Text

DC-2010-01-FINAL Operating Test
	ML102300236
Person / Time
Site:	Diablo Canyon
Issue date:	01/11/2010
From:	Apger G; NRC Region 4
To:	;
References
	50-275/10-301, 50-323/10-301, DC-2010-01
	Download: ML102300236 (163)
	v • d • e

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJA_ROA1

Title:

DETERMINE DILUTION REQUIREMENTS FOR A POWER INCREASE Examinee:

Evaluator:

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

References:

DCPP Unit 1 Cycle 16 Reactivity Briefing Sheet (9000 MWD/MTU)

Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 Minutes Critical Steps: 2-6 Job Designation: RO Task Number: G2.1.25 Rating: 3.9 JOHN P. LYLEED HURST AUTHOR: GARY HUTCHISON DATE: 12/10/09 REV. 1

JPM TITLE: DETERMINE DILUTION REQUIREMENTS JPM NUMBER:

FOR A POWER INCREASE NRCL081LJA_ROA1 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 procedure and told the step with which to begin.

Required Materials: Calculator, Reactivity Briefing Sheet Initial Conditions: Unit 1 was ramped down due to problems with Govenor valve 4. Unit 1 has been at 90% power for 3 days with Control Bank D at 200 steps.

Initiating Cue: Shift Foreman directs you to determine the dilution or boration requirements to increase power to 95% assuming final rod position of 210 steps using the data from the Reactivity Briefing Sheet.

Task Standard: Operator determines that 230 (+/- 5 ) gallons of primary water is required.

NRCL081LJA_ROA1 PAGE 2 OF 6 REV. 1 rev 1.doc

JPM TITLE: DETERMINE DILUTION REQUIREMENTS JPM NUMBER:

FOR A POWER INCREASE NRCL081LJA_ROA1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions Operator obtains Reactivity Briefing

1. Operator obtains correct procedure Sheet.

Note: Provide exam copy of Reactivity Briefing Sheet 1.1 Step was: Sat: _______ Unsat _______*

Operator determines that power

2. ** Calculates reactivity from change in coefficient is -12.57 pcm/% power. **

power 2.2 Operator determines PCM for 5%

2.1 increase in power. (-62.85 pcm) **

Step was: Sat: _______ Unsat _______*

Operator determines PCM for Control

3. **Calculates reactivity from change in Bank D at 210 steps. (28 pcm) **

rod position 3.2 Operator determines PCM for Control 3.1 Bank D at 200 steps. (59.8 pcm) **

3.3 Operator determines PCM for change in rod position. (PCM at 200 - PCM at 220 steps = 31.8 pcm ) **

Step was: Sat: _______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

NRCL081LJA_ROA1 PAGE 3 OF 6 REV. 1 rev 1.doc

JPM TITLE: DETERMINE DILUTION REQUIREMENTS JPM NUMBER:

FOR A POWER INCREASE NRCL081LJA_ROA1 INSTRUCTOR WORKSHEET Step Expected Operator Actions Accounts for reactivity from change

4. ** Calculates reactivity left after in rods position on total reactivity accounting change in rod position. from change in power. (-62.8 + 31.8 =

-31.05 pcm)**

4.1 Step was: Sat: _______ Unsat _______*

Determines that 2.47 % power change

5. **Determines % power change from is left to dilution water. (-31.05 pcm/

reactivity associated with dilution. -12.57 pcm/% power)**

5.1 Step was: Sat: _______ Unsat _______*

Determines that 230 (+/- 5 ) gallons

6. **Determines amount of primay water of primary water is required. (2.47%

to add.

93 gal/% = 230 gallons) **

6.1 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.

NRCL081LJA_ROA1 PAGE 4 OF 6 REV. 1 rev 1.doc

JPM TITLE: DETERMINE DILUTION REQUIREMENTS JPM NUMBER:

FOR A POWER INCREASE NRCL081LJA_ROA1 ANSWER KEY Initial Conditions: Unit 1 was ramped down due to problems with Govenor valve 4. Unit 1 has been at 90% power for 3 days with Control Bank D at 200 steps Initiating Cue: Shift Foreman directs you to determine the dilution or boration requirements to increase power to 95% assuming final rod position of 210 steps using the data from the Reactivity Briefing Sheet.

Answer Key Operator determines that 230 (+/- 5 ) gallons of primary water is required.

NRCL081LJA_ROA1 PAGE 5 OF 6 REV. 1 rev 1.doc

EXAMINEE CUE SHEET JPM NUMBER:

NRCL081LJA_ROA1 Initial Conditions: Unit 1 was ramped down due to problems with Govenor valve 4. Unit 1 has been at 90% power for 3 days with Control Bank D at 200 steps Initiating Cue: Shift Foreman directs you to determine the dilution or boration requirements to increase power to 95% assuming final rod position of 210 steps using the data from the Reactivity Briefing Sheet.

NRCL081LJA_ROA1 PAGE 6 OF 6 REV. 1 rev 1.doc

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJA-ROA2

Title:

ESTIMATE DECAY HEAT AND HEATUP RATE Examinee:

Evaluator:

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

Copy of Appendix B of OP AP SD-5 to be provided to the student for calculations. Attached to JPM

References:

OP AP SD-5, Loss of Residual Heat Removal, Rev. 9A Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 2, 3, 4 Job Designation: RO K/A Number: G 2.1.2 Rating: 4.1 AUTHOR: GARY HUTCHISON DATE: 12/14/09 REV.1

JPM TITLE: ESTIMATE DECAY HEAT AND HEATUP RATE JPM NUMBER:

NRCL081LJA-ROA2 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: Calculator, Copy of Appendix B of AP SD-5 to be provided to the student for calculations.

Initial Conditions: Unit 1 was shut down five days ago for a refueling outage.

Core is still loaded (has not been off-loaded)

RCS has been drained to half loop for S/G nozzle dam installation

Reactor Vessel level is being maintained at 108 in accordance with OP A-2:III

RHR pump 1-1 just tripped on overcurrent RHR pump 1-2 can NOT be started RCS temperature is 110°F NR RVRLIS level is 108 Initiating Cue: The Shift Foreman has directed you to determine the time to reach 200°F.

NRCL081LJA_ROA2 rev PAGE 2 OF 5 REV.1 1.doc

JPM TITLE: ESTIMATE DECAY HEAT AND HEATUP RATE JPM NUMBER:

NRCL081LJA-ROA2 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 Refers to Appendix B of OP AP SD-5 Note: May refer to SD-0 first.

Appendix B may be used in other than SD-5.

1.2 May refer to Foldout Page of OP AP SD-5.

Step was: Sat: ______ Unsat _______*

- 2. Calculate the predicted decay heat 2.1 From the Predicted Heat Load load. curve, determines predicted heat load to be 13 MW (-0.5, +0.5). **

2.2 Determines the fraction of previously used assemblies installed in core to be 1.0. **

Note: A fraction of 1.0 is used since the core has not been off-loaded 2.3 Calculates the estimated decay heat load to be 13 MW (-0.5, +0.5). **

Step was: Sat: ______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes Critical Step and Sub Steps.

NRCL081LJA_ROA2 rev PAGE 3 OF 5 REV. 1 1.doc

JPM TITLE: ESTIMATE DECAY HEAT AND HEATUP RATE JPM NUMBER:

NRCL081LJA-ROA2 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 3. Predict the heat up rate. 3.1 Uses 13 MW (-0.5, +0.5) from previous step.

3.2 Determines inventory factor to be 0.45 (based on 108 RCS level). **

3.3 Calculates the predicted heat up rate to be 5.85 (5.63 to 6.08) degrees per minute. **

Step was: Sat: ______ Unsat _______*

- 4. Calculate the estimated time to 4.1 Calculates current temperature reach 200°F. difference to be 90°F. **

4.2 Calculates the time to reach 200°F to be 15.4 (14.8 to 16.0) minutes. **

Step was: Sat: ______ Unsat _______*

5. Inform the Shift Foreman. 5.1 Informs the Shift Foreman.

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.

NRCL081LJA_ROA2 rev PAGE 4 OF 5 REV. 1 1.doc

JPM NUMBER:

NRCL081LJA-ROA2 EXAMINEE CUE SHEET Initial Conditions: Unit 1 was shut down five days ago for a refueling outage.

Core is still loaded (has not been off-loaded)

RCS has been drained to half loop for S/G nozzle dam installation

Reactor Vessel level is being maintained at 108 in accordance with OP A-2:III

RHR pump 1-1 just tripped on overcurrent RHR pump 1-2 can NOT be started RCS temperature is 110°F NR RVRLIS level is 108 Initiating Cue: The Shift Foreman has directed you to determine the time to reach 200°F.

NRCL081LJA_ROA2 rev PAGE 5 OF 5 REV. 1 1.doc

Loss of Residual Heat Removal U1&2 OP AP SD-5 REV. 9A PAGE 5 OF 6 APPENDIX B Estimation of Decay Heat and Heatup RateT31417, T31098

1. PREDICTED HEAT LOAD

1. REDUCTION FACTOR FOR REFUELED CORES MW X = MW Predicted Fraction of Previously Estimated Heat Load Used Assemblies Decay Heat Installed in Core

Load

Use 1.0 if unknown 02 opapsd5.DOC 1022.1402 Page 5 of 7

Loss of Residual Heat Removal U1&2 OP AP SD-5 REV. 9A PAGE 6 OF 6 APPENDIX B (Continued)

2. HEAT UP RATE PREDICTION MW X = Degrees per Minute Estimated Inventory Predicted Decay Heat Factor Heat Up Load Rate

a. INVENTORY FACTOR - Degrees/MW Min 107' 0.52 108' 0.45 Nozzle Dams Installed OR NO Nozzle Dams Installed AND SG Tubes Voided SG Tubes Not Voided 110' 0.40 112' 0.36 0.29 114' 0.33 0.27 116' 0.31 0.26 118' 0.31 0.054 Upper Internals Removed (Use 118' if Upper Internals Installed) 120' 0.06 130' 0.03 138' 0.02

3. ESTIMATED TIME TO REACH 200 DEGREES 200 Delta Temp Existing

- Temperature ÷ Actual or =

Predicted Minutes to Delta Temp Heat Up Rate reach 200 02 opapsd5.DOC 1022.1402 Page 6 of 7

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJA-ROA3

Title:

REVIEW A TAGOUT FOR A CCP Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Clearance 1C16 D-08-002 is required to complete this JPM.

References:

Operator Valve Identification Diagram, 106708,Sheet 5 Rev. 131 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 2 Job Designation: RO/SRO K/A Number: G 2.2.13 Knowledge of tagging and clearance procedures K/A Rating 4.1 / 4.3 AUTHOR: GARY HUTCHISON/ JEFF KOCAN DATE: 12/2/2009 REV.1

JPM TITLE: REVIEW A TAGOUT FOR A CCP JPM NUMBER: NRCL081LJA-ROA3 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. 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: Clearance 1C16 D-08-002 and OVID 106708 sheet 5 Initial Conditions: Unit 1 is 100% power, steady state.

Initiating Cue: Perform a review of all clearance points on Clearance 1C16 D-08-002, Uncouple for rotation check, for technical errors.

Task Standard: Find and correct the two technical clearance errors within the clearance points.

NRCL081LJA_ROA3 PAGE 2 OF 6 REV. 1 rev 1.doc

JPM TITLE: REVIEW A TAGOUT FOR A CCP JPM NUMBER: NRCL081LJA-ROA3 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct reference material. Cue: Provide Operator with clearance sheet.

1.1 Operator selects Operator Valve Identification Diagram (OVID).

1.2 Selects Section 106708, Sheet 8.

Note: Operator may obtain valve and breaker number using optional reference material.

Note: Clearance Legend TAGS:

DANGER (D)

CAUTION (C)

CONTROL BOARD CAUTION (CBC)

POSITIONS:

RACKED OUT (RO)

RACKED IN (RI)

CLOSED (CL)

OPEN (OP)

Step was: Sat: _______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

NRCL081LJA_ROA3 PAGE 3 OF 6 REV. 1 rev 1.doc

JPM TITLE: REVIEW A TAGOUT FOR A CCP JPM NUMBER: NRCL081LJA-ROA3 INSTRUCTOR WORKSHEET Step Expected Operator Actions Operator determines point #2 tag

2. **Identify Centrifugual Charging should be a Danger tag. **

Pump 1-1 clearance errors.

2.2 Determines point #5 CVCS-1-8477B 2.1 is for CCP 1-2, not CCP 1-1 . **

2.3 May identify clearance doesnt close the CCP 1-1 suction valve, but this is not required for rotation check.

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.

NRCL081LJA_ROA3 PAGE 4 OF 6 REV. 1 rev 1.doc

JPM TITLE: REVIEW A TAGOUT FOR A CCP JPM NUMBER:

NRCL081LJA-ROA3 ANSWER SHEET Initial Conditions: Unit 1 is 100% power, steady state.

Initiating Cue: Perform a review of all clearance points on Clearance 1C16 D-08-002, Uncouple for rotation check, for technical errors.

Task Standard: Find and correct the two technical clearance errors within the clearance points.

Technical Errors point 0002 should be a Danger Tag point 0005 is for CCP 12 not pump 11 May suggest Charging pp suction valve (8394A) should be added to clearance but this point is not required for a rotation check.

NRCL081LJA_ROA3 PAGE 5 OF 6 REV. 1 rev 1.doc

JPM TITLE: JPM NUMBER:

NRCL081LJA-ROA3 EXAMINEE CUE SHEET Initial Conditions: Unit 1 is 100% power, steady state.

Initiating Cue: Perform a review of all clearance points on Clearance 1C16 D-08-002, Uncouple for rotation check, for technical errors.

Answer NRCL081LJA_ROA3 PAGE 6 OF 6 REV. 1 rev 1.doc

Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL081LJA-ROA4

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. 10 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 3.3 Job Designation: RO/SRO K/A: G 2.3.4; Knowledge of radiation exposure limits under normal or emergency conditions.

Rating: 3.2 / 3.7 AUTHOR: SEAN CURRIE/GARY HUTCHISON DATE: 12/2/2009 REV. 1

JPM

Title:

Stay Time Determination JPM Number: r: NRCL081LJA-ROA4 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. 10 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 300 mrem/hr. Your current year exposure history, according to your NRC Form 4 is as follows:

Committed Dose Equivalent (CDE) 15 mrem

Committed Effective Dose Equivalent (CEDE) 250 mrem

Deep Dose Equivalent (DDE) 450 mrem

Eye Dose Equivalent (LDE) 15 mrem

Shallow Dose Equivalent (SDE) 10 mrem

Effective Dose Equivalent (EDE) 450 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.

Denotes an entry required on the JPM cover sheet

- Denotes a Critical Step NRCL081LJA_ROA4 Rev 1.doc Page 2 of 5 REV. 1

JPM

Title:

Stay Time Determination JPM Number: NRCL081LJA-ROA4 Instructor Worksheet Start Time:

Step Expected Operator Actions

1. Determine TEDE 1.1 TEDE = DDE + CEDE 1.2 TEDE = 450 mrem + 250 mrem 1.3 TEDE = 700 mrem Step was: Sat: ______ Unsat _______*

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

2000 - 700 = 1300 mrem Step was: Sat: ______ Unsat _______*

3. Determine maximum stay time ** 3.1 Stay time = Margin / Dose Rate 3.2 Stay time = 1300 mrem / 300 mrem/hr

- 3.3 Stay time = 4.33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months ACCEPTABLE TIME: 4.1 - 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Step was: Sat: ______ Unsat _______*

Stop Time:

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

NRCL081LJA_ROA4 Rev 1.doc Page 3 of 5 REV. 1

JPM

Title:

Stay Time Determination JPM Number: NRCL081LJA-ROA4 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 300 mrem/hr. Your current year exposure history, according to your NRC Form 4 is as follows:

Committed Dose Equivalent (CDE) 15 mrem

Committed Effective Dose Equivalent (CEDE) 250 mrem

Deep Dose Equivalent (DDE) 450 mrem

Eye Dose Equivalent (LDE) 15 mrem

Shallow Dose Equivalent (SDE) 10 mrem

Effective Dose Equivalent (EDE) 450 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 TEDE = DDE + CEDE TEDE = 450 mrem + 250 mrem TEDE = 700 mrem Margin = 2000 - 700 = 1300 mrem Stay time = Margin / Dose Rate 1300 mrem / 300 mrem/hr Stay time = 4.33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months NRCL081LJA_ROA4 Rev 1.doc Page 4 of 5 REV. 1

JPM Number: NRCL081LJA-ROA4 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 300 mrem/hr. Your current year exposure history, according to your NRC Form 4 is as follows:

Committed Dose Equivalent (CDE) 15 mrem

Committed Effective Dose Equivalent (CEDE) 250 mrem

Deep Dose Equivalent (DDE) 450 mrem

Eye Dose Equivalent (LDE) 15 mrem

Shallow Dose Equivalent (SDE) 10 mrem

Effective Dose Equivalent (EDE) 450 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 NRCL081LJA_ROA4 Rev 1.doc Page 5 of 5 REV. 1

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJA_SROA1

Title:

DETERMINE SHIFT STAFFING DURING REFUELING OPERATIONS Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Provide copy of OP1.DC37

References:

OP1.DC37 "Plant Logs." Rev. 40 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 Minutes Critical Steps: 2 Job Designation: SRO K/A Number: G 2.1.5 Rating: 3.9 JOHN P. LYLEED HURST AUTHOR: GARY HUTCHISON DATE: 12/2/09 REV.1

JPM TITLE: DETERMINE SHIFT STAFFING DURING JPM NUMBER:

REFUELING OPERATIONS NRCL081LJA_SROA1 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 procedure and told the step with which to begin.

Required Materials: Shift Watch List for this JPM, OP1.DC37 Initial Conditions: Unit 1 is operating at 100% power, Unit 2 is 10 days into a refueling outage in mode 6.

Initiating Cue: Review the Shift Watch List for dayshift.

Task Standard: Operator determines U1 Work Control Lead can not be TS/Eplan and Ops Responder (OR).

Operator determines that watch list doesnt have four management licenses designated.

NRCL081LJA_SROA1 PAGE 2 OF 8 REV. 1 rev 1.doc

JPM TITLE: DETERMINE SHIFT STAFFING DURING JPM NUMBER:

REFUELING OPERATIONS NRCL081LJA_SROA1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions Operator reviews shift logs for

1. Operator reviews shift watch list completeness and accuracy.

1.1 Step was: Sat: _______ Unsat _______*

Determines that U1 Work Control

2. ** Determines errors with staffing Lead can not be TS/Eplan and Ops Responder (OR).**

2.1 2.2 Determines that watch list doesnt have four management licenses designated. **

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.

NRCL081LJA_SROA1 PAGE 3 OF 8 REV. 1 rev 1.doc

JPM TITLE: DETERMINE SHIFT STAFFING DURING JPM NUMBER:

REFUELING OPERATIONS NRCL081LJA_SROA1 ANSWER KEY Initial Conditions: Unit 1 is operating at 100% power, Unit 2 is 10 days into a refueling outage in mode 6.

Initiating Cue: Review the Shift Watch List for dayshift Answer Key

Operator determines U1 Work Control Lead can not be TS/Eplan and Ops Responder (OR).

Operator determines that watch list doesnt have four management licenses designated.

NRCL081LJA_SROA1 PAGE 4 OF 8 REV. 1 rev 1.doc

EXAMINEE CUE SHEET JPM NUMBER:

NRCL081LJA_SROA1 Initial Conditions: Unit 1 is operating at 100% power, Unit 2 is 10 days into a refueling outage in mode 6.

Initiating Cue: Review the Shift Watch List for dayshift NRCL081LJA_SROA1 PAGE 5 OF 8 REV. 1 rev 1.doc

JPM TITLE: DETERMINE SHIFT STAFFING DURING JPM NUMBER: NRCL081LJA_SROA1 REFUELING OPERATIONS STUDENT HANDOUT Hand the following two pages to examinee NRCL081LJA_SROA1 PAGE 6 OF 8 REV. 1 rev 1.doc

69-20533 Attachment 7.1 Shift Watch List Position Name EPlan R OR FBM STA Comm #2 Shift Manager WERNER, ERIK X X X Work Control Shift Foreman KENNEDY, MICHAEL X X SFM Extra (Optional) BEALS, DAVID X SFM Extra (Optional) MERTOGUL, REMZI X Shift Engineer U1 Shift Foreman MEHIGAN, CHRISTOPHE X X U1 SCO Control Room Assistant U1 Work Control Lead KATZ, RAYMOND X X X U1 Balance of Plant CO HACKLEMAN, JOHN X X U2 SCO U1 CO RACETTE, GARRY X X U1 Turbine Building PERRY, DANIEL X X Additional CO U1 Aux Building SPARKS, BRYAN X X U1 Polisher LEE, MICHAEL X X Intake and Outside KONDO, MARK X U2 Shift Foreman HURST, CLAYTON X U2 Work Control Lead JANES JR, RICHARD X X (Optional)

Auxiliary Senior U2 Balance of Plant CO TRYGG, JACK X X X U2 CO MOYER, JAMES X X U2 Turbine Building ANNONI, GRANT X X U2 Aux Building ANTHONY, DAVID X X U2 Polisher KNIGHT, JAMES NRCL081LJA_SROA1 PAGE 7 OF 8 REV. 1 rev 1.doc

69-20533 Attachment 7.1 Work Control Extra License MARTIN, TIMOTHY Shift Control Tech 1 - Days HART, DANIEL X Shift Control Tech 2 Days PELYPEC, MICHAEL X Shift Control Tech 1 Swings CIMBUR, NIKOLA X Shift Control Tech 2 Swings EVENSON, DONNA X Shift Control Tech 1 Mids Shift Control Tech 2 Mids RP Tech Days GOETTIG, JEFFRY X RP Tech Swings FIELDING, RICKY X RP Tech Mids FIELDING, RICKY X Chem Tech Days SHELDON, KEITH X Chem Tech Swings LIBBY, DENNIS X Chem Tech Mids LIBBY, DENNIS X Additional Personnel KISER, JACK X Additional Personnel SILVA, STEPHEN X Additional Personnel VOGEL, JAY X Additional Personnel SMITH, JARED X Additional Personnel HALL, TODD X Additional Personnel BEERFELDT, STEVEN X Additional Personnel STEFFENS, TYLER X Additional Personnel BARE, CHRISTINE X Additional Personnel HURLBURT JR, JOHN X NRCL081LJA_SROA1 PAGE 8 OF 8 REV. 1 rev 1.doc

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJA_SROA2

Title:

REVIEW OPERATOR LOGS Examinee:

Evaluator:

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

References:

Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 Minutes Critical Steps:

Job Designation: SRO Task Number: G2.1.3 Rating: 3.9 JOHN P. LYLEED HURST AUTHOR: GARY HUTCHISON DATE: 12/14/09 REV. 1

JPM TITLE: REVIEW OPERATOR LOGS JPM NUMBER:

NRCL081LJA_SROA2 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 procedure and told the step with which to begin.

Required Materials: Operator Log Sheet for this JPM Initial Conditions: Unit 1 is operating at 100% power, with a overcurrent trip on 52-1G-46 for 8000B.

Initiating Cue: Review the shift logs.

Task Standard: Operator determines that Pressurizer PORV PCV-456 was taken to close

> 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from loss of Bus.

NRCL081LJA_SROA2 PAGE 2 OF 7 REV. 1 rev 1.doc

JPM TITLE: REVIEW OPERATOR LOGS JPM NUMBER:

NRCL081LJA_SROA2 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions Operator reviews shift logs for

1. Operator reviews shift logs completeness and accuracy.

1.1 Step was: Sat: _______ Unsat _______*

Determines that PCV-455C was not

2. ** Determines time PORV taken to taken to close within one hour of close greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months block valve 8000B being inoperable as required in TS 3.4.11.C.1. **

2.1 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.

NRCL081LJA_SROA2 PAGE 3 OF 7 REV. 1 rev 1.doc

EXAMINEE CUE SHEET JPM NUMBER:

NRCL081LJA_SROA2 Initial Conditions: Unit 1 is operating at 100% power, with a overcurrent trip on 52-1G-46 for 8000B.

Initiating Cue: Review the shift logs.

NRCL081LJA_SROA2 PAGE 4 OF 7 REV. 1 rev 1.doc

JPM TITLE: REVIEW OPERATOR LOGS JPM NUMBER: NRCL081LJA_SROA2 STUDENT HANDOUT Hand the following two pages to examinee NRCL081LJA_SROA2 PAGE 5 OF 7 REV. 1 rev 1.doc

69-20533 10/03/2006 Attachment 7.1 Diablo Canyon Power Plant Operations Shift Log Unit 1 Today - Dayshift NPG has gone 193 days without a plant event.

NPG has operated 18 days without a critical equipment event.

Unit 1 Days at Power: 10 Days Operating Mode: 1 Gross Generation: 1178 MWe Power Level: 100% Net Generation: 1128 MWe Shift Manager Turnover PRA NEXT SHIFT: GREEN GRID STATUS NEXT SHIFT: NORMAL AVERAGE RCS CALCULATED LEAKRATE: 0.01 GPM CONDENSER INLEAKAGE: 0.0 GPD MAIN GENERATOR H2 USAGE: Daily = 369 SCF / 5 day average = 428 SCFD NEW EMERGENT WORK

52-1G-46 (8000B) overcurrent trip SHUTDOWN TECH SPECS / ECGS

TS 3.4.11 for 8000B TURNOVER ITEMS

Generate clearance for 52-1G-46

69-20533 10/03/2006 Attachment 7.1 Log Entries Time Entry User User Type 7:09 Power Range NIs 100.2 Calorimetric Power 99.6 Generator MW 1177.6 Bank GLH1 CO D @ 231 Boron Conc. 1262 ppm. from sample taken on: Today at 0145 hrs. Ave. Delta I -2.9 Target Delta I -2.8 Gov.Vlv. 4 Pos. 24.5 N. Cond.

Press. 1.96 S. Cond. Press. 2.08 Contmt. Press. +0.097 Boric Acid Integrator 116449 Primary Water Integrator 681744 DILUTING 10 gallons approx every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; RUNNING EQUIPMENT: ASW pp 1-1; CCW pps 1-1 & 1-2; CFCU's 1-1, 1-2, & 1-3 In HIGH; CCP 1-3 with 78 gpm letdown in service 8149B; BA transfer pp 1-1 aligned to blender; Primary water pp 1-2; Letdown filter 1-1; Seal injection filter 1-1 and Mixed bed demin 1-2 all in service; Makeup water transfer pp 02; Cond / Booster pp sets 1-1 &

1-3; Circ water pp 1-2 aligned for Auto Reclose and SCW h/x supply; Stator Top Delta T at 9.4 degrees, Bottom Delta T at 8.0 degrees, flow @ 825.8 gpm; Condenser Delta P's: NW @ 7.0 psid, NE @ 7.4 psid, SW @ 7.2 psid, SE @ 7.5 psid 7:59 Diluted RCS with 10 gallons of primary water. 10 gallons total this shift GLH1 CO 8:24 Authorized Discharge of LDT 0-1 Per Discharge Permit 2009-0-109 RNF5 USFM 8:48 Reviewed STP I-1A (Shift Checklist), satisfactory. Gross sump leakage = .0184 RNF5 USFM gpm 9:36 Commenced Discharge of LDT 0-1 @ 83%. Batch # 2009-0-109. SCARP BCS1 AUXSR Sheldon informed 11:15 Chemistry Technician B. Leasburg reports U1 RCS Boron Conc. = 1260 ppm., bcl6 CHEM SCARP Sample taken @ 0845 hours0.00978 days 0.235 hours 0.0014 weeks 3.215225e-4 months . A 30 minute Cation Bed run is not requested 11:36 Diluted RCS with 10 gallons of primary water. 20 gallons total this shift GLH1 CO 12:16 Secured Discharge of LDT 0-1 @ 10%. Batch # 200-0-109 BCS1 AUXSR 15:53 Diluted RCS with 10 gallons of primary water. 30 gallons total this shift GLH1 CO 17:00 Overcurrent trip on 52-1G-46 breaker for 8000B. GLH1 CO 17:00 Entered TS 3.4.11 for inoperable PORV block valve. RNF5 USFM 17:05 Turbine Building watch reports breaker 52-1G-46 in tripped position and has RNF5 USFM burnt insulation smell at breaker.

17:07 52-1G-46 in tripped position and has burnt insulation smell. JMB1 TURB 17:09 Contacted maintenance to investigate breaker 52-1G-46. RNF5 USFM 18:05 PCV-455C switch placed to closed position GLH1 CO 18:17 Electrical Maintenance reports that 52-1G-46 has indications of shorted wiring. RNF5 USFM 18:53 Diluted RCS with 10 gallons of primary water. 40 gallons total this shift GLH1 CO Page 2

Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL081LJA-SROA5

Title:

Classify a Loss of Shutdown Cooling Event Examinee:

Evaluator:

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

References:

DCPP Emergency Action Level Matrix & Background Document EVENT Number 43360 May 12, 2007 Alternate Path: Yes No X Time Critical: Yes X No Time Allotment: 15 minutes Critical Steps: 2.1 Job Designation: SRO K/A: G 2.4.41; Knowledge of the emergency action level thresholds and classifications.

Rating: 4.6 AUTHOR: SEAN CURRIE/GARY HUTCHISON DATE: 12/14/09 REV. 1

JPM

Title:

Classify a Loss of Shutdown JPM Number: r: NRCL081LJA-SROA5 Cooling Event 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: DCPP Emergency Action Level Matrix & Background Document Initial Conditions: Unit 1 is cooling down and just entered Mode 5 in preparation for a refueling outage with the following conditions:

Auxiliary Power is cleared for maintenance.

Emergency Diesel Generator EDG 1-1 cleared for maintenance.

Offsite power is being supplied by startup power.

At 1200 hrs, Morro-Bay-Diablo transmission line fails resulting in a loss of startup power.

Emergency Diesel Generator EDG 1-3 generator output breaker trips on over-current.

Emergency Diesel Generator EDG 1-2 starts but trips on over-speed, interrupting RCS heat removal.

At 1220, EDG 1-2 over-speed is reset and plant cooldown is re-established.

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 are reported to the Shift Manager.

NRCL081LJA_SROA5.doc Page 2 of 5 REV. 1

JPM

Title:

Classify a Loss of Shutdown JPM Number: NRCL081LJA-SROA5 Cooling Event 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. Determine DCPP emergency ** 2.1 Determines that the Cold SD/Refuel Action Level System Malfunction/Loss of Power C.1 is an ALERT (CA1.1)

Step was: Sat: ______ Unsat _______*

3. Report Event Classification. 3.1 Reports to Shift Manager an initial classification of ALERT.

ACCEPTABLE TIME: 15 minutes 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 NRCL081LJA_SROA5.doc Page 3 of 5 REV. 1

JPM

Title:

Classify a Loss of Shutdown JPM Number: NRCL081LJA-SROA5 Cooling Event Answer Key Initial Conditions: Unit 1 is cooling down and just entered Mode 5 in preparation for a refueling outage with the following conditions:

Auxiliary Power is cleared for maintenance.

Emergency Diesel Generator EDG 1-1 cleared for maintenance.

Offsite power is being supplied by startup power.

At 1200 hrs, Morro-Bay-Diablo transmission line fails resulting in a loss of startup power.

Emergency Diesel Generator EDG 1-3 generator output breaker trips on over-current.

Emergency Diesel Generator EDG 1-2 starts but trips on over-speed, interrupting RCS heat removal.

At 1220, EDG 1-2 over-speed is reset and plant cooldown is re-established.

Initiating Cue: Determine the proper event classification and report results to the Shift Manager.

Document Your Answer Here Cold SD/Refuel System Malfunction/Loss of Power C.1 is an ALERT (CA1.1) due to Loss of ALL offsite and Onsite Power to Vital Buses F,G, and H for > 15 min.

EVENT CLASSIFICATION IS: ALERT (CA1.1)

NRCL081LJA_SROA5.doc Page 4 of 5 REV. 1

JPM Number: NRCL081LJA-SROA5 Examinee Cue Sheet Initial Conditions: Unit 1 is cooling down and just entered Mode 5 in preparation for a refueling outage with the following conditions:

Auxiliary Power is cleared for maintenance.

Emergency Diesel Generator EDG 1-1 cleared for maintenance.

Offsite power is being supplied by startup power.

At 1200 hrs, Morro-Bay-Diablo transmission line fails resulting in a loss of startup power.

Emergency Diesel Generator EDG 1-3 generator output breaker trips on over-current.

Emergency Diesel Generator EDG 1-2 starts but trips on over-speed, interrupting RCS heat removal.

At 1220, EDG 1-2 over-speed is reset and plant cooldown is re-established.

Initiating Cue: Determine the proper event classification and report results to the Shift Manager.

Document Your Answer Here NRCL081LJA_SROA5.doc Page 5 of 5 REV. 1

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJC-C1

Title:

INITIATE CONTAINMENT SPRAY MANUALLY Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: This JPM is to be simulated in the Unit 2 Control Room.

References:

U2 EOP FR-Z.1, Response to High Containment Pressure, Rev. 7 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 3, 4 Job Designation: RO/SRO Task Number: KA 026A4.01 Rating: 4.5/4.3 AUTHOR: GARY HUTCHISON DATE: 12/3/2009 REV. 2

JPM TITLE: INITIATE CONTAINMENT SPRAY MANUALLY JPM NUMBER:

NRCL081LJC-C1 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 2 experienced a LOCA. EOP E-1 is in progress and Safety Injection is reset.

Initiating Cue: Containment pressure is 25 psig. The EEC confirms a MAGENTA path on the Containment Critical Safety Function Status Tree. All higher priority critical safety functions have been addressed. The Shift Foreman directs you to manually initiate containment spray in accordance with EOP FR-Z.1. Components indications are as seen unless otherwise noted.

Task Standard: Containment spray is initiated and aligned for injection phase.

NRCL081LJC-C1 rev PAGE 2 OF 6 REV. 2 2.doc

JPM TITLE: INITIATE CONTAINMENT SPRAY MANUALLY JPM NUMBER:

NRCL081LJC-C1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References EOP FR Z.1.

Cue: Start with Step 3.

Step was: Sat: ______ Unsat _______*

2. Check if containment spray is 2.1 Checks if EOP ECA-1.1 is the required. procedure in effect.

Cue: EOP ECA-1.1 is not in effect.

2.2 Checks containment pressure greater than 22 psig.

Cue: Containment Pressure is 25 psig.

Step was: Sat: ______ Unsat _______*

- 3. Start the containment spray 3.1 Turns control switches to the pumps. START position for containment spray pumps 21 and 22. **

Cue: Containment spray pumps red lights ON, green lights OFF, stable amps.

Step was: Sat: ______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes Critical Step and Sub Steps.

NRCL081LJC-C1 rev PAGE 3 OF 6 REV. 2 2.doc

JPM TITLE: INITIATE CONTAINMENT SPRAY MANUALLY JPM NUMBER:

NRCL081LJC-C1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 4. Checks containment spray system 4.1 Determines that ECCS is aligned for for proper valve alignment. injection flow.

4.2 Takes control switch for 9001A and B to OPEN position. **

Cue: 9001A & B red lights ON, green lights OFF.

4.3 Verifies 8992 open.

4.4 Takes control switch for 8994A&B to the OPEN position**.

Cue: 8994A & B red lights ON, green lights OFF.

Step was: Sat: ______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes Critical Step and Sub Steps.

NRCL081LJC-C1 rev PAGE 4 OF 6 REV. 2 2.doc

JPM TITLE: INITIATE CONTAINMENT SPRAY MANUALLY JPM NUMBER:

NRCL081LJC-C1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

5. Checks Containment Isolation 5.1 Checks Phase B portion of monitor Phase B valves light Box D Red Activated light ON Cue: Phase B Red lights are ON 5.2 Checks Phase B portion of monitor light Box D White status lights OFF Cue: All Phase B white lights are OFF Cue: Another Operator will complete FR Z.1 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.

NRCL081LJC-C1 rev PAGE 5 OF 6 REV. 2 2.doc

JPM NUMBER:

NRCL081LJC-C1 EXAMINEE CUE SHEET Initial Conditions: Unit 2 experienced a LOCA. EOP E-1 is in progress and Safety Injection is reset.

Initiating Cue: Containment pressure is 25 psig. The EEC confirms a MAGENTA path on the Containment Critical Safety Function Status Tree. All higher priority critical safety functions have been addressed. The Shift Foreman directs you to manually initiate containment spray in accordance with EOP FR-Z.1. Components indications are as seen unless otherwise noted.

NRCL081LJC-C1 rev Page 6 of 6 REV. 2 2.doc

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJC-C2

Title:

REMOVE POWER RANGE CHANNEL N42 FROM SERVICE Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: This JPM is to be simulated in the Unit 2 Control Room.

References:

OP AP-5, Malfunction of Protection or Control Channel, Rev. 30 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 2, 3, 4, 5, 6 Job Designation: RO/SRO Task Number: 217400.015 Rating: 3.6 AUTHOR: GARY HUTCHISON DATE: 12/3/2009 REV. 1

JPM TITLE: REMOVE POWER RANGE CHANNEL N42 FROM JPM NUMBER:

SERVICE NRCL081LJC-C2 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 2 is at 100% power. A malfunction caused power range channel N42 to fail high. Rod control was placed in MANUAL after rods stepped in five (5) steps.

The Shift Foreman has requested the Maintenance to:

trip bistables BS421C and BS421D, and

remove the control power and instrument power fuses.

Initiating Cue: The Shift Foreman directs you to remove power range channel N42 from service, with the exception of pulling fuses, in accordance with OP AP-5, Attachment 4.1.

Task Standard: Power range channel N42 has been removed from service, with the exception of pulling fuses, in accordance with OP AP-5.

NRCL081LJC-C2 REV PAGE 2 OF 5 REV. 1 1.DOC

JPM TITLE: REMOVE POWER RANGE CHANNEL N42 FROM JPM NUMBER:

SERVICE NRCL081LJC-C2 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References OP AP-5, Attachment 4.1, Actions to be performed for NI failure.

Note: Operator may review STP I-2C1.

Step was: Sat: ______ Unsat _______*

- 2. Place rod stop bypass switch the **********************************

failed channel position. Cue: If the operator refers to the requirement to use concurrent verification, state that require-ment is waived for this JPM.

2.1 Places the ROD STOP BYBASS switch in the BYPASS PR N42 position. **

Cue: Switch in BYPASS PR N42 postion. If asked about alarm:

PK07-07, PWR RNG 42 ROD STOP BYPASSED -- ON.

Step was: Sat: ______ Unsat _______*

- 3. Place power mismatch bypass 3.1 Places the POWER MISMATCH switch to the failed channel BYPASS switch in the BYPASS position. PR N42 position. **

Cue: Switch in BYPASS PR N42 postion.

Step was: Sat: ______ Unsat _______*

NRCL081LJC-C2 REV PAGE 3 OF 5 REV. 1 1.DOC

JPM TITLE: REMOVE POWER RANGE CHANNEL N42 FROM JPM NUMBER:

SERVICE NRCL081LJC-C2 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 4. Place quadrant power tilt alarm 4.1 Places the QUADRANT POWER upper section switch to the failed TILT ALARM UPPER SECTION channel position. switch in the PRN42 position. **

Cue: Switch in PRN42 postion.

4.2 Verifies that the CHANNEL DEFEAT light has lit.

Step was: Sat: ______ Unsat _______*

- 5. Place quadrant power tilt alarm 5.1 Places the QUADRANT POWER lower section switch to the failed TILT ALARM LOWER SECTION channel position. switch in the PRN42 position. **

Cue: Switch in PRN42 postion.

5.2 Verifies that the CHANNEL DEFEAT light has lit.

Step was: Sat: ______ Unsat _______*

- 6. Place the comparator defeat switch 6.1 Places the COMPARATOR to the failed channel position. CHANNEL DEFEAT switch in the N42 position. **

Cue: Switch in N42 postion.

6.2 Verifies that the COMPARATOR DEFEAT light has lit.

Cue: Maintenance Services will remove the control power and instrument power fuses.

Step was: Sat: ______ Unsat _______*

Stop Time:

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

NRCL081LJC-C2 REV PAGE 4 OF 5 REV. 1 1.DOC

JPM NUMBER:

NRCL081LJC-C2 EXAMINEE CUE SHEET Initial Conditions: Unit 2 is at 100% power. A malfunction caused power range channel N42 to fail high. Rod control was placed in MANUAL after rods stepped in five (5) steps.

The Shift Foreman has requested the Maintenance to:

trip bistables BS421C and BS421D, and

remove the control power and instrument power fuses.

Initiating Cue: The Shift Foreman directs you to remove power range channel N42 from service, with the exception of pulling fuses, in accordance with OP AP-5, Attachment 4.1.

NRCL081LJC-C2 REV PAGE 5 OF 5 REV. 1 1.DOC

Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL081LJC-S1

Title:

MANUALLY FEED S/G USING FR-H1 Examinee:

Evaluator:

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

References:

FR-H1, Response to Loss of Secondary Heat Sink Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 1.1, 2, 3, 4.1-4.7 Job Designation: RO/SRO K/A: 059 A4.08 Rating: 3.0/2.9 AUTHOR: CHRIS STEELY/GARY HUTCHISON DATE: 12/2/2009 REV. 1

JPM

Title:

MANUALLY FEED S/G USING FR-H1 JPM Number:

NRCL081LJC-S1 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: FR-H1, Response to Loss of Secondary Heat Sink Initial Conditions: Unit 1 is tripped. RCS temperature is 570 F and RCS pressure is 2230 PSIG. Feed flow to all S/Gs has been lost.

Initiating Cue: The Shift Foreman directs you to manually restore feed flow to S/Gs in order to restore a heat sink per FR-H1 step 7.

Task Standard: DO NOT READ TO STUDENT: MFW pumps will be tripped at start of scenario, so a MFW pump must be started and discharge pressure increased enough to establish feedwater flow to at least one S/G (Alternate Path).

Denotes an entry required on the JPM cover sheet

- Denotes a Critical Step NRCL081LJC-S1 Rev 1.DOC Page 2 of 6 REV. 1

JPM

Title:

MANUALLY FEED S/G USING FR-H1 JPM Number:

NRCL081LJC-S1 Instructor Worksheet Start Time:

Step Expected Operator Actions

1. Check Condensate System - IN 1.1 Checks at least one Condensate/Booster SERVICE Pump set running in recirc on VB3.

Step was: Sat: ______ Unsat _______*

2. Manually set Zero demand on ALL 2.1 Set ZERO demand on Mn Fdwtr Cont &

MFW Control Valves AND MFW Bypass Vlvs controllers on CC3 touch Control Bypass Valve Controllers screens Step was: Sat: ______ Unsat _______*

3. Check MFW Isolation Valves - 3.1 Sees that MFW Isolation Valves are open OPEN (VB3)

Step was: Sat: ______ Unsat _______*

4 Establish MFW flow capability 4.1 Verify Condenser - Available by checking PK 08-14 C-9 annunciator on 4.2 Verify MSIVs - OPEN (VB3) 4.3 Verify manual isolation for HP steam to MFW pumps - OPEN (MS-1-95, MFW Pp 1-1 AND MS-1-92, MFW Pp 1-2)

Cue: MS-1-95 and MS-1-92 are OPEN.

NRCL081LJC-S1 Rev 1.DOC Page 3 of 6 REV. 1

JPM

Title:

MANUALLY FEED S/G USING FR-H1 JPM Number:

NRCL081LJC-S1 Instructor Worksheet Step Expected Operator Actions

5. Check ANY MFW Pump - 5.1 Determines that no MFW Pumps are latched LATCHED **

5.2 Determines FCV-53 AND FCV-54 switches in RECIRC on VB3

- 5.3 Press ALARM/TRIP RESET on MFW Pp S/U station (VB3).

- 5.4 Take Trip/Latch switch to RESET to latch the MFW Pp Turbine (Hold until latched, ~ 2 min).

- 5.5 Press RAMP UP TO IDLE, verify ramp to ~

600 RPM.

- 5.6 Press IDLE TO STANDBY, verify ramp to ~

3000 RPM.

Step was: Sat: ______ Unsat _______*

6. Increase MFW Pump speed ** 6.1 Presses Raise PB on MFW pp S/U station until discharge pressure is 100 or uses CC3 touch screen (may have to PSIG GREATER THAN S/G toggle the DFW Control PB on S/U station) pressure ** to increase MFW discharge pressure > S/G pressure **

7. Check PK09-11, FEEDWATER ** 7.1 Resets FW Isolation on VB3**

ISOLATION, finds alarm is active **

8. Throttle open - MFW Control ** 8.1 Uses CC2 touch screen to establish MFW Bypass Valves or MFW Control flow with either MFW control or Bypass Valves ** valves Step was: Sat: ______ Unsat _______*

Stop Time:

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

NRCL081LJC-S1 Rev 1.DOC Page 4 of 6 REV. 1

JPM Number: NRCL081LJC-S1 Examinee Cue Sheet Initial Conditions: Unit 1 is tripped. RCS temperature is 570 F and RCS pressure is 2230 PSIG. Feed flow to all S/Gs has been lost.

Initiating Cue: The Shift Foreman directs you to manually restore feed flow to S/Gs in order to restore a heat sink per FR-H1 step 7.

NRCL081LJC-S1 Rev 1.DOC Page 5 of 6 REV. 1

JPM

Title:

MANUALLY FEED S/G USING FR-H1 JPM Number:

NRCL081LJC-S1 Simulator Setup Initialize the simulator to the RELAP INIT 510 (100%, MOL).

If possible, a second instructor should be available during this JPM to control PZR pressure when required.

Enter drill file 6807 or manually insert the following:

Command Description

1. mal afw1 act,0,0,d,0 Trips AFW pp 1-1

2. pmp afw1 4,0,0,0,d,0 Trips AFW pp 1-2 from starting

3. pmp afw2 4,0,0,0,d,0 Trips AFW pp 1-3 from starting

4. ovr xrei022h act,1,0,0,c,fnispr.1t.10,5 Reset MSRS

5. delm bsgnwrr1 Removes bsgnwrr1 from monitor

6. monv bsgnwrr1 Monitors steam generator wide range level

7. run 120

8. mal pp14a act,0,0,0,d,2 Inadvertent Reactor Trip, Train A

9. mal pp14b act,0,0,0,d,2 Inadvertent Reactor Trip, Train B

10. ovr xv2i260o act,1,0,0,c,fnispr.1t.10,0 Trips RCP 11

11. ovr xv2i261o act,1,0,0,c,fnispr.1t.10,0 Trips RCP 12

12. ovr xv2i262o act,1,0,0,c,fnispr.1t.10,0 Trips RCP 13

13. ovr xv2i263o act,1,0,0,c,fnispr.1t.10,0 Trips RCP 14 Perform the following:

1. Place FCV-53/54 in RECIRC.

2. Place Steam Dump Control in Steam Pressure Mode.

3. Place LCV-12 in CONT ONLY.

4. Stop all but one Condensate/Booster Pump sets.

5. Trip both MFW pumps Inform the examiner that the simulator setup is complete.

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

NRCL081LJC-S1 Rev 1.DOC Page 6 of 6 REV. 1

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJC-S2

Title:

ESTABLISH EMERGENCY BORATION Examinee:

Evaluator:

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

References:

OP AP-6, Emergency Boration, Rev. 19 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 4 Job Designation: RO/SRO Task Number: KA 004A2.14 Rating: 3.8 / 3.9 AUTHOR: GARY HUTCHISON DATE: 08/25/09 REV. 0

JPM TITLE: ESTABLISH EMERGENCY BORATION JPM NUMBER:

NRCL081LJC-S2 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 shutdown in MODE 3 and an unexplained increase in reactivity is causing source range counts to increase.

Initiating Cue: The Shift Foreman directs you to emergency borate.

Task Standard: Emergency boration has been established.

NRCL081LJC-S2.DOC PAGE 2 OF 7 REV. 0

JPM TITLE: ESTABLISH EMERGENCY BORATION JPM NUMBER:

NRCL081LJC-S2 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References OP AP-6.

1.2 Reads NOTES prior to Step 1.

Note: This is an alternate path JPM.

Emergency boration will be accomplished via the RWST due to FCV-110B and CVCS-8104 failing closed.

Step was: Sat: ______ Unsat _______*

2. Initiate emergency boration using 2.1 Verifies charging in service.

make-up controls.

2.2 Places VCT makeup control in the BORATE mode.

2.3 Determines amount of boric acid required per Appendix A.

2.4 Sets TARGET BATCH.

Note: Appendix A guidance is to borate until control is regained.

Cue: The SFM is referring to EOP FR-S.1, Appendix D, to isolate dilution flow paths and directs you to continue emergency boration.

2.5 Resets the BATCHED GALLONS indicator to ZERO 2.6 Set BORIC ACID FLOW SP > 30 GPM.

Step continued on next page

Denotes an entry required on the JPM cover sheet.

- Denotes Critical Step and Sub Steps.

NRCL081LJC-S2.DOC PAGE 3 OF 7 REV. 0

JPM TITLE: ESTABLISH EMERGENCY BORATION JPM NUMBER:

NRCL081LJC-S2 INSTRUCTOR WORKSHEET Step Expected Operator Actions

2. Initiate emergency boration using 2.7 Presses START and verifies at least 30 make-up controls (continued). GPM boric acid flow.

Note: Operator may attempt to open FCV-110B manually.

2.8 Diagnoses that FCV-110B is failed closed.

2.9 Verifies boric acid transfer pump is selected to high speed.

2.10 Closes HCV-104 (BATP 1-1) or HCV-105 (BATP 1-2), as applicable.

2.11 Verifies that VCT pressure is less than 30 psig.

2.12 Determines that emergency boration flow of at least 30 gpm is NOT attainable.

Step was: Sat: ______ Unsat _______*

3. Initiate alternate boration method 3.1 Reads NOTE prior to Step 2.

using CVCS-8104.

3.2 Attempts to open 8104.

3.3 Diagnoses that 8104 will NOT open.

3.4 Determines that emergency boration flow of at least 30 gpm is NOT attainable.

Step was: Sat: ______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes Critical Step and Sub Steps.

NRCL081LJC-S2.DOC PAGE 4 OF 7 REV. 0

JPM TITLE: ESTABLISH EMERGENCY BORATION JPM NUMBER:

NRCL081LJC-S2 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 4. Initiate alternate boration method 4.1 Opens 8805A and 8805B. **

using the RWST.

4.2 Closes LCV-112B and LCV-112C. **

4.3 Adjusts charging flow to greater than 90 gpm. **

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.

NRCL081LJC-S2.DOC PAGE 5 OF 7 REV. 0

JPM NUMBER:

NRCL081LJC-S2 EXAMINEE CUE SHEET Initial Conditions: Unit 1 is shutdown in MODE 3 and an unexplained increase in reactivity is causing source range counts to increase.

Initiating Cue: The Shift Foreman directs you to emergency borate.

NRCL081LJC-S2.DOC PAGE 6 OF 7 REV. 0

JPM TITLE: ESTABLISH EMERGENCY BORATION JPM NUMBER:

NRCL081LJC-S2 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-514 (HSB, 550°F, MOL).

Trip the reactor.

Reset all shutdown bank step counters to zero.

Perform a rod bank update on the PPC.

Verify NR-45 is displaying source ranges.

Enter drill file 1063 or manually insert the following:

Command Description set acvcvctw=12000 Increase VCT level ramp pcvcvct=40,5,0 Ensures VCT pressure < 30 psig mal nisla act,4,600,0,d,0 Causes source range NIs to increase by four decades over 10 minutes.

mal nislb act,4,600,0,d,0 vlv cvc13 2,0,0,0,d,0 #rcvf110b FCV-110B fails closed.

vlv cvc28 2,0,0,0,d,0 #rcvh8104 8104 fails closed.

run 10 Runs for 10 sec.

anack Acknowledges alarms Inform the examiner that the simulator setup is complete.

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

NRCL081LJC-S2.DOC PAGE 7 OF 7 REV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJC-S3

Title:

ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION Examinee:

Evaluator:

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

References:

EOP E-1.4, Transfer to Hot Leg Recirculation, Rev. 19 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 4 Job Designation: RO/SRO Task Number: KA 006A4.05 Rating: 3.9/3.8 AUTHOR: GARY HUTCHISON DATE: 04/29/09 REV. 0

JPM TITLE: ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION JPM NUMBER:

NRCL081LJC-S3 INSTRUCTOR WORKSHEET Directions: No PLANT controls or equipment are to be operated during the performing 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 Unit 1 reactor trip and safety injection has occurred. Cold leg recirculation was initiated just over 10.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ago. Both RHR pumps are running and both SI pumps are aligned for hot leg recirculation.

Initiating Cue: The Shift Foreman directs you to align RHR pump 12 for hot leg recirculation, per EOP E-1.4, steps 6 - 7.

Task Standard: RHR pump 12 aligned for hot leg recirculation in accordance with EOP E-1.4.

NRCL081LJC-S3.DOC PAGE 2 OF 5 REV. 0

JPM TITLE: ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION JPM NUMBER:

NRCL081LJC-S3 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References EOP E-1.4.

Step was: Sat: ______ Unsat _______*

2. Check RHR pump 12 running. 2.1 Observes that RHR pump 12 is running.

Step was: Sat: ______ Unsat _______*

3. Open 8716B, RHR pump 12 3.1 Opens valve 8716B.

discharge crosstie valve. 3.2 Verifies valve open.

Step was: Sat: ______ Unsat _______*

- 4. Open 8703, RHR to hot legs 1 4.1 Attempts to open valve 8703, goes and 2. to RNO after determining 8703 will not open.

4.2 Cuts in series contactors for 8809A AND B **

4.3 Opens 8809A AND B **

4.4 Close 8716B, RHR Pp 2 Disch Crosstie Vlv **

4.5 Throttle RHR HX Outlet valve as needed to maintain motor current LESS THAN 57 amps if needed 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.

NRCL081LJC-S3.DOC PAGE 3 OF 5 REV. 0

JPM NUMBER:

NRCL081LJC-S3 EXAMINEE CUE SHEET Initial Conditions: A Unit 1 reactor trip and safety injection has occurred. Cold leg recirculation was initiated just over 10.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ago. Both RHR pumps are running and both SI pumps are aligned for hot leg recirculation.

Initiating Cue: The Shift Foreman directs you to align RHR pump 12 for hot leg recirculation, per EOP E-1.4, steps 6 - 7.

NRCL081LJC-S3.DOC PAGE 4 OF 5 REV. 0

JPM TITLE: ALIGN RHR PUMP 12 FOR HOT LEG RECIRCULATION JPM NUMBER:

NRCL081LJC-S3 ATTACHMENT 1, SIMULATOR SETUP Select RELAP JPM IC 628. Click the BYPASS SWCK button on the expert screen to continue after control boards are aligned.

Cutout series contactors for 8009A & B Manually insert the following:

Command Description vlv rhr7 1,0,0,0,d,0 Fails 8703 closed This SNAP allows entry into EOP E-1.4 at Step 6. Both SI and RHR pumps are running.

Hang control board caution tags on 8105 and 8106.

Inform the examiner that the simulator setup is complete.

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

NRCL081LJC-S3.DOC PAGE 5 OF 5 REV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJC-S4

Title:

START A REACTOR COOLANT PUMP Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: Print out NRCL081LJC-S4 Attactment.pdf to hand to examinee at step 8.

References:

OP A-6:I, Reactor Coolant Pumps - Place in Service, Rev. 38 AR PK05-03, RCP NO. 13, Rev. 33 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 25 minutes Critical Steps: 6, 7, 8 Job Designation: RO/SRO Task Number: KA 003A1.02 Rating: 2.9 / 2.9 AUTHOR: GARY HUTCHISON ` 12/3/09 REV. 2

JPM TITLE: START A REACTOR COOLANT PUMP JPM NUMBER: NRCL081LJC-S4 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 in HOT STANDBY with three reactor coolant pumps running.

Initiating Cue: The Shift Foreman directs you to start Reactor Coolant Pump 1-3 in accordance with OP A-6:I, step 6.3.6 Task Standard: Reactor Coolant Pump 1-3 has been started in accordance with OP A-6:I and following the start, RCP 13 secured due to multiple alarms .

NRCL081LJC-S4 REV PAGE 2 OF 7 REV. 2 2.DOC

JPM TITLE: START A REACTOR COOLANT PUMP JPM NUMBER: NRCL081LJC-S4 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References OP A-6:I.

Step was: Sat: ______ Unsat _______*

2. Check all related RCP alarms are 2.1 Reads NOTE cleared.

2.2 Observes that PK05-03 and PK05-05 are cleared.

Note: Operator may display PICTURE RCP on the PPC to monitor RCP parameters.

Step was: Sat: ______ Unsat _______*

- 3. Start the Oil Lift Pump and allow 3.1 Verifies RCS pressure is > 325 psig.

it to run at least two minutes.

3.2 Reads NOTE about active alarms.

3.3 Checks RCP related alarms are clear.

3.4 May use PICTURE RCP on the PPC 3.5 Reads CAUTION about Startup power.

3.6 Reads NOTE about Lift pp interlock

- 3.7 Starts the RCP 1-3 oil lift pump.

3.8 Verifies that the RCP 1-3 oil lift pump has started.

3.9 Reads NOTE about RCP amps.

3.10 Waits for two minutes prior to starting the RCP.

Step was: Sat: ______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes Critical Step and Sub Steps.

NRCL081LJC-S4 REV PAGE 3 OF 7 REV. 2 2.DOC

JPM TITLE: START A REACTOR COOLANT PUMP JPM NUMBER: NRCL081LJC-S4 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 4. Start the RCP. ** 4.1 Starts RCP 1-3.

4.2 Verifies RCP 1-3 has started.

4.3 Verifies normal operation of RCP 1-3 by observing pump motor amps and loop 3 flow (FI-434, FI-435, FI-436).

Step was: Sat: _______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes Critical Step and Sub Steps.

NRCL081LJC-S4 REV PAGE 4 OF 7 REV. 2 2.DOC

JPM TITLE: START A REACTOR COOLANT PUMP JPM NUMBER: NRCL081LJC-S4 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 5. Observes that PK05-03 and then 5.1 Refers to PK 05-03 PK05-05 have alarmed.

5.2 Reads Caution about multiple alarms.

5.3 Observes that RCP 13 radial bearing temperature and RCP 13 seal leakoff flow lo are in alarm.

5.4 May check RCP vibration computer for RCP 13.

Cue: Hand examinee printouts of RCP vibration computer screens for RCP 13 5.5 Trips RCP 13 on VB2.**

5.6 Verifies RCP 13 is secured.

5.7 Proceeds to implement OP AP-28 Reactor Coolant Pump Malfunction Cue: Another Operator will address OP AP-28.

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.

NRCL081LJC-S4 REV PAGE 5 OF 7 REV. 2 2.DOC

JPM NUMBER: NRCL081LJC-S4 EXAMINEE CUE SHEET Initial Conditions: Unit 1 is in HOT STANDBY with three reactor coolant pumps running.

Initiating Cue: The Shift Foreman directs you to start Reactor Coolant Pump 1-3 in accordance with OP A-6:I, step 6.3.6 NRCL081LJC-S4 REV PAGE 6 OF 7 REV. 2 2.DOC

JPM TITLE: START A REACTOR COOLANT PUMP JPM NUMBER: NRCL081LJC-S4 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-514 (Hot standby MOL).

Ensure RCP vibration computer program started on simulator floor PC.

Go to RUN.

Perform the following:

1. Trip the reactor

2. Stop RCP 1-3.

3. Allow the plant to stabilize.

Enter drill file 6806 or manually insert the following:

Command Description

1. xmt rcp21 3,244,60,0, Increases RCP 13 radial brg temperature when RCP 13 red lite is on c,xv2o262r

2. ser 1244 act,1,0,50, Brings in PK05-05 RCP Vibration alarm when RCP 13 red lite is on c,xv2o262r Go to FREEZE.

Inform the examiner that the simulator setup is complete.

Go to RUN when the directed by the examiner.

NRCL081LJC-S4 REV PAGE 7 OF 7 REV. 2 2.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJC-S5

Title:

Respond to High Radiation Alarm on RM-44B Examinee:

Evaluator:

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

References:

AR PK02-06 CONTMT VENT ISOLATION Rev. 16 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 Minutes Critical Steps: 1, 2, 3 Job Designation: RO/SRO Task Number: KA 029A3.01 Rating: 3.8/4.0 AUTHOR: GARY HUTCHISON DATE: 12/2/2009 REV. 1

JPM TITLE: RESPOND TO HIGH RADIATION ALARM ON RM- JPM NUMBER:

44B NRCL081LJC-S5 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. 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: None Initial Conditions: Unit 1 is in mode 3. A Containment Purge was in progress when RM-44B went into alarm and a Containment Vent Isolation occurred.

Maintenance has determined that the alarm was spurious.

Initiating Cue: The Shift Foreman directs you to respond to the alarm per AR PK02-06 step 2.1.5 Task Standard: RM-44B high radiaton alarm and CVI are reset and RM-11 and 12 sample pump flowpath aligned per step 2.1.5.

NRCL081LJC-S5 rev Page 2 of 6 REV. 1 1.doc

JPM TITLE: RESPOND TO HIGH RADIATION ALARM ON RM- JPM NUMBER:

44B NRCL081LJC-S5 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

- 1. Reset spurious alarm on RM-44B. 1.1 Reads Caution prior to resetting alarm.

- 1.2 Reset alarm on RM-44B by pressing Fail/ACK pushbutton.

1.3 Verifies Alert, High, and CVI ALM lights go out.

Step was: Sat: ______ Unsat _______*

- 2. Reset containment ventilation ** 2.1 Reset containment ventilation isolation signal. isolation signal by depressing both trains Reset pushbuttons.

2.2 Verifies CVI red lights on VB1 go out.

2.3 Verifies PK02-06 goes out.

Step was: Sat: ______ Unsat _______*

- 3. Opens Valves to restore flow to ** 3.1 Opens FCV-678, Supply to Gas and RM-11 & 12 sample pump. Air Particulate Monitors RM-11 &

RM-12 on VB4.

- 3.2 Opens FCV-679, Supply to RM-11

& RM-12 Outside Containment

- 3.3 Opens FCV-681, Return to Containment from RM-11 & RM-12 Step was: Sat: ______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes a Critical Step.

NRCL081LJC-S5 rev Page 3 of 6 REV. 1 1.doc

JPM TITLE: RESPOND TO HIGH RADIATION ALARM ON RM- JPM NUMBER:

44B NRCL081LJC-S5 INSTRUCTOR WORKSHEET

4. Restart sample pump for RM-11 **********************************

& 12 and contact Maintenance. Cue: Another Operator will restart the sample pump for RM-11 & 12 and contact Maintenance.

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.

NRCL081LJC-S5 rev Page 4 of 6 REV. 1 1.doc

JPM NUMBER:

NRCL081LJC-S5 EXAMINEE CUE SHEET Initial Conditions: Unit 1 is in mode 3. A Containment Purge was in progress when RM-44B went into alarm and a Containment Vent Isolation occurred.

Maintenance has determined that the alarm was spurious.

Initiating Cue: The Shift Foreman directs you to respond to the alarm per AR PK02-06 step 2.1.5 NRCL081LJC-S5 rev Page 5 of 6 REV. 1 1.doc

JPM TITLE: RESPOND TO HIGH RADIATION ALARM ON RM- JPM NUMBER:

44B NRCL081LJC-S5 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-510 (100%, MOL).

Manually insert the following:

Command Description Xmt rms35 3,0.0023,1,0,d,5 High rad on RM-44B, clears after 5 seconds Run 65 Runs 65 seconds Inform the examiner that the simulator setup is complete.

Go to RUN when directed by the examiner.

NRCL081LJC-S5 rev Page 6 of 6 REV. 1 1.doc

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJC-S6

Title:

CROSSTIE OF VITAL BUS G TO H Examinee:

Evaluator:

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

References:

EOP ECA-0.3, Restore 4kV Buses, Appendix X and Appendix Q, Rev.

14A Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 25 minutes Critical Steps: 2, 4, 5, 6, 7, 9, 10, 12, 13, 16 Job Designation: RO/SRO Task Number: KA 062A4.01 Rating: 3.3 / 3.1 AUTHOR: GARY HUTCHISON DATE: 10/22/09 REV.1

JPM TITLE: CROSSTIE OF VITAL BUS G TO H JPM NUMBER:

NRCL081LJC-S6 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 reactor trip and safety injection has occurred concurrent with a loss of all off-site power. Diesel generator 11 and diesel generator 13 have failed due to lube oil pressure problems. Diesel generator 12 is supplying 4kV bus G. CCW Pp 12 has failed resulting in a complete loss of CCW flow.

Initiating Cue: The Shift Foreman directs you to crosstie 4kV bus G to 4kV bus H and energize 480V Bus H per EOP ECA-0.3, Appendix X, commencing at step 4.c. Steps 4.a and 4.b have been completed. The Site Emergency Coordinator has concurred with this implementation.

Task Standard: 4kV and 480V bus H are energized after being crosstied to 4kV bus G in accordance with ECA-0.3.

NRCL081LJC-S6 REV PAGE 2 OF 9 REV.1 1.DOC

JPM TITLE: CROSSTIE OF VITAL BUS G TO H JPM NUMBER: NRCL081LJC-S6 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure. 1.1 References ECA-0.3, Appendix X.

Step was: Sat: ______ Unsat _______*

- 2. Verify OPEN the 4kV to 480 2.1 Opens 52-HH-10. **

VAC bus feeder breaker for the deenergized bus to be reenergized. 2.2 Verifies that 52-HH-10 has opened.

Step was: Sat: ______ Unsat _______*

3. On the deenergized 480V bus to 3.1 Opens all 480V Bus H breakers be reenergized, open all 480V opened.

breakers.

Cue: An Operator has opened all the 480V breakers on bus H.

Step was: Sat: ______ Unsat ___*

- 4. Cut in the DIR PWR, LOSS OF 4.1 Places D/G DIR PWR, LOSS OF FIELD, & BKR OC PROT RLYS FLD & BKR OC PROT RLYS C/O for diesel generator 12. SW to CUT-IN. **

Step was: Sat: ______ Unsat _______*

- 5. Reset SI. 5.1 Checks PK08-21 Safety Injection Actuation status.

5.2 Manually depresses both pushbuttons, if required. **

5.3 Checks at least one of the following:

Monitor Light Box B Safety Injection red light OFF, OR

PK08-21, Safety Injection Actuation not ON.

Step was: Sat: ______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes Critical Step and Sub Steps.

NRCL081LJC-S6 REV PAGE 3 OF 9 REV.1 1.DOC

JPM TITLE: CROSSTIE OF VITAL BUS G TO H JPM NUMBER: NRCL081LJC-S6 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 6. Cutout the auto transfer FCOs for 6.1 Places all Xfer to S/U PWR C/O 4kV and 12kV buses. toggle switch to CUT-OUT. **

Step was: Sat: ______ Unsat _______*

- 7. Depress all auto transfer reset 7.1 Reads NOTE.

pushbuttons.

7.2 Depresses all AUTO XFER RESET pushbuttons, if required. **

7.3 Verifies that all Auto Xfer indicating blue lights are off.

Step was: Sat: ______ Unsat _______*

8. Verify OPEN all vital 4kV bus 8.1 Observes that all vital 4kV bus aux auxiliary feeder breakers. feeder breakers are OPEN:

52-HH-13 OPEN

52-HG-13 OPEN

52-HF-13 OPEN Step was: Sat: ______ Unsat _______*

- 9. Verify OPEN all vital 4kV bus 9.1 Observes that vital 4kV bus startup startup feeder breakers. feeder breakers:

52-HF-14 & 52-HH-14 are CLOSED and Opens Breakers**

52-HG-14 is OPEN Step was: Sat: ______ Unsat _______*

- 10. Verify OPEN the 4kV startup 10.1 Opens 52-HG-15. **

feeder breaker 52-HG-15.

10.2 Verifies that 52-HG-15 has opened.

Step was: Sat: ______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes Critical Step and Sub Steps.

NRCL081LJC-S6 REV PAGE 4 OF 9 REV.1 1.DOC

JPM TITLE: CROSSTIE OF VITAL BUS G TO H JPM NUMBER: NRCL081LJC-S6 INSTRUCTOR WORKSHEET Step Expected Operator Actions

11. Verify that Steps 4.b and 4.c of 11.1 Reads CAUTION and NOTE this appendix are complete.

Cue: Steps 4.b and 4.c of this appendix are complete.

Step was: Sat: ______ Unsat _______*

- 12. Close 4kV startup feeder breaker 12.1 Inserts sync key for 4kV bus H for the deenergized bus being startup feeder breaker 52-HH-14.

reenergized.

12.2 Turns sync switch to ON. **

12.3 Closes 52-HH-14. **

12.4 Verifies that 52-HH-14 has closed.

Step was: Sat: ______ Unsat _______*

- 13. Close the 4kV startup feeder 13.1 Inserts sync key for 4kV bus G breaker for the bus that will be startup feeder breaker 52-HG-14.

supplying power to the deenergized bus. 13.2 Turns sync switch to ON. **

13.3 Closes 52-HG-14. **

13.4 Verifies that 52-HG-14 has closed.

13.5 Verifies running diesel generator remains stable.

Step was: Sat: ______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes Critical Step and Sub Steps.

NRCL081LJC-S6 REV PAGE 5 OF 9 REV.1 1.DOC

JPM TITLE: CROSSTIE OF VITAL BUS G TO H JPM NUMBER: NRCL081LJC-S6 INSTRUCTOR WORKSHEET Step Expected Operator Actions

14. IMPLEMENT Appendix Q to start 14.1 Reads cautions 4kV loads as needed on the reengergized bus.

Cue: An operator has been stationed at VB4 and will implement Appendix Q and will monitor the diesel generator.

Step was: Sat: ______ Unsat _______*

15. Verify that Step 4.d of this 15.1 Verifies that Step 4.d of this Appendix is complete PRIOR to Appendix is complete.

performing the next step.

Cue: Step 4 of this Appendix is complete.

Step was: Sat: ______ Unsat _______*

- 16. Close the 4kV to 480V bus feeder 16.1 Closes 52-HH-10.**

breaker for the reenergized bus.

16.2 Verifies that 52-HH-10 has closed.

Step was: Sat: ______ Unsat _______*

17. Implement Appendix Q for 17.1 Implements Appendix Q for starting starting 480V loads as needed. 480V bus loads as needed.

Cue: An operator has been stationed at VB4 with Appendix Q to monitor the diesel generator.

Step was: Sat: ______ Unsat _______*

Stop Time:

Denotes an entry required on the JPM cover sheet.

- Denotes Critical Step and Sub Steps.

NRCL081LJC-S6 REV PAGE 6 OF 9 REV.1 1.DOC

JPM TITLE: CROSSTIE OF VITAL BUS G TO H JPM NUMBER: NRCL081LJC-S6 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.

NRCL081LJC-S6 REV PAGE 7 OF 9 REV.1 1.DOC

JPM NUMBER:

NRCL081LJC-S6 EXAMINEE CUE SHEET Initial Conditions: A reactor trip and safety injection has occurred concurrent with a loss of all off-site power. Diesel generator 11 and diesel generator 13 have failed due to lube oil pressure problems. Diesel generator 12 is supplying 4kV bus G. CCW Pp 12 has failed resulting in a complete loss of CCW flow.

Initiating Cue: The Shift Foreman directs you to crosstie 4kV bus G to 4kV bus H and energize 480V Bus H per EOP ECA-0.3, Appendix X, commencing at step 4.c. Steps 4.a and 4.b have been completed. The Site Emergency Coordinator has concurred with this implementation.

NRCL081LJC-S6 REV PAGE 8 OF 9 REV.1 1.DOC

JPM TITLE: CROSSTIE OF VITAL BUS G TO H JPM NUMBER:

NRCL081LJC-S6 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to the IC-510 (100%, MOL).

Enter drill file 1032 or manually insert the following:

Command Description

1. mal deg1a act,2,0,0,d,0 Fails DG 11

2. mal deg1c act,2,0,0,d,0 Fails DG 13

3. mal syd1 act,1,1,0,d,0 Loss of offset power

4. mal ppl2a act,0,0,0,d,2 Inadvertent SI, Train A

5. mal ppl2b act,0,0,0,d,2 Inadvertent SI, Train B

6. pmp ccw2 4,0,0,4,d,0 CCW pp 1-2 OC trip

7. loa afw14 act,f,0, 60,d,0 Opens knife switch for AFW pp 1-2

8. loa css8 act,f,0,60,d,0 Opens knife switch for cont. spray pp 1-2

9. loa rhr10 act,f,0,60,d,0 Opens knife switch for RHR pp 1-2

10. loa ccw31 act,f,0,60,d,0 Opens knife switch for CCW pp 1-3

11. loa sis2 act,f,0,60,d,0 Opens knife switch for SI pp 1-2

12. dsc ven14 act,f,0,60,d,0 Opens breaker for CFCU 1-4

13. run Drill 63 (Strips 480v bus H). Manual insert is not practical due to large number of actions.

Freeze simulator Inform the examiner that the simulator setup is complete.

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

NRCL081LJC-S6 REV PAGE 9 OF 9 REV.1 1.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJP-P2

Title:

CLOSE AN MSIV FCV-43 (Lead 3) LOCALLY Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: This JPM can be performed on Unit 1 or Unit 2.

References:

U2 EOP E-2, Faulted Steam Generator Isolation, Appendix L, Rev 13.

U1 EOP E-2, Faulted Steam Generator Isolation, Appendix L, Rev 17.

Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 1, 2, 3 Job Designation: RO/SRO Task Number: KA APE040AA1.03 Rating: 4.3 / 4.3 JOHN BECERRA AUTHOR: GARY HUTCHISON DATE: 12/11/09 REV. 1

JPM TITLE: CLOSE AN MSIV LOCALLY JPM NUMBER:

NRCL081LJP-P2 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 for the appropriate Unit.

Initial Conditions: A main steam line rupture has occurred on Unit 1/Unit 2 downstream of the MSIVs. MSIV FCV-43 has failed to close automatically. Manual attempts to close it from VB-3 have also been unsuccessful. FCV-43 bypass valve, FCV-23, is closed.

Initiating Cue: After completion of your tailboard, the Shift Foreman provides you with an eight inch Crescent wrench, a diagonal cutter, and a flashlight, then directs you to locally CLOSE MSIV FCV-43 in accordance with Appendix L of EOP E-2.

Task Standard: Unit 1/Unit 2 MSIV FCV-43 has been CLOSED in accordance with Appendix L of EOP E-2.

NRCL081LJC-P2 REV PAGE 2 OF 4 REV. 1 1.DOC

JPM TITLE: CLOSE AN MSIV LOCALLY JPM NUMBER:

NRCL081LJP-P2 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

- 1. Locally CLOSE MSIV air supply 1.1 CLOSES air supply valve **

or common air supply valves. Common air supply valve AIR-I-1-1044 Unit 1 AIR-I-2-1044 Unit 2 OR MSIV air supply valve AIR-I-1-4054 Unit 1 AIR-I-2-4027 Unit 2 Step was: Sat: ______ Unsat _______*

- 2. REMOVES BOTH accumulator 2.1 REMOVES BOTH accumulator drain drain caps. caps.**

Step was: Sat: ______ Unsat _______*

- 3. OPEN MSIV air accumulator 3.1 OPENS drain valves **

drain valves. AIR-I-1-1547 Unit 1 AIR-I-2-1547 Unit 2 AND AIR-I-1-1548 Unit 1 AIR-I-2-1548 Unit 2 Cue: You hear the flow of steam stop.

If asked the Control Room reports that FCV-43 has closed.

3.2 Reports to the Control Room that you have closed FCV-43.

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.

NRCL081LJC-P2 REV PAGE 3 OF 4 REV. 1 1.DOC

JPM NUMBER:

NRCL081LJP-P2 EXAMINEE CUE SHEET Initial Conditions: A main steam line rupture has occurred on Unit 1/Unit 2 downstream of the MSIVs. MSIV FCV-43 has failed to close automatically. Manual attempts to close it from VB-3 have also been unsuccessful. FCV-43 bypass valve, FCV-23, is closed.

Initiating Cue: After completion of your tailboard, the Shift Foreman provides you with an eight inch Crescent wrench, a diagonal cutter, and a flashlight, then directs you to locally CLOSE MSIV FCV-43 in accordance with Appendix L of EOP E-2.

NRCL081LJC-P2 REV PAGE 4 OF 4 REV. 1 1.DOC

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJP-P1 U2

Title:

ALIGN 480V BUSES FOR CONTROL FROM THE HOT SHUTDOWN PANEL Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: This is a Unit 2 JPM.

References:

U2 OP AP-8A, Control Room Inaccessibility - Establishing Hot Standby, Rev. 22 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 1, 2, 3, 4, 5, 6 Job Designation: RO/SRO Task Number: KA 062A4.04 Rating: 2.6 / 2.7 AUTHOR: GARY HUTCHISON 12/3/09 REV. 0

JPM TITLE: ALIGN 480V BUSES FOR CONTROL FROM THE HOT JPM NUMBER:

SHUTDOWN PANEL NRCL081LJP-P1 U2 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 OP AP-8A, Appendix F.

Initial Conditions: A fire in the control boards has caused a Unit 2 Control Room evacuation. OP AP-8A is being performed and the operating crew is ready to align all 480 VAC loads for control from the Hot Shutdown Panel.

Initiating Cue: The Shift Foreman directs you to perform Appendix F of OP AP-8A.

Task Standard: Breakers and switches aligned per Appendix F of OP AP-8A NRCL081LJC-P1 u2.doc PAGE 2 OF 7 REV. 0

JPM TITLE: ALIGN 480V BUSES FOR CONTROL FROM THE HOT JPM NUMBER:

SHUTDOWN PANEL NRCL081LJP-P1 U2 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

- 1. Place the control transfer cutout 1.1 Locates the 480V vital bus F aux switches for 480V vital bus F to relay panel in the vital switchgear the CUT-IN position. room.

Note: CUT IN / CUT OUTs switches are located inside the aux relay panel.

The aux relay panel may be opened.

1.2 Places the following switches to the CUT-IN position:

switch 43BX, letdown orifice valve 8149B. **

switch 43X-2F-1, containment fan cooler CFCU 22. **

Step was: Sat: ______ Unsat _______*

- 2. Open 480V vital bus F breakers to 2.1 Opens the following breakers:

prevent spurious operation.

FCV-430 bkr 52-2F-11. **

LCV-112B bkr 52-2F-12 **

8805A bkr 52-2F-19. **

FCV-750 bkr 52-2F-23. **

Step was: Sat: ______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes Critical Step and Sub Steps.

NRCL081LJC-P1 u2.doc PAGE 3 OF 7 REV. 0

JPM TITLE: ALIGN 480V BUSES FOR CONTROL FROM THE HOT JPM NUMBER:

SHUTDOWN PANEL NRCL081LJP-P1 U2 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 3. Place the control transfer cutout 3.1 Locates 480V vital bus G aux relay switches for 480V vital bus G to panel in the vital switchgear room.

the CUT-IN position.

Note: CUT IN / CUT OUTs switches are located inside the aux relay panel.

The aux relay panel may be opened.

3.2 Places the following switches to the CUT-IN position:

switch 43X-22-30, FCV-95.**

switch 43X-2G-2, CFCU 25.**

switch 43X-2G-57, emergency borate valve 8104.**

switch 43X-2G-4, BATP 2-2.**

switch 43X-2G-44, LCV-106.**

switch 43X-2G-68, LCV-107.**

Step was: Sat: ______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes Critical Step and Sub Steps.

NRCL081LJC-P1 u2.doc PAGE 4 OF 7 REV. 0

JPM TITLE: ALIGN 480V BUSES FOR CONTROL FROM THE HOT JPM NUMBER:

SHUTDOWN PANEL NRCL081LJP-P1 U2 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 4. Open 480V vital bus G breakers to 4.1 Opens the following breakers:

prevent spurious operation.

FCV-356 bkr 52-2G-36. **

9003A bkr 52-2G-48. **

8982A bkr 52-2G-58. **

LCV-112C bkr 52-2G-11.**

8805B bkr 52-2G-14. **

FCV-363 bkr 52-2G-23. **

8100 bkr 52-2G-26. **

FCV-431 bkr 52-2G-28 **

Step was: Sat: ______ Unsat _______*

- 5. Open 480V vital bus H breakers to 5.1 Opens the following breakers:

prevent spurious operation.

9003B bkr 52-2H-06. **

Opens 8982B bkr 52-2H-12. **

Opens FCV-355 bkr 52-2H-16. **

Opens FCV-357 bkr 52-2H-17. **

Opens FCV-749 bkr 52-2H-18. **

Step was: Sat: ______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes Critical Step and Sub Steps.

NRCL081LJC-P1 u2.doc PAGE 5 OF 7 REV. 0

JPM TITLE: ALIGN 480V BUSES FOR CONTROL FROM THE HOT JPM NUMBER:

SHUTDOWN PANEL NRCL081LJP-P1 U2 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 6. Place the control transfer cutout 6.1 Locates the 480V bus 23D control switches for 480V bus 23D to the transfer cutout switch inside bus CUT-IN position. 23D panel behind control transfer relay 43X-3D-6.

Note: The examinee should simulate this step. The panel should NOT be opened.

6.2 Places PZR Htr Group 2 Control Transfer Cutout Switch in the CUT-IN position. **

Cue: Cut-out switch has been CUT-IN.

6.3 Open 72-2321and 72-2224 to prevent spurious operation of the Reactor Head Vents. **

6.4 Informs the HSDP Operator that the 480V Bus Alignment is complete.

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.

NRCL081LJC-P1 u2.doc PAGE 6 OF 7 REV. 0

JPM NUMBER:

NRCL081LJP-P1 U2 EXAMINEE CUE SHEET Initial Conditions: A fire in the control boards has caused a Unit 2 Control Room evacuation. OP AP-8A is being performed and the operating crew is ready to align all 480 VAC loads for control from the Hot Shutdown Panel.

Initiating Cue: The Shift Foreman directs you to perform Appendix F of OP AP-8A.

NRCL081LJC-P1 u2.doc PAGE 7 OF 7 REV. 0

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL081LJP-P1 U1

Title:

ALIGN 480V BUSES FOR CONTROL FROM THE HOT SHUTDOWN PANEL Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: This is a Unit 1 JPM.

References:

U1 OP AP-8A, Control Room Inaccessibility - Establishing Hot Standby, Rev. 26 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 1, 2, 3, 4, 5, 6 Job Designation: RO/SRO Task Number: KA 062A4.04 Rating: 2.6 / 2.7 AUTHOR: GARY HUTCHISON 12/3/09 REV. 0

JPM TITLE: ALIGN 480V BUSES FOR CONTROL FROM THE HOT JPM NUMBER:

SHUTDOWN PANEL NRCL081LJP-P1 U1 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 OP AP-8A, Appendix F.

Initial Conditions: A fire in the control boards has caused a Unit 1 Control Room evacuation. OP AP-8A is being performed and the operating crew is ready to align all 480 VAC loads for control from the Hot Shutdown Panel.

Initiating Cue: The Shift Foreman directs you to perform Appendix F of OP AP-8A.

Task Standard: Breakers and switches aligned per Appendix F of OP AP-8A NRCL081LJC-P1 u1.doc PAGE 2 OF 7 REV. 0

JPM TITLE: ALIGN 480V BUSES FOR CONTROL FROM THE HOT JPM NUMBER:

SHUTDOWN PANEL NRCL081LJP-P1 U1 INSTRUCTOR WORKSHEET Start Time:

Step Expected Operator Actions

- 1. Place the control transfer cutout 1.1 Locates the 480V vital bus F aux switches for 480V vital bus F to relay panel in the vital switchgear the CUT-IN position. room.

Note: CUT IN / CUT OUTs switches are located inside the aux relay panel.

The aux relay panel may be opened.

1.2 Places the following switches to the CUT-IN position:

switch 43BX, letdown orifice valve 8149B. **

switch 43X-1F-1, containment fan cooler CFCU 12. **

Step was: Sat: ______ Unsat _______*

- 2. Open 480V vital bus F breakers to 2.1 Opens the following breakers:

prevent spurious operation.

FCV-430 bkr 52-1F-11. **

LCV-112B bkr 52-1F-12 **

8805A bkr 52-1F-19. **

FCV-750 bkr 52-1F-23. **

Step was: Sat: ______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes Critical Step and Sub Steps.

NRCL081LJC-P1 u1.doc PAGE 3 OF 7 REV. 0

JPM TITLE: ALIGN 480V BUSES FOR CONTROL FROM THE HOT JPM NUMBER:

SHUTDOWN PANEL NRCL081LJP-P1 U1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 3. Place the control transfer cutout 3.1 Locates 480V vital bus G aux relay switches for 480V vital bus G to panel in the vital switchgear room.

the CUT-IN position.

Note: CUT IN / CUT OUTs switches are located inside the aux relay panel.

The aux relay panel may be opened.

3.2 Places the following switches to the CUT-IN position:

switch 43X-12-30, FCV-95.**

switch 43X-1G-2, CFCU 15.**

switch 43X-1G-57, emergency borate valve 8104.**

switch 43X-1G-4, BATP 1-2.**

switch 43X-1G-44, LCV-106.**

switch 43X-1G-68, LCV-107.**

Step was: Sat: ______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes Critical Step and Sub Steps.

NRCL081LJC-P1 u1.doc PAGE 4 OF 7 REV. 0

JPM TITLE: ALIGN 480V BUSES FOR CONTROL FROM THE HOT JPM NUMBER:

SHUTDOWN PANEL NRCL081LJP-P1 U1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 4. Open 480V vital bus G breakers to 4.1 Opens the following breakers:

prevent spurious operation.

FCV-356 bkr 52-1G-36. **

9003A bkr 52-1G-48. **

8982A bkr 52-1G-58. **

LCV-112C bkr 52-1G-11.**

8805B bkr 52-1G-14. **

FCV-363 bkr 52-1G-23. **

8100 bkr 52-1G-26. **

FCV-431 bkr 52-1G-28 **

Step was: Sat: ______ Unsat _______*

- 5. Open 480V vital bus H breakers to 5.1 Opens the following breakers:

prevent spurious operation.

9003B bkr 52-1H-06. **

Opens 8982B bkr 52-1H-12. **

Opens FCV-355 bkr 52-1H-16. **

Opens FCV-357 bkr 52-1H-17. **

Opens FCV-749 bkr 52-1H-18. **

Step was: Sat: ______ Unsat _______*

Denotes an entry required on the JPM cover sheet.

- Denotes Critical Step and Sub Steps.

NRCL081LJC-P1 u1.doc PAGE 5 OF 7 REV. 0

JPM TITLE: ALIGN 480V BUSES FOR CONTROL FROM THE HOT JPM NUMBER:

SHUTDOWN PANEL NRCL081LJP-P1 U1 INSTRUCTOR WORKSHEET Step Expected Operator Actions

- 6. Place the control transfer cutout 6.1 Locates the 480V bus 13D control switches for 480V bus 13D to the transfer cutout switch inside bus CUT-IN position. 13D panel behind control transfer relay 43X-3D-6.

Note: The examinee should simulate this step. The panel should NOT be opened.

6.2 Places PZR Htr Group 2 Control Transfer Cutout Switch in the CUT-IN position. **

Cue: Cut-out switch has been CUT-IN.

6.3 Open 72-1321and 72-1224 to prevent spurious operation of the Reactor Head Vents. **

6.4 Informs the HSDP Operator that the 480V Bus Alignment is complete.

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.

NRCL081LJC-P1 u1.doc PAGE 6 OF 7 REV. 0

JPM NUMBER:

NRCL081LJP-P1 U1 EXAMINEE CUE SHEET Initial Conditions: A fire in the control boards has caused a Unit 1 Control Room evacuation. OP AP-8A is being performed and the operating crew is ready to align all 480 VAC loads for control from the Hot Shutdown Panel.

Initiating Cue: The Shift Foreman directs you to perform Appendix F of OP AP-8A.

NRCL081LJC-P1 u1.doc PAGE 7 OF 7 REV. 0

Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL081LJC-P3

Title:

Local Verification of Containment Isolation Phase B Examinee:

Evaluator:

Print Signature Date Results: Sat Unsat Total Time: minutes Comments: This JPM can be performed on Unit 1 or Unit 2.

References:

System Lesson Guide B6A, Reactor Protection System, page 2.2-45 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 1,2,3 Job Designation: RO K/A: 103 A2.03 Rating: 3.5/3.8 AUTHOR: CHRIS STEELY/GARY HUTCHISON DATE: 12/10/2009 REV. 1

JPM

Title:

Local Verification Cont. Isolation Phase B JPM Number:

NRCL081LJC-P3 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:

Initial Conditions: The reactor has tripped and Phase B isolation has occurred. The following lights on Monitor Light Box D do not indicate the complete actuation of Phase B:

Spray Pump 1 Discharge Valve - 9001A (Should be OPEN)

Spray Additive Tank Out - 8994B (Should be OPEN)

CCW HDR C ISO - FCV 355 (Should be CLOSED)

Initiating Cue: The Shift Foreman directs you to enter the plant and locally verify the correct position of the non-indicating Phase B valves. The breakers for the associated valves have been opened.

Task Standard: DO NOT READ TO STUDENT: Spray Pump 1 Discharge Valve -

9001A, will be CLOSED and will need to be repositioned OPEN (Alternate Path). Spray Additive Tank outlet valve 8994B will be CLOSED and will need to be repositioned OPEN (Alternate Path). CCW HDR C ISO- FCV 355 will be OPEN and will need to be repositioned CLOSED (Alternate Path).

Denotes an entry required on the JPM cover sheet

- Denotes a Critical Step NRCL081LJC-P3 Rev 1.DOC Page 2 of 4 REV. 1

JPM

Title:

Local Verification Cont. Isolation Phase B JPM Number:

NRCL081LJC-P3 Instructor Worksheet Start Time:

Step Expected Operator Actions

1. Locally verify proper actuation of Location: 115 Aux Bldg Cnm Pen area Phase B Containment isolation CUE: Valve position is as seen.

Valves that are not properly indicating on Monitor Light Box 1.1 Opens Spray Pump 1 Discharge Valve -

D. ** 9001A **

CUE: Valve position indicator is up.

Step was: Sat: ______ Unsat _______*

2. Locally verify proper actuation of Location: 73 Aux Bldg near Spray Add Tank Phase B Containment isolation CUE: Valve Position is as seen.

Valves that are not properly indicating on Monitor Light Box 2.1 Opens Spray Additive Tank Out - 8994B **

D. ** CUE: Valve position indicator is up.

Step was: Sat: ______ Unsat _______*

3. Locally verify proper actuation of Location: 85 Turb. Bldg upper area of CCW HX Phase B Containment isolation room Valves that are not properly CUE: Valve Position is as seen.

indicating on Monitor Light Box D. ** 3.1 Closes CCW HDR C ISO - FCV 355 **

CUE: Valve Position indicator shows C.

Step was: Sat: ______ Unsat _______*

Stop Time:

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

NRCL081LJC-P3 Rev 1.DOC Page 3 of 4 REV. 1

JPM Number: NRCL081LJC-P3 Examinee Cue Sheet Initial Conditions:

The reactor has tripped and Phase B isolation has occurred. The following lights on Monitor Light Box D do not indicate the complete actuation of Phase B:

Spray Pump 1 Discharge Valve - 9001A (Should be OPEN)

Spray Additive Tank Out - 8994B (Should be OPEN)

CCW HDR C ISO - FCV 355 (Should be CLOSED)

Initiating Cue:

The Shift Foreman directs you to enter the plant and locally verify the correct position of the non-indicating Phase B valves. The breakers for the associated valves have been opened.

NRCL081LJC-P3 Rev 1.DOC Page 4 of 4 REV. 1

Appendix D Scenario Outline Form ES-D-1 Facility: Diablo Canyon Scenario No.: 1 Op-Test No.: Jan 2010 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Operating per OP-L-4. Reactor Power is 100 percent. Diesel Generator 1-1 is paralleled with Bus H for EDG Monthly Surveillance Testing.

Turnover: Secure EDG 1-1. Maintain power at 100 percent.

Event Malf. Event Event No. No. Type* Description 1 N(BOP) Unload and Secure EDG 1-1. After output breaker is opened, EDG trips on low lube oil pressure. (Will not get back) 2 I(ATC/SRO) Tc channel fails high.

TS 3 C(ALL) TS Steam Generator Tube Leak (SG1-2) (Action Level 3b) (Requires downpower per OP AP-25) 4 C(ALL) Loss of all (230kV and 500kV) Offsite Power, results in reactor trip.

(We will have to insert reactor trip due to DCPP main generator supplying in house loads and would survive the load rejection.)

5 C(BOP) EDG 1-3 output breaker fails to auto close. Manual action to close the breaker.

6 C(BOP) (TDAFWP Steam Supply) FCV-95 fails to Auto Open. (Manual Action Required)

MD AFW pump 1-3 fails to auto start. (Manual Action Required) 7 M(ALL) SGTR on SG 1-2 Isolate Ruptured Steam Generator - CRITICAL TASK Close FCV-37 (Powered from Bus H) (TDAFWP steam supply from SG 1-2) - CRITICAL TASK Restore AFW - CRITICAL TASK

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRCSIM081 01 Appendix D outline Rev 2.doc Rev. 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 1 Page 1 of 8 Event

Description:

Unload and Secure EDG 1-1 (STP M-9A)

Time Position Applicants Actions or Behavior SRO Directs BOP to unload and secure EDG 1.1 BOP Place the DG 1-1 Feeder Sync switch in "ON".

BOP Reduce DG 1-1 load to about 0.1 MW, and promptly OPEN 52-HH-7, DG 1-1 Output Breaker, to separate DG 1-1 from the bus.

BOP Determines DG 1-1 has tripped.

SRO Refers to PK 16-15 DSL GEN 11 SHUTDOWN RELAY TRIP and PK 16-06 DIESEL 11 LUBE OIL SYSTEM.

SRO/BOP Dispatches operator to DG 11 to determine alarms at local annunciator panel.

SRO Directs Maintenance to investigate trip SRO Refers to TS 3.8.1.B NRCSIM081 01 Appendix D outline Rev 2.doc Rev. 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 2 Page 2 of 8 Event

Description:

Tc Fails High (OP AP-5)

Time Position Applicants Actions or Behavior ATC Acknowledges and reports the following Annunciators:

PK04-10 (AUCTIONED TAVG HIGH)

PK04-03 (TAVG DEVIATION FROM REF)

PK04-01 (RCL DELTA-T DEVIATION)

PK06-03 (PPS RTD FAILURE)

ATC Places rod control to manual and informs SRO Places Pzr level control in manual and adjusts charging flow as necessary.

ATC Enters AP-5 and directs ATC to return Tavg to match Tref.

SRO Determines that PK06-03 is ON, and PK06-01 is OFF.

BOP

1) Determine which Protection Set is affected from the Main Annunciator Typewriter or CRT. (set 4)

2) Directs local operator to open ALL the doors for the racks in the affected protection set and inspect PER Attachment 4.2, "Eagle 21 Rack Inspection/Compensatory Measure Tracking Sheet."

Protection Set 4 - Racks 15, 16 SRO Since PK06-03 is ON, determine which Instrument Channels are in the affected rack using Attachment 4.1.

BOP IMPLEMENT Attachment 4.2 to monitor the status of the unaffected racks in the BOP IDENTIFY affected Protection Set and Rack number BOP REFER to Attachment 4.1 pages 3-17 to determine failed channel bistable BOP COMPLETE Attachment 4.3, "Bistable Trip Authorization."

BOP/ATC Defeats Loop 4 DT and TAVG ATC Select redundant recorder, if available.

NRCSIM081 01 Appendix D outline Rev 2.doc Rev. 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 2 Page 3 of 8 Event

Description:

Tc Fails High (OP AP-5) continued Time Position Applicants Actions or Behavior ATC CHECK Steam Dumps NOT Actuated

Steam Dump Valves - CLOSED

UI-500 Demand - ZERO

Dumps Arming Signal light - OFF

Dumps Trip Signal light - OFF SRO NOTIFY I&C to Investigate SRO/ATC VERIFY Affected Channels are Removed From Service Prior to Performing Maintenance SRO/ATC/BOP PLACE Out-of-Service Stickers On the Affected Indicators:

SRO/ATC PERFORM Required TS/ECG Actions for INOPERABLE Channels ATC WHEN Failure has been Corrected, Return CHANNEL to NORMAL Status ATC Return CONTROL SYSTEM to AUTO SRO Refers to TS 3.3.1.X, 3.3.1.E, 3.3.2.M NRCSIM081 01 Appendix D outline Rev 2.doc Rev. 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Page 4 of 8 Event

Description:

Steam Generator Tube Leak on SG 1-2 (OP AP-3)

Time Position Applicants Actions or Behavior ATC/BOP Acknowledges and announces radiation monitoring alarms and begins an investigation into possible tube leak.

SRO Begins investigation into possible SG tube leakage by directing ATC/BOP to monitor RCS leakage and identify the affected SG. Refers to PK 11-06 SRO Direct ATC/BOP through actions in OP AP-3 (SG Tube Failure)

ATC CHECK PZR Level and Charging Flow BOP TRY To Identify Affected S/G ATC CHECK If VCT Level Can Be Maintained SRO/ATC CHECK If Plant Should Be Shut Down SRO Determines per OP O-4 action level 3b that plant must be in Mode 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months After crew determines that a shutdown is required, Shift Manager will direct a ramp rate of 10 MW/min to take the unit offline.

SRO Refers to OP AP-25 to ramp unit at 10 MW/min ATC Ramps turbine at 10 MW/min

Places MW feedback in service.

Set desired Ramp Rate. (10 MW/Min)

Set Target to desired load. (<200 MW)

Commence ramp by Pressing GO ATC Turns backup heaters on ATC Commences RCS boration

Set target Batch on flow controller (40 gallons)

Verify Boric Acid Flow Rate set to desired flow

Start Boration and verify response.

Return controller to auto at conclusion of Batch SRO Directs Chemistry to sample per CAP AP-1 SRO Refers to TS 3.4.13.B NRCSIM081 01 Appendix D outline Rev 2.doc Rev. 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 4-6 Page 5 of 8 Event

Description:

Loss of all Offsite Power (230kV and 500kV), EDG 1-3 output breaker fails to Auto Close, FCV-95 (TDAFWP Steam Supply) fails to Auto Open, and MD AFW pump 1-3 fails to Auto Start. (OP AP-26)

Time Position Applicants Actions or Behavior Perform remaining immediate actions of E-0 Reactor Trip or Safety ALL Injection VERIFY reactor tripped

Rods bottom lights lit

Power decreasing

Reactor trip breakers open VERIFY turbine tripped

All Turb Stm Stop Vlvs - CLOSED VERIFY vital 4kV buses energized - crew determines that 2 vital buses are de-energized BOP ENERGIZE a Non-Vital Bus From a D/G (EDG 1-3 output breaker will fail to Auto Close thus necessitating manual action to close this breaker).

CHECK SI - Actuated - determines that PK 08-21 is off.

Determines that PK 02-02 is off and NO SI bistable lights are on

Announce reactor trip on Public Address system

Directs BOP to throttle AFW flow and maintain heat sink BOP FCV -95 will fail to Auto Open - Will have to be opened manually BOP MD AFW pump 1-3 will fail to Auto Start - (Manual Action Required)

Critical Task SRO Transitions to EOP E-0.1 Reactor Trip Response ATC Checks RCS temperature stable or trending to 547 F ATC Check Fdwtr status -

Tavg < 554 F,

FW isolation red light on,

AFW flow > 435 gpm ATC Check all rods fully inserted ATC Check Pzr level > 17% and charging and letdown in service ATC Check Pzr pressure > 1850 psig, and trending to 2235 psig BOP Check S/G levels - control between 20% and 65%

NRCSIM081 01 Appendix D outline Rev 2.doc Rev. 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Page 6 of 8 Event

Description:

SGTR on SG 1-2 (EOP E-3)

Time Position Applicants Actions or Behavior ATC Determines that Pzr level is decreasing and a Safety Injection is required SRO Directs manual Safety Injection and transitions back to EOP E-0 ALL Re-verifies immediate action steps of E-0 SRO Announce Reactor Trip/SI on Public Address System Performs Appendix E of EOP E-0 BOP

Check Main generator tripped

Verify Containment Isolation Phase A

Verify Containment Vent Isoation

Verify SI status

Verify Fdwtr Isolation

Verify Containment Spray and Phase B - not required

CHECK Main Steamline Isol NOT REQUIRED

Check ECCS flow

Report ESF equipment status to SFM

Check Excess letdown not in service

Turn on Aux Bldg Vent Charcoal Filter Preheater

Check Secondary System Status

Check Aux Bldg and Control Room Ventilation status

Check Diesel Generator Status

Verify Battery Chargers supplying Vital Batteries

Isolate reheat steam to MSRs

Maintain Seal Injection flow 8-13 gpm

Notify SFM Appendix E is complete ATC Check AFW status and throttle as needed ATC Check RCS temperature stable or trending to 547 F ATC Check Pzr Safetys, PORVs, and Spray valves closed ATC Check if RCPs should be stopped ATC Check S/Gs not Faulted ATC Check for Ruptured S/G - notes that S/G 1-2 increasing in an unexpected manner.

SRO/ATC Recognition of transition from tube failure to tube rupture on SG 1-2 SRO Direct ATC/BOP through actions of EOP E-3(SGTR) - transition from EOP E-0 SRO/ATC 1. Check if RCPs should be stopped ATC 2. Identify ruptured SG (Will have occurred from earlier tube leak)

NRCSIM081 01 Appendix D outline Rev 2.doc Rev. 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Page 7 of 8 Event

Description:

SGTR on SG 1-2 (EOP E-3) continued Time Position Applicants Actions or Behavior ATC 3. Isolate flow from ruptured SG (SG 1-2) CRITICAL TASK

Set PCV-20 to 8.67 turns

Check PCV-20 closed or throttling to control pressure at 1020 psig

Close S/G 12 MSIV

Close FCV directs local operator to trip TDAFW pp and locally close FCV-37 Note: Closing FCV-37 (TDAFWP steam supply from SG 1-2) will be part of this critical task.

Verify blowdown and sample valves are close for S/G 12 ATC 4. Check ruptured SG levels - stop AFW flow to S/G 12 SRO/ATC 5. Verify ruptured SG isolation from step three completed CRITICAL TASK ATC 6. Check ruptured SG pressure greater than 225#

SRO 7. Prepare for RCS cooldown BOP 8. Block Low Steam Line Pressure SI BOP 9. Initiate RCS cooldown using 40% Steam Dumps - not used, since condenser not available BOP 10. Initiate RCS cooldown using 10% Steam Dumps SRO 11. Check Intact S/G level ATC 12. Check PZR PORVs and Block Valves BOP 13. Reset SI BOP 14. Reset both trains of Containment Isolation Phase A and B BOP 15. Establish Instrument Air to Containment BOP 16. Check status of RHR pumps SRO 17. Check if RCS cooldown should be stopped ATC 18. Check Ruptured SG Pressure (Stable or Increasing)

BOP 19. Check RCS Sub-Cooling based on Core Exit T/Cs ATC 20. Depressurize RCS using Pzr Spray Valves (not used, no RCPs)

ATC 21. Depressurize RCS using PORVs to minimize break flow and refill PZR ATC 22. Check RCS Pressure (Increasing)

ATC 23. Depressurize RCS using Aux Spray to minimize break flow (N/A )

24. Check if ECCS flow should be terminated ATC NRCSIM081 01 Appendix D outline Rev 2.doc Rev. 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Page 8 of 8 Event

Description:

SGTR on SG 1-2 (EOP E-3) continued Time Position Applicants Actions or Behavior

25. Stop ECCS pumps and place in Standby BOP

26. Isolate Charging Injection BOP NRCSIM081 01 Appendix D outline Rev 2.doc Rev. 2

MAJOR EVENT

SUMMARY

AND SCENARIO OBJECTIVES A. Unload and Secure EDG 1-1. After output breaker is opened, EDG trips on low lube oil pressure. (Will not get EDG 1-1 back)

B. Loop 4 Tcold channel fails high. ATC takes manual control of rods and crew enters AP-5 Malfunction of Eagle 21 Protection or Control Channel C. S/G 12 tube leak at 200 gpd. Crew enters AP-3 SG Tube Failure. Crew commences ramp per OP AP-25 Rapid Load Reduction or Shutdown at 10 MW/min.

D. During the ramp a loss of offsite power and a reactor trip occurs. The crew will go to EOP E-0 and then to EOP E-0.1. The crew must start AFW pp 13 or open FCV-95 to establish AFW flow (CT).

E. Crew should re-energize 4kv Bus F by manually closing D/G 13 output breaker 52-HF-7.

F. A S/G 12 tube rupture at 400 gpm will occur 6 minutes after the reactor trip. The crew should determine that Pressurizer level cant be maintained and performs an manual Safety Injection and goes back to E-0 Reactor Trip or Safety Injection.

G. Crew transitions from E-0 to E-3 Steam Generator Tube Rupture and performs ruptured S/G isolation (CT). The crew must close FCV-37 from S/G 12 (CT).

NRCSIM081 01 Appendix D outline Rev 2.doc Rev. 1

ATTACHMENT 1 - SIMULATOR SET-UP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator Init 510 100% power, Mol, CB = 772 per Checklist Integrators: BA - 0 and PW -40 Setup Drill 81 Reset normal engineering values Setup

Start D/G 11 and parallel to Bus F

Cutin Protection relays for D/G 11

Load D/G 11 to 0.5 MW 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 772 and current date, and STP I-1C Attachment 12.4 due in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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 RBU is updated.

o R2B blowdown flows at 90 gpm.

o Operational mode correct for current conditions. 1 o Delta-I target slope matches Delta-I curve SPDS (screens and time updating), A screen RM, B screen SPDS.

The chart recorders are operating properly, and advanced.

Run Chart Recorder program and select all digital chart recorders 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.

1 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.

NRCSIM081 01 Appendix D outline Rev 2.doc Rev. 1

TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION X = manual entry required X 0 min DRILL 6801 After SFM reports the crew has taken the watch, load session MALS, OVRs, etc. by DRILL FILE or MANUALLY (below) 0 min vlv afw7 1,0,0,0,d,xv3i219o FCV-95 fails to open automatically 0 min pmp afw2 1,0,0,0,d,0 AFW pp 13 fails to automatically start 0 min bkr eps15 1,0,0,0,d,0 block auto closure of d/g 13 output bkr 52-hf-7 When D/G 11 mal deg1a act 2,0,5,c,.not.jbkhh7,0 D/G 11 trips on low lube oil press after output bkr 52-HH- ser 0254 act,1,0,5,c,.not.jbkhh7, 52-hh-7 is opened 7 is opened.

X When requested Report D/G 11 local annunciator indicates a Low Lube oil pressure trip.

10 min after D/G xmt rcs132 3,679,0,605, Loop 4 tcold fails high 11 trip c,.not.jbkhh7, X When requested Report that Racks 15 & 16 trouble LEDs are lit.

15 min after Loop plp aux25 act,200,0,900, S/G 12 tube leak at 200 gpd 4 Tcold fails high c,txmt410b(4).gt.675, At 80% power mal syd1 act 1,1,0,c,fnispr.lt.80.0,0 Loss of offsite power and reactor trip mal ppl4b act 0,0,5,c,fnispr.lt.80.0,0 On Safety Mal syd1 act,2,60,30,c,jpplsi Loss of Startup (230 KV) power Injection 6 minutes after mal rcs4b act 400,60,360,c,jpplp4,0 400 gpm SGTR on SG 12 reactor trip X After RX trip Drill 32 N.O. Action on reactor trip X When requested Vlv mss1 2,0,90,200,d,0 Closes FCV-37 locally X When requested Vlv Mfw3 2,0,600,120,d,0 Closes FCV-440 locally NRCSIM081 01 Appendix D outline Rev 2.doc Rev. 1

Drl_6801.txt

NRC L081 sim 01

glh1, 8/18/09

init 510

start d/g 11 and parrallel to bus F, load to 2.5 MW

d/g 11 trips on low lube oil press after 52-hh-7 is opened mal deg1a act 2,0,5,c,.not.jbkhh7,0 ser 0254 act,1,0,5,c,.not.jbkhh7, #alm300b

pt-505 fails at 100% power value

xmt tur2 1,0,0,0,d,0 #pxmtst1(1) per RNF5

loop 4 tcold fails high 10 min after d/g trip xmt rcs132 3,679,0,605,c,.not.jbkhh7, #txmt410b(4)

s/g 12 tube leak at 200 gpd 15 min after tcold fails high plp aux25 act,200,0,900,c,txmt410b(4).gt.675, #wrmssglk(2)

loss of offsite power and reactor trip at 80% power mal syd1 act 1,1,0,c,fnispr.lt.80.0,0 mal ppl4b act 0,0,5,c,fnispr.lt.80.0,0

block auto closure of d/g 13 output bkr 52-hf-7 bkr eps15 1,0,0,0,d,0 #jbkhf7

fcv-95 fails to open automatically vlv afw7 1,0,0,0,d,xv3i219o #rmsf095

afw pp 13 fails to automatically start pmp afw2 1,0,0,0,d,0 #oafp13

400 gpm sgtr on s/g 12 6 min after reactor trip mal rcs4b act 400,60,360,c,jpplp4,0 NRCSIM081 01 Appendix D outline Rev 2.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 Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: Green PROTECTED EQUIPMENT: Train A/B, Bus 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:

ACTIVE SHUTDOWN TECH SPECS / ECGS:

TS 3.8.1.b STP I-1C Att. 12.4 completed 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago TURNOVER ITEMS:

Secure EDG 1-1 per STP M-9A.

OPERABILITY ITEMS:

None PRIORITY ITEMS FOR NEXT SHIFT:

None.

ANNUNCIATORS IN ALARM

PK16-03, 16-09, 16-20, 13-10, 13-15 NRCSIM081 01 Appendix D outline Rev 2.doc Rev. 1

SHIFT FOREMAN TURNOVER COMMENTS:

1. Reactivity management:

a. Time in core life: MOL

b. Power History: At 100%.

c. Boron concentration is 772 ppm from a sample taken 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago.

d. Diluting 40 gallon batches every 2-4 hours. Last dilution was 30 minutes ago.

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 CONTROL ROOM ABNORMAL STATUS See Abnormal Status Board.

NRCSIM081 01 Appendix D outline Rev 2.doc Rev. 1

Appendix D Scenario Outline Form ES-D-1 Facility: Diablo Canyon Scenario No.: 5 Op-Test No.: Jan2010 Examiners: Operators:

Initial Conditions: Operating per OP-L-4. Reactor Power is at 100 percent. EOL 100 ppm CB. High electrical grid demand Turnover: Maintain Power at 100 Percent.

Event Malf. No. Event Event No. Type* Description I (BOP) 1 TS (SRO) PT-455 fails high. (TS) 2 Mal sei1 Seismic event < 0.30gs Turb3 C(ALL) High Turbine Vibration (due to seismic event)

N(BOP) 3 R(ATC) Initiate Ramp to take unit offline.

PK09-13 High bearing temp/vibration > 5 mils on Main Feed pump 4 C(ALL) 11.

C(BOP,SRO) Steam Generator C MFRV (FCV-530) fails closed. (During power 5 T/S (SRO) reduction) Crew can control in manual. (TS)

Auto Reactor Trip SIGNAL on Low-Low S/G level. (FCV-530 fails 6

closed again, and wont reopen)

M(ALL)

Auto trip signal fails & MAN reactor trip from control board unsuccessful. Enter E-0 then FR-S.1 Crew inserts negative Reactivity per Step 4 of FR-S1 (critical task)

Steam Break on MFP turbine steam supply w/MSLI signal failure 7 MSS-4 M(ALL) after emergency boration.

Manually Isolated all S/Gs .prior to transitioning to E-2. (critical task )

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

1. Total malfunctions (5-8) 6

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

3. Abnormal events (2-4) 4

4. Major transients (1-2) 2

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

6. EOP contingencies requiring substantive actions (0-2) 1

7. Critical tasks (2-3) 2 NRCSIM081 05 Appendix D outline Rev 2.doc Rev. 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: LO81 Scenario No.: __5__ Event No.: __1__ Page _1_ of _7_

Event

Description:

____PT-455 pressurizer channel fails high_______________________________

Time Position Applicants Actions or Behavior ATC Identifies pressurizer pressure failing BOP Identifies PORV455C open and manually closes SRO Enter AP-5 Malfunction of Eagle Protection or Control Channel ATC May place Master Pzr Pressure Controller HC-455K in manual ATC Determines PT-455 not selected as control or backup ATC Determines PT-455 not selected as a Recorder input SRO Notifies I&C SRO Recognizes T/S 3.3.1.E & M OTDT, Pressure High/Low Trips SRO Recognizes T/S 3.3.2.L & D S/I & P-11 ESF SRO Recognizes T/S 3.4.11.B1 & 2 (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months )

BOP Closes Block Valve 8000B for Inoperable PORV SRO Directs WCL to remove power to 8000B ATC Returns HC-455K to Auto (if placed in manual)

NRCSIM081 05 Appendix D outline Rev 2.doc Rev. 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: LO81 Scenario No.: __5__ Event No.: __2__ Page _2_ of _7_

Event

Description:

_______Seismic event/High Turbine vibration______________________

Time Position Applicants Actions or Behavior ALL Acknowledge seismic event and determine size SRO Refers to PK12-17 SRO Refer to OP-AP-29 Main Turbine Malfunction BOP Determine Turbine vibration is >5 mils & increasing SRO Notify Predictive Maintenance & System Engineer SRO Evaluate Load Reduction per OP-AP-29 attachment 3.3 if 7mil is exceeded per attachment 3.3.

BOP Reports Seismic computer indicates 0.15g CUE Shift Manager directs that Unit is to be taken offline at 10 MW/min .

NRCSIM081 05 Appendix D outline Rev 2.doc Rev. 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: LO81 Scenario No.: __5__ Event No.: __3__ Page _3_ of _7_

Event

Description:

__Ramp offline per AOP-25________________

Time Position Applicants Actions or Behavior SRO Tailboards ramp SRO Provides oversight for reactivity changes BOP Sets up & commences ramp

Places MW feedback in service.

Set desired Ramp Rate. (10 MW/Min)

Set Target to desired load. (<200 MW)

Commence ramp by Pressing GO ATC Determines required boration and starts borating

Set target Batch on flow controller (40 gallons)

Verify Boric Acid Flow Rate set to desired flow

Start Boration and verify response.

Return controller to auto at conclusion of Batch ATC Turns on Pzr B/U heaters ATC Verifies Rod in Auto and proper overlap while inserting BOP Verify proper DFWCS operation BOP Start stby cnd/bstr set NRCSIM081 05 Appendix D outline Rev 2.doc Rev. 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: LO81 Scenario No.: __5__ Event No.: __4__ Page _4_ of _7_

Event

Description:

______High Vibration on Main Feed Pump 11 ________________

_______________________PK 09-13 Input 573_______________________________________

Time Position Applicants Actions or Behavior SRO Refers to ARP PK09-13.

BOP Determines Vibration is > 5 mil SRO Directs power power rate decrease at 50 to 200MWe/min in accordance with OP-AP-25

Places MW feedback in service.

Set desired Ramp Rate. (10 MW/Min)

Set Target to desired load. (<550 MW)

Commence ramp by Pressing GO BOP Trips Main Feed Pump 11 when < 550MWe NRCSIM081 05 Appendix D outline Rev 2.doc Rev. 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: LO81 Scenario No.: __5__ Event No.: __5__ Page _5_ of _7_

Event

Description:

____Main Feed Regulation Valve fails closed______________________

Time Position Applicants Actions or Behavior BOP Takes Manual control of FCV-530 and restores S/G 13 level to program SRO Refers to T/S 3.7.3, but valve is capable of closing on FWI NRCSIM081 05 Appendix D outline Rev 2.doc Rev. 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: LO81 Scenario No.: __5__ Event No.: __6__ Page _6_ of _7_

Event

Description:

______Auto Trip on Low S/G level fails______________________

Time Position Applicants Actions or Behavior ATC Notes that FCV-530 has went closed, tries to open in manual ATC May try to open FCV-1530 (FCV-530 Bypass)

SRO Directs manual reactor trip ATC Attempts Man Reactor Trip but is unsucessful BOP De-energizes 480v Bus 13D & 13E per E-0 Step 1 RNO BOP Reports that Bus 13E fdr breaker will not open SRO Directs entry into FR-S.1 ATC Manually inserts control rods BOP Trips Turbine BOP Starts AFW pumps ATC/BOP Starts emergency boration by opening 8805A or B (critical task)

ATC/BOP Closes LCV-112B or C ATC Verifies at least 90 gpm charging flow BOP Performs Manual Cnm Vent Isolation by closing valves on VB4 to clear CVI white lights

FCV-678

FCV-679/681 NRCSIM081 05 Appendix D outline Rev 2.doc Rev. 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: LO81 Scenario No.: __5__ Event No.: __7__ Page _7_ of _7_

Event

Description:

______Main Steam Break on Main Feed Pump 11 supply___________ ______

________________________with MSIL signal failure_________________________________

Time Position Applicants Actions or Behavior ALL Recognize excessive steam flow noise ATC Verifies S/I BOP Recognizes Main Steam line isolation failure & manually closes MSIVs per FR-S1 step 13 (critical task)

SRO Verify Reactor remains subcritical and directs transition to E-0.

Performs Appendix E of EOP E-0 BOP

Check Main generator tripped

Verify Containment Isolation Phase A

Verify Containment Vent Isoation

Verify SI status

Verify Fdwtr Isolation

Verify Containment Spray and Phase B - not required

CHECK Main Steamline Isol NOT REQUIRED

Check ECCS flow

Report ESF equipment status to SFM ATC Check AFW status and throttle as needed ATC Check RCS temperature stable or trending to 547 F ATC Check Pzr Safetys, PORVs, and Spray valves closed ATC Check if RCPs should be stopped ATC Check S/Gs not Faulted ATC Check S/Gs not Ruptured ATC Check RCS intact SRO Determines ECCS flow should be reduced ATC Resets SI BOP Resets Vital 4KV auto transfer relays ATC Stops all but one ECCS CCP Terminate Scenario after going to 1 ECCS CCP NRCSIM081 05 Appendix D outline Rev 2.doc Rev. 2

MAJOR EVENT

SUMMARY

AND SCENARIO OBJECTIVES A. PT-455 fails high. Crew closes PCV-455C and refers to AP-5.

B. Seismic event and Main Turbine High Vibration. Crew refers to AP-29 and will ramp offline per Shift Managers direction at 10 MW/min.

C. Crew ramps unit at 10 MW/min per AP-25.

D. VCT level channel LT-112 fails high causing letdown to divert to the LHUTs. Crew goes to AP-19 Malfunction of Reactor Makeup Control System and aligns letdown back to the VCT.

E. MFW pp 11 has high vibration causing Crew to increase ramp to 50 MW/min to 50% power.

At 50% power Crew secures MFW pp 11.

F. After MFW pp trip FCV-530 fails closed in auto, and manual control must be taken on FCV-530 to restore S/G level.

G. FCV-530 and FCV-1530 go closed and can not be re-opened. Crew should initiate a Manual Reactor trip. The Reactor trip breakers and the Feeder breaker for Bus 13E will not open, so the Crew transitions from E-0 to FR S-1 Response to Nuclear Power Generation / ATWS and must insert negative reactivity per step 4 (CT).

H. A steam line break downstream of the MSIVs occurs and the MSL isolation signal will not close the MSIVs. The Crew must manually close the MSIVs (CT). The Crew transitions back to E-O and reduces ECCS flow.

I. The scenario is terminated after going to 1 ECCS charging pump.

NRCSIM081 05 Appendix D outline Rev 2.doc Rev. 2

ATTACHMENT 1 - SIMULATOR SET-UP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator Init 515 100% power, Mol, CB = 47 per Checklist

Integrators: BA - 0 and PW - 500 Setup Drill 81 Reset normal engineering values CONTROL BOARD SETUP Copies of commonly used forms and procedures are available.

Any tags are placed/removed as necessary.

Primary integrator = 500 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 47 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 Operational mode correct for current conditions. 1 o Delta-I target slope matches Delta-I curve 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.

1 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.

NRCSIM081 05 Appendix D outline Rev 2.doc Rev. 2

TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION X = manual entry required X 0 min DRILL 6805 After SFM reports the crew has taken the watch, load session MALS, OVRs, etc. by DRILL FILE or MANUALLY (below) 0 min mal ppl5a act 3,0,0,d,0 ATWS mal ppl5b act 3,0,0,d,0 0 min vlv mss7 1,0,0,0,d,xv3i183c MSIVs wont close in auto vlv mss8 1,0,0,0,d,xv3i184c vlv mss9 1,0,0,0,d,xv4i185c vlv mss10 1,0,0,0,d,xv4i186c 0 min ovr xv5i239o act,0,0,0,d,0 52-HE-4 for 13E breaker wont trip 0 min cnv mfw11 1,0,0,0,d,0 FCV-1530 wont open 3 min xmt pzr15 3,2642,0,180,d,0 PT-455 fails high X When requested Dsc pzr2 act, 0,0,0,d,0 Opens breaker for 8000B 10 minutes PT- mal sei1 act 0.15,10,600, Seismic at 0.15g 455 failure c,pxmtpzr(1).gt.2400, On Seismic mal tur3c act 7.5,60,0,c,jmlsei1, Turbine bearing 3 high vibration 5 min after ramp xmt cvc19 3,100,60,300,c,ggo, LT-112 fails high starts 10 minutes after mal mfw2a act 7,60,600, MFW pp 11 high vibration LT-112 failure c, bxmtl112.gt.90, After MFW pp 11 cnv mfw5 2,0,60,120, FCV-530 fails closed in auto, failure clears trip c,xv3o195g,ftd530_man when FCV-530 taken to manual When FCV-530 in bst aux1 1,0,0,600, c,ftd530_man,0 Starts 10 minute instructor timer to activate manual second failure of FCV-530 10 min after FCV- c jistbst1, cnv mfw5 2,0,60,0,d,0 FCV-530 fails closed again, and wont re-530 taken to man. open 2 min after LCV- mal mss4 act Main steam line break outside containment 112B or C is 1e+07,120,120,c,xv2o232g.or.xv2o closed 231g, DO NOT OPEN REACTOR TRIP BREAKERS UNTIL BORATION STARTED IN FR S-1 STEP 4.

X When requested Mal ppl5a clr Opens reactor trip breakers Mal ppl5b clr NRCSIM081 05 Appendix D outline Rev 2.doc Rev. 2

Drl_6805.txt

NRC L081 SCENARIO 05

GLH1, 12/3/9

mal PPL5A REACTOR TRIP BREAKER RTA FAILURE TO OPEN (TRAIN A) mal ppl5a act 3,0,0,d,0

mal PPL5B REACTOR TRIP BREAKER RTB FAILURE TO OPEN (TRAIN B) mal ppl5b act 3,0,0,d,0

VLV MSS7 MAIN STEAM ISO VLV 1 #rmsf041 vlv mss7 1,0,0,0,d,xv3i183c #rmsf041

VLV MSS8 MAIN STEAM ISO VLV 2 #rmsf042 vlv mss8 1,0,0,0,d,xv3i184c #rmsf042

VLV MSS9 MAIN STEAM ISO VLV 3 #rmsf043 vlv mss9 1,0,0,0,d,xv3i185c #rmsf043

VLV MSS10 MAIN STEMA ISO VLV 4 #rmsf044 vlv mss10 1,0,0,0,d,xv3i186c #rmsf044

ovr VB5121E 52 HE 4 TRIP & RESET XV5I239O #xv5i239 ovr xv5i239o act,0,0,0,d,0 #vb5121e

XMT PZR15 PZR PRESS #pxmtpzr(1) xmt pzr15 3,2642,0,180,d,0 #pxmtpzr(1)

mal SEI1 SEISMIC ACTIVITY mal sei1 act 0.15,10,600,c,pxmtpzr(1).gt.2400,

mal TUR3C TURBINE VIBRATION (BEARING # 3) mal tur3c act 7.5,60,0,c,jmlsei1,

XMT CVC19 VCT 1-1 LEVEL, ALM0341, SPDS, LI-112 #bxmtl112 xmt cvc19 3,100,60,300,c,ggo, #bxmtl112

mal MFW2A MAIN FEEDWATER PUMP 1-1 VIBR ALARM AND TRIP mal mfw2a act 7,60,600,c,bxmtl112.gt.90,0

CNV MFW5 MAIN FEEDWATER REG. VALVE #rfwf530 cnv mfw5 2,0,60,120,c,xv3o195g,ftd530_man #rfwf530

CNV MFW11 FEEDWATER REG. BYPASS VALV #rfwfrbv(3) cnv mfw11 1,0,0,0,d,0 #rfwfrbv(3)

instructor bistable for timing of 2nd FCV-530 failure bst aux1 1,0,0,600, c,ftd530_man,0 #jistbst1

fails fcv-530 closed 10 min after taking to manual tc jistbst1, cnv mfw5 2,0,60,0,d,0

mal MSS4 STEAMLINE BREAK OUTSIDE CONTAINMENT (DOWNSTEAM OF MSIV) mal mss4 act 1e+07,120,120,c,xv2o232g.or.xv2o231g, NRCSIM081 05 Appendix D outline Rev 2.doc Rev. 2

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: 523 Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: Green PROTECTED EQUIPMENT: Train A/B, Bus 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:

ACTIVE SHUTDOWN TECH SPECS / ECGS:

None.

TURNOVER ITEMS:

None OPERABILITY ITEMS:

None PRIORITY ITEMS FOR NEXT SHIFT:

Hold at 100% power, high electrical demand on system ANNUNCIATORS IN ALARM

None

SHIFT FOREMAN TURNOVER COMMENTS:

1. Reactivity management:

a. Time in core life: EOL

b. Power History: At 100%.

c. Boron concentration is 47 ppm from a sample taken 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago. BAST at 7500 ppm.

d. Use Deborating demin for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months every shift. Last time in service was 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago.

e. Delta I is stable.

2. No one is in Containment, no entries are expected

3. U-2 is operating at 100% power COMPENSATORY MEASURES:

None CONTROL ROOM ABNORMAL STATUS See Abnormal Status Board.

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Diablo Canyon Scenario No.: 3 Op-Test No.: L081-3 Examiners: Operators:

Initial Conditions: 100% Power, MOL, 772 ppm CB Turnover: PRA Status: Green. Protected Equipment - Train A/B, Buses F,G& H, Prot. Sets I,II, III, IV. AFW pp 11 cleared due to bearing replacement. U-2 at 100% power. Swap ASW trains after watch is taken.

Event Malf. No. Event Event Description and Time Line No. Type*

1 N (BOP) Swaps ASW pp trains.

2 Pmp asw2 C (SRO, ASW pp 12 trip 5 minutes after train swap (TS 3.7.8.A), ASW pp 11 doesnt auto BOP) start.

Pmp asw1 3 Dsc rod1 I (ATC) Loss of power to DRPI (TS 3.1.7.B)

I ( SRO) 4 Ser 0829 C (All) Loss of Main Transformer cooling.

R (ATC) 5 mal rcs4d M (All) S/G 14 tube rupture during ramp. Requires manual Safety Injection (CT) mal ppl3a mal ppl3b 6 Mal syd1 M Loss of Startup power on unit trip.

7 Pmp cvc1 C (BOP) Both Charging pumps fail to start after transfer to D/G. (CT)

Pmp cvc2 8 Vlv pzr C (All) Pzr PORV and block valve stick open after S/G isolation (CT) in EOP E-3.

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

1. Total malfunctions (5-8) 6

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

3. Abnormal events (2-4) 3

4. Major transients (1-2) 1

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

6. EOP contingencies requiring substantive actions (0-2) 1

7. Critical tasks (2-3) 3 NRCSIM081 03 Appendix D outline Rev 2.doc Rev. 2

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: L081-3 Scenario No.: 3 Event No.: 1 Page 1 of 6 Event

Description:

Swaps ASW pp trains Time Position Applicants Actions or Behavior SRO Directs Swap of ASW train from HX 11 to HX 12 per OP E-5:IV

Has intake watch secure continuous chlorination to the in-service ASW BOP suction bay

Advise U2 Control Room to place the U2 standby ASW pump in "MANUAL",

BOP to prevent a possible auto-start.

Place the Mode Selector Switch for the standby ASW pump 12 in BOP "MANUAL"

Place the Control Switch for the standby ASW pump 12 in "START", to start BOP the pump

OPEN the CCW HX 12 saltwater inlet valve FCV-603 on the HX being BOP placed in service.

OPEN the CCW HX 12 shell-side outlet valve FCV-431 on the HX being BOP placed in service.

CLOSE the CCW HX 11 shell-side outlet valve FCV-430 on the HX being BOP placed in standby

CLOSE the CCW HX 11 saltwater inlet valve FCV-602 on the HX being BOP placed in standby.

BOP

SHUT DOWN ASW pump 11.

BOP

place the Mode Selector Switch for ASW pump 11 in "AUTO".

Advise U2 Control Room that the U2 standby ASW pump can be placed in BOP "AUTO".

BOP

Place in service continuous chlorination to the in-service ASW suction bay NRCSIM081 03 Appendix D outline Rev 2.doc Rev. 2

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: L081-3 Scenario No.: 3 Event No.: 2 Page 2 of 6 Event

Description:

ASW pp 12 trips on overcurrent Time Position Applicants Actions or Behavior CO Acknowledge alarm PK 01-03, Input 427, Aux Salt Water Pump OC Trip.

CO/BOP Diagnose Aux Salt Water Pump 1-2 tripped on Over Current.

SRO Responds per Annunciator Response Procedure PK 01-03 (May refer to OP AP-10).

SRO

Directs Starting of Standby ASW Pump 1-1.

BOP

Starts ASW Pump 1-1 BOP

Verifies CCW-ASW HX DP is within limits.

BOP

Direct continuous chlorination to be secured.

BOP

Dispatch operator to investigate failure.

SRO

Directs Maintenance to investigate failure of ASW pump 1-2

Refers to Tech Spec 3.7.8 ASW System Condition A (72 Hour completion SRO time with 1 train inoperable)

NRCSIM081 03 Appendix D outline Rev 2.doc Rev. 2

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: L081-3 Scenario No.: 3 Event No.: 3 Page 3 of 6 Event

Description:

Loss of Power to DRPI Time Position Applicants Actions or Behavior ATC/BOP Diagnose loss of power to DRPI Note: PK03-21 may be referred to first ATC Refers to PK03 PPC Rx Alarm Axial Flux/Rod Position SRO Step 2.2.2.d - Directs N.O. to place DRPI on B/U power per OP A-3:I ATC Refers to PK03 DRPI Failure/Rod Bottom ATC Places control rods in manual SRO Refer to Tech Specs 3.1.7.B If not done as part of PK03-25, step 2.1.3 - Directs N.O. to place DRPI on B/U power SRO per OP A-3:I ATC Returns control rods to Auto after restoration of DRPI NRCSIM081 03 Appendix D outline Rev 2.doc Rev. 2

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: L081-3 Scenario No.: 3 Event No.: 4 Page 4 of 6 Event

Description:

Loss of Main Transformer Bank Cooling Time Position Applicants Actions or Behavior CO Acknowledge alarm PK 14-21, Input 829, Mn Bk Xfmr Annun and UV.

SRO Dispatches operator to investigate local alarms Operator reports that NO cooling fans or oil pumps are running on Main Bank C Transformer.

Directs power reduction at 50 MW per minute per direction in AR PK14-21 using OP SRO AP-25, "Rapid Load Reduction or Shutdown,"

ATC Commences ramp to take unit offline at 50 MW/min

Places MW feedback in service.

Set desired Ramp Rate. (10 MW/Min)

Set Target to desired load. (<200 MW)

Commence ramp by Pressing GO ATC Verifies Control Rods Inserting in AUTO ATC Turns PZR Backup Heaters - ON ATC Borates the RCS using the Reactivity Handbook to determine the quantity of boric acid to add.

Set target Batch on flow controller (40 gallons)

Verify Boric Acid Flow Rate set to desired flow

Start Boration and verify response.

Return controller to auto at conclusion of Batch As time permits:

BOP When < 35% Rx power, shutdown MFW Pp 12 BOP When < 35% Rx power, shutdown the No. 2 Heater Drip Pump BOP When < 35% Rx power, shutdown down all but one Cnd/Bstr pump set BOP Reset the MSRs per OP C-5:III NRCSIM081 03 Appendix D outline Rev 2.doc Rev. 2

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: L081-3 Scenario No.: 3 Event No.: 5 &6 Page 5 of 6 Event

Description:

SGTR and Loss of Startup power Time Position Applicants Actions or Behavior SRO Responds to AR PK11-18 and/or PK11-06 SRO Diagnoses S/G tube rupture; may enter AP-3.

SRO/BOP Starts 2nd CCP per AP-3 SRO/BOP Isolates letdown flow (close 8149C and LCV-459/460) per AP-3 ATC Determines leak too large to maintain Pzr level SRO Directs SI ATC Performs Manual Safety Injection** (CT)

ALL Perform immediate actions of E-0 Reactor Trip or Safety Injection

VERIFY reactor tripped

VERIFY turbine tripped

VERIFY vital 4kV buses energized

CHECK SI - Actuated 4KV vital busses transfer to Diesel Generator due to loss of Startup Power Performs Appendix E of EOP E-0

Check Main generator tripped

Verify Containment Isolation Phase A

Verify Containment Vent Isoation

Verify SI status

Verify Fdwtr Isolation

Verify Containment Spray and Phase B - not required

CHECK Main Steamline Isol NOT REQUIRED

Check ECCS flow BOP/ATC

Report ESF equipment status to SFM

Check Excess letdown not in service

Turn on Aux Bldg Vent Charcoal Filter Preheater

Check Secondary System Status

Check Aux Bldg and Control Room Ventilation status

Check Diesel Generator Status

Verify Battery Chargers supplying Vital Batteries

Isolate reheat steam to MSRs

Maintain Seal Injection flow 8-13 gpm

Notify SFM Appendix E is complete BOP/ATC Closes MSIVs per Appendix E

- Critical Task NRCSIM081 03 Appendix D outline Rev 2.doc Rev. 2

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: L081-3 Scenario No.: 3 Event No.: 7&8 Page 6 of 6 Event

Description:

Charging pumps fail to start & Pzr PORV and Block Valve sticks open Time Position Applicants Actions or Behavior BOP Determines Charging pumps 11 & 12 did start after transfer to Diesel , and starts both Charging pumps. ** (CT)

ATC Throttles AFW flow as directed by SRO.

ATC Check RCS temperature stable or trending to 547 F ATC Check Pzr Safetys, PORVs, and Spray valves closed ATC Check if RCPs should be stopped ATC Check S/Gs not Faulted SRO May direct early isolation of S/G 1-4 SRO Determines S/G 1-4 is ruptured and recognizes procedure transition criteria met ALL Implements F-0; monitors CSFSTs SRO Directs transition to E-3 ATC/BOP Isolates S/G 14 ** (CT)

ATC/BOP

Sets 10% steam dump to 8.67 turns ATC/BOP

Isolates S/G 1-4 MSIV (may be closed in Appendix E)

ATC/BOP

Isolates AFW flow when S/G level > 15%

SRO Determines cooldown target temperature BOP Determines that PORV used to depressurize has stuck open and tries to close PORV and block valve.

SRO Determines that since PORV AND Associated Block Valve CANNOT be Closed, that a transition to EOP ECA-3.1 is required.

SRO Transitions to ECA 3.1 ATC Resets SI ATC Resets Both Trains of Containment Isolation Phase A BOP Opens FCV-584 to establish Instrument Air to Containment SRO Directs cooldown to cold shutdown using 10% steam dumps, maintaining cooldown rate in RCS Cold Legs - LESS THAN 100°F in any ONE HOUR period Terminate Scenario after Cooldown is commenced.

- Critical Task NRCSIM081 03 Appendix D outline Rev 2.doc Rev. 2

MAJOR EVENT

SUMMARY

AND SCENARIO OBJECTIVES A. Swaps ASW trains per OP E-5:IV Swapping pumps for HXs during single CCW HX operation.

B. ASW Pump 12 trips on over current. Crew restarts ASW pp 11 per AR PK01-03.

C. Loss of power to DRPI. ATC takes manual control of rods and crew enters either PK03-21 or PK03-25 to address the power failure and restore power to DRPI.

D. PK 14-21 MAIN TRANSF alarms. Report from plant operator indicates that all forced cooling has been lost to MTB C. Crew commences ramp at 50 MW/min to take unit offline using AP-25 Rapid Load Reduction or Shutdown.

E. During the ramp a S/G tube rupture occurs on S/G 14. Crew enters AP-3 Steam Generator Tube Failure and determines Pressurizer level cant be maintained and performs an manual Safety Injection (CT) and goes to E-0 Reactor Trip or Safety Injection.

F. After the Unit trip, Startup power is lost and vital 4KV buses transfer to Diesel Generators.

G. Both CCPs fail to restart on the transfer and must be manually restarted (CT).

H. Crew transitions from E-0 to E-3 Steam Generator Tube Rupture and performs ruptured S/G isolation (CT). When crew tries to depressurize RCS, the PORV and associated Block valve stick open.

I. Crew transitions to ECA 3.1 SGTR With Loss of Reactor Coolant -Subcooled Recovery Desired, Scenario is terminated after commencing RCS cooldown.

NRCSIM081 03 Appendix D outline Rev 2.doc Rev. 2

ATTACHMENT 1 - SIMULATOR SET-UP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator Init 510 100% power, Mol, CB = 772 per Checklist

Integrators: BA - 0 and PW -40

Tags: FCV-95 Setup Drill 81 Reset normal engineering values Setup Drill 40 Clears TDAFW pp 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 1185 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 Operational mode correct for current conditions. 1 o Delta-I target slope matches Delta-I curve 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.

1 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.

NRCSIM081 03 Appendix D outline Rev 2.doc Rev. 2

TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION X = manual entry required X 0 min DRILL 6803 After SFM reports the crew has taken the watch, load session MALS, OVRs, etc. by DRILL FILE or MANUALLY (below) 0 min Mal ppl3a act,1,0,0,d,0 Fails Auto SI Mal ppl3b act,1,0,0,d,0 0 min Pmp asw1 1,0,0,0,d,0 ASW pp 11 doesnt auto start 5 minutes after Pmp asw2 6,10,1,300,c,xv1o242g ASW pp 12 trips on overcurrent ASW pp 11 s/d X When requested Report ASW pp 12 motor terminal box has blown off, B and C phase OC flags dropped at breaker 10 min after ASW Dsc rod1 act,0,0,600,c,xv1o243b Loss of normal power to DRPI pp 12 trip X When requested Report that DRPI transformer looks fine, but 52-1F-45 is tripped.

X When requested Dsc eps17 act,1,0,0,d,0 Closes DRPI b/u breaker and transfers DRPI to transfer Loa eps1 act,1,0,0,d,0 pwr supply to b/u DRPPI to B/U 10 min from rods Ser 0829 act,1,0,600,c,xc1i085f PK14-21 #0829 for MTB local annunciator in manual X When requested Report that NO cooling fans or oil pumps are running on Main Bank C Transformer. If asked Oil and Winding Temperatures 95 C and slowing rising.

12 minutes after Mal rcs4d act,400,150,720,c,ggo 400 gpm SGTR on SG 14 ramp started On Safety Mal syd1 act,2,60,30,c,jpplsi Loss of Startup (230 KV) power Injection Pmp cvc1 1,0,0,0,c,jpplsi CCP 11 and 12 fail to auto start after bus Pmp cvc2 1,0,0,0,c,jpplsi transfer to diesel.

X After RX trip Drill 32 N.O. Action on reactor trip If manually Vlv pzr4 2,1,0,3,c,xv2i205o Fails PCV-455C open opened Vlv pzr5 2,1,0,3,c,xv2i206o Fails PCV-456 open Vlv pzr6 2,1,0,3,c,xv2i204o Fails PCV-474 open When associated Vlv pzr1 2,1,0,0,c, xv2i204o Fails 8000A open when PCV-474 opened PORV is manually opened Vlv pzr2 2,1,0,0,c, xv2i205o Fails 8000B open when PCV-455C opened Vlv pzr3 2,1,0,0,c, xv2i206o Fails 8000C open when PCV-456 opened NRCSIM081 03 Appendix D outline Rev 2.doc Rev. 2

Drl_6803.txt

NRC L081 scenario #3

glh1, 10/21/2009

init 510

fail auto si Mal ppl3a act,1,0,0,d,0 Mal ppl3b act,1,0,0,d,0

ASW pp 11 doesnt auto start Pmp asw1 1,0,0,0,d,0

ASW pp 12 trips on overcurrent Pmp asw2 6,10,1,300,c,xv1o242g

Loss of power to DRPI Dsc rod1 act,0,0,600,c,xv1o243b

PK14-21 #0829 for MTB local annunciator Ser 0829 act,1,0,600,c,xc1i085f

400 gpm SGTR on SG 14 Mal rcs4d act,400,150,720,c,ggo

Loss of Startup (230 KV) power Mal syd1 act,2,60,30,c,jpplsi

CCP 11 and 12 fail to auto start after bus transfer to diesel.

Pmp cvc1 1,0,0,0,c,jpplsi Pmp cvc2 1,0,0,0,c,jpplsi

Fails PCV-455C open Vlv pzr4 2,1,0,3,c,xv2i205o

Fails PCV-456 open Vlv pzr5 2,1,0,3,c,xv2i206o

Fails PCV-474 open Vlv pzr6 2,1,0,3,c,xv2i204o

Fails 8000A open when PCV-474 opened Vlv pzr1 2,1,0,0,c, xv2i204o

Fails 8000B open when PCV-455C opened Vlv pzr2 2,1,0,0,c, xv2i205o

Fails 8000C open when PCV-456 opened Vlv pzr3 2,1,0,0,c, xv2i206o NRCSIM081 03 Appendix D outline Rev 2.doc Rev. 2

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 Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: Green PROTECTED EQUIPMENT: Train A/B, Bus 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:

ACTIVE SHUTDOWN TECH SPECS / ECGS:

AFW pp 11 cleared due to bearing replacement - LCO 3.7.5 Condition B.

TURNOVER ITEMS:

Swap ASW pump 11 to pump 12 and HX 11 to HX 12 per OP E-5:IV OPERABILITY ITEMS:

None PRIORITY ITEMS FOR NEXT SHIFT:

None.

ANNUNCIATORS IN ALARM

None

SHIFT FOREMAN TURNOVER COMMENTS:

1. Reactivity management:

a. Time in core life: MOL

b. Power History: At 100%.

c. Boron concentration is 772 ppm from a sample taken 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago.

d. Diluting 40 gallon batches every 2-4 hours. Last dilution was 30 minutes ago.

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 CONTROL ROOM ABNORMAL STATUS See Abnormal Status Board.

ML102300236

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