ML102300250

DC-2010-01-Draft Operating Test

ML102300250
Person / Time
Site:	Diablo Canyon
Issue date:	08/18/2010
From:	Apger G Operations Branch IV
To:	Pacific Gas & Electric Co
References
Download: ML102300250 (186)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ____Diablo Canyon_________________

Date of Examination: ___1/11/2010_

Examination Level: RO SRO Operating Test Number: __L081____

Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations N, R Determine Boration/Dilution requirement for a power increase.

G 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9)

Conduct of Operations D, R Estimate Heat Up Rate (LJC-014)

G 2.1.2 Knowledge of operator responsibilities during all modes of plant operation. (4.1)

Equipment Control N, R Review a tagout for a CCP G 2.2.13 Knowledge of tagging and clearance procedures (4.1)

Radiation Control N, R Calculate Maximum Stay Time G 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (3.2)

Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

A3 and A4 are RO/SRO

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ____Diablo Canyon_________________

Date of Examination: ___1/11/2010_

Examination Level: RO SRO Operating Test Number: __L081____

Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations N, R Determine the correct number of shift staffing during refueling operations.

G 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. (3.9)

Conduct of Operations N, R Review Operator Logs G 2.1.3 Knowledge of shift or short-term relief turnover practices. (3.9)

Equipment Control N, R Review tagout of CCP G 2.2.13 Knowledge of tagging and clearance procedures (4.3)

Radiation Control N, R Calculate Maximum Stay Time G 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (3.7)

Emergency Procedures/Plan N, R Emergency event classification G 2.4.41 Knowledge of the emergency action level thresholds and classifications. (4.6)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE JOHN P. LYLEED HURST AUTHOR:

GARY HUTCHISON DATE:

10/16/09 REV. 0 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

JPM TITLE: DETERMINE DILUTION REQUIREMENTS FOR A POWER INCREASE JPM NUMBER:

NRCL081LJA_ROA1 INSTRUCTOR WORKSHEET NRCL081LJA_ROA1.

DOC PAGE 2 OF 6 REV. 0 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 Reactivity Briefing Sheet.

Task Standard:

Operator determines that 230 (+/- 2 ) gallons of primary water is required.

JPM TITLE: DETERMINE DILUTION REQUIREMENTS FOR A POWER INCREASE JPM NUMBER:

NRCL081LJA_ROA1 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

NRCL081LJA_ROA1.

DOC PAGE 3 OF 6 REV. 0 Start Time:

Step Expected Operator Actions

1.

Operator obtains correct procedure 1.1 Operator obtains Reactivity Briefing Sheet.

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

2.

• • Calculates reactivity from change in power 2.1 Operator determines that power coefficient is -12.57 pcm/% power. **

2.2 Operator determines PCM for 5%

increase in power. (-62.85 pcm) **

Step was: Sat: _______ Unsat _______*

3.

• • Calculates reactivity from change in rod position 3.1 Operator determines PCM for Control Bank D at 210 steps. (28 pcm) **

3.2 Operator determines PCM for Control 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 _______*

JPM TITLE: DETERMINE DILUTION REQUIREMENTS FOR A POWER INCREASE JPM NUMBER:

NRCL081LJA_ROA1 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

NRCL081LJA_ROA1.

DOC PAGE 4 OF 6 REV. 0 Step Expected Operator Actions

4.

• • Calculates reactivity left after accounting change in rod position.

4.1 Accounts for reactivity from change in rods position on total reactivity from change in power. (-62.8 + 31.8 =

-31.05 pcm)**

Step was: Sat: _______ Unsat _______*

5.

• • Determines % power change from reactivity associated with dilution.

5.1 Determines that 2.47 % power change is left to dilution water. (-31.05 pcm/

-12.57 pcm/% power)**

Step was: Sat: _______ Unsat _______*

6.

• • Determines amount of primay water to add.

6.1 Determines that 230 (+/- 2 ) gallons of primary water is required. (2.47%

• 93 gal/% = 230 gallons) **

Step was: Sat: _______ Unsat _______*

Stop Time:

Total Time:

(Enter total time on the cover page)

JPM TITLE: DETERMINE DILUTION REQUIREMENTS FOR A POWER INCREASE JPM NUMBER:

NRCL081LJA_ROA1 ANSWER KEY NRCL081LJA_ROA1.

DOC PAGE 5 OF 6 REV. 0 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 Reactivity Briefing Sheet.

Answer Key Operator determines that 230 (+/- 2 ) gallons of primary water is required.

EXAMINEE CUE SHEET JPM NUMBER:

NRCL081LJA_ROA1 NRCL081LJA_ROA1.

DOC PAGE 6 OF 6 REV. 0 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 Reactivity Briefing Sheet.

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE AUTHOR:

GARY HUTCHISON DATE:

10/22/09 REV.0 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.

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:

STA, SRO Task Number:

43600.084 Rating:

3.8

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

NRCL081LJA-ROA2 INSTRUCTOR WORKSHEET NRCL081LJA_ROA2.DOC PAGE 2 OF 5 REV.0 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.

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

NRCL081LJA-ROA2 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJA_ROA2.DOC PAGE 3 OF 5 REV. 0 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 load.

2.1 From the Predicted Heat 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 _______*

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

NRCL081LJA-ROA2 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJA_ROA2.DOC PAGE 4 OF 5 REV. 0 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 reach 200°F.

4.1 Calculates current temperature 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)

JPM NUMBER:

NRCL081LJA-ROA2 EXAMINEE CUE SHEET NRCL081LJA_ROA2.DOC PAGE 5 OF 5 REV. 0 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.

Loss of Residual Heat Removal U1&2 OP AP SD-5 REV. 9A PAGE 5 OF 6 02 opapsd5.DOC 1022.1402 Page 5 of 7 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

Loss of Residual Heat Removal U1&2 OP AP SD-5 REV. 9A PAGE 6 OF 6 02 opapsd5.DOC 1022.1402 Page 6 of 7 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 SG Tubes Voided NO Nozzle Dams Installed AND 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

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE AUTHOR:

GARY HUTCHISON DATE:

11/04/2009 REV.0 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

JPM TITLE: REVIEW A TAGOUT FOR A CCP JPM NUMBER: NRCL081LJA-ROA3 INSTRUCTOR WORKSHEET NRCL081LJA_ROA3.

DOC PAGE 2 OF 6 REV. 0 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.

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

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

NRCL081LJA_ROA3.

DOC PAGE 3 OF 6 REV. 0 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:

MAN-ON-LINE (M)

CAUTION (C)

CONTROL BOARD CAUTION (CBC)

POSITIONS:

RACKED OUT (RO)

RACKED IN (RI)

CLOSED (CL)

OPEN (OP)

Step was: Sat: _______ Unsat _______*

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

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

NRCL081LJA_ROA3.

DOC PAGE 4 OF 6 REV. 0 Step Expected Operator Actions

2.

• • Identify Auxiliary Feedwater Pump 1-2 clearance errors.

2.1 Operator determines point #3 tag should be a MAN-ON-LINE tag.

2.2 Determines point #4 FW-2-169 Position should be CLOSED (CL).

2.3 Determines point #6 valve FW-2-191 should be FW-2-173 for AFW Pp 2-2.

Step was: Sat: _______ Unsat _______*

Stop Time:

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

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

NRCL081LJA-ROA3 ANSWER SHEET NRCL081LJA_ROA3.

DOC PAGE 5 OF 6 REV. 0 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

JPM TITLE:

JPM NUMBER:

NRCL081LJA-ROA3 EXAMINEE CUE SHEET NRCL081LJA_ROA3.

DOC PAGE 6 OF 6 REV. 0 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

Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure AUTHOR:

SEAN CURRIE DATE:

05/24/2009 REV. 0 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 K/A:

G 2.3.4; Knowledge of radiation exposure limits under normal or emergency conditions.

Rating:

3.2

JPM

Title:

Stay Time Determination JPM Number: NRCL081LJA-ROA4 Instructor Worksheet NRCL081LJA_ROA4.doc Page 2 of 5 REV. 0 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 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

JPM

Title:

Stay Time Determination JPM Number: NRCL081LJA-ROA4 Instructor Worksheet NRCL081LJA_ROA4.doc Page 3 of 5 REV. 0 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 Limits for TEDE 2.1 Determines DCPP Administrative Limit 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 <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> ACCEPTABLE TIME: 4.1 - 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time:

(Enter total time on the cover page)

JPM

Title:

Stay Time Determination JPM Number: NRCL081LJA-ROA4 ANSWER KEY NRCL081LJA_ROA4.doc Page 4 of 5 REV. 0 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 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 <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />

JPM Number: NRCL081LJA-ROA4 Examinee Cue Sheet NRCL081LJA_ROA4.doc Page 5 of 5 REV. 0 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 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

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE JOHN P. LYLEED HURST AUTHOR:

GARY HUTCHISON DATE:

10/19/09 REV. 0 Number:

NRCL081LJA_SROA1

Title:

DETERMINE SHIFT STAFFING DURING REFUELING OPERATIONS Examinee:

Evaluator:

Print Signature Date Results:

Sat Unsat Total Time:

minutes Comments:

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 Task Number:

G2.1.3 Rating:

3.9

JPM TITLE: DETERMINE SHIFT STAFFING DURING REFUELING OPERATIONS JPM NUMBER:

NRCL081LJA_SROA1 INSTRUCTOR WORKSHEET NRCL081LJA_SROA1

.DOC PAGE 2 OF 8 REV. 0 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 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.

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.

JPM TITLE: DETERMINE SHIFT STAFFING DURING REFUELING OPERATIONS JPM NUMBER:

NRCL081LJA_SROA1 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

NRCL081LJA_SROA1

.DOC PAGE 3 OF 8 REV. 0 Start Time:

Step Expected Operator Actions

1.

Operator reviews shift watch list 1.1 Operator reviews shift logs for completeness and accuracy.

Step was: Sat: _______ Unsat _______*

2.

• • Determines errors with staffing 2.1 Determines that U1 Work Control Lead can not be TS/Eplan and Ops Responder (OR).**

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)

JPM TITLE: DETERMINE SHIFT STAFFING DURING REFUELING OPERATIONS JPM NUMBER:

NRCL081LJA_SROA1 ANSWER KEY NRCL081LJA_SROA1

.DOC PAGE 4 OF 8 REV. 0 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 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.

EXAMINEE CUE SHEET JPM NUMBER:

NRCL081LJA_SROA1 NRCL081LJA_SROA1

.DOC PAGE 5 OF 8 REV. 0 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

JPM TITLE: DETERMINE SHIFT STAFFING DURING REFUELING OPERATIONS JPM NUMBER: NRCL081LJA_SROA1 STUDENT HANDOUT NRCL081LJA_SROA1

.DOC PAGE 6 OF 8 REV. 0 Hand the following two pages to examinee

69-20533

.1 NRCL081LJA_SROA1

.DOC PAGE 7 OF 8 REV. 0 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 (Optional)

JANES JR, RICHARD X

X 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 Shift Watch List

69-20533

.1 NRCL081LJA_SROA1

.DOC PAGE 8 OF 8 REV. 0 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

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE JOHN P. LYLEED HURST AUTHOR:

GARY HUTCHISON DATE:

10/29/09 REV. 0 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

JPM TITLE: REVIEW OPERATOR LOGS JPM NUMBER:

NRCL081LJA_SROA2 INSTRUCTOR WORKSHEET NRCL081LJA_SROA2

.DOC PAGE 2 OF 7 REV. 0 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from loss of Bus.

JPM TITLE: REVIEW OPERATOR LOGS JPM NUMBER:

NRCL081LJA_SROA2 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

NRCL081LJA_SROA2

.DOC PAGE 3 OF 7 REV. 0 Start Time:

Step Expected Operator Actions

1.

Operator reviews shift logs 1.1 Operator reviews shift logs for completeness and accuracy.

Step was: Sat: _______ Unsat _______*

2.

• • Determines time PORV taken to close greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 2.1 Determines that PCV-455C was not taken to close within one hour of block valve 8000B being inoperable as required in TS 3.4.11.C.1. **

Step was: Sat: _______ Unsat _______*

Stop Time:

Total Time:

(Enter total time on the cover page)

EXAMINEE CUE SHEET JPM NUMBER:

NRCL081LJA_SROA2 NRCL081LJA_SROA2

.DOC PAGE 4 OF 7 REV. 0 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.

JPM TITLE: REVIEW OPERATOR LOGS JPM NUMBER: NRCL081LJA_SROA2 STUDENT HANDOUT NRCL081LJA_SROA2

.DOC PAGE 5 OF 7 REV. 0 Hand the following two pages to examinee

Diablo Canyon Power Plant Operations Shift Log Unit 1 Today - Dayshift 69-20533 10/03/2006.1 NPG has operated 18 days without a critical equipment event.

NPG has gone 193 days without a plant event.

Unit 1 Days at Power: 10 Days Operating Mode: 1 Power Level: 100%

Gross Generation: 1178 MWe 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

Time Entry User User Type 7:09 Power Range NIs 100.2 Calorimetric Power 99.6 Generator MW 1177.6 Bank 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; 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 GLH1 CO 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 gpm 9:36 Commenced Discharge of LDT 0-1 @ 83%. Batch # 2009-0-109. SCARP Sheldon informed BCS1 AUXSR 11:15 Chemistry Technician B. Leasburg reports U1 RCS Boron Conc. = 1260 ppm.,

Sample taken @ 0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br />. A 30 minute Cation Bed run is not requested bcl6 CHEM SCARP 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 burnt insulation smell at breaker.

RNF5 USFM 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 69-20533 10/03/2006.1 Log Entries Page 2

Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure AUTHOR:

SEAN CURRIE DATE:

05/24/2009 REV. 0 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

JPM

Title:

Classify a Loss of Shutdown Cooling Event JPM Number: NRCL081LJA-SROA5 Instructor Worksheet NRCL081LJA_SROA5.doc Page 2 of 5 REV. 0 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.

JPM

Title:

Classify a Loss of Shutdown Cooling Event JPM Number: NRCL081LJA-SROA5 Instructor Worksheet NRCL081LJA_SROA5.doc Page 3 of 5 REV. 0 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 Action Level 2.1 Determines that the Cold SD/Refuel System Malfunction/Loss of Power C.1 is an ALERT (CA1.1) 2.2 Determines that the Cold SD/Refuel System Malfunction/RCS Temperature C.3 is an UNUSUAL EVENT (CU3.1)

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

JPM

Title:

Classify a Loss of Shutdown Cooling Event JPM Number: NRCL081LJA-SROA5 Answer Key NRCL081LJA_SROA5.doc Page 4 of 5 REV. 0 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.

The Cold SD/Refuel System Malfunction/RCS Temperature C.3 is an UNUSUAL EVENT (CU3.1) due to RCS temperature exceeding 200F EVENT CLASSIFICATION IS: ALERT (CA1.1)

JPM Number: NRCL081LJA-SROA5 Examinee Cue Sheet NRCL081LJA_SROA5.doc Page 5 of 5 REV. 0 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

Rev. 0 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: ___Diablo Canyon_________________

Date of Examination: ___1/11/2010_

Exam Level: RO SRO-I SRO-U Operating Test No.: ____L081 _____

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

System / JPM Title Type Code*

Safety Function

a. C1 Initiate Containment Spray Manually (LJC-010)

D, C, E, L 5

b. C2 Remove Power Range Channel N42 from Service (LJC-051)

C, D, E 7

c. S1 Manually feed S/Gs using FR-H1 N, A, S 4-S

d. S2 Establish Emergency Boration (LJC-063)

D, A, E, S 1

e. S3 Align RHR pump 12 for Hot Leg Recirculation (modified LJC-028)

M, S, A, EN, L

2

f. S4 Start an RCP (LJC-120)(bank, alternate path)

M, A, E, S, L 4-P

g. S5 Respond to High Radiation Alarm on RE-44B N, S 8

h. S6 Cross-tie Vital Bus G to H (LJC-032)

D, E, S 6

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. P1 Align 480V Buses for control from Hot Shutdown Panel (LJP-007)

D, E, L 6

j. P2 Close an MSIV locally (LJP-008)

D, L, E, R 4-S

k. P3 Locally verify Containment Isolation Phase B M, R, L, E, A 5

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1

- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

Rev. 0 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: ___Diablo Canyon_________________

Date of Examination: ___1/11/2010_

Exam Level: RO SRO-I SRO-U Operating Test No.: ____L081 _____

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

System / JPM Title Type Code*

Safety Function

a. C1 Initiate Containment Spray Manually (LJC-010)

D, C, E, L 5

b. C2 Remove Power Range Channel N42 from Service (LJC-051)

C, D, E 7

c. S1 Manually feed S/Gs using FR-H1 N, A, S 4-S

d. S2 Establish Emergency Boration (LJC-063)

D, A, E, S 1

e. S3 Align RHR pump 12 for Hot Leg Recirculation (modified LJC-028)

M, S, A, EN, L

2

f. S4 Start an RCP (LJC-120)(bank, alternate path)

M, A, E, S, L 4-P

g. S5 Respond to High Radiation Alarm on RE-44B N, S 8

h.

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. P1 Align 480V Buses for control from Hot Shutdown Panel (LJP-007)

D, E, L 6

j. P2 Close an MSIV locally (LJP-008)

D, L, E, R 4-S

k. P3 Locally verify Containment Isolation Phase B M, R, L, E, A 5

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1

- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure AUTHOR:

CHRIS STEELY/GARY HUTCHISON DATE:

12/2/2009 REV. 1 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

JPM

Title:

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

Instructor Worksheet NRCL081LJC-S1 Rev 1.DOC Page 2 of 6 REV. 1 NRCL081LJC-S1 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

JPM

Title:

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

Instructor Worksheet NRCL081LJC-S1 Rev 1.DOC Page 3 of 6 REV. 1 NRCL081LJC-S1 Start Time:

Step Expected Operator Actions

1.

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

Step was: Sat: ______ Unsat _______*

2.

Manually set Zero demand on ALL MFW Control Valves AND MFW Control Bypass Valve Controllers 2.1 Set ZERO demand on Mn Fdwtr Cont &

Bypass Vlvs controllers on CC3 touch screens Step was: Sat: ______ Unsat _______*

3.

Check MFW Isolation Valves -

OPEN 3.1 Sees that MFW Isolation Valves are 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.

JPM

Title:

JPM Number:

Instructor Worksheet NRCL081LJC-S1 Rev 1.DOC Page 4 of 6 REV. 1 MANUALLY FEED S/G USING FR-H1 NRCL081LJC-S1 Step Expected Operator Actions

5. Check ANY MFW Pump -

LATCHED **

5.1 Determines that no MFW Pumps are 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 until discharge pressure is 100 PSIG GREATER THAN S/G pressure **

6.1 Presses Raise PB on MFW pp S/U station or uses CC3 touch screen (may have to toggle the DFW Control PB on S/U station) to increase MFW discharge pressure > S/G pressure **

7. Check PK09-11, FEEDWATER ISOLATION, finds alarm is active **

7.1 Resets FW Isolation on VB3**

8. Throttle open - MFW Control Bypass Valves or MFW Control Valves **

• • 8.1 Uses CC2 touch screen to establish MFW flow with either MFW control or Bypass valves Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time:

(Enter total time on the cover page)

JPM Number: NRCL081LJC-S1 Examinee Cue Sheet NRCL081LJC-S1 Rev 1.DOC Page 5 of 6 REV. 1 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.

JPM

Title:

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

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

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE AUTHOR:

GARY HUTCHISON DATE:

08/25/09 REV. 0 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

JPM TITLE:

ESTABLISH EMERGENCY BORATION JPM NUMBER:

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

JPM TITLE:

ESTABLISH EMERGENCY BORATION JPM NUMBER:

NRCL081LJC-S2 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-S2.DOC PAGE 3 OF 7 REV. 0 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 make-up controls.

2.1 Verifies charging in service.

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

JPM TITLE:

ESTABLISH EMERGENCY BORATION JPM NUMBER:

NRCL081LJC-S2 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-S2.DOC PAGE 4 OF 7 REV. 0 Step Expected Operator Actions

2. Initiate emergency boration using make-up controls (continued).

2.7 Presses START and verifies at least 30 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 using CVCS-8104.

3.1 Reads NOTE prior to Step 2.

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 _______*

JPM TITLE:

ESTABLISH EMERGENCY BORATION JPM NUMBER:

NRCL081LJC-S2 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-S2.DOC PAGE 5 OF 7 REV. 0 Step Expected Operator Actions

• • 4.

Initiate alternate boration method using the RWST.

4.1 Opens 8805A and 8805B. **

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)

JPM NUMBER:

NRCL081LJC-S2 EXAMINEE CUE SHEET NRCL081LJC-S2.DOC PAGE 6 OF 7 REV. 0 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.

JPM TITLE:

ESTABLISH EMERGENCY BORATION JPM NUMBER:

NRCL081LJC-S2 ATTACHMENT 1, SIMULATOR SETUP NRCL081LJC-S2.DOC PAGE 7 OF 7 REV. 0 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 mal nislb act,4,600,0,d,0 Causes source range NIs to increase by four decades over 10 minutes.

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.

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE AUTHOR:

GARY HUTCHISON DATE:

04/29/09 REV. 0 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

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

NRCL081LJC-S3 INSTRUCTOR WORKSHEET NRCL081LJC-S3.DOC PAGE 2 OF 5 REV. 0 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 <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 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.

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

NRCL081LJC-S3 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-S3.DOC PAGE 3 OF 5 REV. 0 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 discharge crosstie valve.

3.1 Opens valve 8716B.

3.2 Verifies valve open.

Step was: Sat: ______ Unsat _______*

• • 4. Open 8703, RHR to hot legs 1 and 2.

4.1 Attempts to open valve 8703, goes 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)

JPM NUMBER:

NRCL081LJC-S3 EXAMINEE CUE SHEET NRCL081LJC-S3.DOC PAGE 4 OF 5 REV. 0 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 <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 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.

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

NRCL081LJC-S3 ATTACHMENT 1, SIMULATOR SETUP NRCL081LJC-S3.DOC PAGE 5 OF 5 REV. 0 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.

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE AUTHOR:

GARY HUTCHISON

`

10/22/09 REV. 1 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

JPM TITLE: START A REACTOR COOLANT PUMP JPM NUMBER: NRCL081LJC-S4 INSTRUCTOR WORKSHEET NRCL081LJC-S4 REV 1.DOC PAGE 2 OF 7 REV. 1 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.

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

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-S4 REV 1.DOC PAGE 3 OF 7 REV. 1 Start Time:

Step Expected Operator Actions

1. Obtain the correct procedure.

1.1 References OP A-6:I.

Cue: Section 6.2 actions to make RCP 1-3 available have been verified and the prerequisites and precautions and limitations have been tailboarded. Start at Step 6.3.6 Step was: Sat: ______ Unsat _______*

2. Check all related RCP alarms are cleared.

2.1 Reads NOTE 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 it to run at least two minutes.

3.1 Reads NOTE 3.2 Starts the RCP 1-2 oil lift pump.

3.3 Verifies that the RCP 1-2 oil lift pump has started.

3.4 Waits for two minutes prior to starting the RCP.

Step was: Sat: ______ Unsat _______*

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

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-S4 REV 1.DOC PAGE 4 OF 7 REV. 1 Step Expected Operator Actions

• • 4. Start the RCP.

Cue: The Shift Foreman is reviewing the Technical Specifications.

The motor heaters have been deenergized.

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 _______*

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

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-S4 REV 1.DOC PAGE 5 OF 7 REV. 1 Step Expected Operator Actions

• • 5. Observes that PK05-03 and then PK05-05 have alarmed.

5.1 Refers to PK 05-03 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)

JPM NUMBER: NRCL081LJC-S4 EXAMINEE CUE SHEET NRCL081LJC-S4 REV 1.DOC PAGE 6 OF 7 REV. 1 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

JPM TITLE: START A REACTOR COOLANT PUMP JPM NUMBER: NRCL081LJC-S4 ATTACHMENT 1, SIMULATOR SETUP NRCL081LJC-S4 REV 1.DOC PAGE 7 OF 7 REV. 1 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, c,xv2o262r Increases RCP 13 radial brg temperature when RCP 13 red lite is on

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

Inform the examiner that the simulator setup is complete.

Go to RUN when the directed by the examiner.

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE AUTHOR:

GARY HUTCHISON DATE:

08/19/2009 REV. 0 Number:

NRCL081LJC-S5

Title:

Respond to High Radiation Alarm on RE-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

JPM TITLE:

RESPOND TO HIGH RADIATION ALARM ON RE-44B JPM NUMBER:

NRCL081LJC-S5 INSTRUCTOR WORKSHEET NRCL081LJC-S5.DOC Page 2 of 6 REV. 0 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 at 100% power. A Containment Purge was in progress when RE-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:

RE-44B high radiaton alarm and CVI are reset and RM-11 and 12 sample pump flowpath aligned per step 2.1.5.

JPM TITLE:

RESPOND TO HIGH RADIATION ALARM ON RE-44B JPM NUMBER:

NRCL081LJC-S5 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

NRCL081LJC-S5.DOC Page 3 of 6 REV. 0 Start Time:

Step Expected Operator Actions

• • 1. Reset spurious alarm on RE-44B.

1.1 Reads Caution prior to resetting alarm.

1.2 Reset alarm on RE-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 isolation signal.

• • 2.1 Reset containment ventilation 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 RE-11 & 12 sample pump.

3.1 Opens FCV-678, Supply to Gas and Air Particulate Monitors RE-11 &

RE-12 on VB4.

3.2 Opens FCV-679, Supply to RE-11

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

JPM TITLE:

RESPOND TO HIGH RADIATION ALARM ON RE-44B JPM NUMBER:

NRCL081LJC-S5 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes a Critical Step.

NRCL081LJC-S5.DOC Page 4 of 6 REV. 0

4. Restart sample pump for RE-11 &

12 and contact Maintenance.

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

Step was: Sat: ______ Unsat _______*

Stop Time:

Total Time:

(Enter total time on the cover page)

JPM NUMBER:

NRCL081LJC-S5 EXAMINEE CUE SHEET NRCL081LJC-S5.DOC Page 5 of 6 REV. 0 Initial Conditions:

Unit 1 is at 100% power. A Containment Purge was in progress when RE-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

JPM TITLE:

RESPOND TO HIGH RADIATION ALARM ON RE-44B JPM NUMBER:

NRCL081LJC-S5 ATTACHMENT 1, SIMULATOR SETUP NRCL081LJC-S5.DOC Page 6 of 6 REV. 0 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 RE-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.

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE AUTHOR:

GARY HUTCHISON DATE:

10/22/09 REV.1 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

JPM TITLE:

CROSSTIE OF VITAL BUS G TO H JPM NUMBER:

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

JPM TITLE:

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

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-S6 REV 1.DOC PAGE 3 OF 9 REV.1 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 VAC bus feeder breaker for the deenergized bus to be reenergized.

2.1 Opens 52-HH-10. **

2.2 Verifies that 52-HH-10 has opened.

Step was: Sat: ______ Unsat _______*

3. On the deenergized 480V bus to be reenergized, open all 480V breakers.

3.1 Opens all 480V Bus H breakers opened.

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

Step was: Sat: ______ Unsat ___*

• • 4.

Cut in the DIR PWR, LOSS OF FIELD, & BKR OC PROT RLYS for diesel generator 12.

4.1 Places D/G DIR PWR, LOSS OF FLD & BKR OC PROT RLYS C/O 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 _______*

JPM TITLE:

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

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-S6 REV 1.DOC PAGE 4 OF 9 REV.1 Step Expected Operator Actions

• • 6. Cutout the auto transfer FCOs for 4kV and 12kV buses.

6.1 Places all Xfer to S/U PWR C/O toggle switch to CUT-OUT. **

Step was: Sat: ______ Unsat _______*

• • 7. Depress all auto transfer reset pushbuttons.

7.1 Reads NOTE.

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 auxiliary feeder breakers.

8.1 Observes that all vital 4kV bus aux 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 startup feeder breakers.

9.1 Observes that vital 4kV bus startup 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 feeder breaker 52-HG-15.

10.1 Opens 52-HG-15. **

10.2 Verifies that 52-HG-15 has opened.

Step was: Sat: ______ Unsat _______*

JPM TITLE:

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

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-S6 REV 1.DOC PAGE 5 OF 9 REV.1 Step Expected Operator Actions

11. Verify that Steps 4.b and 4.c of this appendix are complete.

11.1 Reads CAUTION and NOTE Cue: Steps 4.b and 4.c of this appendix are complete.

Step was: Sat: ______ Unsat _______*

• • 12. Close 4kV startup feeder breaker for the deenergized bus being reenergized.

12.1 Inserts sync key for 4kV bus H startup feeder breaker 52-HH-14.

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 breaker for the bus that will be supplying power to the deenergized bus.

13.1 Inserts sync key for 4kV bus G startup feeder breaker 52-HG-14.

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 _______*

JPM TITLE:

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

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-S6 REV 1.DOC PAGE 6 OF 9 REV.1 Step Expected Operator Actions

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

14.1 Reads cautions 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 Appendix is complete PRIOR to performing the next step.

15.1 Verifies that Step 4.d of this Appendix is complete.

Cue: Step 4 of this Appendix is complete.

Step was: Sat: ______ Unsat _______*

• • 16. Close the 4kV to 480V bus feeder breaker for the reenergized bus.

16.1 Closes 52-HH-10.**

16.2 Verifies that 52-HH-10 has closed.

Step was: Sat: ______ Unsat _______*

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

17.1 Implements Appendix Q for starting 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:

JPM TITLE:

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

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-S6 REV 1.DOC PAGE 7 OF 9 REV.1 Total Time:

(Enter total time on the cover page)

JPM NUMBER:

NRCL081LJC-S6 EXAMINEE CUE SHEET NRCL081LJC-S6 REV 1.DOC PAGE 8 OF 9 REV.1 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.

JPM TITLE:

CROSSTIE OF VITAL BUS G TO H JPM NUMBER:

NRCL081LJC-S6 ATTACHMENT 1, SIMULATOR SETUP NRCL081LJC-S6 REV 1.DOC PAGE 9 OF 9 REV.1 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.

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE AUTHOR:

GARY HUTCHISON DATE:

10/22/2009 REV. 1 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

JPM TITLE: INITIATE CONTAINMENT SPRAY MANUALLY JPM NUMBER:

NRCL081LJC-C1 INSTRUCTOR WORKSHEET NRCL081LJC-C1 rev 1.doc PAGE 2 OF 5 REV.1 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.

Task Standard:

Containment spray is initiated and aligned for injection phase.

JPM TITLE: INITIATE CONTAINMENT SPRAY MANUALLY JPM NUMBER:

NRCL081LJC-C1 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-C1 rev 1.doc PAGE 3 OF 5 REV.1 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 required.

2.1 Checks if EOP ECA-1.1 is the 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 pumps.

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

Cue: Containment spray pumps are running with stable amps.

Step was: Sat: ______ Unsat _______*

JPM TITLE: INITIATE CONTAINMENT SPRAY MANUALLY JPM NUMBER:

NRCL081LJC-C1 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-C1 rev 1.doc PAGE 4 OF 5 REV.1

• • 4. Checks containment spray system for proper valve alignment.

4.1 Determines that ECCS is aligned for injection flow.

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

Cue: 9001A & B indicate open.

4.3 Verifies 8992 open.

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

Cue: 8994A & B indicate open.

Step was: Sat: ______ Unsat _______*

5. Checks Containment Isolation Phase B valves 5.1 Checks Phase B portion of monitor 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:

JPM TITLE: INITIATE CONTAINMENT SPRAY MANUALLY JPM NUMBER:

NRCL081LJC-C1 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-C1 rev 1.doc PAGE 5 OF 5 REV.1 Total Time:

(Enter total time on the cover page)

JPM NUMBER:

NRCL081LJC-C1 EXAMINEE CUE SHEET NRCL081LJC-C1 rev 1.doc Page 6 of 6 REV. 1 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.

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE AUTHOR:

GARY HUTCHISON DATE:

08/06/2009 REV. 0 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

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

NRCL081LJC-C2 INSTRUCTOR WORKSHEET NRCL081LJC-C2.DOC PAGE 2 OF 5 REV. 0 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.

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

NRCL081LJC-C2 INSTRUCTOR WORKSHEET NRCL081LJC-C2.DOC PAGE 3 OF 5 REV. 0 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: If asked about alarm: PK07-07, PWR RNG 42 ROD STOP BYPASSED -- ON.

Step was: Sat: ______ Unsat _______*

• • 3.

Place power mismatch bypass switch to the failed channel position.

3.1 Places the POWER MISMATCH BYPASS switch in the BYPASS PR N42 position. **

Step was: Sat: ______ Unsat _______*

• • 4. Place quadrant power tilt alarm upper section switch to the failed channel position.

4.1 Places the QUADRANT POWER TILT ALARM UPPER SECTION switch in the PRN42 position. **

4.2 Verifies that the CHANNEL DEFEAT light has lit.

Step was: Sat: ______ Unsat _______*

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

NRCL081LJC-C2 INSTRUCTOR WORKSHEET NRCL081LJC-C2.DOC PAGE 4 OF 5 REV. 0 Step Expected Operator Actions

• • 5. Place quadrant power tilt alarm lower section switch to the failed channel position.

5.1 Places the QUADRANT POWER TILT ALARM LOWER SECTION switch in the PRN42 position. **

5.2 Verifies that the CHANNEL DEFEAT light has lit.

Step was: Sat: ______ Unsat _______*

• • 6. Place the comparator defeat switch to the failed channel position.

6.1 Places the COMPARATOR CHANNEL DEFEAT switch in the N42 position. **

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)

JPM NUMBER:

NRCL081LJC-C2 EXAMINEE CUE SHEET NRCL081LJC-C2.DOC PAGE 5 OF 5 REV. 0 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.

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE AUTHOR:

GARY HUTCHISON 08/25/09 REV. 0 Number:

NRCL081LJP-P1

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

JPM TITLE:

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

NRCL081LJP-P1 INSTRUCTOR WORKSHEET NRCL081LJC-P1.DOC PAGE 2 OF 7 REV. 0 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

JPM TITLE:

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

NRCL081LJP-P1 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-P1.DOC PAGE 3 OF 7 REV. 0 Start Time:

Step Expected Operator Actions

• • 1.

Place the control transfer cutout switches for 480V vital bus F to the CUT-IN position.

1.1 Locates the 480V vital bus F aux relay panel in the vital switchgear 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 prevent spurious operation.

2.1 Opens the following breakers:

• 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 _______*

JPM TITLE:

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

NRCL081LJP-P1 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-P1.DOC PAGE 4 OF 7 REV. 0 Step Expected Operator Actions

• • 3.

Place the control transfer cutout switches for 480V vital bus G to the CUT-IN position.

3.1 Locates 480V vital bus G aux relay panel in the vital switchgear room.

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 _______*

JPM TITLE:

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

NRCL081LJP-P1 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-P1.DOC PAGE 5 OF 7 REV. 0 Step Expected Operator Actions

• • 4. Open 480V vital bus G breakers to prevent spurious operation.

4.1 Opens the following breakers:

• 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 prevent spurious operation.

5.1 Opens the following breakers:

• 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 _______*

JPM TITLE:

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

NRCL081LJP-P1 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-P1.DOC PAGE 6 OF 7 REV. 0 Step Expected Operator Actions

• • 6.

Place the control transfer cutout switches for 480V bus 23D to the CUT-IN position.

6.1 Locates the 480V bus 23D control transfer cutout switch inside bus 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)

JPM NUMBER:

NRCL081LJP-P1 EXAMINEE CUE SHEET NRCL081LJC-P1.DOC PAGE 7 OF 7 REV. 0 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.

NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE JOHN BECERRA AUTHOR:

GARY HUTCHISON DATE:

08/25/09 REV. 0 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 is a Unit 2 JPM.

References:

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

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

JPM TITLE:

CLOSE AN MSIV LOCALLY JPM NUMBER:

NRCL081LJP-P2 INSTRUCTOR WORKSHEET NRCL081LJC-P2.DOC PAGE 2 OF 4 REV. 0 Directions:

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

Required Materials:

Procedure EOP E-2, Appendix L.

Initial Conditions:

A main steam line rupture has occurred on Unit 2 downstream of the MSIVs. MSIV FCV-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 2 MSIV FCV-43 has been CLOSED in accordance with Appendix L of EOP E-2.

JPM TITLE:

CLOSE AN MSIV LOCALLY JPM NUMBER:

NRCL081LJP-P2 INSTRUCTOR WORKSHEET

• Denotes an entry required on the JPM cover sheet.

• • Denotes Critical Step and Sub Steps.

NRCL081LJC-P2.DOC PAGE 3 OF 4 REV. 0 Start Time:

Step Expected Operator Actions

• • 1.

Locally CLOSE MSIV air supply or common air supply valves.

1.1 CLOSES Common air supply valve AIR-I-2-1044 OR MSIV air supply valve AIR-I-2-4027.**

Step was: Sat: ______ Unsat _______*

• • 2. REMOVES BOTH accumulator drain caps.

2.1 REMOVES BOTH accumulator drain caps.**

Step was: Sat: ______ Unsat _______*

• • 3. OPEN MSIV air accumulator drain valves.

3.1 OPENS drain valves AIR-I-2-1547 AND AIR-I-2-1548.**

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)

JPM NUMBER:

NRCL081LJP-P2 EXAMINEE CUE SHEET NRCL081LJC-P2.DOC PAGE 4 OF 4 REV. 0 Initial Conditions:

A main steam line rupture has occurred on 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.

Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure AUTHOR:

CHRIS STEELY/GARY HUTCHISON DATE:

12/10/2009 REV. 1 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

JPM

Title:

Local Verification Cont. Isolation Phase B JPM Number:

NRCL081LJC-P3 Instructor Worksheet NRCL081LJC-P3 Rev 1.DOC Page 2 of 4 REV. 1 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

JPM

Title:

Local Verification Cont. Isolation Phase B JPM Number:

Instructor Worksheet NRCL081LJC-P3 Rev 1.DOC Page 3 of 4 REV. 1 NRCL081LJC-P3 Start Time:

Step Expected Operator Actions

1. Locally verify proper actuation of Phase B Containment isolation Valves that are not properly indicating on Monitor Light Box D. **

Location: 115 Aux Bldg Cnm Pen area CUE: Valve position is as seen.

1.1 Opens Spray Pump 1 Discharge Valve -

9001A **

CUE: Valve position indicator is up.

Step was: Sat: ______ Unsat _______*

2. Locally verify proper actuation of Phase B Containment isolation Valves that are not properly indicating on Monitor Light Box D. **

Location: 73 Aux Bldg near Spray Add Tank CUE: Valve Position is as seen.

2.1 Opens Spray Additive Tank Out - 8994B **

CUE: Valve position indicator is up.

Step was: Sat: ______ Unsat _______*

3. Locally verify proper actuation of Phase B Containment isolation Valves that are not properly indicating on Monitor Light Box D. **

Location: 85 Turb. Bldg upper area of CCW HX room CUE: Valve Position is as seen.

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)

JPM Number: NRCL081LJC-P3 Examinee Cue Sheet NRCL081LJC-P3 Rev 1.DOC Page 4 of 4 REV. 1 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 r

correct position of the non-indicating Phase B valves. The breakers fo the associated valves have been opened.

NRCSIM081 01 Appendix D outline Rev 1.doc 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 No.

Malf.

No.

Event Type*

Event Description 1

N(BOP)

TS 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)

TS Tc channel fails high.

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

Description:

Unload and Secure EDG 1-1 (OP J-6B:IV)

Time Position Applicants Actions or Behavior SRO Directs BOP to unload and secure EDG 1.1 BOP 6.5.1 While limiting load changes to less than 0.5 MW every two minutes, slowly adjust the governor speed control in the LOWER direction to lower DG 1-1 load to approximately 0.5 MW.

BOP 6.5.2 WHEN DG 1-1 load has been reduced to about 0.5 MW, THEN before continuing, maintain load at 0.5 MW for at least five minutes for cooldown.

BOP 6.5.3 Place the DG 1-1 Feeder Sync switch in "ON".

BOP 6.5.4 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 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 1.doc Rev. 1 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 2 Page 2 of 7 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)

SRO Directs ATC/BOP to carry out actions of OP AP-5 (Malfunction of Eagle 21 Protection or Control Channel)

BOP IF PK06-01 OR PK06-03 is ON,

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

2) 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 1 - Racks 1, 2, 3, 4 Protection Set 2 - Racks 6, 7, 8, 10 Protection Set 3 - Racks 11, 13 Protection Set 4 - Racks 15, 16 BOP IF PK06-03 is ON, THEN perform the following:

1) Identify which "RTD FAILURE" red LEDs are LIT

2) Determine which Instrument Channels are in the affected rack using.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 1.doc Rev. 1 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 2 Page 3 of 7 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 1.doc Rev. 1 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Page 4 of 7 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/ATC/BOP Verify affected S/G is 1-2 and direct ATC/BOP through actions in OP AP-3 (SG Tube Failure)

ATC CHECK PZR Level and Charging Flow ATC 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 ATC Turns backup heaters on ATC Commences RCS boration SRO Directs Chemistry to sample per CAP AP-1 SRO Refers to TS 3.4.13.B

NRCSIM081 01 Appendix D outline Rev 1.doc Rev. 1 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 4-6 Page 5 of 7 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 ALL Perform remaining immediate actions of E-0 Reactor Trip or Safety Injection VERIFY reactor tripped VERIFY turbine tripped VERIFY vital 4kV buses energized CHECK SI - Actuated 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).

SRO Transitions to EOP E-0.1 Reactor Trip Response ALL Recognition of loss of power to non-vital 4kV and 12kV buses - Loss of Offsite Power.

SRO Recognizing Loss of Offsite Power - Enter OP AP-26 (Loss of Offsite Power) and direct the following actions.

SRO to Aux Op.

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

NRCSIM081 01 Appendix D outline Rev 1.doc Rev. 1 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Page 6 of 7 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 BOP Performs Appendix E of EOP E-0 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

23. Identify ruptured SG (Will have occurred from earlier tube leak)

ATC

23. Isolate flow from ruptured SG (SG 1-2) CRITICAL TASK Note: Closing FCV-37 (TDAFWP steam supply from SG 1-2) will be part of this critical task.

ATC

4. Check ruptured SG levels 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 BOP

10. Initiate RCS cooldown using 10% Steam Dumps SRO

11. Initiate Evaluation of Plant Status ATC

12. Check PZR PORVs and Block Valves BOP

23. 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 to minimize break flow and refill PZR

NRCSIM081 01 Appendix D outline Rev 1.doc Rev. 1 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Page 7 of 7 Event

Description:

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

21. Depressurize RCS using PORVs ATC

22. Check RCS Pressure (Increasing)

ATC

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

ATC

24. Check if ECCS flow should be terminated BOP

25. Stop ECCS pumps and place in Standby BOP

26. Isolate Charging Injection

NRCSIM081 01 Appendix D outline Rev 1.doc Rev. 1 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 1.doc Rev. 1 ATTACHMENT 1 - SIMULATOR SET-UP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator per Checklist Init 510 100% power, Mol, CB = 772 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Circuit breaker flags are correct.

Equipment status lamicoids are correct:

B.A. XFER PP SUPPLYING BLENDER

- BA Pp 1-2 SUPPLYING IN-SERVICE SCW HX

- CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP

- CWP 1-1 SELECTED TO BUS 2F

- Cont. Rm. Vent Train 1 Bus F SELECTED TO BUS 1H

- Cont. Rm. Vent Train 1 Bus H The proper Delta-I curve and Reactivity Handbook for the simulator INIT are in place The Rod Step Counters indicate correctly.

PPC Setup:

o 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 1.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 output bkr 52-HH-7 is opened.

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

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

10 min after D/G 11 trip xmt rcs132 3,679,0,605, c,.not.jbkhh7, Loop 4 tcold fails high X

When requested Report that Racks 15 & 16 trouble LEDs are lit.

15 min after Loop 4 Tcold fails high plp aux25 act,200,0,900, c,txmt410b(4).gt.675, S/G 12 tube leak at 200 gpd 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 Loss of offsite power and reactor trip On Safety Injection Mal syd1 act,2,60,30,c,jpplsi Loss of Startup (230 KV) power 6 minutes after reactor trip mal rcs4b act 400,60,360,c,jpplp4,0 400 gpm SGTR on SG 12 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 1.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 1.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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 1.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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 02 Appendix D outline Rev 1.doc Rev. 0 Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility:

Diablo Canyon Scenario No.:

2 Op-Test No.:

L081-2 Examiners:

Operators:

Initial Conditions: 15% Power, MOL, 1185 ppm CB Turnover: PRA Status: Green. Protected Equipment - Train B, Buses H& G, Prot. Sets II, III, IV. CCP 13 cleared due to excessive bearing vibration. U-2 at 100% power. Crew parallels generator and ramps at 3 MW/min to 28% power.

Event No.

Malf. No.

Event Type*

Event Description and Time Line 1

R (ATC)

N(ALL)

Parallels generator and ramps to 28% at 3 MW/min.

2 Xmt pzr40 I (ATC)

Controlling Pzr level channel (LT-459) fails high. (TS 3.3.1) 3 Pmp cvc1 C (ALL)

CCP 11 trips on overcurrent. (TS 3.5.2) 4 N (ATC, BOP)

Restore letdown.

5 mal sei1 M

0.28g earthquake 10 minutes after LT-459 failure.

6 mal rcs3b M (ALL)

Small break (3.5) LOCA after earthquake. (Requires RCP trip Criteria - CT) 7 mal ppl1b pmp sis1 C (ATC, BOP)

Phase A train B fails to actuate on SI.

SI pp 11 trips on overcurrent on SI.

8 Vlv cvc6 C (BOP)

Seal Return valve Inside Containment 8112 fails to close (requires Operator action - CT)

• (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) 5

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

3. Abnormal events (2-4) 2

4. Major transients (1-2) 1

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

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

7. Critical tasks (2-3) 2

NRCSIM081 02 Appendix D outline Rev 1.doc Rev. 0 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

L081-2 Scenario No.:

2 Event No.:

1 Page 1 of 6 Event

Description:

Parallels generator and ramps to 28%

Time Position Applicants Actions or Behavior SRO Directs Parallel the Main Unit Generator to the 500KV system PER OP C-3:II, "Main Unit Startup," starting at Step 6.3.5 SRO Station operators and review actions to be taken at each station immediatelyafter paralleling the main generator to the system:

BOP Adjust generator frequency to slightly greater than grid frequency.

BOP Close PCB-532 when the synchroscope pointer is slightly before the 12 o'clock position.

ATC Control steam generator pressure (in auto or manual) such that the 10%

steam dump valves and the main steam safety valves are prevented from lifting BOP Manually check synchronism for PCB-632 and then close the breaker BOP Increase turbine load to 28% power at 3 MW/min ATC Adjusts rods to maintain Tavg matched to Tref

NRCSIM081 02 Appendix D outline Rev 1.doc Rev. 0 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

L081-2 Scenario No.:

2 Event No.:

2 Page 2 of 6 Event

Description:

Pzr level channel (LT-459) fails high Time Position Applicants Actions or Behavior SRO Responds to PK 05-22 PZR LEVEL HI/LO CONTROL SRO/BOP Diagnoses LT-459 failing high ATC Takes manual control of PZR level control, increases charging flow SRO Enters AP-5 ATC Selects B/U channel for control and Level recorder SRO Refers to Tech Specs 3.3.1 (Condition M - 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

SRO Determines bistables to be tripped as time permits (AP-5, attachment 4.1, rack 1)

LC 459A High Lvl Trip SRO Directs Maintenance to investigate

NRCSIM081 02 Appendix D outline Rev 1.doc Rev. 0 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

L081-2 Scenario No.:

2 Event No.:

3 Page 3 of 6 Event

Description:

CCP 11 trips on overcurrent Time Position Applicants Actions or Behavior ATC Recognizes trip of CCP 1-1 SRO Refers to AR PK04-17 SRO Enters AP-17, Section A BOP Verifies suction flow path & starts CCP 1-2 SRO Directs letdown restoration per OP B-1A:XII ATC Stabilizes PZR level controls; returns to auto SRO Refers to Tech Spec 3.5.2 (Condition A - 14 days)

SRO Directs Maintenance to investigate

NRCSIM081 02 Appendix D outline Rev 1.doc Rev. 0 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

L081-2 Scenario No.:

2 Event No.:

4 Page 4 of 6 Event

Description:

Restores Letdown Time Position Applicants Actions or Behavior ALL Restores letdown per OP B-1A:XII BOP Reviews Precautions and Limitations of OP B-1A:XII SRO Performs Reactivity Brief for returning Letdown.

BOP Manually adjust Letdown temperature control, TCV-130, to 35-40% demand.

BOP Check open letdown isolation valve 8152.

BOP Place letdown back pressure control valve, PCV-135 in manual and open 60%.

BOP Open letdown isolation valves LCV-459 and LCV-460.

ATC Increase normal charging to 87 gpm and adjust RCP seal injection flow to between 8 GPM and 13 GPM per RCP using HCV-142.

BOP Manually adjust Letdown temperature control, TCV-130, to 35-40% demand.

BOP Open orfice isolation valve 8149C.

BOP Adjust PCV-135 to control at 350 psig,5.8 turns, and place in Auto.

ATC Adjust charging flow and when pressurizer level is on reference, return to auto.

BOP Adjust TCV-130 to maintain normal letdown temperature and return to Auto

NRCSIM081 02 Appendix D outline Rev 1.doc Rev. 0 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

L081-2 Scenario No.:

2 Event No.:

5 & 6 Page 5 of 6 Event

Description:

Earthquake and Small break LOCA Time Position Applicants Actions or Behavior ALL Recognizes Seismic event SRO Refers to AR PK15-24 and CP M-4 ATC Determines Pzr level decreasing and increases charging flow BOP Isolates letdown if time permits ATC Advocates a Safety Injection based on not being able to maintain Pzr level SRO Directs a manual Safety Injection SRO Enters E-0 ALL Performs immediate actions ALL

• • Recognize RCP trip criteria and trips RCPs (CT)

• • Critical Task

NRCSIM081 02 Appendix D outline Rev 1.doc Rev. 0 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

L081-2 Scenario No.:

2 Event No.:

7 & 8 Page 6 of 6 Event

Description:

Phase A train B failure and 8112 seal return fails to close Time Position Applicants Actions or Behavior BOP Implement Appendix E, ESF Auto Actions, Secondary And Auxiliaries Status BOP Determines Train B of Phase A Containment Isolation is not met.

Takes action to place the following valves to the closed position:

9355B - PZR Liquid Sample OC 9356B - RCS Sample OC 8880 - N2 supply to Accumulators 8152 - Letdown Isolation 8100 - RCP Seal Return **

8029 - Containment Primary Water 8045 - PRT N2 supply 633 - Containment Fire Water Supply 584 - Instrument Air Supply Rad Waste Isolation Train BOP Determines 8112 did not close, and closes 8112 RCP seal return **

Note: either 8100 OR 8112 must be closed to satisfy the critical task BOP Verify Containment Spray & MSL isolation not required BOP CHECK ECCS flow and VERIFY pump operation ATC Throttles AFW flow as directed by SRO.

ATC Places 2nd CCW Heat Exchanger in-service SRO Conducts Procedure Transition Brief for E-1, Loss of Reactor of Secondary Coolant.

SRO Enter E-1, Loss of Reactor of Secondary Coolant.

BOP Shuts down D/Gs; returns them to Auto ATC Aligns CCW cooling to RHR HXs SRO Conducts Procedure Transition Brief for E-1.2 Post LOCA Cooldown and Depressurization Terminate Scenario after E-1.2 tailboard is complete.

• • Critical Task

NRCSIM081 02 Appendix D outline Rev 1.doc Rev. 0 MAJOR EVENT

SUMMARY

AND SCENARIO OBJECTIVES A.

Commences ramp to 28% power at 3 MW/min.

B.

Centrifugal Charging Pump 11 trips on over current. Crew goes to AP-17 Loss of Charging section A to restore charging flow.

C.

Crew restores letdown after charging is restored in AP-17 per OP B-1A:XII CVCS-letdown system establish normal letdown following isolation.

D.

LT-459 Pressurizer controlling level channel fails high. Crew enters AP-5 Malfunction of Eagle 21 Protection or Control Channel to address instrument failure.

E.

Earthquake at 0.28g causes Small break LOCA. Crew is unable to maintain Pressurizer level and performs a manual Safety Injection and enters E-0 Reactor Trip or Safety Injection.

F.

On the Safety Injection, Train B of Phase A Containment Isolation does not actuate, and isolation must be done via manual operator actions.

G.

On the Safety Injection, 8112 RCP seal return valve inside containment does not close and must be manually isolated. (CT)

H.

The RCPs must be tripped within 5 minutes of RCS pressure going below 1300 psig. (CT)

I.

Crew transitions from E-0 to E-1 Loss of Reactor or Secondary Coolant and performs verification steps.

J.

Crew transitions to E-1.2 Post LOCA cooldown and depressurization, Scenario is terminated after transition tailboard.

NRCSIM081 02 Appendix D outline Rev 1.doc Rev. 0 ATTACHMENT 1 - SIMULATOR SET-UP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator per Checklist Load snap31 and IC_31 from exam flashdrive Init 31 15% power, Mol, CB = 1185 Integrators: BA - 0 and PW -40 Tags: CCP 13 Setup Drill 81 Reset normal engineering values Setup Loa cvc67 act,0,0,0,d,0 Swap to CCP 11 in service and shutdown CCP 13, then activate Loa cvc67 if not done in snap 31 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 02 Appendix D outline Rev 1.doc Rev. 0 TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION X = manual entry required X

0 min DRILL 6802 After SFM reports the crew has taken the watch, load session MALS, OVRs, etc. by DRILL FILE or MANUALLY (below) 0 min mal ppl1b act,2,0,0,d,0 Phase A train B fails to actuate.

0 min Vlv cvc6 1,0,0,0,d,xv2i221c 8112 fails as is until C/S taken to close 10 minutes after PCB 632 closed Xmt pzr40 3,100,30,600,c,xc3i033c Pzr level channel (LT-459) fails high 10 min from LT-459 failure Pmp cvc1 4,0,0,600,c, llc459a CCP 11 trips on overcurrent X

When requested Report CCP 11 motor hot to touch, B phase OC flags dropped at breaker 10 min after PCV-135 in Manual Mal sei1 act,0.28,10,600, c,xv2i159m 0.28g earthquake On Seismic mal rcs3b act,3.5,300,30, c,jmlsei1,0 Small break LOCA (3.5) on loop 2 cold leg X

After RX trip Drill 32 N.O. Action on reactor trip On Safety Injection Pmp sis1 4,0,0,20,c,jpplsi SI pp 11 trips on S.I.

NRCSIM081 02 Appendix D outline Rev 1.doc Rev. 0 Drl_6802.txt

• NRC L081 scenario #2

• glh1, 9/29/9

• init 510

• Phase A train B fails to actuate mal ppl1b act,2,0,0,d,0

• SI pp 12 trips on OC on SI pmp sis1 4,0,0,20,c,jpplsi

• 8112 fails as is until C/S taken to close Vlv cvc6 1,0,0,0,d,xv2i221c

• Pzr level channel (LT-459) fails high Xmt pzr40 3,100,30,600,c,xc3i033c

• CCP 11 trips on overcurrent Pmp cvc1 4,0,0,600,c,llc459a

• 0.28g earthquake Mal sei1 act,0.28,10,600,c,xv2i159m

• Small break LOCA (3.5) on loop 2 cold leg mal rcs3b act,3.5,300,30,c,jmlsei1,0

NRCSIM081 02 Appendix D outline Rev 1.doc Rev. 1 DIABLO CANYON POWER PLANT OPERATIONS SHIFT LOG UNIT 1 OPERATING MODE:

1 POWER LEVEL:

15 GROSS GENERATION:

0 MWe NET GENERATION 0

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:

CCP 13 cleared due to excessive bearing vibration.

TURNOVER ITEMS:

Parallel the unit starting at OP C-3:II step 6.3.5 Ramp to 28% power at 3 MW/min per OP L-3 (at step 6.44 to parallel)

OPERABILITY ITEMS:

• None PRIORITY ITEMS FOR NEXT SHIFT:

• Perform STP R-2B and continue power ascension.

ANNUNCIATORS IN ALARM

• None

NRCSIM081 02 Appendix D outline Rev 1.doc Rev. 1 SHIFT FOREMAN TURNOVER COMMENTS:

1.

Reactivity management:

a.

Time in core life: MOL

b.

Power History: Tripped from 100% 3 days ago.

c.

Boron concentration is 1185 ppm from a sample taken 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago.

d.

Dilute in 100 gallon batches as needed after parallel.

e.

After paralleling unit, ramp at 3 MW/min to 280 MW, dont exceed 28% power.

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 03 Appendix D outline Rev 1.doc Rev. 1 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 No.

Malf. No.

Event Type*

Event Description and Time Line 1

N (BOP)

Swaps ASW pp trains.

2 Pmp asw2 Pmp asw1 C (SRO, BOP)

ASW pp 12 trip 5 minutes after train swap (TS 3.7.8.A), ASW pp 11 doesnt auto start.

3 Dsc rod1 I (ATC)

I ( SRO)

Loss of power to DRPI 4

Ser 0829 C (All)

R (ATC)

Loss of Main Transformer cooling.

5 mal rcs4d mal ppl3a mal ppl3b M (All)

S/G 14 tube rupture during ramp. Requires manual Safety Injection (CT) 6 Mal syd1 M (All)

Loss of Startup power on unit trip.

7 Pmp cvc1 Pmp cvc2 C (BOP)

Both Charging pumps fail to start after transfer to D/G. (CT) 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) 7

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

3. Abnormal events (2-4) 3

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) 3

NRCSIM081 03 Appendix D outline Rev 1.doc Rev. 1 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 BOP Has intake watch secure continuous chlorination to the in-service ASW suction bay BOP Advise U2 Control Room to place the U2 standby ASW pump in "MANUAL",

to prevent a possible auto-start.

BOP Place the Mode Selector Switch for the standby ASW pump 12 in "MANUAL" BOP Place the Control Switch for the standby ASW pump 12 in "START", to start the pump BOP OPEN the CCW HX 12 saltwater inlet valve FCV-603 on the HX being placed in service.

BOP OPEN the CCW HX 12 shell-side outlet valve FCV-431 on the HX being placed in service.

BOP CLOSE the CCW HX 11 shell-side outlet valve FCV-430 on the HX being placed in standby BOP CLOSE the CCW HX 11 saltwater inlet valve FCV-602 on the HX being placed in standby.

BOP SHUT DOWN ASW pump 11.

BOP place the Mode Selector Switch for ASW pump 11 in "AUTO".

BOP Advise U2 Control Room that the U2 standby ASW pump can be placed in "AUTO".

BOP Place in service continuous chlorination to the in-service ASW suction bay

NRCSIM081 03 Appendix D outline Rev 1.doc Rev. 1 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 SRO Refers to Tech Spec 3.7.8 ASW System Condition A (72 Hour completion time with 1 train inoperable)

NRCSIM081 03 Appendix D outline Rev 1.doc Rev. 1 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 SRO If not done as part of PK03-25, step 2.1.3 - Directs N.O. to place DRPI on B/U power per OP A-3:I ATC Returns control rods to Auto after restoration of DRPI

NRCSIM081 03 Appendix D outline Rev 1.doc Rev. 1 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.

SRO Directs power reduction at 50 MW per minute per direction in AR PK14-21 using OP AP-25, "Rapid Load Reduction or Shutdown,"

ATC Commences ramp to take unit offline at 50 MW/min 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.

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 1.doc Rev. 1 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 BOP/ATC Implements Appendix E BOP/ATC Closes MSIVs per Appendix E

• • Critical Task

NRCSIM081 03 Appendix D outline Rev 1.doc Rev. 1 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 Implement Appendix E, ESF Auto Actions, Secondary And Auxiliaries Status 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.

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 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 1.doc Rev. 1 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 1.doc Rev. 1 ATTACHMENT 1 - SIMULATOR SET-UP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator per Checklist Init 510 100% power, Mol, CB = 772 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 1.doc Rev. 1 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 Mal ppl3b act,1,0,0,d,0 Fails Auto SI 0 min Pmp asw1 1,0,0,0,d,0 ASW pp 11 doesnt auto start 5 minutes after ASW pp 11 s/d Pmp asw2 6,10,1,300,c,xv1o242g ASW pp 12 trips on overcurrent 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 pp 12 trip Dsc rod1 act,0,0,600,c,xv1o243b Loss of normal power to DRPI X

When requested Report that DRPI transformer looks fine, but 52-1F-45 is tripped.

X When requested to transfer DRPPI to B/U Dsc eps17 act,1,0,0,d,0 Loa eps1 act,1,0,0,d,0 Closes DRPI b/u breaker and transfers DRPI pwr supply to b/u 10 min from rods in manual Ser 0829 act,1,0,600,c,xc1i085f PK14-21 #0829 for MTB local annunciator 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 ramp started Mal rcs4d act,400,150,720,c,ggo 400 gpm SGTR on SG 14 On Safety Injection Mal syd1 act,2,60,30,c,jpplsi Loss of Startup (230 KV) power Pmp cvc1 1,0,0,0,c,jpplsi Pmp cvc2 1,0,0,0,c,jpplsi CCP 11 and 12 fail to auto start after bus transfer to diesel.

X After RX trip Drill 32 N.O. Action on reactor trip If manually opened Vlv pzr4 2,1,0,3,c,xv2i205o Fails PCV-455C open 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 PORV is manually opened Vlv pzr1 2,1,0,0,c, xv2i204o Fails 8000A open when PCV-474 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 1.doc Rev. 1 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

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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 04 Appendix D outline Rev 1.doc Rev. 0 Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility:

Diablo Canyon Scenario No.:

4 Op-Test No.:

L081-4 Examiners:

Operators:

Initial Conditions: 100% Power, MOL, 772 ppm CB Turnover: PRA Status: Green. Protected Equipment - Train B, Buses H& G, Prot. Sets II, III, IV. AFW pp 11 cleared due to bearing replacement. U-2 at 100% power. Crew ramps unit at 3 MW/min to 50% power in preparation of CWP tunnel cleaning.

Event No.

Malf. No.

Event Type*

Event Description and Time Line 1

R (ATC)

N (SRO)

Ramps to 50% at 3 MW/min.

2 Xmt cvc I (All)

VCT level channel LT-114 fails high.

3 Pmp cvc1 C (SRO)

Loss of UC fuse to MDAFW pp 13. (TS 3.7.5) 4 Xmt pzr41 I (ATC, SRO)

Backup Pzr level channel (LT-461) fails low. (TS 3.3.1) 5 mal gen1 M (All)

Main Transformer Bank Sudden Pressure Trip causes Reactor trip.

6 mal eps4 Differential trip on 4KV bus G (lose 2 CCPs)

Mal syd1 Loss of offsite power 7

Pmp cvc1 C (All)

CCP 11 trips on OC - lose all Charging pumps.

8 Pmp afw1 C (All)

MDAFW pp 12 trip on OC - Loss of Heat Sink with no High Head Injection.

• (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) 5

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

3. Abnormal events (2-4) 2

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) 2

NRCSIM081 04 Appendix D outline Rev 1.doc Rev. 0 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

L081-4 Scenario No.:

4 Event No.:

1 Page 1 of 6 Event

Description:

Starts ramp to 50% power Time Position Applicants Actions or Behavior SRO Directs RO to perform RCS boration for ramp.

ATC Performs Boration of RCS in accordance with OP B-1A:VII, Makeup Control System Operation, may use Attachment 1 for guidance.

Set target Batch on flow controller (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 RO to perform ramp to 50%.

ATC Sets up ramp on DEHC Console per SRO direction using OP C-3:III, Main Unit Turbine - At Power Operations. (May use Committed Posting for Direction)

Places MW feedback in service.

Set desired Ramp Rate. (3 MW/Min)

Set Target to desired load. (<200 MW)

Commence ramp by Pressing GO

NRCSIM081 04 Appendix D outline Rev 1.doc Rev. 0 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

L081-4 Scenario No.:

4 Event No.:

2 Page 2 of 6 Event

Description:

VCT level channel LT-114 fails high.

Time Position Applicants Actions or Behavior ATC Determines VCT level on PPC L0112A is increasing.

BOP Determines VCT level on VB-2 is decreasing.

SRO Determines that VCT level channel LT-114 has failed high SRO Enters OP AP-19 Malfunction of Reactor Makeup Control System.

ATC Ensure Reactor Makeup Control System selector switch is set to mode desired (usually AUTO)

ATC Ensure Reactor Makeup Control System auto makeup is selected to START ATC Verifies Reactor Makeup System Pumps and Valves in AUTO on VB2.

SRO Refers to Appendix A for LT-114 BOP Aligns LCV-112A to VCT BOP Verifies Suction to CCP 13 SRO Notifies Maintenance to troubleshoot and repair LT-114

NRCSIM081 04 Appendix D outline Rev 1.doc Rev. 0 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

L081-4 Scenario No.:

4 Event No.:

3 Page 3 of 6 Event

Description:

Loss of UC fuse to MDAFW pp 13 Time Position Applicants Actions or Behavior SRO Refers to PK 18-18 4KV Bus F DC Cont UV or Trouble input 146 BOP Notes that AFW pp 13 white light is out SRO Declares AFW pp 13 inoperable and enters TS 3.7.5, Condition C (mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />)

SRO Directs an Operator to the 4kV Vital Bus F Room to report the status of the 4kV Bus F DC potential (white) lights on each breaker door Local Operator reports that 52-HF-9 breaker DC potential white light is not lit.

SRO Directs Operator to open breaker door and report status of Closing spring charged flag UC fuse holder DC knife switch Local Operator reports that breaker closing spring is charged, UC fuses installed in the ON position, and DC knife switch is closed.

NRCSIM081 04 Appendix D outline Rev 1.doc Rev. 0 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

L081-4 Scenario No.:

4 Event No.:

4 Page 4 of 6 Event

Description:

Backup Pzr level channel (LT-461) fails low Time Position Applicants Actions or Behavior BOP/ATC Diagnoses LT-461 failing low BOP Determines letdown is isolated.

ATC Takes manual control of PZR level control and reduces charging to seals only SRO Enters AP-5 ATC Selects alternate channel for backup control SRO Refers to Tech Specs 3.3.1.M (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />), 3.3.3.A (30 days)

SRO Determines bistables to be tripped (Rack 13)

LC 461A High Lvl Trip SRO Directs Maintenance to investigate failure of LT-461 SRO Reactivity Tailboard for restoring letdown.

NRCSIM081 04 Appendix D outline Rev 1.doc Rev. 0 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

L081-4 Scenario No.:

4 Event No.:

5 & 6 Page 5 of 6 Event

Description:

Main Transformer Bank Sudden Pressure Trip & Loss of 4KV bus G and Offsite power Time Position Applicants Actions or Behavior SRO Determines Reactor Trip and enters E-0 Reactor Trip or Safety Injection 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 - Not Actuated BOP Determines 4KV bus G is de-energized due to a differential trip, and 4KV bus F and H are energized from their Diesel Generators.

ATC Check SI not required SRO Directs BOP to minimize cooldown while maintaining a heat sink.

BOP Reports that no AFW pumps are available SRO Determines conditions met for transition to E-0.1 ALL Monitors CSFSTs SRO Reports RED PATH for HEAT SINK SRO Directs transition to FR-H.1 Response To Loss Of Secondary Heat Sink

• • Critical Task

NRCSIM081 04 Appendix D outline Rev 1.doc Rev. 0 Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

L081-4 Scenario No.:

4 Event No.:

7 & 8 Page 6 of 6 Event

Description:

Loss of Heat Sink with no High Head Injection Time Position Applicants Actions or Behavior SRO/BOP Determines that low AFW flow is not due to operator action and that a secondary heat sink is required.

SRO/ATC Determines no CCPs are available ATC Stops all RCPs ALL Initiates Bleed & Feed **

ATC Actuates SI**

ATC Reset SI ATC Reset Phase A BOP Open FCV-584 Instrument air to Containment ATC Opens available PORVs**

ATC Implements Steps 1-7 of E-0 SRO Continues attempts to establish secondary heat sink Maintenance reports off of clearance on AFW pp 11 BOP Opens FCV-37 and FCV-38 to align Steam supply to AFW pp 11 SRO Directs Aux Watch to start AFW pp 11 BOP Verifies >435 gpm AFW flow ALL Establishes NR level in at least one S/G > 15%

ATC Checks RCS temperatures decreasing ATC Closes PORVs ** until Subcooing > 20 F and RVLIS full range > 60% **

Terminate Scenario after last PORV is closed.

• • Critical Task

NRCSIM081 04 Appendix D outline Rev 1.doc Rev. 0 MAJOR EVENT

SUMMARY

AND SCENARIO OBJECTIVES A.

Commences ramp to 50% power at 3 MW/min.

B.

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.

C.

Crew responds to PK 18-18 4KV BUS F DC CONTROL UV and determines that the cause is a problem with MDAFW pp 13. SRO refers to TS 3.7.5.C D.

LT-461 Pressurizer backup level channel fails low. Crew enters AP-5 Malfunction of Eagle 21 Protection or Control Channel to address instrument failure E.

Main Transformer Bank Sudden Pressure Trip causes Reactor trip. Crew enters E-0 Reactor Trip or Safety Injection. Lose offsite power and 4KV bus G shortly after reactor trip.

F.

Crew transitions from E-0 to FR H-1 Response to Loss of Secondary Heat Sink and performs bleed and feed steps since no high head injection is available (CT).

G.

Maintenance reports off clearance on AFW pp 11. Crew establishes AFW flow to the S/Gs, Scenario is terminated after Pressurizer PORVs are closed (CT).

NRCSIM081 04 Appendix D outline Rev 1.doc Rev. 0 ATTACHMENT 1 - SIMULATOR SET-UP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator per Checklist Init 510 100% power, Mol, CB = 772 Integrators: BA - 0 and PW -40 Tags: FCV-95 Setup Drill 81 Reset normal engineering values Setup Drill 40 Clears TDAFW pp Setup Turn Pzr Backup Heater ON Close FCV-37 & 38 and open breakers dsc mss1 act,0 dsc mss2 act,0 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 04 Appendix D outline Rev 1.doc Rev. 0 TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION X = manual entry required X

0 min DRILL 6804 After SFM reports the crew has taken the watch, load session MALS, OVRs, etc. by DRILL FILE or MANUALLY (below) 10 minutes after ramp started Xmt cvc20 3,100,30,600,c,ggo VCT level channel LT-114 fails high 10 min after VCT level channel fails Dsc afw11 act,0,0,600, c,bxmtl114.gt.90 Loss of UC fuse to AFW pp 13 X

When requested Report that 52-HF-9 breaker DC potential white light is not lit.

X When requested Report that breaker closing spring is charged, UC fuses installed in the ON position, and DC knife switch is closed.

10 minutes after blown UC fuse Xmt pzr42 2,0,0,600, c,.not.xv3o222w Backup Pzr level channel (LT-461) fails low 10 minutes after LCV-460 closed Mal gen1 act,3,0,600,c,xv2o210g MTB sudden pressure trip X

After RX trip Drill 32 N.O. Action on reactor trip On reactor trip Mal eps4d act,2,0,10,c,jpplp4 Loss of 4KV bus G on reactor trip On reactor trip Mal syd1 act,2,60,10,c,jpplp4 Loss of offsite power On reactor trip Pmp cvc1 4,0,0,12,c,jpplp4 OC trip on CCP 11 On reactor trip Pmp afw1 4,0,0,12,c,jpplp4 OC trip on AFW pp 12 X

When requested Vlv mfw2 2,0,600,60,d,0 Locally closes FCV-439 X

When requested Vlv ccw5 2,1,150,60,d,0 Locally open FCV-431 After FR H-1 feed and bleed is done. (Step 22)

Dsc mss1 act,1,0,0,d,0 Dsc mss2 act,1,0,0,d,0 Dsc afw7 act,1,0,0,d,0 Vlv afw7 clr Mal afw1 clr Closes breakers for FCV-37 & 38, and FCV-95. Clears FCV-95 failed in closed position and AFW pp trip malfunction X

After FR H-1 feed and bleed is done. (Step 22)

Report that Maintenance has reported off clearance on AFW pp 11, and control room can pull tags and restart AFW pp 11.

X When requested to locally start TDAFWP Loa afw1 act,0,0,0,d,0 Loa afw2 act,1,60,0,d,0 Reset FCV-152 trip handle and slow opens FCV-152.

NRCSIM081 04 Appendix D outline Rev 1.doc Rev. 0 Drl_6804.txt

• NRC L081 scenario #4

• glh1, 9/29/9

• init 510

• VCT level channel LT-114 fails high xmt cvc20 3,100,30,600,c,ggo

• Loss of UC fuse to AFW pp 13 dsc afw11 act,0,0,600,c,bxmtl114.gt.90

• Backup Pzr level channel (LT-461) fails low Xmt pzr42 2,0,0,600,c,.not.xv3o222w

• MTB sudden pressure trip Mal gen1 act,3,0,600,c,xv2o210g

• Loss of 4KV bus G on reactor trip Mal eps4d act,2,0,10,c,jpplp4

• Loss of offsite power Mal syd1 act,2,60,10,c,jpplp4

• OC trip on CCP 11 Pmp cvc1 4,0,0,10,c,jpplp4

• OC trip on AFW pp 12 Pmp afw1 4,0,0,10,c,jpplp4

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.

TURNOVER ITEMS:

• None OPERABILITY ITEMS:

• None PRIORITY ITEMS FOR NEXT SHIFT:

• Ramp unit at 3 MW/min to 50% power in preparation of tunnel cleaning. Maintenance will start tunnel cleaning on CWP 12 after unit is at 50% power. Tunnel cleaning is scheduled for 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

ANNUNCIATORS IN ALARM

• PK09-18

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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago. Latest BAST ppm sample was 7500 ppm.

d.

Start with a 40 gallon boration prior to ramp and continue 40 gallon borations every 15 minutes for the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the ramp.

e.

Place rods in manual as needed for I control.

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 Scenario Outline Form ES-D-1 NRCSIM081 05 Appendix D outline Rev 1.doc Rev. 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 No.

Malf. No.

Event Type*

Event Description 1

I(ATC)

TS (SRO)

PT-456 fails high.

2 Mal sei1 Siesmic event < 0.30gs Turb3 C(ALL)

High Turbine Vibration (due to seismic event) 3 N(BOP)

R(ATC)

Initiate Ramp to take unit offline.

4 I(ATC)

VCT Level transmitter 112 fails high (ramp over minute).

5 C(ALL)

PK09-13 High bearing temp/vibration > 5 mils on Main Feed pump

11.

6 C(BOP)

T/S (SRO)

Steam Generator C MFRV (FCV-530) fails closed. (During power reduction) Crew can control in manual.

7 Auto Reactor Trip SIGNAL on Low-Low S/G level.

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 8

MSS-4 M(ALL)

Steam Break on MFP turbine steam supply w/MSLI signal failure 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

Appendix D Required Operator Actions Form ES-D-2 NRCSIM081 05 Appendix D outline Rev 1.doc Rev. 1 Op-Test No.: LO81 Scenario No.: __5__ Event No.: __1__

Page _1_ of _1_

Event

Description:

____PT-456 backup pressurizer channel fails high____________

Time Position Applicants Actions or Behavior ATC Identifies pressurizer pressure failing BOP Identifies PORV456 open and manually closes SRO Enter AP-5 Malfunction of Eagle Protection or Control Channel ATC Places Master Pzr Pressure Controller HC-455K in manual ATC Repositions pressure channel selector switch to PT455/PT474 ATC Repositions Pzr Pressure recorder channel to PT-455 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 BOP Closes Block Valve 8000C for Inoperable PORV SRO Directs WCL to remove power to 8000C ATC Returns HC-455K to Auto

Appendix D Required Operator Actions Form ES-D-2 NRCSIM081 05 Appendix D outline Rev 1.doc Rev. 1 Op-Test No.: LO81 Scenario No.: __5__ Event No.: __2__

Page _2_ of _1_

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.

Appendix D Required Operator Actions Form ES-D-2 NRCSIM081 05 Appendix D outline Rev 1.doc Rev. 1 Op-Test No.: LO81 Scenario No.: __5__ Event No.: __3__

Page _3_ of _1_

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 ATC Determines required boration and starts borating ATC/BOP Maintains Tave/Tref within required limit BOP Verify proper DFWCS operation ATC Verifies Rod in Auto and proper overlap while inserting

Appendix D Required Operator Actions Form ES-D-2 NRCSIM081 05 Appendix D outline Rev 1.doc Rev. 1 Op-Test No.: LO81 Scenario No.: __5__ Event No.: __4__

Page _4_ of _1_

Event

Description:

______VCT Level Transmitter 112 Fails High______________

Time Position Applicants Actions or Behavior SRO Refers to AR PK04-24 ATC/BOP Diagnose LT-112 failure SRO Refers to OP-AP-19 Malfunction of Reactor Make Up Control system BOP Places LCV-112A control switch to VCT

Appendix D Required Operator Actions Form ES-D-2 NRCSIM081 05 Appendix D outline Rev 1.doc Rev. 1 Op-Test No.: LO81 Scenario No.: __5__ Event No.: __5__

Page _5_ of _1_

Event

Description:

______High Vibration on Main Feed Puump 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 increase to 50 to 200MWe/min in accordance with OP-AP-25 BOP Trips Main Feed Pump when < 550MWe Op-AP-25 Step 4.3.1

Appendix D Required Operator Actions Form ES-D-2 NRCSIM081 05 Appendix D outline Rev 1.doc Rev. 1 Op-Test No.: LO81 Scenario No.: __5__ Event No.: __6__

Page _6_ of _1_

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

Appendix D Required Operator Actions Form ES-D-2 NRCSIM081 05 Appendix D outline Rev 1.doc Rev. 1 Op-Test No.: LO81 Scenario No.: __5__ Event No.: __7__

Page _7_ of _1_

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 Tries to open FCV-1530 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

Appendix D Required Operator Actions Form ES-D-2 NRCSIM081 05 Appendix D outline Rev 1.doc Rev. 1 Op-Test No.: LO81 Scenario No.: __5__ Event No.: __8__

Page _8_ of _1_

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 Directs transition to E-0.

BOP Performs Appendix E SRO Determines ECCS flow should be reduced ATC Resets SI ATC Resets Cnm Isolation Phase A 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 1.doc Rev. 1 MAJOR EVENT

SUMMARY

AND SCENARIO OBJECTIVES A.

PT-456 fails high. Crew closes PCV-456 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 1.doc Rev. 1 ATTACHMENT 1 - SIMULATOR SET-UP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator per Checklist Init 515 100% power, Mol, CB = 47 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 1.doc Rev. 1 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 mal ppl5b act 3,0,0,d,0 ATWS 0 min vlv mss7 1,0,0,0,d,xv3i183c vlv mss8 1,0,0,0,d,xv3i184c vlv mss9 1,0,0,0,d,xv4i185c vlv mss10 1,0,0,0,d,xv4i186c MSIVs wont close in auto 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 pzr18 3,2642,0,180,d,0 PT-456 fails high X

When requested Dsc pzr3 act, 0,0,0,d,0 Opens breaker for 8000C 10 minutes PT-456 failure mal sei1 act 0.15,10,600, c,pxmtpzr(2).gt.2400, Seismic at 0.15g On Seismic mal tur3c act 7.5,60,0,c,jmlsei1, Turbine bearing 3 high vibration 5 min after ramp starts xmt cvc19 3,100,60,300,c,ggo, LT-112 fails high 10 minutes after LT-112 failure mal mfw2a act 7,60,600, c, bxmtl112.gt.90, MFW pp 11 high vibration After MFW pp 11 trip cnv mfw5 2,0,60,30, c,xv3o195g,ftd530_man FCV-530 fails closed in auto, failure clears when FCV-530 taken to manual When FCV-530 in manual bst aux1 1,0,0,600, c,ftd530_man,0 Starts 10 minute instructor timer to activate second failure of FCV-530 10 min after FCV-530 taken to man.

c jistbst1, cnv mfw5 2,0,60,0,d,0 FCV-530 fails closed again, and wont re-open 3 min after LCV-112B or C is closed mal mss4 act 1e+07,120,180,c,xv2o232g.or.xv2o

231g, Main steam line break outside containment DO NOT OPEN REACTOR TRIP BREAKERS UNTIL BORATION STARTED IN FR S-1 STEP 4.

X When requested Mal ppl5a clr Mal ppl5b clr Opens reactor trip breakers

NRCSIM081 05 Appendix D outline Rev 1.doc Rev. 1 Drl_6805.txt

• NRC L081 SCENARIO 05

• GLH1, 10/20/9

• 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,xv4i185c #rmsf043

• VLV MSS10 MAIN STEMA ISO VLV 4 #rmsf044 vlv mss10 1,0,0,0,d,xv4i186c #rmsf044

• ovr VB5121E 52 HE 4 TRIP & RESET XV5I239O #xv5i239 ovr xv5i239o act,0,0,0,d,0 #vb5121e

• XMT PZR18 PZR PRESS #pxmtpzr(2) xmt pzr18 3,2642,0,180,d,0 #pxmtpzr(2)

• mal SEI1 SEISMIC ACTIVITY mal sei1 act 0.15,10,600,c,pxmtpzr(2).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 2,0,60,30,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+07,120,180,c,xv2o232g.or.xv2o231g,

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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago. BAST at 7500 ppm.

d.

Use Deborating demin for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> every shift. Last time in service was 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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.

ES-301 Transient and Event Checklist Form ES-301-5 Facility:

Diablo Canyon Date of Exam:

1/11/10 Operating Test No.: L081 A

P P

L I

C A

N T

E V

E N

T T

Y P

E Scenarios 1

3 5

T O

T A

L M

I N

I M

U M(*)

CREW POSITION CREW POSITION CREW POSITION CREW POSITION S

R O

A T

C B

O P

S R

O A

T C

B O

P S

R O

A T

C B

O P

S R

O A

T C

B O

P R

I U

RO-1,3,5 RX 3

1 1

1 0 NOR 3

1 2

1 1 1 I/C 2,3,4 1,2,4, 5

2,4,7

,8 11 4

4 2 MAJ 7

6,7 5

4 2

2 1 TS 0

0 2 2 RO-2,4,6 RX 3

1 1

1 0 NOR 1

1 1

1 1 I/C 3,4, 5,6 2,4 6

4 4 2 MAJ 7

6,7 3

2 2 1 TS 0

0 2 2 RO-7,8 RX 4

1 1

1 0 NOR 1

3 2

1 1 1 I/C 3,4, 5,6 1,2,4, 5

3,4,8 11 4

4 2 MAJ 7

6,7 5

4 2

2 1 TS 0

0 2 2 SRO-I 1,2,3 RX 4

1 1

1 0 NOR 0

1 1 1 I/C 2,3,4 1,2,4

,5 3,4,8 10 4

4 2 MAJ 7

6,7 5

4 2

2 1 TS 2,3 1,5 4

0 2 2

Instructions:

1.

Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Diablo Canyon Date of Exam: 1/11/10 Operating Test No.: L081 A

P P

L I

C A

N T

E V

E N

T T

Y P

E Scenarios 1

3 5

T O

T A

L M

I N

I M

U M(*)

CREW POSITION CREW POSITION CREW POSITION CREW POSITION S

R O

A T

C B

O P

S R

O A

T C

B O

P S

R O

A T

C B

O P

S R

O A

T C

B O

P R

I U

SRO-I 4,5 RX 3

1 1

1 0 NOR 1

1 1

1 1 I/C 2,3,4 2,4 2,4,7

,8 9

4 4 2 MAJ 7

6,7 5

4 2

2 1 TS 2,3 2

0 2 2 SRO-I 6,7 RX 3

1 1

1 0 NOR 0

1 1 1 I/C 2,3,4 1,2,4

,5 2,3,8

,4 11 4

4 2 MAJ 7

6,7 5

4 2

2 1 TS 1,5 2,3 4

0 2 2 RX 1

1 0 NOR 1

1 1 I/C 4

4 2 MAJ 2

2 1 TS 0

2 2 RX 1

1 0 NOR 1

1 1 I/C 4

4 2 MAJ 2

2 1 TS 0

2 2

Instructions:

3.

Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

4.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.