ML091270007

DC-2008-06-Final Operating Test

ML091270007
Person / Time
Site:	Diablo Canyon
Issue date:	06/27/2008
From:	NRC Region 4
To:	Pacific Gas & Electric Co
References
Download: ML091270007 (289)

Text

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCADM061-COO-RO1

Title:

Determine if Channel Check Criteria is Met Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Designed for RO Candidates in a classroom setting.

References:

STP I-1A, Mode 1 Checklist, Rev. 109, Page 14 OPS Policy B-5, Rev. 5 Photo of SG Level Channels Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 1, 2 Job Designation: RO K/A: G 2.1.7; Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Rating: 4.4 AUTHOR: DAVID BURNS DATE: 01/24/2008 REV. 0

JPM TITLE: DETERMINE IF CHANNEL CHECK JPM NUMBER: NRCADM061-COO-RO1 CRITERIA IS MET INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

Required Materials: OPS Policy B-5, Channel Check Criteria, Rev. 5 Photo of SG Level Channels Initial Conditions: Unit One is at 100% power. A concern over the accuracy of the Steam Generator Level indication has been raised.

Initiating Cue: The Shift Foreman has requested you CHANNEL CHECK the current Steam Generator Levels and report any channels that do not meet the CHANNEL CHECK requirement outlined in OPS Policy B-5; Channel Check Criteria. Use the attached picture of SG Level channels to determine which channel(s) meet or do not meet the requirements.

Task Standard: DO NOT READ TO STUDENTS: All level channels that do not meet the channel check requirement are identified. This will be documented on the student handout.

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JPM TITLE: DETERMINE IF CHANNEL CHECK JPM NUMBER: NRCADM061-COO-RO1 CRITERIA IS MET INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

• • 1. Identify LI-519 does not meet the 2.1 Identifies the following channel as not CHANNEL CHECK criteria. meeting the CHANNEL CHECK requirements of OPS Policy B-5, Channel is reading 7 % lower than other 2 channels.

• LI-519 Step was: Sat: ______ Unsat _______*

• • 2. Identify LI-538 does not meet the 2.1 Identifies the following channel as not CHANNEL CHECK criteria. meeting the CHANNEL CHECK requirements of OPS Policy B-5, Channel is reading 7 % Higher than other 2 channels.

• LI-538 Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

DC-2008-06-FINAL Page 3 of 6 REV. 0 OPERATING TEST.DOC

JPM NUMBER: NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initial Conditions: Unit One is at 100% power. A concern over the accuracy of the Steam Generator Level indication has been raised.

Initiating Cue: The Shift Foreman has requested you CHANNEL CHECK the current Steam Generator Levels and report any channels that do not meet the CHANNEL CHECK requirement outlined in OPS Policy B-5; Channel Check Criteria.

Use the attached picture of SG Level channels to determine which channel(s) meet or do not meet the requirements.

Channel Met Not Met Channel Met Not Met LI-517 LI-537 LI-518 LI-538 LI-519 LI-539 LI-527 LI-547 LI-528 LI-548 LI-529 LI-549 DC-2008-06-FINAL Page 4 of 6 REV. 0 OPERATING TEST.DOC

JPM

Title:

DETERMINE IF CHANNEL CHECK JPM NUMBER: NRCADM061-COO-RO1 CRITERIA IS MET ATTACHMENT 1, SIMULATOR SETUP The simulator is not needed for the performance of this JPM.

DC-2008-06-FINAL Page 5 of 6 REV. 0 OPERATING TEST.DOC

JPM

Title:

DETERMINE IF CHANNEL CHECK JPM NUMBER: NRCADM061-COO-RO1 CRITERIA IS MET ANSWER KEY Initial Conditions: Unit One is at 100% power. A concern over the accuracy of the Steam Generator Level indication has been raised.

Initiating Cue: The Shift Foreman has requested you CHANNEL CHECK the current Steam Generator Levels and report any channels that do not meet the CHANNEL CHECK requirement outlined in OPS Policy B-5; Channel Check Criteria.

Use the attached picture of SG Level channels to determine which channel(s) meet or do not meet the requirements.

Channel Met Not Met Channel Met Not Met LI-517 X LI-537 X LI-518 X LI-538 X LI-519 X LI-539 X LI-527 X LI-547 X LI-528 X LI-548 X LI-529 X LI-549 X DC-2008-06-FINAL Page 6 of 6 REV. 0 OPERATING TEST.DOC

JPM TITLE: DETERMINE IF CHANNEL CHECK JPM NUMBER: NRCADM061-COO-RO1 CRITERIA IS MET ANSWER KEY DC-2008-06-FINAL Page 7 of 6 REV. 0 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCADM061-COO-RO2

Title:

Application of Overtime Restrictions Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Designed for RO Candidates in a classroom setting.

References:

OM14.ID1, Overtime Restrictions, Rev. 12 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 2, 3 Job Designation: RO K/A: G 2.1.5; Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Rating: 2.9 AUTHOR: DAVID BURNS DATE: 01/24/2008 REV. 1

JPM TITLE: APPLICATION OF OVERTIME JPM NUMBER: NRCADM061-COO-RO2 RESTRICTIONS INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

Required Materials: OM14.ID1, Overtime Restrictions, Rev. 12 Initial Conditions: Unit One is at 2% power. You are a Reactor Operator assigned to work in the control room during a plant restart, following a mini-outage for CWP repairs.

Initiating Cue: The Shift Foreman has requested that you review your previous work history and verify that you have not exceeded any overtime restrictions in the past 10 days while supporting the mini-outage. Identify and document ALL overtime restrictions violated.

You are currently scheduled to work 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> today, as the Unit 1 Control Operator.

Task Standard: DO NOT READ TO STUDENTS: All overtime restrictions that have been exceeded have been identified. This will be documented on the student handout.

DC-2008-06-FINAL Page 9 of 6 REV. 0 operating test.doc

JPM TITLE: APPLICATION OF OVERTIME JPM NUMBER: NRCADM061-COO-RO2 RESTRICTIONS INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Identifies that the 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> limits are 1.1 Identifies that following limits do not apply.

not exceeded.

• 16 consecutive hours.

• 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Note: Turnover time is not counted as actual time worked.

Step was: Sat: ______ Unsat _______*

• • 2. Identifies that the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limit is 2.1 Identifies that the following limit was exceeded. exceeded.

• 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Note: This limit was exceeded after working on Wednesday and again on Thursday.

(ONLY ONE IS REQUIRED)

Step was: Sat: ______ Unsat _______*

• • 3. Identifies that the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limit is 2.1 Identifies that following limit was exceeded.

exceeded.

• 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 days.

Note: This limit was exceeded after working on Sunday, 73 hours8.449074e-4 days <br />0.0203 hours <br />1.207011e-4 weeks <br />2.77765e-5 months <br /> total.

Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

DC-2008-06-FINAL Page 10 of 6 REV. 0 OPERATING TEST.DOC

JPM NUMBER: NRCADM061-COO-RO2 EXAMINEE CUE SHEET Initial Conditions: Unit One is at 2% power. You are a Reactor Operator assigned to work in the control room during a plant restart, following a mini-outage for CWP repairs.

Initiating Cue: The Shift Foreman has requested that you review your previous work history and verify that you have not exceeded any overtime restrictions in the past 10 days while supporting the mini-outage. Identify and document ALL overtime restrictions violated.

You are currently scheduled to work 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> today, as the Unit 1 Control Operator.

Previous Work Schedule:

Day Number of Hours Turnover Time Position Worked (Hours)

Sunday 0 0 OFF Monday 12 1 U1 BOPCO Tuesday 12 0.5 U1 BOPCO Wednesday 13 0.5 U1 BOPCO Thursday 12 1 U1 BOPCO Friday 12 0 U1 CO Saturday 0 0 OFF Sunday 12 0 U1 CO Monday 0 0 OFF Today 12 0 U1 CO Overtime Restrictions Violated:

DC-2008-06-FINAL Page 11 of 6 REV. 0 OPERATING TEST.DOC

JPM

Title:

APPLICATION OF OVERTIME JPM NUMBER: NRCADM061-COO-RO2 RESTRICTIONS ATTACHMENT 1, SIMULATOR SETUP DC-2008-06-FINAL Page 12 of 6 REV. 0 OPERATING TEST.DOC

JPM

Title:

APPLICATION OF OVERTIME JPM NUMBER: NRCADM061-COO-RO2 RESTRICTIONS ATTACHMENT 1, SIMULATOR SETUP The simulator is not needed for the performance of this JPM.

DC-2008-06-FINAL Page 13 of 6 REV. 0 OPERATING TEST.DOC

JPM

Title:

APPLICATION OF OVERTIME JPM NUMBER: NRCADM061-COO-RO2 RESTRICTIONS ANSWER KEY Initial Conditions: Unit One is at 2% power. You are a Reactor Operator assigned to work in the control room during a plant restart, following a mini-outage for CWP repairs.

Initiating Cue: The Shift Foreman has requested that you review your previous work history and verify that you have not exceeded any overtime restrictions in the past 10 days while supporting the mini-outage. Identify and document ALL overtime restrictions violated.

You are currently scheduled to work 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> today, as the Unit 1 Control Operator.

Previous Work Schedule:

Day Number of Hours Turnover Time Position Worked (Hours)

Sunday 0 0 OFF Monday 12 1 U1 BOPCO Tuesday 12 0.5 U1 BOPCO Wednesday 13 0.5 U1 BOPCO Thursday 12 1 U1 BOPCO Friday 12 0 U1 CO Saturday 0 0 OFF Sunday 12 0 U1 CO Monday 0 0 OFF Today 12 0 U1 CO Overtime Restrictions Violated:

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> on Wednesday and Thursday. (Only one is required) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 days on Sunday. (73 hours8.449074e-4 days <br />0.0203 hours <br />1.207011e-4 weeks <br />2.77765e-5 months <br /> total)

DC-2008-06-FINAL Page 14 of 6 REV. 0 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCADM061-EC-RO

Title:

Determine Clearance Points and Tagging Requirements Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Designed for RO Candidates in a classroom setting.

References:

OP F-1:III, Service Cooling Water - Shutdown and Clearing, Rev. 16 OP2.ID2; Tagging Requirements, Rev. 12 OVID 106715, Sheet 2, Rev. 45 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 1, 2, 3 Job Designation: RO K/A: G 2.2.13; Knowledge of tagging and clearance procedures.

Rating: 4.1 AUTHOR: DAVID BURNS DATE: 01/24/2008 REV. 1

JPM TITLE: DETERMINE CLEARANCE POINTS JPM NUMBER: NRCADM061-EC-RO INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

Required Materials: OP F-1:III, Service Cooling Water - Shutdown and Clearing, Rev. 16 OP2.ID2; Tagging Requirements, Rev. 12 OVID 106715, Sheet 2, Rev. 45 Initial Conditions: Unit One is at 100% power. Maintenance is planned for SCW Pump 1-1 to replace the pump Impeller. A clearance requiring the pump to be isolated, vented and drained is required.

Initiating Cue: The Work Control Shift Foreman has directed you to identify all clearance points, their respective position for this clearance, along with the appropriate tagging requirements.

Task Standard: DO NOT READ TO STUDENTS: All clearance points are identified with required position and proper tagging requirements. This will be documented on the student handout.

DC-2008-06-FINAL Page 16 of 6 REV.1 operating test.doc

JPM TITLE: DETERMINE CLEARANCE POINTS JPM NUMBER: NRCADM061-EC-RO INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

• • 1. Identify breaker required to be re- 2.1 Identifies the following breakers to be positioned for isolation of power to OPENED:

SCWP 1-1.

• 52-11D-05 (motor)

NOTE: May place Control Board Caution (CBC) Tag on SCW PP 1-1. (not part of critical task).

1.2 Identifies that a DANGER tag should be used for this component.

Step was: Sat: ______ Unsat _______*

2. Identify valves required to be closed 2.1 Identifies the following valves CLOSED:

to isolate SCWP 1-1.

• SCW-1-9 discharge valve

• SCW-1-1 suction valve 2.2 Identifies that a DANGER tag should be used for these components.

Step was: Sat: ______ Unsat _______*

3. Identify valves required to be 3.1 Identifies the following valves OPEN.

opened to drain and vent SCWP 1-1.

• SCW-1-3 pump suction drain

• SCW-1-5 pump casing vent

• SCW-1-7 pump discharge drain

• SCW-1-423 pump discharge drain NOTE: May CAUTION tag pump control switch, but not required.

3.2 Identifies that a CAUTION Tag should be used for these components.

Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

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JPM NUMBER: NRCADM061-EC-RO EXAMINEE CUE SHEET Initial Conditions: Unit One is at 100% power. Maintenance is planned for SCW Pump 1-1 to replace the pump Impeller. A clearance requiring the pump to be isolated, vented and drained is required.

Initiating Cue: The Work Control Shift Foreman has directed you to identify all clearance points, their respective position for this clearance, along with the appropriate tagging requirements.

Component ID DESCRIPTION CLEARED TAGGING POSITION REQUIREMENT DC-2008-06-FINAL Page 18 of 6 REV. 0 OPERATING TEST.DOC

JPM

Title:

Determine Clearance Points JPM NUMBER: NRCADM061-EC-RO ATTACHMENT 1, SIMULATOR SETUP The simulator is not needed for the performance of this JPM.

DC-2008-06-FINAL Page 19 of 6 REV. 0 OPERATING TEST.DOC

JPM

Title:

Determine Clearance Points JPM NUMBER: NRCADM061-EC-RO ANSWER KEY Initial Conditions: Unit One is at 100% power. Maintenance is planned for SCW Pump 1-1 to replace the pump Impeller. A clearance requiring the pump to be isolated, vented and drained is required.

Initiating Cue: The Work Control Shift Foreman has directed you to identify all clearance points, their respective position for this clearance, along with the appropriate tagging requirements.

DC-2008-06-FINAL Page 20 of 6 REV. 0 OPERATING TEST.DOC

JPM

Title:

Determine Clearance Points JPM NUMBER: NRCADM061-EC-RO ANSWER KEY Component ID DESCRIPTION CLEARED TAGGING POSITION REQUIREMENT SCW PP-1-1 Control Switch OFF Control Board Caution*

52-11D-05 SCW Pump 1-1 480 v Supply OPEN DANGER SCW-1-9 SCW Pump 1-1 Discharge Valve CLOSED DANGER SCW-1-1 SCW Pump 1-1 Suction Valve CLOSED DANGER SCW 1-3 SCW Pump 1-1 Suction Drain Valve OPEN CAUTION SCW 1-5 SCW Pump 1-1 Casing Vent Valve OPEN CAUTION SCW-1-7 SCW Pump 1-1 Discharge Drain Valve OPEN CAUTION SCW-1-423 SCW Pump 1-1 Discharge Drain Valve OPEN CAUTION

• CBC for SCW pump control switch is not required for completion of this task.

DC-2008-06-FINAL Page 21 of 6 REV. 0 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCADM061-RC-RO

Title:

Stay Time Determination Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Designed for RO Candidates in a classroom setting.

References:

RP1.ID6, Personnel Dose Limits and Monitoring Requirements, Rev. 8 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 3.3 Job Designation: RO K/A: G 2.3.4; Knowledge of radiation exposure limits under normal or emergency conditions.

Rating: 3.2 AUTHOR: DAVID BURNS DATE: 01/258/2008 REV. 1

JPM TITLE: STAY TIME DETERMINATION JPM NUMBER: NRCADM061-RC - RO INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

Required Materials: RP1.ID6, Personnel Dose Limits and Monitoring Requirements, Rev. 8 Attachment 8.1 Initial Conditions: The Work Control Shift Foreman (WCSFM) has requested you to hang a clearance in an area where the known radiation dose rate is 280 mrem/hr. Your current year exposure history, according to your NRC Form 4 is as follows:

• Committed Dose Equivalent (CDE) 10 mrem

• Committed Effective Dose Equivalent (CEDE) 200 mrem

• Deep Dose Equivalent (DDE) 400 mrem

• Eye Dose Equivalent (LDE) 20 mrem

• Shallow Dose Equivalent (SDE) 5 mrem Initiating Cue: The WCSFM has directed you to determine your maximum stay time in the High Radiation Area while hanging clearance before exceeding the DCPP Administrative Dose Guideline for Whole Body Total Effective Dose Equivalent (TEDE).

Task Standard: DO NOT READ TO STUDENT: Maximum Stay time is calculated.

DC-2008-06-FINAL Page 23 of 280 REV. 0 OPERATING TEST.DOC

JPM TITLE: STAY TIME DETERMINATION JPM NUMBER: NRCADM061-RC - RO INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Determine TEDE 1.1 TEDE = DDE + CEDE 1.2 TEDE = 400 mrem + 200 mrem 1.3 TEDE = 600 mrem Step was: Sat: ______ Unsat _______*

2. Determine DCPP Administrative 2.1 Determines DCPP Administrative Limits for TEDE Limit for TEDE = 4500 mrem 2.2 Determines DCPP Administrative Guideline for TEDE = 2000 mrem 2.3 Determine MARGIN to Administrative Guideline is:

2000 - 600 = 1400 mrem Step was: Sat: ______ Unsat _______*

• • 3. Determine maximum stay time 3.1 Stay time = Margin / Dose Rate 3.2 Stay time = 1400 mrem / 280 mrem/hr

• • 3.3 Stay time = 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

DC-2008-06-FINAL Page 24 of 280 REV. 0 OPERATING TEST.DOC

JPM NUMBER: NRCADM061-RC - RO EXAMINEE CUE SHEET Initial Conditions: The Work Control Shift Foreman (WCSFM) has requested you to hang a clearance in an area where the known radiation dose rate is 280 mrem/hr. Your current year exposure history, according to your NRC Form 4 is as follows:

• Committed Dose Equivalent (CDE) 10 mrem

• Committed Effective Dose Equivalent (CEDE) 200 mrem

• Deep Dose Equivalent (DDE) 400 mrem

• Eye Dose Equivalent (LDE) 20 mrem

• Shallow Dose Equivalent (SDE) 5 mrem Initiating Cue: The WCSFM has directed you to determine your maximum stay time in the High Radiation Area while hanging clearance before exceeding the DCPP Administrative Dose Guideline for Whole Body Total Effective Dose Equivalent (TEDE).

Document Your Answer Here DC-2008-06-FINAL Page 25 of 280 REV. 0 OPERATING TEST.DOC

JPM TITLE: STAY TIME DETERMINATION JPM NUMBER: NRCADM061-RC - RO ATTACHMENT 1, SIMULATOR SETUP DC-2008-06-FINAL Page 26 of 280 REV. 0 OPERATING TEST.DOC

JPM TITLE: STAY TIME DETERMINATION JPM NUMBER: NRCADM061-RC - RO ATTACHMENT 1, SIMULATOR SETUP The simulator is not needed for the performance of this JPM.

DC-2008-06-FINAL Page 27 of 280 REV. 0 OPERATING TEST.DOC

JPM TITLE: STAY TIME DETERMINATION JPM NUMBER: NRCADM061-RC - RO ANSWER KEY Initial Conditions: The Work Control Shift Foreman (WCSFM) has requested you to hang a clearance in an area where the known radiation dose rate is 280 mrem/hr. Your current year exposure history, according to your NRC Form 4 is as follows:

• Committed Dose Equivalent (CDE) 10 mrem

• Committed Effective Dose Equivalent (CEDE) 200 mrem

• Deep Dose Equivalent (DDE) 400 mrem

• Eye Dose Equivalent (LDE) 20 mrem

• Shallow Dose Equivalent (SDE) 5 mrem Initiating Cue: The WCSFM has directed you to determine your maximum stay time in the High Radiation Area while hanging clearance before exceeding the DCPP Administrative Dose Guideline for Whole Body Total Effective Dose Equivalent (TEDE).

DC-2008-06-FINAL Page 28 of 280 REV. 0 OPERATING TEST.DOC

JPM TITLE: STAY TIME DETERMINATION JPM NUMBER: NRCADM061-RC - RO ANSWER KEY Document Your Answer Here TEDE = DDE + CEDE TEDE = 400 mrem + 200 mrem TEDE = 600 mrem Margin = 2000 - 600 = 1400 mrem Stay time = Margin / Dose Rate 1400 mrem / 280 mrem/hr Stay time = 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> DC-2008-06-FINAL Page 29 of 280 REV. 0 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCADM061-RC-SRO

Title:

Authorize Gas Decay Tank Discharge Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Designed for SRO Candidates in a classroom setting.

References:

OP G-2:V, Gaseous Radwaste System - Gas Decay Tank Discharge, Rev. 10 CAP A-6; Gaseous Radwaste Discharge Management, Rev. 29 ECG 39.4, Radioactive Gaseous Effluent Monitoring Instrumentation, Rev. 10 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 4 Job Designation: SRO K/A: G 2.3.6; Ability to approve release permits.

Rating: 3.8 AUTHOR: DAVID BURNS DATE: 01/28/2008 REV. 1

JPM TITLE: AUTHORIZE GAS DECAY TANK JPM NUMBER: NRCADM061-RC-SRO DISCHARGE INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

Required Materials: OP G-2:V, Gaseous Radwaste System - Gas Decay tank Discharge, Rev.

10 CAP A-6; Gaseous Radwaste Discharge Management, Rev. 29 ECG 39.4, Radioactive Gaseous Effluent Monitoring Instrumentation, Rev. 10 Completed Attachment 11.1 Initial Conditions: RE-22, Gaseous Discharge Radiation Monitor was declared inoperable on June 6th, 2008 @ 1350 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.13675e-4 months <br />.

It is June 16th, 2008. You are the Unit 1 Shift Foreman. Gas Decay Tank 1-1 is planned to be discharged today on your watch.

You have just received the Authorization for a Gas Decay Tank Discharge attachment from CAP A-6, from the control operator for your final approval.

Initiating Cue: As the Unit 1 Shift Foreman review the discharge authorization form for accuracy and completeness. Document any discrepancies noted and determine if the discharge should be approved or not approved based on your review.

Task Standard: DO NOT READ TO STUDENTS: 2 Technical errors are identified and discharge authorization is not approved. This will be documented on the student handout.

DC-2008-06-FINAL Page 31 of 6 REV. 0 operating test.doc

JPM TITLE: AUTHORIZE GAS DECAY TANK JPM NUMBER: NRCADM061-RC-SRO DISCHARGE INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Review Sample Information and 2.1 Identifies that a second sample of the Analysis information for GDT should have been done, since RE-accuracy. 22 is inoperable.

Step was: Sat: ______ Unsat _______*

2. Review Release Authorization 2.2 Determines that Release Authorization (CHEM) for accuracy. (CHEM) is correct.

Step was: Sat: ______ Unsat _______*

3. Review Release Information and 3.2 Identifies that Gas Decay Tank Pressure Approval for accuracy. has decreased by 6 psig.

Step was: Sat: ______ Unsat _______*

• • 4. Determine if Authorization 4.1 Determines that the Authorization should be approved. should not be approved, based on either condition not meeting the procedural requirements.

Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

DC-2008-06-FINAL Page 32 of 6 REV. 0 OPERATING TEST.DOC

JPM NUMBER: NRCADM061-RC-SRO EXAMINEE CUE SHEET Initial Conditions: RE-22, Gaseous Discharge Radiation Monitor was declared inoperable on June 6th, 2008 @ 1350 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.13675e-4 months <br />.

It is June 16th, 2008. You are the Unit 1 Shift Foreman. Gas Decay Tank 1-1 is planned to be discharged today on your watch.

You have just received the Authorization for a Gas Decay Tank Discharge attachment from CAP A-6, from the control operator for your final approval.

Initiating Cue: As the Unit 1 Shift Foreman review the discharge authorization form for accuracy and completeness. Document any discrepancies noted and determine if the discharge should be approved or not approved based on your review.

Technical Errors Identified:

[ ] APPROVE Discharge [ ] DO NOT Approve Discharge DC-2008-06-FINAL Page 33 of 6 REV. 0 OPERATING TEST.DOC

JPM NUMBER: NRCADM061-RC-SRO EXAMINEE CUE SHEET DC-2008-06-FINAL Page 34 of 6 REV. 0 OPERATING TEST.DOC

AUTHORIZE GAS DECAY TANK DISCHARGE JPM NUMBER: NRCADM061-RC-SRO ATTACHMENT 1, SIMULATOR SETUP The simulator is not needed for the performance of this JPM.

DC-2008-06-FINAL Page 35 of 6 REV. 0 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Initial Conditions: RE-22, Gaseous Discharge Radiation Monitor was declared inoperable on June 6th, 2008 @ 1350 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.13675e-4 months <br />.

It is June 16th, 2008. You are the Unit 1 Shift Foreman. Gas Decay Tank 1-1 is planned to be discharged today on your watch.

You have just received the Authorization for a Gas Decay Tank Discharge attachment from CAP A-6, from the control operator for your final approval.

Initiating Cue: As the Unit 1 Shift Foreman review the discharge authorization form for accuracy and completeness. Document any discrepancies noted and determine if the discharge should be approved or not approved based on your review.

Technical Errors Identified:

Section 1: Second sample not completed, required when RE-22 is Inoperable.

P&L 5.3 and Step 6.1.2.b.4 Section 2: Pressure in Gas Decay Tank has dropped 6 PSIG, Discharge Shall not be performed.

P&L 5.8

[ ] APPROVE Discharge [ X ] DO NOT Approve Discharge AUTHOR: DAVID BURNS DATE: 01/24/2008 REV. 1

JPM TITLE: DETERMINATION OF SHIFT STAFFING AND JPM NUMBER: NRCADM061-COO-OVERTIME RESTRICTIONS SRO1 INSTRUCTOR WORKSHEET Number: NRCADM061-COO-SRO1

Title:

Determination of Shift Staffing and Overtime Restrictions Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Designed for SRO Candidates in a classroom setting.

References:

OM14.ID1, Overtime Restrictions, Rev. 12 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 1, 2, 3 DC-2008-06-FINAL Page 37 of 6 REV. 0 operating test.doc

JPM TITLE: DETERMINATION OF SHIFT STAFFING AND JPM NUMBER: NRCADM061-COO-OVERTIME RESTRICTIONS SRO1 INSTRUCTOR WORKSHEET Job Designation: SRO K/A: G 2.1.5; Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Rating: 3.9 DC-2008-06-FINAL Page 38 of 6 REV. 0 operating test.doc

JPM TITLE: DETERMINATION OF SHIFT STAFFING AND JPM NUMBER: NRCADM061-COO-OVERTIME RESTRICTIONS SRO1 INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

Required Materials: OM14.ID1, Overtime Restrictions, Rev. 12 Initial Conditions: Unit One is at 100% power. You are the Unit 1 Shift Foreman and one of the Reactor Operators assigned to work in the control room has called in sick. You have been assigned to find a replacement Reactor Operator.

Initiating Cue: Assuming today is June 16th, based on their work hour history, evaluate whether any of the following 3 Reactor Operators could work from 0700 to 1900 today without advanced approval.

Task Standard: DO NOT READ TO STUDENTS: All Reactor Operators that can work the shift have been identified. This will be documented on the student handout.

DC-2008-06-FINAL Page 39 of 6 REV. 0 operating test.doc

JPM TITLE: DETERMINATION OF SHIFT STAFFING AND JPM NUMBER: NRCADM061-COO-OVERTIME RESTRICTIONS SRO1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

• • 1. Evaluates RO1 previous work 1.2 Identifies that following limit applies.

schedule.

• 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 days.

1.3 Determines that RO1 is not eligible. **

Note: This limit will be exceeded after working today.

Step was: Sat: ______ Unsat _______*

• • 2. Evaluates RO2 previous work 2.1 Determines that no limits have been schedule. exceeded.

2.2 Determines that RO2 is eligible. **

Step was: Sat: ______ Unsat _______*

• • 3. Evaluates RO3 previous work 3.1 Identifies that following limit applies.

schedule.

• 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

3.2 Determines that RO3 is not eligible. **

Note: This limit will be exceeded after working today.

Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

DC-2008-06-FINAL Page 40 of 6 REV. 0 OPERATING TEST.DOC

JPM NUMBER: NRCADM061-COO-SRO1 EXAMINEE CUE SHEET Initial Conditions: Unit One is at 100% power. You are the Unit 1 Shift Foreman and one of the Reactor Operators assigned to work in the control room has called in sick. You have been assigned to find a replacement Reactor Operator.

Initiating Cue: Assuming today is June 16th, based on their work hour history, evaluate whether any of the following 3 Reactor Operators could work from 0700 to 1900 today without advanced approval.

Previous Work Schedule:

Mon Tues Wed Thurs Fri Sat Sun Mon Operator June 9 June 10 June 11 June 12 June 13 June 14 June 15 June 16 RO1 OFF 0700- 0700- 0700- 0700- 0700- 0700-1900 1900 1900 1900 1900 1900 RO2 0700- 0700- 0700- 0700- OFF 0700- 0700-1900 1900 1900 1900 1900 1900 RO3 OFF 0700- 0700- 0700- 0700- OFF 0700-1700 1700 1700 1700 2100 Reactor Operator(s) eligible to work June 16th Yes No RO1 [ ] [ ]

RO2 [ ] [ ]

RO3 [ ] [ ]

DC-2008-06-FINAL Page 41 of 6 REV. 0 OPERATING TEST.DOC

JPM TITLE: DETERMINATION OF SHIFT STAFFING JPM NUMBER: NRCADM061-COO-SRO1 AND OVERTIME RESTRICTIONS ATTACHMENT 1, SIMULATOR SETUP The simulator is not needed for the performance of this JPM.

DC-2008-06-FINAL Page 42 of 6 REV. 0 OPERATING TEST.DOC

JPM TITLE: DETERMINATION OF SHIFT STAFFING AND JPM NUMBER: NRCADM061-COO-SRO1 OVERTIME RESTRICTIONS ANSWER KEY Initial Conditions: Unit One is at 100% power. You are the Unit 1 Shift Foreman and one of the Reactor Operators assigned to work in the control room has called in sick. You have been assigned to find a replacement Reactor Operator.

Initiating Cue: Assuming today is June 16th, based on their work hour history, evaluate whether any of the following 3 Reactor Operators could work from 0700 to 1900 today without advanced approval.

DC-2008-06-FINAL Page 43 of 6 REV. 0 OPERATING TEST.DOC

JPM TITLE: DETERMINATION OF SHIFT STAFFING AND JPM NUMBER: NRCADM061-COO-SRO1 OVERTIME RESTRICTIONS ANSWER KEY Previous Work Schedule:

Mon Tues Wed Thurs Fri Sat Sun Mon Operator June 9 June 10 June 11 June 12 June 13 June 14 June 15 June 16 RO1 OFF 0700- 0700- 0700- 0700- 0700- 0700-1900 1900 1900 1900 1900 1900 RO2 0700- 0700- 0700- 0700- OFF 0700- 0700-1900 1900 1900 1900 1900 1900 RO3 OFF 0700- 0700- 0700- 0700- OFF 0700-1700 1700 1700 1700 2100 Reactor Operator(s) eligible to work June 16th Yes No RO1 [ ] [X]

RO2 [X] [ ]

RO3 [ ] [X]

DC-2008-06-FINAL Page 44 of 6 REV. 0 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCADM061-COO-SRO2

Title:

Approve Movement of Spent Fuel Assemblies Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Designed for SRO Candidates in a classroom setting.

References:

OP B-8DS3, Insert Shuffle Within the Spent Fuel Pool, Rev. 18 Tech Spec 3.7.17, Spent Fuel Assembly Storage, Rev. 9 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 1, 2, 3, 4 Job Designation: SRO K/A: G 2.1.40; Knowledge of refueling administrative requirements.

Rating: 3.9 AUTHOR: DAVID BURNS DATE: 01/24/2008 REV. 1

JPM TITLE: APPROVE MOVEMENT OF SPENT FUEL JPM NUMBER: NRCADM061-COO-ASSEMBLIES SRO2 INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

Required Materials: Tech Spec 3.7.17, Spent Fuel Assembly Storage, Rev. 9 Initial Conditions: Unit One is at 100% power. Reactor Engineering is planning to move several spent fuel assemblies from the permanent storage racks in the spent fuel pool to the new cask pit storage rack.

Initiating Cue: You are the SRO assigned to review the proposed changes. Review each change and determine if the proposed move to the cask pit storage rack should be allowed or dis-allowed, based on the conditions given for each assembly.

Task Standard: DO NOT READ TO STUDENTS: Determination of proper storage location for each fuel assembly in made. This will be documented on the student handout.

DC-2008-06-FINAL Page 46 of 7 REV. 0 OPERATING TEST.DOC

JPM TITLE: APPROVE MOVEMENT OF SPENT FUEL JPM NUMBER: NRCADM061-COO-ASSEMBLIES SRO2 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

• • 1. Determine if Element K-24 can 2.1 Determines that the assembly discharge be placed in the Cask Pit Storage burn up and Initial Enrichment is in the Rack. acceptable region on Figure 3.7.17-4 2.1 Determines that Decay time is less than allowable limit.

2.1 Determines that the assembly should not be moved to the Cask Pit Storage Rack.

Step was: Sat: ______ Unsat _______*

2. Determine if Element F-06 can 2.1 Determines that the assembly discharge be placed in the Cask Pit Storage burn up and Initial Enrichment is in the Rack. acceptable region on Figure 3.7.17-4 2.2 Determines that Decay time meets allowable limit.

2.3 Determines that the assembly can be moved to the Cask Pit Storage Rack.

Step was: Sat: ______ Unsat _______*

• • 3. Determine if Element G-17 can 3.1 Determines that the assembly discharge be placed in the Cask Pit Storage burn up and Initial Enrichment is in the Rack. Unacceptable region on Figure 3.7.17-4 3.2 Determines that Decay time meets the allowable limit.

3.3 Determines that the assembly should not be moved to the Cask Pit Storage Rack.

Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

DC-2008-06-FINAL Page 47 of 7 REV. 0 OPERATING TEST.DOC

JPM TITLE: APPROVE MOVEMENT OF SPENT FUEL JPM NUMBER: NRCADM061-COO-ASSEMBLIES SRO2 INSTRUCTOR WORKSHEET

• • 4. Determine if Element D-32 can 4.1 Determines that the assembly discharge be placed in the Cask Pit Storage burn up and Initial Enrichment is in the Rack. acceptable region on Figure 3.7.17-4 4.2 Determines that Decay time meets allowable limit.

4.3 Determines that the assembly can be moved to the Cask Pit Storage Rack.

Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

DC-2008-06-FINAL Page 48 of 7 REV. 0 OPERATING TEST.DOC

JPM NUMBER: NRCADM061-COO-SRO2 EXAMINEE CUE SHEET Initial Conditions: Unit One is at 100% power. Reactor Engineering is planning to move several spent fuel assemblies from the permanent storage racks in the spent fuel pool to the new cask pit storage rack.

Initiating Cue: You are the SRO assigned to review the proposed changes. Review each change and determine if the proposed move to the cask pit storage rack should be allowed or dis-allowed, based on the conditions given for each assembly.

Element Initial Discharge Decay Allow or Dis-allow Enrichment Burnup Time (wt% U-235) (GWd/mtU) (Years)

K-24 3.0 26 8 Allow [ ] Dis-allow [ ]

F-06 3.25 23 12 Allow [ ] Dis-allow [ ]

G-17 3.5 21 11 Allow [ ] Dis-allow [ ]

D-32 3.5 25 14 Allow [ ] Dis-allow [ ]

DC-2008-06-FINAL Page 49 of 7 REV. 0 OPERATING TEST.DOC

JPM TITLE: APPROVE MOVEMENT OF SPENT FUEL JPM NUMBER: NRCADM061-COO-ASSEMBLIES SRO2 ATTACHMENT 1, SIMULATOR SETUP The simulator is not needed for the performance of this JPM.

DC-2008-06-FINAL Page 50 of 7 REV. 0 OPERATING TEST.DOC

JPM TITLE: APPROVE MOVEMENT OF SPENT FUEL JPM NUMBER: NRCADM061-COO-ASSEMBLIES SRO2 ANSWER KEY Initial Conditions: Unit One is at 100% power. Reactor Engineering is planning to move several spent fuel assemblies from the permanent storage racks in the spent fuel pool to the new cask pit storage rack.

Initiating Cue: You are the SRO assigned to review the proposed changes. Review each change and determine if the proposed move to the cask pit storage rack should be allowed or dis-allowed based on the conditions given for each assembly.

DC-2008-06-FINAL Page 51 of 7 REV. 0 OPERATING TEST.DOC

JPM TITLE: APPROVE MOVEMENT OF SPENT FUEL JPM NUMBER: NRCADM061-COO-ASSEMBLIES SRO2 ANSWER KEY Element Initial Discharge Decay Allow or Dis-allow Enrichment Burnup Time (wt% U-235) (GWd/mtU) (Years)

K-24 3.0 26 8 Allow [ ] Dis-allow [ X ]

F-06 3.25 23 12 Allow [ X ] Dis-allow [ ]

G-17 3.5 21 11 Allow [ ] Dis-allow [ X ]

D-32 3.5 25 14 Allow [ X ] Dis-allow [ ]

DC-2008-06-FINAL Page 52 of 7 REV. 0 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCADM061-EC-SRO

Title:

Evaluate Clearance Points and Tagging Requirements Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Designed for SRO Candidates in a classroom setting.

References:

OP F-1:III, Service Cooling Water - Shutdown and Clearing, Rev. 16 OP2.ID2; Tagging Requirements, Rev. 12 OVID 106715, Sheet 2, Rev. 43 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 1, 2, 3 Job Designation: SRO K/A: G 2.2.13; Knowledge of tagging and clearance procedures.

Rating: 4.3 AUTHOR: DAVID BURNS DATE: 01/24/2008 REV. 1

JPM TITLE: DETERMINE CLEARANCE POINTS JPM NUMBER: NRCADM061-EC-SRO INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.

Required Materials: OP F-1:III, Service Cooling Water - Shutdown and Clearing, Rev. 16 OP2.ID2; Tagging Requirements, Rev. 12 OVID 106715, Sheet 2, Rev. 43 Initial Conditions: Unit One is at 100% power. Maintenance is planned for SCW Pump 1-1 to replace the pump Impeller. A clearance requiring the pump to be isolated, vented and drained is required.

Initiating Cue: The Work Control Shift Foreman has directed you to verify all the clearance points and their respective positions for this clearance, along with the appropriate tagging requirements. Document any discrepancies noted.

Task Standard: DO NOT READ TO STUDENTS: All clearance points are identified with required position and proper tagging requirements. This will be documented on the student handout.

DC-2008-06-FINAL Page 54 of 6 REV. 0 operating test.doc

JPM TITLE: DETERMINE CLEARANCE POINTS JPM NUMBER: NRCADM061-EC-SRO INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

• • 1. Identify breaker for isolation of 2.1 Identifies that a DANGER tag should be SCWP 1-1, power supply is used for this component:

tagged incorrectly.

• 52-11D-05 (motor)

Step was: Sat: ______ Unsat _______*

• • 2. Identify discharge valve is 2.3 Identifies the following valve should be required to be re-positioned for CLOSED:

isolation of SCWP 1-1, check valve is not allowed isolation

• SCW-1-9 discharge valve point.

Step was: Sat: ______ Unsat _______*

• • 3. Identify additional valve required 3.3 Identifies the following valves OPEN.

to be opened to drain and vent SCWP 1-1.

• SCW-1-423 pump discharge drain NOTE: Student may identify PJ-11-1, Breaker 5 as additional point; this is not required for work on the pump.

3.2 Identifies that a CAUTION Tag should be used for this components.

Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

DC-2008-06-FINAL Page 55 of 6 REV. 0 OPERATING TEST.DOC

JPM NUMBER: NRCADM061-EC-SRO EXAMINEE CUE SHEET Initial Conditions: Unit One is at 100% power. Maintenance is planned for SCW Pump 1-1 to replace the pump Impeller. A clearance requiring the pump to be isolated, vented and drained is required.

Initiating Cue: The Work Control Shift Foreman has directed you to verify all the clearance points and their respective positions for this clearance, along with the appropriate tagging requirements. Document any discrepancies noted.

Component ID DESCRIPTION CLEARED TAGGING POSITION REQUIREMENT SCW PP-1-1 Control Switch OFF CBC 52-11D-05 SCW Pump 1-1 480 v Supply OPEN CAUTION SCW-1-293 SCW Pump 1-1 Discharge Valve CLOSED DANGER SCW-1-1 SCW Pump 1-1 Suction Valve CLOSED DANGER SCW 1-3 SCW Pump 1-1 Suction Drain Valve OPEN CAUTION SCW 1-5 SCW Pump 1-1 Casing Vent Valve OPEN CAUTION SCW-1-7 SCW Pump 1-1 Discharge Drain Valve OPEN CAUTION Discrepancies found DC-2008-06-FINAL Page 56 of 6 REV. 0 OPERATING TEST.DOC

JPM

Title:

Determine Clearance Points JPM NUMBER: NRCADM061-EC-SRO ATTACHMENT 1, SIMULATOR SETUP DC-2008-06-FINAL Page 57 of 6 REV. 0 OPERATING TEST.DOC

JPM

Title:

Determine Clearance Points JPM NUMBER: NRCADM061-EC-SRO ATTACHMENT 1, SIMULATOR SETUP The simulator is not needed for the performance of this JPM.

DC-2008-06-FINAL Page 58 of 6 REV. 0 OPERATING TEST.DOC

JPM

Title:

Determine Clearance Points JPM NUMBER: NRCADM061-EC-SRO ANSWER KEY Initial Conditions: Unit One is at 100% power. Maintenance is planned for SCW Pump 1-1 to replace the pump Impeller. A clearance requiring the pump to be isolated, vented and drained is required.

Initiating Cue: The Work Control Shift Foreman has directed you to verify all the clearance points and their respective positions for this clearance, along with the appropriate tagging requirements. Document any discrepancies noted.

DC-2008-06-FINAL Page 59 of 6 REV. 0 OPERATING TEST.DOC

JPM

Title:

Determine Clearance Points JPM NUMBER: NRCADM061-EC-SRO ANSWER KEY Component ID DESCRIPTION CLEARED TAGGING POSITION REQUIREMENT SCW PP-1-1 Control Switch OFF CBC 52-11D-05 SCW Pump 1-1 480 v Supply OPEN CAUTION SCW-1-293 SCW Pump 1-1 Discharge Valve CLOSED DANGER SCW-1-1 SCW Pump 1-1 Suction Valve CLOSED DANGER SCW 1-3 SCW Pump 1-1 Suction Drain Valve OPEN CAUTION SCW 1-5 SCW Pump 1-1 Casing Vent Valve OPEN CAUTION SCW-1-7 SCW Pump 1-1 Discharge Drain Valve OPEN CAUTION Discrepancies found Component ID DESCRIPTION CLEARED TAGGING POSITION REQUIREMENT 52-11D-05 SCW Pump 1-1 480 v Supply OPEN DANGER SCW-1-9 not SCW Pump 1-1 Discharge Valve CLOSED DANGER SCW-1-293 SCW-1-423 SCW Pump 1-1 Discharge Drain Valve OPEN CAUTION Student may identify PJ-11-1, Breaker 5 as additional point; this is not required for work on the pump.

DC-2008-06-FINAL Page 60 of 6 REV. 0 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCADM061-EP-SRO

Title:

CLASSIFY AN EARTHQUAKE WITH A RADIATION RELEASE Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: The simulator is not needed for the performance of this JPM.

References:

DCPP Emergency Action Level Matrix & Background Document Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 2 Job Designation: SRO K/A: G 2.4.41; Knowledge of the emergency action level thresholds and classifications.

Rating: 4.6 AUTHOR: DAVID BURNS DATE: 01/28/08 REV. 1

JPM

Title:

CLASSIFY AN EARTHQUAKE WITH A JPM Number:

RADIATION RELEASE NRCADM061-EP-SRO Instructor Worksheet Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.

Required Materials: DCPP Emergency Action Level Matrix & Background Document.

Initial Conditions: Unit 1 is at 100% power. An earthquake of magnitude 0.23g has been felt in the control room and confirmed by PK 15-24 annuciator SEISMIC INSTR SYSTEM.

The auxiliary board operator reports that gas decay tank 11 was full and has suddenly depressurized. RE-14 and RE-14R have gone into alarm and investigation shows that they channel check and are reading Offscale high. RE-87 is currently reading 4.0E0 µCi/cc.

A Dose Assessment using EP R-2, Release of Airborne Radioactive Materials Initial Assessment has been performed using PPC Meteorological Data.

The following results are predicted at the site boundary:

TEDE: 150 mR Thyroid CDE: 600 mR Initiating Cue: Determine the proper event classification and report results to the Shift Manager.

Task Standard: DO NOT READ TO STUDENT: The proper event classification is determined and the results reported to the Shift Manager.

DC-2008-06-FINAL Page 62 of 280 REV. 0 OPERATING TEST.DOC

JPM

Title:

CLASSIFY AN EARTHQUAKE WITH A JPM Number:

RADIATION RELEASE NRCADM061-EP-SRO Instructor Worksheet Start Time:

Step Expected Operator Actions

1. Obtain correct procedure. 1.1 References DCPP Emergency Action Level Matrix.

Step was: Sat: _______ Unsat ______*

• • 2. DCPP Emergency Action Level 2.1 Determines the Earthquake event is Matrix or EP G-1. an ALERT (HA 1.1).

2.2 Determines the Gas Decay Tank Release event is a SITE AREA EMERGENCY (RS 1.2)**

Note: Order of classification is not important, final classification is critical step.

Step was: Sat: _______ Unsat ______*

3. Report Event Classification 3.1 Reports to Shift Manager an initial classification of Site Area Emergency.

Step was: Sat: _______ Unsat ______*

Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL Page 63 of 280 REV.1 OPERATING TEST.DOC

JPM Number:

NRCADM061-EP-SRO Examinee Cue Sheet Initial Conditions: Unit 1 is at 100% power. An earthquake of magnitude 0.23g has been felt in the control room and confirmed by PK 15-24 annuciator SEISMIC INSTR SYSTEM.

The auxiliary board operator reports that gas decay tank 11 was full and has suddenly depressurized. RE-14 and RE-14R have gone into alarm and investigation shows that they channel check and are reading Offscale high. RE-87 is currently reading 4.0E0 µCi/cc.

A Dose Assessment using EP R-2, Release of Airborne Radioactive Materials Initial Assessment has been performed using PPC Meteorological Data.

The following results are predicted at the site boundary:

TEDE: 150 mR Thyroid CDE: 600 mR Initiating Cue: Determine the proper event classification and report results to the Shift Manager.

Document Your Answer Here DC-2008-06-FINAL Page 64 of 280 REV.1 OPERATING TEST.DOC

JPM

Title:

CLASSIFY AN EARTHQUAKE WITH A JPM Number:

RADIATION RELEASE NRCADM061-EP-SRO , Simulator Setup DC-2008-06-FINAL Page 65 of 280 REV.1 OPERATING TEST.DOC

JPM

Title:

CLASSIFY AN EARTHQUAKE WITH A JPM Number:

RADIATION RELEASE NRCADM061-EP-SRO Attachment 1, Simulator Setup The simulator is not needed for the performance of this JPM.

DC-2008-06-FINAL Page 66 of 280 REV.1 OPERATING TEST.DOC

JPM

Title:

CLASSIFY AN EARTHQUAKE WITH A JPM Number:

RADIATION RELEASE NRCADM061-EP-SRO Attachment 1, Simulator Setup Initial Conditions: Unit 1 is at 100% power. An earthquake of magnitude 0.23g has been felt in the control room and confirmed by PK 15-24 annuciator SEISMIC INSTR SYSTEM.

The auxiliary board operator reports that gas decay tank 11 was full and has suddenly depressurized. RE-14 and RE-14R have gone into alarm and investigation shows that they channel check and are reading Offscale high. RE-87 is currently reading 4.0E0 µCi/cc.

A Dose Assessment using EP R-2, Release of Airborne Radioactive Materials Initial Assessment has been performed using PPC Meteorological Data.

The following results are predicted at the site boundary:

TEDE: 150 mR Thyroid CDE: 600 mR Initiating Cue: Determine the proper event classification and report results to the Shift Manager.

Document Your Answer Here Earthquake event is an ALERT (HA 1.1).

Gas Decay Tank Release event is a SITE AREA EMERGENCY (RS 1.2)

EVENT CLASSIFICATION IS: SITE AREA EMERGENCY (RS 1.2)

DC-2008-06-FINAL Page 67 of 280 REV.1 OPERATING TEST.DOC

JPM

Title:

CLASSIFY AN EARTHQUAKE WITH A JPM Number:

RADIATION RELEASE NRCADM061-EP-SRO , Simulator Setup DC-2008-06-FINAL Page 68 of 280 REV.1 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC-IPSi

Title:

PERFORM A LOCAL START OF A DIESEL GENERATOR Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Direct from DCPP Bank - LJP-038 This JPM is Written for use on Unit 1, ensure associated procedure is correct.

References:

OP AP-8A, Control Room Inaccessibility, Establishing Hot Standby, Rev. 21 (Unit 1)

Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 1, 2, 3, 4, 7, 8 Job Designation: RO/SROI/SROU Task Number: 6/064/A4.01 Rating: 4.0/4.3 AUTHOR: DAVID BURNS DATE: 01/21/08 REV. 1

JPM TITLE: PERFORM A LOCAL START OF A DIESEL JPM NUMBER:

GENERATOR NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.

Required Materials: Copy of OP AP-8A, Attachment 6.3, Step 3.

Initial Conditions: A vertical board fire has required an evacuation of the Control Room.

Plant control has been established from the Hot Shutdown Panel.

Initiating Cue: The Shift Foreman directs you to establish local control and start diesel generator 12 in accordance with OP AP-8A, Attachment 6.3, step 3.

Task Standard: Diesel generator 12 has been started in accordance with OP AP-8A.

DC-2008-06-FINAL PAGE 70 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: PERFORM A LOCAL START OF A DIESEL JPM NUMBER:

GENERATOR NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

• • 1. Place the Droop Switch on the 1.1 Reads CAUTION prior to Step 3.

excitation cubicle to the ISOC position. 1.2 Locates the diesel generator 12 Droop Switch on the excitation cubicle.

1.3 Places the droop switch in the ISOC position.**

Step was: Sat: ______ Unsat _______*

• • 2. Verify Mode Control selector 2.1 Locates the Mode Control selector switch on the local control panel is switch on the diesel generator 12 to the TEST position. local control panel.

2.2 Places the Mode Control selector switch in the TEST position. **

Step was: Sat: ______ Unsat _______*

• • 3. Place the diesel generator Control 3.1 Locates the diesel generator 12 Selection switch on the excitation Control Selection switch on the cubicle to the LOCAL position. excitation cubicle.

3.2 Places the Control Selection switch in the LOCAL position. **

Step was: Sat: ______ Unsat _______*

• • 4. Place the Appendix R Fuse 4.1 Locates the 43DC-12/SS switch on Selector switch 43DC-12/SS to the the diesel generator 12 local control BACKUP position. panel.

4.2 Places the Appendix R Fuse Selector switch 43DC-12/SS to the BACKUP position. **

Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 71 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: PERFORM A LOCAL START OF A DIESEL JPM NUMBER:

GENERATOR NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

5. Depress the Alarm Relay Reset 5.1 Locates alarm relay reset push button push button. on diesel generator 12 local control panel.

5.2 Depresses Alarm Relay Reset pushbutton.

Step was: Sat: ______ Unsat _______*

6. Place the Engine Control switch 6.1 Reads NOTE.

on the local control panel to the START position.

6.2 Locates the Engine Control switch at the diesel generator 12 local control panel.

6.3 Places the Engine Control switch to the START position.

Cue: No change in room observed.

Step was: Sat: ______ Unsat _______*

• • 7. Place the 125VDC Control 7.1 Locates control power transfer switch Power Transfer Switch, EQD-12, EQD-12 opposite the diesel generator to the BACKUP position. 12 local control panel.

7.2 Moves the transfer switch down to the BACKUP PWR SUP position. **

Cue: The normal power supply light is OFF and the backup power supply light is ON.

Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 72 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: PERFORM A LOCAL START OF A DIESEL JPM NUMBER:

GENERATOR NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 8. Restart the diesel generator. 8.1 Locates the Engine Control switch at the diesel generator 12 local control panel.

8.2 Places the Engine Control switch to the START position. **

Note: Various parameters indicate the D/G is running, including:

• Noise in room

• Lube oil pressure increasing

• Fuel oil pressure increasing

• Jacket water pressure increasing Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 73 OF 280 REV. 1 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initial Conditions: Unit One is at 100% power. A concern over the accuracy of the Steam Generator Level indication has been raised.

Initiating Cue: The Shift Foreman has requested you CHANNEL CHECK the current Steam Generator Levels and report any channels that do not meet the CHANNEL CHECK requirement outlined in OPS Policy B-5; Channel Check Criteria.

Task Standard: DO NOT READ TO STUDENT: Maximum Stay time is calculated.

DC-2008-06-FINAL PAGE 74 OF 280 REV. 1 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET DC-2008-06-FINAL PAGE 75 OF 280 REV. 1 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC-IPSi

Title:

PERFORM A LOCAL START OF A DIESEL GENERATOR Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Direct from DCPP Bank - LJP-038 This JPM is Written for use on Unit 2, ensure associated procedure is correct.

References:

OP AP-8A, Control Room Inaccessibility, Establishing Hot Standby, Rev. 18B (Unit 2)

Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 1, 2, 3, 4, 7, 8 Job Designation: RO/SROI/SROU Task Number: 6/064/A4.01 Rating: 4.0/4.3 AUTHOR: DAVID BURNS DATE: 01/21/08 REV. 1

JPM TITLE: PERFORM A LOCAL START OF A DIESEL JPM NUMBER:

GENERATOR NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.

Required Materials: Copy of OP AP-8A, Attachment 6.3, Step 3.

Initial Conditions: A vertical board fire has required an evacuation of the Control Room.

Plant control has been established from the Hot Shutdown Panel.

Initiating Cue: The Shift Foreman directs you to establish local control and start diesel generator 21 in accordance with OP AP-8A, Attachment 6.3, step 3.

Task Standard: Diesel generator 21 has been started in accordance with OP AP-8A.

DC-2008-06-FINAL PAGE 77 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: PERFORM A LOCAL START OF A DIESEL JPM NUMBER:

GENERATOR NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

• • 1. Place the Droop Switch on the 1.1 Reads CAUTION prior to Step 3.

excitation cubicle to the ISOC position. 1.2 Locates the diesel generator 21 Droop Switch on the excitation cubicle.

1.3 Places the droop switch in the ISOC position.**

Step was: Sat: ______ Unsat _______*

• • 2. Verify Mode Control selector 2.1 Locates the Mode Control selector switch on the local control panel is switch on the diesel generator 21 to the TEST position. local control panel.

2.2 Places the Mode Control selector switch in the TEST position. **

Step was: Sat: ______ Unsat _______*

• • 3. Place the diesel generator Control 3.1 Locates the diesel generator 21 Selection switch on the excitation Control Selection switch on the cubicle to the LOCAL position. excitation cubicle.

3.2 Places the Control Selection switch in the LOCAL position. **

Step was: Sat: ______ Unsat _______*

• • 4. Place the Appendix R Fuse 4.1 Locates the 43DC-21/SS switch on Selector switch 43DC-21/SS to the the diesel generator 22 local control BACKUP position. panel.

4.2 Places the Appendix R Fuse Selector switch 43DC-21/SS to the BACKUP position. **

Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 78 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: PERFORM A LOCAL START OF A DIESEL JPM NUMBER:

GENERATOR NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

5. Depress the Alarm Relay Reset 5.1 Locates alarm relay reset push button push button. on diesel generator 21 local control panel.

5.2 Depresses Alarm Relay Reset pushbutton.

Step was: Sat: ______ Unsat _______*

6. Place the Engine Control switch 6.1 Reads NOTE.

on the local control panel to the START position.

6.2 Locates the Engine Control switch at the diesel generator 21 local control panel.

6.3 Places the Engine Control switch to the START position.

Cue: No change in room observed.

Step was: Sat: ______ Unsat _______*

• • 7. Place the 125VDC Control 7.1 Locates control power transfer switch Power Transfer Switch, EQD-21, EQD-21 opposite the diesel generator to the BACKUP position. 21 local control panel.

7.2 Moves the transfer switch down to the BACKUP PWR SUP position. **

Cue: The normal power supply light is OFF and the backup power supply light is ON.

Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 79 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: PERFORM A LOCAL START OF A DIESEL JPM NUMBER:

GENERATOR NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 8. Restart the diesel generator. 8.1 Locates the Engine Control switch at the diesel generator 21 local control panel.

8.2 Places the Engine Control switch to the START position. **

Note: Various parameters indicate the D/G is running, including:

• Noise in room

• Lube oil pressure increasing

• Fuel oil pressure increasing

• Jacket water pressure increasing Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 80 OF 280 REV. 1 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initial Conditions: Unit One is at 100% power. A concern over the accuracy of the Steam Generator Level indication has been raised.

Initiating Cue: The Shift Foreman has requested you CHANNEL CHECK the current Steam Generator Levels and report any channels that do not meet the CHANNEL CHECK requirement outlined in OPS Policy B-5; Channel Check Criteria.

Task Standard: DO NOT READ TO STUDENT: Maximum Stay time is calculated.

DC-2008-06-FINAL PAGE 81 OF 280 REV. 1 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET DC-2008-06-FINAL PAGE 82 OF 280 REV. 1 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC-IPSj

Title:

CLOSE AN MSIV LOCALLY Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Direct from DCPP Bank - LJP-008 This JPM is written for use on Unit 1, ensure associated procedure is correct.

References:

EOP E-2, Faulted Steam Generator Isolation, Appendix L, Rev. 16, (Unit 1).

Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 1, 2, 3, 4 Job Designation: RO/SROI/SROU Task Number: 4P/035/A4.06 Rating: 4.5/4.6 AUTHOR: DAVID BURNS DATE: 01/21/08 REV. 1

JPM TITLE: CLOSE AN MSIV LOCALLY JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.

Required Materials: Procedure EOP E-2, Appendix L.

Initial Conditions: A main steam line rupture has occurred on Unit 1 downstream of the MSIVs. MSIV FCV-41 has failed to close automatically. Manual attempts to close it from VB-3 have also been unsuccessful. FCV-41 bypass valve, FCV-25 is closed.

Initiating Cue: The Shift Foreman directs you to locally CLOSE MSIV FCV-41 in accordance with Appendix L of EOP E-2.

Task Standard: Unit 1 MSIV FCV-41 has been CLOSED in accordance with Appendix L of EOP E-2.

DC-2008-06-FINAL PAGE 84 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: CLOSE AN MSIV LOCALLY JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

• • 1. Obtains appropriate tools 1.1 Locates the following tools.

• Crescent Wrench

• Diagonal Cutters or equivialent

• Flashlight Step was: Sat: ______ Unsat _______*

• • 2. Locally CLOSE MSIV air 2.1 Locates and CLOSES supply or common air supply Common air supply valve valves.

AIR-I-1-3302.**

OR MSIV air supply valve AIR-I-1-4061.**

Step was: Sat: ______ Unsat _______*

• • 3. REMOVES BOTH 3.1 REMOVES BOTH both 3/4 accumulator 3/4 inch drain accumulator drain caps.**

caps.

Step was: Sat: ______ Unsat _______*

• • 4. OPEN MSIV air accumulator 4.1 OPENS drain valves drain valves.

AIR-I-1-1207 **

AND AIR-I-1-1208 **

Cue: You hear the flow of steam stop.

If asked the Control Room reports that FCV-41 has closed.

4.2 Reports to the Control Room that FCV-41 is closed.

Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 85 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: CLOSE AN MSIV LOCALLY JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 86 OF 280 REV. 1 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initial Conditions: Unit One is at 100% power. A concern over the accuracy of the Steam Generator Level indication has been raised.

Initiating Cue: The Shift Foreman directs you to locally CLOSE MSIV FCV-41 in accordance with Appendix L of EOP E-2.

Task Standard: DO NOT READ TO STUDENT: Maximum Stay time is calculated.

DC-2008-06-FINAL PAGE 87 OF 280 REV. 0 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET DC-2008-06-FINAL PAGE 88 OF 280 REV. 0 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC-IPSj

Title:

CLOSE AN MSIV LOCALLY Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Direct from DCPP Bank - LJP-008 This JPM is written for use on Unit 2, ensure associated procedure is correct.

References:

EOP E-2, Faulted Steam Generator Isolation, Appendix L, Rev. 12, (Unit 2).

Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 1, 2, 3, 4 Job Designation: RO/SROI/SROU Task Number: 4P/035/A4.06 Rating: 4.5/4.6 AUTHOR: DAVID BURNS DATE: 01/21/08 REV. 1

JPM TITLE: CLOSE AN MSIV LOCALLY JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.

Required Materials: Procedure EOP E-2, Appendix L.

Initial Conditions: A main steam line rupture has occurred on Unit 2 downstream of the MSIVs. MSIV FCV-41 has failed to close automatically. Manual attempts to close it from VB-3 have also been unsuccessful. FCV-41 bypass valve, FCV-25 is closed.

Initiating Cue: The Shift Foreman directs you to locally CLOSE MSIV FCV-41 in accordance with Appendix L of EOP E-2.

Task Standard: Unit 2 MSIV FCV-41 has been CLOSED in accordance with Appendix L of EOP E-2.

DC-2008-06-FINAL PAGE 90 OF 280 REV. 0 OPERATING TEST.DOC

JPM TITLE: CLOSE AN MSIV LOCALLY JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtains appropriate tools 1.1 Locates the following tools.

• Crescent Wrench

• Diagonal Cutters or equivialent

• Flashlight Step was: Sat: ______ Unsat _______*

• • 2. Locally CLOSE MSIV air supply 2.1 Locates and CLOSES or common air supply valves.

Common air supply valve AIR-I-2-3302.**

OR MSIV air supply valve AIR-I-2-4034.**

Step was: Sat: ______ Unsat _______*

• • 3. REMOVES BOTH accumulator 3.1 REMOVES BOTH both 3/4 3/4 inch drain caps. accumulator drain caps.**

Step was: Sat: ______ Unsat _______*

• • 4. OPEN MSIV air accumulator 4.1 OPENS drain valves drain valves.

AIR-I-2-1207**

AND AIR-I-2-1208 **

Cue: You hear the flow of steam stop.

If asked the Control Room reports that FCV-41 has closed.

4.2 Reports to the Control Room that FCV-41 is closed.

Step was: Sat: ______ Unsat _______*

Stop Time:

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 91 OF 280 REV. 0 OPERATING TEST.DOC

JPM TITLE: CLOSE AN MSIV LOCALLY JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 92 OF 280 REV. 0 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initial Conditions: Unit One is at 100% power. A concern over the accuracy of the Steam Generator Level indication has been raised.

Initiating Cue: The Shift Foreman directs you to locally CLOSE MSIV FCV-41 in accordance with Appendix L of EOP E-2.

Task Standard: DO NOT READ TO STUDENT: Maximum Stay time is calculated.

DC-2008-06-FINAL PAGE 93 OF 280 REV. 0 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET DC-2008-06-FINAL PAGE 94 OF 280 REV. 0 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC-IPSk

Title:

ESTABLISH BACKUP COOLING TO A CENTRIFUGAL CHARGING PUMP Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Direct from DCPP bank - LJP-130 This JPM is written for use on Unit 1, ensure associated procedure is correct.

References:

OP AP SD-4, Loss of Component Cooling Water, Rev. 16 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 25 minutes Critical Steps: 1, 2, 3, 5, 6, 8, 9 Job Designation: RO/SROI/SROU Task Number: 02/004/K1.18 Rating: 2.9/3.2 AUTHOR: DAVID BURNS DATE: 1/21/08 REV. 1

JPM TITLE: ESTABLISH BACKUP COOLING TO A CENTRIFUGAL JPM NUMBER:

CHARGING PUMP NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.

Required Materials: Copy of OP AP SD-4, Appendix C.

Initial Conditions: Unit 1 was operating in MODE 5 with preparations being made to transition to MODE 4 when a complete loss of CCW occurred. The SFM has entered OP AP SD-4, Loss of Component Cooling Water.

Initiating Cue: The Shift Foreman directs you to line up backup cooling to CCP 11 in accordance with OP AP SD-4, Appendix C.

Task Standard: Backup cooling has been aligned to CCP 11 in accordance with Appendix C of OP AP SD-4.

DC-2008-06-FINAL PAGE 96 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: ESTABLISH BACKUP COOLING TO A CENTRIFUGAL JPM NUMBER:

CHARGING PUMP NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

• • 1. Locates backup hoses 1.1 Locates backup cooling hoses in CCW 1-3 pump room. **

Step was: Sat: ______ Unsat _______*

• • 2. Connect each of the 2 hoses 2.1 Reads Notes.

2.2 Connects Hose A from:**

• FP-1-347 (sprinkler test valve near #3 CCWp room) to

• Connection on fire door B21 (outside CCP room)

Note: Will need to remove protective plug cap in order to connect hoses to door.

2.3 Connects Hose B from:**

• Connection on fire door B21 to

• FP-1-1295 (manifold on CCP room wall)

Step was: Sat: ______ Unsat _______*

• • 3. Connect each of the 1 hoses. 3.1 Connects Hose C from:**

• Manifold FP-1-1303 to

• Oil cooler CCW-1-700 3.2 Reads Notes 3.3 Connects Hose D from:**

• Oil cooler CVCS-1-488A to

• Floor drain

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 97 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: ESTABLISH BACKUP COOLING TO A CENTRIFUGAL JPM NUMBER:

CHARGING PUMP NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 98 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: ESTABLISH BACKUP COOLING TO A CENTRIFUGAL JPM NUMBER:

CHARGING PUMP NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

4. Verify valves on the process 4.1 Verifies the following valves closed:

manifold to the CCP closed.

a. FP-1-1295

b. FP-1-1296

c. FP-1-1303 Step was: Sat: ______ Unsat _______*

• • 5. Flush the fire main, manifold, and 5.1 Slowly OPENS:

hoses.

a. FP-1-348. **

b. FP-1-1295.**

Note: Sequence of cooler flush is optional.

c. Oil cooler flush:

• disconnect hose at CCW 700, attach flush connector.

• open FP-1-1303 and direct discharge to floor drain for at least 1 minute.

• close FP-1-1303, remove flush connector.

• reconnect hose at CCW 700. **

Step was: Sat: ______ Unsat _______*

• • 6. Reestablish water supply from 6.1 Opens FP-1-1303.**

manifold to cooler inlets.

Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 99 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: ESTABLISH BACKUP COOLING TO A CENTRIFUGAL JPM NUMBER:

CHARGING PUMP NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

7. Verify affected CCP status. 7.1 Reads Caution.

7.2 Calls the control room and requests that the CCP remains shutdown until the alignment is complete.

Cue: CCP 1-1 IS OFF and will remain OFF until alignment is complete.

Step was: Sat: ______ Unsat _______*

• • 8. Isolate CCW inlet and outlet 8.1 Closes the following valves: **

isolation valves to pump coolers.

a. CCW-1-453 Note - will need cutters for sealed valves. b. CCW-1-454 Step was: Sat: ______ Unsat _______*

• • 9. Establish firewater flowpath 9.1 Reads Caution and Notes.

through coolers.

1.1 9.2 Opens the following valves:

1.1.1 a. CVCS-1-488A 1.2 b. CCW-1-700 Note: Operator may notify the control room to expect fire main alarms.

9.3 Verifies a steady stream of water to the floor drain.

Cue: A steady stream of water is flowing into floor drain.

9.4 Throttles FP-1-1303 to adjust flow for 12 gpm to the oil cooler.

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 100 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: ESTABLISH BACKUP COOLING TO A CENTRIFUGAL JPM NUMBER:

CHARGING PUMP NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 101 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: ESTABLISH BACKUP COOLING TO A CENTRIFUGAL JPM NUMBER:

CHARGING PUMP NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

10. Inform the control room of CCP 10.1 Informs the control room that CCP 11 availability. 11 has sufficient cooling for continuous operation.

1.3 Step was: Sat: ______ Unsat Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 102 OF 280 REV. 1 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initial Conditions: Unit One is at 100% power. A concern over the accuracy of the Steam Generator Level indication has been raised.

Initiating Cue: The Shift Foreman has requested you CHANNEL CHECK the current Steam Generator Levels and report any channels that do not meet the CHANNEL CHECK requirement outlined in OPS Policy B-5; Channel Check Criteria.

Task Standard: DO NOT READ TO STUDENT: Maximum Stay time is calculated.

DC-2008-06-FINAL PAGE 103 OF 280 REV. 1 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET DC-2008-06-FINAL PAGE 104 OF 280 REV. 1 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC-IPSk

Title:

ESTABLISH BACKUP COOLING TO A CENTRIFUGAL CHARGING PUMP Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Direct from DCPP bank - LJP-130 This JPM is written for use on Unit 2, ensure associated procedure is correct.

References:

OP AP SD-4, Loss of Component Cooling Water, Rev. 16 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 25 minutes Critical Steps: 1, 2, 3, 5, 6, 8, 9 Job Designation: RO/SROI/SROU Task Number: 02/004/K1.18 Rating: 2.9/3.2 AUTHOR: DAVID BURNS DATE: 1/21/08 REV. 1

JPM TITLE: ESTABLISH BACKUP COOLING TO A CENTRIFUGAL JPM NUMBER:

CHARGING PUMP NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.

Required Materials: Copy of OP AP SD-4, Appendix C.

Initial Conditions: Unit 2 was operating in MODE 5 with preparations being made to transition to MODE 4 when a complete loss of CCW occurred. The SFM has entered OP AP SD-4, Loss of Component Cooling Water.

Initiating Cue: The Shift Foreman directs you to line up backup cooling to CCP 21 in accordance with OP AP SD-4, Appendix C.

Task Standard: Backup cooling has been aligned to CCP 21 in accordance with Appendix C of OP AP SD-4.

DC-2008-06-FINAL PAGE 106 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: ESTABLISH BACKUP COOLING TO A CENTRIFUGAL JPM NUMBER:

CHARGING PUMP NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

• • 1. Locates backup hoses 1.1 Locates backup cooling hoses in back of CCW 2-3 pump room. **

Step was: Sat: ______ Unsat _______*

• • 2. Connect each of the 2 hoses 2.1 Reads Notes.

2.2 Connects Hose A from:**

• FP-2-350 (sprinkler test valve near #3 CCWp room) to

• Connection on fire door B39-2 (outside CCP room) 2.3 Connects Hose B from:**

• Connection on fire door B39-2 to

• FP-2-1295 (manifold on CCP room wall)

Step was: Sat: ______ Unsat _______*

• • 3. Connect each of the 1 hoses. 3.1 Connects Hose C from:**

• Manifold FP-2-1303 to

• Oil cooler CCW-2-700 3.2 Reads Notes 3.3 Connects Hose D from:**

• Oil cooler CVCS-2-582 to

• Floor drain Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 107 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: ESTABLISH BACKUP COOLING TO A CENTRIFUGAL JPM NUMBER:

CHARGING PUMP NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

4. Verify valves on the process 4.1 Verifies the following valves manifold to the CCP closed. closed:

a. FP-2-1295

b. FP-2-1296

c. FP-2-1303 Step was: Sat: ______ Unsat _______*

• • 5. Flush the fire main, manifold, 5.1 Slowly OPENS:

and hoses.

d. FP-2-351. **

e. FP-2-1295. **

Note: Sequence of cooler flush is optional.

f. Oil cooler flush:

• disconnect hose at CCW 700, attach flush connector.

• open FP-2-1303 and direct discharge to floor drain for at least 1 minute.

• close FP-2-1303, remove flush connector.

• reconnect hose at CCW 700. **

Step was: Sat: ______ Unsat _______*

• • 6. Reestablish water supply from 6.1 Opens FP-2-1303.**

manifold to cooler inlets.

Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 108 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: ESTABLISH BACKUP COOLING TO A CENTRIFUGAL JPM NUMBER:

CHARGING PUMP NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

7. Verify affected CCP status. 7.1 Reads Caution.

7.2 Calls the control room and requests that the CCP remains shutdown until the alignment is complete.

Cue: CCP 2-1 IS OFF and will remain OFF until alignment is complete.

Step was: Sat: ______ Unsat _______*

• • 8. Isolate CCW inlet and outlet 8.1 Closes the following valves: **

isolation valves to pump coolers.

c. CCW-2-453 Note - will need cutters for sealed valves. d. CCW-2-454 Step was: Sat: ______ Unsat _______*

• • 9. Establish firewater flowpath 9.1 Reads Caution and Notes.

through coolers.

1.4 9.2 Opens the following valves:

1.4.1 a. CVCS-2-582 1.5 b. CCW-2-700 Note: Operator may notify the control room to expect fire main alarms.

9.3 Verifies a steady stream of water to the floor drain.

Cue: A steady stream of water is flowing into floor drain.

9.4 Throttles FP-2-1303 to adjust flow for 12 gpm to the oil cooler.

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 109 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: ESTABLISH BACKUP COOLING TO A CENTRIFUGAL JPM NUMBER:

CHARGING PUMP NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 110 OF 280 REV. 1 OPERATING TEST.DOC

JPM TITLE: ESTABLISH BACKUP COOLING TO A CENTRIFUGAL JPM NUMBER:

CHARGING PUMP NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

10. Inform the control room of CCP 10.1 Informs the control room that CCP 21 availability. 21 has sufficient cooling for continuous operation.

1.6 Step was: Sat: ______ Unsat Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 111 OF 280 REV. 1 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initial Conditions: Unit One is at 100% power. A concern over the accuracy of the Steam Generator Level indication has been raised.

Initiating Cue: The Shift Foreman has requested you CHANNEL CHECK the current Steam Generator Levels and report any channels that do not meet the CHANNEL CHECK requirement outlined in OPS Policy B-5; Channel Check Criteria.

Task Standard: DO NOT READ TO STUDENT: Maximum Stay time is calculated.

DC-2008-06-FINAL PAGE 112 OF 280 REV. 1 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET DC-2008-06-FINAL PAGE 113 OF 280 REV. 1 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC-CRSa

Title:

INCREASE ACCUMULATOR PRESSURE Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Modified from DCPP Bank, LJC-077

References:

AR PK02-05, ACCUM PRESSURE HI-LO, Rev. 18A OP B-3B:I, Accumulators - Fill and Pressurize, Rev. 26 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 25 minutes Critical Steps: 4, 5, 6 Job Designation: RO/SROI/SROU Task Number: 3/006/A1.13 Rating: 3.5/3.7 AUTHOR: DAVID BURNS DATE: 01/20/08 REV. 0

JPM TITLE: INCREASE ACCUMULATOR PRESSURE JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.

Required Materials: None Initial Conditions: Unit 1 is 100% power, steady state conditions.

Initiating Cue: Annunciator PK02-05, ACCUM PRESSURE HI-LO, is in alarm, and an investigation indicates low pressure in Accumulator 1-1.

Task Standard: Accumulator pressure is restored and associated alarms are cleared.

DC-2008-06-FINAL PAGE 115 OF 280 REV. 0 OPERATING TEST.DOC

JPM TITLE: INCREASE ACCUMULATOR PRESSURE JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References AR PK02-05.

Step was: Sat: ______ Unsat _______*

2. Verify abnormal condition. 2.1 Reads NOTE.

2.2 Checks PI-960 and PI-961 to verify the alarm is not due to an instrument failure.

Cue: Operability requirements do not have to be addressed at this time.

Step was: Sat: ______ Unsat: _______*

3. Check accumulator level. 3.1 Checks accumulator level 1-1 within alarm limits.

Step was: Sat: ______ Unsat _______*

• • 4. Goes to Section 2.3 Low pressure 4.1 Determines that OP B-3B:I is to be entered to recover pressure. **

Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 116 OF 280 REV. 0 OPERATING TEST.DOC

JPM TITLE: INCREASE ACCUMULATOR PRESSURE JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 5. Goes to step 6.3 of OP B-3B:I. 5.1 Reads NOTE.

5.2 Determines that refilling the accumulator is unnecessary.

5.2 Verifies HCV-943 is closed.

5.3 Checks open valve SI 8880.

5.4 Reads CAUTION.

5.5 Opens accumulator fill and vent isolation valve 8875A.**

5.6 Determines that accumulator pressure is not increasing. **

5.6 Closes SI-1-8875A.

Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 117 OF 280 REV. 0 OPERATING TEST.DOC

JPM TITLE: INCREASE ACCUMULATOR PRESSURE JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET

• • 6. Performs steps to Reset Nitrogen 6.1 Contacts Aux. Control Board and Regulator and repressurize the confirms HP Nitrogen Supply accumulator. Pressure is available.

Cue: HP Nitrogen Pressure is 900 psig.

6.2 Verifies Closed SI-1-8875A**

6.3 Closes SI-1-8880. **

6.4 Reads Caution.

6.5 Cycles HCV-943 open and then closed to reduce pressure down stream of nitrogen regulator.**

6.6 Verifies HCV-943 is closed. **

6.7 Reads Caution.

6.8 Opens SI-1-8880. **

6.9 Open SI-8875A. **

6.10 Monitors accumulator 1-1 pressure and closes SI-8875A when pressure is between 620 and 645 psig.**

Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 118 OF 280 REV. 0 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initial Conditions: Unit One is at 100% power. A concern over the accuracy of the Steam Generator Level indication has been raised.

Initiating Cue: The Shift Foreman has requested you CHANNEL CHECK the current Steam Generator Levels and report any channels that do not meet the CHANNEL CHECK requirement outlined in OPS Policy B-5; Channel Check Criteria.

Task Standard: DO NOT READ TO STUDENT: Maximum Stay time is calculated.

DC-2008-06-FINAL PAGE 119 OF 280 REV. 0 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET DC-2008-06-FINAL PAGE 120 OF 280 REV. 0 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initalize the simulator to the IC-510 (100%, MOL).

Enter drill file 6601 (NRC-CRSa) or manually insert the following:

Command Description

1. delm psisacc(1) Removes point from monitor screen

2. monv psisacc(1) Monitors Accumulator 1-1 pressure

3. set psisacc(1)=609 Lowers Accumulator 1-1 pressure to 594 psig

4. set cnpgaccn=600 Set n2 press < accum press

5. tc rsih943.gt.0.25, set Reset n2 press after HCV-943 cycled cnpgaccn=665.0

6. run 10 Runs sim for 10 seconds Inform the examiner that the simulator setup is complete.

Go to RUN when the examinee is given the cue sheet.

DC-2008-06-FINAL PAGE 121 OF 280 REV. 0 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC-CRSb

Title:

RESPOND TO HIGH PRT PRESSURE Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: NEW

References:

OP A-4B:IV, Pressurizer Relief Tank Normal Operations, Rev. 1 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 2&3 Job Designation: RO/SROI/SROU Task Number: 5/007/A2.02 Rating: 2.6/3.2 AUTHOR: DAVID BURNS DATE: 01/29/08 REV. 0

JPM TITLE: RESPOND TO HIGH PRT PRESSURE JPM NUMBER: NRCADM061 COO-RO1 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.

Required Materials: None Initial Conditions: Unit 1 is 100% power, steady state conditions.

Initiating Cue: Annunciator PK05-25, PRT PRESS/LVL/TEMP is in alarm.

Shift Foreman has directed you to Lower PRT level to 84% and pressure to 3 psig per Step 6 of OP A-4B;IV, Pressurizer Relief Tank - Normal Operation.

Task Standard: PRT parameters are restored to normal with system returned to normal alignment.

DC-2008-06-FINAL PAGE 123 OF 280 REV. 0 OPERATING TEST.DOC

JPM TITLE: RESPOND TO HIGH PRT PRESSURE JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References OP A-4B:IV.

Step was: Sat: ______ Unsat _______*

• • 2. Lowers PRT level. 2.1 Verifies RCS-1-8030, PRT Primary water supply valve is CLOSED.

2.2 Reads Caution.

2.3 Establishes contact with Aux Senior Watch.

2.4 Direct Aux Senior to monitor RCDT level and Run Both RCDT Pumps Cue: Aux Senior will monitor level in RCDT and run both RCDT pumps.

2.5 OPENS RCS-1-8031 to drain PRT to RCDT **

2.6 Maintains contact with Aux Senior and closes RCS-1-8031 if level in RCDT exceeds 60%.**

2.7 CLOSES RCS-1-8031 when PRT Level reaches 84%**

2.8 Direct Aux Senior to return both RCDT pumps to AUTO.

Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 124 OF 280 REV. 0 OPERATING TEST.DOC

JPM TITLE: RESPOND TO HIGH PRT PRESSURE JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 3. Lower PRT Pressure 3.1 Establishes contact with Aux Senior Watch and informs him of intention to vent the PRT to the Waste Gas Header.

3.2 Verifies that PRT pressure is less than 10 psig and Waste Gas Header is available.

Cue: Waste Gas Header is available Aux Senior will monitor pressure.

3.3 CLOSES RCS-8045, PRT Nitrogen Supply Isolation.

3.4 OPENS PCV-472, PRT Vent to vent header. **

3.5 Monitors PRT Pressure.

3.6 CLOSES PCV-472, PRT to vent header when PRT pressure is ~3 psig. **

Cue: PRT Pressure is stable.

3.9 OPENS RCS-1-8045.

Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 125 OF 280 REV. 0 OPERATING TEST.DOC

JPM TITLE: RESPOND TO HIGH PRT PRESSURE JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 126 OF 280 REV. 0 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initial Conditions: Unit 1 is 100% power, steady state conditions.

Initiating Cue: Annunciator PK05-25, PRT PRESS/LVL/TEMP is in alarm.

Shift Foreman has directed you to Lower PRT level to 84% and pressure to 3 psig per Step 6 of OP A-4B;IV, Pressurizer Relief Tank - Normal Operation.

Task Standard: PRT parameters are restored to normal with system returned to normal alignment.

DC-2008-06-FINAL PAGE 127 OF 280 REV. 0 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET DC-2008-06-FINAL PAGE 128 OF 280 REV. 0 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initialize the simulator to the IC-510 (100%, MOL).

Enter drill file 6602 (NRC-CRSb) or manually insert the following:

Command Description

7. set aprts=6.1 increase prt steam mass to increase pressure to 12.0 psig

8. set aprtw=94000 increase prt water mass for 88.6%

level

9. vlv pzr6 2,0.05,1,0,d,5 #rrcp474 VLV PZR6 PRZR POWER RELIEF VALVE #rrcp474

10. anack Inform the examiner that the simulator setup is complete.

Go to RUN when the examinee is given the cue sheet.

Will have to monitor RCDT level and start RCDT pumps when directed and inform operator if RCDT level of 60% is exceeded.

LOA LWS1 act,2 LOA LWS2 act,2 MON SYS - Aux Board Screen DC-2008-06-FINAL PAGE 129 OF 280 REV. 0 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC-CRSc

Title:

VERIFY MISALIGNED ROD IS NOT STUCK Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Modified from DCPP Bank - LJC-066 Designed to be run in parallel with NRC- CRSd.

References:

OP AP-12B, Control Rod Misalignment, Rev. 12 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 3, 5, 6 Job Designation: RO/SROI Task Number: 01/001/A2.03 Rating: 3.5/4.2 AUTHOR: DAVID BURNS DATE: 01/20/08 REV. 1

JPM TITLE: VERIFY MISALIGNED ROD IS NOT STUCK JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.

Required Materials: None Initial Conditions: Unit 1 is at approximately 35% power after a load rejection from 50%.

Control rod K14 was observed to be >12 steps above the other Control Bank D rods based on DRPI. Procedure OP AP-12B, Control Rod Misalignment has been implemented.

Initiating Cue: The Shift Foreman directs you to verify that the misalignment rod is not stuck in accordance with OP AP-12B, Step 14.

Task Standard: All actions of OP AP-12B, step 14, have been completed and the status of control rod K14 (stuck or not stuck) has been verified and the results reported the Shift Foreman.

DC-2008-06-FINAL PAGE 131 OF 280 REV.1 operating test.doc

JPM TITLE: VERIFY MISALIGNED ROD IS NOT STUCK JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References OP AP-12B.

Step was: Sat: ______ Unsat _______*

2. Record the bank step counter 2.1 Reads CAUTIONS prior to Step 14.a, position for all control banks and and verifies with RBU, other PPC shutdown banks A & B method or RIL curve that rod height will remain above the RIL.

2.2 Verifies CBD rod groups are on the same step, and matches the rod groups on CBD until equal if not.

2.3 Records on AP-12B the bank positions for all control banks, and shutdown banks SBA and SBB.

Step was: Sat: ______ Unsat _______*

• • 3. Place the bank selector to the 3.1 Turns the ROD BANK/MODE affected bank. SELECT switch to the CBD position. **

Step was: Sat: ______ Unsat _______*

4. Record the plant process computer 4.1 Displays the Control Bank D position position for the affected bank. from the plant computer and records the value.

Note: Operator may call up the CBD address listed in App. B of AP-12B (U0052), or record the value from an existing group display.

Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 132 OF 280 REV.1 operating test.doc

JPM TITLE: VERIFY MISALIGNED ROD IS NOT STUCK JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 5. Drive the affected bank in several 5.1 Inserts rods for Control Bank D for steps (enough to see a DRPI several steps until a DRPI change is change). observed. **

5.2 Notes that rod K2 moves and diagnoses that rod K2 is not stuck. **

5.3 Reports status to Shift Foreman.

Note: Status of control rod may be reported after rod restored to its recorded position.

Step was: Sat: ______ Unsat _______*

• • 6. Return the rods in the affected 6.1 Withdraws Control Bank D until the bank to the position recorded in bank is restored to its previously OP AP-12B, Step 14.a. recorded position. **

Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 133 OF 280 REV.1 operating test.doc

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initial Conditions: Unit 1 is at approximately 35% power after a load rejection from 50%.

Control rod K14 was observed to be >12 steps above the other Control Bank D rods based on DRPI.

Procedure OP AP-12B, Control Rod Misalignment has been implemented.

Initiating Cue: The Shift Foreman has requested you CHANNEL CHECK the current Steam Generator Levels and report any channels that do not meet the CHANNEL CHECK requirement outlined in OPS Policy B-5; Channel Check Criteria.

Task Standard: DO NOT READ TO STUDENT: Maximum Stay time is calculated.

DC-2008-06-FINAL PAGE 134 OF 280 REV.1 operating test.doc

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET DC-2008-06-FINAL PAGE 135 OF 280 REV.1 operating test.doc

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initialize the simulator to IC-512 (50%, MOL).

Verify step counters and RBU are updated to current CBD rod position.

Enter drill file 6608 in conjuction with setup for NRC-CRSd.

Place Rod Control Switch to Manual after simulator goes to freeze.

Inform the examiner that the simulator setup is complete.

Go to RUN when the examinee is given the cue sheet.

DC-2008-06-FINAL PAGE 136 OF 280 REV.1 operating test.doc

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC-CRSd

Title:

RESPOND TO A LOAD TRANSIENT BYPASS Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Direct from DCPP Bank - LJC-089 Designed to be run in parrellel with NRC-CRSc.

OP AP-2, Full Load Rejection, Rev. 17

References:

Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 3, 4 Job Designation: RO/SROI Task Number: 4S/056/A1.08 Rating: 2.3/2.6 AUTHOR: DAVID BURNS DATE: 1/21/08 REV. 1

JPM TITLE: RESPOND TO A LOAD TRANSIENT BYPASS JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.

Required Materials: None Initial Conditions: Unit 1 was operating at 75% power when a load rejection occurred due to the main generator output breakers opening.

Initiating Cue: The Shift Foreman directs you to verify the correct configuration of the load transient bypass feature by performing Step 3 of OP AP-2.

Task Standard: The correct configuration of the load transient bypass feature has been verified in accordance with Step 3 of OP AP-2.

DC-2008-06-FINAL PAGE 138 OF 280 REV. 0 OPERATING TEST.DOC

JPM TITLE: RESPOND TO A LOAD TRANSIENT BYPASS JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References OP AP-2.

Step was: Sat: ______ Unsat _______*

2. Check Load Transient Bypass 2.1 Observes LTB Switch - Blue light (LTB) - Actuated OFF.

2.2 Recognizes plant power was initially greater than 70%.

2.3 Attempts to initiate an LTB from VB-3 by momentarily placing LTB control switch in the ACTUATE position.

2.4 Notes the LTB Switch - Blue light is still OFF.

Step was: Sat: ______ Unsat _______*

• • 3. Starts Standby Cond/Booster Pp 3.1 Manually starts the Standby Set. Cond/Booster Pp Set. **

• Places Auto/Man switch in MANUAL.

• Places start switch in START.

Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 139 OF 280 REV. 0 OPERATING TEST.DOC

JPM TITLE: RESPOND TO A LOAD TRANSIENT BYPASS JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 4. Manually initiates LTB actions. 4.1 Opens FCV-55, feedwater heater (these substeps may be done in bypass valve. **

any order) 4.2 Opens FCV-230, condensate polisher bypass valve. **

Note: FCV-230 takes approximately 2 minutes to stroke.

4.3 Opens FCV-31, stator and H2 coolers flow control valve. **

• Places Hagen controller in MAN

• Depresses lower pushbutton Note: Full Open is 0% controller demand.

4.4 Verifies open TCV-23, generator cold gas temperature control valve.

• Places Moore controller in MAN and verifies or adjusts Moore KNOB to drive the valve 100% OPEN.

4.5 Closes LCV-12, condensate reject to the CST. **

• Places Hagen controller in MAN.

• Depresses lower pushbutton.

Step was: Sat: ______ Unsat _______*

Stop Time:

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 140 OF 280 REV. 0 OPERATING TEST.DOC

JPM TITLE: RESPOND TO A LOAD TRANSIENT BYPASS JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Total Time: (Enter total time on the cover page)

Initial Conditions: Unit One is at 100% power. A concern over the accuracy of the Steam Generator Level indication has been raised.

Initiating Cue: The Shift Foreman has requested you CHANNEL CHECK the current Steam Generator Levels and report any channels that do not meet the CHANNEL CHECK requirement outlined in OPS Policy B-5; Channel Check Criteria.

Task Standard: DO NOT READ TO STUDENT: Maximum Stay time is calculated.

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

DC-2008-06-FINAL PAGE 141 OF 280 REV. 0 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET DC-2008-06-FINAL PAGE 142 OF 280 REV. 0 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initialize the simulator to IC-512 (50%, MOL).

Enter drill file 6608 or manually insert the following:

Command Description

1. mal rod4a Sticks rod K14, clears at 35% power.

act,1,k14,20,d,fnisper.lt.35.0

2. bst rod2 2,0,0,0,C,fnispr.lt.35.0 Stops rods at 35%

3. mal cnd1 act,2,0,0,d,0 Prevents LTB relay actuation

4. mal gen4 act,1,0,10,d,0 Generator loss of load

5. run 60 Freezes simulator after 60 seconds Inform the examiner that the simulator setup is complete Go to RUN when the examinee is given the cue sheet.

DC-2008-06-FINAL PAGE 143 OF 280 REV. 0 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC-CRSe

Title:

INITIATE A NATURAL CIRCULATION COOLDOWN Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Modified from DCPP Bank - LJC-046 Designed to be run in parrellel with NRC-CRSf

References:

EOP E-0.2, Natural Circulation Cooldown, Rev. 21 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 3, 4 Job Designation: RO/SROI Task Number: 02/002/A2.03 Rating: 4.1/4.3 AUTHOR: DAVID BURNS DATE: 05/16/08 LINE MANAGER REV. 1

JPM

Title:

Initiate A Natural Circulation Cooldown JPM Number: NRC-CRSe Instructor Worksheet Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.

Required Materials: None Initial Conditions: Unit 1 has tripped from 100% power. EOP E-0.1, Reactor Trip Response, is complete and reactor coolant pumps are not available.

EOP E-0.2 has been performed up to and including Step 9. Boration to Cold Shutdown is complete and all CRDM fans are running.

Initiating Cue: The Shift Foreman directs you to initiate a natural circulation cooldown in accordance with EOP E-0.2, Step 10.

Task Standard: A natural circulation cooldown has been initiated in accordance with EOP E-0.2.

DC-2008-06-FINAL Page 145 of 280 REV. 1 operating test.doc

JPM

Title:

Initiate A Natural Circulation Cooldown JPM Number: NRC-CRSe Instructor Worksheet Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References EOP E-0.2.

1.2 Reads CAUTION.

1.3 Reads NOTE.

Step was: SAT: _____ Unsat _____*

2. Check status of all S/Gs. 2.1 Checks steam release capabilities of all S/Gs are available.

2.2 Checks feed flow is available to all S/Gs.

Step was: SAT: _____ Unsat _____*

• • 3. Check MSIVs open. 3.1 Determines MSIVs are not open.**

Step was: SAT: _____ Unsat _____*

• • 4. Initiate an RCS cooldown.. 4.1 Places SG 10% dump valves is Manual. **

4.2 Manually opens 10% dump valves until RCS temperature starts to lower. **

Note: Once a cooldown is verified, the JPM may be terminated.

Step was: SAT: _____ Unsat _____*

Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

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JPM Number: NRC-CRSe Examinee Cue Sheet Initial Conditions: Unit One is at 100% power. A concern over the accuracy of the Steam Generator Level indication has been raised.

Initiating Cue: The Shift Foreman has requested you CHANNEL CHECK the current Steam Generator Levels and report any channels that do not meet the CHANNEL CHECK requirement outlined in OPS Policy B-5; Channel Check Criteria.

Task Standard: DO NOT READ TO STUDENT: Maximum Stay time is calculated.

DC-2008-06-FINAL Page 147 of 280 REV. 1 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE AUTHOR: DAVID BURNS DATE: 01/21/08 REV. 1

JPM TITLE: RESTORATION OF BUSES AFTER A LOSS OF JPM NUMBER: NRC-CRSF OFFSITE POWER INSTRUCTOR WORKSHEET Initialize the simulator to IC-510 (100%, MOL).

Enter drill file 6609.

Inform the examiner that the simulator setup is complete.

Go to RUN when the examinee is given the cue sheet.

Or manually insert the following:

Ovr XC1I072T act,1 Trips the reactor Ovr XV2i260o act,1 Trips the RCPs Ovr XV2i261o act,1 Ovr XV2i262o act,1 Ovr XV2i263o act,1 Ovr XREo006H act,1 Resets MSRs Ovr XC3i136m act,1 Takes FWRVs to manual and closes Ovr XC3i136L act,1 Ovr XC3i137m act,1 Ovr XC3i137L act,1 Ovr XC3i138m act,1 Ovr XC3i138L act,1 Ovr XC3i139L act,1 Ovr XC3i139m act.1 Ovr XV2i260 act,1 Stop CND/BSTR Pp 1-2 Run 180 Select E-0.2 display on SPDS.

Type grpdis cooldown on a CC2 PPC computer, and enter a 5 second update rate.

Verify MSRs are RESET Verify all but one CND/BSTR Pp set are STOPPED Inform the examiner that the simulator setup is complete.

Go to RUN when the examinee is given the cue sheet.

NRC-CRSf Number:

Title:

RESTORATION OF BUSES AFTER A LOSS OF OFFSITE POWER DC-2008-06-FINAL PAGE 149 OF 280 0 OPERATING TEST.DOC

JPM TITLE: RESTORATION OF BUSES AFTER A LOSS OF JPM NUMBER: NRC-CRSF OFFSITE POWER INSTRUCTOR WORKSHEET Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Direct from DCPP Bank - LJC-210 Designed to be run in parrellel with NRC-CRSe.

References:

OP AP-26, Loss of Offsite Power, Rev. 10A Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 2, 3, 4, 6, 8, 13 Job Designation: RO/SROI Task Number: 06/062/A4.01 Rating: 3.3/3.1 DC-2008-06-FINAL PAGE 150 OF 280 0 OPERATING TEST.DOC

JPM TITLE: RESTORATION OF BUSES AFTER A LOSS OF JPM NUMBER: NRC-CRSF OFFSITE POWER INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.

Required Materials: None Initial Conditions: The Reactor inadvertently tripped from 50% power, BOL. After the trip, the Unit 1 S/U transformer failed resulting in a loss of startup power.

OP AP-26, Section A, Step 1 has been performed. Unit 2 is operating at 100% power.

Initiating Cue: The Shift Foreman directs you to energize the Unit 1 Startup Bus from the Unit 2 Startup Bus in accordance with OP AP-26, Loss of Offsite Power, Section A, starting at Step 2.

Task Standard: Unit 1 Startup bus is ready for restoration of non-vital buses and loads.

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JPM TITLE: RESTORATION OF BUSES AFTER A LOSS OF JPM NUMBER: NRC-CRSF OFFSITE POWER INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure and 1.1 Obtains OP AP-26 and locates locate appropriate section Section A: Restoration of Buses.

Cue: Begin with Step 2.

Step was: Sat: ______ Unsat _______*

• • 2. Place all condensate and booster 2.1 Places all condensate/booster pump pump selector switches in STANDBY SELECT switches in MANUAL. MANUAL. **

Step was: Sat: ______ Unsat _______*

• • 3. Cutout auto transfer feature FCOs 3.1 Places AUTO XFR TO S/U PWR for all vital and non-vital 4kV and C/O switches for 4kV buses H, G, F, 12kV buses. D and E, and 12kV buses D and E, in CUTOUT. **

Step was: Sat: ______ Unsat _______*

• • 4. Depress all vital and non-vital 4.1 Depresses 4KV BUS AUTO XFR 4kV and 12kV auto transfer relay RESET pushbuttons for 4kV buses F, push buttons. G, and H.

4.2 Verifies blue lights off.

4.3 Observes that the non-vital bus transfer relays are NOT acutated or depresses non-vital transfer relay reset pushbuttons.

Step was: Sat: ______ Unsat _______*

5. Open both non-vital 4kV Bus E 5.1 Observes that the following breakers supply breakers are open:

• 52-HE-2 (may green-flag)

• 52-HE-3 Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

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JPM TITLE: RESTORATION OF BUSES AFTER A LOSS OF JPM NUMBER: NRC-CRSF OFFSITE POWER INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 6. Open all non-vital 4kV Bus E load 6.1 Opens the following breakers: **

breakers

• 52-HE-12

• 52-HE-10

• 52-HE-8

• 52-HE-7

• 52-HE-5

• 52-HE-4 Step was: Sat: ______ Unsat _______*

7. Open both non-vital 4kV Bus D 7.1 Observes that the following breakers supply breakers are open:

• 52-HD-15 (may green-flag)

• 52-HD-14 Step was: Sat: ______ Unsat _______*

• • 8. Open all non-vital 4kV Bus D load 8.1 Opens the following breakers:**

breakers

• 52-HD-6

• 52-HD-8

• 52-HD-10

• 52-HD-11

• 52-HD-12

• 52-HD-13 Step was: Sat: ______ Unsat _______*

9. Open both non-vital 12kV Bus D 9.1 Observes that the following breakers supply breakers are open:

• 52-VD-8 (may green-flag)

• 52-VD-4 Step was: Sat: ______ Unsat _______*

10. Open both non-vital 12kV Bus E 10.1 Observes that the following breakers supply breakers are open:

• 52-VE-2 (may green-flag)

• 52-VE-6 Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

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JPM TITLE: RESTORATION OF BUSES AFTER A LOSS OF JPM NUMBER: NRC-CRSF OFFSITE POWER INSTRUCTOR WORKSHEET Step Expected Operator Actions

11. Verify Unit 1 12kV Startup Bus 11.1 Observes that the following breakers breakers are open are open:

• 52-VU-11

• 52-VU-12 (may green-flag)

Step was: Sat: ______ Unsat _______*

12. Verify S/U XFMR Low Side 12.1 Pulls S/U XFMER 1-1 LOW SIDE Voltage Adjust pulled to Manual. VLTG ADJUST switch out.

Step was: Sat: ______ Unsat _______*

• • 13. Energize the Unit 1 Startup Bus **********************************

from the Unit 2 Startup Bus Cue: Energize the Unit 1 12kV S/U bus from the Unit 2 12kV S/U bus.

13.1 Goes to Step 5 of the procedure 13.2 Verifies Unit 2 Startup Bus white potential light - ON.

13.3 Positions the 12 KV S/U BUS X-TIE FDR SYNC switch to ON. **

13.4 Closes 52-VU-11. **

13.5 Verifies that 52-VU-11 has closed.

13.6 Verifies Unit 1 voltages restored.

13.7 Reads 30 MVA limit.

13.8 Observes that the following breakers are closed:

• 52-VU-14

• 52-HG-15 Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

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JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initial Conditions: Unit One is at 100% power. A concern over the accuracy of the Steam Generator Level indication has been raised.

Initiating Cue: The Shift Foreman has requested you CHANNEL CHECK the current Steam Generator Levels and report any channels that do not meet the CHANNEL CHECK requirement outlined in OPS Policy B-5; Channel Check Criteria.

Task Standard: DO NOT READ TO STUDENT: Maximum Stay time is calculated.

DC-2008-06-FINAL PAGE 155 OF 280 0 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET DC-2008-06-FINAL PAGE 156 OF 280 0 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initialize the simulator to IC-510 (100%, MOL).

Enter drill file 6609.

Inform the examiner that the simulator setup is complete.

Go to RUN when the examinee is given the cue sheet.

DC-2008-06-FINAL PAGE 157 OF 280 0 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC-CRSg

Title:

RESPOND TO A LOSS OF CCW FLOW TO RCPs Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Direct from DCPP Bank - LJC-127

References:

AR PK01-08, CCW HEADER C, Rev. 16 OP AP-11, Malfunction of Component Cooling Water System, Rev. 23 Alternate Path: Yes X No Time Critical: Yes X No Time Allotment: 5 Minutes Critical Steps: 4 Job Designation: RO/SROI Task Number: 08/008/K3.03 Rating: 4.1/4.2 AUTHOR: DAVID BURNS DATE: 1/21/08 REV. 1

JPM TITLE: RESPOND TO A LOSS OF CCW FLOW TO RCPS JPM NUMBER: NRC-CRSG INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.

Required Materials: None Initial Conditions: Unit 1 is operating at 100% power with all systems aligned for normal full power operation.

Initiating Cue: PK01-08, CCW Header C, has just alarmed. Inputs 265 and 1372, RCP L.O. Clr CCW Flow Lo, are causing the alarm.

Task Standard: CCW has been restored to the RCP lube oil coolers or, if the problem cannot be corrected, the appropriate remedial actions have been taken in accordance with applicable plant procedures.

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JPM TITLE: RESPOND TO A LOSS OF CCW FLOW TO RCPS JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References AR PK01-08.

Step was: Sat: ______ Unsat _______*

2. Perform actions for RCP lube oil 2.1 OBSERVES that two CCW pumps cooler low flow. are running.

2.2 OBSERVES that FCV-355 and FCV-356 are open.

Note: Operator may observe that FCV-749 is closed at this time.

2.3 CHECKS RCP bearing temperatures on PPC.

Note: Operator may use PICTURE RCP on PPC to monitor RCPs.

2.4 Refers to OP AP-11, Section E.

Step was: Sat: ______ Unsat _______*

3. Verifies CCW Flow to all RCP 3.1 Reads CAUTION prior to Step 1.

lube oil coolers. 3.2 OPENS or VERIFIES OPEN the following:

• FCV-355

• FCV-356

• FCV-363 3.3 OBSERVES that FCV-749 is CLOSED.

3.4 Attempts to OPEN FCV-749.

Cue: (IF operator requests local operation of FCV-749: THEN)

The Shift Foreman has dispatched an operator to Containment to OPEN FCV-749.

3.5 Reads Time Critical RNO for Step 1 Step was: Sat: ______ Unsat _______*

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

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JPM TITLE: RESPOND TO A LOSS OF CCW FLOW TO RCPS JPM NUMBER:

NRCADM061-COO-RO1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 4. IF CCW Flow to RCP(s) 4.1 Manually TRIPS the REACTOR by CANNOT be restored to Lube Oil positioning either REACTOR TRIP Coolers within 5 minutes, THEN switch (CC-1 or VB-2) to TRIP. **

1) TRIP reactor.

4.2 Verifies reactor has tripped.

2) TRIP affected RCP.

3) GO TO EOP E-O. Note: Operator may verify reactor trip, and perform other immediate actions of EOP E-0, before or after tripping the RCPs (reactor is tripped 1st).

4.3 STOPS all four RCPs within 5 minutes of JPM start time. **

Time last RCP tripped: ________.

4.4 VERIFIES RCPs have stopped.

4.5 Commences EOP E-0 actions.

Cue: Other operators will perform EOP E-0.

Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

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JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initial Conditions: Unit One is at 100% power. A concern over the accuracy of the Steam Generator Level indication has been raised.

Initiating Cue: The Shift Foreman has requested you CHANNEL CHECK the current Steam Generator Levels and report any channels that do not meet the CHANNEL CHECK requirement outlined in OPS Policy B-5; Channel Check Criteria.

Task Standard: DO NOT READ TO STUDENT: Maximum Stay time is calculated.

THIS TASK IS TIME CRITICAL DC-2008-06-FINAL PAGE 162 OF 280 REV. 1 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET DC-2008-06-FINAL PAGE 163 OF 280 REV. 1 OPERATING TEST.DOC

JPM NUMBER:

NRCADM061-COO-RO1 EXAMINEE CUE SHEET Initialize the simulator to IC-510 (100%, MOL).

Enter drill file 1127 or manually insert the following:

Command Description

1. vlv ccw6 2,0,0,0,d,0 Fails FCV-749 to the closed position.

2. run 30 FREEZES simulator after 30 seconds.

Inform the examiner that the simulator setup is complete.

Go to RUN when the examinee is given the cue sheet.

DC-2008-06-FINAL PAGE 164 OF 280 REV. 1 OPERATING TEST.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRC-CRSh

Title:

ISOLATE RUPTURED STEAM GENERATOR 1-2 Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Direct from DCPP Bank - LJC-031

References:

EOP E-3, Steam Generator Tube Rupture, Rev. 28A Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 2, 4, 5, 7, 10 Job Designation: RO Task Number: 4P/035/A2.01 Rating: 4.5 M

AUTHOR: DAVID BURNS DATE: 03/28/08 REV.0

JPM TITLE: ISOLATE RUPTURED STEAM GENERATOR 1-2 JPM NUMBER: NRC-CRSh INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions, initiating cue, and task standard. The examiner will then ask if any clarifications are needed. The examinee may be given the applicable procedure and step with which to begin.

Required Materials: None Initial Conditions: A steam generator tube rupture occurred on steam generator 1-2. All required actions of EOP E-0 and EOP E-3 are complete up to the isolation of steam generator 1-2.

Initiating Cue: You are directed by the Shift Foreman to isolate steam generator 1-2 in accordance with EOP E-3, Steps 3 and 4.

Task Standard: Steam generator 1-2 is isolated per Steps 3 and 4 of EOP E-3.

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JPM TITLE: ISOLATE RUPTURED STEAM GENERATOR 1-2 JPM NUMBER: NRC-CRSh INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References EOP E-3.

1.2 Reads CAUTION prior to Step 3.a.

Step was: Sat: ______ Unsat _______*

• • 2. Verify ruptured SG 10% steam 2.1 Verifies controller is in AUTO.

dump controller in AUTO and set to 1040 psig. 2.2 Turns controller pot setting to 1040 psig or 8.67 turns. **

Note: The operator may take the controller to manual while adjusting the pot setting.

Step was: Sat: ______ Unsat _______*

3. Check ruptured SG 10% steam 3.1 Checks PCV-20 controller output on dump valve closed. VB-3 at 0% or valve status green light ON.

Note: The 10% steam dump may open due to SG pressure. If this occurs, the RNO for this step should be performed. (This would make this step Critical.)

Step was: Sat: ______ Unsat _______*

• • 4. Close ruptured steam generator 4.1 Places FCV-42 control switch in the MSIV and MSIV bypass valves. CLOSE position. **

4.2 Checks SG 1-2 MSIV bypass valve, FCV-24, green light is ON.

Step was: Sat: ______ Unsat _______*

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JPM TITLE: ISOLATE RUPTURED STEAM GENERATOR 1-2 JPM NUMBER: NRC-CRSh INSTRUCTOR WORKSHEET Step Expected Operator Actions

• • 5. Close the steam supply valve from 5.1 Places the control switch for the ruptured SG to the TD AFW FCV-37 to the CLOSE position. **

pump.

5.2 Recognizes that FCV-37 fails to close. **

5.3 Verifies at least one MD AFW Pp is providing adequate flow.

5.4 Directs a Nuclear Operator to manually trip the TD AFW pump.

5.5 Directs a Nuclear Operator to open supply breaker 52-1H-30 for FCV-37. **

5.6 Directs a Nuclear Operator to close steam supply vlv FCV-37. **

Step was: Sat: ______ Unsat _______*

6. Verify blowdown and sample 6.1 Verifies FCV-154, blowdown isolation valves OC closed. isolation valve, green light ON 6.2 Verifies FCV-248, sample isolation valve, green light ON.

Step was: Sat: ______ Unsat _______*

• • 7. Removes Thot input to the SCMM 7.1 Goes to PAM 4. **

from SG 1-2.

7.2 Presses CONFIGURATION

SUMMARY

7.3 Presses FAILED STEAM GENERATOR. **

7.4 Presses LOOP 2. **

7.5 Presses DISABLE LOOP. **

Step was: Sat: ______ Unsat _______*

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JPM TITLE: ISOLATE RUPTURED STEAM GENERATOR 1-2 JPM NUMBER: NRC-CRSh INSTRUCTOR WORKSHEET Step Expected Operator Actions

8. Check ruptured S/G isolated from 8.1 Checks ruptured S/G MSIV and intact S/Gs. Bypass valves - CLOSED OR 8.2 Checks ALL other MSIVs and Bypass Valves - CLOSED Step was: Sat: ______ Unsat _______*

9. Check ruptured SG narrow range 9.1 Reads Caution prior to step.

level greater than 6%.

9.2 Checks SG 1-2 narrow range level greater than 6%.

Step was: Sat: ______ Unsat _______*

• • 10. Stop feed flow to the ruptured 10.1 Verifies LCV-107 is CLOSED.

steam generator.

10.2 Verifies LCV-111 is CLOSED.**

10.3 Checks that AFW flow (FI-158) to SG 1-2 indicates 0 gpm.

Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time: (Enter total time on the cover page)

DC-2008-06-FINAL PAGE 169 OF 280 REV.0 OPERATING TEST.DOC

Initial Conditions: Unit One is at 100% power. A concern over the accuracy of the Steam Generator Level indication has been raised.

Initiating Cue: The Shift Foreman has requested you CHANNEL CHECK the current Steam Generator Levels and report any channels that do not meet the CHANNEL CHECK requirement outlined in OPS Policy B-5; Channel Check Criteria.

Task Standard: DO NOT READ TO STUDENT: Maximum Stay time is calculated.

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DC-2008-06-FINAL PAGE 171 OF 280 REV.0 OPERATING TEST.DOC

Initialize the simulator to IC-510, (100%, MOL).

Enter drill file 1031 or manually insert the following:

Vlv mss1 2,1,0,0,d,0 Electrically fails AFWP 1-1 steam supply valve, FCV-37 Enter drill file 1011 or manually insert the following:

Mal RCS4B act,1000 Steam Generator Tube Rupture S/G 1-2 Mal PPL2A act,0,0,0,d,10 SI actuation Mal PPL2B act,0,0,0,d,10 SI actuation Run 240 This setup allows entry into EOP E-3 at Step 3 with ruptured steam generator 1-2 level at approximately 20% and increasing.

Ensure PAM 4 Failed SG Loop 2 Thot Enabled and return PAM 4 screen to System Summary.

Inform the examiner that the simulator setup is complete.

Go to RUN when the examinee is given the cue sheet.

When the examinee requests that FCV-152 be tripped, activate LOA/AFW/AFW1 (1)

Tripped or, at the expert command, type loa afw1, act,1,0,0,d,0.

When directed:

o To open FCV-37 breaker 52-1H-30: DSC MSS2 ACT,0 o To close FCV-37: VLV MSS1,2,0 DC-2008-06-FINAL PAGE 172 OF 280 REV.0 OPERATING TEST.DOC

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Diablo Scenario 1 Op-Test No.: L061-1 Canyon No.:

Examiner Operators s:  :

Initial Conditions: 100% Power, MOL, 782 ppm CB Turnover: PRA Status: Green. Protected Equipment - Train B, Buses H& G, Prot. Sets II, III, IV. Sub-Cooled Margin Monitor train B OOS due to PT-403 failure. Swap CCW pps 1-1 and 1-3. U-2 at 100% power.

Event Malf. Eve Event Description and Time Line No. No. nt Typ e*

1 N Swap CCW Pump 1-1 and 1-3 2 Pmp cnd10 R Heater 2 Drip Pump trips on over current (programmed ramp to 770 MWE at 40 MW/min).

3 Pmp asw1 C Auxiliary Saltwater pump 11 trips on over current 3 minutes after generator < 771 MW. (TS 3.7.8.A) 4 xmt tur2 I PT-505 fails low 10 minutes after ASW pp 12 is started. (TS 3.3.1.T) 5 mal sei1 M 0.28g earthquake 10 minutes after PT-505 failure.

6 mal rcs1 M DBA LOCA after earthquake.

7 mal ppl1b C Phase A train B fails to actuate on SI.

8 bkr eps 11 C Auxiliary Saltwater Pump 1-2 fails to restart on SI.

Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 1 Event 1 Page 1 of 7 No.: No.: No.:

Event Swap CCW Pumps 1-1 and 1-3

Description:

Time Position Applicants Actions or Behavior SRO Briefs crew on swap of CCW pumps per OP F-2:II.

BOP Starts CCW Pump 1-3 & secures CCW Pump 1-1.

• Checks the idle pump is available for normal system operation.

• Selects the CCW Pump 1-3 Standby selector switch to manual.

• Starts CCW Pump 1-3, verifies normal running amps and flow.

• Places CCW Pump 1-1 control switch in stop.

• Verifies CCW header flow returns to normal.

Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 1 Event 2 Page 2 of 7 No.: No.: No.:

Event Heater 2 Drain Pump Trip

Description:

Time Position Applicants Actions or Behavior RO Acknowledge alarm PK10-14, Input 636, Heater 2 Drain Pump OC Trip.

BOP Diagnose Heater 2 Drain Pump tripped on Over Current.

SRO Responds per Annunciator Response Procedure PK10-14.

• Transitions to AP-15, Section C, based on Heater 2 Drain Pump Trip.

SRO Enters AP-15 Loss of Feedwater Flow, Section C Heater 2 Drain Pump Trip.

• Verifies MFP suction pressure is greater than 260 psig.

• Verifies Programmed Ramp is occurring

• Checks MFP suction pressure is greater than 260 pisg.

BOP Check MFP Suction Pressure Greater Than 260 psig.

RO Verify Programmed Ramp Occurring.

• DEH MW Feedback in service, Target set to 770 MW, Ramp Rate at 40 Mw/Min.

SRO Transitions to Section D, Step 2 of AP-15, Condensate/Booster Set Trip.

• Verifies MFP suction pressure is greater than 260 psig.

• Determines transition to AP-25 Rapid Load Reduction is SRO Enters AP-25 Rapid Load Reduction or Shutdown.

• Verifies Control Rods inserting in Auto.

• Verifies Pressurizer backup heaters - ON.

• Verifies Charging system operation is adequate.

• Verifies Digital Feedwater Controls controlling SG Levels in Auto.

D t i R i t d Di t B ti f RCS (B d RO Verify Control Rods inserting in Auto in response to Ramp.

RO Verifies Backup Pressurizer Heater groups are ON.

BOP/RO Verify Charging System operation is adequate.

• Controls charging in Manual as needed to prevent Letdown Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

RO Performs Boration of RCS using Boration Checklist and Makeup controller.

• Set Target Batch on flow controller (as determined by SRO)

SRO Responds per Annunciator Response Procedure 03-14, Rod LO LO Insertion limit.

RO Performs Emergency Boration Per AP-6, Emergency Boration Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 1 Event 3 Page 3 of 7 No.: No.: No.:

Event ASW Pump 11 Over Current Trip

Description:

Time Position Applicants Actions or Behavior CO Acknowledge alarm PK 01-03, Input 427, Aux Salt Water Pump OC CO/BOP Diagnose Aux Salt Water Pump 1-1 tripped on Over Current.

SRO Responds per Annunciator Response Procedure PK 01-03 (May refer to OP AP-10).

• Directs Starting of Standby ASW Pump 1-2.

• Verifies CCW-ASW HX DP is within limits.

• Direct continuous chlorination to be secured.

• Dispatch operator to investigate failure.

• Directs Maintenance to investigate failure of ASW pump 1 1 BOP Starts ASW Pump 1-2

• Selects manual on auto/manual selector switch.

• Starts ASW Pump 1-2, verifies normal running amps.

Ch k ASW/CCW t i t t d CCW HX i t Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 1 Event 4 Page 4 of 7 No.: No.: No.:

Event PT-505 fails low

Description:

Time Position Applicants Actions or Behavior RO/BOP Diagnose failure (LOW) of PT-505, 1st Stage Impulse pressure.

SRO Direct RO to place Rod Control in MANUAL RO Places Rod Control in MANUAL SRO Enters AP-5, Malfunction of Eagle 21 Protection or Control Channel.

• Verifies Primary and Secondary Control Systems are controlling properly in AUTO (Step to place rods in manual will be completed prior to this step)

• Directs RO to recover temperature with rod motion in manual (Reactivity Brief should include discussion on 3 steps pull and wait).

• Determines failure not to be related to Eagle 21.

• Determines alternate channel is not available for selection.

• Determines redundant recorder is not available. (Tref will have to be manually determined)

• Determines LTB and Steam Dumps are not actuated.

Notifies Maintenance to in estigate RO Restores Tave to Tref using manual control rods - observes 3 steps pull and wait requirement.

BOP Verify LTB and Steam Dumps not Actuated.

BOP Places Steam Dumps in Steam Pressure Mode, Per STP I-4-P505.

• Places HC-507 in Manual

• Places Train A & B Steam Dump Control Bypass Selector Switch in OFF/RESET

• Places Steam Dump Mode select to Steam Pressure Mode

• Verify UI-500 indicates 0%

• Places Train A & B Steam Dump Control Bypass Selector Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 1 Event 5 Page 5 of 7 No.: No.: No.:

Event Seismic Event & DBA LOCA

Description:

Time Position Applicants Actions or Behavior RO/BOP Diagnose seismic event, based on ground motion and seismic alarms.

/

RO/BOP Diagnose Automatic Reactor Trip and Safety Injection.

/

RO/BOP Perform immediate actions:

• Verify Reactor Tripped.

• Verify Turbine Tripped.

• Verify Vital 4 KV Buses Energized.

Ch k SI A t t d SRO Enter E-0, Reactor Trip or Safety Injection

• Verify completion of Immediate Actions.

• Recognizes RCP trip criteria met, directs RCPs to be tripped. **

• Direct implementation of Appendix E.

• Checks status of AFW flows, direct throttling to minimum required flow.

• Checks for RCS cooldown.

• Checks Pressurizer safeties, PORVs and Spray valves closed.

• Checks steam generators are not faulted or ruptured.

• Determines RCS is not intact and recognizes procedure transition criteria met for EOP E-1, Loss of Reactor of RO Implements Appendix E

• Diagnose Partial Phase A

• Performs verification steps in Appendix E (See events 6 & 7 for actions)

BOP Throttles AFW flow as directed by SRO.

• Closes TD AFW pump LCVs.

• Throttles MD AFW LCVs.

RO/BOP Trips Reactor Coolant pumps**

Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

RO/BOP Places 2nd CCW Heat Exchanger in-service - note: only one ASW pump is available

• • Critical Task Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 1 Event 5 Page 6 of 7 No.: No.: No.:

Event DBA LOCA

Description:

Time Position Applicants Actions or Behavior SRO Conducts Procedure Transition Brief for E-1, Loss of Reactor of Secondary Coolant.

• Plant Status

• Major Actions

• Foldout Page Assignments SRO Enter E-1, Loss of Reactor of Secondary Coolant.

• Performs verification steps

• May transition to FR-Z.2, Response to Containment Flooding.

and/or FR-P.1, Response to Imminent Pressurized Thermal Shock based on scenario timing.

RO/BOP Perform verification steps in E-1 as directed by SRO.

RO/BOP Report status of RHR Pumps (OFF) when RWST level reaches 33%

SRO Enter E-1.3, Transfer to Cold Leg Recirculation **

• Direct Reset of SI & Phase A and B

• Check Status of ECCS Pumps - Direct securing 2 CFCUs.

• Dispatch operator to close breakers

• Direct valve manipulations to place RHR in service from the recirc sump.

RO Reset SI, Phase A and Phase B RO Secure 2 CFCUs as directed by SRO Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

RO/BOP Perform the valve manipulations to place RHR in service from the Recirc Sump. **

• Close 8716 A & B - RHR Pump Discharge Crossties.

• Close 8700 A & B - RHR RHR Suction Isolation valves.

• Cut in Series contactor and Open 8982B - Pump 2 Sump suction.

• Open FCV-364 - CCW to RHR Heat Exchanger No. 2.

• Start RHR Pump 1-2.

• Cut in Series contactor and Close 8974 A & B - SI pump Recirc.

• Open 8804 - RHR discharge to SI Pump 1-2.

• Close 8105 and 8106 - CCP Recirculation isolation.

Terminate after cold leg recirculation is established

• • Critical Task Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 1 Event 7&8 Page 7 of 7 No.: No.: No.:

Event Phase A Train B Fails/ ASW Pump 1-2 fails to restart

Description:

Time Position Applicants Actions or Behavior CO/BOP Determines Train B of Phase A Containment Isolation is not met.

Takes action to place the following valves to the closed position:

• 9355B - PZR Liquid Sample OC

• 9356B - RCS Sample OC

• 8880 - N2 supply to Accumulators

• 8152 - Letdown Isolation

• 8100 - RCP Seal Return

• 8029 - Containment Primary Water

• 8045 - PRT N2 supply

• 633 - Containment Fire Water Supply CO/BOP Starts ASW Pump 1-2 **

• • Critical Task Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

MAJOR EVENT

SUMMARY

AND SCENARIO OBJECTIVES A. Crew will swap CCW pumps, CCW pump 1-3 will be started and CCW Pump 1-1 will be secured using, OP F-2:II, CCW System - Changing Over Pumps and Common Components.

B. Heater 2 Drip Pump trips on over current. Programmed ramp to 770 MWE at 40 MW/min.

Crew responds per AP-15 Loss of Feedwater Flow and AP-25 Rapid Load Reduction or Shutdown.

C. Auxiliary Saltwater pump 11 trips on over current. Crew responds per AR PK 01-03 Aux Salt Water Pumps and verifies ASW pp 12 in service.

D. PT-505 fails low, causing inward rod motion. Rod are taken to manual, and crew enters AP-5 Malfunction of Eagle 21 Protection or Control Channel to address instrument failure.

E. Earthquake at 0.28g causes DBA LOCA. Crew enters E-0 Reactor Trip or Safety Injection on automatic Reactor Trip and Safety Injection.

F. On the Safety Injection, Train B of Phase A Containment Isolation does not actuate, and isolation must be done via manual operator actions.

G. On the Safety Injection, ASW pump 1-2 fails to start, and must be restarted manually.

H. Crew transitions from E-0 to E-1 Loss of Reactor or Secondary Coolant and performs verification steps.

I. Crew may go to FR Z.2 Response to Containment Flooding due to Hi Level in the Recirculation Sump, crew will transfer out of FR Z.2 at step 1, monitor level and return to procedure and step in effect.

J. Crew will go to E-1.3 Transfer to Cold Leg Recirculation, at 33% RWST level, and transfer to cold leg recirculation, only one train of RHR is available due to failure of ASW pp 1-1.

K. Scenario is terminated after cold leg recirculation is aligned.

Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2 1.6.1.1.1.1 ATTACHMENT 1 - SIMULATOR SET-UP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Init 510 100% power, MOL, CB = 782 Simulator per

• Integrators: BA - 0 and PW - 40 Checklist

• Tags: OOS on SCMM & PT-403 on VB2 Setup Drill 81 Reset normal engineering values Setup Drill 41 Clears Subcooled Margin Monitor Train Drill 79 B Limit NI response on a DBA LOCA CONTROL BOARD SETUP Copies of commonly used forms and procedures are available.

Any tags are placed/removed as necessary.

Primary integrator =40 gal, Boron = 0 gal.

Record PPC MAX (BOL = 99.8, MOL = 100.0, EOL = 100.2) on CC2 lamicoid The plant Abnormal Status Board is updated with last CCP CB near 782 and current date.

Circuit breaker flags are correct.

Equipment status lamicoids are correct:

B.A. XFER PP SUPPLYING BLENDER - BA Pp 1-2 SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - Cont. Rm. Vent Train 1 Bus F SELECTED TO BUS 1H - Cont. Rm. Vent Train 1 Bus H The proper Delta-I curve and Reactivity Handbook for the simulator INIT are in place The Rod Step Counters indicate correctly.

PPC Setup:

o QP TAVG, ALM/MODE-1, QP CHARGING, BIG U1169 o RBU is updated.

o PEN running.

o R2B blowdown flows at 90 gpm.

o Reactor trip status correct 1(Pg 2 of Group display Mode-1).

o Operational mode correct for current conditions.2 o Delta-I target slope matches Delta-I curve (DeltaI menu Option 5, constants K0500-0503=100% power target DeltaI / 100)

SPDS (screens and time updating), A screen RM, B screen SPDS.

The chart recorders are operating properly, and advanced.

All typewriters are on, with adequate paper/ribbon/etc., and are in the ON LINE status.

The Annunciator Horn is on (BELL ON).

Sound Effects are on (SOUND ON).

The video and audio systems are SECURED.

Communications systems are turned on and functional.

1 If not correct, place PPC display in ovrd mode, and press add/omit key. Type point Y0006D and select F2 to restore processing. This should update the trip breaker status.

2 Allow about ten minutes for the PPC to automatically update the plant mode. If still not correct, place PPC display in ovrd mode, and type APMC.

Follow menu to manually override to correct mode.

Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

1.6.1.1.1.2 Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

1.6.1.1.1.3 TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION X = manual entry required X 0 min DRILL 6603 After SRO reports the crew has taken the watch, load session MALS, OVRs, etc. by DRILL FILE or MANUALLY (below) 0 min pmp asw2 1,0,0,0,d,0 Block auto start of ASW pp 12 0 min bkr eps11 3,0,0,0,d,0 Blocks 52-HG-14 from closing S/U to bus G fdr 3 min pmp cnd10 6,3,300,180,d,0 Heater 2 Drain Tank PP 11 OC trip X When Report Htr 2 Drain pp motor has burnt smell, A & C phase OC requested relays dropped at breaker

< 771 MW pmp asw1 ASW pp 1-1 trips on OC 6,6,5,180,c,smss.lt.771 X When Ser 0425 act,1,0,0,d,55 Brings in door alarms for ASW Pps requested during inspections.

X When Report ASW pp 11 motor is hot to touch, B phase OC relay requested dropped at bkr X When Report ASW pump 1-2 discharge pressure is 48 psig and 11,500 requested gpm flow.

10 min after xmt tur2 2,0,0,600,c,xv1o243r PT-505 fails low ASW pp 12 started 10 minutes mal sei1 act 0.28 g earthquake after PT-505 0.28,10,480,c,jmlsyd2 failure On Seismic mal rcs1 act 3,4,15,c,jmlsei1 DBA LOCA on loop 4 mal ppl1b act 2,0,0,d,0 Cnm Iso Phase A train B fails to actuate On reactor trip Drill 32 NO action on a trip PA X When dsc sis14 act,1,0,0,d,0 opens 8976 breaker requested dsc rhr4 act,1,0,0,d,0 opens 8980 breaker Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

DIABLO CANYON POWER PLANT OPERATIONS SHIFT LOG UNIT 1 OPERATING MODE: 1 POWER LEVEL: 100  %

GROSS GENERATION: 1198 MWe NET GENERATION 1148 MWe DAYS AT POWER: 120 1.6.2 Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: GREEN -

PROTECTED EQUIPMENT: Train B, Buses H & G, Prot. Sets II,III,IV HOMELAND SECURITY THREAT LEVEL: YELLOW GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.05 gpm URGENT WORK:

• None ACTIVE SHUTDOWN TECH SPECS / ECGS:

• PT-403 - T.S 3.3.3.A - 30 days; due in 29 days, 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />.

TURNOVER ITEMS:

• PT-403 failed low 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago. The problem has been identified and it is expected to be returned to service in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

• Swap CCW Pump 1-1 and 1-3 immediately after assuming the watch, to equalize run times.

OPERABILITY ITEMS:

• None PRIORITY ITEMS FOR NEXT SHIFT:

• Repair of PT-403.

ANNUNCIATORS IN ALARM

• PK 05-07, PK 05-09 1.6.2.1.1 Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

1.6.2.1.2 SHIFT FOREMAN TURNOVER COMMENTS:

1. Reactivity management:

a. Time in core life: MOL

b. Power History: 100%

c. Boron concentration is 782 ppm from a sample taken 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.

d. Diluting 40 gallons every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

e. I is stable

2. No one is in Containment, no entries are expected

3. U-2 is operating at 100% power COMPENSATORY MEASURES:

None 1.6.2.2 CONTROL ROOM ABNORMAL STATUS See Abnormal Status Board.

Scenario 01 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Diablo Scenario 2 Op-Test No.: L061-1 Canyon No.:

Examiner Operators s:  :

Initial Conditions: 50% MOL, 937 ppm CB Turnover: Completed tunnel cleaning and both CWPs in service. Crew is to ramp unit to 60% power per OP L-4. D/G 11 was cleared 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> ago due for lube oil heater replacement. Expected back in 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />.

PRA Status is Orange. U2 is at 100% power.

Event Malf. Eve Event Description and Time Line No. No. nt Typ e*

1 R Ramp to 60% power per OP L-4.

2 vlv pzr6 C PORV PCV-474 fails to 25% open (TS 3.4.11.B) 5 minutes after ramp started.

3 cnh mss2 I PCV-19 S/G 11 10% dump controller fails to 100% demand 10 min after PORV block valve 8000A is closed. (TS 3.7.4.A) 4 mal nis6c I Power range channel NI-43 fails to 200% (TS 3.3.1.D,E) 5 min after PCV-19 b/u air cut-in.

5 loa cnd1 M Loss of Condenser Vacuum 12 minutes after NI-43 fails high, leads to manual reactor trip.

6 bkr eps13 C S/U feeder Overcurrent trip for 4KV bus H on bus transfer. (no power AFW pp 12) 7 mal afw1 C AFW pp 11 trips when started 8 xmt afw3 I AFW pp 13 discharge pressure transmitter limited to 360 psig, causes AFW LCV-113 & 115 to go closed in AUTO.

9 pmp afw2 C AFW pp 13 trips on Overcurrent after LCV-113 & 115 taken to Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

manual to restore AFW flow, leads to Loss of Heat Sink.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 2 Event 1 Page 1 of 9 No.: No.: No.:

Event Ramp to 60% power.

Description:

Time Position Applicants Actions or Behavior SRO Reviews and briefs OP L-4 for ramp to 60%.

• Covers Ramp Plan - 3 MW/Min Ramp.

• Performs reactivity Brief for ramp. (Dilution Plan)

SRO Directs RO to perform RCS dilution for ramp.

RO Performs Dilution of RCS in accordance with OP B-1A:VII, Makeup Control System Operation, may use Attachment 1 for guidance.

• Set target Batch on flow controller (200 gallons)

• Verify Primary Water Flow Rate set to desired flow.

• Start Dilution and verify response.

SRO Directs RO to perform ramp to 60%.

RO Sets up ramp on DEHC Console per SRO direction using OP C-3:III, Main Unit Turbine - At Power Operations. (May use Committed Posting for Direction)

• Raise Valve Position Limit.

• Places MW feedback in service.

• Set desired Ramp Rate. (3 MW/Min) 1 2

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 2 Event 2 Page 2 of 9 No.: No.: No.:

Event PORV PCV-474 goes to 25% open

Description:

Time Position Applicants Actions or Behavior BOP Diagnose PORV PCV-474 has opened partially.

RO Determine that PORV PCV-474 should be closed based on SRO Direct BOP to close PORV PCV-474.

BOP Diagnose that PORV PCV-474 will not close and report to SRO SRO Direct BOP to close PORV Block Valve 8000A.

BOP Closes PORV Block valve 8000A. **

RO Acknowledge alarm PK 05-20, input 1150, PZR Relief/Safety Valve SRO Responds per Annunciator Response Procedure PK 05-20.

• Refers to Tech Spec 3.4.11B (Determines 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> close block valve and remove power from block valve, also 72 hrs to restore PORV.)

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

• • Critical Task Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 2 Event 3 Page 3 of 9 No.: No.: No.:

Event PCV-19 controller fails to 100% demand

Description:

Time Position Applicants Actions or Behavior BOP Diagnose PCV-19 10% Steam Dump has Failed OPEN.

BOP/CO Determine that PCV-19 should be closed based on Steam Generator SRO Direct BOP to close PCV-19.

BOP Attempts to close PCV-19 by taking controller to manual and decreasing demand, determines controller has failed.

SRO Direct BOP to cut in backup air system and close PCV-19.

BOP Cuts in backup air and closes PCV-19 using backup air control switch CO Monitors plant for affects from increased steam flow.

SRO Refers to Tech Spec 3.7.4 (Determines Action A applies and 7 days to SRO Contacts Maintenance.

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 2 Event 4 Page 4 of 9 No.: No.: No.:

Event NI-43 Power Range channel fails high

Description:

Time Position Applicants Actions or Behavior RO Reports unexpected control rod motion.

RO Diagnoses NI-43 failure- HIGH SRO Directs CO to place Rods to be placed in Manual. (RO may take this action without direction).

RO Places Rod Control in Manual - and verifies Rod Motion has stopped SRO Directs ramp to be placed on HOLD (If SRO Desires, ramp can be placed on hold to stabilize the plant.)

RO/BOP Places Ramp on HOLD - Push HOLD on DEHC Controller SRO Enters AP-5, Malfunction of Eagle 21 Protection or Control Channel.

• Verifies Primary and Secondary Control Systems are controlling properly in AUTO (Step to place rods in manual will be completed prior to this step)

• Determines failure not to be related to Eagle 21.

• Determines alternate channel is not available for selection.

• Determines redundant recorder is not available.

• Determines LTB and Steam Dumps are not actuated.

• Notifies Maintenance to investigate

• Uses attachment 4.1 determine affected control systems BOP Removes NI-43 from service per AP-5 Attachment 4.1

• Places Miscellaneous Control and Indication switches (4) to failed channel Position. (This will allow RO to move Control Rods)

• Places Comparator defeat switch to failed channel position SRO Directs RO to recover temperature with rod motion in manual (Reactivity Brief should include discussion on 3 steps pull and wait).

RO Restores Tave to Tref using manual control rods - observes 3 steps pull and wait requirement.

RO Returns Rod Control to Auto (as time permits.)

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 2 Event 5 Page 5 of 9 No.: No.: No.:

Event Loss of Condenser Vacuum

Description:

Time Position Applicants Actions or Behavior BOP/RO Diagnose decreasing condenser vacuum SRO Enters AP-7, Degraded Condenser (As time permits)

• Checks Condenser Pressure vs. Attachment 6.2 Limits.

• Directs RO to Ramp Unit down. (As time permits)

• Direct RO to perform a Manual Turbine Trip or Immediate ti fE0 RO Performs manual turbine trip when condenser pressure approaches turbine trip setpoint as directed by SRO.

RO/BOP Perform immediate actions:

• Verify Reactor Tripped.

• Verify Turbine Tripped.

• Verify Vital 4 KV Buses Energized. (4kV Bus H is not energized)

Ch k SI A t t d SRO Enter E-0, Reactor Trip or Safety Injection

• Verify completion of Immediate Actions.

o Notes 4KV Bus H is not energized (Refer to ECA-0.3)

• Direct BOP to maximize AFW flow.

• Determines Transition to E-0.1 is required.

• Implements F-0, monitors CSFSTs

• Determines RED PATH for Heat Removal

• Transitions to FR H.1, Response to Loss of Secondary Heat BOP Attempts to establish AFW flow.

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 2 Event 6 Page 6 of 9 No.: No.: No.:

Event 4KV Bus H startup feeder breaker overcurrent trip

Description:

Time Position Applicants Actions or Behavior BOP Verifies vital 4KV buses energized per E-0

• Determines 4kV Bus H Feeder Breaker has tripped on Overcurrent.

BOP Diagnosis affect of loss of 4kV bus on AFW Pump 1-2 (Pump has no power)

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 2 Event 7 Page 7 of 9 No.: No.: No.:

Event AFW Pump 11 trips when started

Description:

Time Position Applicants Actions or Behavior BOP Determines FCV-152 has tripped and AFW pump 11 is not running.

BOP/SR Directs Aux Bldg watch to restart AFW pp 11 (Aux Bldg watch will not O be able to reset)

BOP Reports failure of AFW Pump 1-1 to SRO.

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 2 Event 8 Page 8 of 9 No.: No.: No.:

Event AFW Pump 13 discharge pressure transmitter failure

Description:

Time Position Applicants Actions or Behavior BOP Determines AFW pp 13 is running but LCV-113 & 115 are closed.

BOP Places LCV-113 & 115 controllers in manual and increases demand to restore AFW flow to S/Gs 13 & 14. **

BOP Report failure of AFW Pump 1-3 to SRO.

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

• • Critical Task Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 2 Event 9 Page 9 of 9 No.: No.: No.:

Event AFW Pump 12 trips on overcurrent / Loss of Heat Sink

Description:

Time Position Applicants Actions or Behavior SRO Transitions to FR-H.1, Response to Loss of Secondary Heat Sink.

• Verifies Secondary Heat Sink is Required.

• Verifies ECCS CCP Status

• Dispatches operators to investigate loss of pumps and to verify alignments.

• Direct RO to secure all RCPs.

RO Stops all RCPs.

BOP Adjust 10% Steam Dump controllers to 1005 PSIG (8.38 turns)

BOP Depressurizes RCS using PORV - to less than 1915 psig.

RO Blocks PZR low pressure and low steam line pressure SI BOP Resets FW Isolation BOP Bypass Fdwtr Heaters and Cond Demins (FCV-55 & 230)

BOP Close ALL MSIVs and MSIV Bypass Vlvs.

BOP Depressurize 2 S/Gs to <490 psig using 10% Steam Dumps.

BOP Establishes feed flow from condensate system prior to Feed &

Bleed criteria being met.**

BOP Stabilize Steam Generator pressures at 480 psig.

Terminate after condensate flow is established.

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

• • Critical Task Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

MAJOR EVENT

SUMMARY

AND SCENARIO OBJECTIVES L. Crew starts ramp to 60% power at 2-3 mw/min per OP L-4. Crew should perform a dilution for the power ascension.

M. PORV PCV-474 opens to 25%. The operator should verify pressure less than 2335 psig, and try to close the PORV. Since the PORV will not close, the block valve 8000A should then be closed. Follows up per PK 05-20.

N. S/G 11 10% steam dump.PCV-19 controller fails to 100% demand. Operator should verify pressure < 1020 psig and try placing controller in Manual and decrease demand. This will not work, so operator should cut-in backup air toggle switch and close 10% dump valve using backup air control switch.

O. Power range NI-43 fails high. Rods will drive in if in AUTO. Operator should diagnose NI problem and take rods to Manual. SRO will refer to AP-5 for guidance. NI-43 will be defeated per AP-5 attachment to restore rod control.

P. A condenser vacuum leak will cause entry into AP-7. This will require a Turbine trip, which should cause a reactor trip above P-9. If below P-9, a load rejection will occur and rods will insert to match Tavg to no load Tref. In this case, both MFW pumps will trip on low vacuum which will require a reactor trip. EOP E-0 will be entered.

Q. On the bus transfer from the Unit trip, 4KV bus H Startup feeder breaker will trip on overcurrent which will de-energize the bus. This will cause a loss of power to AFW pp 12.

R. AFW pp 11 will trip on starting. Damage to its overspeed mechanism will render it inoperable.

S. AFW pp 13 discharge pressure transmitter will only go to 360 psig. This will cause LCV-113 &

115 to close to prevent pump runout. The operator should see AFW pp 13 running, and place LCV-115 & 113 in manual to restore AFW flow. Shortly after this is done, AFW pp 13 will trip on overcurrent. This will cause a loss of heat sink and require transition to FR H-1 upon exiting E-0.

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

T. The scenario is terminated after flow is established from the condensate system per FR H-1.

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

1.6.2.2.1.1 ATTACHMENT 1 - SIMULATOR SET-UP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Init 512 50% power, MOL, CB = 937 Simulator per

• Integrators: BA - 0 and PW - 20 Checklist

• Tags: CT - D/G 1-1 to manual & bkr Setup Drill 81 Reset normal engineering values Setup Drill 34 Clears D/G 11, place D/G in manual Setup Turn on Backup heaters and Swap to sequential valve.

CONTROL BOARD SETUP Copies of commonly used forms and procedures are available.

Any tags are placed/removed as necessary.

Primary integrator = 20 gal, Boron = 0 gal.

Record PPC MAX (BOL = 99.8, MOL = 100.0, EOL = 100.2) on CC2 lamicoid The plant Abnormal Status Board is updated with last CCP CB near 937, stp I-1C every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Circuit breaker flags are correct.

Equipment status lamicoids are correct:

B.A. XFER PP SUPPLYING BLENDER - BA Pp 1-2 SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - Cont. Rm. Vent Train 1 Bus F SELECTED TO BUS 1H - Cont. Rm. Vent Train 1 Bus H The proper Delta-I curve and Reactivity Handbook for the simulator INIT are in place The Rod Step Counters indicate correctly.

PPC Setup:

o QP TAVG, ALM/MODE-1, QP CHARGING, BIG U1169 o RBU is updated.

o PEN running.

o R2B blowdown flows at 90 gpm.

o Reactor trip status correct 3(Pg 2 of Group display Mode-1).

o Operational mode correct for current conditions.4 o Delta-I target slope matches Delta-I curve (DeltaI menu Option 5, constants K0500-0503=100% power target DeltaI / 100)

SPDS (screens and time updating), A screen RM, B screen SPDS.

The chart recorders are operating properly, and advanced.

All typewriters are on, with adequate paper/ribbon/etc., and are in the ON LINE status.

The Annunciator Horn is on (BELL ON).

Sound Effects are on (SOUND ON).

The video and audio systems are SECURED.

Communications systems are turned on and functional 3

If not correct, place PPC display in ovrd mode, and press add/omit key. Type point Y0006D and select F2 to restore processing. This should update the trip breaker status.

4 Allow about ten minutes for the PPC to automatically update the plant mode. If still not correct, place PPC display in ovrd mode, and type APMC.

Follow menu to manually override to correct mode.

Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

1.6.2.2.1.2 TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION X = manual entry required X 0 min DRILL 6604 After SRO reports the crew has taken the watch, load session MALS, OVRs, etc. by DRILL FILE or MANUALLY (below) 0 min xmt afw3 5,375,0,0,d,0 AFW pp 13 discharge pressure limited to 360 psig, will close LCV-113 & 115 on pump start 5 min after vlv pzr6 2,0.25,5,300,c,ggo PCV-474 opens to 25%

ramp started 10 min after cnh mss2 2,1,15,600, PCV-19 controller fails to 100%, must 8000A closed c,rrc8000a.lt.0.1 use b/u air to close 2 minutes after Report as Turbine Bldg watch noise from Pipe Rack area.

10% steam dump is open 5 min after mal nis6c act NI-43 fails high PCV-19 B/U air 200,5,600,c,xv3i345c cut-in 12 min after loa cnd1 act,0.2,60,720, Condenser Vacuum leak NI-43 c,xnii410d comparator defeat On AFW pp 11 mal afw1 act 0,0,0, FCV-152 trips when pump rpm > 4100 start c,ofpstdfp.gt.4100 X When Report damage to overspeed trip mechanism, cant reset requested On tranfer to bkr eps13 4,0,0,2,c,xv4o218r 52-hh-14 S/U fdr to bus H trips on s/u overcurrent After placing pmp afw2 6,5.06,1,30, AFW pp 13 trips on overcurrent LCV-113 & 115 c,xv3o151m.and.xv3o152m in manual X ON Rx Trip Drill 32 NO Actions X When Report pump motor hot to touch, overcurrent relay flags dropped requested at breaker X When Dsc pzr1 act,0,0,0,d,0 Open Breaker for 8000A requested Scenario 02 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 3

DIABLO CANYON POWER PLANT OPERATIONS SHIFT LOG UNIT 1 OPERATING MODE: 1 POWER LEVEL: 50  %

GROSS GENERATION: 550 MWe NET GENERATION 515 MWe DAYS AT POWER: 120 1.6.3 Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: YELLOW - D/G 1-1 MOW PROTECTED EQUIPMENT: Train A/B, Buses F & G, Prot. Sets I,II,III,IV HOMELAND SECURITY THREAT LEVEL: YELLOW GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.05 gpm URGENT WORK:

• None ACTIVE SHUTDOWN TECH SPECS / ECGS:

• D/G 1-1. Lube oil heater replacement. TS 3.8.1 Action B - 7 days. Declared inoperable 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> ago.

TURNOVER ITEMS:

• Repairs on D/G 1-1 are in process. Expected to be returned to service in 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />. STP I-1C was completed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago.

• Unit at 50% for last 3 days due to tunnel cleaning. This is complete with both CWPs in service. Your crew is to ramp unit to 60% power.

• OP L-4 step 6.2.3 is in progress, and complete up to sub-step d.2, all Prerequisites have been met.

OPERABILITY ITEMS:

• None PRIORITY ITEMS FOR NEXT SHIFT:

• D/G 1-3 lube oil heater replacement ANNUNCIATORS IN ALARM

• PK 13-15, PK 14-16, PK 16-03, 04, 09, PK08-04, PK14-19, PK09-18 Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

1.6.3.1.1 Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

1.6.3.1.2 SHIFT FOREMAN TURNOVER COMMENTS:

4. Reactivity management:

a. Time in core life: MOL

b. Power History: 50% for last 3 days.

c. Boron concentration is 937 ppm from a sample taken 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.

d. Diluting 20 gallons every 2 - 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

e. The last dilution was completed 30 minutes ago.

f. I is stable

5. No one is in Containment, no entries are expected

6. U-2 is operating at 100% power COMPENSATORY MEASURES:

None 1.6.3.2 CONTROL ROOM ABNORMAL STATUS See Abnormal Status Board.

1.6.3.3 Ramp Plan for return to 60% Power Perform one 200 gal dilution prior to ramp.

Ramp Turbine at 3 MW/Min to 60% power.

Leave Rod Control in Auto.

Perform additional dilutions as needed to maintain Tavg and Tref matched.

Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Diablo Scenario 3 Op-Test No.: L061-1 Canyon No.:

Examiner Operators s:  :

Initial Conditions: 25% BOL, 1182 ppm Turnover: PRA Status - Yellow. AFW pp 11 cleared for bearing replacement. CFCU 1-2 is cleared for motor replacement. High Swell Warning in effect. Reduce power to 20% on both units in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Unit 2 power reduction to 20% was completed 10 minutes ago. Ramp to 20% power was delayed by problems with Main Feedwater Bypass valves. Issue has been resolved, continue ramp to 20% Per OP L-4.

Event Malf. Eve Event Description and Time Line No. No. nt Typ e*

1 N Set 10% Steam Dumps for low power conditions.

2 R Ramp to 20% power due to high swell warning.

3 pmp ven8 C CFCU 14 over current trip 2 min after ramp started. (TS 3.6.6) 4 xmt pzr40 I Controlling Pressurizer level channel LT-459 fails low 7 min after CFCU 14 trip. (TS 3.3.1) 5 mal ccw2 C Letdown heat exchanger tube leak 4 min after letdown restored.

6 mal rcs4b M 600 gpm Steam Generator 12 tube rupture after FCV-361 is opened.

7 mal mss3b C Steam break outside containment on Steam Generator 12 on reactor trip.

Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 3 Event 1 Page 1 of 7 No.: No.: No.:

Event Set 10% Steam Dumps for low power conditions

Description:

Time Position Applicants Actions or Behavior SRO Reviews and briefs OP L-4 for setting 10% to 8.38 turns (1005 psig)

BOP Sets 10% steam dumps to 8.38 turns (1005 psig) for each dump valve (PCV 19,20,21,22)

• Places 10% dump controller Manual

• Sets controller to 8.38 turns

• Returns 10% controller to AUTO 3

4 5

6 7

8 Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

9 10 Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 3 Event 2 Page 2 of 7 No.: No.: No.:

Event Ramp to 20% due to high swell warning

Description:

Time Position Applicants Actions or Behavior SRO Reviews and briefs OP L-4 for ramp to 20%.

• Covers Ramp Plan - 3 MW/Min Ramp.

Performs reactivity Brief for ramp. (Boration Plan)

SRO Directs RO to perform RCS boration for ramp.

RO Performs Boration of RCS in accordance with OP B-1A:VII, Makeup Control System Operation, may use Attachment 1 for guidance.

• Set target Batch on flow controller (10 gallons)

• Verify Boric Acid Flow Rate set to desired flow.

• Start Boration and verify response.

SRO Directs RO to perform ramp to 20%.

RO Sets up ramp on DEHC Console per SRO direction using OP C-3:III, Main Unit Turbine - At Power Operations. (May use Committed Posting for Direction)

• Places MW feedback in service.

• Set desired Ramp Rate. (3 MW/Min)

• Set Target to desired load (<200 MW) 11 Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

12 Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 3 Event 3 Page 3 of 7 No.: No.: No.:

Event CFCU 1-4 overcurrent trip

Description:

Time Position Applicants Actions or Behavior RO/BOP Diagnose CFCU 14 trips on over current.

RO Acknowledge alarm PK 01-21, Input 300, Containment Fan Cooler 1-4 OC Responds per Annunciator Response Procedure PK 01-21.

SRO

• Directs BOP to place fan cooler 1-5 in service.

• Refers to Tech Specs 3.6.6 Containment Spray and Cooling Systems (Determines 7 day action statement applies action BOP Starts another CFCU as directed by SRO.

• References OP H-2:I

• Starts selected CFCU in Low Speed. (1-5)

• Stops CFCU, selects Hi Speed and Restarts CFCU.

Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 3 Event 4 Page 4 of 7 No.: No.: No.:

Event Pzr level channel LT-459 fails low

Description:

Time Position Applicants Actions or Behavior BOP/RO Diagnose Pressurizer Level Channel LT-459 Failing Low.

SRO Direct RO to place charging control in MANUAL and reduces to seals only RO Places Charging Control in Manual and controls flow to maintain Pressurizer Level RO Acknowledge alarm PK 05-21, input 314, Pressurizer Level Low SRO Determines AP-5, Malfunction of Eagle 21 Protection or Control Channel is appropriate procedure to address this event.

BOP Diagnose Letdown Isolation and report to SRO RO Diagnose Loss of Pressurizer Heaters, Low Level cutout, report to SRO SRO Enters AP-5, Malfunction of Eagle 21 Protection or Control Channel.

• Verifies Primary and Secondary Control Systems are controlling properly in AUTO (Step to place charging in manual will be completed prior to this step)

• Determines failure not to be related to Eagle 21.

• Determines alternate channel is available for selection. (Directs RO to select alternate Pressurizer Level Control Channel)

• Determines redundant recorder is available. (Directs RO to select matching level recorder)

• Determines LTB and Steam Dumps are not actuated.

• Notifies Maintenance to investigate

• Uses attachment 4.1 determine affected control systems.

RO Selects alternate channel for Pressurizer level control and recorder BOP/RO Re-establishes letdown per OP B-1A:XII, CVCS - Letdown System, Establish Normal Letdown following Letdown Isolation.

• Places PCV-135 in manual and opens to 60%

• Places TCV-130 in manual and opens to 50%

• Increase charging flow to ~87 gpm and adjust seal injection flow.

• Open Letdown Orifice valve 8149C Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

RO Places Pressurizer Heaters in Auto.

Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 3 Event 5 Page 5 of 7 No.: No.: No.:

Event Letdown Heat Exchanger tube leak

Description:

Time Position Applicants Actions or Behavior RO/BOP Diagnose unexpected change in VCT level and letdown flow.

RO Acknowledge alarm PK 11-21, input 1066, Process Monitor Hi Rad SRO Responds per Annunciator Response Procedure PK 11-21.

• Directs BOP to check process radiation monitors.

• Verifies automatic actions have occurred (CCW Head tank RCV-16 Closed)

BOP Check radiation monitors, can use PPC RAD MAP - Reports RE-17A BOP/RO Verifies RCV-16, CCW Head Tank Vent is closed.

SRO Enters AP-11 Malfunction of CCW System Section B: CCW System Inleakage.

• Verifies CCW Head tank isolation. (RCV-16 Closed)

• Verifies RCP Operability.

• Verifies CCW Surge Tank Makeup, not source of inleakage, requests sample.

• Determines Leak Location - Letdown Heat Exchanger BOP Isolates normal letdown, closes 8149C and LCVs 459 & 460.**

RO Reduces charging flow to seals only.

BOP Isolates Normal Charging - Closes 8146.

BOP Places Excess Letdown in service per OP B-1A:IV

• Opens CCW supply to Excess Letdown HX - FCV-361.

Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

• • Critical Task Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 3 Event 6 Page 6 of 7 No.: No.: No.:

Event S/G 12 tube rupture

Description:

Time Position Applicants Actions or Behavior RO Acknowledge alarm PK 11-06, Input 423, SJAE HI Radiation RO Acknowledge alarm, PK 11-18, Input 471, Main Steam Line Hi Rad.

BOP Checks for increasing Radiation Monitor trends, reports RE-15 and 72 counts increasing.

BOP Checks for decreasing RCS pressure and Pressurizer Level, Reports rapid drop in both indications SRO Responds per Annunciator Response Procedure PK 11-18.

• Diagnoses a Steam Generator Tube Failure and Transitions to AP-3, Steam Generator Tube Failure

• Directs BOP to isolate Letdown and start additional Charging Pumps (if time permits)

BOP Starts additional charging pump and isolates letdown as directed.

RO Performs a Manual Safety Injection RO/BOP Perform immediate actions:

• Verify Reactor Tripped.

• Verify Turbine Tripped.

• Verify Vital 4 KV Buses Energized.

SRO Enter E-0, Reactor Trip or Safety Injection

• Verify completion of Immediate Actions.

• Recognizes RCP trip criteria met, directs RCPs to be tripped. **

• Direct implementation of Appendix E.

• Checks status of AFW flows, direct throttling to minimum required flow.

• Determines SG 1-2 is Faulted recognizes procedure transition RO Implements Appendix E

• Performs verification steps in Appendix E

• Reports status to SRO at step 9 and 18 Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

BOP Throttles AFW flow as directed by SRO.

• Closes TD AFW pump LCVs.

RO/BOP Th l Coolant Trips Reactor MD AFWpumps**

LCV

• • Critical Task Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Op-Test L061-1 Scenario 3 Event 7 Page 7 of 7 No.: No.: No.:

Event Main Steam Line break on S/G 12

Description:

Time Position Applicants Actions or Behavior SRO Conducts Procedure Transition Brief for E-2, Faulted Steam Generation Isolation.

• Plant Status

• Major Actions SRO Enter E-2, Faulted Steam Generation Isolation.

• Directs Isolation of Steam Generator 1-2 (Early Isolation may have been performed as part of E-0)

• Transitions to E 3 at Step 7 of E 2 valid alarms on SG Rad BOP Performs Isolation Steps for Steam Generator 1-2 **

• Verifies All MSIVs and Bypass Valves Closed

• Checks for any Intact SG

• Identifies Faulted SGs as only 1-2.

• Isolates Faulted SG 1-2 o Verifies Feedwater Isolation Valve Closed - FCV-439 o Verifies Blowdown Isolation Valves are Closed o Verifies 10% Dump Valve is closed o Verifies AFW flow is isolated**

SRO Conducts Procedure Transition Brief for E-3, Steam Generator Tube Rupture.

• Plant Status

• Major Actions SRO Enters E-3, Steam Generator Tube Rupture

• Directs isolation of Steam Generator 1-2 (Early Isolation may have been performed as part of E-0)

• Determines Feedwater flow should remain isolated to SG 1-2.**

• Determines Ruptured SG pressure is less than 225 psig.**

RO/BOP Verify Isolation Steps are completed as directed by SRO.

Terminate scenario after transition to ECA 3.1 Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

• • Critical Task Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

MAJOR EVENT

SUMMARY

AND SCENARIO OBJECTIVES U. Places 10% steam dumps at lower setting for low power conditions.

V. Starts ramp to 20% power at 2-5 MW/min per OP L-4. Operator should perform boration to counter positive reactivity from ramp.

W. Containment Fan Cooler Unit (CFCU) 14 trips on overcurrent. Crew will start CFCU 1-5 X. Pzr controlling level channel (LT-459) fails low causing a letdown isolation. Pzr heater will also be de-energized. Crew takes manual control of charging flow and reduces to minimum.

Another level channel is selected for control per AP-5, and letdown is restored per OP B-1A:XII.

Y. After letdown is restored, a Letdown Heat Exchanger tube leak develops that requires manual letdown isolation. Crew will respond per AP-11, and excess letdown will placed in service.

Z. A 600 gpm S/G tube leak will develop on S/G 12 requiring a Safety Injection per AP-3. On the reactor trip a steam line break outside containment will occur for S/G 12.

AA. Crew will go from E-0 to E-2, although an early isolation of S/G 12 may be performed while in E-0.

BB. Crew will transition from E-2 to E-3. E-3 will require a transition to ECA 3.1 for a faulted/ruptured S/G.

CC. Terminate scenario after transition to ECA 3.1.

Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

1.6.3.3.1.1 ATTACHMENT 1 - SIMULATOR SET-UP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Init NRC03 25% power, BOL, CB = 1182 Simulator per

• Integrators: BA - 4 and PW - 0 Checklist

• Tags: FCV-95, FCV-37 & 38 , CFCU 1-2 Setup Drill 81 Reset normal engineering values Setup dsc vent1 act,0,0,0,d,0 (Open Clears CFCU 1 Hang tag Bkr)

Setup Drill 57 Clears TDAFWP Turn on Pzr backup heaters Per ramp plan 1 PPC SDS with SCREENS display CONTROL BOARD SETUP Copies of commonly used forms and procedures are available.

Any tags are placed/removed as necessary - close FCV-37 & 38, then place tags. CFCU 1-2 Primary integrator = 0 gal, Boron = 10 gal.

Record PPC MAX (BOL = 99.8, MOL = 100.0, EOL = 100.2) on CC2 lamicoid The plant Abnormal Status Board is updated with last CCP CB near 1182 and current date, XLD boron conc at 2200 ppm.

Circuit breaker flags are correct.

Equipment status lamicoids are correct:

B.A. XFER PP SUPPLYING BLENDER - BA Pp 1-2 SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - Cont. Rm. Vent Train 1 Bus F SELECTED TO BUS 1H - Cont. Rm. Vent Train 1 Bus H The proper Delta-I curve and Reactivity Handbook for the simulator INIT are in place The Rod Step Counters indicate correctly.

PPC Setup:

o QP TAVG, ALM/MODE-1, QP CHARGING, BIG U1169 o RBU is updated.

o PEN running.

o R2B blowdown flows at 90 gpm.

o Reactor trip status correct 5(Pg 2 of Group display Mode-1).

o Operational mode correct for current conditions.6 o Delta-I target slope matches Delta-I curve (DeltaI menu Option 5, constants K0500-0503=100% power target DeltaI / 100)

SPDS (screens and time updating), A screen RM, B screen SPDS.

The chart recorders are operating properly, and advanced.

All typewriters are on, with adequate paper/ribbon/etc., and are in the ON LINE status.

5 If not correct, place PPC display in ovrd mode, and press add/omit key. Type point Y0006D and select F2 to restore processing. This should update the trip breaker status.

6 Allow about ten minutes for the PPC to automatically update the plant mode. If still not correct, place PPC display in ovrd mode, and type APMC.

Follow menu to manually override to correct mode.

Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

The Annunciator Horn is on (BELL ON).

Sound Effects are on (SOUND ON).

The video and audio systems are SECURED.

Communications systems are turned on and functional.

Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

1.6.3.3.1.2 TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION X = manual entry required X 0 min DRILL 6605 After SRO reports the crew has taken the watch, load session MALS, OVRs, etc. by DRILL FILE or MANUALLY (below) 2 min after pmp ven8 4,0,0,120,c,ggo CFCU 14 OC trip starting ramp X when CFCU 1-4 tripped on thermal overload - Blue light is lit.

requested 7 min after xmt pzr40 3,-13,0,420, LT-459 Pzr level fails low CFCU trip c,ochfs14.lt.0.5 4 min after mal ccw2 act 100,120,240, Letdown HX leak letdown c,xv2i214o restored X when LCV-69 & 70 are closed.

requested X when loa ccw27 act,0,0,0,d,0 close CCW-406 & 409 to isolate L/D requested HX after FCV-361 mal rcs4b act 600,120,10, SGTR 12 at 600 gpm opened c,xv1i213o X On reactor trip Drill 32 NO action on reactor trip On reactor trip mal mss3b act,9.0e6,10,10, S/G 12 steam break outside c,fnispr.lt.5.0 containment X If Requested to Drill 17 Opens S/G Blowdown sample valves sample S/G s if no Phase A.

per CAP AP-1 Ask if Phase A reset & Inside Cnm B/D valves are open (per CAP AP-1) prior to running drill.

Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

DIABLO CANYON POWER PLANT OPERATIONS SHIFT LOG UNIT 1 OPERATING MODE: 1 POWER LEVEL: 25  %

GROSS GENERATION: 246 MWe NET GENERATION 202 MWe DAYS AT POWER: 15 1.6.4 Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: GREEN - TDAFP 1-1 MOW PROTECTED EQUIPMENT: Train A & B, Buses F, G & H, Prot Sets I,II,III & IV HOMELAND SECURITY THREAT LEVEL: YELLOW GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.05 gpm URGENT WORK:

• None ACTIVE SHUTDOWN TECH SPECS / ECGS:

• TDAFP 1 TS 3.7.5 Action B - 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, due in 70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br />.

TURNOVER ITEMS:

• A bearing is being replaced on TDAFP 1-1. It was removed from service 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago. Work is expected to be completed in approximately 12 more hours.

• High Swell Warning in effect. Reduce power to 20% on both units in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Unit 2 power reduction to 20% was completed 10 minutes ago.

• Ramp to 20% power was delayed by problems with Main Feedwater Bypass valves. Issue has been resolved, continue ramp to 20% Per OP L-4 step 6.4.3.t.

• OP O-28 Intake Management actions have been implemented.

• Camera at Intake is OOS for maintenance, do back in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

• CFCU 1-2 is cleared for motor replacement.

OPERABILITY ITEMS:

• None PRIORITY ITEMS FOR NEXT SHIFT:

• Reduce power to 20% per OP L-4.

Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

• OP L-4 step 6.4.3 is in progress, and complete up to sub-step 6.4.3t, all Prerequisites have been met.

ANNUNCIATORS IN ALARM

• PK 09-18 1.6.4.1.1 Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

1.6.4.1.2 SHIFT FOREMAN TURNOVER COMMENTS:

7. Reactivity management:

a. Time in core life: BOL

b. Power History: 100%

c. Boron concentration is 1182 ppm from a sample taken 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.

d. Borate 10 gallon batches as needed for Tavg Control per Reactor Engineering.

e. Ramp at 3 MW/min to 200 MW.

f. Use rods as needed to maintain I with in +/- 2% of target.

8. No one is in Containment, no entries are expected

9. U-2 is ramping to 20% power.

COMPENSATORY MEASURES:

None 1.6.4.2 CONTROL ROOM ABNORMAL STATUS See Abnormal Status Board.

1.6.4.3 Ramp Plan for reduction to 20% Power Borate 10 gallon per Reactor Engineering.

Ramp down to 200 MW, at 3 MW/min.

Leave Rod Control in Auto, Use rods in manual as needed to maintain I with in +/- 2% of target.

Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2

Scenario 03 DC-2008-06-FINAL OPERATING TEST.DOC Rev.2 Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Diablo Scenario 4 Op-Test No.: L061-1 Canyon No.:

Examiner Operators s:  :

Initial Conditions: 75% BOL, 1251 ppm CB Turnover: PRA - Yellow. Auxiliary Saltwater Pump 11 cleared for motor inspection. Unit has been operating at 75% power for 3 days due to 500kV transmission line problems. Line problems have been resolved, and Cal ISO requests full power output to prevent Stage 3 Involuntary power interruptions.

Direction is to return unit to full power as soon as possible. Unit 2 is at 100% power.

Event Malf. Eve Event Description and Time Line No. No. nt Typ e*

1 R Ramp to 100% power per OP L-4.

2 mal rod6a I Continuous rod motion after first rod movement.

3 pmp cvc3 C Charging Pump 13 over current trip, 7 min after rod problem. (ECG 8.1) 4 dsc rod1 I Loss of normal DRPI power. (TS 3.1.7) **NOT USED**

5 xmt pzr15 I Controlling PZR pressure channel (PT-457) fails 5 min after DRPI power is restored. ( TS 3.3.1, 3.3.2, 3.3.3).

6 mal sei1 M 0.25 g Earthquake, 6 min after PT-457 fails low.

7 mal mfw2b C MFW PP 12 trips on high vibration due to earthquake.

8 mal mss4 M Main steam line break downstream of MSIVs after MFW pp trip 9 vlv mss9 C MSIV for SG 13 fails to close 10 mal ppl3a C Auto safety injection will not actuate, operators must perform a mal ppl3b manual SI.

Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

• • NOTE** - This scenario was terminated when the SRO transitioned to EOP Procedure E-2.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 4 Event 1 Page 1 of 9 No.: No.: No.:

Event Ramp to 100% power

Description:

Time Position Applicants Actions or Behavior SRO Reviews and briefs OP L-4 for ramp to 100%.

• Covers Ramp Plan - 5 MW/Min Ramp.

• Performs reactivity Brief for ramp (Dilution Plan)

SRO Directs RO to perform RCS dilution for ramp.

RO Performs Dilution of RCS in accordance with OP B-1A:VII, Makeup Control System Operation, may use Attachment 1 for guidance.

• Set target Batch on flow controller (100 gallons)

• Verify Primary Water Flow Rate set to desired flow.

• Start Dilution and verify response.

SRO Directs RO to perform ramp to 100%.

RO Sets up ramp on DEHC Console per SRO direction using OP C-3:III, Main Unit Turbine - At Power Operations. (May use Committed Posting for Direction)

• Raise Valve Position Limit.

• Places MW feedback in service.

• Set desired Ramp Rate. (3 MW/Min)

Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

13 14 Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 4 Event 2 Page 2 of 9 No.: No.: No.:

Event Uncontrolled outward rod motion

Description:

Time Position Applicants Actions or Behavior RO Diagnoses unexpected control rod motion.

SRO Directs RO to place Rods in Manual RO Places Rod Control in Manual and verifies rod motion has stopped **

SRO Enters AP-12A, Continuous Withdrawal or Insertion of a Control Rod Bank.

• Verifies Rod Control is in Manual

• Verifies Rod Motion has stopped.

• Directs RO to match Tavg and Tref using turbine as needed.

RO/BOP May place ramp on hold to maintain temperature.

BOP Restart Ramp as needed for temperature control.

Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

• • Critical Task Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 4 Event 3 Page 3 of 9 No.: No.: No.:

Event Charging pump 13 overcurrent trip

Description:

Time Position Applicants Actions or Behavior RO/BOP Diagnose trip of CCP 1-3 RO Acknowledge alarm PK 04-16, input 217, Charging Pump 1-3 OC Trip.

SRO Responds per Annunciator Response Procedure PK 04-16.

• Checks indications to confirm alarm - Blue light on pump

• Determines AP-17 Loss of Charging is appropriate procedure t dd thi t BOP Diagnose Letdown Isolation and report to SRO.

SRO Enters AP-17, Loss of Charging. Section A.

• Directs BOP to verify a suction flowpath.

• Directs BOP to Verify charging pump recirc valves are open.

• Directs RO to Close FCV-128

• Directs BOP to Start ECCS Charging pump (either one)

• Directs RO to establish minimum charging flow to RCP seals l

BOP Performs actions as directed by SRO

• Verifies suction path from VCT to charging pump suction is aligned by checking LCV-112 B & C Open.

• Verifies CCP recirc valves are open (8105 and 8106).

RO Performs actions as directed by SRO.

• Closes FCV-128 Establishes minim m flo (9 gpm) to RCP seals onl BOP/RO Re-establishes letdown per OP B-1A:XII, CVCS - Letdown System, Establish Normal Letdown following Letdown Isolation.

• Places PCV-135 in manual and opens to 60%

• Places TCV-130 in manual and opens to 50%

• Increase charging flow to ~87 gpm and adjust seal injection flow.

• Open Letdown Orifice valve 8149C RO Returns Pzr level control to Auto (as time permits)

Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 4 Event 4 Page 4 of 9 No.: No.: No.:

Event Loss of DRPI power - ***Event NOT USED***

Description:

Time Position Applicants Actions or Behavior RO/BOP Diagnose Loss of DRPI indication.

SRO Direct RO to verify Rod Control is in Manual.

RO Verify Rod Control is in Manual.

RO Acknowledge alarm PK 03-21, input 553, Rod Position Indication Urgent SRO Responds per Annunciator Response Procedure PK 03-21.

• Verify Rod Control is in Manual

• Verify Ramp is placed on HOLD

• Refer to Tech Spec 3.1.7, DRPI System (Determines Action B applies - rods to manual, monitor temperature and restore in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.)

Di N l O l DRPI b k l

• • • EVENT NOT USED***

Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 4 Event 5 Page 5 of 9 No.: No.: No.:

Event Pzr Pressure Channel PT-457 fails low.

Description:

Time Position Applicants Actions or Behavior BOP/RO Diagnose Pressurizer Pressure Channel PT-457 Failing Low.

SRO Direct RO to place pressure control in MANUAL and control pressure.

RO Places Pressure Control in Manual and controls to maintain Pressurizer Pressure RO Acknowledge alarm PK 05-17, input 535, Pressurizer Pressure Low SRO Responds per Annunciator Response Procedure PK 05-17.

• Directs BOP to channel check all PZR Pressure Channels.

• Determines AP-5, Malfunction of Eagle 21 Protection or Control Channel is appropriate procedure to address this BOP Report failure of PT-457 and other channels are SAT.

SRO Enters AP-5, Malfunction of Eagle 21 Protection or Control Channel.

• Verifies Primary and Secondary Control Systems are controlling properly in AUTO (Step to place pressure control in manual will be completed prior to this step)

• Determines failure not to be related to Eagle 21.

• Determines alternate channel is available for selection. (Directs RO to select alternate Pressurizer Pressure Control Channel)

• Determines redundant recorder is available. (Directs RO to select matching Pressurizer pressure recorder)

• Determines LTB and Steam Dumps are not actuated.

• Notifies Maintenance to investigate

• Uses attachment 4.1 determine affected control systems.

• Directs RO to restore Pressurizer Heaters

• Refers to Tech Spec o 3.3.1.M (Place channel in tripped position within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in MODE 3 in 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> )

RO Selects alternate channel (455/456) for Pressurizer Pressure Control and Recorder Input.

RO Returns Pressurizer Pressure Control to Auto (if time permits),

including Heaters Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 4 Event 6&7 Page 6 of 9 No.: No.: No.:

Event 0.25g Earthquake/Main Feedwater Pump 1-2 Trip

Description:

Time Position Applicants Actions or Behavior RO/BOP Diagnose seismic event, based on ground motion and seismic alarms.

/

RO/BOP Diagnose Main Feedwater Pump 1-2 High Vibrations RO Acknowledge multiple alarms (high priority is PK 09-12, input 588, FWP 1-2 Turbine Trip) RED Window.

SRO Responds per Annunciator Response Procedure PK 09-12 Main Feedwater Pump Trip

• May Enter AP-15 Loss of Feedwater Flow Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 4 Event 8 Page 7 of 9 No.: No.: No.:

Event Main steam line break downstream of MSIVs

Description:

Time Position Applicants Actions or Behavior BOP/RO Diagnoses Steam line break SRO Directs Manual Reactor Trip and Safety Injection RO Performs Manual Reactor Trip and Safety Injection (Auto will not RO/BOP )** immediate actions:

Perform

• Verify Reactor Tripped.

• Verify Turbine Tripped.

• Verify Vital 4 KV Buses Energized.

SRO Enter E-0, Reactor Trip or Safety Injection

• Verify completion of Immediate Actions.

• Direct implementation of Appendix E.

• Checks status of AFW flows, direct throttling to minimum required flow.

• Checks for RCS cooldown.

• Checks Pressurizer safeties, PORVs and Spray valves closed.

• Checks steam generators are not faulted or ruptured.

• Determines Steam Generator 1-3 is faulted and recognizes procedure transition criteria met for EOP E-2, Faulted Steam Generator Isolation.

• Implements F 0 monitors CSFSTs No Challenges RO Implements Appendix E

• Performs verification steps in Appendix E Reports stat s to SRO at step 9 and 18 BOP Throttles AFW flow as directed by SRO.

• Closes TD AFW pump LCVs.

Throttles MD AFW LCVs (Ma Isolate flo to SG 1 3)

Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

• • Critical Task Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 4 Event 9 Page 8 of 9 No.: No.: No.:

Event MSIV for S/G 13 fails open

Description:

Time Position Applicants Actions or Behavior SRO Conducts Procedure Transition Brief for E-2, Faulted Steam Generation Isolation.

• Plant Status

• Major Actions SRO Enter E-2, Faulted Steam Generation Isolation.

• Directs Isolation of Steam Generator 1-3 (Early Isolation may have been performed as part of E-0)

• Determines ECCS Flow should be reduced.

• Transitions to E 1 1 SI Termination at Step 8 of E 2 BOP Performs Isolation Steps for Steam Generator 1-3

• Verifies All MSIVs and Bypass Valves Closed o Determines MSIV 43 (Steam Lead 3) will not close.

o Dispatches Nuclear Operator to implement Appendix L

• Checks for any Intact SG

• Identifies Faulted SGs as only 1-3.

• Isolates Faulted SG 1-3 o Verifies Feedwater Isolation Valve Closed - FCV-440 o Verifies Blowdown Isolation Valves are Closed o Verifies 10% Dump Valve is closed Verifies AFW flo is isolated **

BOP Reports MSIV 43 will not close to SRO.

Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

• • Critical Task Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 4 Event 10 Page 9 of 9 No.: No.: No.:

Event Auto Safety Injection will not actuate/ SI Termination

Description:

Time Position Applicants Actions or Behavior See event 8 for actions for auto SI malfunction.

SRO Conducts Procedure Transition Brief for E-1.1, SI Termination.

• Plant Status

• Major Actions

• Foldout Page Assignments Enters E-1.1, SI Termination

• Directs RO to Reset SI

• Directs RO/BOP to align Charging.

• Verifies Pressure is stable or increasing.

• Directs RO to isolate Charging Injection.

• Directs RO to secure both SI Pumps.

RO Resets both trains of Safety Injection.

BOP Resets Auto Transfer Relays (3) - Blue lights out.

RO Secures 1 ECCS Charging Pump.

RO Closes 8803 A/B and 8801 A/B to isolate charging injection RO/BOP Establish normal charging flow and seal injection Terminate scenario after Normal Charging is established Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1 MAJOR EVENT

SUMMARY

AND SCENARIO OBJECTIVES DD. Crew starts ramp to 100% power per OP L-4. A dilution will be required to counter the negative reactivity from the ramp.

EE. Continuous rod motion will occur on the first rod movement. Control Operator will take rods to manual. Crew refers to AP-12A. Ramp may be placed on hold FF. Charging pump 13 will trip on overcurrent, which will isolate letdown. Crew refers to AP-17, Crew will then start another Charging Pump and restore letdown.

GG. DRPI normal power supply will be lost. Crew refers to PK03-21. DRPI power will be transferred to backup. ***EVENT NOT USED***

HH. Pzr pressure controlling channel PT-457 fails low, which turns backup heaters on. Crew refers to AP-5, and swaps controlling channels to restore pressure control.

II. An earthquake (0.25g) occurs which causes MFW pp 12 to trip. Since power is below 80%, a manual reactor trip is not called for.

JJ. After the MFW pp trip, a steam line break occurs downstream of the MSIVs. The MSIV for S/G 13 will not close.

KK. An automatic Safety Injection will not occur, forcing the crew to perform a manual SI.

LL. The crew with move through E-0 and may perform an early isolation of S/G 13. The crew will then go to E-2 and E-1.1.

MM. The scenario is terminated after Normal charging is established in E-1.1.

Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

1.6.4.3.1.1 ATTACHMENT 1 - SIMULATOR SET-UP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Init NRC04 75% power, BOL, CB = 1251 Simulator per

• Integrators: BA - 4 and PW - 0 Checklist

• Tags: ASW pp 11 C/S Setup Drill 81 Reset normal engineering values Setup Transfer turbine to sequential Prepares Turbine for ramp up.

valve and remove feebacks.

Setup Start ASW pp 12 & align ASW Swaps to ASW pp 12 going thru CCW and CCW thru CCW HX 12. HX 12.

Shutdown ASW pp 11.

Then manually enter: Secures ASW pp 11 and opens DC

• loa asw6 act,0,0,0,d,0 knife switch and turns off UV alarm to

• ser 0146 act,0,0,0,d,0 simulate racking out the pump breaker.

Swap CL and Radwaste tags to CCW HX 1-2 CONTROL BOARD SETUP Copies of commonly used forms and procedures are available.

Any tags are placed/removed as necessary.

Primary integrator = 0 gal, Boron = 4 gal.

Record PPC MAX (BOL = 99.8, MOL = 100.0, EOL = 100.2) on CC2 lamicoid The plant Abnormal Status Board is updated with last CCP CB near 1251 and current date.

Circuit breaker flags are correct.

Equipment status lamicoids are correct:

B.A. XFER PP SUPPLYING BLENDER - BA Pp 1-2 SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - Cont. Rm. Vent Train 1 Bus F SELECTED TO BUS 1H - Cont. Rm. Vent Train 1 Bus H The proper Delta-I curve and Reactivity Handbook for the simulator INIT are in place The Rod Step Counters indicate correctly.

PPC Setup:

o QP TAVG, ALM/MODE-1, QP CHARGING, BIG U1169 o RBU is updated.

o PEN running.

o R2B blowdown flows at 90 gpm.

o Reactor trip status correct 7(Pg 2 of Group display Mode-1).

o Operational mode correct for current conditions.8 7

If not correct, place PPC display in ovrd mode, and press add/omit key. Type point Y0006D and select F2 to restore processing. This should update the trip breaker status.

8 Allow about ten minutes for the PPC to automatically update the plant mode. If still not correct, place PPC display in ovrd mode, and type APMC.

Follow menu to manually override to correct mode.

Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

o Delta-I target slope matches Delta-I curve (DeltaI menu Option 5, constants K0500-0503=100% power target DeltaI / 100)

SPDS (screens and time updating), A screen RM, B screen SPDS.

The chart recorders are operating properly, and advanced.

All typewriters are on, with adequate paper/ribbon/etc., and are in the ON LINE status.

The Annunciator Horn is on (BELL ON).

Sound Effects are on (SOUND ON).

The video and audio systems are SECURED.

Communications systems are turned on and functional.

Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

1.6.4.3.1.2 TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION X = manual entry required X 0 min DRILL 6606 After SRO reports the crew has taken the watch, load session MALS, OVRs, etc. by DRILL FILE or MANUALLY (below) 0 min mal rod6a act Continuous rod motion on first 8,0,0,c,xc1o026l outward rod movement. ***

0 min mal ppl3a act 1,0,0,d,0 Auto SI is prevented from being actuated.

mal ppl3b act 1,0,0,d,0 0 min vlv mss9 1,0,0,0,d,0 FCV-43 S/G 13 MSIV fails open 7 min after rod pmp cvc3 CCP 13 overcurrent trip.

problem 6,7.02,5,420,c,jmlrod6(1) when Report that CCP 13 motor hot to touch, C phase over current flag requested at 52-HG-11.

5 min after dsc rod1 Loss of DRPI normal power supply.

letdown act,0,0,300,c,xv2i214o restored ***EVENT NOT USED***

X when requested Report that the normal supply breaker (52-1F-45) has tripped open and will not reset. Circuit downstream of the breaker checks out SAT. (Time Compression)

X when loa eps1 act,1,0,0,d,0 DRPI on backup power requested 5 min after LD xmt pzr21 2,0,0,300,c,iepsdrpi PT-457 fails low Restored 6 min after PT- mal sei1 act 0.25,10,360, 0.25g earthquake 457 failure c,pxmtpzr(3).lt.1300 On Seismic mal mfw2b act MFW pp 12 hi vibration trip 24,20,10,c,jmlsei1 On MFW pp mal mss4 act 1e+07,120,30, Main steam line break downstream of trip c,jmlmfw2(2) MSIVs On reactor trip Drill 32 NO actions on a reactor trip when Report that Appendix L has been performed and FCV-43 will not requested close.

• • • if required to cause outward rod motion in a reasonable time period, increase RCS boron concentration in 1 ppm segments using a 60 sec ramp in mal rcs5 to get Tavg < Tref.

Scenario 04 DC-2008-06-FINAL OPERATING TEST.DOC REV. 1

DIABLO CANYON POWER PLANT OPERATIONS SHIFT LOG UNIT 1 OPERATING MODE: 1 POWER LEVEL: 75  %

GROSS GENERATION: 901 MWe NET GENERATION 865 MWe DAYS AT POWER: 21 1.6.5 Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: Green - ASW PP 1-1 MOW PROTECTED EQUIPMENT: Train B, Buses H & G, Prot. Sets II,III,IV HOMELAND SECURITY THREAT LEVEL: YELLOW GRID STATUS NEXT SHIFT: CAL ISO has declared a Stage 2 Emergency, Stage 3 Emergency is imminent unless more generation comes on line.

AVERAGE RCS CALCULATED LEAKRATE: 0.05 gpm URGENT WORK:

• None ACTIVE SHUTDOWN TECH SPECS / ECGS:

• ASW PP 1 motor inspection. T.S 3.7.4.A - 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Due in 62 hours7.175926e-4 days <br />0.0172 hours <br />1.025132e-4 weeks <br />2.3591e-5 months <br />.

TURNOVER ITEMS:

• ASW PP 1-1 was cleared 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> ago to perform a motor inspection. It is expected to be returned to service in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

• Unit has been operating at 75% power for 3 days due to 500kV transmission line problems. Line problems have been resolved, and Cal ISO requests full power output to prevent Stage 3 Involuntary power interruptions.

• Direction is to return unit to full power as soon as possible per OP L-4.

• OP L-4 step 6.2.3 is in progress, and complete up to sub-step d.2, all Prerequisites have been met.

OPERABILITY ITEMS:

• None PRIORITY ITEMS FOR NEXT SHIFT:

• Return unit to full power as soon as possible.

Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1

ANNUNCIATORS IN ALARM

• None 1.6.5.1.1 Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1

1.6.5.1.2 SHIFT FOREMAN TURNOVER COMMENTS:

10. Reactivity management:

a. Time in core life: BOL

b. Power History: 75% for last 3 days.

c. Boron concentration is 1251 ppm from a sample taken 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.

d. Commence 100 gallon dilutions every 15 minutes for first hour per Reactor Engineering.

e. Commence ramp to 1160 MW at 5 MW/min. Lower ramp rate as needed to keep I in target band and Tavg +/- 3 F of Tref.

f. Leave rods in Auto, unless needed to maintain I in target band.

11. No one is in Containment, no entries are expected

12. U-2 is operating at 100% power COMPENSATORY MEASURES:

None 1.6.5.2 CONTROL ROOM ABNORMAL STATUS See Abnormal Status Board.

1.6.5.3 Ramp Plan for return to 100% Power Perform one 300 gal dilution prior to ramp.

Ramp Turbine at 5 MW/Min to 95% power.

Leave Rod Control in Auto.

Perform additional dilutions as needed to maintain Tavg and Tref matched.

Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1

Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1 Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Diablo Scenario 5 -BU Op-Test No.: L061-1 Canyon No.:

Examiner Operators s:  :

Initial Conditions: 100% Power, MOL, 782 ppm CB Turnover: PRA Status: Yellow. Protected Equipment - Train B, Buses H& G, Prot. Sets II, III, IV. RHR pp 11 is cleared for seal repair. U-2 at 100% power.

Event Malf. Eve Event Description and Time Line No. No. nt Typ e*

1 mal cvc8 C RCP seal injection filter plugs up, reducing charging flow to seals.

2 R TOC requests ramp to 800 MW at 25 MW/min 3 xmt rcs93 I Loop 3 NR Tcold fails high at 1000 MW. (TS )

4 mal eps4c C 4KV bus F diff trip 12 min after Loop 3 Tcold failure (TS )

5 mal mfw2a C Both MFW pumps trip spuriously.

mal mfw2b 6 mal ppl5a M Reactor trip breakers wont open from the control room. ATWS.

mal ppl5b 7 ovr C 52-hd-13 fdr for bus 13d fails to open, so 1 MG set stays in service.

xv5i245o Crew must insert rods and go to FR S.1.

8 vlv afw7 C TDAFW pp 11 fcv-95 won't open automatically, crew must open at VB3.

Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 5 Event 1 Page 1 of 6 No.: No.: No.:

Event RCP seal injection filter plugs.

Description:

Time Position Applicants Actions or Behavior RO Diagnose RCP seal injection filter plugging.

RO Acknowledge alarm PK 04-22, input 498, RCP Seal Injection Filter 1 SRO Responds per Annunciator Response Procedure PK 04-22.

• Direct RO to throttle HCV-142 as needed to control flow.

• Monitor RCP operation - PPC Display - RCP

• Direct Nuclear Operator to swap seal injection filters.

Direct RO to reestablish RCP seal flow when filter is swapped RO Reestablish seal injection flow of >8 gpm using HCV-142.

BOP Monitor RCP parameters as directed by SRO.

Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 5 Event 2 Page 2 of 6 No.: No.: No.:

Event Ramp to 800 MW at 25 MW/min

Description:

Time Position Applicants Actions or Behavior SRO Receives call from TOC - Ramp to 800 MW at 25 MW/MIN.

SRO Enters AP-25 Rapid Load Reduction or Shutdown.

• Directs RO to Reduce Turbine Load - 800 MW target @ 25 MW/MIN.

• Verifies Control Rods inserting in Auto.

• Verifies Pressurizer backup heaters - ON.

• Verifies Charging system operation is adequate.

Verifies Digital Feedwater Controls controlling SG Levels in BOP/RO Sets up ramp on DEHC Console per SRO direction using OP C-3:III, Main Unit Turbine - At Power Operations. (May use Committed Posting for Direction)

• Places MW feedback in service.

• Set desired Ram Rate. (25MW/Min)

S tT t t d i d l d (800 MW)

RO Verify Control Rods inserting in Auto in response to Ramp.

RO Verifies Backup Pressurizer Heater groups are ON.

BOP/RO Verify Charging System operation is adequate.

• Verifies at Least One Charging Pump is in service.

• Controls charging in Manual as needed to prevent Letdown RO Performs Boration of RCS using Boration Checklist and Makeup controller.

• Set Target Batch on flow controller (as determined by SRO)

• Verify Boric Acid Flow rate set to desired flow.

Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 5 Event 3 Page 3 of 6 No.: No.: No.:

Event Loop 3 NR Tcold fails high at 1000 MW.

Description:

Time Position Applicants Actions or Behavior RO Diagnose inward rod motion as unwarranted.

BOP Diagnose Loop 3 Tavg Failure.

SRO Direct RO to Place Rods in Manual and Ramp on HOLD.

RO Select Manual on Rod Control and place Ramp on HOLD.

RO Acknowledge Alarm PK 04-02, Input 388, Tavg deviation LP3.

SRO Responds per Annunciator Response Procedure PK 06-03.

• Directs BOP to channel check all Temperature Channels.

• Determines AP-5, Malfunction of Eagle 21 Protection or Control Channel is appropriate procedure to address this BOP Report failure of Loop 3 Temperature channels and all others are SRO Enters AP-5, Malfunction of Eagle 21 Protection or Control Channel.

• Verifies Primary and Secondary Control Systems are controlling properly in AUTO (Step to place rod control in manual will be completed prior to this step)

• Determines failure is related to Eagle 21.

• Dispatches operator to Eagle 21 Protection Set 3 racks 11 & 13.

• Determines alternate channel is available for selection. (Directs RO to Loopout Loop 3 T & Tavg) and return rods to auto.

• Determines LTB and Steam Dumps are not actuated.

• Notifies Maintenance to investigate

• Uses attachment 4.1 determine affected control systems.

• Refers to Tech Spec o 3.3.1.E (Place channel in tripped position within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in MODE 3 in 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> )

RO Defeats Loop 3 inputs to rod control, Loop 3 T & Tavg.

RO Returns Rod control to Automatic when Tavg/Tref is within 1F.

Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1

RO/BOP Resumes ramp (as time permits)

Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 5 Event 4 Page 4 of 6 No.: No.: No.:

Event 4KV bus F diff trip 12 min after Loop 3 Tcold failure

Description:

Time Position Applicants Actions or Behavior BOP Diagnoses failure of 4kV Bus F RO Recognizes loss of DRPI, places rods in manual RO Acknowledges multiple alarms - Determines PK 18-17, input 141 is highest priority, 4 kV bus F UV.

SRO Responds per Annunciator response Procedure PK18-17 (PK18-16 and 18-22)

• Determines AP-27 Loss of Vital 4 kV and/or 480V Bus is SRO Enters AP-27, Loss of Vital 4 kV and/or 480V Bus.

• Determines DRPI is de-energized - directs RO to Place Rods in Manual and place Ramp on HOLD.

• Directs Nuclear Operator to place DRPI on Backup.

• Contacts Maintenance to investigate failure.

• Directs RO/BOP to verify Pumps are running (Starts CCW pump 1-3)

• Implements attachment 4.1 for loss of 480V Bus F.

• Directs BOP to place PORV PCV-474 in closed position.

• Direct BOP to place CFCU 1-5 in service.

• Direct BOP to secure Diesel Generator 1-3

• Direct Nuclear Operators to place Battery Charger 1-1 on Charger 121 BOP Manually starts alternate equipment as required:

• CFCU 15 CCW pp13 BOP Positions PCV-474 to close BOP Shuts down D/G 1-3 RO Returns Control Rods to Auto when DRPI is restored.

Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1

Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 5 Event 5, 7, 8, Page 5 of 6 No.: No.: No.: 9 Event Feed Pumps trip / ATWS

Description:

Time Position Applicants Actions or Behavior RO/BOP Diagnose both Main Feedwater Pumps have tripped, manually trips

/ the reactor.

RO/BOP Recognizes Reactor Trip Initiate without Actuation.

SRO SRO Directs RO and BOP to Perform Immediate Actions RO Attempts a manual Reactor Trip - Reports Reactor did not trip BOP Attempts to open 13D/13E breakers - Reports 13D will not open.

SRO Diagnose an ATWS RO Manually inserts control rods **

BOP Trips main turbine **

SRO Enters E-0, Reactor Trip or Safety Injection

• Determines Reactor will not trip.

• Determines Transition to FR-S.1Response to Nuclear Power Generation ATWS is required SRO Enters FR-S.1, Response to Nuclear Power Generation ATWS

• Verifies Control Rods are be inserted

• Dispatch personnel to open Reactor Trip Breakers Locally.

• Verify turbine is tripped.

• Verify status of AFW - Direct BOP to start TDAFW Pump

• Directs RO to Start Emergency Boration

• Verifies Reactor is sub-critical & adequate SDM BOP Diagnoses that AFW Pump 1-1 has failed to start.

• Starts TDAFW pump **

RO Reports to SRO when Reactor Trip Breakers are opened.

RO Initiates emergency boration Terminate scenario after transition to E-0.1 Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1

Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test L061-1 Scenario 5 Event 6 Page 6 of 6 No.: No.: No.:

Event Both Main Feedwater pumps trip

Description:

Time Position Applicants Actions or Behavior BOP Reports to SRO both MFW pumps are tripped, no main Feedwater flow is available SRO Acknowledge report of No Main Feedwater Available.

Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1

MAJOR EVENT

SUMMARY

AND SCENARIO OBJECTIVES NN. RCP seal injection filter plugs up, reducing charging flow to seals. Crew refers to PK 04-22 and swaps to other filter.

OO. TOC requests ramp down to 800 MW at 25 MW/min.

PP. At 1000 MW, a Loop 3 Tcold RTD fails high, which causes rods to drive in. Rod control is taken to manual and crew refers to AP-5 for actions.

QQ. 4KV Bus F de-energizes due to a differential trip. Crew refers to AP-27 for actions.

RR. Both MFW pumps trip spuriously. Crew should try to manually trip the reactor. Crew goes from E-0 to FR S.1 since 52-HD-13 breaker will not open from the control room.

SS. Turbine driven AFW pp 11 must be manually started from VB3.

TT. Crew transitions back to E-0 from FR S.1 and then to E-0.1 for Reactor trip recovery.

UU. Terminate scenario after transition to E-0.1.

Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1

1.6.5.3.1.1 ATTACHMENT 1 - SIMULATOR SET-UP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Init 510 100% power, MOL, CB = 782 Simulator per

• Integrators: BA - 0 and PW - 40 Checklist

• Tags: CT - RHR pp 11 Setup Drill 81 Reset normal engineering values Setup

• loa rhr9 act,0,0,0,d,0 Clears RHR pp 1-1, overides DC

• ser 0219 act,0,0,0,d,0 undervoltage alarm off to simulate Breaker racked out CONTROL BOARD SETUP Copies of commonly used forms and procedures are available.

Any tags are placed/removed as necessary.

Primary integrator = 40 gal, Boron = 0 gal.

Record PPC MAX (BOL = 99.8, MOL = 100.0, EOL = 100.2) on CC2 lamicoid The plant Abnormal Status Board is updated with last CCP CB near 40 and current date.

Circuit breaker flags are correct.

Equipment status lamicoids are correct:

B.A. XFER PP SUPPLYING BLENDER - BA Pp 1-2 SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - Cont. Rm. Vent Train 1 Bus F SELECTED TO BUS 1H - Cont. Rm. Vent Train 1 Bus H The proper Delta-I curve and Reactivity Handbook for the simulator INIT are in place The Rod Step Counters indicate correctly.

PPC Setup:

o QP TAVG, ALM/MODE-1, QP CHARGING, BIG U1169 o RBU is updated.

o PEN running.

o R2B blowdown flows at 90 gpm.

o Reactor trip status correct 9(Pg 2 of Group display Mode-1).

o Operational mode correct for current conditions.10 o Delta-I target slope matches Delta-I curve (DeltaI menu Option 5, constants K0500-0503=100% power target DeltaI / 100)

SPDS (screens and time updating), A screen RM, B screen SPDS.

The chart recorders are operating properly, and advanced.

All typewriters are on, with adequate paper/ribbon/etc., and are in the ON LINE status.

The Annunciator Horn is on (BELL ON).

Sound Effects are on (SOUND ON).

The video and audio systems are SECURED.

Communications systems are turned on and functional.

9 If not correct, place PPC display in ovrd mode, and press add/omit key. Type point Y0006D and select F2 to restore processing. This should update the trip breaker status.

10 Allow about ten minutes for the PPC to automatically update the plant mode. If still not correct, place PPC display in ovrd mode, and type APMC.

Follow menu to manually override to correct mode.

Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1

1.6.5.3.1.2 TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION X = manual entry required X 0 min DRILL 6607 After SRO reports the crew has taken the watch, load session MALS, OVRs, etc. by DRILL FILE or MANUALLY (below) 0 min mal pp15a act,3,0,0,d,0 ATWS (13D & E Available) mal pp15b act,3,0,0,d,0 0 min ovr xv5i245o act,0,0,0,d,0 52-hd-13 fdr for bus 13d fails to open 0 min vlv afw7 1,0,0,0,d,xv3i219 tdafwp fcv-95 won't open automatically, clears when c/s taken to open 3 min mal cvc8 act 100,120,180,d,0 SEAL INJECTION FILTER 11 PLUGGED X When Report Seal Injection Filter 11 dP is pegged high.

requested X Aux Bldg loa cvc3 act,1,30,0,d,0 valve in seal injection filter 12 watch X Aux Bldg loa cvc2 act,0,30,0,d,0 valve out seal injection filter 11 watch X When desired CALL AS TOC Require Ramp to 800 Mw Net. Start ramp within 5 minutes, request 25 MW/min ramp rate.

At 1000 MW xmt rcs93 Loop 3 NR Tcold fails high 3,679,30,0,c,smss.lt.1000 X When Report Rack 13 has trouble LED.

requested 12 min after mal eps4c act 2,0,720, 4KV bus F diff trip Tcold failure c,txmt410b(3).gt.675 X When Report burnt insulation smell from 4KV bus F room.

requested X When loa eps1 act,1,0,0,d,0 transfers DRPI to backup reqested X When Drill 46 swap batt 11 -> chrg 121 requested 10 min after mal mfw2a act 25,5,10, both MFW pp's trip bus differential mal mfw2b act 25,5,10, X When mal pp15a clr Locally opens Train A & B RTBs requested mal pp15b clr Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1

DIABLO CANYON POWER PLANT OPERATIONS SHIFT LOG UNIT 1 OPERATING MODE: 1 POWER LEVEL: 100  %

GROSS GENERATION: 1198 MWe NET GENERATION 1155 MWe DAYS AT POWER: 120 1.6.6 Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: YELLOW - RHR PP 1-1 MOW PROTECTED EQUIPMENT: Train B, Buses H & G, Prot. Sets II,III,IV HOMELAND SECURITY THREAT LEVEL: YELLOW GRID STATUS NEXT SHIFT: Midway #3 line cleared AVERAGE RCS CALCULATED LEAKRATE: 0.05 gpm URGENT WORK:

• None ACTIVE SHUTDOWN TECH SPECS / ECGS:

• RHR PP 1-1 -pump seal repair. T.S 3.5.2.A - 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Due in 62 hours7.175926e-4 days <br />0.0172 hours <br />1.025132e-4 weeks <br />2.3591e-5 months <br />.

TURNOVER ITEMS:

• RHR PP 1-1 was cleared 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> ago to repair a pump seal. It is expected to be returned to service in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

OPERABILITY ITEMS:

• None PRIORITY ITEMS FOR NEXT SHIFT:

• RHR PP 1-1 pump seal repairs.

ANNUNCIATORS IN ALARM

• None 1.6.6.1.1 Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1

1.6.6.1.2 SHIFT FOREMAN TURNOVER COMMENTS:

13. Reactivity management:

a. Time in core life: MOL

b. Power History: 100%

c. Boron concentration is 782 ppm from a sample taken 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.

d. Diluting 40 gallons every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

e. Last dilution was 30 minutes ago

f. I is stable

14. No one is in Containment, no entries are expected

15. U-2 is operating at 100% power COMPENSATORY MEASURES:

None 1.6.6.2 CONTROL ROOM ABNORMAL STATUS See Abnormal Status Board.

Scenario 05 DC-2008-06-FINAL OPERATING TEST.DOC Rev. 1