooling to FPC-HX-1B is not following valves to close and verifies required, then close the following: Green light on and Red light off for: (Note:

Either this

RCC-V-129 (Fuel Pool HX-A/B

RCC-V-129 step or the RCC Cooling Inlet) next step is

RCC-V-130 critical. At

RCC-V-130 (Fuel Pool HX-A/B least one of RCC Cooling Outlet) these steps

RCC-V-131 must be

RCC-V-131 (Fuel Pool HX-A/B performed)

RCC Cooling Outlet) 6 Step 5.6.2d Direct OPS2 to perform Step 5.6.2d If candidate approaches front panel to S/U*

If RCC cooling to FPC-HX-1B is of SOP-FPC-OPS to close RCC-V- use the radio, direct candidate to required, or SW is to be aligned to 9A and RCC-V-10A. simulate communications. (Note: If both FPC-HX-1A and FPC-HX-1B, RCC-V-9A and RCC-V-10A are RCC-V-then close the following: 129, V-130 closed (Note: No simulator actions and V-

RCC-V-9A (FPC-HX-1A RCC are required). 131were Cooling Inlet) (FPC HX Room) previously closed, this

RCC-V-10A (FPC-HX-1A RCC is not a Cooling Outlet) (FPC HX Room) critical step

- refer to above step).

NOTE: SW-V-187A and SW-V-188A keylock switch spring returns to NORMAL from OPEN, and maintains in CLOSE.

LO001756 Rev.1 Page 4 of 9

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 7 Step 5.6.2e Obtains key 219 from key locker and S/U*

Open SW-V-187A (FPC-HX-1A places key in the control switch and Backup Cooling SW-A Inlet) (H13- turns the control switch for SW-V-P626). 187A clockwise to open and allows switch to spring return to Norm.

Verifies Red light on and Green light off.

8 Step 5.6.2f Obtains key 221 and places key in S/U*

Open SW-V-188A (FPC-HX-1A the control switch and turns the Backup Cooling SW-A Outlet) (H13- control switch for SW-V-188A P626). clockwise to open and allows switch to spring return to Norm.

Verifies Red light on and Green light off.

9 Step 5.6.3 Performs this step.

S/U If desired, then lineup Standby Service Water Cooling to FPC-HX-1B as follows:

10 Step 5.6.3a Given as complete in the Initial If OSP-SW-M102 is referenced, refer S/U Conditions - does not perform. candidate to Initial Conditions.

Refer to OSP-SW-M102 for Standby Service Water Loop B for component flow requirements.

11 Step 5.6.3b Recognizes that SW-P-1A is given in S/U Initial Conditions as running.

Verify SW-P-1B is running.

LO001756 Rev.1 Page 5 of 9

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 12 Step 5.6.3c Recognizes that these valves were S/U*

closed in a previous step - does not If RCC cooling to FPC-HX-1A is not perform.

required, then close the following: (Note:

If this step was not previously Either this

RCC-V-129 (Fuel Pool HX-A/B step or the performed it may be performed at RCC Cooling Inlet) next step is this point. critical. At

RCC-V-130 (Fuel Pool HX-A/B least one of Turns the control switch for the RCC Cooling Outlet) these steps following valves to close and verifies must be

RCC-V-131 (Fuel Pool HX-A/B Green light on and Red light off for: performed)

RCC Cooling Outlet)

RCC-V-129

RCC-V-130

RCC-V-131 13 Step 5.6.3d Directs OPS2 to perform Step 5.6.3d If candidate approaches front panel to S/U*

of SOP-FPC-OPS to close RCC-V- use the radio, direct candidate to If RCC cooling to FPC-HX-1A is 9B and RCC-V-10B. simulate communications.

required, or SW is to be aligned to (Note: If both FPC-HX-1A and FPC-HX-1B, RCC-V-9B and RCC-V-10B are RCC-V-129, V-130 then close the following: closed (Note: No simulator actions and V-131 are required). were not

RCC-V-9B (FPC-HX-1B RCC previously Cooling Inlet) (FPC HX Room) closed this

RCC-V-10B (FPC-HX-1B RCC is a critical Cooling Outlet) (FPC HX Room) step).

NOTE: SW-V-187B and SW-V-188B keylock switch spring returns to NORMAL from OPEN, and maintains in CLOSE.

LO001756 Rev.1 Page 6 of 9

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 14 Step 5.6.3e Obtains key 220 and places key in Note: during validation it was S/U*

the control switch and turns the recognized that this valve is on P627 Open SW-V-187B (FPC-HX-1B control switch for SW-V-187B and not P626. If recognized, authorize Backup Cooling SW-B Inlet) (H13-clockwise to open and allows switch an editorial change to allow the JPM P626).

to spring return to Norm. to continue.

Verifies Red light on and Green light off.

15 Step 5.6.3f Obtains key 222 and places key in Note: during validation it was S/U*

the control switch and turns the recognized that this valve is on P627 Open SW-V-188B (FPC-HX-1A control switch for SW-V-188B and not P626. If recognized, authorize Backup Cooling SW-B Outlet) (H13-clockwise to open and allows switch an editorial change to allow the JPM P626).

to spring return to Norm. to continue.

Note: during validation it was recognized that this valve is on P627. Verifies Red light on and Green light off.

Termination Criteria: Student informs CRS that Service Water has been aligned to both Fuel Pool Cooling Heat Exchangers.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LO001756 Rev.1 Page 7 of 9

RESULTS OF JPM ALIGN SERVICE WATER TO THE FUEL POOL COOLING HEAT EXCHANGERS Examinee (Print): _________________________________________________________________

Evaluator (Print): _________________________________________________________________

Task Standard: Service Water has been aligned to FPC-HX-1A and to FPC-HX-1B.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LO001756 Rev.1 Page 8 of 9

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia was operating in Mode 1 when a complete loss of RCC occurred.

A reactor scram was inserted and efforts are underway to restore RCC cooling.

SW-P-1A and SW-P-1B are running.

Fuel Pool temperatures are rising.

Free release of RCC heat exchanger water to the Service Water spray ponds has been approved.

OSP-SW-M101 and OSP-SW-M102 have been referenced for component flow requirements.

OPS2 has been briefed and is on station.

Initiating Cue:

The CRS directs you to align Service Water to both Fuel Pool Cooling Heat Exchangers per SOP-FPC-OPS Section 5.6.

Inform the CRS when Service Water has been aligned to both Fuel Pool Cooling heat exchangers.

Page 9 of 9

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE SWAP RCC PUMPS (PARTIAL LOSS OF RCC FLOW) (CR/SIM) (ALT PATH)

LESSON LENGTH .5 HRS INSTRUCTIONAL MATERIALS INCLUDED LESSON PLAN PQD CODE Rev. No.

SIMULATOR GUIDE PQD CODE Rev. No.

JPM PQD CODE LO001806 Rev. No. 0 EXAM PQD CODE Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/21/14 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE SAT Coordinator APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

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

Run the following CAEP file:

RCC-P-1A trip on event 1.

RCC-P-1C trip on event 1.

RWCU-P-1A does not auto trip.

RWCU-V-4 does not auto close.

Event 1 should trigger when RCC-P-1Bs red light goes out with a 3 second time delay.

Special Setup Instructions:

None JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: None Safety Items: None Task Number: RO-0221; RO-0048 Validation Time: 8 minutes Alternate Path: Yes Time Critical: NO PPM

Reference:

SOP-RCC-OPS Section 5.1 Rev. 4 Location: SIMULATOR ABN-RCC Rev. 6 NUREG 1123 Ref: Performance Method: PERFORM Task Standard: RCC-P-1B was started, RWCU-P-1C was stopped, RWCU-V-104 is throttled open and RWCU-V-4 is closed.

LO001806 Rev. 0 Page 2 of 8

JPM CHECKLIST INITIAL RCC Pump maintenance on RWCU-P-1C is schedule to be performed next shift. No maintenance has been performed on CONDITIONS: RCC-P-1B. OPS2 has been briefed and is standing by to swap RCC pumps.

INITIATING The CRS directs you to swap RCC pumps to RCC-P-1B running and RCC-P-1C in standby per SOP-RCC-OPS section 5.1. Inform CUE: the CRS when the RCC pump swap has been completed.

Items are Critical Steps Time Step Task Element Performance Standard Evaluators Cue Results 1 Step 5.1.1 Performs this step.

S/U If Standby RCC pump is to be started, then START Standby RCC Pump as follows:

2 Step 5.1.1a Recognizes RCC-P-1A is already S/U running and does not perform this If starting RCC-P-1A.

step.

3 Step 5.1.1b Performs this step.

S/U If starting RCC-P-1B then perform the following:

4 Step 5.1.1b 1) Contacts OPS2 and requests status of RCC-V-1B is open.

S/U RCC-V-1B (verify valve open).

Verify RCC-V-1B open (Pump Suction) (RB 548 J9/4.1).

5 Step 5.1.1b 2) Contacts OPS2 and requests status of RCC-V-2B is open.

S/U RCC-V-2B (verify valve open).

Verify RCC-V-2B open (Pump Discharge) (RB 548 J9/4.1).

6 Step 5.1.1b 3) Recognizes initial conditions state S/U If maintenance was performed.. maintenance was not performed and does not perform this step.

LO001806 Rev. 0 Page 3 of 8

Items are Critical Steps Time Step Task Element Performance Standard Evaluators Cue Results 7 Step 5.1.1b 4) Turns RCC-P-1Bs control switch, S/U*

Place RCC-RMS-P-1B in Auto after RCC-RMS-P-1B, clockwise to start.

Start (H13-P820).

Observes Red light on and Green light off.

Releases RCC-RMS-P-1B in the Auto after Start position.

8 Step 5.1.2 Performs this step. S/U Stop one RCC pump as follows:

WARNING: Check valve RCC-V-23A(B)(C) may require manual manipulation to fully close. Exercise caution to ensure all personnel stay clear of the movement of the valve handle which will move quickly as valve is closing.

9 Step 5.1.2a Does not perform this step. S/U If stopping RCC-P-1A.

10 Step 5.1.2b Does not perform this step. S/U If stopping RCC-P-1B.

11 Step 5.1.2c Performs this step. S/U If stopping RCC-P-1C then perform the following:

12 Step 5.1.2c 1) Turns RCC-P-1Cs control switch, S/U*

Place RCC-RMS-1C in Auto after RCC-RMS-1C, to stop.

Stop (H13-P820).

Observes Green light on and Red light off.

Releases RCC-RMS-1C in the auto after stop position.

LO001806 Rev. 0 Page 4 of 8

Items are Critical Steps Time Step Task Element Performance Standard Evaluators Cue Results 13 Recognizes RCC-P-1B tripped. Perform required actions.

S/U*

Inform the CRS that RCC-P-1B has tripped (and only RCC-P-1A is running).

14 ABN-RCC. Refers to ABN-RCC and recognizes S/U Step 4.0 Subsequent Actions no immediate operator actions.

Step 4.1 If a complete loss of RCC flow occurs or a loss of RCC flow to the Drywell occurs, then perform the Recognizes neither condition exists following and does not perform this step.

15 Step 4.2 Performs this step. S/U If a partial loss of RCC flow occurs then perform the following:

NOTE: If RCC flow is lost to the Radwaste Building, OG-RF-20A(B)(C) may trip.

16 Step 4.2.1 Recognizes RCC-P-1B has not S/U If an RCC pump has tripped then restarted.

verify the standby RCC pump has Turns RCC-P-1Bs control switch, started.

RCC-RMS-1B, clockwise to start and recognizes the pump does not start.

17 Step 4.2.2 Recognizes only one RCC pump is S/U If two RCC pumps are running, then running and does not perform this verify RCC-V-6 is open. step.

NOTE: Closing RWCU-V-4 without throttling open RWCU-V-104 will result in RWCU-RV-3 lifting, if CRD seal purge is not isolated.

LO001806 Rev. 0 Page 5 of 8

Items are Critical Steps Time Step Task Element Performance Standard Evaluators Cue Results 18 Step 4.2.3 May go to backpanel to verify RCC- S/U If RCC-V-6 (RW/RB Supply) is V-6 is closed or may make the closed, then perform the following: determination RCC-V-6 is closed based on only one RCC pump running.

19 Step 4.2.3a Turns the control switch for RWCU- S/U*

Stop RWCU-P-1A(B). P-1A counterclockwise to stop.

Observes Green light on and Red light off.

20 Step 4.2.3b Turns the control switch for RWCU- S/U*

Throttle open RWCU-V-104. V-104 clockwise to open until both the Red and Green light are on.

21 Step 4.2.3c Turns the control switch for RWCU- S/U*

Close RWCU-V-4 (RWCU Suction V-4 counterclockwise to close.

Outboard Isolation).

Observes Green light on and Red light off.

Termination Criteria: When RWCU-V-4 has been closed, inform the Student that the termination point of the JPM has been reached.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LO001806 Rev. 0 Page 6 of 8

RESULTS OF JPM SWAP RCC PUMPS (PARTIAL LOSS OF RCC FLOW)

Examinee (Print): _________________________________________________________________

Evaluator (Print): _________________________________________________________________

Task Standard: RCC-P-1B was started, RWCU-P-1C was stopped, RWCU-V-104 is throttled open and RWCU-V-4 is closed.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LO001806 Rev. 0 Page 7 of 8

STUDENT JPM INFORMATION CARD Initial Conditions:

RCC Pump maintenance on RWCU-P-1C is schedule to be performed next shift.

No maintenance has been performed on RCC-P-1B. OPS2 has been briefed and is standing by to swap RCC pumps.

Initiating Cue:

The CRS directs you to swap RCC pumps to RCC-P-1B running and RCC-P-1C in standby per SOP-RCC-OPS section 5.1.

Inform the CRS when the RCC pump swap has been completed.

Page 8 of 8

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE Emergency Drywell Venting (PPM 5.5.15) (CR/SIM)

LENGTH OF LESSON 1 Hour INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code LR000161 Rev. No. 11 JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/21/99 REVISED BY Ron Hayden DATE 10/31/14 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE SAT Coordinator APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

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

N/A Special Setup Instructions:

None JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: flashlight/laser pointer, if required; Safety Items: High Voltage inside panels PPE Task Number: RO-0687 Validation Time: 10 Minutes Alternate Path: No Time Critical: No PPM

Reference:

PPM 5.5.15 Rev. 5 Location: Control Room NUREG 1123 Ref: 223001 A4.07 (4.2/4.1) Performance Method: Simulate Task Standard: All personnel have been evacuated from the Reactor Building and Emergency Drywell Venting has been initiated.

LR000161 Rev. 11 Page 1 of 8

JPM CHECKLIST INITIAL A LOCA has occurred. PPM 5.2.1 has been entered and plant conditions require containment venting. Neither Standby Gas train CONDITIONS: is currently operating.

INITIATING The CRS directs you to vent the drywell in accordance with PPM 5.5.15 using SGT train B. Inform the CRS when venting of the CUE: Drywell has been initiated. The performance of this JPM is simulated. Control manipulations will not be performed.

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step DO NOT ALLOW STUDENT TO OPEN THE EOP DRAWER IN THE CONTROL ROOM 1 Obtains procedure/tools/ equipment Student indicates the EOP drawer is You have obtained procedure and S/U*

for PPM 5.5.15. where the procedure, tools, equipment bag from the drawer.

equipment and safety equipment Hand student working copy of would be obtained to perform procedure.

procedure.

2 Step 4.1 Recognizes direction to use SGT-B is S/U given in Initiating Cue.

Select the SGT Train to be used for venting.

3 Step 4.2 Recognizes direction to use SGT-B is S/U given in Initiating Cue - does not If the SGT A will be used...

perform this step.

LR000161 Rev. 11 Page 2 of 8

Time Step Task Element Performance Standard Evaluators Cue Results 4 Step 4.3 Opens H13-P891 Bay 1 door and The indicated lead has been lifted S/U*

identifies terminal 16 on TM-K2 and taped.

If the SGT B train will be used for 09.

venting, then override SGT-V-1B (inlet from containment) isolation Simulates/verbalizes that the logic by lifting and taping the grey terminal 16 screw would be removed (top) lead on terminal 16 of TM-K2- and the grey (top) lead would be 1-09, at H13-P891, Bay 1. lifted and taped.

5 Step 4.4 Opens H13-P892 Bay 4 door and A jumper has been installed between S/U*

identifies terminal 14 and 15 on TM- the terminal points indicated.

Override CEP-V-1A (Drywell K1-4-05.

Exhaust Outboard) isolation logic by installing a jumper between terminal Simulates/verbalizes that the screws 14 and terminal 15 of TM-K1-4-05, from terminals 14 and 15 would be at H13-P892 Bay 4. removed and a jumper would be installed between them.

6 Step 4.5 Opens H13-P891 Bay 4 door and A jumper has been installed between S/U*

identifies terminals 14 and 15 on the terminal points indicated Override CEP-V-2A (Drywell TM-K2-4-07.

Exhaust Inboard) isolation logic by installing a jumper between 14 and Simulates/verbalizes that the screws 15 of TM-K2-4-07 at P891 Bay 4. from terminals 14 and 15 would be removed and a jumper would be installed between them.

7 Step 4.6 Observes Green light on and Red Green light is on, Red light is off S/U Verify CEP-V-11, (Exhaust to Rx light is off for CEP-V-11.

Bldg Plenum) is closed.

8 Step 4.7 Performs this step.

S/U If not operating, then start SGT Train A(B) as follows:

LR000161 Rev. 11 Page 3 of 8

Time Step Task Element Performance Standard Evaluators Cue Results 9 Step 4.7.1 Observes Red light on and Green Red light is on, Green light is off.

S/U Verify SGT-V-2A (2B), (Inlet from light off for SGT-V-2B. Red flag displayed.

Reactor Building) is open.

10 Step 4.7.2 Observes Red light on and Green Red light is on, Green light is off.

S/U Verify SGT-V-3A2, Fan A-1 Inlet light off for SGT-V-3B1. Red flag displayed.

(3B1, Fan B2 Inlet) is open.

11 Step 4.7.3 Simulates opening SGT-V-5B2 by The control switch is pointing to S/U*

taking control switch clockwise to open.

Open SGT-V-5A1 (5B2) (Exhaust to Stack). open. The Red light is on, the Green light is off.

The red flag is displayed.

The control switch returns to center.

12 Step 4.7.4 Simulates placing the control switch The control switch is in ON, the S/U*

for SGT-EHC-1B2 clockwise to on. three blue heater lights are Place SGT-EHC-1A1 (1B2), (Main illuminated Heater control switch), to on.

13 Step 4.7.5 Observes Red light on and Green 10 seconds after the heater control S/U light out for SGT-FN-1B2. switch was manipulated, the Red Verify SGT-FN-1A1 (1B2) automatically starts approximately light is on and Green light is off for SGT-FN-1B-2.

10 seconds after heater energization.

LR000161 Rev. 11 Page 4 of 8

Time Step Task Element Performance Standard Evaluators Cue Results 14 Step 4.7.6 Observes SGT-DPIC-1B2 and The black knob is under the A on S/U verbalizes it should be in Automatic. SGT-DPIC-1B2.

Verify the following:

The red arrow lowers and is now in

SGT-DPIC-1A-1 (1B-2), Fan the green shaded area and is pointing Controller, controlling in to the thin red line.

Automatic.

SGT-DPIC-1A-1 (1B-2) maintaining a negative pressure in Observes SGT-DPIC-1B- controller SGT-DPIC-1B2 is set as you see it.

Reactor Building . set at -1.7 in.

SGT-DPIC-1A-1 (1B2) controller set at -1.7 in.

15 Step 4.7.7 Observes SGT-DPIC-1B1 and SGT-DPIC-1B1 is set as you see it.

S/U Verify SGT-DPIC-1A2 (1B1), Fan verbalizes that it should be set to controller (Lag fan) in automatic set control at -1.7 in.

at -1.7 in.

16 Step 4.8 Simulates making a plant When student starts towards the front S/U*

announcement to evacuate the panels ask what actions would be Evacuate all personnel from the Reactor Building. taken. If announcement would be reactor building before continuing in made then cue the student that the this procedure.

announcement has been made and all personnel have been evacuated from the Reactor Building.

CAUTION: Venting the Drywell through the SGT system at high Drywell pressures may rupture SGT system ducting and release the radioactivity directly into the Secondary Containment.

LR000161 Rev. 11 Page 5 of 8

Time Step Task Element Performance Standard Evaluators Cue Results 17 Step 4.9 Simulates taking the control switch The control switch is pointing to S/U*

for SGT-V-1B clockwise to open. open.

Open SGT-V- 1A (1B), (Inlet from containment). The Red light is on, the Green light is off.

The red flag is displayed.

The control switch returns to center when released.

18 Step 4.10 Simulates taking the control switch The control switch turns to open.

S/U*

Open CEP-V-1A (Drywell Exhaust for CEP-V-1A clockwise to open. The Red light is on, the Green light Outboard Isolation). is off.

The control switch returns to Norm when released.

19 Step 4.11 Simulates opening CEP-V-2A by The control switch turns to open.

S/U*

Open CEP-V-2A (Drywell Exhaust taking control switch clockwise to The Red light is on, the Green light Inboard Isolation). open. is off.

The control switch returns to Norm when released.

Termination Criteria: The student informs the CRS that Drywell venting has been started.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LR000161 Rev. 11 Page 6 of 8

RESULTS OF JPM:

EMERGENCY DRYWELL VENTING Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: All personnel have been evacuated from the Reactor Building and Emergency Drywell Venting has been initiated.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LR000161 Rev. 11 Page 7 of 8

STUDENT JPM INFORMATION CARD Initial Conditions:

A LOCA has occurred.

PPM 5.2.1 has been entered and plant conditions require containment venting.

Neither Standby Gas train is currently operating.

Initiating Cue:

The CRS directs you to vent the Drywell in accordance with PPM 5.5.15 using SGT train B.

Inform the CRS when venting of the drywell has been initiated.

THE PERFORMANCE OF THIS JPM IS SIMULATED.

CONTROL MANIPULATIONS WILL NOT BE PERFORMED.

Page 8 of 8

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE BYPASS RCIC TRIPS AND ISOLATIONS (Control Room & Plant)

LESSON LENGTH .5 HRS INSTRUCTIONAL MATERIALS INCLUDED LESSON PLAN PQD CODE Rev. No.

SIMULATOR GUIDE PQD CODE Rev. No.

JPM PQD CODE LR000218 Rev. No. 13 EXAM PQD CODE Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/21/94 REVISED BY Ron Hayden DATE 2/17/15 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE SAT Coordinator APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

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

N/A Special Setup Instructions:

This JPM starts in the Control Room and then proceeds to RCIC pump room stairwell.

JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: NONE Safety Items: Hard Hat Safety Glasses Task Number: RO-0545 Validation Time: 9 Minutes Alternate Path: No Time Critical: No PPM

Reference:

5.6.2 Rev. 2; PPM 5.5.5 Rev. 7 Location: Plant NUREG 1123 Ref: 295003 AA1.03 (4.4 / 4.4) Performance Method: Simulate Task Standard: The RCIC high area temperature isolation and the 25 psig high exhaust pressure trip have been prevented.

LR000218 Rev. 13 Page 2 of 7

JPM CHECKLIST INITIAL A station blackout has occurred. RCIC is operating normally and is restoring RPV level.

CONDITIONS:

INITIATING The CRS directs you to prevent the RCIC high area temperature isolation and the 25 psig high exhaust pressure trip per PPM 5.6.2 CUE: steps 8.2.5 and 8.2.6. Inform the CRS when RCIC high area temperature isolation and the 25 psig high exhaust pressure trip have been prevented. Control manipulations will not be performed. All actions and steps will be simulated.

Items are Critical Steps Time JPM Step Task Element Performance Standard Evaluators Cue Results THE FOLLOWING DISCUSSION SHOULD BE DONE TO OBTAIN BOTH PPM 5.6.2 AND PPM 5.5.5: NOTE:

THE EOP DRAWER IN THE CONTROL ROOM SHOULD NOT BE OPENED. A DISCUSSION OF WHERE THE PROCEDURES AND TOOLS ARE FOUND IS SUFFICIENT - PROCEDURES AND TOOLS ARE LOCATED IN THE EOP DRAWER LOCATED AT THE STEPS TO THE CRS PLATFORM. AFTER THE DISCUSSION - HAND STUDENT COPY OF EACH PROCEDURE DISCUSSED AND CUE THAT STUDENT ALSO HAS PLASTIC BAG CONTAINING REQUIRED TOOLS.

1 Simulates obtaining PPM 5.6.2 and Verbalizes where PPM 5.6.2 would Hand student PPM 5.6.2 and cue that EOP tool bag from EOP drawer. be obtained from. student also has plastic bag required S/U*

tools.

2 Step 8.2.5 Performs this step.

S/U Prevent a RCIC high area temperature isolation (160°F) and RCIC pump room area high differential temperature (50°dT) by performing the following:

3

Place test switch LD-RMS-S2A Simulates inserting key (which was The switch is turned and is pointed to TEST (RCIC-V-8 Isol Pipe Area in EOP tool bag) and turning the test to Test. S/U*

Temp) (H13-P632) (Key 117/2-632). switch, LD-RMS-S2A, clockwise to Test.

LR000218 Rev. 13 Page 3 of 7

Items are Critical Steps Time JPM Step Task Element Performance Standard Evaluators Cue Results 4

Place test switch LD-RMS-S2B to Simulates inserting key (which was The switch is turned and is pointed TEST (RCIC-V-63/76 Isol Pump in EOP tool bag) and turning the test to Test. S/U*

Area Temp) (H13-P642) (Key switch, LD-RMS-S2B, clockwise to 127/2-642). Test.

5 Step 8.2.6 Verbalizes this step.

Prevent a RCIC high exhaust S/U pressure trip (25 psig) by ensuring the trip is bypassed in accordance with PPM 5.5.5 Overriding RCIC Low RPV Pressure Isolation and High Exhaust Pressure Trip.

6 Obtains PPM 5.5.5 and EOP tool If not discussed previously, states Refer to discussion at the beginning bag. that procedure would be obtained of JPM. S/U*

from EOP drawer (none of the tools in the drawer are required for this task).

7 PPM 5.5.5 Performs this step.

S/U*

Step 4.2 If overriding the RCIC high exhaust pressure trip interlock to prevent a RCIC high exhaust pressure trip (25 psig), then perform the following:

NOTE: RCIC-PS-9A and RCIC-PS-9B and associated isolation valves are located on the North wall at the bottom of Stairway S-3 (NW stairwell) outside the RCIC Room Door.

NOTE: The two crescent wrenches necessary for the following pipe cap removal are pre-staged at RCIC-PS-9A and RCIC-PS-9B.

8 PPM 5.5.5 Simulated closing RCIC-V-756A by The handwheel has stopped rotating turning valve clockwise. in the clockwise direction. S/U*

Step 4.2.1 Close RCIC-V-756A, (RCIC-PS-9A Instrument Isolation Valve).

LR000218 Rev. 13 Page 4 of 7

Items are Critical Steps Time JPM Step Task Element Performance Standard Evaluators Cue Results 9 Step 4.2.2 Verbalizes that plant keys would be The wrenches are unlocked.

used to unlock pre-staged wrenches. S/U*

Remove the pipe cap between The pipe cap is no longer attached to RCIC-PS-9A and RCIC-V-756A. Simulates removal of the pipe cap the pipe.

using pre-staged crescent wrenches by turning it counter clockwise.

10 Step 4.2.3 Simulated closing RCIC-V-756B by The handwheel has stopped rotating turning it clockwise. in the clockwise direction. S/U*

Close RCIC-V-756B, (RCIC-PS-9B Instrument Isolation Valve).

11 Step 4.2.4 Simulates removal of the pipe cap The pipe cap is no longer attached to using pre-staged crescent wrenches the pipe. S/U*

Remove the pipe cap between by turning it counter clockwise.

RCIC-PS-9B and RCIC-V-756B.

Termination Criteria: Student informs CRS that RCIC high temperature isolation and high exhaust pressure trips have been prevented per PPM 5.6.1.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LR000218 Rev. 13 Page 5 of 7

RESULTS OF JPM BYPASS RCIC TRIPS AND ISOLATIONS Examinee (Print): _________________________________________________________________

Evaluator (Print): _________________________________________________________________

Task Standard: The RCIC high area temperature isolation and the 25 psig high exhaust pressure trip have been prevented.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LR000218 Rev. 13 Page 6 of 7

STUDENT JPM INFORMATION CARD Initial Conditions:

A station blackout has occurred.

RCIC is operating normally and is restoring RPV level.

Initiating Cue:

The CRS directs you to prevent the RCIC high area temperature isolation and the 25 psig high exhaust pressure trip per PPM 5.6.2 steps 8.2.5 and 8.2.6.

Inform the CRS when the RCIC high area temperature isolation and the 25 psig high exhaust pressure trip have been prevented.

CONTROL MANIPULATIONS WILL NOT BE PERFORMED.

ALL ACTIONS AND STEPS WILL BE SIMULATED.

Page 7 of 7

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE RESET HPCS DG MECHANICAL OVERSPEED TRIP (Plant)

MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LR001563 Rev. No. 4 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 06/04/03 REVISED BY Ron Hayden DATE 12/29/14 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE SAT Coordinator APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

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

N/A Special Setup Instructions:

N/A JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: None Safety Items: None Task Number: EO-1572; RO-1305 Validation Time: 8 Minutes Alternate Path: No Time Critical: No PPM

Reference:

SOP-DG3-SHUTDOWN Rev. 12 Location: Plant NUREG 1123 Ref: 264000 A4.04 (3.7 / 3.7) Performance Method: Simulate Task Standard: The HPCS DG mechanical overspeed trip has been reset and the Unit Mode Selector Switch is in AUTO.

LR001563 Rev. 4 Page 1 of 6

JPM CHECKLIST INITIAL The HPCS DG has tripped on mechanical overspeed.

CONDITIONS:

INITIATING The CRS directs you to reset the HPCS DG mechanical overspeed trip. Inform the CRS when the mechanical overspeed trip has CUE: been reset and the Unit Mode Selector Switch is in AUTO. Control manipulations will not be performed. All actions and steps will be simulated.

Items are Critical Steps Time Step Element Standard Cue Sat/Unsat EVALUATOR NOTE: When the student identifies that SOP-DG3-SHUTDOWN Section 5.3 (located in the book racks in the HPCS DG Room) is the procedure to be used, hand him a copy of that section.

NOTE: This section is to be performed if the diesel engine has tripped on mechanical overspeed, and is performed at the engine.

1 Step 5.3.1 Simulates turning the Unit Mode The Unit Mode Selector Switch Selector Switch clockwise to handle is pointing to MAINT. S/U*

Place the Unit Mode Sel Sw in MAINT (E-CP-DG/EP3). MAINT. The Green MAINT light is on, the Red Auto light is off.

2 Step 5.3.2 Simulates relatching the red engine The red lever moves downward and overspeed trip lever by pushing it has locked in place. S/U*

Relatch the engine overspeed trip lever by pushing it down until it down until it locks in place. The red lever has contacted the limit locks in place. (The trip lever should switch.

contact its limit switch when it is reset).

3 Step 5.3.3 Simulates depressing the black The Lockout Reset pushbutton has Lockout Reset pushbutton at E-CP- been depressed. S/U*

Reset the lockout relay by depressing the Lockout Reset pushbutton (E- DG/EP3.

CP-DG/EP3).

LR001563 Rev. 4 Page 2 of 6

LR001563 Rev. 4 Page 3 of 6

Time Step Element Standard Cue Sat/Unsat 4 Step 5.3.4 Verifies the Lockout Relay is reset The Lockout Relay handle is straight with black flag showing and verifies up and down, the black flag is S/U Verify the Lockout Relay is reset, the white light is on. displayed, and the white light above and white light (E22B-K1) is illuminated (H22-P028) (HPCS label HPCS-RLY-E22B-K1 is on.

Switchgear Room).

NOTE: DG-3 will start during the following step, if an auto initiation signal is present.

5 Step 5.3.5 Simulates turning the Unit Mode The Unit Mode Selector Switch Selector Switch counter clockwise to handle is pointing to AUTO. S/U*

Place the Unit Mode Sel Sw to AUTO.

AUTO (E-CP-DG/EP3). The Red Auto light is on, the Green MAINT light is off.

Termination Criteria: Student informs CRS that the HPCS DG mechanical overspeed trip has been reset.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LR001563 Rev. 4 Page 4 of 6

RESULTS OF JPM:

RESET HPCS DG MECHANICAL OVERSPEED TRIP Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: The HPCS DG mechanical overspeed trip has been reset and the Unit Mode Selector Switch is in AUTO.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LR001563 Rev. 4 Page 5 of 6

STUDENT JPM INFORMATION CARD Initial Conditions:

The HPCS DG has tripped on mechanical overspeed.

Cue:

The CRS directs you to reset the HPCS DG mechanical overspeed trip.

Inform the CRS when the mechanical overspeed trip has been reset and the Unit Mode Selector Switch is in AUTO.

Control manipulations will not be performed.

All actions and steps will be simulated.

Page 6 of 6

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE RESPOND TO CONTROL ROOM HVAC HIGH RADIATION (Plant) (Alt Path)

LESSON LENGTH .5 HRS INSTRUCTIONAL MATERIALS INCLUDED LESSON PLAN PQD CODE Rev. No.

SIMULATOR GUIDE PQD CODE Rev. No.

JPM PQD CODE LO001595 Rev. No. 3 EXAM PQD CODE Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/21/06 REVISED BY Ron Hayden DATE 12/29/14 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

Isolate Control Room Remote Air Intake MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

N/A JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: None Safety Items: None Task Number: RO-0114 Validation Time: 10 minutes Alternate Path: No Time Critical: No PPM

Reference:

ABN-RAD-CR Rev. 12 Location: Plant NUREG 1123 Ref: 288000A2.02 (3.7/3.8) Performance Method: Simulate Task Standard: The NW Remote Air Intake (#1) is isolated by closing WOA-V-52A and pulling fuse F4 in COHV-1.

LO001595 Rev. 3 Page 2 of 8

Isolate Control Room Remote Air Intake JPM CHECKLIST INITIAL A Reactor Building High Radiation signal is present. All automatic actions have been verified. The "B" Control Room Ventilation CONDITIONS: and Emergency Filtration systems have been secured and the "A" Control Room ventilation (WMA-FN-51A) and Emergency Filtration Fans (WMA-FN-54A) are operating. A Hi-Hi radiation alarm has been confirmed on the Northwest remote air intake (WOA-RIS-31A and WOA-RIS-311B read 5,000 CPM). No alarm is observed on the Southeast side (Both WOA-RIS-32Aand WOA-RIS-31B read normal).

INITIATING The CRS directs you to isolate both valves associated with the Northwest Remote Air Intake per ABN-RAD-CR. Notify the CRS CUE: when actions per ABN-RAD-CR have been completed for the high radiation condition. Control manipulations will not be performed. All actions and steps will be simulated.

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step Candidate is given a copy of ABN-RAD-CR that includes subsequent actions AND both attachment 7.1 and 7.2.

CAUTION : If shifting of the Control Room remote air intakes is required due to radiation concerns, it should be completed within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months of receipt of the Hi-Hi radiation alarm on Control Room remote air intake radiation monitors.

NOTE: Both Control Room remote air intakes are normally lined up to supply the Control Room.

NOTE: If both radiation monitors on one remote air intake are inoperable, then use field team survey data to determine the remote air intake with the highest radiation level.

NOTE: Only one remote intake may be isolated at any given time.

1 Step 4.1 Verbalizes step - Action completed S/U by initial conditions.

Monitor remote air intake radiation levels.

2 Step 4.2 Verbalizes step - Cue provided by S/U initial conditions.

If a HI-HI alarm is received on one or more of the remote air intake radiation monitors, then perform the following:

LO001595 Rev. 3 Page 3 of 8

Isolate Control Room Remote Air Intake

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 3 Step 4.2.1 Verbalizes step - Cue provided by S/U Determine the remote air intake with initial conditions.

the highest radiation level.

4 Step 4.2.2 Determines that Attachment 7.1 is S/U*

required to be performed.

Isolate the remote air intake with the highest radiation level per Attachment 7.1 or 7.2.

CAUTION: Operation of the CREF system with both WMA-FN-51A and WMA-FN-51B in operation, and one remote air intake isolated, can result in excessive airborne particulates inside the remote air intake ductwork, and create the inability of the CREF system to perform its design safety function 5 Attachment 7.1 Step 7.1.1 Verbalizes step - Cue provided by S/U Verify only one Control Room initial conditions.

Supply Fan (WMA-FN-51A or WMA-FN-51B) is in operation.

6 Step 7.1.2 Checks the stem position indicator The springs base plate is at the open S/U on WOA-V-51B is pointed to OPEN. pointer and the red arrow on the limit Verify WOA-V-51B is open (SE #2)

Remote intake outboard isolation. switch plate is pointing to open.

7 Step 7.1.3 Checks the stem position indicator The springs base plate is at the open S/U on WOA-V-52B is pointed to OPEN. pointer and the red arrow on the limit Verify WOA-V-52B is open (SE #2) switch plate is pointing to open.

Remote intake inboard isolation.

LO001595 Rev. 3 Page 4 of 8

Isolate Control Room Remote Air Intake

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 8 Step 7.1.4 Simulates using plant keys to unlock The lock is removed. S/U*

Unlock and close WOA-V-52A, NW the lock. The handwheel has stopped turning

(#1) Remote Intake Inboard in the direction indicated.

Simulates using hand wheel to close Isolation. WOA-V-52A. The springs base plate is at the shut pointer and the red arrow on the limit switch plate is pointing to shut.

9 Step 7.1.5 Recognizes that isolation of both S/U RAIs valves was part of initial cue If necessary to isolate both remote and performs this step.

intake valves, then perform the following:

10 Step 7.1.5a Locates valve - See Evaluators The valve is danger tagged in the S/U Cue. open position as the valves operator Unlock and close WOA-V-51A, NW is broken.

(#1) Remote Intake Outboard Isolation. The springs base plate is at the open pointer and the red arrow on the limit switch plate is pointing to open.

11 Step 7.1.5b Verbalizes step - Step cannot be If checked, the springs base plate is S/U performed due to previous step. at the closed pointer and the red Verify WOA-V-51D opens, NW (#1)

Remote Intake Purge. arrow on the limit switch plate is pointing to shut.

LO001595 Rev. 3 Page 5 of 8

Isolate Control Room Remote Air Intake

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step 12 Step 7.1.6 In panel COHV-1, simulates The indicated fuse has been S/U*

removing fuse F4 by pulling down removed.

If remote air intake # 1 is isolated and out on the white fuse holder. If student checks WOA-V-51D - the using only valve WOA-V-52A, then springs base plate is at the open remove fuse F4 in Control, Cable pointer and the red arrow on the limit Spreading and Critical Switchgear switch plate is pointing to open.

Rooms Control Panel COHV-1 (RW 525) to Open WOA-V-51D, NW (#1) Remote Intake Purge.

Termination Criteria: Student informs CRS that the NW Remote Air Intake is isolated. May add that only WOA-V-52A is closed, and Fuse F4 has been pulled.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

LO001595 Rev. 3 Page 6 of 8

Isolate Control Room Remote Air Intake RESULTS OF JPM RESPOND TO CONTROL ROOM HVAC HIGH RADIATION Examinee (Print): _________________________________________________________________

Evaluator (Print): _________________________________________________________________

Task Standard: The NW Remote Air Intake (#1) is isolated by closing WOA-V-52A and pulling fuse F4 in COHV-1.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

LO001595 Rev. 3 Page 7 of 8

STUDENT JPM INFORMATION CARD Initial Conditions:

A Reactor Building High Radiation signal is present.

All automatic actions have been verified.

The "B" Control Room Ventilation and Emergency Filtration systems have been secured and the "A" Control Room ventilation (WMA-FN-51A) and Emergency Filtration Fans (WMA-FN-54A) are operating.

A Hi-Hi radiation alarm has been confirmed on the Northwest remote air intake (WOA-RIS-31A and WOA-RIS31B read 5,000 CPM).

No alarm is observed on the Southeast side (WOA-RIS-32A and WOA-RIS31B read normal).

Initiating Cue:

The CRS directs you to isolate both valves associated with the Northwest Remote Air Intake per ABN-RAD-CR.

Notify the CRS when actions per ABN-RAD-CR have been completed for the high radiation condition.

CONTROL MANIPULATIONS WILL NOT BE PERFORMED.

ALL ACTIONS AND STEPS WILL BE SIMULATED.

Page 8 of 8

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE COLUMBIA GENERATING STATION SIMULATOR EXAMINATION Raise Power with Flow; Control Rod Exercise Surveillance - Uncoupled Rod; Complete OSP-ELEC-M701; Spurious HPCS initiation; Minimum LESSON TITLE Seismic EQ - Loss of Power to RHR-V-16A; Another MSE - Circ Water line Rupture Causes Back Pressure To Rise -Insert a Manual Scram; OBE; LOCA, DW Floor Rupture; Loss of Startup Power; RHR-P-2B Breaker Fails to Auto Close; RHR-V-16B Fails to open; Emergency Depressurize due to exceeding Drywell Temp of 330°F LENGTH OF LESSON 1.5 Hours INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code LO001801 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 10/21/14 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. 1 FORM ES-D-1 Columbia Generating Station ILC NRC Exam April, 2015 Facility: Columbia NRC Scenario No: 1 Examiners: _______________ Operators: _______________

Initial conditions: Reactor Power is 90%. Power was reduced due to economic dispatch. OSP-ELEC-M701, DG-1 monthly surveillance is in progress and completed up to step 7.3.69.

SM-1 has been transferred to TR-S. There are twenty minutes left in the run. OPS2 is in DG-1 room.

Turnover: Raise reactor power with Flow to 95% power. The reactivity brief has been performed. At that time stop the power increase and perform OSP-CRD-M701, Control Rod Exercise of Fully Withdrawn Rods (MODE 1) starting with rod 18-59 and working across from left to right and then from top to bottom until all fully withdrawn control rods have been exercised.

Concurrently, complete OSP-ELEC-M701.

Event Timeline Event Event Description No. Type*

1. T=0 R (ATC) Raise power with Flow.

2. T=0 N (BOP) Complete OSP-ELEC-M701, DG-1 Monthly Operability Test.

3. T = 10 C (ATC) Perform Control Rod Exercise surveillance - OSP-CRD-M701.

C (SRO) Second rod is uncoupled.

TS (SRO)

4. T = 25 I (BOP) HPCS Spurious Injection I (SRO)

TS (SRO)

5. T = 35 Minimum Seismic Earthquake.

RHR-V-16A loses power.

6. T = 40 C (SRO) Another Seismic Tremor.

CW Pipe Rupture outside Protected Area.

MT Back Pressure rise requiring a Reactor scram and MT Trip.

7. T = 50 M (All) Operating Basis Earthquake.

Loss of Startup Power.

Critical Task is to initiate systems required to restore RPV level back to +13 to +54 level band prior to RPV level reaching -161.

Page 2 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-1 Columbia Generating Station ILC NRC Exam April, 2015

8. T = 55 M (All) LOCA.

Drywell Floor Rupture.

C (BOP) RHR-P-2B breaker fails to auto close.

9. T = 60 C (SRO) RHR-B-16B Fails to open results in the inability to spray the Drywell.

10. T = 70 Emergency Depressurize due to High Drywell Temperature GT 330°F.

Critical Task is to initiate an Emergency Depressurization when Drywell Temperature cannot be restored and maintained LT 330°F and within 5 minutes of DW/T reaching 330°F.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 3 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 SCENARIO DESCRIPTION EVENT 1 - Power is raised to 95% with Recirc Flow.

EVENT 2 - Complete OSP-ELEC-M701 (DG-1 Monthly Operability Surveillance).

EVENT 3 - Perform OSP-CRD-M701 (Control Rod Exercise Surveillance). Control Rod 22-59 will be uncoupled when checked. Tech Specs will be referenced and the rod will be driven full in and isolated with cooling flow maintained.

EVENT 4 - Spurious HPCS injection. The HPCS pump will start and begin injecting into the reactor. The crew will take actions per ABN-LEVEL and secure the HPCS pump and close the injection valve. Tech Specs will be referenced.

EVENT 5 - Minimum Seismic Earthquake causes scaffold to fall into RHR-V-16A cubicle.

EVENT 6 - Another MSE results in a Circ Water line rupture outside the protected area. As a result, Main Turbine back pressure will start to rise. The crew should recognize that the event is not recoverable and insert a manual scram to remove the Main Turbine from service.

EVENT 7 - After the immediate scram actions have been performed, an OBE will occur causing a loss of Startup Power (and the Drywell Floor Ruptures and a LOCA to start on time delay).

EVENT 8 - LOCA, Drywell Floor Rupture and RHR-P-2B Breaker Fails to Auto Close - is closed manually and the pump starts. LOCA requires Wetwell and Drywell spray initiation.

EVENT 9 - One spray valve, RHR-V-16B does not open, which results in an inability to spray the Drywell.

EVENT 10 -Emergency Depressurize due to Drywell temperature when it cannot be restored and maintained LT 330°F.

The scenario will be terminated when RPV level is being returned to normal or as directed by the scenario coordinator.

Page 4 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 1

==

Description:==

Raise reactor power with flow to 95% power.

This event is initiated by shift turnover.

Time Position Applicants Actions or Behavior T=0 SRO Directs ATC to raise power with flow to achieve 95% reactor power at a rate not to exceed 1% per minute.

ATC Notes Reactor Power and/or Main Generator Output.

Verifies both RRC pumps individual controllers are in AUTO and depresses Master Controller Raise P/B to increase flow/power as directed.

At 95% power, stops the power increase.

Reports power/pressure and level after power increase stops.

COMMENTS:

Page 5 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 2

==

Description:==

Complete Diesel Generator 1 Monthly Operability Test, OSP-ELEC-M701.

The event is initiated by the turnover and is performed after the TSW pumps are swapped.

Time Position Applicants Actions or Behavior T = 20 BOP Step 7.3.70 - Perform the following (H13-P800):

a. Reduce reactive load to 0.2 Megavars using Diesel Gen 1 Voltage Regulator control switch. (Turns Voltage Regulator C/S to lower)

b. Gradually reduce DG-1 load to 0.2 MW, over approximately one minute period, using Diesel Gen 1 Governor control switch. (Turns Governor C/S to lower)

c. Open E-CB-DG1/7, DG-1 Output Breaker. (Places CB-DG1/7 to trip)

Step 7.3.71 -Log the time when DG-1 was unloaded.

Step 7.3.72 - Verify E-CB-DG1/7 Close Permit light is illuminated.

Step 7.3.73 - Test governor speed control using Diesel Gen 1 Governor control switch as follows (H13-P800):

a. Lower frequency to approximately 58 Hz. (Turns Governor C/S to lower)

b. Raise frequency to approximately 62 Hz. (Turns Governor C/S to raise)

c. Lower frequency to 60 Hz. (Turns Governor C/S to lower)

Step 7.3.74 - If required (monthly), then test voltage regulator control using the Diesel Gen 1 Voltage Regulator control switch as follows (H13-P800):

a. Lower voltage to the lower stop. (Turns Voltage Regulator C/S to lower until voltage stops lowering)

b. Record the voltage and field current.

c. Raise voltage to 4600V or the upper stop (whichever happens first). (Turns Voltage Regulator C/S to raise to get 4600 volts)

d. Record the voltage and field current:

e. Adjust voltage to approximately 4160 volts. (Turns Voltage Regulator C/S to lower)

Page 6 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 2 Step 7.3.75 - Verify DG-1 output voltage is 4160 volts (H13-P800).

a. If necessary, then adjust voltage using Diesel Gen 1 Voltage Regulator control switch.

Step 7.3.76 - Verify DG-1 frequency is 60 Hz (H13-P800).

a. If necessary, then adjust frequency using Diesel Gen 1 Governor control switch.

Step 7.3.77 - Place Engine Speed Selector switch to IDLE (E-CP-DG/RP1)

(Contacts OPS2 and directs placing the engine speed selector switch to IDLE).

BOOTH OPERATOR: Take LOA-DGN026 to IDLE and report completion.

Step 7.3.78 - Allow DG-1 to idle for GE 15 minutes.

COMMENTS:

Page 7 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 3

==

Description:==

Perform OSP-CRD-M701, Control Rod Exercise. Control Rod 22-59 is not coupled.

This event is initiated by shift turnover and started after Reactor Power has been raised to 95%.

Time Position Applicants Actions or Behavior NOTE TO BOP EVALUATOR - Ensure the BOP operator does NOT respond to this event.

T = 10 SRO Directs performance of OSP-CRD-M701.

ATC Performs OSP-CRD-M701 section 7.11for control rod 18-59 (coupling check OK):

Step 7.11.3 - Select the control rod to be moved (Depresses pushbutton for control rod 18-59).

Step 7.11.4 - Peer verify the correct control rod is selected.

Step 7.11.5 - Insert the control rod one notch as indicated on the Four-Rod display (Depresses and releases the insert pushbutton).

Step 7.11.6 - Verify the indicated control rod position changes during control rod movement (verifies position changes).

Step 7.11.7 - If control rod position is not available.

Step 7.11.8 - If the control rod was initially full out then perform the following:

Continuously withdraw the control rod one notch (to notch 48) as indicated on the Four Rod display (Depresses the Continuous withdraw and the Withdraw pushbuttons).

Verify the indicated control rod position changes during control rod movement.

NOTE: A valid coupling integrity check requires the ROD OVERTRAVEL annunciator (H13-P603-A7-1.8) not received when a continuous withdrawal signal is applied to the control rod drive.

Verify coupling integrity of the control rod (Rod Overtravel alarm not received).

Record stall flow on Attachment 9.2.

Verify position 48 is illuminated or verify the full out indicating light is illuminated.

Page 8 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 3 Step 7.11.9 - If the control rod was not initially full out Step 7.11.10 - If the control rod fails to settle.

Initial on Attachment 9.1 for each control rod that has been exercised satisfactorily (Steps 7.11.3 through 7.11.10) (Initials Attachment 9.1 for rod 18-59).

Step 7.11.12 - Peer verify the correct final control rod position..

Step 7.11.13 - Report any difficulties while performing the exercise Step 7.111.14 - Repeat Steps 7.11.3 through 7.11.13 for all rods to be exercised at this power level.

ATC Performs OSP-CRD-M701 section 7.11for control rod 22-59 (coupling check fails):

Step 7.11.3 - Select the control rod to be moved (Depresses pushbutton for control rod 22-59).

Step 7.11.4 - Peer Verify the correct control rod is selected.

Step 7.11.5 - Insert the control rod one notch as indicated on the Four-Rod display (Depresses and releases the insert pushbutton).

Step 7.11.6 - Verify the indicated control rod position changes during control rod movement (verifies position changes).

Step 7.11.7 - If control rod position is not available.

Step 7.11.8 - If the control rod was initially full out then perform the following:

Continuously withdraw the control rod one notch (to notch 48) as indicated on the Four Rod display (Depresses the Continuous withdraw and the Withdraw pushbuttons).

Verify the indicated control rod position changes during control rod movement.

NOTE: A valid coupling integrity check requires the ROD OVERTRAVEL annunciator (H13-P603-A7-1.8) not received when a continuous withdrawal signal is applied to the control rod drive.

Verify coupling integrity of the control rod (Rod Overtravel no alarm received).

Page 9 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 3 ATC Acknowledges ROD OVERTRAVEL alarm and refers to ARP:

Notify CRS/Shift Manager and SNE of the condition.

If in Modes 1 or 2, then perform the required actions of Tech Spec 3.1.3.

Refers the CRS to Tech Spec 3.1.3.

SRO Contacts SNE.

Declares Control Rod 22-59 inoperable.

Refers to Tech Spec 3.1.3, Control Rod Operability, and determines Condition C applies: Fully insert the inoperable control rod within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months AND disarm the associated CRD within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Directs control rod 22-59 be fully inserted.

ATC Depresses the insert pushbutton and inserts control rod 22-59 full in.

SRO May direct SOP-CRD-HCU section 5.4 be performed to isolate control rod 22-59.

ROLEPLAY: If rod has not been inserted, as SNE direct rod insertion.

ROLEPLAY: If directed to isolate control rod 22 acknowledge direction only - no simulator manipulations need to be performed.

ROLEPLAY: If asked, there are no slow or inoperable control rods.

COMMENTS:

Page 10 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 4

==

Description:==

HPCS Spurious Injection.

This event is initiated by activating TRIGGER 1 when Tech Specs for the uncoupled control rod have been referenced, or as directed by the scenario coordinator.

Time Position Applicants Actions or Behavior BOOTH OPERATOR - ACTIVATE TRIGGER 1.

T = 35 BOP Responds to annunciators and recognizes that HPCS-P-1 is running and injecting into the core.

Refers to H13-P601.A1 1-6 HPCS Actuated annunciator ARP.

SRO Acknowledge report of pump start.

Updates crew and enters ABN-LEVEL.

ATC Acknowledges RPV High level alarm.

Verifies Reactor Feed Pumps are responding to maintain RPV level.

Reports power, pressure, and level status to CRS.

SRO Per subsequent actions of ABN-LEVEL, directs verification by two independent indications that adequate core cooling exists and that mis-operation of the automatic mode exists.

Page 11 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 4 BOP Observes two RPV level indications and two containment pressure indications and reports that HPCS actuation is invalid.

SRO Directs HPCS-P-1 be stopped and HPCS-V-4 be closed.

BOP Secures HPCS-P-1 and closes HPCS-V-4.

Reports completion to CRS.

Directs DG-3 operation be verified.

SRO Refers to Tech Specs 3.5.1 Condition B.

Recognizes the event is also reportable as a single train failure.

Contacts Work Control to investigate inadvertent HPCS initiation.

Verifies RCIC operability.

May also refer to PPM 1.3.83 for protected systems.

ATC Recognizes RPV High level alarm clears.

Verifies RPV level is being controlled by RFW.

Reports power, pressure, and level status to CRS.

COMMENTS:

Page 12 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 5

==

Description:==

Minimum Seismic Earthquake - Loss of power to RHR-V-16A.

This event is initiated by ACTIVATING TRIGGER 2 after DG-1 has been placed in IDLE - BOOTH OPERATOR SEE BELOW INSTRUCTIONS Time Position Applicants Actions or Behavior BOOTH OPERATOR: Start EQ on lowest volume and run for 10 seconds total. 5 Seconds into the MSE - ACTIVATE TRIGGER 2.

T = 20 BOP Acknowledges Minimum Seismic Alarm, pulls ARP and refers CRS to ABN-EARTHQUAKE.

Investigates and reports 16 amber lights illuminated on Bd. L.

SRO Updates crew and enters ABN-EARTHQUAKE.

Directs earthquake announcement be performed.

Directs monitoring of Control Room instrumentation for evidence of increasing Drywell leakage, Drywell pressure, Drywell activity, and leak detection temperatures.

BOP Makes announcement and directs SAS (meets booth operator at booth door) to repeat on the Maintenance and Security radio channels.

BOP / Responds to RHR-A OUT OF SERVICE annunciator.

ATC Refers to ARP and BISI indications.

Recognizes RHR-V-16A has no lights lit.

Informs the CRS.

SRO Directs local investigation of RHR-V-16A breaker on MC-7B-B cubicle 7C.

ROLEPLAY - Two minutes after being sent to investigate report scaffolding has fallen into and damaged the breaker for RHR-V-16A.

COMMENTS:

Page 13 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 6

==

Description:==

Another Minimum Seismic Earthquake results in Circ Water Rupture Outside Protected Area (on a 2 minute time delay) requiring insertion of a Reactor Scram and Main Turbine Trip.

This event is initiated when ABN-EARTHQUAKE actions have been completed by ACTIVATING TRGGER 3 - BOOTH OPERATOR SEE BELOW INSTRUCTIONS.

Time Position Applicants Actions or Behavior BOOTH OPERATOR: Start EQ on lowest volume and run for 5 seconds and then ACTIVATE TRIGGER 3. Allow EQ to run another 5 seconds and then stop it.

T = 35 BOP Acknowledges Minimum Seismic Alarm - may recheck amber lights.

ROLEPLAY: Two minutes after Earthquake contact the control room as OPS 4 and report a piping break between the cooling towers has resulted in a large volume of water flowing away from the plant and out into the desert.

SRO May direct announcement concerning pipe rupture be performed.

BOP Makes announcement if directed.

Acknowledges Offgas alarms and reports rising Offgas exhaust flow.

Reports lowering MWe output and rising MT Back Pressure.

SRO Updates crew and enters ABN-BACKPRESSURE.

Sets backpressure as a key parameter.

Directs power reduction to comply with Attachment 7.1 limits. Should not reduce power to LT 840 MW as Attachment 7.1 backpressure limit lowers at that point).

SCENARIO NOTE: It takes about 7 minutes to get to a back pressure reading close to 8 in Hg and MWe to be 980 - could be longer if power is reduced in an attempt to keep plant/Main Turbine on line longer.

Page 14 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 6 SRO Determines that it is necessary to trip the Main Turbine due to rising back pressure.

Conducts a brief on pending reactor scram and Main Turbine trip.

May direct a RRC flow reduction prior to directing the Reactor Scram.

ATC Lowers Core Flow if directed.

SRO Directs ATC to insert a manual scram.

ATC 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 Power On and INSERT P/B Reports EOP entry on low RPV water level of +13.

Reports ALL RODS IN.

SRO May direct MT Trip prior to its auto trip.

Updates crew and enters PPM 5.1.1, RPV Control, on Low RPV water level (EOP entry on high RPV pressure may also be required).

Directs restoration of RPV level to +13 inches to +54 inches with Condensate and Feed system.

SRO May direct stopping all Circ Water pumps. (Note: It is anticipated that when TR-S is lost on next event that is how CW Pumps will become secured).

COMMENTS:

Page 15 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 7

==

Description:==

Operating Basis Earthquake; Loss of Startup Power (on a 10 sec. time delay)

This event is initiated by ACTIVATING TRIGGER 4 after the scram report and after EOPs have been entered and a level band has been given - BOOTH OPERATOR SEE BELOW INSTRUCTIONS.

Time Position Applicants Actions or Behavior BOOTH OPERATOR: Start EQ track on lowest volume and take 20 seconds to get to full volume.

After 5 seconds ACTIVATE TRIGGER 4. Allow EQ track to run another 5 seconds after reaching max volume and then stop it.

Critical Task is to initiate systems required to restore RPV level back to +13 to +54 level band prior to RPV level reaching -161.

T = 55 BOP Reports OBE annunciator, pulls ARP and refers SRO to ABN-EARTHQUAKE.

Investigates and reports indications on Bd. L (all red and amber lights lit).

BOP Investigates electrical boards when the Startup Transformer locks out and updates crew that Startup Transformer is locked out and SM-7 and SM-8 have been repowered by Backup Transformer and SM-4 is powered from DG-3.

SRO Due to the loss of feedwater directs RPV level restoration with RCIC and/or HPCS and/or CRD.

ATC Initiates RCIC and or HPCS using quick cards.

Restarts CRD pump using ARP.

Uses RCIC and/or HPCS to maintain RPV Level as directed.

BOP/ATC Recognizes MSIVs are closed, updates crew and takes manual control of RPV pressure at 800 to 1050 psig with SRVs.

SRO Directs RPV Pressure be maintained with SRVs with a band of 800 to 1050 psig.

(Note: With MSIVs closed, RPV level band should be -50 to +54).

Page 16 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 7 BOP/ATC Cycles SRVs as necessary to maintain RPV Pressure between 800 and 1050 psig.

SRO Directs actuations for low RPV level (+13) be verified.

BOP Verifies and reports actuations complete.

BOP/ATC Recognizes that CAS compressors are not running.

Directs OPS 3 to place FW on CAS Heat Exchanger cooling and reset and restart CAS compressors A and B BOOTH OPERATOR: Two minutes after being directed place firewater on CAS and reset and restart the CAS compressors by ACTIVATING TRIGGER 23 and report completion to control room.

COMMENTS:

Page 17 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 8

==

Description:==

LOCA (on a 4 minute time delay from Trigger 4 activation); Drywell Floor Failure; RHR-P-2B Breaker Fails to Auto Close.

This event is initiated by trigger 4 which has already been activated.

Time Position Applicants Actions or Behavior T = 55 BOP Reports Drywell pressure rising and at 1.68 psig reports EOP entry into PPM 5.2.1 (reports others as they occur - SP/T, SP/L, DW/T)

SRO Updates crew and enters PPM 5.2.1, Primary Containment Control.

Directs actuations for 1.68 psig DW/P be verified.

BOP Verifies actuations for 1.68 psig and notes RHR-P-2B is not running.

Attempts to manually start RHR-P-2B by taking the control switch to start.

Recognizes the pump does start and verifies proper operation.

Reports 1.68 actuations complete and failure of RHR-P-2B to auto start to CRS.

BOP Observes that Wetwell and Drywell pressures are approximately the same and informs the CRS of possible DW floor failure.

Reports Wetwell pressure when GT 2 psig.

SRO Directs Wetwell Sprays be initiated with RHR-P-2A or RHR-P-2B.

May direct SP Cooling be initiated.

Directs sprays be terminated before Wetwell pressure drops to 0 psig.

Page 18 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 8 BOP Initiates Wetwell sprays using quick card and opens RHR-V-27A or RHR-V-27B.

Initiates Suppression Pool Cooling using quick card (if directed) by opening RHR-V-24A or RHR-V-24B.

Reports Wetwell sprays initiated.

COMMENTS:

Page 19 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 9

==

Description:==

RHR-B Spray Line ruptured inside containment results in the inability to Spray Drywell.

This event is initiated from TRIGGER 4 which has already been activated.

Time Position Applicants Actions or Behavior T = 65 SRO Sets Key parameter of Drywell Temperature of 285°F.

BOP Reports Drywell Temperature as it approaches and when it reaches 285°F.

SRO Ensures parameters are within DSIL, WW/L LT 51, RRC pumps are stopped and directs Drywell Cooling Fans be secured.

ATC/BOP Stops Drywell Cooling Fans and reports completion to CRS.

SRO Directs Drywell sprays be initiated with RHR-P-2B.

BOP Using quick card, verifies within DSIL and takes the control switches for RHR-V-17B and RHR-V-16B to open.

Recognizes RHR-V-16B does not open and informs the CRS.

SRO Directs EO be dispatched to open RHR-V-16B.

Sets Drywell Temperature / Drywell Pressure as KEY parameters due to lack of drywell pressure/temperature response to spray initiation.

ATC/BOP Reports Drywell temperature as it rises towards 330°F.

COMMENTS:

Page 20 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 10

==

Description:==

EMERGENCY DEPRESSURIZATION required when Drywell Temperature reaches 330°F.

This event is initiated when it is determined that Drywell Temperature cannot be restored and maintained LT 330°F.

Time Position Applicants Actions or Behavior Critical Task is to initiate an Emergency Depressurization when Drywell Temperature cannot be restored and maintained LT 330°F and within 5 minutes of DW/T reaching 330°F.

T = 60 BOP Reports Drywell temperature as it approaches 330°F.

ROLEPLAY - If sent, when Drywell temperature reaches 325°F report that RHR-V-16B will not open manually and that you have contacted mechanical maintenance to help get the valve open.

SRO When Drywell Temperature cannot be restored and maintained below 330°F, determines that an Emergency Depressurization is required:

Updates crew and exits the pressure leg of PPM 5.1.1, RPV Control, and enters PPM 5.1.3, Emergency RPV Depressurization.

Directs preventing injection from low pressure ECCS pumps not required for adequate core cooling.

ATC/BOP Stops low pressure ECCS injection as required to maintain RPV level.

SRO Requests Wetwell level and when reported GT 17 feet, directs seven SRVs, ADS preferred, be opened.

ATC/BOP Opens seven ADS SRVs as directed and reports completion to CRS.

SRO Directs RPV/L maintenance -50 to +54.

Page 21 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 10 Termination Cue: The scenario will be terminated when the reactor has been Emergency Depressurized and RPV level is under control in the band of -50 inches to +54 inches or as directed by the scenario coordinator.

COMMENTS:

Page 22 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 TURNOVER INFORMATION Initial conditions: Columbia is operating at 90% power due to economic dispatch. APRM-A is bypassed due to a failed power supply.

Turnover: ATC - Raise Reactor power with flow to 95% power. The reactivity brief has been performed.

BOP - After the power increase continue with OSP-ELEC-M701, DG-1 Monthly Operability Test starting at step 7.3.70.

ATC - After the power increase has been completed, perform OSP-CRD-M701, Control Rod Exercise, starting with rod 18-59 and working across from left to right and then from top to bottom until all fully withdrawn control rods have been exercised. The reactivity brief has been performed.

Page 23 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 SIMULATOR SETUP INSTRUCTIONS Reset to IC 214 Flag all alarmed annunciators.

Depress all illuminated BISIs.

Place a blue tag on APRM-A.

Set up earthquake machine on lowest volume and paused.

Stage a phone next to DG-1 controls - ensure cord protector used on floor.

Have copy of OSP-CRD-M701 ready.

Have copy of OSP-ELEC-M701 ready.

Place Simulator in Run.

CREWS SHOULD BE GIVEN SURVEILLANCE PROCEDURES IN ADVANCE TO REVIEW - EXAM SECURITY REQUIRED.

NOTE: The CRD surveillance requires a peer check. Inform the crew that when asked for the peer check has been completed.

Page 24 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 SCHEDULE FILE

0

<ACTION>Insert malfunction MAL-RMC006-2259</ACTION>

<DESCRIPTION>ROD 2259 UNCOUPLED</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction BKR-RHR002 to FAI_AUT_CLOS</ACTION>

<DESCRIPTION>RHR-P-2B BREAKER</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction MAL-RHR009F to FAIL_AS_IS</ACTION>

<DESCRIPTION>RHR-V-16B SPRAY VALVE</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction MAL-NIS005A to DOWNSCALE</ACTION>

<DESCRIPTION>APRM-A FAILURE</DESCRIPTION>

</ITEM>

1

<ACTION>Insert override OVR-CSS001B to ON delete in 20 on event 1</ACTION>

<DESCRIPTION>HPCS MANUAL INITIATION ARMED-DEP</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction MAL-RWB001 to 0.1 delete in 10 on event 2</ACTION>

</ITEM>

0

<ACTION>Insert malfunction MOV-RHR008F after 30 to FAIL_CNTRL_PWR on event 2</ACTION>

<DESCRIPTION>RHR-V-16A LOSS OF POWER</DESCRIPTION>

</ITEM>

Page 25 of 26

Appendix D NRC Scenario No. 1 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015

0

<ACTION>Insert malfunction MAL-RWB001 to 0.1 delete in 10 on event 3</ACTION>

</ITEM>

0

<ACTION>Insert malfunction MAL-CFW003 after 120 to 2400 in 600 on event 3</ACTION>

<DESCRIPTION>CONDENSER AIR LEAK</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction MAL-RWB001 to 0.2 delete in 10 on event 4</ACTION>

</ITEM>

0

<ACTION>Insert malfunction MAL-OED001 after 10 on event 4</ACTION>

<DESCRIPTION>LOCKOUT TR-S</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction MAL-PCN006 on event 4</ACTION>

<DESCRIPTION>Drywell Floor Failure</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction MAL-RRS009A after 240 to 500000 in 600 on event 4</ACTION>

<DESCRIPTION>Steam Line break in Drywell 2 minutes after OBE</DESCRIPTION>

</ITEM>

0

<ACTION>Schedule Schedule/local.sch</ACTION>

<DESCRIPTION>Local Schedule file</DESCRIPTION>

</ITEM>

</SCHEDULE>

Page 26 of 26

INSTRUCTIONAL COVER SHEET PROGRAM OPERATIONS TRAINING COURSE TITLE COLUMBIA GENERATING STATION SIMULATOR EXAMINATION Perform SGT-B System Operability surveillance; APRM Flow Unit A fails upscale; TD-TE-4A fails upscale - RCIC Isolates; RRC-P-1A high LESSON TITLE vibrations; RRC-P-1A seals fail results in LOCA; Hydraulic ATWS; Reduced SLC flow; Lower Level; RWCU-V-4 fails to close; RFW Pumps trip; ATWS ED on Low RPV level LENGTH OF LESSON 1.5 Hours INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code LO001802 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 10/21/14 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 April, 2015 Facility: Columbia NRC Scenario No: 2 Examiners: _______________ Operators: _______________

Initial conditions: Columbia is operating 100% power. OSP-SGT-M702 is scheduled to be performed. APRM A has a failed power supply and is bypassed.

Turnover: Perform OSP-SGT-M702.

Event Timeline Event Event Description No. Type*

1. T=0 N (BOP) Perform SGT B System Operability surveillance - OSP-SGT-M702.

2. T = 05 I (ATC) APRM Flow Unit A fails upscale.

TS (SRO)

3. T=15 I (BOP) LD-TE-4A fails high causing a RCIC isolation and RCIC turbine trip.

I (SRO) RCIC-V-8 does not auto close - is closed manually.

TS (SRO)

4. T=25 R (ATC) RRC-P-1A high vibration.

Reduce reactor power with RRC flow.

5. T = 45 C (ATC) RRC-P-1A upper and lower seals fail requiring entry into single loop C (SRO) operations. When seals fail a LOCA begins and a manual reactor scram is inserted.

6. T = 55 Hydraulic ATWS.

Reduced SLC Flow.

C (ATC) RWCU-V-4 does not close - close RWCU-V-1 to isolate RWCU.

Lower RPV Level -80 to -140.

Critical Task is to inhibit ADS prior to an automatic initiation.

Critical Task is to terminate and prevent injection into the RPV with the exception of SLC, RCIC, and CRD, to establish a Lowered Level.

7. T = 50 M (All) Hydraulic ATWS; Scram/Reset/Scram not effective in inserting control rods; Control rods can be manually driven in.

Critical Task is to Insert Control Rods.

Page 2 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-1 Columbia Generating Station ILC NRC Exam April, 2015 Event Timeline Event Event Description No. Type*

8. T = 70 C (ATC) Both RFW Pumps trip and cannot be restarted.

C (SRO)

M (All) RPV level cannot be maintained due to loss of the Reactor Feed Pumps and at -183 ATWS - Emergency Depressurization is required.

Critical Task is to initiate an Emergency Depressurization when RPV water level cannot be maintained above -183 and within five minutes of RPV level reaching -183.

Critical Task is during an ATWS with an Emergency Depressurization required, stop and prevent injection except from RCIC, SLC and CRD prior to any injection occurring from that system into the RPV.

Critical Task is when RPV pressure is below MSCP and within 5 minutes of reaching MSCP, slowly inject into the RPV with Table 5 systems to return RPV level to -183 to LL.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 3 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 SCENARIO DESCRIPTION The scenario begins with Columbia operating at full power. APRM A is INOP.

EVENT 1 - Perform OSP-SGT-M702, SGT B Monthly Operability surveillance.

EVENT 2 - APRM Flow Unit A fails upscale due to failed instrument. The CRS will refer to LCS and Tech Specs for the failed flow unit.

EVENT 3 - RCIC isolation on failed temperature instrument. RCIC-V-8 does not auto close but does close when manually attempted. Tech Specs will be referenced for the RCIC isolation.

EVENT 4 - A high vibration alarm will be received for RRC-P-1A. Vibration level reports from the field will be received which require RRC-P-1A speed to be lowered and eventually stopped.

EVENT 5 - When reactor power is lowered to 97%, the lower seal for RRC-P-1A will begin to fail. When reactor power reaches 92% the upper seal for RRC-P-1A will begin to fail. This will result in a LOCA and rising Drywell pressure. A manual scram will be inserted prior to Drywell pressure reaching the automatic scram setpoint of 1.68 psig.

EVENT 6 - When the reactor is scrammed a Hydraulic ATWS occurs. SLC will be initiated but develop only 13 gpm injection flow. Additionally, RWCU-V-4 will not close automatically or manually. RWCU-V-1 can be closed to isolate RWCU system. RPV level will be lowered to -80 to -140.

EVENT 7 - Control rods will be inserted per PPM 5.5.11, Alternate Control Rod Insertion. Scram - Reset -

Scram is not effective in inserting control rods but control rods may be inserted by individually driving them.

EVENT 8 - When control rods are being manually driven in both Reactor Feedwater pumps trip due to failed high RPV level instrumentation. Signals cannot be reset which results in RFPs not being able to be restarted and causes RPV level to drop. When RPV level cannot be restored and maintained GT -183, an ATWS Emergency Depressurization will be performed. Injection will be stopped and prevented, and seven ADS SRVs will be opened. When RPV pressure reaches MSCP (188 psig), RPV injection will recommence.

The scenario will be terminated when RPV level is being maintained in the given band or as directed by the scenario coordinator.

Page 4 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 1

==

Description:==

Perform SGT B Monthly Surveillance OSP-SGT-M702.

The event is initiated by the turnover.

Time Position Applicants Actions or Behavior T=0 SRO Directs Standby Gas Treatment System B monthly operability surveillance, OSP-SGT-M702 be performed.

ROLEPLAY - If asked there are no paint fumes, etc. in SGT area and SGT integrity has been verified.

BOP Performs the following actions for OSP-SGT-M702 steps:

7.1.1 - Contacts OPS 2 and verifies no paint fumes.

7.1.2 - Contacts OPS 2 and verifies SGT integrity.

7.1.3 - Records moisture reading on SGT-MI-4B (reads zero).

7.1.4 - Verifies SGT-V-2B is open (Rx Bldg. inlet).

7.1.5 - Verifies SGT-V-3B1 is open (fan 1B2 inlet).

7.1.6 - Depresses BISI Manual Out of Service pushbutton.

7.1.7 - Informs CRS to enters SGT system B as inoperable in the TS surveillance log.

7.1.8 - Places SGT-DPIC-1B2 in MANUAL.

7.1.9 - Adjusts SGT-DPIC-1B2 output to minimum (100%).

7.1.10 - Places SGT-EHC-1B2 control switch to ON.

7.1.11 - Verifies SGT-FN-1B2 auto starts 10 sec. after heaters energize.

7.1.12 - Promptly opens SGT-V-5B2 (exhaust to stack).

7.1.13 - Slowly adjusts SGT-DPIC-1B2 to obtain 4800 CFM +/- 480CFM.

7.1.14 - Verifies Reactor Building pressure controller REA-DPIC-1A (B) responds (MAN or AUTO) to control Reactor Building pressure at approximately -0.8 WC.

7.1.15 - Records Date and Time.

Standby Gas Treatment is left in this configuration for the remainder of the scenario.

Page 5 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 1 COMMENTS:

Page 6 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 2

==

Description:==

APRM Flow Unit A fails upscale.

The event is initiated after the SGT surveillance has been started by ACTIVATING TRIGGER 1.

Time Position Applicants Actions or Behavior BOOTH OPERATOR - ACTIVATE TRIGGER 1.

T = 05 ATC Acknowledges ROD OUT BLOCK and FLOW REFERENCE OFF NORMAL alarms and refers to ARP.

Observes Flow Unit indications on P603 apron and reports APRM Flow Unit A Upscale or INOP light is lit.

SRO Refers to LCS 1.3.2.1 (7 days) and Tech. Spec. 3.3.1.1 Condition A - place in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ).

Contacts Work Control/PSRO for investigation of Flow Unit A failure.

SRO Directs bypassing Flow Unit A.

ATC Moves the Flow Unit Bypass switch to bypass Flow Unit A as directed.

Resets annunciators.

SRO Conducts Brief.

COMMENTS:

Page 7 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 3

==

Description:==

LD-TE-4A Fails upscale - Causes a RCIC System isolation.

The event is initiated after the SGT surveillance steps have been completed by ACTIVATING TRIGGER 2.

Time Position Applicants Actions or Behavior BOOTH OPERATOR - ACTIVATE TRIGGER 2.

T = 15 BOP Responds to RCIC system alarms:

RCIC DIV 1 OUT OF SERVICE; RCIC TURBINE TRIP; LEAK DET RCIC EQUIP AREA TEMP HI and HI HI.

Reports the LEAK DET RCIC EQUIP AREA TEMP HI HI annunciator is a possible EOP entry.

Refers to ARPs.

Reports that RCIC-V-1 is closed (green light on vertical panel is lit).

SRO Directs back panel investigation of Leak Detection monitors.

BOP Investigates leak detection monitors and notes LD-TE-4B is indicating 82°F (normal) and LD-TE-4A is indicating upscale (3 up arrows) and 400 °F on digital display.

Reports observations to CRS.

BOP Observes that the white light indicating DIV 1 ISOLATION SIGNAL is in.

Refers to ARP for RCIC OUT OF SERVICE and that it was caused by RCIC ISOL SIGNAL A INITIATION and refers to the that ARP.

Recognizes that the automatic actions state that RCIC-V-1 and RCIC-V-8 close and that RCIC-V-8 is still open.

Informs the CRS.

SRO Directs RCIC-V-8 be closed.

ROLEPLAY - If sent to RCIC pump room (wait two minutes) - nothing abnormal observed.

BOP Obtains key 11 and takes the control switch for RCIC-V-8 to close.

Observes RCIC-V-8 does close.

Page 8 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 3 Informs the CRS when RCIC-V-8 is closed.

Refers the CRS to Tech Spec 3.5.3.

SRO References Tech Spec 3.5.3 and notes condition A applies: Verify HPCS operable and Restore RCIC to operable status in 14 days.

refers to Tech Spec 3.3.6.1 Function 3e for LD-TE-4A failure.

Conducts brief.

COMMENTS:

Page 9 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 4

==

Description:==

High vibrations on RRC-P-1A that require the pump to be stopped.

The event is initiated after the CRS has conducted a brief for RCIC being inoperable by ACTIVATING TRIGGER 3.

Time Position Applicants Actions or Behavior BOOTH OPERATOR - ACTIVATE TRIGGER 3.

T = 25 ATC Reports RRC-P-1A High vibration alarm and references the ARP.

SRO Directs OPS 2 be dispatched to check Vibration Panel RRC-VMP-1 on 522 Rx.

Bldg.

ROLEPLAY: Two minutes after request, call 2171 and report vibrations for RRC-P-1A are:

RRC-VBI-P1A/PXY = 4 PK-G & rising slowly on both A/B channels.

RRC-VBI-P1A/PZ = 4.5 PK-G & rising slowly.

(If crew delays in lowering pump speed, call as OPS 2 and report vibration levels rising slowly at the direction of the scenario coordinator.)

COMMENTS: ARP 4.602.A6, 2-4 step 4: if casing vibration exceeds 6.0 PK-G (on PXY) then trip RRC-P-1A and enter ABN-RRC-LOSS.

SRO Directs lowering RRC-P-1A (and RRC-P-1B) speed per ARP step 2c and 2d in an effort to reduce pump vibrations.

May set a key parameter of vibrations on RRC-P-1A.

ATC Lowers RRC pump speed as directed:

Verifies pumps individual controller in Auto.

Depresses the lower pushbutton on the Master Controller to lower speed as directed.

(May also place the pumps individual controller in Manual and use it to lower pump speed).

COMMENTS:

Page 10 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 5

==

Description:==

RRC-P-1A seal failures resulting in a LOCA, rising Drywell Pressure and a Reactor Scram.

The event is active at the beginning of the scenario, but is only realized when Reactor Power reaches 97% (Trigger 4) by the failure of the lower seal for RRC-P-1A. At 92% power, the upper seal will fail (Trigger 5), which will result in rising Drywell Pressure.

Time Position Applicants Actions or Behavior T = 40 ATC While lowering pump speed, acknowledges and reports RRC-P-1A SEAL STAGING FLOW HI/LOW annunciator (4.602.A6.2-3).

Refers to ARP.

Recognizes the failure of the lower seal based on rising Upper Seal pressure.

Refers CRS to ABN-RRC-SEAL.

Directs an EO to check seal staging flow, RRC-FIS-39A.

SRO Updates crew and enters ABN-RRC-SEAL.

Sets Key Parameter of Upper Seal pressure.

ROLEPLAY: Wait 2 minutes after being directed to check RRC-FIS-39A, and then report RRC-FIS-39A indicated 5 gpm.

NOTE: If power is lowered to LE 92% the upper seal fails causing seal pressure to drop. RRC-P-1A should also be secured if upper seal pressure reaches 925 psig.

ATC As pump speed is lowered, acknowledges and reports RRC-P-1A OUTER SEAL LEAKAGE HI annunciator (4.602.A6.2-2).

Recognizes the upper seal pressure is now trending down indicating a loss of the outer seal.

Directs an EO to check outer seal leakage (RRC-FIS-2A) and seal staging flow (RRC-FIS-7A) for RRC-P-1A.

SRO Conducts brief on the impending stopping of RRC-P-1A.

Page 11 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 5 ATC Reports Upper seal pressure as it drops.

Informs the CRS when Key Parameter reached.

SRO Directs stopping RRC-P-1A by depressing the stop pushbutton.

ATCP Stops RRC-P-1A as directed by depressing the ASD stop pushbutton.

BOP Acknowledges Leak Detection Drywell Flow Drain Flow High and reports Unidentified Leakage in the drywell increasing.

Reports rising drywell pressure.

SRO Directs Reactor scram prior to the 1.68 psig auto scram.

COMMENTS:

Page 12 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 6

==

Description:==

Hydraulic ATWS. Reduced SLC flow. RWCU-V-4 does not close.

This event is active at the beginning of the scenario and is realized when a manual reactor scram is inserted.

Time Position Applicants Actions or Behavior Critical Task is to inhibit ADS prior to an automatic initiation.

Critical Task is to terminate and prevent injection into the RPV with the exception of SLC, RCIC, and CRD, to establish a Lowered Level.

T = 60 ATC Manually scrams the reactor as directed and performs immediate operator actions of PPM 3.3.1:

Places mode switch to shutdown

Monitors/reports power/level/pressure

Reports APRMs not downscale and performs the following:

Depresses the manual scram pushbuttons

Initiates ARI

Recognizes reactor power is GT 5% and performs the following:

Informs the CRS

Removes the SLC keylock switch blanks and inserts both keys in the control switches.

Initiates SLC injection by performing the following:

Places SLC System A control switch to the OPER position.

Places SLC System B control switch to the OPER position.

Insert SRMs and IRM by depressing the power on and insert pushbuttons Reports all rods not in and current reactor power.

ATC Reports initial SLC tank level of 4800 gallons and that SLC flow rate is only 13 gpm.

Directs local investigation of SLC flow low.

Page 13 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 6 ROLEPLAY - Wait three minutes and report relief valves lifting and you have contacted mechanical maintenance for assistance.

CRS Updates crew on EOP entry into PPM 5.1.1, RPV Control, and directs/verifies that the Mode Switch has been placed in SHUTDOWN.

Updates crew and exits PPM 5.1.1 (RPV Control) and transitions to PPM 5.1.2 (RPV Control - ATWS).

Directs BOP to:

Inhibit ADS and take manual control of HPCS.

Verify actuations for +13 and -50 as they occur.

Verify pressure is being maintained by the bypass valves in Auto.

BOP Takes both ADS control switches to the INHIBIT position and acknowledges associated alarms.

Arms and Depresses the HPCS system initiation pushbutton while holding the control switch for HPCS-P-1 to STOP.

Takes the control switch for HPCS-V-4 to close when it gets fully opened.

Reports ADS inhibited and manual control of HPCS taken to CRS.

CRS Directs bypassing the MSIV isolation interlocks on high tunnel temperature and low RPV level per PPM 5.5.6.

BOP Goes to EOP drawer and gets PPM 5.5.6 procedure and equipment bag containing two keys.

Performs PPM 5.5.6:

At H13-P609 places MS-RMS-S84 to BYPASS

At H13-P611 places MS-RMS-S85 to BYPASS Updates Crew on the completion of PPM 5.5.6.

Page 14 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 6 BOP Recognizes and reports EOP entry conditions due to Drywell pressure, Drywell temperature and Wetwell level (as they occur).

SRO Updates crew and enters PPM 5.2.1, Secondary Containment Control.

Establishes a key parameter: Wetwell pressure of 2 psig.

May establish a key parameter of Drywell temperature at 285°F.

BOP Reports when Wetwell pressure reaches 2 psig.

CRS Recognizes RCIC-V-1 is already closed (noted to keep Main Turbine on line).

CRS Directs performance of PPM 5.5.1, Overriding ECCS valve logic to allow throttling RPV injection.

BOP Goes to EOP drawer and pulls PPM 5.5.1 procedure and equipment bag containing 5 keys.

Performs PPM 5.5.1:

HPCS - Override HPCS-V-4 (HPCS RPV injection valve) automatic logic by placing HPCS-RMS-S25 in the OVERRIDE position (H13-P625).

LPCS - Override LPCS-V-5 (LPCS RPV injection valve) automatic logic by placing LPCS-RMS-S21 in the OVERRIDE position (H13-P629).

RHR Loop A - Override RHR-V-42A (RHR RPV injection valve) automatic logic by placing RHR-RMS-S105 in the OVERRIDE position (H13-P629).

RHR Loop B - Override RHR-V-42B (RHR RPV injection valve) automatic logic by placing RHR-RMS-S106 in the OVERRIDE position (H13-P618).

RHR Loop C - Override RHR-V-42C (RHR RPV injection valve) automatic logic by placing RHR-RMS-S107 in the OVERRIDE position (H13-P618).

Updates crew to completion of PPM 5.5.1, and that the ECCS injection valves are closed and throttleable.

Page 15 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 6 CRS Direct the ATC to:

Stop and prevent condensate and feedwater.

Lower level to a band less than -65 but greater than -183 (preferred band is -80 to -140).

Commence RPV injection at -65.

ATC Aligns the Feed and Condensate system per the quick card as follows:

Step 2.1.1 - Start closing RFW-V-112A and RFW-V-112B

Step 2.1.2 - Start opening RFW-V-118.

Step 2.1.3 - Verify RFW-V-109 is closed.

Step 2.1.4 - Verify RFW-V-117A and RFW-V-117B open.

Step 2.1.5 - Verify RFW-LIC-620 is in manual (V selected for Valve position demand) with 0 output.

Step 2.1.6 - If Reactor Feed Pumps are operating then perform the following:

a. If non-ATWS, then verify RFPs have ramped down in speed

b. Place RFW-P-1B in MDEM mode.

c. Place RFW-P-1A in MDEM mode.

d. Control Turbine speed as required.

e. If desired, then place RFW-FCV-2A (B) in manual and slowly open to approximately 80%.

Step 2.1.7 - Verify RFW-V-112A and RFW-V-112B are fully closed.

Step 2.1.8 - Verify RFW-V-118 is fully open.

Page 16 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 6

Step 2.1.9 - If Reactor Feed Pumps are operating, then adjust the running RFP speed to establish ~ 200 psid across RFW-FCV-10A & 10B using either Feedwater touch screen (H13-P840).

Step 2.1.10 - Adjust RFW-LIC-620 manual output to control RPV level.

Reports EOP entry on low RPV water level at +13.

Reports Reactor Power as it drops due to lowering level.

Maintains RPV level between -65 and -183 as directed (-80 to -140 is the preferred band).

Does not commence feeding until -65.

Comments:

Page 17 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 7

==

Description:==

Hydraulic ATWS - Insert Control Rods.

This event is active at the beginning of the scenario and is realized when a manual reactor scram is inserted.

Time Position Applicants Actions or Behavior Critical Task is to Insert Control Rods.

T = 70 SRO Directs PPM 5.5.11 be performed to insert control rods.

BOP Goes to EOP drawer and pulls procedure for PPM 5.5.11 and equipment bag.

Performs PPM 5.5.11:

Determines that no RPS scram lights are lit and:

Removes one TB1 ARI fuse (P650 F01, F02, F03 or F04)

Removes one TB2 ARI fuse (P650 F01, F02, F03 or F04).

Observes that some or all blue scram valve lights are lit and determines Tab B should be performed:

Operator Actions per TAB B:

Places the SDV HIGH LEVEL TRIP control switch to BYPASS.

Determines the scram cannot be reset.

Overrides RPS trip signals per Attachment 6.1.

Page 18 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 7 ATTACHEMNT 6.1 At H13-P611 - Installs a jumper between RPS-RLY-K9B terminal stud 2 and RPS-RLY-K12F terminal stud 4.

At H13-P611 - Installs a jumper between RPS-RLY-K9D terminal stud 2 and RPS-RLY-K12H terminal stud 4.

At H13-P609 - Installs a jumper between RPS-RLY-K9A terminal stud 2 and RPS-RLY-K12E terminal stud 4.

At H13-P609 - Installs a jumper between RPS-RLY-K9C terminal stud 2 and RPS-RLY-K12G terminal stud 4.

Continues with Tab B operator actions:

Reset the scram by depressing reset pushbuttons.

Ensures both CRD pumps are running.

Determines that CRD drive header pressure can be established and performs Attachment 6.2 to bypass all RSCS rod blocks:

At H13-P613 - Installs one jumper from terminal 7 to terminal 8 on Baily Alarm Card AHH.

At H13-P613 - Installs one jumper from terminal 7 to terminal 8 on Baily Alarm Card AGG.

Places the RWM bypass switch to bypass on H13-P603.

Manually starts to drive control rods by starting at 10-43 and inserting every other rod in every other row.

Reports success in driving control rods to CRS.

Page 19 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 7 When the Scram Discharge Volume has been drained for more than 2 minutes initiates a manual scram by depressing the four red manual scram pushbuttons.

If all rods did not insert, continues scram/reset/scram Tab B and raises SDV drain time by 2 minutes.

Determines no control rod motion and requests drain time extension.

Comments:

Page 20 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 8

==

Description:==

Both Reactor Feedwater Pumps trip after manual insertion of control rods, or as determined by the scenario coordinator, which requires an Emergency Depressurization when RPV Level drops to -183.

The event is initiated after control rods are being driven in per PPM 5.5.11 or as determined by the scenario coordinator by ACTIVATING TRIGGER 7.

Time Position Applicants Actions or Behavior BOOTH OPERATOR - ACTIVATE TRIGGER 7.

Critical Task is to initiate an Emergency Depressurization when RPV water level cannot be maintained above -183 and within five minutes of RPV level reaching -183.

Critical Task is during an ATWS with an Emergency Depressurization required, stop and prevent injection except from RCIC, SLC and CRD prior to any injection occurring from that system into the RPV.

Critical Task is when RPV pressure is below MSCP and within 5 minutes of reaching MSCP, slowly inject into the RPV with Table 5 systems to return RPV level to -183 to LL.

T=60 ATC Reports reactor power as it drops due to lowering RPV level.

Responds to RFW Trip Annunciators and recognizes that both Reactor feedwater pumps have tripped.

Attempts to reset both pumps by taking the EMERG TRIP/RESET switch to reset but recognizes neither will reset and informs the CRS.

SRO Directs all injection flow be maximized.

Conducts brief/update.

May set a Key Parameter of RPV level.

ATC Reports RPV level as it drops.

Reports Key Parameter met (if key parameter was established) or reports RPV level at TAF.

SRO Updates crew and exits the pressure leg of PPM 5.1.2, RPV Control - ATWS, and enters PPM 5.1.5, Emergency RPV Depressurization - ATWS.

Enters leg Y of PPM 5.1.2, RPV Control - ATWS.

Page 21 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 8 SRO Directs stop and preventing all injection into the RPV except RCIC, SLC, and CRD.

Determines Wetwell level is GT 17 and directs seven ADS SRVs be opened.

BOP Opens 7 ADS SRVs as directed.

Observes containment response as each SRV is opened.

Reports 7 ADS SRVs are opened and RPV pressure dropping.

SRO Seta a Key Parameter of MSCP of 188 psig.

BOP Informs CRS when MSCP is reached.

SRO Directs RPV level be returned to -80 to -140 level band (dont go GT -65) using Table 5 systems: Condensate, RCIC, CRD, RHR A/B via SDC and SLC.

ATC Commences to feed the RPV using Condensate Booster pumps to level band given.

COMMENTS:

Page 22 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 TURNOVER INFORMATION Initial Conditions:

Columbia is operating 100% power.

OSP-SGT-M702 is scheduled to be performed.

APRM A has a failed power supply and is bypassed.

Turnover:

Perform the Standby Gas Treatment B System Monthly Operability surveillance, OSP-SGT-M702.

Page 23 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 SIMULATOR SETUP INSTRUCTIONS Reset to IC-213.

Hang a blue Equipment Tag on the Bypass Switch for APRM A/C/E in the A position on H13-P603.

Have surveillance ready for each crew.

Page 24 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 SCHEDULE

1

<ACTION>Insert malfunction PMP-SLC001F to 60</ACTION>

<DESCRIPTION>SLC-P-1A REDUCED FLOW</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction PMP-SLC002F to 100</ACTION>

<DESCRIPTION>SLC-P-1B REDUCED FLOW</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-CRD007A1 to 100</ACTION>

<DESCRIPTION>HYDRAULIC ATWS EAST SDV BLOCKAGE</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-CRD007B1 to 100</ACTION>

<DESCRIPTION>HYDRAULIC ATWS WEST SDV BLOCKAGE</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-CRD007A2 to 80</ACTION>

<DESCRIPTION>HYDRAULIC ATWS EAST SDV</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-CRD007B2 to 80</ACTION>

<DESCRIPTION>HYDRAULIC ATWS WEST SDV</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-NIS005A to DOWNSCALE</ACTION>

Page 25 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015

<DESCRIPTION>APRM-A FAILURE</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MOV-RWU010F to FAIL_AS_IS</ACTION>

</ITEM>

1

<ACTION>Insert malfunction MOV-RCI016F to FAIL_AUTO_CLOSE</ACTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-NIS006A to UPSCALE on event 1</ACTION>

<DESCRIPTION>APRM FLOW UNIT A FAILS</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction XMT-SCN068A to 700 on event 2</ACTION>

<DESCRIPTION>LD-TE-4A FAILS HIGH</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction ANN-602A6B04 to ON on event 3</ACTION>

<DESCRIPTION>RECIRC A MOTOR VIB HIGH ANNUNCIATOR</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-RRP001A to 2 in 600 on event 4</ACTION>

<DESCRIPTION>RRC-P-1A LOWER SEAL FAILS</DESCRIPTION>

</ITEM>

1

Page 26 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015

<ACTION>Insert malfunction ANN-602A6B03 to ON on event 4</ACTION>

<DESCRIPTION>RECIRC A PUMP SEAL STAGING FLOW HIGH/LOW</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-RRP001C after 1 to 40 in 120 on event 5</ACTION>

<DESCRIPTION>RRC-P-1A UPPER SEAL FAILS</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction ANN-602A6B02 to ON on event 5</ACTION>

<DESCRIPTION>RECIRC A PUMP OUTER SEAL LEAKAGE HIGH</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-RRS004A to 0.5 in 900 on event 6</ACTION>

<DESCRIPTION>RECIRC LINE RUPTURE</DESCRIPTION>

</ITEM>

1

<ACTION>Insert override OVR-FPT002B to ON on event 7</ACTION>

<DESCRIPTION> RFW A EMERG TRIP C/S TO ON</DESCRIPTION>

</ITEM>

1

<ACTION>Insert override OVR-FPT007B to ON on event 7</ACTION>

<DESCRIPTION>RFW B EMERG TRIP C/S TO ON</DESCRIPTION>

</ITEM>

1

<ACTION>Schedule Schedule/Local.sch</ACTION>

</ITEM>

Page 27 of 28

Appendix D NRC Scenario No. 2 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015

1

<ACTION>Event Events/LO001802.evt</ACTION>

</ITEM>

</SCHEDULE>

EVENT

<EVENT>

</EVENT>

Page 28 of 28

INSTRUCTIONAL COVER SHEET PROGRAM OPERATIONS TRAINING COURSE TITLE COLUMBIA GENERATING STATION SIMULATOR EXAMINATION DG-3 Monthly Surveillance, Failure of HPCS-P-2; Control Rod drifts in; FWH-6B High Level Trip; DEH Leak Requiring Scram;, Lockout of TR-S; LESSON TITLE DG-1 and DG-2 Fail to Auto Start; LOCA; ED on low RPV Water Level LENGTH OF LESSON 1.5 Hours INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code LO001803 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 10/21/14 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. 3 FORM ES-D-1 Columbia Generating Station ILC NRC Exam April, 2015 Facility: Columbia NRC Scenario No: 3 Examiners: _______________ Operators: _______________

Initial Conditions: 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 7.3.31.

Event Timeline Event Event Description No. Type*

1. T=0 N (BOP) Synchronize and load DG-3 per monthly surveillance OSP-ELEC-M703.

2. T = 05 C (ATC) Control Rod 06-43 Drifts In.

C (SRO) SRO - Tech Spec.

TS (SRO)

3. T = 15 C (BOP) Failure of HPCS-P-2 requiring manual trip of DG-3.

TS (SRO)

SRO - Tech Spec.

C (ATC) High Level Trip of FWH-6B requiring reducing core flow to LE 92 Mlbm/hr.

4. T = 25 C (SRO) Rod Line GT 100% requiring using Fast Shutdown Sequence to insert control rods to lower rod line.

R (ATC)

M (All) DEH Leak - eventually requires a manual scram be inserted.

5. T = 45 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 and prior to the MT tripping.

6. T = 55 C (ATC) TR-S Lockout; MSIVs close; Initiate RCIC/CRD for level control.

C (BOP)

C (SRO)

7. T = 60 I (BOP) DG-1 and DG-2 Fails to Auto Start.

Page 2 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-1 Columbia Generating Station ILC NRC Exam April, 2015 Event Timeline Event Event Description No. Type*

8. T = 65 M (All) LOCA - Spray wetwell and drywell.

9. T = 70 RPV level drops to TAF. Initiate Emergency Depressurization on low RPV Level and return level to normal with low pressure ECCS pumps.

Critical Task is to initiate Drywell Sprays when Wetwell Pressure exceeds 12 psig, prior to exceeding PSP and after verifying DSIL and RHR not required for adequate core cooling.

Critical Task is to initiate an Emergency Depressurization after RPV water level reaches TAF and within 5 minutes of level dropping below -161 inches.

Critical Task is to ensure RPV water level restoration and maintenance above TAF when low pressure ECCS is available and within 5 minutes of ECCS becoming available for injection.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 3 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 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.

EVENT 1 - The BOP operator will continue with this surveillance and sync DG-3.

EVENT 2 - Control rod 06-43 drifts into the core. The ATC operator will select the rod and drive it full in. Tech Specs will be referenced.

EVENT 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.

EVENT 4 - 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).

EVENT 5 - 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.

EVENT 6 - 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.

EVENT 7 - 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.

EVENT 8 - 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.

EVENT 9 - RPV level will eventually drop to LT -161 and an Emergency Depressurization will be initiated to facilitate feeding with low pressure ECCS pumps.

The scenario will be terminated when RPV level is being returned to normal band and sprays have been re-initiated as appropriate.

Page 4 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 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 7.3.32.

BOP (N) Performs the following per steps in OSP-ELEC-M703:

Step 7.3.32 - Places the CB-4DG3 Sync Selector Switch to D. GEN/BUS.

7.3.33 - Raises voltage using the Voltage Regulator until Incoming voltage is higher than Running voltage.

7.3.34 - PDIS is not available.

7.3.35 - Takes the Governor control switch to raise until the synchronizing scope is running Slow in the Fast direction.

7.3.36 - When the synchronizing scope is 5 minutes before the 12 oclock position, places the control switch for CB-4/DG3 in the close position and:

Verifies CB-4/DG3 closes

Lowers KVARS to zero or slightly positive by turning the Voltage Regulator to lower.

Ensures load is GE 100 KW taking the Governor control switch to raise.

7.3.37 - Loads DG-3 to 1300 KW over 30 seconds using the Governor control switch.

7.3.38 - Adjusts KVARS to 350 out using the Voltage Regulator control switch.

Page 5 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 1

7.3.39 - Places the CB-4/DG3 Synchronizing scope selector switch to off.

7.3.40 - Notifies Munro that DG-3 is synchronized to the grid.

7.3.41 - Waits two minutes

7.3.342 - Contacts OPS3 to verify DEA-FN-31 and DMA-FN-31 start.

7.3.43 - Loads DG-3 to 2340 KW and LE 2600 KW over 30 seconds using the Governor control switch.

7.3.44 - Adjusts KVARS to 650 out using the Voltage Regulator control switch.

7.3.45 - Logs the time.

COMMENTS:

Page 6 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 2

==

Description:==

Control Rod 06-43 Drifts In.

This event is initiated when the BOP operator has commenced the HPCS DG surveillance and CB-4/DG3 has been closed, and is initiated by activating TRIGGER 1.

Time Position Applicants Actions or Behavior BOOTH OPERATOR - ACTIVATE TRIGGER 1.

T = 05 ATC Acknowledges Rod drift annunciator and informs the CRS.

Scans Full Core display to identify the drifting rod or refers to Rod Worth Minimizer to identify the drifting control rod.

Identifies control rod 06-43 as the drifting control rod.

SRO Updates crew and enters ABN-ROD.

ATC Per immediate actions of ABN-ROD:

Selects control rod 06-43 and recognizes the rod is drifting into the core.

Depresses the Continuous Insert pushbutton.

Drives control rod 06-43 to its full in position.

Releases the continuous insert pushbutton and observes the rod remains full in.

Informs the CRS that control rod 06-43 has been driven to its full in position and remains there with the continuous insert pushbutton released.

SRO Directs drift annunciator be reset.

Contacts SNE to initiate a Mon Run (may initiate one manually).

ROLEPLAY: When asked for a Mon Run inform the CRS that no thermal limits have been exceeded.

Page 7 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 2 Refers to Tech Spec 3.1.3 and recognizes condition C applies: Fully insert the control rod within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and Disarm the associated CRD in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

May direct control rod 06-43 be isolated with cooling maintained.

ROLEPLAY: If directed to isolate the rod - acknowledge direction only - no simulator actions are required.

COMMENTS:

Page 8 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 3

==

Description:==

Failure of HPCS-P-2 (DG-3 Service Water pump).

This event is initiated after DG-3 KVARS have been raised to 650 and the Tech Specs for the drifting control rod have been referenced and is initiated by activating TRIGGER 2.

Time Position Applicants Actions or Behavior BOOTH OPERATOR - ACTIVATE TRIGGER 2.

T = 10 BOP Acknowledges alarms associated with the loss of HPCS-P-2.

Scans panel and recognizes HPCS-P-2 is not running and SW-V-29 is going closed.

Informs CRS of loss of HPCS-P-2.

May give ABN reference and state that a local trip of DG-3 is required (immediate action of ABN-SW).

May direct OPS 4 investigate loss of the Service Water 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 - NO fire.

If requested, there is nothing obviously wrong at the breaker.

SRO Updates crew and enters into ABN-SW.

Directs BOP to have DG-3 tripped at the local panel (if not already performed).

BOOTH OPERATOR - 30 seconds after request to trip DG-3, activate TRIGGER 20 and inform the control room that DG-3 has been tripped locally.

Page 9 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 3 SRO Contacts Work Control/ 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 PPM 1.3.83.

COMMENTS:

Page 10 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 4

==

Description:==

High Level Trip of High Pressure Feedwater Heater 6B.

This event is initiated when the Tech Specs for HPCS have been referenced and is initiated by activating TRIGGER 3. It takes 30 seconds to get alarm).

Time Position Applicants Actions or Behavior BOOTH OPERATOR - ACTIVATE TRIGGER 3.

T = 30 ATC 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 that the controllers are responding but that level in FWH 6B is still high and cannot be controlled.

ATC 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 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 416°F and final temp is about 393°F).

Recognizes that 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 92 Mlbm/hr prior to RO reducing to LT 3486 MWT.)

Page 11 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 4 SRO Updates crew and enters ABN-POWER, ABN-CORE, and ABN-FWH-Hi/Level-trip and directs RRC flow be lowered to LE 92 Mlbm/hr core flow (should provide a target flow) per subsequent actions of ABN-POWER.

Directs control rods be inserted per the fast shutdown sequence to maintain below the 100% rod line.

Ensures plant operating in acceptable region of Attachment 7.1.

When conditions are stable may request a Mon Run.

ROLEPLAY: If a Mon Run is requested, inform the CRS that no thermal limits have been violated.

ATC Reduces core flow to LE 92 Mlbm/hr (if GT 92 Mlbm/hr). Reports Power, Pressure and Level after the flow reduction.

Refers to the Fast Shutdown Sequence and inserts control rods starting at first page to reduce the rod line LT 100% (should only take 2 or 3 rods to lower rod line).

Reports Power, Pressure and Level after the flow reduction and rod insertion.

COMMENTS:

Page 12 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 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 control rods have been inserted 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 and prior to the MT tripping.

T = 45 BOP Acknowledges DEH Reservoir Level Low annunciator and refers to ARP.

Notes time the DEH Level Low alarm annunciated.

Directs OPS3 to investigate locally and report level on DEH-LG-17.

Refer CRS to ABN-DEH-LEAK.

Updates crew and enters ABN-DEH-LEAK.

SRO Directs filling the DEH reservoir per SOP-DEH-OPS and look for DEH leaks.

Starts 15 minute clock for step 4.1.1 of ABN-DEH-LEAK.

May direct camera tour in an attempt to locate 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 requires a manual scram.

If asked to fill reservoir report that efforts are being performed to fill the reservoir.

BOP Acknowledges DEH Reservoir Level Low Low annunciator and refers to ARP (It takes 11 minutes from low level alarm to get low-low alarm).

SRO May direct flow reduction to 60 mlbm prior to scram.

Directs manual scram; trip of Main Turbine, and trip of Main Generator per step 4.1.1 of ABN-DEH-LEAK.

Page 13 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 5 Lowers RRC flow if directed.

RO Announces Listen up for the scram report and:

Places MODE switch to shutdown

Reports APRM downscales, RPV pressure and trend and RPV level and trend.

Inserts IRMs and SRMs.

Reports EOP entry on low RPV level.

Reports all rods in.

May, based on DEH system status, initiate a trip of the Main Turbine (if not BOP automatically completed) by depressing the two Turbine trip pushbuttons.

May, based on DEH system status, initiate a trip of the Main Generator (if not automatically complete) by depressing the two red Unit Emergency and Unit Overall Emergency pushbuttons.

Updates crew and enters PPM 5.1.1, RPV Control, on low RPV water level.

SRO BOOTH OPERATOR - When the MT trips, remove DEH annunciator malfunctions on ANN-820B1F07 and ANN-820B1G07 (DEH Low and Low Low annunciators).

COMMENTS:

Page 14 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 6

==

Description:==

Lockout of the Startup Transformer. MSIVs close, Initiate RCIC and start CRD.

This event is automatically initiated when CB-S1 breaker closes.

Time Position Applicants Actions or Behavior T = 55 Investigates electrical board status when lights go out after TR-S lockout.

BOP Notes no power to SM-1, SM-2, SM-3, SH-5 or SH-6 and notes Lockout on TR-S alarm. Checks TR-S indications and recognizes no voltage on the bus.

Notes TR-B is powering SM-7 and SM-8.

Updates crew on plants electrical board status.

BOP Recognizes MSIVs have closed and updates crew that pressure control with SRVs at a pressure band of 800 to 1050 psig.

SRO Directs pressure control with SRVs at a pressure band of 800 to 1050 psig.

Working down the level leg of PPM 5.1.1, recognizes no high pressure injection sources are running.

Directs RCIC and CRD be initiated and injection to RPV at a level band of

-50 to +54.

BOP Using the quick card, Arms and Depresses RCIC Manual Initiation pushbutton and verifies injection at 600 gpm (May increase injection flow to 700 gpm later in the scenario).

Starts the CRD pumps as directed.

May direct ABN-CRD-MAXFLOW be performed to facilitate running both CRD pumps.

Page 15 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 5 BOOTH OPERATOR - If requested, wait 3 minutes and then activate TRIGGER 26 to place both CRD suction and discharge filters on line and report completion to control room.

BOP Recognizes no CAS air compressors are running and 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.

COMMENTS:

Page 16 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 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 active from the beginning of the scenario and is realized 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 When TR-S locks out when actuations are verified, recognizes that neither DG-1 BOP (C) 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 OPS2 verify DG operation after starting.

ROLEPLAY - After requested, wait 5 minutes and report DG 1 and DG2 operating normally.

COMMENTS:

Page 17 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 8

==

Description:==

LOCA - Initiate Containment Sprays (Note: It takes about 13 minutes after the MT trips to get to TAF and 35 more seconds to get to -183).

This event is initiated automatically one minute after the MSIVs close.

Time Position Applicants Actions or Behavior Critical task is to initiate Drywell Sprays when Wetwell Pressure exceeds 12 psig, prior to exceeding PSP and after verifying DSIL and RHR not required for adequate core cooling.

T = 65 ATC/BOP Recognizes rising DW Pressure and reports EOP entry at 1.68 psig.

Also reports additional primary containment EOP entries as they occur (DW/T and SP/L).

SRO Updates crew and enters PPM 5.2.1, Primary Containment Control and re-enters 5.1.1, RPV Control, due to high DW pressure.

Directs actuations be verified for +13 and 1.68 psig.

ATC/BOP Reports wetwell pressure when it reaches 2 psig.

SRO Directs wetwell sprays with RHR. Directs securing sprays before Wetwell pressure drops to zero psig.

May set a Key Parameter of wetwell pressure of 12 psig and drywell temperature of 285°.

BOP Using quick card, initiates wetwell sprays and supplements with wetwell cooling (if directed) and reports completion to CRS.

BOP Reports wetwell pressure when it reaches 12 psig and when drywell temperature reaches 285°.

SRO Directs drywell cooling fans be secured.

BOP Secures drywell cooling fans as directed and reports completion.

Page 18 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 8 SRO Directs DSIL verification and then drywell sprays be initiated. Directs securing sprays before drywell pressure drops to zero psig.

BOP Verifies within DSIL and using quick card, initiates drywell sprays as directed.

Observes drywell pressure drop and reports sprays effective.

COMMENTS:

Page 19 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 9

==

Description:==

LOCA (Note: It takes about 13 minutes after the MT trips to get to TAF and 35 more seconds to get to -183).

This event is initiated automatically (using Event Trigger 10) when Startup power closes in on SM-1.

Time Position Applicants Actions or Behavior T = 70 ATC Reports RPV level dropping even with RCIC and CRD running.

Gives RPV level reports as level continues to lower.

SRO Directs SLC initiation.

Directs ADS be inhibited when ADS timers initiate.

As level drops, expands RPV level band.

ATC Initiates SLC per quick card and informs CRS when completed.

BOP/ATC 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 CRS.

BOP/ATC Reports RPV level as it transitions from Wide Range to Fuel Zone indicators.

Reports RPV level at TAF and trend continues down slow.

Page 20 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 9

==

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 after RPV water level reaches TAF and within 5 minutes of level dropping below -161 inches.

Time Position Applicants Actions or Behavior SRO Determines that Emergency Depressurization is required.

Updates crew and exits the pressure leg of PPM 5.1.1, RPV Control, and enters PPM 5.1.3, Emergency Depressurization, and determines wetwell level GT 17.

Directs 7 ADS SRVs be opened.

BOP Opens 7 ADS SRVs as directed.

SRO Directs wetwell and drywell sprays and suppression pool cooling be secured to facilitate RPV injection.

BOP Secures drywell and wetwell sprays and Suppression Pool cooling as directed.

Allows ECCS injection valves to open at 470 psig.

Reports RPV injection as it occurs.

Reports RPV level rising and again when GT TAF (-161 inches).

Page 21 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 9 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).

BOP/ATC Secures injection systems as directed to return RPV level to -50 to +54 band.

Reinitiates wetwell and drywell sprays as appropriate using quick card.

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.

Page 22 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 TURNOVER INFORMATION Initial Conditions:

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 7.3.31.

Page 23 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 SIMULATOR SETUP Reset to IC-212.

Have HPCS DG Surveillance signed off thru step 7.3.31.

Ensure sign at SRO desk indicates a Division 3 work week.

Flag locked in annunciators.

Page 24 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 SCHEDULE FILE

1

<ACTION>Insert malfunction MAL-DGN007B</ACTION>

<DESCRIPTION>DG2 UV - FAIL AUTO START</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-DGN006B</ACTION>

<DESCRIPTION>DG2 ECCS - FAIL AUTO START</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-DGN006A</ACTION>

<DESCRIPTION>DG1 ECCS - FAIL AUTO START</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-DGN007A</ACTION>

<DESCRIPTION>DG1 UV - FAIL AUTO START</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-RMC004-0643 to IN on event 1</ACTION>

<DESCRIPTION>ROD 0643 DRIFTS</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction PMP-SSW001S on event 2</ACTION>

<DESCRIPTION>HPCS-P-2 SHAFT SEIZURE</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction AOV-FWH050F to CLOSE on event 3</ACTION>

<DESCRIPTION>HD-LCV-6B2 RFW-HX-6B LEVEL CONTROL DUMP VLV</DESCRIPTION>

</ITEM>

1

Page 25 of 26

Appendix D NRC SCENARIO No. 3 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015

<ACTION>Insert malfunction AOV-FWH049F to CLOSE on event 3</ACTION>

<DESCRIPTION>HD-LCV-6B1 RFW-HX-6B LEVEL CONTROL VALVE</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction ANN-820B1F07 to ON on event 4</ACTION>

<DESCRIPTION>DEH RESVR LEVEL LOW ALARM</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction ANN-820B1G07 after 660 to ON on event 4</ACTION>

<DESCRIPTION>DEH RESVR LEVEL LOW-LOW ALARM</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-OED001 on event 10</ACTION>

<DESCRIPTION>TR-S LOCKOUT</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-RRS004B to 2 in 900 on event 10</ACTION>

<DESCRIPTION>RECIRC LINE RUPTURE</DESCRIPTION>

</ITEM>

1

<ACTION>Schedule Schedule/Local.sch</ACTION>

</ITEM>

1

<ACTION>Event Events/LO001803.evt</ACTION>

</ITEM>

</SCHEDULE>

EVENT FILE

<EVENT>

</EVENT>

Page 26 of 26

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE COLUMBIA GENERATING STATION SIMULATOR EXAMINATION Start CW-P-1A; Raise power with flow; RHR-RLY-K112C fails and RHR-V-42C opens; SDV level instrument fails, Half scram, 2 control rods LESSON TITLE scram, one not full in; Steam Leak Main Steam Tunnel; Partial Electric ATWS, Pull fuses to insert rods, SLC fails to initiate; CB-S1 fails to auto close; Main Steam Tunnel leak gets larger and spreads to a second area; Emergency Depressurize when 2 Areas GT Max Safe LENGTH OF LESSON 1.5 Hours INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code LO001804 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 10/21/14 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. 4 FORM ES-D-1 Columbia Generating Station ILC NRC Exam April, 2015 Facility: Columbia NRC Scenario No: 4 Examiners: _______________ Operators: _______________

Initial conditions: Reactor Power is 90%. Power was reduced due to CW-P-1B not being available. The work on CW-P-1B has been completed. OPS4 is standing by in the CWPH for a start of CW-P-1B Turnover: Start CW-P-1B. After the pump start, raise reactor power with flow to 100%. The reactivity brief has been performed.

Event Timeline Event Event Description No. Type*

1. T=0 N (BOP) Start CW-P-1B.

2. T=5 R (ATC) Raise power with Flow.

3. T = 10 I (BOP) RHR-RLY-K112C Fails and RHR-V-42C opens.

I (SRO)

TS (SRO)

4. T = 20 I (ATC) Scram Discharge Volume level instrument fails - Half Scram.

I (SRO)

TS (SRO) 2 Control Rods Scram but one does not go full in.

5. T = 35 M (All) Main Steam Tunnel steam leak - Insert a manual reactor scram.

One Main steam line does not isolate.

6. T = 40 C (ATC) Electric ATWS - B RPS side - Pull fuses to insert control rods.

I (BOP)

SLC fails to initiate.

Critical Task is to insert control rods.

7. T = 60 C (BOP) CB-S1 Fails to auto close - closed manually - repower SL-11.

8. T = 70 C (SRO) Main Steam Tunnel steam leak gets larger and spreads to another area.

9. T = 70 Emergency Depressurize when 2 Areas GT Max Safe Temperatures.

Critical task is to initiate an EMERGENCY DEPRESSURIZATION when 2 Areas have exceeded their Max Safe Operating Temperatures and within 5 minutes of establishing that the second areas temperature has exceeded its MSOT.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 SCENARIO DESCRIPTION EVENT 1 - Start CW-P-1B.

EVENT 2 - Power will be raised to 100% with Flow.

EVENT 3 - The next event is a failure of RHR-RLY-K112C which is the RHR-V-42B/C Open Permissive relay. The crew will respond and find RHR-V-42C going open. The crew will manually close RHR-V-42C.

The CRS will refer to Tech Specs and declare RHR-C Inoperable and refer to the instrumentation Tech Spec for RHR-RLY-1K112C.

EVENT 4 - The next event is a failure of a Scram Discharge Volume level switch high which causes a half scram on A RPS. Due to failed fuses on the B RPS side, two control rods will scram but only one goes full in. Control rod 30-03 stops at position 10. The crew will enter ABN-ROD and reduce reactor power with flow to LE 80 Mlbm/hr. Control rod 30-03 will be manually driven full in. Tech Spec for the control rod and SDV level switch will be referenced.

EVENT 5 - The next event is a steam leak in the Main Steam Tunnel. As temperatures rise the crew will determine the MSIVs will eventually close and a manual reactor scram will be inserted. When the isolation for high Main Steam Tunnel temperature occurs, both the inboard and outboard MSIVs on the A Main Steam line do not close.

EVENT 6 - When the scram is inserted, only about one quarter of the control rods will insert due to a partial Electric ATWS on the B RPS side (A RPS is tripped due to the SDV instrument failure). When SLC is started the systems will not initiate. The crew will pull RPS fuses and all control rods will insert.

EVENT 7 - When the Main Turbine trips the startup breaker for SM-1 will not auto close. Actions will be taken to manually close the S1 breaker and then to repower SL-11.

EVENT 8 -The Main Steam line steam leak gets bigger and spreads to a second area.

EVENT 9 - The crew will Emergency Depressurize the RPV when two areas are greater than their Max Safe Operating temperatures.

The scenario will be terminated after the Emergency Depressurization has been performed.

Page 3 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 1

==

Description:==

Start CW-P-1B per SOP-CW-START.

This event is initiated by shift turnover.

Time Position Applicants Actions or Behavior T=0 SRO Directs the start of CW-P-1B per SOP-CW-START.

BOP Performs SOP-CW-START Section 5.3 actions as follows:

5.3.1 - No actions

5.3.2 - Verifies section 5.1 complete.

5.3.3 - Contacts OPS4 to verify upper and lower motor bearing lube oil levels OK.

5.3.4 - Contacts OPS4 and verifies motor air ports free of obstructions.

5.3.8 - Verifies CWPH bay level between 441 (23) and 445 elevation (27).

5.3.9 - Places C/S for CW-V-13B and TSW-V-115B to OPEN and when valves start to open releases switch.

5.3.10 - Observes blue ready to start light on.

5.3.12 Makes plant announcement of CW-P-1B start.

5.313 - Places CW-P-1B C/S to START (verifies pump starts, discharge valve opens, and CW-V-13B and TSW-V-115B close).

Acknowledges CW PMP B DISCH NOT FULL OPEN alarm.

Informs CRS that CW-P-1B is running.

COMMENTS:

Page 4 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 2

==

Description:==

Raise Power with Flow to 100%.

This event is initiated by shift turnover.

Time Position Applicants Actions or Behavior T=5 SRO Directs ATC to raise power with flow to achieve 100% reactor power at 1% per minute (1 Hz per minute).

ATC Notes Reactor Power and Main Generator Output.

Verifies both RRC pumps individual controllers are in AUTO and depresses Master Controller Raise P/B to increase flow/power as directed.

ATC Informs the CRS of Power/Pressure/Level after power increase has been completed.

COMMENTS:

Page 5 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 3

==

Description:==

RHR-RLY-K112C (RHR B/C Injection Valve Open Permissive) fails and RHR-V-42C goes open.

This event is initiated by activating TRIGGER 1 after Reactor Power is at least 95%.

Time Position Applicants Actions or Behavior BOOTH OPERATOR: ACTIVATE TRIGGER 1.

T = 10 BOP Responds to RHR B/C INJECTION VLV OPEN PERMISSIVE alarm.

Refers to the ARP.

Observes RHR-V-42C going open and informs the CRS.

SRO Observes Reactor Pressure GT 470 psig and directs RHR-V-42C be closed.

BOP Takes the control switch for RHR-V-42C to close, recognizes it closes, and informs the CRS.

SRO Directs backpanel investigation of RHR-RLY-K112B and RHR-RLY-K112C.

BOP Investigates H13-P618 and recognizes RHR-RLY-K112C is picked up and RHR-RLY-K112B is not.

Reports findings to CRS.

SRO Due to RHR-V-42C opening - Declares RHR-C Inoperable and enters Tech Spec 3.5.1 and determines condition A applies - restore low pressure injection/spray subsystem to operable status within 7 days.

Page 6 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 3 SRO Declares RHR-RLY-K112C inop and enters Tech Spec 3.3.5.1 and determines function is 2f and that condition C applies (Restore channel to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months - Declare supported features inop when redundant feature ECCS initiation capability is inoperable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is not applicable).

SRO Conducts brief.

COMMENTS:

Page 7 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 4

==

Description:==

Scram Discharge Volume Level Switch fails upscale - Half Scram - Two Control Rods scram but only One goes Full In.

The event is initiated by activating TRIGGER 2 after Tech Specs for the RHR system have been referenced.

Time Position Applicants Actions or Behavior BOOTH OPERATOR - ACTIVATE TRIGGER 2.

T = 10 ATC Responds to annunciators: SDV LEVEL HIGH TRIP and 1/2 SCRAM SYSTEM A.

Recognizes a half scram on RPS A and informs the CRS.

ATC Responds to ROD DRIFT alarm - Scans the full core display (or observes RWM screen) for drifting and/or scrammed control rods.

Recognizes two control rods have blue scram lights lit and informs the CRS.

ATC Selects control rod 30-03 and observes it is at position 10.

Selects control rod 34-03 and observes it is full in (position 00).

BOP Makes an announcement for half scram on RPS A system.

Investigates backpanel for SDV level switch and recognizes RPS-RLY-K1A has dropped out.

SRO Updates crew and enters ABN-ROD.

May set a key parameter of a third scrammed control rod.

Refers to section 4.2 and directs core flow be lowered to LE 80 Mlbm/hr (should give a specific value).

ATC Ensures both individual pump controllers are in AUTO and depresses the Master Controller lower pushbutton to lower flow to directed value.

Informs CRS of Power/Pressure and RPV Level when flow decrease has been completed (power will be about 80% at the end of the flow reduction).

Page 8 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 4 SRO Directs control rod 30-03 be selected and driven full in using the continuous insert pushbutton.

ATC Selects control rod 30-03 and depresses the continuous insert pushbutton and drives the control rod full in.

Releases the continuous insert pushbutton and verifies the control rod remains at position 00.

Informs the CRS that the control rod is full in.

SRO For control rods - Refers to Tech Spec 3.1.3 Condition C applies (Insert rod within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and disarm within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ).

For SDV Level switch - Refers to Tech Spec 3.3.1.1 Condition A and recognizes system already in tripped condition.

SRO Per ARP for 1/2 SCRAM SYSTEM A - directs announcement be made stopping all maintenance and surveillance testing that has a potential for generating a trip on RPS B side.

BOP Makes announcement as directed.

COMMENTS:

Page 9 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 5

==

Description:==

Main Steam Tunnel Steam Leak - MSIV closure - Two MSIVs fail to close. It takes six minutes to get the first temperature alarm after trigger 3 initiation. It takes another 2 minutes to get MSIV closure and an automatic reactor scram.

This event is initiated when the Tech Specs for the SDV level switch failure have been referenced by activating TRGGER 3.

Time Position Applicants Actions or Behavior BOOTH OPERATOR - ACTIVATE TRIGGER 3.

ROLEPLAY: Wait one minute after trigger 3 is activated and call the control room on x2222 and, as the security fire tour, inform the control room that it feels like there is steam coming up from between the floor plugs on the North side of the Reactor Building 522 elevation.

T = 35 CRS Takes the phone call and after the call is completed performs a update and informs the crew of the potential steam leak report.

Directs investigation of leak detection monitors on H13-P632 and H13-P642.

BOP Investigates leak detection monitors and reports temperatures and delta temperatures rising for the Main Steam Tunnel on LD-MON-2B points A1-1 and A1-2.

SRO Updates crew and enters ABN-HELB.

May direct that the Reactor Building be evacuated due to a steam leak.

BOP Acknowledges LEAK DET MSL TUNNEL dT HIGH and refers to ARP.

Provides temperature and trend on Main Steam Tunnel temperatures.

SRO Updates crew and directs a manual scram prior to an automatic scram.

NOTE: The remainder of these steps occur after the scram but are included here for continuity purposes.

Acknowledges the LEAK DET STEAM TUNNEL TEMP HI HI annunciators and informs the CRS of the EOP entry.

SRO Updates the crew and enters PPM 5.3.1, Secondary Containment Control.

Page 10 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 5 BOP When the MSIVs close, takes all of the control switches for the MSIVs to the close position.

Recognizes MS-V-22A and MS-V-28A did not close automatically and will not manually close and reports the failure of MS-V-22A and MS-V-28A to close to the CRS.

COMMENTS:

Page 11 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 6

==

Description:==

Electric ATWS B RPS side. SLC Fails to initiate.

This event was activated when TRIGGER 3 was initiated for the last event and is realized when a manual scram is inserted.

Time Position Applicants Actions or Behavior Critical Task is to insert control rods.

T = 55 ATC Manually scrams the reactor as directed and performs immediate operator actions of PPM 3.3.1:

Places mode switch to shutdown

Monitors/reports power/level/pressure

Reports APRMs not downscale and performs the following:

Depresses the manual scram pushbuttons

Initiates ARI

Recognizes reactor power is GT 5% and performs the following:

Informs the CRS

Removes the SLC keylock switch blanks and inserts both keys in the control switches.

Initiates SLC injection by performing the following:

Places SLC System A control switch to the OPER position.

Places SLC System B control switch to the OPER position.

Insert SRMs and IRM by depressing the power on and insert pushbuttons Reports all rods not in and current reactor power (about 12% and drops to downscale lit).

Reports an Electrical ATWS on B RPS side in that three RPS white lights are still illuminated.

Recognizes and reports that neither SLC pump started and neither SLC suction valve opened when the key lock switches were taken to OPER.

Page 12 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 6 CRS Updates crew on EOP entry into PPM 5.1.1, RPV Control, and directs/verifies that the Mode Switch has been placed in SHUTDOWN.

Updates crew and exits PPM 5.1.1, RPV Control, and transitions to PPM 5.1.2, RPV Control - ATWS.

Directs BOP to:

Inhibit ADS and take manual control of HPCS.

Verify pressure is being maintained by the bypass valves in Auto.

Directs RPV level be maintained -50 to +54.

BOP Takes both ADS control switches to the INHIBIT position and acknowledges associated alarms.

Arms and Depresses the HPCS system initiation pushbutton while holding the control switch for HPCS-P-1 to STOP.

Takes the control switch for HPCS-V-4 to close when it gets fully opened.

Reports ADS inhibited and manual control of HPCS taken to CRS.

SRO Prioritizes the power leg of PPM 5.1.2, RPV Control ATWS, and directs control rod insertion by pulling RPS fuses per PPM 5.5.11, Alternate Control Rod Insertion.

Page 13 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 6 BOP Refers to PPM 5.5.11 and determines there are white RPS scram lights lit on the B RPS side and performs the following:

Updates crew that RPS fuses are about to be removed and control rods should be inserting.

Removes the four fuses in H13-P611 associated with B RPS:

LL-F13

MM-F21

BB-F12

AA-F20 ATC As RPS fuses are being removed, informs the CRS that control rods are inserting.

When the last RPS fuse is removed, informs the CRS that all control rods are inserted.

SRO May direct SLC switches be taken to OFF.

ATC Takes the control switches for both SLC Systems to off if directed.

Reports completion to CRS.

SRO Updates crew and exits PPM 5.1.2, RPV Control - ATWS and enters PPM 5.1.1, RPV Control.

SRO Directs RPV level control at -50 to + 54 with Condensate, Feed, RCIC and HPCS as necessary.

Directs PPM 3.3.1 be completed.

Page 14 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 6 ATC Announces reactor scram over PA.

Transfers RPV level control to Startup level control valves per SOP-RFW-FCV-QC:

Step 2.1.1 Starts closing RFW-V-112A and RFW-V-112B.

Step 2.1.2 Starts opening RFW-V-118.

Step 2.1.3 Verifies RFW-V-109 open.

Step 2.1.4 Verifies RFW-V-117A and RFW-V-117B open Step 2.1.5 Verifies RFW-LIC-620 in manual.

Step 2.1.6 Places RFW-P-1B in MDEM; Places RFW-P-1A in MDEM; Adjusts turbine speed as required.

Step 2.1.7 Verifies RFW-V-112A and RFW-V-112B closed.

Step 2.1.8 Verifies RFW-V-118 open.

Step 2.1.9 Adjusts turbine speed to get 200 psid across Startup valves.

Step 2.1.10 Adjusts level in manual.

Step 2.1.11 Places RFW-LIC-620 in automatic at 36.

Informs the CRS feed pumps are on the Startup level controllers in automatic.

COMMENTS:

Page 15 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 7

==

Description:==

Breaker CB-S1 fails to auto close on transfer of electrical busses to Startup power.

This event is active from the beginning of the scenario and is realized when the Main Turbine trips and the electrical plant transfers to the Startup Transformer.

Time Position Applicants Actions or Behavior T = 55 BOP Responds to the electrical boards and recognizes SM-1 is de-energized, SM-7 is on Backup power and DG-1 is running. Verifies SW-A running to support DG-1 operation.

Observes there are no lockouts indicated on SM-1.

Takes the sync selector switch for CB-S1 to the MAN position.

Takes the control switch for CB-S1 to close and observes red light comes on and green light goes out and that the breaker did close to repower SM-1.

BOP Observes SL-11 not energized and re-energizes it using the quick card:

Verifies SM-1 energized

Takes control switch for CB-11/1 to open

Closes CB-1/11

Closes CB-11/1

Verifies SL-11 energized.

Informs CRS of electrical board status and actions taken.

ATC Recognizes a CRD pump is not running and starts a CRD pump using ARP guidance.

COMMENTS:

Page 16 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 8

==

Description:==

Steam Leak gets larger and spreads to a second area. It takes 75 seconds to get the temperature alarm and nine minutes total to reach Max Safe temperature after trigger initiation.

This event is initiated when control rods are inserted and SM-1 and SL-11 have been repowered by activating TRIGGER 4.

Time Position Applicants Actions or Behavior BOOTH OPERATOR - ACTIVATE TRIGGER 4.

T = 65 SRO Sets a key parameter of Main Steam Tunnel Temperature of 320°F (Max Safe).

BOP Reports Main Steam Tunnel temperature as it approaches and when it reached Max Safe temperature of 320°F.

Acknowledges LEAK DET RWCU ROOM TEMP HI HI annunciator and refers to the ARP.

Informs the CRS of EOP entry.

Acknowledges Secondary Containment dP High annunciator and reports it as an EOP entry.

SRO Updates crew and reenters PPM 5.3.1, Secondary Containment Control.

Directs back panel investigation of the RWCU temperature.

BOP Investigates back panel leak detection monitors and observes temperature on LD-MON-1B point A2-4 trending up and reports current value and trend to the CRS.

SRO Establishes a Key Parameter of Max Safe temperature of 340°F.

Page 17 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 8 SRO Updates crew and reenters PPM 5.3.1, Secondary Containment Control.

BOP Monitors RWCU Pipe Area temperature as it rises and reports when it reaches max safe temperature of 340°F.

SRO Directs second operator verify max safe temperature in two areas exceeded.

COMMENTS:

Page 18 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 9

==

Description:==

EMERGENCY DEPRESSURIZATION when 2 Areas exceed Max Safe Operating Temperatures.

This event is initiated when it is determined that 2 Areas have exceeded their Max Safe Operating Temperatures.

Time Position Applicants Actions or Behavior Critical task is to initiate an EMERGENCY DEPRESSURIZATION when 2 Areas have exceeded their Max Safe Operating Temperatures and within 5 minutes of establishing that the second areas temperature has exceeded its MSOT.

T = 70 ATC Verifies max safe temperature exceeded in two areas and informs the CRS.

SRO Per PPM 5.3.1, Secondary Containment Control, determines that any one parameter has exceeded its maximum safe operating value in 2 or more areas and an Emergency Depressurization is required.

Updates crew that an Emergency depressurization is required and takes the PPM 5.1.1, RPV Control override to PPM 5.1.3, Emergency RPV Depressurization.

SRO Determines a high drywell pressure signal is not in and Wetwell level is GT 17 foot and directs seven SRVs, ADS preferred, be opened.

ATC/BOP Opens seven ADS SRVs as directed.

Verifies containment response as each is opened and reports completion to CRS.

SRO Directs pumps not required for adequate core cooling be stopped from injecting.

Directs RPV/L maintenance -50 inches to +54 inches.

ATC Maintains RPV level as required to maintain water level band.

Page 19 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 9 Termination Cue: The scenario can be terminated when the reactor has been Emergency Depressurized or as directed by the scenario coordinator.

COMMENTS:

Page 20 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 TURNOVER INFORMATION Initial conditions: Reactor Power is 90%. Power was reduced due to CW-P-1B not being available. The work on CW-P-1B has just been completed. OPS4 is standing by in the CWPH for a start of CW-P-1B.

Turnover: Start CW-P-1B. After the pump start, raise reactor power with flow to 100%. The reactivity brief has been performed.

Page 21 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 SIMULATOR SETUP INSTRUCTIONS Reset to IC 211.

Ensure power at 90%.

Place Simulator in Run.

Page 22 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 SCHEDULE

1

<ACTION>Insert malfunction BKR-EPS049 to FAI_AUT_CLOS</ACTION>

</ITEM>

1

<ACTION>Insert malfunction AOV-RRS003F to FAIL_AS_IS</ACTION>

<DESCRIPTION>MS-V-22A INBOARD MSIV</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction AOV-RRS007F to FAIL_AS_IS</ACTION>

<DESCRIPTION>MS-V-28A OUTBOARD MSIV</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction RLY-RHR013F to TRIP on event 1</ACTION>

<DESCRIPTION>RHR-RLY-K112C - RHR-V-42C INJECT LW PRESS INTRLK</DESCRIPTION>

</ITEM>

1

<ACTION>Insert override OVR-SLC001C to OFF</ACTION>

<DESCRIPTION>SLC KEYLOCK SWITCH TO OFF</DESCRIPTION>

</ITEM>

1

<ACTION>Insert override OVR-SLC002C to OFF</ACTION>

<DESCRIPTION>SLC KEYLOCK SWITCH TO OFF</DESCRIPTION>

</ITEM>

Page 23 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015

1

<ACTION>Insert malfunction MOV-RHR023F to OPEN after 2 on event 1 delete in 10</ACTION>

</ITEM>

1

<ACTION>Insert malfunction RLY-RPS045F to TRIP on event 2</ACTION>

<DESCRIPTION>RPS-RLY-K1A SCRAM DISCH VOL HI LEVEL SCRAM</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-RMC007-3003 after 2 on event 2 delete in 2</ACTION>

<DESCRIPTION>ROD 3003 SINGLE ROD SCRAM</DESCRIPTION>

</ITEM>

1

<ACTION>Insert override IND-RMC001BPF to ON after 2 on event 2</ACTION>

<DESCRIPTION>SCRAM LIGHT FOR 3003</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-RMC007-3403 after 2 on event 2</ACTION>

<DESCRIPTION>ROD 3403 SINGLE ROD SCRAM</DESCRIPTION>

</ITEM>

0

<ACTION>insert malfunction MAL-RRS006B to 21500 in 300 on event 3</ACTION>

<DESCRIPTION>>MSL-B BREAK IN THE STEAM TUNNEL</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction RLY-RPS025F to FAIL_TO_TRIP on event 3</ACTION>

Page 24 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015

<DESCRIPTION>RPS-RLY-K14A RPS AUTO SCRAM RELAY</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction RLY-RPS026F to FAIL_TO_TRIP on event 3</ACTION>

<DESCRIPTION>RPS-RLY-K14B RPS AUTO SCRAM RELAY</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction RLY-RPS027F to FAIL_TO_TRIP on event 3</ACTION>

<DESCRIPTION>RPS-RLY-K14C RPS AUTO SCRAM RELAY</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction RLY-RPS028F to FAIL_TO_TRIP on event 3</ACTION>

<DESCRIPTION>RPS-RLY-K14D RPS AUTO SCRAM RELAY</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction RLY-RPS029F to FAIL_TO_TRIP on event 3</ACTION>

<DESCRIPTION>RPS-RLY-K14E RPS AUTO SCRAM RELAY</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction RLY-RPS030F to FAIL_TO_TRIP on event 3</ACTION>

<DESCRIPTION>RPS-RLY-K14F RPS AUTO SCRAM RELAY</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction RLY-RPS031F to FAIL_TO_TRIP on event 3</ACTION>

<DESCRIPTION>RPS-RLY-K14G RPS AUTO SCRAM RELAY</DESCRIPTION>

</ITEM>

Page 25 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015

1

<ACTION>Insert malfunction RLY-RPS032F to FAIL_TO_TRIP on event 3</ACTION>

<DESCRIPTION>RPS-RLY-K14H RPS AUTO SCRAM RELAY</DESCRIPTION>

</ITEM>

1

<ACTION>Insert override OVR-RPS007B to OFF on event 3</ACTION>

<DESCRIPTION>ARI-RMS-4A SDV SYSTEM ATWS-ARI SYSTEM A TRIP</DESCRIPTION>

</ITEM>

1

<ACTION>Insert override OVR-RPS008B to OFF on event 3</ACTION>

<DESCRIPTION>ARI-RMS-4B SDV SYSTEM ATWS-ARI SYSTEM B TRIP</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction ANN-603A7D01 to OFF on event 3</ACTION>

<DESCRIPTION>ATWS-ARI IN TEST/LOSS OF POWER</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction ANN-603A8D01 to OFF on event 3</ACTION>

<DESCRIPTION>ATWS-ARI IN TEST/LOSS OF POWER</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction BST-RRS029F to FAIL_TO_TRIP on event 3</ACTION>

<DESCRIPTION>MS-LS-36A RPV LVL ATWS-RPT & ARI (RECIRC)</DESCRIPTION>

</ITEM>

1

Page 26 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015

<ACTION>Insert malfunction BST-RRS030F to FAIL_TO_TRIP on event 3</ACTION>

<DESCRIPTION>MS-LS-36B RPV LVL ATWS-RPT & ARI (RECIRC)</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction BST-RRS031F to FAIL_TO_TRIP on event 3</ACTION>

<DESCRIPTION>MS-LS-36C RPV LVL ATWS-RPT & ARI (RECIRC)</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction BST-RRS032F to FAIL_TO_TRIP on event 3</ACTION>

<DESCRIPTION>MS-LS-36D RPV LVL ATWS-RPT & ARI (RECIRC)</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction BST-RRS090F to FAIL_TO_TRIP on event 3</ACTION>

</ITEM>

1

<ACTION>Insert malfunction BST-RRS091F to FAIL_TO_TRIP on event 3</ACTION>

</ITEM>

1

<ACTION>Insert malfunction BST-RRS092F to FAIL_TO_TRIP on event 3</ACTION>

</ITEM>

1

<ACTION>Insert malfunction BST-RRS093F to FAIL_TO_TRIP on event 3</ACTION>

</ITEM>

Page 27 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015

1

<ACTION>Insert override OVR-RMS031F to 350 in 2100 on event 3</ACTION>

</ITEM>

0

<ACTION>insert malfunction MAL-RRS006B from 21500 to 250000 in 600 on event 4</ACTION>

<DESCRIPTION>>MSL-B BREAK IN THE STEAM TUNNEL INCREASES</DESCRIPTION>

</ITEM>

0

<ACTION>insert malfunction XMT-SCN030A from 96 to 360 in 600 on event 4</ACTION>

<DESCRIPTION>>LD-TE-24E RWCU PIPE ROUTING AREA TEMPERATURE RISE </DESCRIPTION>

</ITEM>

0

<ACTION>insert malfunction XMT-SCN031A from 96 to 360 in 600 on event 4</ACTION>

<DESCRIPTION>>LD-TE-24F RWCU PIPE ROUTING AREA TEMPERATURE RISE </DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction XMT-SCN058A to 360 in 300 on event 4</ACTION>

</ITEM>

0

<ACTION>Insert malfunction XMT-SCN060A to 340 in 300 on event 4</ACTION>

</ITEM>

0

Page 28 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015

<ACTION>Insert malfunction XMT-SCN059A to 340 in 300 on event 4</ACTION>

</ITEM>

0

<ACTION>Insert malfunction XMT-SCN061A to 340 in 300 on event 4</ACTION>

</ITEM>

0

<ACTION>Insert malfunction XMT-SCN046A to 200 in 120 on event 4</ACTION>

<DESCRIPTION>LD-TE-29C MSL C PIPE TNL INLET</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction XMT-SCN044A to 200 in 120 on event 4</ACTION>

<DESCRIPTION>LD-TE-29A MSL A PIPE TNL INLET</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction XMT-SCN045A to 200 in 120 on event 4</ACTION>

<DESCRIPTION>LD-TE-29B MSL B PIPE TNL INLET</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction XMT-SCN047A to 200 in 120 on event 4</ACTION>

<DESCRIPTION>LD-TE-29D MSL D PIPE TNL INLET</DESCRIPTION>

</ITEM>

0

<ACTION>Insert override OVR-RMS029F to 350 in 900 on event 4</ACTION>

Page 29 of 30

Appendix D NRC Scenario No. 4 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015

</ITEM>

0

<ACTION>Insert override OVR-RMS028F to 350 in 1200 on event 4</ACTION>

</ITEM>

0

<ACTION>Insert override OVR-RMS030F to 500 in 5400 on event 4</ACTION>

</ITEM>

0

<ACTION>Insert override OVR-RPS097A to OFF on event 6</ACTION>

<DESCRIPTION>RPS CH B1 FUSES REMOVED</DESCRIPTION>

</ITEM>

1

<ACTION>Schedule Schedule/Local.sch</ACTION>

</ITEM>

1

<ACTION>Event Events\LO001804.evt</ACTION>

<DESCRIPTION>Load the Event file</DESCRIPTION>

</ITEM>

</SCHEDULE>

EVENT

<EVENT>

</EVENT>

Page 30 of 30

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE COLUMBIA GENERATING STATION SIMULATOR EXAMINATION CRD flow controller fails; Open CB-4888; Place second RFW Pump in service; Raise power with Recirc Pumps; HPCS-LS-2A trips, HPCS-V-1 LESSON TITLE does not auto close; ARM-RIS-3 fails downscale; MSR Drain Tank controller fails - Scram, MG fail to trip; LOCA, One Wetwell Spray Valve fails to open LENGTH OF LESSON 1.5 Hours INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code LO001805 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 10/21/14 REVISED BY DATE VALIDATED BY DATE TECHNICAL REVIEW DATE INSTRUCTIONAL REVIEW DATE SAT Coordinator APPROVED DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

Appendix D NRC Scenario No. 5 FORM ES-D-1 Columbia Generating Station ILC NRC Exam April, 2015 Facility: Columbia NRC Scenario No: 5 Examiners: _______________ Operators: _______________

Initial conditions: Reactor Power is 60%. RFW-P-1A was removed from service for required maintenance and is ready to be placed back on line. SOP-RFT-START is in progress.

Turnover: The following evolutions are to be completed concurrently: Place RFW-P-1A in service. SOP-RFT-START has been completed up through step 5.9.14 and Dittmer has requested that CB-4888 be opened to facilitate switchyard maintenance. Open CB-4888.

After RFW-P-1A has been placed in service, raise reactor power to 70% using Reactor Recirculation Pumps. The reactivity brief has been completed.

Event Timeline Event Event Description No. Type*

1. T=0 C (BOP) CRD flow controller fails

2. T=5 N (BOP) Open CB-4888

3. T=5 N (ATC) Place second RFW Pump in service

4. T = 30 R (ATC) Raise power with flow to 70% reactor power

5. T = 50 I (BOP) HPCS-LS-2A Spurious Trip; HPCS-V-1 does not auto close TS (SRO)

6. T = 65 TS (SRO) ARM-RIS-3 fails downscale

7. T = 80 C (ATC) MSR Drain Tank Controller Fails - Requires manual scram. MT trip.

C (SRO)

8. T = 85 C (BOP) MG Fail to trip

9. T = 90 M (ALL) LOCA

10. T = 95 C (BOP) Initiate containment sprays - Wetwell Spray Valve RHR-V27A or RHR-V-27B fails to open. (First loop selected for wetwell spray.)

Critical Task is to spray the Drywell when Wetwell pressure reaches 12 psig, prior to exceeding PSP and after verifying DSIL and RHR not required for adequate core cooling.

Critical Task is to secure Drywell sprays after Drywell pressure has dropped LT 12 psig and prior to Drywell pressure reaching zero psig.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 SCENARIO DESCRIPTION EVENT 1 - CRD Drive Header Flow Control Valve controller, CRD-FCV-600, fails to 100% output signal fully opening CRD-FCV-2A (2B). The crew will take manual control of CRD-FCV-600 and adjust output to achieve CRD Cooling Header flow to ~ 62 GPM and Drive Header dP to ~265 psid.

EVENT 2 -BPA requested PCB 4888 be opened to allow BPA to perform switchyard maintenance. The crew will open PCB 4888.

EVENT 3 -RFW-P-1A was secured for maintenance. SOP-RFT-START is in progress and the crew will complete the startup of RFW-P-1A.

EVENT 4 -Following the startup of RFW-P-1A the turnover sheet directs the crew to raise power to 70%

power. The crew will raise power to 70% at a rate of either 1% reactor power per minute or 10 MWe per minute.

EVENT 5 - When reactor power reaches approximately 70% power, or as directed by the scenario coordinator there will be a spurious trip of HPCS-LS-2A which causes a HPCS Suction switchover and HPCS-V-15 to open. The crew will investigate and observe that HPCS-V-1 did not auto close. The crew will take action to close HPCS-V-1. Tech Specs will be reviewed.

EVENT 6 -A downscale failure of ARM-RIS-3 will then occur. The crew will investigate, take actions per ARP and refer to LCS 1.3.7.4.

EVENT 7 - A failure of the valves for a MSR Drain Tank will occur. The BOP operator will attempt to take manual control and reduce drain tank level but will not be successful. Eventually a MSR High Level alarm annunciates. The crew should take action and insert a manual scram and trip the Main Turbine which will trip on High MSR Level in 30 seconds from receipt of the MSR High Level alarm.

EVENT 8 - When a scram is inserted, the Main Turbine will trip but the Main Generator will not trip. The crew will take actions to trip the Main Generator and will be successful when the Unit and Overall Unit pushbuttons are depressed. The Critical Task will be to trip the Main Generator.

EVENT 9 - When the Main Generator is tripped a LOCA will occur. Containment pressure will rise to require Wetwell spray and Drywell spray initiations.

EVENT 10 - When Wetwell Sprays are directed, the first RHR loop selected for Wetwell Sprays will have the Wetwell Spray valve fail to open. The crew will swap loops and spray initiation will be effective. Drywell sprays will be initiated at 12 psig and be effective in reducing containment pressure. Before Wetwell and Drywell pressures reach zero psig the crew will secure Wetwell and Drywell sprays.

The scenario will be terminated when Drywell sprays have been secured.

Page 3 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 1

==

Description:==

CRD flow controller fails.

This event is initiated after the BOP operator has been given direction to open PCB-4888 by activating TRGGER 1.

Time Position Applicants Actions or Behavior BOOTH OPERATOR - ACTIVATE TRIGGER 1 T=0 ATC Responds to the CRD Drive Water Filter DP High alarm.

Observes CRD Cooling Header flow at 70 gpm and Drive Header/Reactor dP at 350 psid and informs the CRS.

Refers to the ARP.

ATC Observes Flow Control Valve CRD-V-2B full open.

Observes CRD-FC-600 red arrow upscale and the signal is at 100% and informs the CRS.

Places CRD-FC-600 controller in manual.

Depresses the close pushbutton to restore CRD Cooling Header flow to

~ 62 GPM and Drive Header dP to ~265 psid.

Observes Flow Control valve dual indication and the red arrow on CRD-FC-600 returning to the green band.

SRO Contacts Work Control for assistance in troubleshooting failure of the CRD-FC-600.

ROLEPLAY - if sent you find nothing obviously wrong at CRD. dP is 9 psid.

COMMENTS:

Page 4 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 2

==

Description:==

BPA requests PCB-4888 be opened to allow BPA to perform switchyard maintenance.

This event is initiated by shift turnover sheet.

Time Position Applicants Actions or Behavior T=0 SRO Directs PCB-4888 to be opened per SOP-ELEC-500KV-OPS section 5.1.2.

BOP Manually opens PCB 4888 Step 5.1.2 a - Verifies Dittmer is informed (done per turnover sheet)

Step 5.1.2b - Places PCB-4888 synch selector switch to manual.

Step 5.1.2c - Places PCB-4888 switch in trip.

Responds to the DEH Warning and DEH Trouble alarms (in due to changing breaker position - no action required per ARP).

Step 5.1.2d - Verify PCB-4888 opens.

Step 5.1.2e - Places PCB-4888 synch selector switch in OFF.

Step 5.1.2f - Informs Dittmer that PCB-4888 is open.

Reports to CRS that PCB-4888 is open.

COMMENTS:

Page 5 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 3

==

Description:==

Place RFW-P-1A on line.

This event is initiated by shift turnover.

Time Position Applicants Actions or Behavior T = 10 SRO Directs RFW-P-1A to be started and placed on line.

ATC Performs actions of SOP-RFT-START as follows:

5.9.15 and 5.9.16 - Raises speed to ~2500 RPM which is ~7.3%

controller output.

5.9.17 - Observes RFW-P-1A in MDVP - selects MDEM and YES.

5.9.18 and 5.9.19 - Raises speed to minimize dP across RFW-V-102A (Pump Discharge Valve) which is ~11% controller output.

5.9.20 - Opens RFW-V-102A.

5.9.21 - Raises RFW-P-1A speed to approximately match speed of RFW-P-1B which is ~13.3% output.

5.9.22 - Places RFW-FCV-2A in Auto.

5.9.23 - Observes RFW-P-1A in Auto.

5.9.24 - Inserts a Bias of >100 RPM on one RFW Pump.

5.9.25 - Verifies feed pump controllers are stable.

5.9.26 - Not performed, as controllers are stable.

5.9.27 - Verifies MS-V-142A, BS-V-44A, and BS-45A are closed.

Reports to CRS that RFW-P-1A is on line.

COMMENTS:

Page 6 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 4

==

Description:==

Downscale failure of ARM-RIS-3.

The event is initiated by activating TRIGGER 2 after PCB-4888 is opened and after actions to place RFW-P-1A have started.

Time Position Applicants Actions or Behavior BOOTH OPERATOR - ACTIVATE TRIGGER 2.

T = 15 BOP Acknowledges P602-A5 6-1 AREA RAD MONITOR DNSCL alarm and pulls ARP.

At H13-P673, observes ARM-RIS-3 white low light is illuminated and the meter is reading downscale.

Informs the CRS.

SRO Directs actions per ARP:

Notify Health Physics.

Refers to LCS 1.3.7.4.

Directs reset of ARM.

BOP Notifies Health Physics.

Attempts to reset ARM (if directed) at H13-P673 and recognizes it does not reset.

SRO Refers to LCS 1.3.7.4 with new fuel in vault.

Directs HP to survey area once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Stops/confirms stoppage of fuel movement.

Roleplay: If crew attempts to verify no new fuel in the vault, provide them information that there are 2 new fuel bundles in the vault but no fuel movement is in progress.

COMMENTS:

Page 7 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 5

==

Description:==

Raise power with flow to ~70% reactor power.

This event is initiated by shift turnover.

Time Position Applicants Actions or Behavior T = 20 SRO Directs power to be raised with Recirc flow to achieve 70% reactor power at a rate not to exceed 10 MWE/min or 1% power/minute.

ATC Notes current Reactor Power and/or Main Generator Output.

Verifies both RRC pumps individual controllers in AUTO.

Depresses Master Controller Raise P/B to increase flow/power as directed.

At 70% power, stops the power increase.

Reports power/pressure and level after power increase stops.

COMMENTS:

Page 8 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 6

==

Description:==

HPCS-LS-2A Spurious trip; HPCS-V-1 does not auto close.

This event is initiated by activating TRIGGER 3 when Reactor Power is ~70%, or as directed by the scenario coordinator.

Time Position Applicants Actions or Behavior BOOTH OPERATOR - ACTIVATE TRIGGER 3.

T = 35 BOP Responds to annunciator HPCS SUCTION SWITCHOVER SUPP POOL LEVEL HIGH annunciator.

Refers to H13-P601.A1 6-6 annunciator ARP.

Recognizes both HPCS suction valves are open.

Informs the CRS of alarm and that both HPCS-V-1 and HPCS-V-15 are open and that HPCS-V-1 should have closed when HPCS-V-15 opened.

Refers CRS to Tech Spec 3.3.5.1.

SRO Acknowledge report.

Directs HPCS-V-1 be closed.

BOP Closes HPCS-V-1 and reports valve did close.

SRO Refers to Tech Spec 3.3.5.1 and Table 3.3.5.1-1 and determines 3.e is applicable which indicates condition D applies - place channel in trip in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or align HPCS to the SP within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Refers to Tech Specs for HPCS-V-1 and determines 3.5.1B applies -

Verify RCIC operable immediately and restore HPCS within 14 days.

COMMENTS:

Page 9 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 7

==

Description:==

Failure of MSR Drain tank 1A level control valves HD-LIC-9A and 9A2 closed.

The event is initiated by activating TRIGGER 4 after tech Specs for HPCS have been referenced.

Note: After valve position is changed, the time it takes to get MSR drain tank high level alarm is dependent on the power level. It then takes another four minutes to get the MSR High level alarm.

Time Position Applicants Actions or Behavior BOOTH OPERATOR - Ensure the InSight window is open with RHDC09SA1 displayed.

BOOTH OPERATOR - Then ACTIVATE TRIGGER 4.

BOOTH OPERATOR - In the InSight window change the value for RHDC09A1 to 0.4.

T = 55 BOP Acknowledges alarm and reports MSR Drain Tank 1A Level High. Refers to ARP.

Investigates controllers at H13-P835 to ensure they are in Auto and recognizes the controllers are opening drain valves but level continues to rise (may attempt manual operation but valve is already full open).

Reports controllers are functioning in Auto (or Manual) and level indication is off scale high.

BOOTH OPERATOR - Three minutes after the drain tank high level alarm, change the value for RHDC09A1 to 0.35 (it is a short time before the MSR High level alarm annunciates - if annunciator does not come in keep backing down on the valves position).

SRO Conduct a brief on actions if level continues to rise and MSR Level High alarm is received.

BOP Acknowledges and reports MSR A Level High alarm and refers to ARP (Turbine Trip has a 30 second time delay).

SRO Directs a manual reactor scram prior to automatic scram actuation (SRO may direct a scram prior to MSR A high Level alarm)

Page 10 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 7 Announces Listen up for the scram report and:

ATC

Places MODE switch to shutdown

Reports APRM downscales, RPV pressure and trend, and RPV level and trend.

Inserts IRMs and SRMs.

Reports EOP entry on low RPV level.

Reports all rods in.

Acknowledges the scram report.

SRO Updates crew and enters PPM 5.1.1, RPV Control, on low RPV water level and directs actions:

Verify all +13 actuations.

Maintain RPV level in band of +13 to +54 inches with feed and condensate.

Maintain pressure 800 to 1050 psig using DEH in Automatic.

Complete actions of PPM 3.3.1 Page 11 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 7 ATC Lines up RFW on the Startup Flow Control Valves using the quick card:

Step 2.1.1 - Places RFW-V-112A and RFW-V-11B C/S to close.

Step 2.1.2 - Places RFW-V-118 C/S to open.

Step 2.1.3 - Observes RFW-V-109 closed.

Step 2.1.4 - Observes RFW-V-117A and RFW-V-117B open.

Step 2.1.5 - Observes RFW-LIC-620 in Manual and at 0% output.

Step 2.1.6 - Places both RFW pumps in MDEM - Selects MDEM and YES.

Step 2.1.7 - Observes RFW-V-112A and RFW-V-112B are closed.

Step 2.1.8 - Observes RFW-V-118 open.

Step 2.1.9 - Depresses the up and/or down arrows to adjust RFW speed to establish a 200 psid across RFW-FCV-10A and 10B.

Maintains RPV level in ordered band.

COMMENTS:

Page 12 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 8

==

Description:==

Failure of Main Generator to trip when Main Turbine Trips.

This event is active at the beginning of the scenario and is realized when the Main Turbine trips following a reactor scram.

Time Position Applicants Actions or Behavior Critical Task is to trip the Main Generator to allow the electrical plant to transfer to the Startup transformer.

T = 65 BOP Recognizes that the electrical plant has not transferred to Startup power.

Observes the countdown timer and recognizes it has timed out.

Recognizes that the Main Generator has failed to trip.

Depresses the red Unit and Overall Unit Lockout pushbuttons.

Verifies the electric plant transferred to the Startup Transformer.

Informs the CRS of the failure of the Main Generator to trip and that the electrical plant has successfully transferred to the Startup Transformer.

COMMENTS:

Page 13 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 9

==

Description:==

LOCA The event is initiated by activating TRIGGER 5 and is initiated after the Main generator has been tripped.

Time Position Applicants Actions or Behavior BOOTH OPERATOR - ACTIVATE TRIGGER 5.

T = 70 ATC/BOP Acknowledges Floor Drain Flow high annunciator and observes rising Drywell pressure.

Reports indication of a primary leak to the CRS.

At 1.68 psig Drywell pressure, reports EOP entry condition (and other containment entries as they occur).

SRO Updates the crew and enters PPM 5.2.1, Primary Containment Control, and re-enters 5.1.1, RPV Control, on high drywell pressure.

Directs 1.68 psig actuations be verified.

Sets a key parameter of 2 psig Wetwell pressure.

May direct a pressure reduction to reduce the driving force of the leak.

BOP Verifies 1.68 psig actuations: Observes: all ECCS pumps started and minimum flow valves opened, SW-P-1A and SW-P-1B started, DG-1 and DG-2 running, GDS for containment isolation valve closure (no yellowed bordered NSSSS groups indicated).

Notes HPCS-P-1 did not start (it was manually overridden off in Event 5).

Reports actuations verified to CRS.

Page 14 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 9 BOP Reports Wetwell pressure at 2 psig.

COMMENTS:

Page 15 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 10

==

Description:==

First Wetwell spray valve opened (either RHR-V-27A or v-27B does not open).

This event is active at the beginning of the scenario and is realized when either RHR-V-27A or RHR-V-27B opening is attempted.

Time Position Applicants Actions or Behavior Critical Task is to spray the Drywell when Wetwell pressure reaches 12 psig, prior to exceeding PSP and after verifying DSIL and RHR not required for adequate core cooling.

Critical Task is to secure Drywell sprays after Drywell pressure has dropped LT 12 psig and prior to Drywell pressure reaching zero psig.

T = 65 SRO Directs Wetwell Spray using either RHR A or B spray loops.

BOP Refers to quick card to initiate Wetwell sprays:

Verifies RHR-P-2A/B running.

Verifies RHR-V-42A/B closed.

Attempts to open RHR-V-27A/B and recognizes it does not open. Reports failure to open to the CRS.

BOOTH OPERATOR - After the attempt to open the first Wetwell spray valve has been made, remove the malfunction on the other RHR loops spray valve.

SRO Directs Wetwell sprays on other RHR loop.

BOP Refers to quick card to initiate Wetwell sprays:

Verifies RHR-P-2A/B running.

Verifies RHR-V-42A/B closed.

Opens RHR-V-27A/B and reports sprays initiated with no effect on containment pressure.

SRO Directs Wetwell sprays be secured prior to Wetwell pressure reaching zero psig.

Sets Key parameter of 12 psig in the Wetwell.

Page 16 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 10 BOP Reports Wetwell pressure at 12 psig.

SRO Directs RRC pumps be verified off and Drywell Cooling fans be secured.

BOP/ATC Verifies RRC pumps off and secures the Drywell Cooling fans on back panels (bottom row of containment fans with the switches that are not in the brown area on the panel).

Reports completion to the CRS.

SRO Directs Drywell sprays (should be initiated on opposite loop that Wetwell sprays are on).

BOP Refers to quick card and:

Verifies RHR-P-2A/B running.

Verifies RHR-V-42A/B closed.

Opens RHR-V-17A/B.

Opens RHR-V-16A/B.

Verifies flow.

Reports Drywell sprays initiated and containment pressures decreasing.

BOOTH OPERATOR - After Drywell sprays have been initiated reduce leak to 0.3.

SRO Directs Drywell sprays be secured before Drywell pressure drops to zero psig.

BOP/ATC Reports Main Steam Tunnel temperature alarms.

When MSIVs close: Updates crew that MSIVs are closed and pressure control is with SRVs at 800 to 1050 psig (or the current pressure band).

Page 17 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 Event No. 10 BOOTH OPERATOR - After MSIVs have closed on high tunnel temperature reduce leak to 0.1.

SRO Directs pressure control with SRVs and gives a pressure band.

BOP Observes Drywell and Wetwell pressures as they drop.

Prior to Drywell pressure reaching zero psig, secures drywell sprays by closing RHR-V-16A/B and RHR-V-17A/B.

Reports Drywell sprays secured to the CRS.

Termination Cue: The scenario can be terminated when Drywell sprays have been secured or as directed by the scenario coordinator.

COMMENTS:

Page 18 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 TURNOVER INFORMATION Initial conditions: Reactor Power is 60%. RFW-P-1A was removed from service for required maintenance and is ready to be placed back on line. SOP-RFT-START is in progress.

Turnover: The following evolutions are to be completed concurrently:

Place RFW-P-1A in service. SOP-RFT-START has been completed up through step 5.9.14.

Dittmer has requested that CB-4888 be opened to facilitate switchyard maintenance. Open CB-4888 per SOP-ELEC-500KV-OPS.

After RFW-P-1A has been placed in service, raise reactor power to 70%

using Reactor Recirculation Pumps. The reactivity brief has been completed.

Page 19 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 SIMULATOR SETUP INSTRUCTIONS Reset to IC 200.

Place Simulator in Run.

Open InSight window from Thunderbar and display RHDC09A1 (dont change valve position).

Flag locked in annunciators.

Have a copy of SOP-RFT-START (pages 1-8 and 51-55) initialed thru step 5.9.14.

Page 20 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015 SCHEDULE FILE

1

<ACTION>Insert malfunction MAL-GEN001 to FAIL TO TRIP</ACTION>

<DESCRIPTION>MAIN GENERATOR TRIP/FAIL TO TRIP</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MOV-RHR016F to FAIL_AS_IS</ACTION>

<DESCRIPTION>RHR-V-27A SUPP POOL SPRAY</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MOV-RHR017F to FAIL_AS_IS</ACTION>

<DESCRIPTION>RHR-V-27B SUPP POOL SPRAY</DESCRIPTION>

</ITEM>

<ACTION>Insert malfunction MOV-CSS001F to FAIL_AUTO_CLOSE</ACTION>

<DESCRIPTION>HPCS-V-1 PUMP SUCTION FROM CST</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction CNH-CRD001E to 100 on event 1</ACTION>

<DESCRIPTION>CRD-FC-600 FLOW CONTROL (M/A STATION) AUTO OUTPUT</DESCRIPTION>

</ITEM>

1

<ACTION>Insert override OVR-RMS027E to OFF on event 2</ACTION>

<DESCRIPTION>ARM-RIS-3 REACTOR BLDG-606 CRITICALITY MONITOR</DESCRIPTION>

</ITEM>

Page 21 of 22

Appendix D NRC Scenario No. 5 FORM ES-D-2 Columbia Generating Station ILC NRC Exam April, 2015

1

<ACTION>Insert malfunction BST-PCN009F to SPURIOUS_TRIP on event 3</ACTION>

<DESCRIPTION>HPCS-LS-2A SUPP POOL LEVEL</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction AOV-FWH060F to FAIL_AS_IS on event 4</ACTION>

<DESCRIPTION>HD-LCV-9A2 HD-TK-1A LEVEL CONTROL DUMP VLV</DESCRIPTION>

</ITEM>

0

<ACTION>Insert malfunction AOV-FWH059F to FAIL_AS_IS on event 4</ACTION>

<DESCRIPTION>HD-LCV-9A1 HD-TK-1A LEVEL CONTROL VALVE</DESCRIPTION>

</ITEM>

1

<ACTION>Insert malfunction MAL-RRS004A to 0.9 on event 5</ACTION>

<DESCRIPTION>RECIRC LINE RUPT</DESCRIPTION>

</ITEM>

</SCHEDULE>

Page 22 of 22

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